BS ISO 26802-2010 Nuclear facilities Criteria for the design and the operation of containment and ventilation systems for nuclear reactors《核设施 核反应堆用防泄漏和通风系统设计和操作准则》.pdf

1、raising standards worldwideNO COPYING WITHOUT BSI PERMISSION EXCEPT AS PERMITTED BY COPYRIGHT LAWBSI Standards PublicationBS ISO 26802:2010Nuclear facilities Criteria forthe design and the operationof containment and ventilationsystems for nuclear reactorsBS ISO 26802:2010 BRITISH STANDARDNational f

2、orewordThis British Standard is the UK implementation of ISO 26802:2010.The UK participation in its preparation was entrusted to TechnicalCommittee NCE/2, Radiation protection and measurement.A list of organizations represented on this committee can beobtained on request to its secretary.This public

3、ation does not purport to include all the necessaryprovisions of a contract. Users are responsible for its correctapplication. BSI 2010ISBN 978 0 580 57124 4ICS 27.120.10Compliance with a British Standard cannot confer immunity fromlegal obligations.This British Standard was published under the auth

4、ority of theStandards Policy and Strategy Committee on 31 August 2010.Amendments issued since publicationDate Text affectedBS ISO 26802:2010Reference numberISO 26802:2010(E)ISO 2010INTERNATIONAL STANDARD ISO26802First edition2010-08-01Nuclear facilities Criteria for the design and the operation of c

5、ontainment and ventilation systems for nuclear reactors Installations nuclaires Critres pour la conception et lexploitation des systmes de confinement et de ventilation des racteurs nuclairesBS ISO 26802:2010ISO 26802:2010(E) PDF disclaimer This PDF file may contain embedded typefaces. In accordance

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8、Every care has been taken to ensure that the file is suitable for use by ISO member bodies. In the unlikely event that a problem relating to it is found, please inform the Central Secretariat at the address given below. COPYRIGHT PROTECTED DOCUMENT ISO 2010 All rights reserved. Unless otherwise spec

9、ified, no part of this publication may be reproduced or utilized in any form or by any means, electronic or mechanical, including photocopying and microfilm, without permission in writing from either ISO at the address below or ISOs member body in the country of the requester. ISO copyright office C

10、ase postale 56 CH-1211 Geneva 20 Tel. + 41 22 749 01 11 Fax + 41 22 749 09 47 E-mail copyrightiso.org Web www.iso.org Published in Switzerland ii ISO 2010 All rights reservedBS ISO 26802:2010ISO 26802:2010(E) ISO 2010 All rights reserved iiiContents Page Foreword .v Introductionvi 1 Scope1 2 Normati

11、ve references1 3 Terms and definitions .2 4 Functions ensured by the ventilation system 6 4.1 General .6 4.2 Main functions .7 5 Architecture and description of the different ventilation systems 8 5.1 Ventilation of the volumes within the primary containment envelope 8 5.2 Ventilation of the volumes

12、 located within the secondary confinement 10 5.3 Ventilation of the volumes located outside the secondary confinement 10 5.4 Miscellaneous ventilation systems not connected with containment envelopes 11 6 Safety aspects for ventilation systems .11 6.1 General principles .11 6.2 Risk assessment proce

13、dure General12 6.3 Risk assessment procedure for severe accidents.14 7 Requirements for the design of ventilation systems.15 7.1 Confinement of radioactive material .16 7.2 Filtration .33 7.3 Reactor specificities35 8 Management of specific risks 38 8.1 Control of combustible gases in the reactor bu

14、ilding.38 8.2 Management of ambient conditions 39 8.3 Prevention of risks linked to releases of heat, gases or toxic vapours 41 8.4 Prevention of risks linked to the deposition of matter in ventilation ducts 41 8.5 Prevention of fire hazard 42 8.6 Consideration of external hazards 45 9 Dispositions

15、concerning the management and the operation of the ventilation systems46 9.1 Organization and operating procedures.46 9.2 Technical operating instructions.46 9.3 Operational management issues .47 9.4 Test procedures and maintenance 47 9.5 Monitoring of the ventilation system.50 9.6 Control of the ve

