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Egypt Research and Nuclear Power Reactors Design Safety Approach Nuclear and Radiological Regulatory Authority Egypt - ENRRA Egypt Research and Nuclear Power Reactors Design Safety Approach Technical Meeting on the Evaluation of Nuclear Power plant Design Safety In the Aftermath of the Fukushima Daiichi Accident 26-29 August 2013 Vienna, Austria EL-MESSIRY Ahmed Egypt Nuclear and Radiological Regulatory Authority ENRRA [email protected] 29 August 2013 1 Nuclear and Radiological Regulatory Authority Egypt - ENRRA AUTHER RESUME B.Sc., M.SC., Ph. D. in Nuclear Engineering, Prof. of nuclear installation safety, Board Member of Egypt Nuclear and Radiological Regulatory Authority ,(2012- now), Sharing in editing Egypt nuclear law and its executive regulation, Member of Review & Assessment of nuclear installations committee, and Nuclear installation Operators licensing committees, Reactor operator of Egypt Test and Research Reactor # 1, (1969-1982). 29 August 2013 2 Nuclear and Radiological PAPER OUTLINE: Regulatory Authority Egypt - ENRRA 1- INTRODUCTION 2- EGYPT NUCLEAR SAFETY APPROACH OF NUCLEAR REACTORS 3- GENERAL DESIGN SAFETY ASPECTS OF NUCLEAR REACTORS 4-FUKUSHIMA ACCIDENT ANALYSES 5- DIFFERENT IMPOVMENTS IN PLANT SYSTEM AS A RESULT OF FUKUSHIMA ACCIDENT 6- FEEDBACK OF FUKUSHIMA ACCIDENT ON SAFETY OF NUCLEAR REACTORS IN EGYPT 29 August 2013 3 Nuclear and Radiological 1. INTRODUCTION Regulatory Authority Egypt - ENRRA The main articles relating to the nuclear platform (infrastructures) of Egypt are: 1.1 Nuclear Organizations, 1.2 Regulatory Body, 1.3 Nuclear power program, 1.4 Nuclear reactors, 1.5 Regulation used in licensing nuclear reactors. 29 August 2013 4 Nuclear and Radiological 1. INTRODUCTION Regulatory Authority Egypt - ENRRA 1.1. Nuclear Organizations in Egypt i. Atomic Energy Authority AEA (Operates two research reactors), ii. Nuclear Power Plant Authority NPPA (Responsible for establishing nuclear power program), iii. Nuclear Material Authority NMA (milling and mining of nuclear materials), iv. Nuclear and Radiological Regulatory Authority NRRA ( Regulate all nuclear and radiation facilities and activities inside the country). 29 August 2013 5 Nuclear and Radiological 1. INTRODUCTION Regulatory Authority Egypt - ENRRA 1.2. Regulatory Body o In 1983, a national center for nuclear safety and radiation control NC-NSRC was established under the umbrella of EAEA – ministry of electricity, it worked under the law 59 of year 1960, hence it was dependent, o In March 2010, A new nuclear law 7 of year 2010 was issued, it replaced the law 59 of year 1960, it stated a necessity of establishing independent regulatory body, o in November 2011, an executive regulation of the nuclear law 7 of year 2010 was issued, o On 5/3/2012, an independent regulatory body was established which replaced the old NC-NSRC, it had the name ENRRA, it reported directly to the prime minister, 29 August 2013 6 Nuclear and Radiological 1. INTRODUCTION Regulatory Authority Egypt - ENRRA 1.3. Nuclear power program o In 1979, Egypt planned a nuclear power program, of 4 nuclear power plant, each of two units, o In 1980, NPPA was established to take over the program, o In 1986, the plan stopped due to Chernobyl accident, o In 2008 the program reinitiated and the site was selected on the seashore of Middetrainian sea, west of Alexandria city, o In 2009, ENRRA submitted a site design requirements and environmental impact assessment report contents to NPPA, which in turn sent the site safety analysis report, it reviewed and assessed, 29 August 2013 7 Nuclear and Radiological 1. INTRODUCTION Regulatory Authority Egypt - ENRRA 1.3. Nuclear power program o In 2011, and due to Fukushima accident, the site design requirements were modified to cope with the resistance of the plant to high earthquakes and flooding , o In 2012 and due to Fukushima accident, safety design requirements of the plant were modified and sent to NPPA, it included addition of a portable emergency power supply, hydrogen re-combination, and cooling water tanks. o In 2012 NPPA prepared a plant technical specifications with the new modification for international bid , o The proposed plant will compose of two units of light water pressurized reactors PWR, with electric power output in the range 1200 : 1600 MWe for each unit , 29 August 2013 8 Nuclear and Radiological 1. INTRODUCTION Regulatory Authority Egypt - ENRRA 1.4. Nuclear reactors EAEA operates two Reactors: i- Egypt Test and Research Reactor #2 ,ETRR#2, This an MPR used for: Isotopes production Mo, TC, Ir, I, Cr, Co 60 production, Neutron activation analysis, Radiotherapy by thermal neutron capture, Material irradiation, Research, o It was built By Argentina, went critical on 1997, o 22 Mw, 20% U235 enrichment, plate type fuel , water cooled