Nuclear facilities – Instrumentation and control systems – Design, location and application criteria for installed area gamma radiation dose rate monitoring equipment for use during normal operation and anticipated operational occurrences
|Publication Date:||1 July 2020|
|ICS Code (Radiation protection):||13.280|
|ICS Code (Reactor engineering):||27.120.10|
This document 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 document.
This document 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 document 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 document.
Radiation monitors utilized in area radiation monitoring equipment are addressed in IEC 60532. As discussed in IEC 60532, 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).