16、ntilation system to prevent fire hazards.51 10 Control and instrumentation 53 10.1 Control53 10.2 Instrumentation .53 10.3 Alarms.54 Annex A (informative) Typical radioactive products in nuclear reactors55 Annex B (informative) Examples of general confinement concepts for nuclear power reactors.58 A

17、nnex C (informative) Examples of safety classification for nuclear power reactors.64 Annex D (informative) Examples of classification of working areas according to radiological contamination hazard .66 BS ISO 26802:2010ISO 26802:2010(E) iv ISO 2010 All rights reservedAnnex E (informative) Example of

18、 classification of types of ventilation, according to radiological contamination hazard Recommended ventilation configurations.68 Annex F (informative) Existing requirements for aerosol filters 73 Annex G (informative) Examples of loads to consider during the design of NPP ventilation systems.78 Ann

19、ex H (informative) Typical values of leaktightness for containment and ventilation systems and periodicities of associated controls.79 Annex I (informative) Primary containment envelope status81 Bibliography 82 BS ISO 26802:2010ISO 26802:2010(E) ISO 2010 All rights reserved vForeword ISO (the Intern

20、ational Organization for Standardization) is a worldwide federation of national standards bodies (ISO member bodies). The work of preparing International Standards is normally carried out through ISO technical committees. Each member body interested in a subject for which a technical committee has b

21、een established has the right to be represented on that committee. International organizations, governmental and non-governmental, in liaison with ISO, also take part in the work. ISO collaborates closely with the International Electrotechnical Commission (IEC) on all matters of electrotechnical sta

22、ndardization. International Standards are drafted in accordance with the rules given in the ISO/IEC Directives, Part 2. The main task of technical committees is to prepare International Standards. Draft International Standards adopted by the technical committees are circulated to the member bodies f

23、or voting. Publication as an International Standard requires approval by at least 75 % of the member bodies casting a vote. Attention is drawn to the possibility that some of the elements of this document may be the subject of patent rights. ISO shall not be held responsible for identifying any or a

24、ll such patent rights. ISO 26802 was prepared by Technical Committee ISO/TC 85, Nuclear energy, Subcommittee SC 2, Radiological protection. BS ISO 26802:2010ISO 26802:2010(E) vi ISO 2010 All rights reservedIntroduction Containment and ventilation systems of nuclear power plants (NPPs) and research r

25、eactors ensure the security of such installations in order to protect the workers, the public and the environment from the dissemination of radioactive contamination originating from the operations of these installations. This International Standard applies specifically to systems of confinement and

26、 ventilation systems for the confinement areas of reactors and their specialized buildings (such as command centres and particular areas for air purging and conditioning). This International Standard is complementary to ISO 17873, which applies mainly to nuclear fuel cycle installations (e.g. reproc

27、essing plants, nuclear fuel fabrication and examination laboratories, plutonium handling facilities) and to radioactive waste storage, research facilities and auxiliary buildings of nuclear reactors. BS ISO 26802:2010INTERNATIONAL STANDARD ISO 26802:2010(E) ISO 2010 All rights reserved 1Nuclear faci

28、lities Criteria for the design and the operation of containment and ventilation systems for nuclear reactors 1 Scope This International Standard specifies the applicable requirements related to the design and the operation of containment and ventilation systems of nuclear power plants and research r

29、eactors, taking into account the following. For nuclear power plants, this International Standard addresses only reactors that have a secondary confinement system based on International Atomic Energy Agency (IAEA) recommendations (see Reference 10). For research reactors, this International Standard

30、 applies specifically to reactors for which accidental situations can challenge the integrity or leak-tightness of the containment barrier, i.e. in which a high-pressure or high-temperature transient can occur and for which the isolation of the containment building and the shut-off of the associated

31、 ventilation systems of the containment building is required. For research reactors in which the increase of pressure or temperature during accidental situations will not damage the ventilation systems, the requirements applicable for the design and the use of ventilation systems are given in ISO 17

32、873. However, the requirements of this International Standard can also be applied. 2 Normative references The following referenced documents are indispensable for the application of this document. For dated references, only the edition cited applies. For undated references, the latest edition of the

33、 referenced document (including any amendments) applies. ISO 10648-2, Containment enclosures Part 2: Classification according to leak tightness and associated checking methods ISO 17873, Nuclear facilities Criteria for the design and operation of ventilation systems for nuclear installations other t

