1、 AMERICAN NATIONAL STANDARD ANSI/ISA-67.02.01-2014 Nuclear Safety-Related Instrument-Sensing Line Piping and Tubing Standard for Use in Nuclear Power Plants Approved 4 April 2014 ANSI/ISA67.02.012014, Nuclear Safety-Related Instrument-Sensing Line Piping and Tubing Standard for Use in Nuclear Power
2、Plants ISBN: 978-0-876640-76-0 Copyright 2014 by the International Society of Automation (ISA). All rights reserved. Not for resale. Printed in the United States of America. No part of this publication may be reproduced, stored in a retrieval system, or transmitted in any form or by any means (elect
3、ronic mechanical, photocopying, recording, or otherwise), without the prior written permission of the Publisher ISA 67 Alexander Drive P.O. Box 12277 Research Triangle Park, North Carolina 27709 - 3 - ANSI/ISA-67.02-01-2014 Preface This preface, as well as all footnotes and annexes, is included for
4、information purposes only and is not part of the revised ANSI/ISA-67.02.01-2014. The 1999 revision incorporated ISA-S67.10, Sample Line Piping and Tubing Standard for Use in Nuclear Power Plants. Applicability of other standards or codes is as stated in the text. Where references are made to other s
5、tandards, a particular paragraph reference is indicated for clarity where applicable. The 2013 revision made minor changes to the 1999 revision. The figures were redrafted to clarify sensing lines from governing ASME codes, and sensing line slopes requirements were clarified with respect to liquid a
6、nd gas service. Two figures were added that are applicable to containment monitoring. The minimum slope recommendation for sensing lines was revised. This revised document has been prepared as part of the service of ISA, the International Society for Automation, toward a goal of uniformity in the fi
7、eld of instrumentation. To be of real value, this document should not be static but should be subject to periodic review. Toward this end, the Society welcomes all comments and criticisms and asks that they be addressed to the Secretary, Standards and Practices Board; ISA; 67 Alexander Drive; P. O.
8、Box 12277; Research Triangle Park, NC 27709; Telephone (919) 549-8411; Fax (919) 549-8288; E-mail: standardsisa.org. ISA Committee SP67.02 formed in 1974, adopted its draft scope on 19 September 1974, and forwarded it to the ISA Standards and Practices Board for acceptance as part of the minutes of
9、that meeting. On 9 December 1974, this committee received an approved Scope and Project, Charter N677, from the American National Standards Institute (ANSI). It is the consensus of the committee that this document addresses those portions of the safety-related, instrument-sensing line and sampling t
10、ubing (piping) runs that are unique to the nuclear power plant, concentrating therefore on meeting nuclear safety considerations as legislated by 10 CFR 50 (Code of Federal Regulations), Appendix A General Design Criteria for Nuclear Power Plants. The separation of redundant sensing lines as contain
11、ed in this document is predicated on the assumption that the equipment and instruments to which those sensing lines are connected are adequately separated. The ISA Standards and Practices Department is aware of the growing need for attention to the metric system of units in general, and the Internat
12、ional System of Units (SI) in particular, in the preparation of instrumentation standards, recommended practices, and technical reports. The Department is further aware of the benefits to USA users of ISA standards of incorporating suitable references to the SI (and the metric system) in their busin
13、ess and professional dealings with other countries. Toward this end, this Department will endeavor to introduce SI-acceptable metric units in all new and revised standards, recommended practices, and technical reports to the greatest extent possible. IEEE/ASTM SI 10, American National Standard for M
14、etric Practice, and future revisions, will be the reference guide for definitions, symbols, abbreviations, and conversion factors. Where the failure of instrument-sensing lines from nuclear safety-related processes to instruments that are not nuclear safety-related is demonstrated not to produce eit
15、her unacceptable leakage of process fluid or unacceptable flooding, jet impingement forces or other failure-related hazards to nuclear safety-related equipment, this document does not apply. CAUTION ISA DOES NOT TAKE ANY POSITION WITH RESPECT TO THE EXISTENCE OR VALIDITY OF ANY PATENT RIGHTS ASSERTE
