BS ISO 26802:2010 - Nuclear facilities. Criteria for the design and the operation of containment and ventilation systems for nuclear reactors – BSI British Standards

BS ISO 26802:2010

Nuclear facilities. Criteria for the design and the operation of containment and ventilation systems for nuclear reactors

Status : Current, Under review   Published : August 2010



BS ISO 26802:2010 Nuclear facilities. Criteria for the design and the operation of containment and ventilation systems for nuclear reactors

BS ISO 26802 is an International Standard which specifies the applicable requirements related to the design and the operation of containment and ventilation systems of nuclear power plants and research reactors, taking into account the following.

For nuclear power plants, BS ISO 26802 addresses only reactors that have a secondary confinement system based on International Atomic Energy Agency (IAEA) recommendations.

For research reactors, BS ISO 26802 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 shutoff of the associated 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 17873. However, the requirements of BS ISO 26802 can also be applied.

Contents of BS ISO 26802:

1 Scope
2 Normative references
3 Terms and definitions
4 Functions ensured by the ventilation system
4.1 General
4.2 Main functions
5 Architecture and description of the different ventilation systems
5.1 Ventilation of the volumes within the primary containment envelope
5.2 Ventilation of the volumes located within the secondary confinement
5.3 Ventilation of the volumes located outside the secondary confinement
5.4 Miscellaneous ventilation systems not connected with containment envelopes
6 Safety aspects for ventilation systems
6.1 General principles
6.2 Risk assessment procedure — General
6.3 Risk assessment procedure for severe accidents
7 Requirements for the design of ventilation systems
7.1 Confinement of radioactive material
7.2 Filtration
7.3 Reactor specificities
8 Management of specific risks
8.1 Control of combustible gases in the reactor building
8.2 Management of ambient conditions
8.3 Prevention of risks linked to releases of heat, gases or toxic vapours
8.4 Prevention of risks linked to the deposition of matter in ventilation ducts
8.5 Prevention of fire hazard
8.6 Consideration of external hazards
9 Dispositions concerning the management and the operation of the ventilation systems
9.1 Organization and operating procedures
9.2 Technical operating instructions
9.3 Operational management issues
9.4 Test procedures and maintenance
9.5 Monitoring of the ventilation system
9.6 Control of the ventilation system to prevent fire hazards
10 Control and instrumentation
Annex A (informative) Typical radioactive products in nuclear reactors
Annex B (informative) Examples of general confinement concepts for nuclear power reactors
Annex C (informative) Examples of safety classification for nuclear power reactors
Annex D (informative) Examples of classification of working areas according to radiological contamination hazard
Annex E (informative) Example of classification of types of ventilation, according to radiological contamination hazard — Recommended ventilation configurations
Annex F (informative) Existing requirements for aerosol filters
Annex G (informative) Examples of loads to consider during the design of NPP ventilation systems
Annex H (informative) Typical values of leaktightness for containment and ventilation systems and periodicities of associated controls
Annex I (informative) Primary containment envelope status


Standard NumberBS ISO 26802:2010
TitleNuclear facilities. Criteria for the design and the operation of containment and ventilation systems for nuclear reactors
StatusCurrent, Under review
Publication Date31 August 2010
Confirm Date11 March 2016
Normative References(Required to achieve compliance to this standard)ICRP Publication 103, ISO 10648-2, ISO 17873
Informative References(Provided for Information)IAEA NS-R-1:2000, EN 12101, CNSC R-7:1991, ISO 2889:2010, NRC Regulatory Guide 1.78:2002, NRC Regulatory Guide 1.52:2001, EUROVENT 4/9:1996, CAN/CSA N287.3, NORDTEST NT VVS 117:1998, CAN/CSA N287.7, CAN/CSA N287.1, IAEA NS-G-1.7:2004, CAN/CSA N288.3.2, ISO 8421-1, EUROVENT 4/4:1976, ASME AG-1:2009, ASHRAE 52.2:1997 Draft, ASHRAE 52.1:1992, ISO 10648-1, ICRP Publication 60:1991, EUROVENT 4/5:1992, NRC Regulatory Guide 1.140:2001, IAEA TS-R-1:2009, EN 779:2002, EN 1822-2:2009, EN 1822-4:2009, ISO 11933-4, NF X 44-060:1993, CAN/CSA N285.3, CEA/CETREVE:1996, ISO 15080, IAEA NS-G-1.13:2005, CAN/CSA N287.6, IAEA NS-G-1.10:2004, CAN/CSA N293, DIN 24185:1994, ASHRAE 52.2:2007, IAEA NS-R-4:2005, CAN/CSA N287.5
International RelationshipsISO 26802:2010
Draft Superseded By08/30151428 DC
DescriptorsNuclear safety, Radiation protection, Air cleaning equipment, Filtration, Air filters, Nuclear-electric power stations, Nuclear power, Sealed, Nuclear containment structures, Nuclear reactors, Nuclear technology, Industrial facilities, Air-conditioning systems, Containment enclosures, Contamination, Ventilation
Title in FrenchInstallations nucléaires. Critères pour la conception et l'exploitation des systèmes de confinement et de ventilation des réacteurs nucléaires
ISBN978 0 580 57124 4
File Size1.824 MB

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