ANSI IEEE N320-1979 Performance Specifications for Reactor Emergency Radiological Monitoring Instrumentation.pdf

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1、 ANSI N320-1979American National Standard Performance Specications for Reactor Emergency Radiological Monitoring InstrumentationSecretariat for N42Institute of Electrical and Electronics Engineers, IncApproved December 6, 1978Reaffirmed December 27, 1985American National Standards InstitutePublished

2、 byThe Institute of Electrical and Electronics Engineers, Inc345 East 47th Street, New York, N.Y. 10017 Copyright 1979 byThe Institute of Electrical and Electronics Engineers, IncNo part of this publication may be reproduced in any form, in an electronic retrieval system or otherwise, without thepri

3、or written permission of the publisher.American National StandardAn American National Standard implies a consensus of those substantially concerned with its scope and provisions.An American National Standard is intended as a guide to aid the manufacturer, the consumer, and the general public.The exi

4、stence of an American National Standard does not in any respect preclude anyone, whether he has approved thestandard or not, from manufacturing, marketing, purchasing, or using products, processes, or procedures notconforming to the standard. American National Standards are subject to periodic revie

5、w and users are cautioned toobtain the latest editions.CAUTION NOTICE:This American National Standard may be revised or withdrawn at any time. The procedures ofthe American National Standards Institute require that action be taken to reafrm, revise, or withdraw this standard nolater than ve years fr

6、om the date of publication. Purchasers of American National Standards may receive currentinformation on all standards by calling or writing the American National Standards Institute.iiiForeword(This Foreword is not a part of ANSI N320-1979, American National Standard Performance Specications for Rea

7、ctor EmergencyRadiological Monitoring Instrumentation.)This standard was prepared under the joint sponsorship of the American National Standards Committee N42 onRadiation Instrumentation and the American National Standards Committee N13 on Radiation Protection. Themembers of both N42 and N13 reviewe

8、d and approved this standard.The performance specications herein were developed by Battelle Northwest Laboratory through collaboration withprincipal manufacturers and industry as well as with acknowledged experts in principal government laboratories. Thework was performed under USAEC contract.At the

9、 time it approved this standard, the American National Standards Committee on Radiation Instrumentation hadthe following personnel:Louis Costrell, Chair David C. Cook, Secretary American Chemical Society.VacantAmerican Conference of Governmental Industrial Hygienists. Jesse LiebermanAmerican Industr

10、ial Hygiene Association .VacantAmerican Nuclear Society . Frank W. ManningAmerican Society of Mechanical Engineers.P.E. GreenwoodAmerican Society of Safety Engineers VacantAtomic Industrial ForumVacantHealth Physics Society J.B. Horner KuperRobert L. Butenhoff (Alt)Institute of Electrical and Electr

11、onics Engineers .Louis CostrellD.C. Cook (Alt)A. J. Spurgin (Alt)J. Forster (Alt)Instrument Society of America . M.T. SlindJ. E. Kaveckis (Alt)Lawrence Berkeley Laboratory.D.A. MackManufacturing Chemists Association VacantNational Electrical Manufacturers Association Theodore HamburgerOak Ridge Nati

12、onal Laboratory. Frank W. ManningD. J. Knowles (Alt)Scientic Apparatus Makers Association VacantU.S. Department of the Army, Materiel Command .Abraham E. CohenU.S. Department of Commerce, National Bureau of Standards Louis CostrellU.S. Civil Defense Preparedness Agency Carl R. Siebentritt, JrU.S. En

13、ergy Research and Development Administration Hodge R. WassonU.S. Naval Research Laboratory David C. CookMembers-at-LargeJ.G. BellianO. W. BilharzS. H. HanauerJohn M. Gallagher, JrVoss A. MooreR. F. SheaE. J. VallarioivThe American National Standards Committee N13 on Radiation Protection, had the fol

14、lowing representatives at thetime of approval:John Poston, Chair R.J. Burk, Secretary American Chemical SocietyIra B. WhitneyAmerican Conference of Governmental Industrial HygienistsD.E. Van FarroweAmerican Industrial Hygiene Association H.W. SpeicherW. D. Kelly (Alt)American Insurance Association K

15、arl H. CarsonAmerican Mutual Insurance Alliance William J. UberAmerican Nuclear Society . Eric T. ClarkeAmerican Occupational Medical Association. William W. Burr, JrAmerican Public Health Association Simon KinsmanGerald S. Parker (Alt)American Society of Mechanical Engineers.Monte HawkinsAmerican S

16、ociety for Testing and Materials L. B. GardnerJ. H. Bystrom (Alt)A. N. TschaecheAssociation of State and Territorial Health Ofcers Sherwood DaviesAtomic Industrial Forum. James E. SohngenElectric Light and Power Group Marvin K. SullivanGordon A. Olson (Alt)Environmental Protection Agency . David S.