16、D IN CONNECTION WITH THIS DOCUMENT, AND ISA DISCLAIMS LIABILITY FOR THE INFRINGEMENT OF ANY PATENT RESULTING FROM THE USE OF THIS DOCUMENT. USERS ARE ADVISED THAT DETERMINATION OF THE VALIDITY OF ANY PATENT RIGHTS, AND THE RISK OF INFRINGEMENT OF SUCH RIGHTS, IS ENTIRELY THEIR OWN RESPONSIBILITY. PU
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21、ALLY, THE USE OF THIS DOCUMENT MAY INVOLVE HAZARDOUS MATERIALS, OPERATIONS OR EQUIPMENT. THE DOCUMENT CANNOT ANTICIPATE ALL POSSIBLE APPLICATIONS OR ADDRESS ALL POSSIBLE SAFETY ISSUES ASSOCIATED WITH USE IN HAZARDOUS CONDITIONS. THE USER OF THIS DOCUMENT MUST EXERCISE SOUND PROFESSIONAL JUDGMENT CON
22、CERNING ITS USE AND APPLICABILITY UNDER THE USERS PARTICULAR CIRCUMSTANCES. THE USER MUST ALSO CONSIDER THE APPLICABILITY OF ANY GOVERNMENTAL REGULATORY LIMITATIONS AND ESTABLISHED SAFETY AND HEALTH PRACTICES BEFORE IMPLEMENTING THIS DOCUMENT. THE USER OF THIS DOCUMENT SHOULD BE AWARE THAT THIS DOCU
23、MENT MAY BE IMPACTED BY ELECTRONIC SECURITY ISSUES. THE COMMITTEE HAS NOT YET ADDRESSED THE POTENTIAL ISSUES IN THIS VERSION. The following people served as members of ISA Subcommittee ISA67.02: NAME COMPANY K. Herman, Chair Bechtel National Inc. J. Weiss, Managing Director Applied Control Solutions
24、 LLC K. Alto Emerson W. Barasa Sargent e.g., sensing lines that transfer pressure energy for measurement of the same pressure energy for the same process. 3.15 root valve: the first valve located on the instrument-sensing/sample line after it taps off the main process. 3.16 sample isolation valve: t
25、he valve nearest the instrument, grab-sample point, or in-line component that is available to personnel during normal plant operation to isolate them from the process. The root valve may or may not perform the function of the isolation valve, depending on its location. 3.17 sample lag time: an inter
26、val of time between the initiation of a discrete sample (particle, molecule, or atom) from the sample tap to termination at a specific volumetric flow rate through the sample line. - 11 - ANSI/ISA-67.02-01-2014 3.18 sample line: a piping and/or tubing system that removes fluid from a process either
27、continuously or periodically for the purpose of determining the constituents or the physical properties of the process fluid. The sample line begins at the process tap or nozzle used for sampling and terminates where the flow of sample fluid ends as a discrete and controlled entity. 3.19 sample sink
28、: an installed device with controlled drainage and/or ventilation at which a grab sample may be obtained. 3.20 sample tap: the point where the sample line taps into the process line (pipe, duct, container) and the point where sample flow begins. It may also be referred to as “sample connection,“ “sa
29、mple nozzle,“ or “process tap.“ 3.21 sample vessel: an integrally valved, portable sample container designed to obtain pressurized samples at process pressure. 3.22 sensing line: for the purpose of this Standard, a pipe or tube or both of relatively static fluid that connects the process being sense
30、d to the sensor (transducer). 4 Pressure boundary and mechanical design requirements Summary of requirements for sensing lines 4.1Tables 1 and 2 summarize the minimum pressure boundary and mechanical design requirements for nuclear safety-related instrument-sensing lines utilized in nuclear power pl
31、ants. Table 1 applies to instrument-sensing lines that do not penetrate the primary reactor containment, and table 2 applies to instrument-sensing lines that penetrate the primary reactor containment. Tables 1 and 2 are divided into four columns. Column 1 refers the user to the applicable figure(s)
32、that graphically show the mechanical design requirements specified in columns 2, 3, and 4. The figure referenced in column 1 also indicates the pressure boundary scope of this Standard. Column 2 indicates the process system code classification. Column 3 indicates the instrument-sensing line seismic
33、category. Where more than one seismic category is listed, the seismic category change is shown on the figure(s) referenced in column 1. Column 4 indicates the applicable design code for the instrument-sensing line. Mechanical design requirements for sensing lines 4.2The design of components, parts,
34、and appurtenances utilized in the instrument-sensing lines under the scope of this Standard shall, as a minimum, be in accordance with the design code(s) specified in column 4 of tables 1 and 2. Figures 1 through 8 illustrate typical applications of these requirements. Instrument-sensing and sample
35、lines in accordance with ANSI B31.1 power piping 4.2.1Where ASME B31.1 is required by this Standard in clause 4, the user shall comply with ASME B31.1, paragraph 122.3 requirements for materials, design, fabrication, examination, and testing. Where instrument-sensing lines identified as ASME B31.1 a
