Building Effective Organizations and Measures to Cope With Severe Weather in Qinshan III NPP

Author(s):  
Jun Zhou

Severe weather such as typhoon has long been a great challenge threats the safe operation of nuclear power plants. To cope with typhoon, Qinshan III NPP has developed an effective management system, including building powerful organizations, creating standard response procedures and consumable storage, which proven to be effective to ensure the safe operation of Qinshan III plant under severe weather conditions.

Author(s):  
Yu Yang ◽  
Wang Can

Nuclear power plants commissioning is an entire inspection and verification process of systems and equipments carried out by commissioning party, to prove that the overall performance of system, equipment and unit can meet the design requirements, operation criteria and nuclear safety criteria, and the plant is qualified for long-term stable and safe operation. As commissioning work has the characteristic of long lasting time, broad scope, high technology and lots of interfaces, and so on, it must be carried out under a set of scientific management system, to accord with requirements of “six controls” of commissioning work. The text aims at researching and investigating into commissioning management system that is in accordance with CPR1000 nuclear power plant commissioning through analysis of constitutes and practice situation of Ling AO phase II project commissioning management system, so as to instruct and standardize the commissioning management of nuclear power plants.


Information ◽  
2020 ◽  
Vol 11 (6) ◽  
pp. 282 ◽  
Author(s):  
Choong-koo Chang

In nuclear power plants, plant management systems are not only very important for operation and maintenance of the facilities, but also play a very important role in analyzing and reporting the events to the authorities when a failure or accident occurs in the facility. In addition, it is also important to ensure that event records are managed transparently so as not to cause any attempt to cover up events. Therefore, this paper proposes a tamper free plant operation system by applying blockchain technology to the integrated plant management system of Korea hydro and nuclear power (KHNP). As a result, this paper will contribute to improving public acceptance by eliminating distrust in safe operation of nuclear power plants.


Author(s):  
Holger Schmidt ◽  
Martin Betz ◽  
Ingo Ganzmann ◽  
Achim Beisiegel ◽  
Thomas Wagner ◽  
...  

Atomic Energy ◽  
2006 ◽  
Vol 101 (2) ◽  
pp. 539-543 ◽  
Author(s):  
Yu. G. Dragunov ◽  
V. P. Denisov

Author(s):  
Se-Youl Won ◽  
Kyeong-Soo Lee ◽  
Jae-Gon Lee

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.


2021 ◽  
Author(s):  
Sam Sadeghi

Safety is the most important aspect and is considered the overwriting priority in nuclear power plants, which comprise of thousands of systems and components that work systematically together for the purpose of generating electricity in a safe, economical and environmentally friendly manner. As the instrumentation and electrical components advance and become more sophisticated and migrate from analog design to the more complicated and error-prone software-based topology, the task of determining that a programmable electronic system (PES) is capable of meeting its safety-related design objective becomes ever more challenging. The dependence on the PES to accomplish its safety-related object must be thoroughly studied to assess the safety-related impacts associated with the potential failure modes of the device. Application Specific Product Qualification (ASPQ) is used to provide neccessay aasurance in the design integrity of a PES and confirms that the product can meet the requirements of a safety-related application. This report is an application specific product qualification (ASPQ) assessment of WEP 1010-110/120-NEA and WEP 1020-110/120-NEA Uninterruptible Power Supplies manufactured by Gambit Electronic Ltd. Information referenced in this report is based on the data received from Gambit, other nuclear power plants using Gambit products and the site visit paid to Gambit, Country-X in August 2007. Gambit WEP 1010- and 10XX-XXX/YY NEA UPS systems are used to provide uninterruptible Class II power to a number of safety-related control and instrumentation power distribution panels for R1 and R2 reactors located in X facility. These UPS are commercial Off-the Shelf (COTS) products intended for industrial uninterruptible power supply applications. An earlier Categorization Assessment Report concluded that UPS perform Category B safety-related functions and therefore, they must be qualified to meet the safety requirements associated with a Class BProgrammable Electronic System (PES) as per IEC 61513.A combination of methods were utilized to demonstrate that the UPS systems were suitable for the target applications, were inherently correct in design, and came with sufficient documentation to allow safe operation by the plant. The key findings of this report indicate that the aforementioned UPS systems are suitable for use in the target application, have strong evidence of reliability through field experience and various product certifications that support correctness of their design and come with thorough documentation that support safe operation and suitability assessment. Two major recommendations made in this report are to establishing a Preventive Maintenance (PM) program by the station to perform replacement of life-limiting components at the minimum frequencies specified by the manufacturerer, and to set ip an inspection and testing program by the station to perform minimum -monthly testing of the output power quality of the UPS systems to minimize the possibility of partial failure, which is the failure of concern and relates to a situation where the loads are supplied with out-of-specification power, undetected.


Author(s):  
H. Reece-Barkell ◽  
W. J. J. Vorster

Effective outage planning and implementation is critical to the efficient and safe operation of commercial nuclear power plants in the UK. Statutory outages are necessary for refuelling, for preventive and corrective maintenance when shutdown conditions are required, and for major modification and improvement projects. Outages involve the support of many companies and individuals working together and, as such, require high levels of coordination. Planning of activities before the outage is critical to the overall success of the outage. Establishing the integrity of power plant piping and pressure vessels is a key objective as part of any outage and the methodology and processes involved are the subject of this paper. Establishing the integrity of piping and pressure vessels requires an understanding of the specific threats, their relationship to the overall condition of the system, and the mitigating measures required to assure safe operation. Understanding the specific threats allows the engineering function of an organisation to advise on pipework and pressure vessel ‘Minimum Acceptable Thicknesses’ which can be used to assure integrity via comparison with thicknesses measured during outage inspections. Minimum Acceptable Thicknesses should be recorded in the outage management documentation so they are accessible during the outage implementation phase. Historically a variety of different methodologies have been used to advise on Minimum Acceptable Thickness requirements including design drawing specified minimum thicknesses, design code based required thicknesses and thicknesses calculated based on Fitness for Purpose methods. It is important that a robust procedure be applied to promote consistency of approach as regards the calculation of pipework and pressure vessel Minimum Acceptable Thickness requirements across all power station assets. An additional consideration is that of ensuring that the approach adopted is consistent with high level safety case guidance, i.e., the assessment is appropriate for the failure tolerability of the plant item. This paper provides an overview of the strategy, methodologies and processes employed to determine Minimum Acceptable Thicknesses for pipework components. These ensure that, over a specified inspection interval, were the weld/component to be defect free, it would not fail due to any of the relevant failure mechanisms, which typically are plastic collapse, creep rupture, fatigue, incremental collapse (ratcheting) or buckling. Readers of this paper will gain a valuable insight into the statutory outage process applicable to nuclear power plants in the UK. A particular focus of this paper is on the structural integrity assessments applied in a non-traditional sense prior to, during and after the statutory outage. As well as sharing a valuable insight into the assessment methodologies this paper highlights best industrial practice.


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