34、han nuclear reactors ICRP 103, The 2007 Recommendations of the International Commission on Radiological Protection, ICRP Publication 103, Annals of the ICRP, 37 (2-4), Elsevier BS ISO 26802:2010ISO 26802:2010(E) 2 ISO 2010 All rights reserved3 Terms and definitions For the purposes of this document,

35、 the following terms and definitions apply. 3.1 Accident 3.1.1 design basis accident DBA accident conditions against which a facility is designed according to established design criteria, and for which the damage to the fuel and the release of radioactive material are kept within authorized limits 3

36、.1.2 beyond-design basis accident BDBA accident conditions more severe than a design basis accident 3.1.3 severe accident accident conditions more severe than a design basis accident and involving significant core degradation 3.2 aerosol solid particles and liquid droplets of all dimensions in suspe

37、nsion in a gaseous fluid 3.3 air exchange rate ratio between the ventilation air flow rate of a containment enclosure or a compartment, during normal operating conditions, and the volume of this containment enclosure or compartment 3.4 air conditioning arrangements that allow sustaining a controlled

38、 atmosphere (temperature, humidity, pressure, dust levels, gas content, etc.) in a defined volume 3.5 balancing damper control valve adjustable device inserted in an aerodynamic duct allowing balancing of the fluid flow and/or the pressure of the fluid during plant operation 3.6 barrier structural e

39、lement that defines the physical limits of a volume with a particular radiological environment and that prevents or limits releases of radioactive substances from this volume EXAMPLE Nuclear fuel cladding, primary circuit, containment building of a nuclear reactor, containment walls of auxiliary bui

40、ldings, filters for some cases. 3.7 cell shielded enclosure shielding structure, of fairly large dimensions, possibly leak-tight See containment enclosure (3.10). NOTE It is often more practicable to limit the spread of a fire by using fire-resistant walls, and to prevent the spread of contamination

41、 in the adjacent volumes. BS ISO 26802:2010ISO 26802:2010(E) ISO 2010 All rights reserved 33.8 containment/confinement arrangement allowing users to maintain separate environments inside and outside an enclosure, blocking the movement between them of process materials and substances resulting from p

42、hysical and chemical reactions that are potentially harmful to workers, to the public, to the external environment, or for the handled products 3.9 containment compartment CC compartment of which the walls are able to contain radioactive substances that would be generated by any plausible fire that

43、breaks out in one of the fire compartments included NOTE It is often more practicable to limit the spread of a fire by using fire-resistant walls, and to prevent the spread of contamination in the adjacent volumes. 3.10 containment enclosure enclosure designed to prevent either the leakage of produc

44、ts contained in the pertinent internal environment into the external environment, or the penetration of substances from the external environment into the internal environment, or both simultaneously See cell (3.7). NOTE This is a generic term used to designate all kinds of enclosures, including glov

45、e boxes, leak-tight enclosures and shielded cells equipped with remotely operated devices. 3.11 containment envelope volume allowing the enclosure, and thus the isolation from the environment, of those structures, systems and components whose failure can lead to an unacceptable release of radionucli

46、des 3.12 containment/confinement system system constituted of a coherent set of physical barriers and/or dynamic systems intended to confine radioactive substances in order to ensure the safety of the workers and the public and the protection of the environment and to avoid releases of radioactive m

47、aterials in the environment NOTE According to IAEA definitions, a containment system concerns the containment structure and the associated systems with the functions of isolation, energy management, and control of radionuclides and combustible gases. This containment system also protects the reactor

48、 against external events and provides radiation shielding during operational states and accident conditions. These two last functions are not described in this International Standard, due to the absence of link with the ventilation systems. 3.13 contamination presence of radioactive substances on or

49、 in a material or a human body or any place where they are undesirable or can be harmful 3.14 decontamination factor measure of the efficiency achieved by a filtration system and corresponding to the ratio of the radiological contents of the inlet and outlet of the filtration system 3.15 discharge stack duct (usually vertical) at the termination of a system, from which the air is discharged to the atmosphere after control BS ISO 26802:2010ISO 26802:2010(E) 4 ISO 2010 All rights reserved3.16 dynamic confinement action allowi