36、re interconnected with process piping systems classified as ASME Section III Class 1, 2, or 3 and are identified as Seismic Category I in tables 1 and 2, the following additional requirements shall apply: ANSI/ISA-67.02-01-2014 - 12 - a) A material manufacturers certificate of compliance with the ma
37、terial specification shall be furnished for all pressure boundary items. b) All pressure boundary items shall be pressure tested in accordance with the applicable ASME Code. c) Design and service limits for lines identified as ASME B31.1 and Seismic Category I by this Standard shall be in accordance
38、 with ASME B31.1, paragraph 104.8. Movements due to earthquakes and other transient dynamic loading shall be included. d) The connection between ASME Section III and ASME B31.1 components shall be in accordance with ASME Section III. Media isolation devices, bellows or diaphragms, and permanently fi
39、lled capillaries 4.2.2This subclause applies principally to capillary instrumentation that is furnished preassembled by the instrument manufacturer, but also may apply to field fabricated assemblies. 4.2.2.1 Bellows or diaphragms Where bellows or diaphragms are identified as ASME B31.1 by this Stand
40、ard, these devices shall be designed in accordance with ASME B31.1, paragraph 104.7. The requirements of 4.2.1 of this Standard shall also apply. 4.2.2.2 Permanently filled capillary tubes Where permanently filled capillary tubes are identified as ASME B31.1 by this Standard, the pressure design and
41、 minimum wall thickness shall be established in accordance with ASME B31.1, or the pressure design shall be established by proof tests in accordance with ASME Section I, paragraph A-22. 4.2.2.3 Pressure testing Each permanently filled capillary tube and media isolation device shall be pressure teste
42、d in accordance with the applicable ASME Code. 4.2.2.4 Fill fluid The fill fluid used shall not shorten the life of or prevent the piping or tubing wetted parts from performing their required functions. Mercury shall not be used as a fill fluid. - 13 - ANSI/ISA-67.02-01-2014 Table 1 Minimum mechanic
43、al design requirements for instrument piping and tubing that do not penetrate the primary reactor containment Illustration Process Piping ASME Code Class Instrument-Sensing Line Seismic Category Applicable Design Code as invoked by this Standard in Clause 4 Figure 1 a otherwise, additional wall thic
44、kness or support may be required for mechanical strength. 6.1.5 Any permanent taps, piping, and tubing provided for testing or calibration shall comply with this Standard. 6.1.6 Where samples are being taken to measure particulates or other impurities that are expected to stratify, a multi-port-type
45、 sampling tap extending across the pipe diameter should be provided. Further, sample-flow rates should be adjusted so that fluid velocity through the sample nozzles is the same as that which exists in the process lines (isokinetic sample rate). The isokinetic sample rate normally should be adjusted
46、for the flow rate expected at 100 percent load. Where isokinetic sampling is required, it is important that there be sufficient upstream straight run ahead of the sample tap to assure a stable, predictable flow profile across the line. Straight-run requirements vary with the upstream configuration.
47、6.1.7 When sampling water, samples should be taken at a point where the fluid is turbulent. If one of the constituents to be measured is considerably heavier than water, or if there is two-phase flow, the points where centrifugal action may cause concentration of any constituents shall be avoided. (
48、Water samples do not present much of a problem where the flow rate assures turbulent flow.) A Reynolds number of 4000 or greater is usually considered sufficient to assure turbulent flow, although there is some variation depending on pipe size and wall roughness. Even with turbulent flow, the sample
49、 should be taken at a distance from the pipe wall (to avoid sampling a stagnant wall film). 6.1.8 In non-radioactive sample lines, the sample-line length should be kept to a minimum for applications where dissolved solids or suspended particulates are the constituent of interest in the sample. Local grab-sample points shall be as close to the process-sampling connection as practical. Selection of piping versus tubing 6.2Tubing is generally preferred over piping because of lower initial cost and greater ease of handling. However, piping should be used in the following cas
