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INTRODUCTION lessons learned from the Fukushima accident under - PowerPoint PPT Presentation

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INTRODUCTION lessons learned from the Fukushima accident under several areas and topics such as: 1- the seismic design; 2- the tsunami effect; 3- the station blackout effect; 4- the station safety design; 5- loss of ultimate heat sink; 6-

  3. INTRODUCTION lessons learned from the Fukushima accident under several areas and topics such as: 1- the seismic design; 2- the tsunami effect; 3- the station blackout effect; 4- the station safety design; 5- loss of ultimate heat sink; 6- spent fuel storage pools design; 7- regulations and organization/crisis management.

  4. REASSESSMENT OF THE FACILITY  The main objective of this reassessment is to evaluate the robustness of the existing reactor protection, in terms of design features against the impact of extreme events, with an emphasis on fulfillment of the basic safety functions to avoid accidents like that happened in Fukushima.

  5. ETRR-2 ACTONS AFTER FUKUSHIMA ACCIDENT  Review and updating of the safety analysis after in-core irradiation for LEU targets to produce Mo-99.  Ensure that the OLCs are maintained as they approved by the current operating license.  Review the emergency power supply and Uninterrupted Power Supply System (UPS) .  Review of the emergency preparedness and the emergency equipment.  Study the interaction of the reactor associated facilities (ET-RR-2, fuel fabrication plant and Radioisotopes Production Plant).  Review of the operator response to the design basis accidents and radiological emergency.

  6.  Complete loss of all electrical power supply (off-site, on-site and batteries).  Loss of ultimate heat sink .  Review the off-site emergency response including management of severe accident.  External Events (extreme earthquakes, extreme weather conditions craft crash, fire).  Internal Events (internal flooding, fire).  Security events.  Review of the site accessibility.  Existing communications means.  Review the postulated initiating events covered by the safety analysis in SAR and IAEANS-R-4.  Events with experimental devices.  Analysis of the BDBAs and combination of events (extreme earthquake that leads to an internal event such as internal flooding and /or fire, station black out, source term calculations).

  7. REASSESSMENT OF THE SITE Requirements:  Low probability of earthquakes and volcanoes.  Low probability of radiation spread by wind.  Enough distance from accommodations.  Enough distance from seas and oceans. * All the mentioned requirements are verified in ETRR-2

  8. REASSESSMENT OF THE BUILDING Requirements:  Earthquake resistance  Submarine doors  Radiation spread resistance  Air confinement  Emergency doors All the mentioned requirements are verified in ETRR-2, It is recommended to increase the submarine doors for electric components rooms.

  9. REASSESSMENT OF RADIATION PROTECTION  Advanced equipment for all type of radiation  Periodically calibration  Failure detectors for the components that may cause radiation release  High level of training on radiation protection and safety culture There is a variety of radiation protection systems and equipment in ETRR-2. More training is recommended in ETRR-2 to increase the safety culture.

  10. REASSESSMENT OF EMERGENCY PREPAREDNESS AND RESPONSE Requirements:  Repeating the emergency plan training periodically.  Verifying the good communications internally and between the reactor and the different centers and authorities to ensure a good coordination and rapid response in case of emergency.  Good monitoring system.  Manual and automatic fire detection. * All the mentioned requirements are verified in ETRR-2

  11. SAFETY FEATURES Requirements :  Redundancy ( cooling pumps)  Diversity (control rods and Gadolinium)  Fail safe ( control rods – Gadolinium- RPS)  Physical separation ( cooling pumps)  Negative reactivity temperature coefficient

  13. DEFENCE IN DEPTH  Prevention of accident  Protection against accident  Mitigation of radiation consequences * The mentioned philosophy is strongly verified in ETRR-2

  14. SAFETY SYSTEMS IN ETRR-2  First shutdown system.  Second shutdown system.  Chimney water injection system.  Evacuation alarm.

  19. SAFETY FUNCTIONS  Safe shutdown.  Enough cooling for the reactor core.  Mitigation of the radiation consequences. * There is additional control room in ETRR-2. It is used in case of emergency to verify these safety functions.

  20. AVAILABILITY AND SAFETY In spite of the importance of availability, it must be limited to levels that keep the reactor operation in safe mode. This limitation of the availability is very important to avoid the human errors. This principle is very clear in the design of the logic systems of ETRR-2. It makes the reactor operation impossible without verifying all of the safety conditions.

  21. DESIGN BASIS ACCIDENTS The reactor design must take all of the expected accidents and their scenarios into consideration to adopt the principle of defense in depth in the design. In ETRR-2, this principle is very clear and adopted with the higher levels of safety multiple barriers and recovery actions. There is a quick reference emergency guide that can be used by the reactor operation group to verify the safety functions easily and quickly in case of emergency.

  23. DESIGN BASIS ACCIDENTS IN ETRR-2  Loss of offsite power supply accident (LOPS).  Loss of flow accident (LOFA).  Loss of heat sink (LOHS).  Loss of coolant accident from pool (Pool LOCA).  Core loss of coolant accident (Core LOCA).  Fast reactivity insertion.  Low reactivity insertion.  Coolant channel blockage.

  27. Preventive and corrective

  28. CIC (NOISE)

  29. Changing cables and connection

  31. Gadolinium valves

  36. ELECTRIC SYSTEM Requirements: Multiple classes for the electric system: Class A (UPS) Class B (Diesel generators) Class C (External power supply) * All the mentioned requirements are verified in ETRR-2

  37. reassessment recommendations are:  shortage detected such as some area is out of the fire fighter car range (there is no paved road), and evacuation alarm does not work in some areas  Periodic tests for safety and safety related systems.  Ensure training and periodic retraining of the workers.  Periodic emergency drills must be done and detecting the shortage and malfunctions in the emergency plan, equipment, communications and personal.  Power of diesel generators should be increase from 500 K.W to 600 K.W to include the feeding of fire pumps in case of loss of site power supply.  Pay attention to preventive maintenance for the safety systems and related equipments according to maintenance plan.

  39. CONCLUSION The reassessment of ETRR-2 shows that all of the basic safety functions are fulfilled during the extreme events.

  40. Thank you

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