and moderated, Beryllium reflector, o Two safety shutdown system, o Open pool type. 29 August 2013 9 Nuclear and Radiological 1. INTRODUCTION Regulatory Authority Egypt - ENRRA 1.4. Nuclear reactors ii- Egypt Test and Research Reactor # 1, ETRR#1, This an Russian type reactor used for: Neutron irradiations, Radioisotope production, Research, o It is an turn key project, went critical on 1963, o 2 Mw, 10% U235 enrichment, rod type fuel , water cooled and moderated, Graphite reflector o One safety shutdown system, o Closed tank type. 29 August 2013 10 Nuclear and Radiological 1. INTRODUCTION Regulatory Authority Egypt - ENRRA 1.5. Regulation used in licensing nuclear reactors Due to the incomplete national regulatory documents framework, ENRRA do review and assessment and licensing of nuclear reactors as follows: A- For power plant we used: i. Up to date versions of IAEA standards as SF-1, GSR part 1 : 6, SSR 2-1 , SSR-2-2, GS-R-3, SSG-2, SSG-12, SSG-16, SSG-22, SSG-25, INSAG series No 10,12, 16,17, 22, 46, ii. US-NRC standards as NUREG 1.7, iii. National regulations. 29 August 2013 11 Nuclear and Radiological 1. INTRODUCTION Regulatory Authority Egypt - ENRRA 1.5. Regulation used in licensing nuclear reactors B- For Research Reactors we used: i. IAEA safety standards as safety series SS- 35 S1,S2, G1, G2 , Service series 1 and 2 , INSAG 3 and recently NS-R-4 with its guides NS-G-4.1:4.6, SSG-20, ii. International standards as US-NRC regulatory guides NUREG 1537 I and II, iii. The vendor country standards (Argentina), iv. Egyptian regulations. 29 August 2013 12 2. EGYPT NUCLEAR Nuclear and radiological SAFETY APPROACH OF Regulatory Authority NUCLEAR REACTORS Egypt - ENRRA 2.1. Safety Fundamentals and principles Safety fundamentals Objectives Principles General specific Management Strategy of Defense in Technical depth 29 August 2013 13 2- EGYPT NUCLEAR Nuclear and radiological SAFETY APPROACH OF Regulatory Authority NUCLEAR REACTORS Egypt - ENRRA 2.2. Methodology The review and assessment R&A Methodology follows basically the concept of defense in depth and placing most emphasis on accident prevention, Safety analysis remains an important part in R&A, it basically follow a deterministic approach with support of probabilistic analysis, Many unexpected accident with very low probabilities should be analyzed, International cooperation should be considered, especially in technology transfer in all aspects of nuclear safety. 29 August 2013 14 2- EGYPT NUCLEAR Nuclear and Radiological SAFETY APPROACH OF Regulatory Authority NUCLEAR REACTORS Egypt - ENRRA 2.3. Principles The main principle is strategy of Defence in Depth Multiple levels of protection is the central feature of defence in depth. This principle states " "To compensate for potential human and mechanical failures, a defence in depth concept is implemented, centered on several levels of protection including successive barriers preventing the release of radioactive material to the environment. The concept includes protection of barriers by averting damage to the plant and to the barriers themselves. It includes further measures to protect the public and the environment from harm in case these barriers are not fully effective". 29 August 2013 15 2- EGYPT NUCLEAR Nuclear and Radiological SAFETY APPROACH OF Regulatory Authority NUCLEAR REACTORS Egypt - ENRRA 2.4. Adopted Rules in safety assessment (a) The effect of single, random failures; (b) System qualification (or lack of qualification) under accident conditions; (c) Safety and protection systems, including reliability in quantitative terms; (d) Support systems, such as normal and emergency electric power and the cooling water; (e) Redundant trip parameters; (f) Actions of systems that are independent; (g) Operator action (e.g. response time, display of information on a console); and (h) Carrying out of frequency or probability evaluations to assess the system response, 29 August 2013 16 3. GENERAL DESIGN Nuclear and Radiological SAFETY ASEPCTS OF Regulatory Authority NUCLEAR REACTORS Egypt - ENRRA 3.1. Passive Nuclear Safety It does not require operator actions in order to carry out its safety function, IAEA classifies the degree of "passive safety" of components from category A to D depending on what the system does not make use of: no moving working fluid, no moving mechanical part, no signal inputs of 'intelligence‘, no external power input or forces. 29 August 2013 17 3. GENERAL DESIGN Nuclear and Radiological SAFETY ASEPCTS OF Regulatory Authority NUCLEAR REACTORS Egypt - ENRRA 3.1. Passive Nuclear Safety Example of a safety system with 'passively safe' components are: The concrete walls and the steel liner of the containment, The fuel cladding, The surge line which connects the hot leg with the pressurizer, The accumulator,
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