| SSR-2/1 Req.4 | The plant design shall provide three fundamental safety functions: control of reactivity; removal of heat from the core and coolant; and confinement and control of radioactive material. | 2.0 (Rev.1/2016) | In force | IAEA SSR-2/1 (Safety of Nuclear Power Plants: Design) |
| SSR-2/1 Req.7 | The plant design shall apply defence in depth with independent levels of protection: prevention of abnormal operation, detection and control, accident control, confinement, and mitigation of off-site consequences. | 2.0 (Rev.1/2016) | In force | IAEA SSR-2/1 (Safety of Nuclear Power Plants: Design) |
| SSR-2/1 Req.14 | A design basis shall be established for every item important to safety, based on analysis of potential initiating events, system failures and external hazards. | 2.0 (Rev.1/2016) | In force | IAEA SSR-2/1 (Safety of Nuclear Power Plants: Design) |
| SSR-2/1 Req.16 | All foreseeable initiating events, including normal operations, shall be identified and analysed, addressing internal hazards such as fire and explosion and external hazards such as earthquakes and flooding. | 2.0 (Rev.1/2016) | In force | IAEA SSR-2/1 (Safety of Nuclear Power Plants: Design) |
| SSR-2/1 Req.25 | Systems important to safety shall meet the single-failure criterion for design-basis accidents: any one independent failure of an active system shall not prevent the safety function from being fulfilled. | 2.0 (Rev.1/2016) | In force | IAEA SSR-2/1 (Safety of Nuclear Power Plants: Design) |
| SSR-2/1 Req.46 | The reactor shall have at least two independent shutdown systems, each capable of sufficient reactivity reduction; for VVER reactors, these include control rods and boric acid in the coolant. | 2.0 (Rev.1/2016) | In force | IAEA SSR-2/1 (Safety of Nuclear Power Plants: Design) |
| SSR-2/1 Req.47 | The coolant system shall be designed to the specified engineering codes (ASME BPVC, PNAE G-7), accounting for pressure, temperature and all specified operating conditions throughout its service life. | 2.0 (Rev.1/2016) | In force | IAEA SSR-2/1 (Safety of Nuclear Power Plants: Design) |
| SSR-2/1 Req.54 | The containment system shall be designed to confine radioactive material, control pressure and temperature, and prevent or minimize radioactive releases in all design-basis accidents. | 2.0 (Rev.1/2016) | In force | IAEA SSR-2/1 (Safety of Nuclear Power Plants: Design) |
| SSR-2/1 Req.68 | The emergency power supply shall be independent of the external grid and provide sufficient stored energy and diesel generation to support all safety functions following a complete loss of off-site power. | 2.0 (Rev.1/2016) | In force | IAEA SSR-2/1 (Safety of Nuclear Power Plants: Design) |
| SSR-2/2 Req.8 | During plant operation, the operator shall maintain all physical barriers, periodically inspect and test systems important to safety, and update operating procedures. | 2.0 (Rev.1/2016) | In force | IAEA SSR-2/2 (Safety of Nuclear Power Plants: Commissioning and Operation) |