ANSI N320-1979 Performance specifications for reactor emergency radiological monitoring instrumentation 《反应堆应急辐射监控仪器的性能规范》.pdf

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1、Copyright The Institute of Electrical and Electronics Engineers, Inc. Provided by IHS under license with IEEENot for ResaleNo reproduction or networking permitted without license from IHS-,-,-N320-79 14805702 0027386 7 I ANSI N320-1979 American National Standard Performance Specifications for Reacto

2、r Emergency Radiological Monitoring Instrumentation Secretariat for N42 Institute of Electrical and Electronics Engineers, Inc Approved December 6, 1978 American National Standards Institute Copyright The Institute of Electrical and Electronics Engineers, Inc. Provided by IHS under license with IEEE

3、Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-American National Standard An American National Standard implies a consensus of those sub- stantially concerned with its scope and provisions. An American National Standard is intended as a guide to aid the manufactur

4、er, the consumer, and the general public. The existence of an American National Standard does not in any respect preclude anyone, whether he has approved the standard or not, from manufacturing, marketing, purchasing, or using products, processes, or procedures not conforming to the standard. Americ

5、an National Standards are subject to periodic review and users are cautioned to obtain the latest editions. CAUTION NOTICE: This American National Standard may be revised or withdrawn at any time. The procedures of the American National Standards Institute require that action be taken to reaffirm, r

6、evise, or withdraw this standard no later than five years from the date of publication. Purchasers of American National Standards may receive current information on all standards by calling or writing the American National, Standards Institute. Copyright 1979 by The Institute of Electrical and Elect

7、ronics Engineers, Inc No part of this publication may be reproduced in any form, in an electronic retrieual system or otherwise, without the prior written permission of the publisher. Copyright The Institute of Electrical and Electronics Engineers, Inc. Provided by IHS under license with IEEENot for

8、 ResaleNo reproduction or networking permitted without license from IHS-,-,-N320-77 Foreword (This Foreword is not a part of ANSI N320-1979, American National Standard Performance Specifications for Re- actor Emergency Radiological Monitoring Instrumentation.) This standard was prepared under the jo

9、int sponsorship of the American National Standards Com- mittee N42 on Radiation Instrumentation and the American National Standards Committee N13 on Radiation Protection. The members of both N42 and N13 reviewed and approved this standard. The performance specifications herein were developed by Batt

10、elle Northwest Laboratory through collaboration with principal manufacturers and industry as well as with acknowledged experts in principal government laboratories. The work was performed under USAEX contract. At the time it approved this standard, the American National Standards Committee on Radiat

11、ion Instrumentation had the following personnel: Louis Costrell, Chairman David C. Cook, Secretary Organization Represented Name of Representative American Chemical Society. . Vacant American Conference of Governmental Industrial Hygienists. . Jesse Lieberman American Industrial Hygiene Association,

12、 Vacant American Nuclear Society. Frank W. Manning American Society of Mechanical Engineers. . P. E. Greenwood American Society of Safety Engineers. Vacant Atomic Industrial Forum . Vacant Health Physics Society. J. B. Horner Kuper Institute of Electrical and Electronics Engineers Louis Costrell Rob

13、ert L. Butenhoff (Alt) D. C. Cook (Alt) A. J. Spurgin (Alt) J. Forster (Alt) J. E. Kaveckis (Alt) Instrument Society of America . M. T. Slind Lawrence Berkeley Laboratory . D. A. Mack Manufacturing Chemists Association. . Vacant National Electrical Manufacturers Association. . Theodore Hamburger Oak

14、 Ridge National Laboratory . Frank W. Manning Scientific Apparatus Makers Association . Vacant U.S. Department of the Army, Materiel Command. Abraham E. Cohen U.S. Department of Commerce, National Bureau of Standards. Louis Costrell U.S. Civil Defense Preparedness Agency. . Carl R. Siebentritt, Jr U

15、.S. Energy Research and Development Administration. Hodge R. Wasson U.S. Naval Research Laboratory. David C. Cook Members-at-Large J. G. Bellian D. J. Knowles (Alt) O. W. Bilharz S. H. Hanauer John M. Gallagher, Jr Voss A. Moore R. F. Shea E. J. Vallario The American National Standards Committee N13

16、 on Radiation Protection, had the following representatives at the time of approval: John Poston, Chairman R. J. Burk, Secretary Organization Represented Name of Representative American Chemical Society. . Ira B. Whitney American Conference of Governmental Industrial Hygienists. . D. E. Van Farrowe