17、SmithHealth Physics Society.Vernon ChilsonJohn J. Ferry (Alt)Institute of Electrical and Electronics Engineers C. D. WilkinsonInstitute of Nuclear Material Management Kenneth G. OkolowitzInternational Association of Governmental Labor Ofcials Jacqueline MessiteFrank J. Bradley (Alt)International Bro

18、therhood of Electrical Workers .Paul R. ShoopManufacturing Chemists Association, Inc. . P. W. McDanielPaul Estey (Alt)National Bureau of Standards Thomas P. LoftusThomas Hobbs (Alt)Nuclear Regulatory Commission Walter CoolUranium Operators Association L. W. SwentR. T. Zittling (Alt)U.S. Bureau of La

19、bor John P. ONeillG. Walker Daubenspeck (Alt)U.S. Department of Energy. Edward J. VallarioU.S. Public Health ServiceRichard F. BoggsGail D. Schmidt (Alt)Individual Members William O. ChateldHugh F. HenryRemus G. McAllisterThomas PhilbinThe American National Standards joint subcommittee N13 and N42,

20、Working Group 6, which was responsible fordeveloping this standard had the following membership:Edward J. Vallario, Chair Joseph G. Bellian*Lyle A. Carter*Vernon T. ChilsonWalter S. CoolRonald L. KathrenJack M. SelbyRobert W. Van Wyck*ConsultantvCLAUSE PAGE1. Scope.11.1 Introduction 12. Definitions.

21、23. References.24. General Consideration for Emergency Instrumentation .34.1 Instrumentation for Monitoring Emergency Conditions within the Reactor Facility 34.2 Instrumentation at or near a Reactor Facility for Assessing a Radioactive Material Release Resultingfrom an Emergency Condition. 44.3 Inst

22、rumentation at a Distance from a Reactor Facility for Assessing the Radioactive MaterialReleased During an Emergency Condition 45. Criteria for Radiological Instrumentation Systems.46. Systems for Monitoring Conditions within the Reactor Facility 76.1 Containment Monitoring Systems for Radioactive N

23、oble Gases 76.2 Containment Monitoring Systems for Airborn Radiohalogens and Particulates. 86.3 Systems for Monitoring Exposure Rate within the Reactor Facility . 97. Instrumentation Systems for Detecting and Quantifying the Release to the Environs.107.1 Plume Detection. 107.2 Stack Effluent Monitor

24、ing System. 108. Installed Systems for Monitoring Conditions in the Environs108.1 Air Monitoring . 108.2 Exposure Rate Monitoring . 119. Portable Instrumentation .119.1 Rate Survey Instruments 119.2 Portable Air Samplers 149.3 Direct Reading Dosimeters 149.4 Personal Alarm Dosimeters . 1510. Bibliog

25、raphy15Copyright 1979 IEEE All Rights Reserved1American National Standard Performance Specications for Reactor Emergency Radiological Monitoring Instrumentation1. ScopeThis standard denes, for various types of instrumentation, the essential performance parameters, and generalplacement for monitoring

26、 the release of radionuclides associated with a postulated serious accident at a reactor facility.This standard does not specify which of the instruments or systems are required nor does it consider the number orspecic locations of such instruments. This standard also does not address single failure

27、 criteriaassociated withnuclear safety instrumentation. For the purpose of this standard, the predominant consideration in the assessment ofradiation emergencies is the measurement of ssion products promptly enough to permit timely emergency decisionsto be made.Where instruments utilized for routine

28、 operations fulll the criteria herein, they need not be duplicated in order to haveseparate emergency instrumentation. Dual purpose instrumentation must meet the requirements of this standard.1.1 IntroductionRegulatory agencies require the development of comprehensive emergency plans for nuclear rea

29、ctor facilities. Suchplans must include the provision of adequate radiological instrumentation to detect and quantify accidental releases ofradioactivity from these facilities. This standard presents performance criteria for instrumentation for detecting andquantifying such release of radioactive ma

30、terials. The criteria are based on estimates of the quantity andcharacterization of radioactive material that could escape as a result of a postulated accident at a reactor facility (seedenitions for auxiliary building(s), calibrate, and check). Throughout these criteria, three verbs have been used

31、toindicate the degree of rigor intended by the specic criterion. The word shallis used to denote a requirement, the wordshouldto denote a recommendation, and the word mayto denote permission, neither a requirement nor arecommendation.It is important that instruments, systems, or individual component

