imagination_APR1400

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42 Beyond your imagination_ APR1400 CHAPTER_3 SAFETY 6. Reactor Containment Building Design against Aircraft Impact A design-specific assessment on the effects on nuclear power plant facilities of the impact of a large commercial aircraft and military aircraft is performed in accordance with 10 CFR Part 52. The velocity of a large commercial aircraft and a military aircraft for the aircraft impact assessment can be considered as 150 m/sec and 215 m/sec respectively. Both single and double shell structure concept has application to protect the nuclear power plant facilities from possible aircraft impact. The outer wall is strengthened to ensure safety of the structure in the event of an aircraft impact. Two distinct types of structural failure modes such as local failure and global collapse are evaluated for reactor containment building and spent fuel pool. The local failures are caused by impact of the aircraft engines and are largely independent from the global behavior characteristics of the impacted structure. Three main evaluations such as the local analysis, the global analysis, and the vibration analysis are performed for the design of nuclear power plant facilities against aircraft impact. External fires caused by aircraft impacts are of relatively short duration and will not have a significant impact on systems necessary to provide cooling of fuel in the reactor vessel or spent fuel pool. This assumption is based on an abundance of oxygen available to support combustion of the fuel and a good firefighter access to the fire. However, fire duration according to Standard Review Plan 9.5.1 is conservatively applied to guarantee structural safety. After the September 11th terrorists’ attack, Korea assessed the safety of operating nuclear power plants against aircraft impact and reconfirmed the safety of structures. The evaluation methods applied to APR1400 nuclear power plant, and the structural integrity were also confirmed. In case of APR1400 nuclear power plant, both single and double shell structures were applied to protect the nuclear facilities from aircraft impact, and the safety of each case was assessedwith the evaluation procedure. Deformed Shape (Global Behavior)
Beyond your imagination_ APR1400 43 Aircraft Impact Locations 7. NRC Design Certification Process of APR1400 Design Certification (DC) is the U.S. NRC (Nuclear Regulatory Commission)’s approval of a specific standardized plant design on the basis of 10 CFR 52 which was developed to reduce licensing uncertainty by resolving design issues at an earlier stage. The scope and contents of the application are essentially equivalent to the level of details found in a Final Safety Analysis Report. Starting from the Pre-application Review meeting and the application of DC, DC is acquired through the U.S. NRC's rulemaking process, followed by the staff’s review of the application, which includes the various discussions on safety issues associated with the proposed nuclear power plant design. During this process, the U.S. NRC provides all stakeholders with opportunities to take part in public meetings and rulemaking activities related to design certifications. KEPCO is aspiring to attain opportunities to share our long years of experience and competence in the safe and peaceful use of nuclear energy and to make a significant contribution to meeting the increasing nuclear power demand across the world in the future. To this end, KEPCO is pursuing to acquire design certification from the NRC with the APR1400, which is an optimal design to meet the NRC’s Severe Accident and Safety Goal Policy Statements. KEPCO notified the NRC in March 2009 of its intent to acquire the Design Certification of APR1400. And then, the first NRC-KEPCO Pre-application meeting on the proposed certification was held on November 18, 2009. In the meeting, KEPCO suggested a tentative plan that it would prepare to file for Design Certification of APR1400 in 2011. Accordingly, a series of Pre-application review meetings are expected before the filing to arrange the NRC review schedule. Important design information will also be provided in advance during the process. Although dependent upon the amount of time the NRC requires reviewing DC applications, the NRC review process is expected to take approximately three years. Since the APR1400 has already undergone a rigorous examination by the Korean Institute for Nuclear Safety (KINS) to acquire the construction permit for the first APR1400 units (SKN 3&4), we are convinced that it wold acquire the NRC DC in 2013 with less time and resources than the precedents. Pre-application Review Meetion Topical Report Submission DC Application Technical Report Submission NRC Staff Review ACRS Review Meetiong DC Rulemaking ACRS:Advisory Committee on Reactor Safeguard
Page 1 and 2: www.kepco.co.kr Beyond your imagina
Page 3 and 4: Clearer than your Anticipation CHAP
Page 5 and 6: APR1400 Design Features General Pla
Page 7 and 8: KEPCO and APR 1400 chosen by the UA
Page 9 and 10: History of Korean Nuclear Technolog
Page 11 and 12: Beyond your imagination_ APR1400 07
Page 13 and 14: Building and Structure Primary Syst
Page 29 and 30: APR1400 Advanced Power Reactor 1400
Page 39 and 40: Safety Goal and Design Philosophy S
Page 45: Beyond your imagination_ APR1400 41
Page 49 and 50: Safety Injection Performance Test f
Page 55 and 56: Vitrification of Low and Intermedia
Page 59 and 60: Reactor Containment Building Work M
Page 67 and 68: Improvement for In-Service Inspecti
Page 73 and 74: CORE DESIGN, FUEL DESIGN & FABRICAT
Page 75: You need more copies? Any questions

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