BS IEC IEEE-63113-2021 pdf download.Nuclear facilities — Instrumentation important to safety — Spent fuel pool instrumentation.
This document provides criteria for spent fuel pool instrumentation for nuclear power generating stations and other nuclear facilities. The document applies to water filled spent fuel pools where the water volume is necessary to prevent a release of fission products that exceeds allowed operational limits.
1.2 Purpose
The purpose of this document is to establish design, performance, qualification, and display criteria for spent fuel pool instrumentation for normal operation, anticipated operational occurrences, design basis events, and design extension conditions (including severe accident conditions).
1.3 Application
This document applies only to instrumentation for monitoring the condition of the spent fuel pool. i.e.. pool level, pool temperature. and area radiation. It does not apply to control systems that are related to the spent fuel pool such as: the pool cooling systems, isolation valve control, crane instrumentation and control, or refuelling machine instrumentation and control.
In some plant designs some of the instruments covered by this document also provide inputs to protection system functions. Such instruments must also comply with requirements for protection systems that are given elsewhere.
The requirements applied to the systems and components performing these functions depend on how they contribute to the safety of the spent fuel pool.
2 Normative references
The following documents are referred to in the text in such a way that some or all of their content constitutes requirements of this document. For dated references, only the edition cited applies. For undated references, the latest edition of the referenced document (including any amendments) applies.
IEC 60709:20 18, Nuclear power plants — Instrumentation, control and electrical power systems important to safety — Separation
IEC/IEEE 60780-323. Nuclear power plants — Electrical equipment important to safety — Qualification
IECIIEEE 60980-344, Nuclear facilities — Equipment important to safety — Seismic qualification
IEC 61226. Nuclear power plants — Instrumentation and control important to safety — Classification of instrumentation and control functions
NOTE 1 The use of IEC 61226 should take account of the discussion given in IEC TR 63123 [19].
IEC 61513, Nuclear power plants — Instrumentation and control important to safety — General requirements for systems
IEC 63046, Nuclear power plants — Electrical power system — General requirements IEEE 384 , 2018, IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits
NOTE 2 This document can be used with either IEEE andlor PEC normative references, but one coherent and consistent set of references shall be defined at the beginning of the project and used as a whole as the basis for the design and for all the project.
3 Terms and definitions
For the purposes of this document, the following terms and definitions apply.
ISO, IEC and IEEE maintain terminological databases for use in standardization at the following addresses:
• IEC Electropedia: available at http:l/www.electropedla.org/
• ISO Online browsing platform: available at http://www.iso.org/obp
• IEEE Standards Dictionary Online: available at http://dictionary.ieee.org
3.1 accident conditions
deviations from normal operation that are less frequent and more severe than anticipated operational occurrences
[SOURCE: IAEA Safety Glossary, 2018 Edition]
3.2 anticipated operational occurrence
deviation of an operational process from normal operation that is expected to occur at least once during the operating lifetime of a facility but which, in the view of appropriate design provisions, does not cause any significant damage to items important to safety or lead to accident conditions
[SOURCE: IAEA Safety Glossary, 2018 Edition]
3.3 common cause failure
failures of two or more structures, systems or components due to a single event or cause
Note 1 to entry: Common causes may be internal or external to an instrumentation and control (l&C) system
Note 2 to entry. The IEC definition differs from the IAEA In that the term specitic was deleted because this additional word is not necessary to understand the deuinition
[SOURCE: IAEA Safety Glossary. 2018 Edition, modified: see Note 2 to entry.]
3.4 design basis accident
postulated accident leading to accident conditions for which a facility is designed In accordance with established design criteria and conservative methodology, and for which releases of radioactive material are kept within acceptable limits
[SOURCE: IAEA Safety Glossary, 2018 Edition].BS IEC IEEE-63113 pdf download.