Přístroje jaderné techniky

Oblast zaměření: Přístroje jaderné techniky
Komise : IEC/SC 45B (Radiation protection instrumentation)
Původce: ISO\IEC\CEN\CENELEC
K připomínkám do: 22.10.2019
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This document provides technical-performance requirements, testing methods, requirements for operational performance and accompanying documents,  packaging, transportation and storage conditions for the system of spectral identification  of liquids in transparent and semitransparent containers (hereinafter referred to as  “system”) based on the method of inelastic (Raman) light scattering by molecules.

 

The standard applies both to stationary and hand-held systems – geometric and mass parameters are not concerned in the tests. The standard is applicable to substance  identification testing criteria as well as verification, approval and operating criteria of the system. Since the standard considers only the functionality of Raman analyzers and their ability to identify single- or multicomponent fluids, it is equally suitable for verifying the Raman analyzers assigned to security screening of threats, inspection of medical solutions, liquid chemicals, etc.

Oblast zaměření: Přístroje jaderné techniky
Komise : IEC/SC 45A (Instrumentation and control of nuclear facilities)
Původce: ISO\IEC\CEN\CENELEC
K připomínkám do: 10.12.2019
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Since strict requirements on safety and availability of nuclear I&C apply, due consideration of cybersecurity threats is needed.

Since nowadays nuclear I&C programmable digital systems are largely based on digital systems including networks, individual I&C systems are more and more interconnected, and the I&C equipment is widely spread within the NPP area, security controls for prevention, detection and correction are needed to protect nuclear I&C programmable digital systems from external and internal cybersecurity threats.

The objective of this standard is to extend the SC45A series of documents addressing cybersecurity with IEC 62645 as its top-level document, by defining nuclear I&C programmable digital system specific security controls for I&C systems of the Safety Classes 1, 2, 3 and for non-classified (NC) I&C systems. The safety classification of I&C systems, and associated safety requirements, are among the biggest differences compared to typical IT systems and standard industrial automation systems. Annex B contains a correspondence between IEC 62645 and IEC 63096.

This standard, based on the security controls defined in ISO/IEC 27002, reflects the special security control requirements for nuclear I&C programmable digital systems. The original ISO/IEC 27002 requirements are either modified, detailed or completed, wherever deemed necessary from a nuclear I&C programmable digital system perspective. Additional nuclear I&C programmable digital system specific security controls that are not identified in ISO/IEC 27002, but deemed necessary are also added.

IEC 63096 refers in detail to a distinct version of IEC 27002 (see clause 2, Normative references). A later modification of IEC 27002 must not automatically influence the modifications, detailing and completions given by IEC 63096 without analysing the consequences from the nuclear I&C perspective.

By applying and extending the ISO/IEC 27002 security controls, this standard implicitly reflects all lifecycle phases of nuclear I&C programmable digital system platforms and systems.

By selecting the highly recommended security controls based on the processes as defined in IEC 62645 and the additional process details described within this standard the risk level will be reduced to an acceptable level.

The selection of security controls shall ensure that both safety and security requirements are met according to IEC 62859. If a specific security control negatively influences safety, safety prevails (see IEC 62859) and a compensatory security control should be implemented.

For the development of this standard ISO/IEC 27009 has been followed as far as applicable, also considering that the ISO/IEC 27009 is not binding for the SC45A IEC standard series.

ISO/IEC 27019 explicitly excludes the “process control domain of nuclear facilities”. 

NOTE: The term “process control domain of nuclear facilities” is a quote from the ISO/IEC 27019.

Oblast zaměření: Přístroje jaderné techniky
Komise : IEC/SC 45A (Instrumentation and control of nuclear facilities)
Původce: ISO\IEC\CEN\CENELEC
K připomínkám do: 10.12.2019
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This International Standard applies to the design, location and application of installed equipment for monitoring local gamma radiation dose rates within nuclear facilities during normal operation and anticipated operational occurrences. High range area gamma radiation dose rate monitoring equipment for accident conditions currently addressed by IEC 60951-1 and IEC 60951-3 is not within the scope of this standard.

This standard is intended to be used in conjunction with IEC 60532 Ed. 3.0:2010.

NOTE  This standard does not apply to the measurement of neutron dose rate. Additional equipment for neutron monitoring may be required, depending on the plant design, if the neutron dose rate makes a substantial contribution to the total dose equivalent to personnel.

This standard provides guidelines for the design principles, the location, the application, the calibration, the operation, and the testing of installed equipment for continuously monitoring local gamma radiation dose rates in nuclear facilities under normal operation conditions and anticipated operational occurrences. These instruments are normally referred to as area radiation monitors. Portable instruments are also used for this purpose but are not covered by this standard.

Radiation monitors utilized in area radiation monitoring equipment are addressed in IEC 60532. As discussed in that standard measurement of gamma radiation may be expressed by a number of alternative quantities depending on national regulations. However, for this type of instrument, the most likely quantity to be measured is the air kerma (Gy), or the ambient dose equivalent H*(10)(Sv).