ANSI N15.41-1984 Nuclear Facilities - Derivation of Measurement Control Programs - General Principles (INMM)《核设施.测量控制程序的推导.一般规则》.pdf

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1、for nuclear facilities - derivation of measurement control programs - general principles 4 ANSI N35.43 84 m 0724350 0009283 2 m ANSI N15.41-1984 American National Standard for Nuclear Facilities - Derivation of Measurement Control Programs - General Principles Secretariat Institute of Nuclear Materi

2、als Management Approved October 1, 1984 American National Standards Institute, Inc 6 American Approval of an American National Standard requires verification by ANSI that the re- quirements for due process, consensus, and other criteria for approval have been met by Consensus is established when, in

3、 the judgment of the ANSI Board of Standards Review, substantial agreement has been reached by directly and materially affected interests. Sub- stantial agreement means much more than a simple majority, but not necessarily unanim- ity. Consensus requires that all views and objections be considered,

4、and that a concerted effort be made toward their resolution. The use of American National Standards is completely voluntary; their existence does not in any respect preclude anyone, whether he has approved the standards or not, from man- ufacturing, marketing, purchasing, or using products, processe

5、s, or procedures not con- forming to the standards. The American National Standards Institute does not develop standards and will in no cir- cumstances give an interpretation of any American National Standard. Moreover, no per- son shall have the right or authority to issue an interpretation of an A

6、merican National Standard in the name of the American National Standards Institute. Requests for inter- pretations should be addressed to the secretariat or sponsor whose name appears on the title page of this standard. CAUTION NOTICE: This American National Standard may be revised or withdrawn at a

7、ny time. The procedures of the American National Standards Institute require that action be taken to reaffirm, revise, or withdraw this standard no later than five years from the date of approval, Purchasers of American National Standards may receive current infor- mation on all standards by calling

8、 or writing the American National Sfandards Institute. National the standards developer. Standard Published by American National Standards Institute 1430 Broadway, New York, New York 10018 Copyright O 1985 by American.Nationa1 Standards Institute, Inc All rights reserved. No part of this publication

9、 may be reproduced in any form, in an electronic retrieval system or otherwise, without the prior written permission of the publisher. Printed in the United States of America AlM185/7 ANSI N15.43 84 0724350 0007283 b (This Foreword is not part of American National Standard N15.41-1984.) This standar

10、d has been developed under the procedures of the American National Stan- Foreword * t dards Institute by Subcommittee INMM-5 on Measurement Controls, part of American National Standards Committee N15 on Methods of Nuclear Material Control. The secre- tariat of Committee N15 is held by the Institute

11、of Nuclear Materials Management. In the interest of controlling the quality of measurements for nuclear materials, the Insti- tute of Nuclear Materials Management has long recognized the importance of measure- ment control programs as a means of managing and safeguarding nuclear materials. This stan

12、dard provides the generic principles from which specific measurement control pro- grams can be derived. The scope of measurement control programs is wide and, therefore, this standard is ex- pected to be reviewed on a continuing basis, resulting in periodic revision. It is recognized that, in some c

13、ases, the standard may not fulfill the users requirements as to application and detail; if such cases prove to be numerous, the standard will require expansion. Committee N15 has the following scope: Standards for the protection, control, and accounting of special materials in all phases of the nucl

14、ear fuel cycle, including analytical procedures where necessary and special to this purpose, except that physical protection of special nuclear material within a nuclear power plant is not included. Standards Committee N15 has 12 subcommittees: INMM-1, Accounting INMM-3, Statistics INMM-5, Measureme

15、nt Controls INMM-6, Inventory Techniques INMM-7, Audit, Records, and Reporting Techniques INMM-8, Calibration Techniques INMM-9, Nondestructive Assay INMM-IO, Physical Security INMM-11, Training and Certification INMM-12, Site Response Planning INMM-13 Transportation INMM-14, International Safeguard

16、s The objective of Subcommittee INMMJ is to propose appropriate standards and guides for the control of measurement processes that measure nuclear materials to ensure that the measurements used are of adequate quality for their intended purpose. Suggestions for improvement of this standard will be w

17、elcome. They should be sent to the Institute of Nuclear Materials Management, Sperry-Univac Plaza, Suite 720-South, 8600 West Bryn Mawr Avenue, Chicago, IL 60631. This standard was processed and approved for submittal to ANSI by American National Standards Committee on Methods of Nuclear Material Co

