CSA N287 7-2008 In-service examination and testing requirements for concrete containment structures for CANDU nuclear power plants (Fourth Edition Update No 1 September 2010).pdf

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1、N287.7-08In-service examination and testing requirements for concrete containment structures for CANDU nuclear power plantsLegal Notice for StandardsCanadian Standards Association (CSA) standards are developed through a consensus standards development process approved by the Standards Council of Can

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17、not load or use this document or make any copies of the contents hereof, and if you do make such copies, you are required to destroy them immediately. Use of this document constitutes your acceptance of the terms and conditions of this Legal Notice.Update No. 1N287.7-08September 2010Note: General In

18、structions for CSA Standards are now called Updates. Please contact CSA Information Products Sales or visit www.ShopCSA.ca for information about the CSA Standards Update Service.Title: In-service examination and testing requirements for concrete containment structures for CANDU nuclear power plants

19、originally published May 2008The following revisions have been formally approved and are marked by the symbol delta () in the margin on the attached replacement pages:Revised Table 1New NoneDeleted NoneCSA N287.7-08 originally consisted of 41 pages (viii preliminary and 33 text), each dated May 2008

20、. It now consists of the following pages:May 2008 iiiviii, 18, and 1133September 2010 9 and 10 Update your copy by inserting these revised pages.Keep the pages you remove for reference. Canadian Standards AssociationIn-service examination and testing requirements for concrete containment structures

21、for CANDU nuclear power plantsSeptember 20107.5.3 During pressure tests, an independent means of pressure monitoring shall be available during the pressurization phase of the test to prevent overpressurization.7.6 Leakage-rate test method7.6.1 The leakage-rate test method should be the absolute meth

22、od using the mass plot analysis technique (see Annex C). The termination criteria are such that the 95% confidence interval is a suitably small fraction of the measured leakage rate and the most recent data remain consistent with the data over the entire test period. 7.6.2 Where the test method spec

23、ified in Clause 7.6.1 is not used, an alternative method that meets the intent of this Standard shall be used.7.6.3 The test specified in Clauses 7.6.1 and 7.6.2 shall not be terminated in the event of abnormal trends.7.7 StabilizationFollowing a controlled pressure change, the pressure and temperat

24、ure shall be stabilized for a minimum period of 1 h unless a shorter stabilization period can be established. Stabilization is complete when the following conditions are met:(a) the average containment atmosphere temperature change is less than 0.25 K/h and is sustained over a 1 h period; and(b) the

25、 mass plot analysis technique demonstrates linearity as assessed by an experienced test engineer.Note: Arrangements should be made to ensure that the atmospheric conditions inside the containment are well mixed to promote stabilization. Well-mixed atmospheric conditions also ensure that instruments

26、give a valid representation of overall containment atmospheric conditions.7.8 HumidityThe conditions of the containment atmosphere during the pressure test shall be such that the dewpoint is low enough to prevent condensation on any surface.7.9 Duration of testThe leakage-rate test duration shall be

27、 determined by a qualified and experienced engineer on the basis of the allowable leakage rate and the accuracy of measurements established for each test procedure. In all cases, a statistically significant number of valid measurements shall be taken.7.10 Measurements7.10.1 Internal measurements of

28、pressure, temperature, and humidity shall be taken such that a statistically valid representation of their behaviour over the leakage-rate test interval is obtained.7.10.2 Pressure and temperature measurements of the surrounding outside environment of the containment structures shall be taken. Where

29、 used directly in the calculations, pressure and temperature measurements shall be recorded at the intervals specified in Clause 7.10.1.9(Replaces p. 9, May 2008)N287.7-08 Canadian Standards AssociationSeptember 20107.11 Instrumentation7.11.1 The precision and number of the instruments used in the l

30、eakage-rate test shall be determined in accordance with the following, at minimum:(a) the magnitude of the expected leakage rate;(b) the magnitude of the target leakage rate; and(c) the predicted total system error of the calculated leakage rate.7.11.2 Instrumentation for leakage-rate testing shall

31、be selected based on the criteria specified in Table 1. See Annex D for further information on selecting instrumentation.Table 1 Instrumentation selection requirements(See Clause 7.11.2.)7.11.3 Temperature measurement devices, pressure gauges, hygrometers, flowmeters, and other instruments used in c

32、onjunction with the tests shall be clearly identified with a unique number and calibrated and certified within 6 months prior to the test or at any time they are suspected of being out of calibration.7.12 Verification7.12.1 An independent means of verifying the measured leakage rate shall be used wh

33、en conducting a leakage-rate test. This may be achieved by one of the following methods:(a) a superimposed known leakage rate (see Clause 7.12.2); or(b) the use of two independent measurement systems to monitor and collect leakage-rate data (see Clause 7.12.3).7.12.2 When a superimposed known leakag

34、e rate is used as the independent verification test, the known leakage rate shall be determined by taking into consideration the expected leakage rate at the test pressure (see Clause 7.5.1) and the predicted total system error. Agreement between the known and calculated leakage rates shall be withi

