Assessment reports
Step 4
- Public Report on the Generic Design Assessment of New Reactor Designs. Westinghouse Electric Company LLC AP1000® Nuclear Reactor. ONR Summary Report ONR-GDA-SR-002 Revision 0]
- Cross-cutting Topics Assessment [ONR-GDA-AR-11-016, Revision 0]
- Internal Hazards Assessment [ONR-GDA-AR-11-001, Revision 0]
- Civil Engineering and External Hazards Assessment [ONR-GDA-AR-11-002, Revision 0]
- Probabilistic Safety Analysis Assessment [ONR-GDA-AR-11-003, Revision 0]
- Fault Studies - Design Basis Faults Assessment [ONR-GDA-AR-11-004a, Revision 0]
- Fault Studies - Containment and Severe Accident Assessment [ONR-GDA-AR-11-004b, Revision 0]
- Control and Instrumentation Assessment [ONR-GDA-AR-11-006, Revision 0]
- Electrical Systems Assessment [ONR-GDA-AR-11-007, Revision 0]
- Fuel and Core Design Assessment [ONR-GDA-AR-11-005, Revision 0]
- Reactor Chemistry Assessment [ONR-GDA-AR-11-008, Revision 0]
- Radiological Protection Assessment [ONR-GDA-AR-11-009, Revision 0]
- Mechanical Engineering Assessment [ONR-GDA-AR-11-010, Revision 0]
- Structural Integrity Assessment [ONR-GDA-AR-11-011, Revision 0]
- Human Factors Assessment [ONR-GDA-AR-11-012, Revision 0]
- Management of Safety and Quality Assurance Assessment [ONR-GDA-AR-11-013, Revision 0]
- Radioactive Waste and Decommissioning Assessment [ONR-GDA-AR-11-014, Revision 0]
- Security Assessment [ONR-GDA-AR-11-015, Revision 0]
Step 3
ONR have published a number of reports following Step 3 of the assessment process for new power station designs. Step 3 provides an overall safety and security review and analysis of the proposed reactor designs.
The HSE have published a number of technical assessment reports on the Westinghouse AP1000, following the conclusion of step 3 of the assessment process for new nuclear power station designs (completed in October 2009).
These reports are internal HSE reports that are published on this web site in the interests of openness. They underpin the main assessment reports which have been written for a more general audience.
- Step 3 internal hazards assessment of the Westinghouse AP1000
Safety assessment of the internal hazards, e.g. fire, explosion, flood, dropped loads, pressure part failure, and steam releases within the reactor buildings, including consideration of the adequacy of the identification, prevention and mitigation of hazards.
- Step 3 civil engineering and external hazards assessment of the Westinghouse AP1000
Safety assessment of the integrity of structural components such as steel-framed buildings, concrete structures such as walls and the containment, and the reactor building foundations and their ability to withstand external hazards such as earthquakes, aircraft impacts, extreme weather, etc.
- Step 3 probabilistic safety analysis of the Westinghouse AP1000
Probabilistic Safety Analysis (PSA) is an integrated, structured, logical safety analysis that combines engineering and operational features in a consistent overall framework. It provides an analysis of the overall risk to the public that might result from a range of faults (e.g. equipment failure, human error, or hazards such as fires).
- Step 3 fault studies assessment of the Westinghouse AP1000
Safety assessment of the design basis analysis and fault studies on matters such as reactor core physics, thermal hydraulics, heat transfer and a wide range of other physical phenomena under steady state, transient and fault conditions.
- Step 3 control and instrumentation assessment of the Westinghouse AP1000
Safety assessment of the control systems typically used to operate the plant under normal conditions, and reactor protection systems used to maintain control of the plant if it goes outside normal conditions. This includes assessment of both hardware and software aspects.
- Step 3 electrical systems assessment of the Westinghouse AP1000
Safety assessment of the essential electrical power supply systems under a wide range of transient and fault conditions. This includes consideration of their likely reliability, and the performance of protection devices.
