Performance of Equipment Qualification Safety Factor of Periodic Safety Review for Qinshan III CANDU NPP

2014 ◽  
Author(s):  
Shen Xiaoyao
Keyword(s):  
Safety Factor ◽  
Nuclear Power ◽  
Power Plants ◽  
Phase Iii ◽  
Safety Review ◽  
Plant Safety ◽  
Number Of Factors ◽  
Commercial Operation ◽  
Periodic Safety ◽  
Equipment Qualification

Qinshan phase III is the only CANDU nuclear power plant (NPP) in China, which has two 728MW units, and starts commercial operation on Dec. 31st, 2002 and July 24th, 2003 respectively. According to the Periodic Safety Review of Nuclear Power Plants (NS-G-2.10) issued by IAEA in 2003 and the corresponding Chinese edition HAD103/11 issued by NNSA in 2006, the first PSR of Qinshan III should be carried out in 2012 and 2013 after 10 years of commercial operation. Comprehensive assessment of plant safety is a complex task and is facilitated by dividing it into a number of factors. The equipment qualification (EQ) factor is an important one of them. In this paper, the equipment qualification safety factor review of PSR is carried out for Qinshan III. Firstly, the project background is described. Then objectives, scopes and main review elements of EQ factor review are summarized. Also, the EQ factor review process is emphasized. Finally, the project team and outcome of EQ factor review are given.

Development of “Proactive Safety Review Guideline for Continuous Improvement on Nuclear Power Plants”

2016 ◽  
Author(s):  
Yoshiyuki Narumiya ◽  
Koji Okamoto ◽  
Shingo Ueno ◽  
Kentaro Hayashi ◽  
Takahiro Kuramoto
Keyword(s):  
Continuous Improvement ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Technical Committee ◽  
Periodic Review ◽  
Safety Review ◽  
Safety Improvement ◽  
Periodic Safety ◽  
Proactive Safety

The Atomic Energy Society of Japan (AESJ) has established and issued the “Proactive Safety Review (PSR+) Guideline for Continuous Improvement on Nuclear Power Plants: 2015” 1) through the discussion at the Periodic Safety Review Subcommittee under the System Safety Technical Committee of the AESJ Standards Committee (SC), and then approved by the both committees. This guideline defines the review concept, perspectives, and methodologies, relating to identifying areas of safety improvement when the licensees implement periodic review for continuous improvement of safety of their nuclear power plants, so called “Proactive Safety Review (PSR+). This paper discusses the details of this newly established standard, including the concept, perspectives, and methodologies, relating to identifying areas of safety improvement. In addition, specific examples of applying this standard and the policy of utilizing this standard in continuously improving the safety of all the nuclear power plants in Japan are also described.

scholarly journals CURRENT STATUS AND PROSPECT FOR PERIODIC SAFETY REVIEW OF AGING NUCLEAR POWER PLANTS IN KOREA

2009 ◽  
Vol 41 (4) ◽  
pp. 545-548
Author(s):  
Tae-Eun Jin ◽  
Heui-Young Roh ◽  
Tae-Ryong Kim ◽  
Young-Sheop Park
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Current Status ◽  
Safety Review ◽  
Periodic Safety

scholarly journals Fracture Analysis and Fatigue Strength Calculation of Anchor Bolt Used in Circulating Water Pump in Nuclear Power Plant

Scanning ◽  
2021 ◽  
Vol 2021 ◽  
pp. 1-8
Author(s):  
Qiang Chen ◽  
Shuai Zu ◽  
Yinhui Che ◽  
Dongxiong Feng ◽  
Yang Li
Keyword(s):  
Fatigue Strength ◽  
Tensile Stress ◽  
Safety Factor ◽  
Nuclear Power ◽  
Power Plants ◽  
Fracture Analysis ◽  
Water Pump ◽  
Axial Vibration ◽  
Circulating Water ◽  
Tool Marks

A circulating water pump is a key equipment of cooling systems in nuclear power plants. Several anchor bolts were broken at the inlet rings of the same type of pumps. The bolts were turned by a special material for seawater corrosion protection. There were obvious turning tool marks at the root of the thread, which was considered as the source of the crack. The fatigue crack extended to the depth of the bolt, causing obvious radiation stripes on the fracture surface, which was a typical fatigue fracture. Obvious overtightening characteristics were found at the head of the broken bolt. Fracture and energy spectrum analysis showed that the bolt was not corroded. The axial vibration of the pump was measured. The static tensile stress along the bolt axis caused by the preload, the axial tensile stress caused by the axial vibration, and the torsional stress were calculated, respectively. According to the fatigue strength theory, the composite safety factor of the bolt fatigue strength was 1.37 when overtightening at 1.2 times the design torque, which was less than the allowable safety factor of 1.5-1.8, so the bolt was not safe, which further verified the conclusion of fracture analysis. The reason for the low safety factor was caused by the overtightening force. The improvement method was to control the bolt preload or increasing the bolt diameter.