35、n the total errors associated with the test, unless there is an explanation for the variance.CriterionDry bulb temperatureDewpoint temperature*Absolute pressure FlowSensor accuracy 0.6 C 1 C or 3.5% RH 0.14 kPa 2% of full scaleResolution 0.06 C 0.1 C or 0.5% RH 0.007 kPa 2% of full scaleRepeatabilit

36、y 0.1 C 0.1 C or 1% RH 0.001% of full scaleRange 2 times the maximum leakage rate at full test pressure*RH = relative humidity.(Replaces p. 10, May 2008)10Standards Update ServiceN287.7-08May 2008Title: In-service examination and testing requirements for concrete containment structures for CANDU nuc

37、lear power plantsPagination: 41 pages (viii preliminary and 33 text), each dated May 2008To register for e-mail notification about any updates to this publicationgo to shop.csa.caclick on CSA Update ServiceThe List ID that you will need to register for updates to this publication is 2020121.If you r

38、equire assistance, please e-mail techsupportcsagroup.org or call 416-747-2233.Visit CSA Groups policy on privacy at csagroup.org/legal to find out how we protect your personal information.Published in May 2008 by Canadian Standards AssociationA not-for-profit private sector organization5060 Spectrum

39、 Way, Suite 100, Mississauga, Ontario, Canada L4W 5N61-800-463-6727 416-747-4044Visit our Online Store at www.ShopCSA.caN287.7-08In-service examination and testing requirements for concrete containment structures for CANDU nuclear power plantsCSA Standard100%ISBN 978-1-55436-694-1Technical Editor: S

40、enka Krsikapa Canadian Standards Association 2008All rights reserved. No part of this publication may be reproduced in any form whatsoever without the prior permission of the publisher.To purchase CSA Standards and related publications, visit CSAs Online Store at www.ShopCSA.ca or call toll-free 1-8

41、00-463-6727 or 416-747-4044.The Canadian Standards Association (CSA) prints its publications on Rolland Enviro100, which contains 100% recycled post-consumer fibre, is EcoLogo and Processed Chlorine Free certified, and was manufactured using biogas energy.May 2008 iiiContents Canadian Standards Asso

42、ciationIn-service examination and testing requirements for concretecontainment structures for CANDU nuclear power plantsTechnical Committee on Concrete Containment and Safety-Related Structures vSubcommittee on In-service Examination and Testing Requirements for Concrete Containment Structures for C

43、ANDU Nuclear Power Plants viiPreface viii1Scope 12 Reference publications 13 Definitions 24 Owner/licensee responsibilities 25 General requirements 35.1 General 35.2 Basis of comparison 35.3 Personnel 35.4 Regulatory authority 46 Examination requirements 46.1 General 46.2 Pre-stressing systems 66.3

44、Frequency of examinations 66.4 Acceptance criteria 76.5 Repair and replacement 77 Leakage-rate test requirements 87.1 Pressure test requirements 87.2 Frequency of tests 87.3 On-power test 87.4 Vacuum-retaining containment structures 87.5 Leakage-rate test pressure 87.6 Leakage-rate test method 97.7

45、Stabilization 97.8 Humidity 97.9 Duration of test 97.10 Measurements 97.11 Instrumentation 107.12 Verification 107.13 Visual inspection and monitoring 117.14 Acceptance 117.15 Retesting 118 Test specifications 119 Test procedures 1310 Test report 13N287.7-08 Canadian Standards Associationiv May 2008

46、AnnexesA (informative) Guidelines for using test beams for evaluating bonded pre-stressing systems 15B (informative) Guidelines for evaluating unbonded post-tensioning systems 19C (informative) Leakage-rate analysis method 23D (informative) Instrument selection guide (ISG) 26E (informative) Performa

47、nce-based test interval option 28F (informative) Guidelines for evaluating pre-stressing systems using instrumented monitoring 31Tables1 Instrumentation selection requirements 10 Canadian Standards AssociationIn-service examination and testing requirements for concretecontainment structures for CAND

48、U nuclear power plantsMay 2008 vTechnical Committee on Concrete Containment and Safety-Related StructuresT.S. Aziz Atomic Energy of Canada Limited,Mississauga, OntarioChairD.J. Armchuk Bruce Power, Tiverton, OntarioVice-ChairA. Blahoianu Canadian Nuclear Safety Commission,Ottawa, OntarioVice-ChairJ.

49、P.D. Brock RCM Technologies Canada Corp.,Pickering, OntarioK.M. Chaudhry Canadian Nuclear Safety Commission,Ottawa, OntarioAssociateR. Cullen Kinectrics Inc.,Toronto, OntarioM. Desharnais Hydro-Qubec,Bcancour, QubecR.J. El Frenn DYWIDAG-Systems International, Canada, Ltd.,Gormley, OntarioL. Gartley Hilti (Canada) Limited,Mississauga, OntarioA. Ghobarah McMaster University,Hamilton, OntarioX.M. Han SNC-Lavalin Nuclear Inc.,Oakville, OntarioJ.D. Hanna Bruce Power, Tiverton, OntarioAssociateJ. Li DYWIDAG-Systems Inter