IEEE 323-2003 pdf download IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations
1.Scope
This standard describes the basic requirements for qualifying Class 1E equipment and interfaces that are tobe used in nuclear power generating stations. The principles, methods, and procedures described areintended to be used for qualifying equipment, maintaining and extending qualification, and updatingqualification, as required, if the equipment is modified, The qualification requirements in this standard,when met, demonstrate and document the ability of equipment to perform safety function(s) underapplicable service conditions including design basis events, reducing the risk of common-cause equipmentfailure. This standard does not provide environmental stress levels and performance requirements.
NOTE–Other lEEE standards that present qualification methods for specific equipment, specific environments, orspecific parts of the qualification program may be used to supplement this standard, as applicable. Annex A lists otherstandards related to equipment qualification.
2.References
This standard shall be used in conjunction with the following standards. When the following standards aresuperseded by an approved version, the revision shall apply.
IEEE Std 344”-1987 (Reaff 1993), IEEE Recommended Practice for Seismic Qualification of Class 1EEquipment for Nuclear Power Generating Stations.1,2
IEEE Std 603″-1998, 1EEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations.
IEEE Std 7-4.3.2″*-2003,IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear PowerGenerating Stations.
3. Definitions
The following terms are considered important for accurate interpretation of this standard. Definitions ofterms are given in The Authoriative Dictionary of IEEE Standards Terms, Seventh Edition (B313, and are
repeated here for convenience in using this standard.
3.1 age conditioning: Exposure of sample equipment to environmental, operational, and system conditionsto simmulate these conditions for a period of tie: desien basis events are not included
3.2 Class 1E: The safety classification of the electric equipment and systems that are essential to emergencyreactor shutdown, containment isolation, reactor core cooling, and containment and reactor heat removal, oare otherwise essential in preventing significant release of radioactive material to the environment.NOTE–The terms Class 1E equipment and safety-related electric equipment are synonymous
3.3 components: Items from which the equipment is assembled, e.g., resistors, capacitors, wires, connectors.transistors,tubes, switches, and springs.
3.4 condition-based qualification: Qualification based on measurement of one or more condition indicators of equipment, its components, or materials for which an acceptance criterion can be correlated to theequipment’s ability to function as specified during an applicable design basis event.
3.5 condition indicator: A measurable physical property of equipment,its components, or materials thatchanges monotonically with time and can be correlated with its safety function performance under designbasis event conditions.
3.6 design basis events: Postulated events used in the design to establish the acceptable performancerequirements for the structures, systems, and components.
3.7 design life: The time period during which satisfactory performance can be expected for a specific set ofservice conditions.
3.8 end condition: Value(s) of equipment condition indicator(s) at the conclusion of age conditioning
3.9 equipment: An assembly of components designed and manufactured to perform specific functions
3.10 equipment qualification: The generation and maintenance of evidence to ensure that equipment willoperate on demand to meet system performance requirements during normal and abnormal service conditions and postulated design basis events.NOTE-Equipment qualification includes environmental and seismic qualification
3.11 harsh environment: An environment resulting from a design basis event, i.e.. loss-of-coolant accident(LOCA), high-energy line break (HELB), and main steam line break (MSLB).
IEEE 323-2003 pdf download
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