18、ntrol, N15. Committee approval of the standard does not necessarily imply that all committee members voted for it ap- proval. At the time it approved this standard, the N15 Committee had the following members: George Huff, Chair Robert Kramer, Secretary (Allied General Nuclear Services) (Northern In

19、diana Public Service Company) ANSI NL5-41 84 W 0724150 0009284 8 W Organization Represented American Council of Independent Laboratories. . American Nuclear Society American Society of Quality Control. . Association of American Railroads, Bureau of Explosives Atomic Industrial Forum, Inc. . Electric

20、 Light and Power Group. Institute of Nuclear Materials Management NationalBureauofStandards Society for Applied Spectroscopy . U.S. Department of Energy . U.S. Nuclear Regulatory Commission . Name of Representative Douglas H. Dief J. W. Arendt Myron Calkins W. S. Chang Walter Meyer L. F. Dale Janies

21、 E. Sohngen (Alt) Harley L. Toy V. P. Reed J. Paul Cali (Ait) Louis Basile Barry L. Rich Frank P. Gillespy Subcommittee INMM-5 on Measurement Controls, which prepared this standard, had the following members: Yvonne M. Ferris, Chair (Rockwell International) Riley Carver Charles W. Emeigh William E.

22、Gilbert, Jr Galen D. Halversen Rodney Hand Robert C. McBroom Neil Zack Rush O. Inlow (Lawrence Livermore National Laboratory (U.S. Nuclear Regulatory Commission) (U.S. Department of Energy, HQ) (Exxon Nuclear Idaho Company) (US. Department of Energy; Albuquerque Operations Office) (Union Carbide Nuc

23、lear Corporation) (Los Alamos National Laboratory) (Rockwell International) (US. Department of Energy, New Brunswick Laboratory) Victor W. Lowe, Jr Jack Markin Carson L. Nealy Charles E. Pietri O I PAGE Contents 1 . ScopeandPurpose 7 1.1 Scope . 7 1.2 Purpose 7 2 . Introduction., 7 3 . ReferencedPub

24、lications 7 3.1 American National Standards 7 3.2 OtherPublications . 8 4.Definitions . 8 5 . Technical Aspects of a Measurement Control Program 8 5.2 Scientific Basis of a Measurement Control Program . 9 5.3 Development of a Measurement Control Program 10 6 . Administrative Aspects of a Measurement

25、 Control Program 11 6.2 Organization and Management . 12 6.3 Training and Qualification of Personnel. 12 6.4 Review of the Measurement Control Program . 13 6.5 Audit of the Measurement Control Program 13 5.1 Purpose. . 8 6.1 Purpose 11 6.6 Documentation 14 6.7 Procedures. . 14 Appendix A Measurement

26、 Control Program . 15 Appendix B A Simple Measurement Control Program 16 Figure B1 Organization Chart 17 Appendix C Suggested Checklist for Review of the Measurement Control Program . 18 Appendix D Typical Internal Control Questionnaire for Program Audit . 19 Appendix E Documentation Needed for a Me

27、asurement Control Program . 20 Appendix F Bibliography . 20 Appendixes ANSI N15-43 84 E 0724350 0007286 3 i American National Standard for Nuclear Facilities - Derivation of Measurement Control Programs - General Principles 1. Scope and Purpose 1.1 Scope. This standard is limited to presenting the g

28、eneric principles from which specific measurement control programs can be derived. Specific measurement control programs for individual measurement processes will be issued in separate standards. Although the prin- ciples presented in this standard are intended primarily to be applied to the measure

29、ment processes used in the nuclear industry, the principles are general enough for application to many other measurement processes as well. 1.2 Purpose. The purpose of this standard is to present general principles for deriving a sound measurement control program for any measurement process used to

30、manage or to safeguard nuclear materials. These prin- ciples address both the technical and the administrative aspects of the measurement control programs. Al - though not a part of the standard, there are also several appendixes that contain examples illustrating the gen- eral principles presented

31、in the body of the standard. 2. Introduction The ability to manage and safeguard nuclear material depends on measurements of various physical and chemical properties such as the compositions of the mass and the isotopes. Because measurements of poor quality may lead to incorrect decisions involving

32、the nuclear material, special effort should be spent on the task of ensuring that the measurements used in the nuclear industry are of adequate quality for their in- tended use, The actiyities devoted to this task consti- tute a measurement control program. A measurement control program should addre

