Implementation of the Rules for the Continued Operation in Korea

Transcription

1 Implementation of the Rules for the Continued Operation in Korea Presented by Jong-Jooh Jooh Kwon

2 Contents I. Dynamic and Innovative Nuclear Energy Activities in Korea II. Process Implementing requirements of the Rules for the Continued Operation

3 Korea Advances towards a New Era of Nuclear Energy Korea has made considerable advances in Nuclear Energy in just half a century Nuclear Energy has enhanced the growth of Korea s national economy, especially during the recent oil price hikes Nuclear Energy is being highlighted as an Environmentally- Friendly energy resources Nuclear energy development is strongly supported by the policies of the Korean government Korea contributes to sustainable development of the global society through its international cooperation activities Source : MoST of ROK

4 Nuclear Policy Basic Directio n Goals 1. Promoting peaceful uses of nuclear energy 2. Securing nuclear safety 3. Enhancing nuclear transparency 1. To provide a stable electricity supply through the development of nuclear energy as the primary source of electricity generation 2. To achieve technological self-reliance in nuclear reactor fuel cycle development 3. To make the nuclear industry one of the major export industries through the participation of the private sector, and by actively promoting the development of commercial nuclear technology 4. To expand the application of nuclear technology to medical, agricultural, and industrial areas Source : MoST of ROK

5 Nuclear Research and Development KEPRI, Plug-in the Future Korea s investment in nuclear R&D 2006 was approximately 206 million U.S. dollars Source : MoST of ROK

6 Nuclear Power Generation Korea is continuously and systematically promoting R&D on nuclear power generation Source : MoST of ROK

7 Nuclear power is the most important energy source in Korea Hydro, 5485, 9% Oil, 4790, 7% Nuclear, 17716, 28% Hydro, 5219, Gas, 69,095, Oil, 14607, 4% 1% 18% Nuclear, 148,749, 40% Gas, 17,436, 27% Coal, 18,465, 29% Coal, 140,346, 37% Installed capacity : 65,514 MW Electricity generation : 3,465 GW

8 Korea is proud of its world class operational performance Source : MoST of ROK

9 Nuclear Safety Regulation Five principles of the nuclear safety regulation 1. Independence 2. Openness 3. Clarity 4. Efficiency 5. Reliability Philosophy of a nuclear safety culture 1. To maintain the highest level of safety 2. To open safety information to the public 3. To promote research on safety and technology development 4. To abide by the international treaties and to expand international cooperation 5. To reinforce the safety related laws and systems 6. To promote a safety culture 7. To induce the general public to participate in the establishment of a safety policy 8. To secure the independence and justification of the regulation

10 Service Life of Korean NPPs as of 2007 KEPRI, Plug-in the Future

11 Regulatory Frame of the Continued Operation Physical condition Safety analysis Equipment qualification Safety Performance Use of operation experience & research results Aging effect O&M procedure Organization & administration Emergency plan Radiation management AMR & AMP for the SSCs within the scope of the CO Added TLAA & radiation environmental impact to PSR Expiration of Design Lifetime PSR PSR Intensified PSR Integrated Field Inspection

12 The Legal System of the Continued Operation Principles Maintaining the CLB during the continued operation Maintaining top level of safety even in the light of international al technical standards Atomic Energy Act. Enforcement Decree Enforcement Regulation. MoST Bulletins. Art 23 state subjects on concerning an implementation of PSR Art 42 state subjects on concerning the time of submission, contents, methods and basis of PSR, and also additions Art 19 state subjects on details of safety factors and technical basis of PSR MoST Bulletins state guidelines on concerning application of the technical basis for continued operation

13 Implementation Process of the Continued Operation PSR AM TLAA Environment Identify PSR safety factors Verify the methods to identify SSC Methods to verify adequacy of AMP Use of operating experiences and latest research findings Identify TLAA Identify methods to evaluate TLAA Identify parameters to be evaluated Perform evaluation of safety factors Perform aging management review Evaluate TLAA Perform radiation environmental impact analysis PSR report with AM review List of SSC, AMP, TLAA & radiation impact report CLB changes affecting the CO Up-dated FSAR Tech. spec. changes

14 Periodic Safety Review 11 safety factors KEPRI, Plug-in the Future Actual physical conditions of reactor facilities at the time of the review, EQ, AMR, safety analysis, safety performance, operating experiences es from other plants and research findings, procedures for O&M, organization n and administration, emergency plan and radiation management Key parameters to assess for the continued operation Actual physical condition : test results to verify function, inspection and maintenance records, current physical condition of SSC, support facilities within and without plant that could be used for operation of nuclear facilities Equipment qualification : the list of equipments and administrative tive procedures included in EQ program, methods and QA, trouble of equipments affected on EQ and corrective action to maintain EQ, protection of equipments ents from environment condition, physical condition and functionality of the qualified equipments, EQ records of the equipment in service duration Aging review : scoping and screening SSC within the scope of AMR, identifying aging mechanism and analysis of effects on degradation, functionality and safety margin, a prediction of future condition, mitigation and AMP

15 Scoping and Screening of SSC within the Scope of AMR All SSCs Review of SSC Function YES Is the SSC Q class? NO Is the SSC relied on to demonstrate compliance with certain NRC regulations? NO YES Is the components considered passive? YES NO Active Components Is the SSC T class? YES NO SSC not within CO Is the component subject to replacement based on qualified life or specified time period? NO YES Go to active components management SSCs within the scope of CO and the associated intended functions are identified List the structures, components, commodity groups that require AMR

16 Aging Management Programs Purpose Ensure that identified aging effects can be managed easily and efficiently during the continued operation Types of AMP Prevention, mitigation, condition monitoring, performance monitoring Evaluating process Identify AMP List of the plant and prepare programs considering 10 attributes, that is scope of the program etc. Review ISI and maintenance procedures etc. of the plant in order r to determine appropriateness of existing procedures If those procedures are not proper, enhanced or new procedures should be developed

17 Time Limited Aging Analysis Identifying TLAA of the plant verify the items of TLAA deriving from FSAR and other documents related with current codes and standards correspond to following six selection criteria - Long lived passive SSC - Aging effects - Assumptions limited to the current license period - Items decided by the power generating reactor to be relevant to judging safety issues - Results and basis of analysis that are related to the performance of intended functions of long-lived lived passive SSC - Items referred to or used in current codes and standards

18 Acceptance criteria KEPRI, Plug-in the Future TLAA should be evaluated to satisfy one of the following three criteria - A : The analysis remain valid for the period of continued operation - B : The analysis have been projected to the end of the period of continued operation - C : The effects of aging on intended functions will be adequately managed for the period of continued operation Examples subject to TLAA Reactor vessel embrittlement irradiated by neutron Metal fatigue Environmental qualification Concrete containment tendon pre-stress Containment liner plate, steel containment vessel, and penetration fatigue Other plant-specifics

19 Radiation Environmental Impact Evaluation Purpose To present attachment for application of continued operation Technical standards Follow recent licensing basis Considerations Input data, collection of meteorogical data, radiological environmental impact due to normal operation, DBA, and continued operation related radiological features of plant operation Public opinion feedback or public hearing Not required

20 Concluding Remarks 1. Basically, regulatory frame of the continued operation is an extension of PSR 2. Through the first application of the continued operation in Korea, we learned that PSR is very useful tool for the continued operation 3. The requirement of the rules for implementing the continued operation have become more intensified than that of either LR in the U.S. or LTO in Europe 4. It is recommended that process, methods, and scope of the continued operation in Korea could be appropriate approaches to other countries