GB/T 15761-1995 Active National standards

GB/T 15761-1995 Design and construction rules for nuclear island systems of 2×600MW PWR nuclear power plants

GB/T 15761-1995 Design and construction rules for nuclear island systems of 2×600MW PWR nuclear power plants

Publish Date: 1995-12-08 Implement Date: 1996-10-01 For services related to genuine standard inquiry, procurement, translation, and other related services in China, please Contact Us

Basic Information

Standard Code: GB/T 15761-1995
Standard Type: National standards
Standard Status: Active
is_force_gb: no
CCS Name: Nuclear power plant
ICS Name: Nuclear power stations, safety
Publish Date: 1995-12-08
Implement Date: 1996-10-01
Pages: 100 pages

Development Information

Word Count: 195 Thousand words Pages: 100 pages

Referenced Standards

GB/T 4083-2005 General safety principles of nuclear reactor protection system GB 4792 GB/T 5204-1994 Periodic tests and monitoring of the safety system of nuclear power plant GB/T 5204-2008 Periodic tests and monitoring of the safety system of nuclear power plant GB/T 5204-2021 Periodic surveillance testing of the safety system of nuclear power plant GB/T 5963-1995 Separation criteria for reactor protection system GB 6249-1986 Regulations for environmental rediation protection of nuclear power plant GB 8703 GB 9134-1988 The technical rules about solid radioactive waste processing system for light water reactor plants GB 9135-1988 The technical rules about radioactive waste processing system for light water reactor plants GB 9136-1988 The technical rules about gaseous radioactive waste processing system for light water reactor plants GB 11806-1989 Regulations for the safe transport of radioactive material GB 11806-2004 Regulations for the safe transport of radioactive material GB 11806-2019 Regulations for the safe transport of radioactive material GB/T 12727-2002 Nuclear power plants—Electrical equipment of the safety system—Qualification GB/T 12727-2017 Qualification of safety class electrical equipment for nuclear power plants GB/T 12727-2023 Qualification of electrical equipment important to safety for nuclear power plants GB/T 12788-2000 Criteria for class 1E power systems for nuclear power plants GB/T 12788-2008 Criteria for class 1E power systems for nuclear power generating stations GB/T 12788-2021 Criteria for class 1E power systems for nuclear power plants GB/T 13177-2000 Standard for preferred power supply for nuclear power plants GB/T 13177-2008 Preferred power supply for nuclear power plants GB/T 13538-1992 Electrical penetration assemblies in containment structures for nuclear power plants GB/T 13538-2017 Electrical penetration assemblies in containment structures for nuclear power plants GB/T 13286-2001 Criteria for independence of class IE equipment and circuits in nuclear power plants GB/T 13286-2008 Criteria for independence of class 1E equipment and circuits in nuclear power plants GB/T 13286-2021 Criteria for independence of class 1E equipment and circuits in nuclear power plants EJ/T 314-1988 Safety Criteria for Accident Analysis in Pressurized Water Reactor Nuclear Power Plants EJ/T 318 EJ/T 319 EL/T 320 EJ/T 321 EJ/T 322-1994 Design Guidelines for Reactor Pressure Vessels of Pressurized Water Reactor Nuclear Power Plants EJ/T 323-1998 EJ/T 323-1998 Design criteria for fuel assemblies in pressurized water nuclear power plants EJ/T 324-1988 Design Guidelines for Fuel-Related Components of Pressurized Water Reactor Nuclear Power Plants EJ/T 325-1988 Design Guidelines for Reactor Coolant Systems of Pressurized Water Reactor Nuclear Power Plants EJ/T 327-1988 The design criteria for the spray system of the safety container of a pressurized water nuclear power plant EJ/T 328-1988 Design Guidelines for Residual Heat Discharge Systems of Pressurized Water Reactor Nuclear Power Plants EJ/T 329 EJ/T 330-1998 Design criteria for evacuation of the control room of a pressurized water reactor nuclear power plant EJ/T 331-1992 After a water loss incident, the safety of the fluid system is crucial EJ/T 332-1988 Design Guidelines for Emergency Core Cooling Systems of Pressurized Water Reactor Nuclear Power Plants EJ/T 334 EJ/T 335 EJ/T 336-1988 Guidelines for the Layout of Nuclear Steam Supply Systems in Pressurized Water Reactor Nuclear Power Plants EJ/T 337-1988 Nuclear steam supply system design criteria for pressurized water reactor nuclear power plants with electric heating and insulation EJ/T 339-1988 The design criteria for safety valve and depressurization valve pipes in pressurized water reactor nuclear power plants EJ/T 340-1988 Nuclear steam supply system interface design criteria for pressurized water reactor nuclear power plant with turbine building EJ/T 343-1988 Cooling water system design criteria for pressurized water reactor nuclear power plants related to safety EJ/T 573-1991 Quality Inspection of Safety-Grade Batteries for Nuclear Power Plants EJ/T 625-2004 Criteria for Diesel Generator Sets for Back-up Power Supply in Nuclear Power Plants EJ/T 635-1992 Design Guidelines for Boron Recovery Systems in Pressurized Water Reactor Nuclear Power Plants EJ/T 639-1992 Nuclear power plant safety-level electrical system and equipment protection guidelines EJ/T 640 EJ/T 641 EJ/T 667-1992 The overpressure protection of the low-pressure system connected to the reactor coolant pressure boundary EJ/T 668-1992 Detection system and design criteria for leak detection of reactor coolant pressure boundary in pressurized water reactor nuclear power plant EJ/T 669-2005 EJ/T 669-2005 Design criteria for chemical and volume control systems in pressurized water nuclear power plants EJ/T 670-1992 EJ/T 670-1992 Post Loss of Steam Accident Control of Hydrogen Concentration in the Safety Casks EJ/T 761-1993 Nuclear power plant seismic instrumentation criteria EJ/T 816-1994 The design criteria for the emergency core cooling pit in a pressurized water reactor nuclear power plant EJ/T 834-1994 Design criteria for auxiliary water supply system of pressurized water reactor nuclear power plant HAF0101 HAF0102 HAF0105 HAF0110 HAF0111 HAF0112 HA

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