17、American Industrial Hygiene Association. H. W. Speicher American Insurance Association. Karl H. Carson American Mutual Insurance Alliance. . William J. Uber American Nuclear Society. Eric T. Clarke W. D. Kelly (Alt) Copyright The Institute of Electrical and Electronics Engineers, Inc. Provided by IH

18、S under license with IEEENot for ResaleNo reproduction or networking permitted without license from IHS-,-,-N320-79 14805702 0027389 2 I Organization Represented American Occupational Medical Association. . American Public Health Association American Society of Mechanical Engineers. . American Socie

19、ty for Testing and Materials . Association of State and Territorial Health Officers. . Atomic Industrial Forum . Electric Light and Power Group. Environmental Protection Agency . Health Physics Society, Institute of Electrical and Electronics Engineers Institute of Nuclear Material Management Intern

20、ational Association of Governmental Labor Officials . Name of Representative William W. Burr, Jr Simon Kinsman Gerald S. Parker (Alt) Monte Hawkins L. B. Gardner J. H. Bystrom (Alt) A. N. Tschaeche Sherwood Davies James E. Sohngen Marvin K. Sullivan Gordon A. Olson (Alt) David S. Smith Vernon Chilso

21、n John J. Ferry (Alt) C. D. Wilkinson Kenneth G. Okolowitz Jacaueline Messite Frank J. Bradley (Alt) International Brotherhood of Electrical Workers. . Paul R. Shoop Manufacturing Chemists Association. Inca P. W. McDaniel 1 Paul Estey (Alt) Thomas Hobbs (Alt) National Bureau of Standards . Thomas P.

22、 Loftus Nuclear Regulatory Commission. Walter Cool Uranium Operators Association . L. W. Swent U.S. Bureau of Labor. . John P. ONeill R. T. Zittling lt) G. Walker Daubenspeck (Alt) U.S. Department of Energy. . Edward J. Vallario U.S. Puljlic Health Service. Richard F. Boggs Gail D. Schmidt (Alt) Ind

23、ividual Members. William O. Chatfield Hugh F. Henry Remus G. McAllister Thomas Philbin The American National Standards joint subcommittee N13 and N42, Working Group 6, which was responsible for developing this standard had the following membership: Edward J. Vallario, Chairman Joseph G. Bellian* Wal

24、ter S. Cool Lyle A. Carter* Ronald L. Kathren Vernon T. Chilson Jack M. Selby Robert W. Van Wyck *Consultant Copyright The Institute of Electrical and Electronics Engineers, Inc. Provided by IHS under license with IEEENot for ResaleNo reproduction or networking permitted without license from IHS-,-,

25、-Contents SECTION PAGE 1 . Scope . 7 1.1 Introduction 7 2 . Definitions . 7 3 . References . 8 4 . General Considerations for Emergency Instrumentation 8 4.1 Instrumentation for Monitoring Emergency Conditions within the Reactor Facility 8 4.2 Instrumentation at or near a Reactor Facility for Assess

26、ing a Radioactive Material 4.3 Instrumentation at a Distance from a Reactor Facility for Assessing the Radioactive Release Resulting from an Emergency Condition 9 Material Released During an Emergency Condition . 9 5 . Criteria for Radiological Instrumentation Systems . 9 6 . Systems for Monitoring

27、Conditions within the Reactor Facility 11 6.2 Containment Monitoring Systems for Airborne Radiohalogens and Particulates 11 6.3 Systems for Monitoring Exposure Rate within the Reactor Facility . 12 7 . Instrumentation Systems for Detecting and Quantifying the Release to the Environs . 12 6.1 Contain

28、ment Monitoring Systems for Radioactive Noble Gases 11 7.1 Plume Detection 12 7.2 Stack Effluent Monitoring System 12 8 . Installed Systems for Monitoring Conditions in the Environs 12 8.1 AirMonitoring . 12 8.2 Exposure Rate Monitoring 12 9 . Portable Instrumentation . 13 9.1 Rate Survey Instrument

29、s 13 9.2 Portable Air Samplers 14 9.3 Direct Reading Dosimeters 14 9.4 Personal Alarm Dosimeters 14 10 . Bibliography . 15 TABLES Table 1 Upper Detection Limit for Noble Gases within the Reactor Containment and for Radioactive Material Released to the Environs via the Stack . 11 Table 2 Upper Detect

30、ion Limit for Radiohalogens or Particulate Radioactive Material within the Reactor Containment . -11 Table 3 Upper Detection Limit for Exposure Rate within the Reactor Containment . 12 Copyright The Institute of Electrical and Electronics Engineers, Inc. Provided by IHS under license with IEEENot fo

