IEC IEEE 63113 pdf – Nuclear facilities – Instrumentation important to safety – Spent fuel pool instrumentation
1 Scope
1.1General
This document provides criteria for spent fuel pool instrumentation for nuclear power generatingstations 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 allowedoperational limits.
1.2Purpose
The purpose of this document is to establish design，performance，qualification,and displaycriteria for spent fuel pool instrumentation for normal operation, anticipated operationaloccurrences, design basis events, and design extension conditions (including severe accident
conditions).
1.3Application
This document applies only to instrumentation for monitoring the condition of the spent fuelpool, 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 inputsto protection system functions. Such instruments must also comply with requirements’ forprotection systems that are given elsewhere.
The requirements applied to the systems and components performing these functions dependon how they contribute to the safety of the spent fuel poo’1.
2Normative references
The following documents are referred to in the text in such a way that some or all of their contentconstitutes requirements of this document. For dated references, only the edition cited applies.
For undated references,the latest edition of the referenced document(including anyamendments) applies.
IEC 60709:2018,Nuclear power plants – Instrumentation, control and electrical power systemsimportant to safety – Separation
IEC/IEEE60780-323， Nuclear power plants – Electrical equipment important to safety -Qualification
IEC/IEEE 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 lEC 61226 should take account of the discussion given in IEC TR 63123[19].
IEC 63046，Nuclear power plants -Electrical power system – General requirements
IEEE Std 384 TM -2018，IEEE Standard Criteria for Independence of Class 1E Equipment andCircuits
NOTE 2 This document can be used with either IEEE andlor lEC normative references, but one coherent andconsistent set of references shall be defined at the beginning of the project and used as a whole as the basis for thedesign and for all the project.
3 Terms and definitions
For the purposes of this document, the following terms and definitions apply.
ISO,IEC and lEEEmaintain terminological databases for use in standardization at the followingaddresses:
×IEC Electropedia: available at http://www.electropedia.orgl
xIso Online browsing platform: available at http://www.iso.orglobp
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 anticipatedoperational 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 leastonce during the operating lifetime of a facility but which, in the view of appropriate designprovisions,does not cause any significant damage to items important to safety or lead toaccident 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 (I&C) system.
Note 2 to entry: The lEC definition differs from the lIAEA in that the term “specific” was deleted because thisadditional word is not necessary to understand the definition.
[SOURCE: IAEA Safety Glossary, 2018 Edition, modified: see Note 2 to entry.J
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 ofradioactive material are kept within acceptable limits
[SOURCE:IAEA Safety Glossary, 2018 Edition]