- Step 3 fuel design assessment of the Westinghouse AP1000
Safety assessment of the performance of the reactor fuel under a wide range of reactor and storage conditions.
- Step 3 reactor chemistry assessment of the Westinghouse AP1000
Safety assessment of the chemistry of new nuclear reactors, including the effects of coolant chemistry on pressure boundary integrity, fuel and core component integrity, fuel storage in cooling ponds, radioactive waste generation, and radiological doses to workers.
- Step 3 radiological protection assessment of the Westinghouse AP1000
Safety assessment of the radiation exposure to workers and the public during normal operation, (including outages, maintenance and work such as refuelling). This includes consideration of whether the principles of radiological protection, namely optimisation and limitation, had been applied appropriately.
- Step 3 mechanical engineering assessment of the Westinghouse AP1000
Safety assessment of essential mechanical items important to safety, e.g. pumps, valves, lifting equipment, fuel handling equipment, etc. This includes the layout and routing of mechanical equipment and systems to ensure appropriate maintenance regimes and protection from degradation.
- Step 3 structural integrity assessment of the Westinghouse AP1000
Safety assessment of nuclear safety related structures, e.g. metal pressure vessels, piping, etc, and their supports. This includes an analysis of the selected materials, design, fabrication, in-manufacture examination and testing, etc.
- Step 3 human factors assessment of the Westinghouse AP1000
Safety assessment of the human factors aspects of the new nuclear power stations, focussing on ensuring that the human actions needed to contribute to safety are feasible.
- Step 3 management of safety and quality assurance assessment of the Westinghouse AP1000
Safety assessment of the RP's Quality Assurance and Management of Safety arrangements.
- Step 3 radioactive waste and decommissioning assessment of the Westinghouse AP1000
Safety assessment of the RP's proposals for the safe minimisation, handling, storage and disposal of radioactive waste arising from all parts of the power station, including a review the proposals for decommissioning.
- Step 3 security assessment of the Westinghouse AP1000
Safety assessment of the RP's plans to ensure protection against the theft or sabotage of nuclear materials or associated facilities.
The HSE have published a number of technical assessment reports on the EDF and AREVA UK EPR™ Reactor UK EPR, following the conclusion of step 3 of the assessment process for new nuclear power station designs (completed in October 2009).
These reports are internal HSE reports that are published on this web site in the interests of openness. They underpin the main assessment reports which have been written for a more general audience.
- Step 3 internal hazards assessment of the EDF and AREVA UK EPR™
Safety assessment of the internal hazards, e.g. fire, explosion, flood, dropped loads, pressure part failure, and steam releases within the reactor buildings, including consideration of the adequacy of the identification, prevention and mitigation of hazards.
- Step 3 civil engineering and external hazards assessment of the EDF and AREVA UK EPR™
Safety assessment of the integrity of structural components such as steel-framed buildings, concrete structures such as walls and the containment, and the reactor building foundations and their ability to withstand external hazards such as earthquakes, aircraft impacts, extreme weather, etc.
- Step 3 probabilistic safety analysis of the EDF and AREVA UK EPR™
Probabilistic Safety Analysis (PSA) is an integrated, structured, logical safety analysis that combines engineering and operational features in a consistent overall framework. It provides an analysis of the overall risk to the public that might result from a range of faults (e.g. equipment failure, human error, or hazards such as fires).
- Step 3 fault studies assessment of the EDF and AREVA UK EPR™
Safety assessment of the design basis analysis and fault studies on matters such as reactor core physics, thermal hydraulics, heat transfer and a wide range of other physical phenomena under steady state, transient and fault conditions.
- Step 3 control and instrumentation assessment of the EDF and AREVA UK EPR™
Safety assessment of the control systems typically used to operate the plant under normal conditions, and reactor protection systems used to maintain control of the plant if it goes outside normal conditions. This includes assessment of both hardware and software aspects.