31、r ResaleNo reproduction or networking permitted without license from IHS-,-,-“ “_“ N320-?y American National Standard Performance Specifications for Reactor Emergency Radiological Monitoring Instrumentation 1. Scope This standard defines, for various types of instrumentation, the essential performan

32、ce parameters, and general placement for monitor- ing the release of radionuclides associated with a postulated serious accident at a reactor facil- ity. This standard does not specify which of the instruments or systems are required nor does it consider the number or specific loca- tions of such in

33、struments. This standard also does not address single failure criteria associ- ated with nuclear safety instrumentation. For the purpose of this standard, the predominant consideration in the assessment of radiation emergencies is the measurement of fission products promptly enough to permit timely

34、emergency decisions to be made. Where instruments utilized for routine op- erations fulfill the criteria herein, they need not be duplicated in order to have separate emergency instrumentation. Dual purpose in- strumentation must meet the requirements of this standard. 1.1 Introduction. Regulatory a

35、gencies require the development of comprehensive emergency plans for nuclear reactor facilities. Such plans must include the provision of adequate radio- logical instrumentation to detect and quantify and the word may to denote permission, neither a requirement nor a recommenda- tion. It is importan

36、t that instruments, systems, or individual components intended for emergency application be: (1) Qualified for use under extreme condi- tions (2) Preoperationally tested over the entire range of operation (3) Periodically checked and calibrated ac- cording to an appropriate calibration program The c

37、riteria herein apply only to instru- mentation installed or located at the reactor facility and intended for use by facility person- nel in the conduct of emergency operations. Instrument selection will of necessity be deter- mined on a case by case basis considering in- dividual facility emergency

38、plans and site specific parameters. These plans involve sev- eral elements including measurement of mete- orological parameters, establishment of com- munications, arrangement for off-site work support personnel, identification of capabil- ities, capability of detecting emergency condi- tions, and q

39、uantifying releases. 2. Definitions accidental releases of radioactivity from these auxiliary building(s). Building(s), near or adja- facilities. This standard presents performance cent to the reactor containment building in criteria for instrumentation for detecting and which system support equipme

40、nt is quantifying such release of radioactive ma- housed, terials. The criteria are based on estimates of the quantity and characterization Of radio- calibrate. To determine the response or reading active material that could escape as a result of a postulated accident at a reactor facility (see radi

41、ation values Over the range of the instm- of an instrument relative to a series of known definitions for auxiliary building(s), calibrate, ment. and check). Throughout these criteria, three verbs have been used to indicate the degree of check. To determine if the detector and all rigor intended by t

42、he specific criterion. The electronic components of a system are operat- word shall is used to denote a requirement, ing satisfactorily by determining consistent the word should to denote a recommendation, response to the same source. 7 Copyright The Institute of Electrical and Electronics Engineers

43、, Inc. Provided by IHS under license with IEEENot for ResaleNo reproduction or networking permitted without license from IHS-,-,-ANSI N320-1979 - N320-79 PERFORMANCE SPECIFICATIONS FOR REACTOR EMERGENCY check source. A radioactive source, not neces- sarily calibrated, which is used to confirm the co

44、ntinuing satisfactory operation. of an instrument. containment. A structure or vessel which en- closes the components of the reactor coolant pressure boundary or which serves as a leak- age limiting barrier to radioactive material that could be released from the reactor coolant pressure boundary, or

45、 both. effluent. Liquid or airborne radioactive ma- terials 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

46、 same property, expressed quantitatively as the standard deviation com- puted from the results of the series of measure- ments. 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

47、operation at a steady state reactor power level of 1 MWa,. reactor facility. The structures, systems and co-mponents used for the operation of a nuclear reactor. If a site contains more than one nuclear reactor, reactor facility means all struc- tures, systems and components used for opera- tion of

48、the nuclear reactors at the site. readout. The device that conveys information regarding the measurement to the user. 3. References When the following American National Stan- dards referred to in this document are super- seded by a revision approved by the American National Standards Institute, Inc,

49、 the latest revision shall apply. ANSI C18.1-1972, American National Stan- dard Specifications for Dry Cells and Bat- teries. ANSI N13.1-1969, American National Stan- dard Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities. 8 ANSI N13.5-1972, American National Stan- dard Specifications for Direct Reading and In- direct Reading Pocket Dosimeters for X- and Gamma Radiation, Performance. ANSI N323-1978, American National Standard Radiation Protec