Explore the Self-Governance on Nuclear Safety Emergency - A Case Study of the 3rd Nuclear Power Plant

2012 ◽  
Vol 260-261 ◽  
pp. 103-106
Author(s):  
Yi Chun Lin ◽  
Yung Nane Yang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Alternative Energy ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Nuclear Safety ◽  
Security Issue ◽  
Safety Issues ◽  
Plant Safety

The ripples of the tsunami crisis in Japan triggered introspections of nuclear plant safety issues in the worldwide. Many countries have claimed the suspension of nuclear power plants. However, some countries such as Taiwan, under nearly 99% energy is exported, the disasters force government and citizen to face the importance of nuclear safety, especially the neighborhoods nearby the nuclear power plants. We have to face the nuclear safety since there is no other alternative energy presently. The 3rd nuclear power plant located in the south of Taiwan, which has the same geographic features with Fukushima, Japan. Presently, there is no precedent in Taiwan of precaution and rescue team and civil supervised mechanic on nuclear security issue. This paper will review according to transparent information, public participation and cross-organization cooperation to propose the execution and work division principles, including information monitor, educational propagation, hide and evacuation, emergence aid and care, rear and refuge service. The ultimate target is to establish self-governance inside nearby neighborhood to confront nuclear disaster at the critical moment.

Impact of Climate Change on EDF’s Nuclear Facilities: Climate Watch Approach

2020 ◽  
Author(s):  
L. Guinard ◽  
S. Parey ◽  
H. Cordier ◽  
L. Grammosenis
Keyword(s):  
Climate Change ◽  
Natural Hazards ◽  
Power Plants ◽  
Low Flow ◽  
Intergovernmental Panel ◽  
Safety Level ◽  
Safety Review ◽  
Climatic Hazards ◽  
Periodic Safety ◽  
Hazard Level

Abstract According to the Periodic Safety Review Process, the safety level is re-assessed every ten years, considering national and international operational feedback, evolution of knowledge and best available practices. Protection against natural hazards is part of this safety level re-assessment. In the current global change context, climate change impact has to be integrated in external natural hazards estimations, such as climatic hazards or external flooding. EDF has consequently implemented a climate watch approach. Undertaken approximately every 5 years, roughly in line with the publication of the assessment reports of the Intergovernmental Panel on Climate Change (IPCC) and with the update of safety licensing basis during Periodic Safety Reviews, this approach is intended to: - revisit the climatic hazards which present a plausible or certain upward trend, and could lead to an increased reference hazard level, - monitor the reach of target levels which should trigger a thorough analysis (concept of Major Climate Event) to ensure the robustness of the reference hazard level between two periodic reviews. This climate watch approach is developed in partnership with the scientific community and is based on the following activities: - compile and analyze datasets on hazards that are subject to changes with climate change (observed and modelled time series), - develop knowledge of associated climatic phenomena (models, projections). The application of this approach is presented in two steps: - the key implications of the last climate watch exercise carried out in 2015, which identified climatic hazards whose evolution is unfavorable and is plausible or certain for the sites of EDF NPPs: ○ High air and water temperatures (for the “heat wave” hazard) ○ Sea level (for the “external flooding” hazard for coastal or estuary sites) ○ Drought or « low flow » hazard for fluvial sites; - the results obtained for the 900 MW units, for which EDF started the 4th periodic safety review in 2019. Such an approach, which is closely linked to periodic reviews, ensures the robustness of nuclear power plants to the climatic hazards through the consideration of the updated hazard levels.

The Integrated Aging Management System Applied to Nuclear Power Plants in Korea

2013 ◽  
Author(s):  
Se-Youl Won ◽  
Kyeong-Soo Lee ◽  
Jae-Gon Lee
Keyword(s):  
Management System ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Operating Experience ◽  
Evaluation Report ◽  
Time Operation ◽  
Standard Guideline ◽  
Periodic Safety ◽  
Long Time

According to Post Fukushima action items in Korea, KHNP has established the integrated aging management system to reinforce aging management of system, structures, and components (SSCs) effectively for seven operating units, which are in service for more than twenty years, and for Kori Unit 1 and Wolsung Unit 1, which are subject to continued operation (CO) based on NUREG-1801 GALL report. KHNP’s integrated aging management programs (AMPs) focus on the establishment of aging management system for long-lived operation of nuclear power plants in Korea. The integrated aging management system consists of the integrated AMP standard guideline, operating guideline for each plant, individual AMPs of each plant, and AMP Data Base (DB) system including implementation results, basic DB information related to facilities operating in NPPs, and operating information such as operating experience and evaluation report. The integrated aging management system is importantly utilized for Periodic Safety Review (PSR) and the renewal of CO. Therefore, it will be largely contributed to keep NPPs the level of safety for long time operation through the effective aging management.

Commercialization Project of Ulchin Vitrification

2010 ◽  
Author(s):  
Hyun-Jun Jo ◽  
Cheon-Woo Kim ◽  
Tae-Won Hwang
Keyword(s):  
Radioactive Waste ◽  
Nuclear Power ◽  
Power Plants ◽  
Cold Test ◽  
Intermediate Level ◽  
Performance Tests ◽  
Cold Crucible ◽  
Commercial Operation ◽  
Intermediate Level Radioactive Waste ◽  
Hot Test

The Ulchin Vitrification Facility (UVF), to be used for the vitirification of low- and intermediate-level radioactive waste (LILW) generated by nuclear power plants (NPPs), is the world’s first commercial facility using Cold Crucible Induction Melter (CCIM) technology. The construction of the facility was begun in 2005 and was completed in 2007. From December 2007 to September 2009, all key performance tests, such as the system functional test, the cold test, the hot test, and the real waste test, were successfully carried out. The UVF commenced commercial operation in October 2009 for the vitrification of radioactive waste.

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