- Step 3 electrical systems assessment of the EDF and AREVA UK EPR™
Safety assessment of the essential electrical power supply systems under a wide range of transient and fault conditions. This includes consideration of their likely reliability, and the performance of protection devices.
- Step 3 fuel design assessment of the EDF and AREVA UK EPR™
Safety assessment of the performance of the reactor fuel under a wide range of reactor and storage conditions.
- Step 3 reactor chemistry assessment of the EDF and AREVA UK EPR™
Safety assessment of the chemistry of new nuclear reactors, including the effects of coolant chemistry on pressure boundary integrity, fuel and core component integrity, fuel storage in cooling ponds, radioactive waste generation, and radiological doses to workers.
- Step 3 radiological protection assessment of the EDF and AREVA UK EPR™
Safety assessment of the radiation exposure to workers and the public during normal operation, (including outages, maintenance and work such as refuelling). This includes consideration of whether the principles of radiological protection, namely optimisation and limitation, had been applied appropriately.
- Step 3 mechanical engineering assessment of the EDF and AREVA UK EPR™
Safety assessment of essential mechanical items important to safety, e.g. pumps, valves, lifting equipment, fuel handling equipment, etc. This includes the layout and routing of mechanical equipment and systems to ensure appropriate maintenance regimes and protection from degradation.
- Step 3 structural integrity assessment of the EDF and AREVA UK EPR™
Safety assessment of nuclear safety related structures, e.g. metal pressure vessels, piping, etc, and their supports. This includes an analysis of the selected materials, design, fabrication, in-manufacture examination and testing, etc.
- Step 3 human factors assessment of the EDF and AREVA UK EPR™
Safety assessment of the human factors aspects of the new nuclear power stations, focussing on ensuring that the human actions needed to contribute to safety are feasible.
- Step 3 management of safety and quality assurance assessment of the EDF and AREVA UK EPR™
Safety assessment of the RP's Quality Assurance and Management of Safety arrangements.
- Step 3 radioactive waste and decommissioning assessment of the EDF and AREVA UK EPR™
Safety assessment of the RP's proposals for the safe minimisation, handling, storage and disposal of radioactive waste arising from all parts of the power station, including a review the proposals for decommissioning.
- Step 3 security assessment of the EDF and AREVA UK EPR™
Safety assessment of the RP's plans to ensure protection against the theft or sabotage of nuclear materials or associated facilities.
The HSE have published their assessment reports on the Westinghouse AP1000 following the conclusion of step 3 of the assessment process for new nuclear power station designs (Completed in October 2009).
The HSE have published their assessment report on the EDF and AREVA UK EPR™ Reactor UK EPR, following the conclusion of step 3 of the assessment process for new nuclear power station designs (Completed in October 2009).
Step 2
The HSE and the Environment Agency have published a number of assessment reports on the EDF and AREVA UK EPR™ Reactor UK EPR and on the Westinghouse AP1000, following the conclusion of the initial stage of the assessment process for new nuclear power station designs (Completed in March 2008)
The HSE and the Environment Agency have published a number of technical assessment reports on the EDF and AREVA UK EPR™ Reactor UK EPR and on the Westinghouse AP1000, following the conclusion of the initial stage of the assessment process for new nuclear power station designs (completed in March 2008).
These reports are internal HSE reports that are published on this web site in the interests of openness. They underpin the main assessment reports which have been written for a more general audience.
HSE report setting out the conclusions of its initial assessment (overview of fundamental acceptability) of the UK EPR nuclear reactor 
Environment Agency summary of findings following its preliminary assessment of the UK EPR nuclear reactor 
Environment Agency statement of findings following its preliminary assessment of the UK EPR nuclear reactor
HSE report setting out the conclusions of its initial assessment (overview of fundamental acceptability) of the AP1000 nuclear reactor 
Environment Agency summary of findings following its preliminary assessment of the AP1000 nuclear reactor
Environment Agency statement of findings following its preliminary assessment of the AP1000 nuclear reactor
