Equipment Requirements Verification
Requirements: 26 of 26·Verification records: 8
| Action | ||||
|---|---|---|---|---|
| 1.2.4-OPB-001-15 | Nuclear plant safety shall be ensured through defence in depth, using a system of physical barriers and engineered measures to protect them.NP-001-15 (General Safety Provisions for Nuclear Power Plants) | 1.0 (15) | Codes & Standards | |
| 1.2.5-OPB-001-15 | All physical barriers shall remain functional during normal operation. If any barrier is found to be impaired, the reactor plant shall be shut down and measures taken to bring the unit to a safe state.NP-001-15 (General Safety Provisions for Nuclear Power Plants) | 1.0 (15) | Codes & Standards | |
| 1.2.6-OPB-001-15 | The plant design shall justify the limits and conditions for safe operation and provide engineered and organizational measures to prevent their violation.NP-001-15 (General Safety Provisions for Nuclear Power Plants) | 1.0 (15) | Codes & Standards | |
| 1.2.9-OPB-001-15 | The plant Safety Analysis Report shall include deterministic and probabilistic safety analyses for all operating states, including an assessment of the probability of a large accidental release.NP-001-15 (General Safety Provisions for Nuclear Power Plants) | 1.0 (15) | Codes & Standards | |
| 1.2.11-OPB-001-15 | The plant design shall provide engineered and organizational measures to prevent accidents and limit their consequences, including beyond-design-basis accident management.NP-001-15 (General Safety Provisions for Nuclear Power Plants) | 1.0 (15) | Codes & Standards | |
| 1.2.12-OPB-001-15 | Limits established for design-basis accidents shall not be exceeded for postulated initiating events with the single-failure criterion applied (any one independent failure).NP-001-15 (General Safety Provisions for Nuclear Power Plants) | 1.0 (15) | Codes & Standards | |
| 3.1-SP-13.13130 | The nuclear plant shall meet fire safety requirements: radiological consequences of a fire shall remain within established limits and personnel shall be protected.SP 13.13130.2009 (Nuclear Power Plant Fire Safety Requirements) | 1.0 (2009) | Codes & Standards | |
| 3.2-SP-13.13130 | A set of organizational and engineered fire safety measures shall be developed for the plant, including protection of systems important to safety against fire hazards.SP 13.13130.2009 (Nuclear Power Plant Fire Safety Requirements) | 1.0 (2009) | Codes & Standards | |
| 3.3-SP-13.13130 | Fire safety measures shall provide safety system redundancy, separation of trains by fire barriers, and prevention of fire spread and dispersion of radioactive material.SP 13.13130.2009 (Nuclear Power Plant Fire Safety Requirements) | 1.0 (2009) | Codes & Standards | |
| 1.7.4-NP-006-98 | The plant fire safety concept shall be presented in the Safety Analysis Report, including principles and criteria for fire prevention and protection against fire consequences.NP-006-98 (Safety Analysis Report Requirements for VVER Nuclear Power Plants) | 2.0 (98) | Codes & Standards | |
| 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.IAEA SSR-2/1 (Safety of Nuclear Power Plants: Design) | 2.0 (Rev.1/2016) | IAEA | |
| 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.IAEA SSR-2/1 (Safety of Nuclear Power Plants: Design) | 2.0 (Rev.1/2016) | IAEA | |
| 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.IAEA SSR-2/1 (Safety of Nuclear Power Plants: Design) | 2.0 (Rev.1/2016) | IAEA | |
| 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.IAEA SSR-2/1 (Safety of Nuclear Power Plants: Design) | 2.0 (Rev.1/2016) | IAEA | |
| 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.IAEA SSR-2/1 (Safety of Nuclear Power Plants: Design) | 2.0 (Rev.1/2016) | IAEA | |
| 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.IAEA SSR-2/1 (Safety of Nuclear Power Plants: Design) | 2.0 (Rev.1/2016) | IAEA | |
| 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.IAEA SSR-2/1 (Safety of Nuclear Power Plants: Design) | 2.0 (Rev.1/2016) | IAEA | |
| 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.IAEA SSR-2/1 (Safety of Nuclear Power Plants: Design) | 2.0 (Rev.1/2016) | IAEA | |
| 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.IAEA SSR-2/1 (Safety of Nuclear Power Plants: Design) | 2.0 (Rev.1/2016) | IAEA | |
| 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.IAEA SSR-2/2 (Safety of Nuclear Power Plants: Commissioning and Operation) | 2.0 (Rev.1/2016) | IAEA | |
| EPC-REQ-001 | Guaranteed net electrical output shall be at least 1,170 MW at the specified cooling water temperature of +15°C.EPC Contract · Schedule 1 (Performance Guarantees) | 1.0 (Contract) | Contract | |
| EPC-REQ-002 | Unit capacity factor shall be at least 90% throughout the two-year warranty period.EPC Contract · Schedule 1 (Performance Guarantees) | 1.0 (Contract) | Contract | |
| EPC-REQ-003 | The design service life of major non-replaceable equipment (reactor pressure vessel, steam generators and pressurizer) shall be at least 60 years.EPC Contract · Schedule 2 (Critical Equipment Specification) | 1.0 (Contract) | Contract | |
| EPC-REQ-004 | Provide the complete construction and acceptance documentation electronically in the engineering information system, with verified links to the 3D model, before commissioning begins.EPC Contract · Schedule 4 (Information Model and Engineering Information Management Requirements) | 2.0 (Contract) | Contract | |
| EPC-REQ-005 | Perform receiving inspection on all safety class 1, 2 and 3 equipment, issue FA-1 acceptance records and register them in Rebario PLM.EPC Contract · Schedule 6 (Supply Quality Assurance Programme) | 1.0 (Contract) | Contract | |
| EPC-REQ-006 | Meet the contract milestone schedule, including primary circuit hydrostatic testing and initial reactor criticality by the specified dates.EPC Contract · Schedule 7 (Construction Milestone Schedule) | 1.2 (Contract) | Contract |