Criteria for Class 1E power systems for nuclear power generating stations
1 Scope
The purpose of this standard is to provide the following, for nuclear power generating stations:
a) The principal design criteria and the design features of the Class 1E power systems that enable the systems to meet their functional requirements under the conditions produced by the applicable design basis events.
b) The requirements for tests and surveillance of the Class 1E power systems.
c) The criteria for sharing Class 1E power systems in multiunit stations.
d) The requirements for documentation of the Class 1E power systems.
This standard applies to the Class 1E portions of the following systems and equipment in single-unit and multiunit nuclear power generating stations:
a) Alternating current power systems;
b) Direct current power systems;
c) Instrumentation and control (I&C) power systems.
These systems include the items listed in Table 1.
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2 Normative references
The following documents contain provisions which, through reference in this text, constitute provisions of this standard. For dated reference, subsequent amendments to (excluding any corrigendum), or revisions of, any of these publications do not apply. However, parties to agreements based on this standard are encouraged to investigate the possibility of applying the latest editions of the standards indicated below. For undated references, the latest edition of the document referred to applies.
GB/T 5204 Periodic tests and monitoring of the safety system of nuclear power plant
GB/T 7163 Requirements of reliability analysis for nuclear power plant safety systems
GB/T 9225 General principles of reliability analysis for nuclear power plant safety systems
GB/T 12727 Nuclear power plants—Electrical equipment of the safety system—Qualification (GB/T 12727-2002, IEC 60780:1998, MOD)
GB/T 12790 Method for identification of documents related to safety class 1E equipment and systems for nuclear power plants
GB/T 13177 Preferred power supply for nuclear power plants
GB/T 13284.1 The safety systems for nuclear power plants—Part 1: Design criteria
GB/T 13286 Criteria for independence of class 1E equipment and circuits in nuclear power plants
GB/T 13538 Electrical penetration assemblies in containment structures for nuclear power plants
GB/T 13626 Application of the single failure criterion to safety systems in nuclear power plant
GB/T 13629 Applicable criteria for digital computers in safety systems of nuclear power plants
GB/T 14546 Recommended practice for the design of DC auxiliary power system for nuclear power stations
EJ/T 519 Guide for planning of pre-operational testing programs for Class 1E power systems for nuclear power generating stations
EJ/T 525.1 Batteries for stationary applications—Part 1: Sizing
EJ/T 525.2 Batteries for stationary applications—Part 2: Criteria for installation design and installation
EJ/T 525.4 Batteries for stationary applications—Part 4: Practice for maintenance, testing, and replacement
EJ/T 625-2004 Criteria for diesel-generator units applied as standby power supplies for nuclear power generating stations
EJ/T 639 Criteria for the protection of Class 1E power systems and equipment in nuclear power generating stations
HAF 003 Code on safety in quality assurance for nuclear power generating stations
3 Terms and definitions
For the purposes of this standard, the following terms and definitions apply.
3.1
acceptable
demonstrated to be adequate by the safety analyses of the station
3.2
actuated equipment
assembly of prime movers and driven equipment used to accomplish a protective action
Note: Examples of prime movers are turbines, motors, and solenoids. Examples of driven equipment are pumps and valves.
3.3
actuation device
component or assembly of components that directly controls the motive power (e.g., electricity, compressed air, hydraulic fluid, etc.) for actuated equipment
3.4
administrative controls
rules, orders, instructions, procedures, policies, practices, and designations of authority and responsibility
3.5
auxiliary supporting features
systems or components that provide services (e.g., cooling, lubrication, energy supply) that are required for the safety systems to accomplish their safety functions
Foreword i
1 Scope
2 Normative references
3 Terms and definitions
4 Principal design criteria
5 Supplementary design criteria
6 Surveillance and test requirements
7 Multiunit station considerations
8 Documentation
Criteria for Class 1E power systems for nuclear power generating stations
1 Scope
The purpose of this standard is to provide the following, for nuclear power generating stations:
a) The principal design criteria and the design features of the Class 1E power systems that enable the systems to meet their functional requirements under the conditions produced by the applicable design basis events.
b) The requirements for tests and surveillance of the Class 1E power systems.
c) The criteria for sharing Class 1E power systems in multiunit stations.
d) The requirements for documentation of the Class 1E power systems.
This standard applies to the Class 1E portions of the following systems and equipment in single-unit and multiunit nuclear power generating stations:
a) Alternating current power systems;
b) Direct current power systems;
c) Instrumentation and control (I&C) power systems.
These systems include the items listed in Table 1.
.... ...
.... ....
2 Normative references
The following documents contain provisions which, through reference in this text, constitute provisions of this standard. For dated reference, subsequent amendments to (excluding any corrigendum), or revisions of, any of these publications do not apply. However, parties to agreements based on this standard are encouraged to investigate the possibility of applying the latest editions of the standards indicated below. For undated references, the latest edition of the document referred to applies.
GB/T 5204 Periodic tests and monitoring of the safety system of nuclear power plant
GB/T 7163 Requirements of reliability analysis for nuclear power plant safety systems
GB/T 9225 General principles of reliability analysis for nuclear power plant safety systems
GB/T 12727 Nuclear power plants—Electrical equipment of the safety system—Qualification (GB/T 12727-2002, IEC 60780:1998, MOD)
GB/T 12790 Method for identification of documents related to safety class 1E equipment and systems for nuclear power plants
GB/T 13177 Preferred power supply for nuclear power plants
GB/T 13284.1 The safety systems for nuclear power plants—Part 1: Design criteria
GB/T 13286 Criteria for independence of class 1E equipment and circuits in nuclear power plants
GB/T 13538 Electrical penetration assemblies in containment structures for nuclear power plants
GB/T 13626 Application of the single failure criterion to safety systems in nuclear power plant
GB/T 13629 Applicable criteria for digital computers in safety systems of nuclear power plants
GB/T 14546 Recommended practice for the design of DC auxiliary power system for nuclear power stations
EJ/T 519 Guide for planning of pre-operational testing programs for Class 1E power systems for nuclear power generating stations
EJ/T 525.1 Batteries for stationary applications—Part 1: Sizing
EJ/T 525.2 Batteries for stationary applications—Part 2: Criteria for installation design and installation
EJ/T 525.4 Batteries for stationary applications—Part 4: Practice for maintenance, testing, and replacement
EJ/T 625-2004 Criteria for diesel-generator units applied as standby power supplies for nuclear power generating stations
EJ/T 639 Criteria for the protection of Class 1E power systems and equipment in nuclear power generating stations
HAF 003 Code on safety in quality assurance for nuclear power generating stations
3 Terms and definitions
For the purposes of this standard, the following terms and definitions apply.
3.1
acceptable
demonstrated to be adequate by the safety analyses of the station
3.2
actuated equipment
assembly of prime movers and driven equipment used to accomplish a protective action
Note: Examples of prime movers are turbines, motors, and solenoids. Examples of driven equipment are pumps and valves.
3.3
actuation device
component or assembly of components that directly controls the motive power (e.g., electricity, compressed air, hydraulic fluid, etc.) for actuated equipment
3.4
administrative controls
rules, orders, instructions, procedures, policies, practices, and designations of authority and responsibility
3.5
auxiliary supporting features
systems or components that provide services (e.g., cooling, lubrication, energy supply) that are required for the safety systems to accomplish their safety functions
Contents of GB/T 12788-2008
Foreword i
1 Scope
2 Normative references
3 Terms and definitions
4 Principal design criteria
5 Supplementary design criteria
6 Surveillance and test requirements
7 Multiunit station considerations
8 Documentation