32、s intended for emergency application be:1) Qualied for use under extreme conditions2) Preoperationally tested over the entire range of operation3) Periodically checked and calibrated according to an appropriate calibration program2Copyright 1979 IEEE All Rights ReservedANSI N320-1979 PERFORMANCE SPE

33、CIFICATIONS FOR REACTOR EMERGENCYThe criteria herein apply only to instrumentation installed or located at the reactor facility and intended for use byfacility personnel in the conduct of emergency operations. Instrument selection will of necessity be determined on acase by case basis considering in

34、dividual facility emergency plans and site specic parameters. These plans involveseveral elements including measurement of meteorological parameters, establishment of communications,arrangement for off-site work support personnel, identication of capabilities, capability of detecting emergencycondit

35、ions, and quantifying releases.2. Definitionsauxiliary building(s): Building(s), near or adjacent to the reactor containment building in which primary systemsupport equipment is housed.calibrate: To determine the response or reading of an instrument relative to a series of known radiation values ove

36、r therange of the instrument.check: To determine if the detector and all electronic components of a system are operating satisfactorily bydetermining consistent response to the same source.check source: A radioactive source, not necessarily calibrated, which is used to conrm the continuing satisfact

37、oryoperation of an instrument.containment: A structure or vessel which encloses the components of the reactor coolant pressure boundary or whichserves as a leakage limiting barrier to radioactive material that could be released from the reactor coolant pressureboundary, or both.efuent: Liquid or air

38、borne radioactive materials released to the environs.environs: The uncontrolled area at or near the site boundary.extracameral: Pertaining to that portion of the instrument exclusive of the detector.precision: The degree of agreement of repeated measurements of the same property, expressed quantitat

39、ively as thestandard deviation computed from the results of the series of measurements.range: The set of values lying between the upper and lower detection limits.reactor: As used in this standard, reactor means a nuclear reactor designed for and capable of operation at a steadystate reactor power l

40、evel of 1 MWth.reactor facility: The structures, systems and components used for the operation of a nuclear reactor. If a site containsmore than one nuclear reactor, reactor facility means all structures, systems and components used for operation of thenuclear reactors at the site.readout: The devic

41、e that conveys information regarding the measurement to the user.3. ReferencesWhen the following American National Standards referred to in this document are superseded by a revision approvedby the American National Standards Institute, Inc, the latest revision shall apply.ANSI C18.1-1972, American

42、National Standard Specications for Dry Cells and Batteries. ANSI N13.1-1969, American National Standard Guide to Sampling Airborne Radioactive Materials in NuclearFacilities. Copyright 1979 IEEE All Rights Reserved3RADIOLOGICAL MONITORING INSTRUMENTATION ANSI N320-1979ANSI N13.5-1972, American Natio

43、nal Standard Specications for Direct Reading and Indirect Reading PocketDosimeters for X- and Gamma Radiation, Performance. ANSI N323-1978, American National Standard Radiation Protection Instrumentation Test and Calibration. 4. General Consideration for Emergency InstrumentationThe criteria contain

44、ed herein concern the basic elements of an emergency radiological instrumentation program. Thisstandard does not specify which of the instruments or systems are required nor does it consider the number of speciclocations. These determinations are made by qualied individuals and regulatory authority.

45、 A distinction is madebetween instrumentation essential to inplant monitoring and that for monitoring in the environs. Primary emphasis isplaced on the selection of instruments and instrument systems and on their ability to provide data rapidly as basis formaking appropriate emergency action decisio

46、ns. The instrumentation should include both installed systems, hereinreferred to as systems, with appropriate readouts and portable instruments, since either portable or installedinstrumentation alone may provide incomplete information.4.1 Instrumentation for Monitoring Emergency Conditions within t

47、he Reactor FacilitySeveral types of emergency instruments or instrumentation systems should be available at the reactor facility tocharacterize severity and extent of an accident. These should include:1) Installed instrumentation systems with remote readout to a safe location capable of characterizi

48、ng releases tocontainment and auxiliary buildings and the radiological problems associated with evacuation and reentry.These systems should be provided with a remote readout at a location which will be habitable under accidentconditions.2) Portable survey instruments to supplement installed instrume

49、nt systems to permit estimation of exposure topersons, to locate radiation sources and determine their distribution, and to make radiological measurementsthat may become of ad hoc interest at locations not covered by installed instrumentation.In determining the type of instrumentation required, the following apply:4.1.1 Continuous measurement of airborne radioactivity in the containment is necessary.4.1.2 Where appropriate, air sampling systems shall be consistent with the requirements stated in ANSI N13.1-1969,American National Standard Guide to Sampling