33、ss all aspects of a measurement process that can affect the quality of the measurements. This means that, in addi- tion to addressing the scientific or technical aspects of the measurement process, the measurement control program should also address the nontechnical or admin- istrative aspects of th

34、e measurement process such as documentation, personnel qualification procedures, and the like. These administrative aspects and certain technical aspects are elements of quality assurance and their implementation establishes quality assurance practices in the measurement control program, These quali

35、ty assurance practices are described in American National Standard Quality Assurance Program Require- ments for Nuclear Power Plants, ANSI/ASME NQA-1- 1983. Although the goal of a generic measurement control program can be generally described as the attainment of a measurement process that generates

36、 measurements of adequate quality, the goal of any particular measure- ment control program must be described more specifi- cally. For a particular measurement control program, a technical, operational meaning must be given ta the idea of “adequate quality by specifying the operating criteria the me

37、asurement process must satisfy. In gener- al, the operating criteria are determined by identifying the consequences of data on the mission for which the date are gathered, then deciding what physical and probabilistic characteristics the measurement process must possess so that the probability of ge

38、nerating mea- surements that lead to undesirable consequences is re- duced to a level consistent with the importance of the mission. 3. Referenced Publications 3.1 American National Standards. This standard is in- tended for use with the following American National Standards. When these standards ar

39、e superseded by a revision approved by the American National Standards Institute, Inc, the revision shall apply. ANSI N15.5-1972, Statistical Terminology and Nota- tion for Nuclear Materials Management ANSI N15.38-1982, Generic Requirements for Audit- ing Nuclear Materials Safeguards Systems ANSI/AS

40、ME NQA-1-1983, Quality Assurance Pxogram Requirements for Nuclear Facilities 7 _ -_ ANSI N35.43 84 II 0724350 0007287 3 M AMERICAN NATIONAL STANDARD N15.41-1984 3.2 Other Publications i Mood, A. M. and others. Introduction to the theory of statistics. 3rd ed. New York: McGraw-Hill Company, 1974. 2 K

41、empthorne, O.; Folks, L. Probability, statistics, and data analysis. Ames, IA: The Iowa State University Press, 1971. 3 Brouns, R. J. and others. A measurement con- trol program for nuclear material accounting. Washing- ton, DC: U.S. Nuclear Regulatory Commission; NUREG/CR-0829; PNL-3021 4. Definiti

42、ons assessment. A continuing evaluation of the adequacy of the established measurement process and its compliance with the established policies, procedures, and practices. audit.A means of assuring that current activities are in compliance with program policies and procedures. error. A deviation fro

43、m correctness. mean able; Le., the first moment about measurement. A value that has been assigned to a char- acteristic of interest. measurement control program. The procedures and activities used to ensure that a measurement process generates measurements of sufficient quality for their intended us

44、e. measurement error model, A description of the uncer- tainty of a measurement process. The model relates the measurement to the true value of the quantity being measured and the source of error associated with the measurement process and describes the probabilistic characteristics of the errors, u

45、sually in terms of the expected value and standard deviation. measurement process. All activities, procedures, and equipment used to obtain a measurement. physical model. A description of how measurements are influenced by physical factors such as temperature, population. The expected value of the r

46、andom vari- sample. The arithmetic average of the ample. Available from Division of Technical Information and Docu- ment Control, U.S. Nuclear Regulatory Commission, Washing- ton, DC 20555. N15.5 that is currently being developed. These definitions will appear in a revised edition of ANSI This defin

47、ition was derived from the definition in ANSI N15.5-1972. composition, density, and the like. Physical models may be as simple as a list of variables and their con- straints or as complicated as a set of equations that describe in detail the effect each variable has on the measurement. procedure. A

48、document that specifies or describes how an activity is to be perfrmed. qualification. The characteristics or abilities gained through education, training, or experience, as measured against established requirements, such as standards or tests, that qualify an individual to perform a required functi

49、on? reference base. A procedure, a process, a material, or an object used to determine and correct for the differ- ence between measurements and an accepted norm. review, A means of assuring that current policies, pro- cedures, and practices are adequate, appropriate, and effective in meeting the goals of the measurement pro- gram. standard deviation. The positive square root of the ariance. uncertainty, A concept employed to describe the in- ability of a measurement process to measure exactly the correct value. variance population. ,The expected value of the squ