Enhancing the treatment of Human Factors in a Nuclear Power Plant’s Periodic Safety Review

2012 ◽  
pp. 263-269
Author(s):  
Dianne Bayer ◽  
Martin Reid ◽  
Gillian Vaughan ◽  
Deborah Lucas
Keyword(s):  
Human Factors ◽  
Nuclear Power ◽  
Safety Review ◽  
Periodic Safety

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.

Seismic re-evaluation of EDF Bugey 900 PWR nuclear power plant in the frame of the 3rd periodic safety review

2010 ◽  
Vol 240 (6) ◽  
pp. 1306-1319 ◽  
Author(s):  
E. Viallet ◽  
P. Labbé ◽  
E. Gallitre ◽  
A. Nadjarian ◽  
D. Vandeputte ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Safety Review ◽  
Periodic Safety

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.

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

Human reliability in non-destructive inspections of nuclear power plant components: modeling and analysis

2019 ◽  
Vol 7 (2B) ◽  
Author(s):  
Vanderley Vasconcelos ◽  
Wellington Antonio Soares ◽  
Raissa Oliveira Marques ◽  
Silvério Ferreira Silva Jr ◽  
Amanda Laureano Raso
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Human Factors ◽  
Nuclear Power ◽  
Power Plants ◽  
Failure Modes ◽  
Cooling System ◽  
Human Reliability ◽  
Non Destructive ◽  
Plant Components

Non-destructive inspection (NDI) is one of the key elements in ensuring quality of engineering systems and their safe use. This inspection is a very complex task, during which the inspectors have to rely on their sensory, perceptual, cognitive, and motor skills. It requires high vigilance once it is often carried out on large components, over a long period of time, and in hostile environments and restriction of workplace. A successful NDI requires careful planning, choice of appropriate NDI methods and inspection procedures, as well as qualified and trained inspection personnel. A failure of NDI to detect critical defects in safety-related components of nuclear power plants, for instance, may lead to catastrophic consequences for workers, public and environment. Therefore, ensuring that NDI is reliable and capable of detecting all critical defects is of utmost importance. Despite increased use of automation in NDI, human inspectors, and thus human factors, still play an important role in NDI reliability. Human reliability is the probability of humans conducting specific tasks with satisfactory performance. Many techniques are suitable for modeling and analyzing human reliability in NDI of nuclear power plant components, such as FMEA (Failure Modes and Effects Analysis) and THERP (Technique for Human Error Rate Prediction). An example by using qualitative and quantitative assessesments with these two techniques to improve typical NDI of pipe segments of a core cooling system of a nuclear power plant, through acting on human factors issues, is presented.

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