Regulatory Guidance for Risk-Informed In-Service Inspection of Nuclear Power Plants in Bulgaria

2007 ◽  
Author(s):  
Adam Toft ◽  
David Lidbury ◽  
Rossitza Miteva ◽  
Dimitar Vasilev
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Best Practice ◽  
Operating Conditions ◽  
Guidance Document ◽  
Draft Guidance ◽  
Nuclear Facilities ◽  
Regulatory Guidance ◽  
The Uk ◽  
Service Inspection

Risk-Informed In-Service Inspection (RI-ISI) aims to integrate service experience, plant and operating conditions, other deterministic information, and risk insights in developing augmented in-service inspection (ISI) programmes for Nuclear Power Plant (NPP). RI-ISI is a developing methodology which is increasingly being adopted world-wide, and is seen as having the potential to make ISI programmes more effective and efficient in terms of both nuclear safety and the economical operation of nuclear plant. The Nuclear Regulatory Agency (NRA) bears responsibility for regulating nuclear facilities in Bulgaria. In anticipation of a forthcoming application by Kozloduy NPP to adopt an RI-ISI programme for selected systems in WWER-1000 plant, the NRA required a suitable regulatory guidance document to help assess such an application. The UK Department of Trade and Industry-funded Project NSP/04-B23 “Assistance with the Regulatory Aspects of Risk-informed In-Service Inspection (RI-ISI)” has enabled the development of a guidance document, the initial draft of which was produced by Serco Assurance in close consultation with the NRA and other Bulgarian stakeholders. This paper presents a description of how current international best practice has been tailored to Bulgarian NPP, and provides a summary of the draft guidance document produced as the principal output of Project NSP/04-B23.

Best practice for chronic oedema in community settings: what can we learn?

2020 ◽  
Vol 25 (12) ◽  
pp. 610-614
Author(s):  
Garry Cooper-Stanton
Keyword(s):  
Service Provision ◽  
Best Practice ◽  
Evidence Base ◽  
Community Services ◽  
Guidance Document ◽  
Community Settings ◽  
Tissue Viability ◽  
Delivery Of Care ◽  
Specialist Nurses ◽  
The Uk

There are various opportunities and challenges in the delivery of care to those diagnosed with chronic oedema/lymphoedema. Service provision is not consistent within the UK, and non-specialist nurses and other health professionals may be called on to fill the gaps in this area. The latest best practice guidance on chronic oedema is directed at community services that care for people within their own homes in primary care. This guide was developed in order to increase awareness, knowledge and access to an evidence base. Those involved in its creation cross specialist fields (lymphoedema and tissue viability), resulting in the document covering a number of areas, including an explanation of chronic oedema, its assessment and management and the association between chronic oedema and wet legs. The document complements existing frameworks on the condition and its management and also increases the available tools within chronic oedema management in the community. The present article provides an overview of the guidance document and discusses its salient features.

Design, Analysis and System-Level Modelling of a Single Axis Capacitive Accelerometer

2016 ◽  
Author(s):  
Zakriya Mohammed ◽  
Owais Talaat Waheed ◽  
Ibrahim (Abe) M. Elfadel ◽  
Aveek Chatterjee ◽  
Mahmoud Rasras
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Noise Analysis ◽  
Linear Displacement ◽  
Operating Conditions ◽  
System Level ◽  
Complete Analysis ◽  
Capacitive Accelerometer ◽  
Static Capacitance ◽  
Cross Axis

The paper demonstrates the design and complete analysis of 1-axis MEMS capacitive accelerometer. The design is optimized for high linearity, high sensitivity, and low cross-axis sensitivity. The noise analysis is done to assure satisfactory performance under operating conditions. This includes the mechanical noise of accelerometer, noise due to interface electronics and noise caused by radiation. The latter noise will arise when such accelerometer is deployed in radioactive (e.g., nuclear power plants) or space environments. The static capacitance is calculated to be 4.58 pF/side. A linear displacement sensitivity of 0.012μm/g (g = 9.8m/s2) is observed in the range of ±15g. The differential capacitive sensitivity of the device is 90fF/g. Furthermore, a low cross-axis sensitivity of 0.024fF/g is computed. The effect of radiation is mathematically modelled and possibility of using these devices in radioactive environment is explored. The simulated noise floor of the device with electronic circuit is 0.165mg/Hz1/2.

The organisation & the costs of the decommissioning nuclear plants in the UK

2009 ◽  
pp. 63-82
Author(s):  
Steve Thomas
Keyword(s):  
Key Words ◽  
Nuclear Power ◽  
Nuclear Fuels ◽  
Nuclear Facilities ◽  
Nuclear Decommissioning ◽  
Nuclear Plants ◽  
New Public ◽  
Public Body ◽  
The Uk ◽  
Jel Classifications

- UK electricity consumers have paid provisions for decommissioning since before 1980 but by 2002, there were still negligible funds available to pay for decommissioning civil nuclear facilities. By then, the two major UK nuclear companies, British Energy and British Nuclear Fuels Limited (BNFL), were both effectively bankrupt. This paper examines: the pre-2002 provisions for decommissioning and how they were lost; the Nuclear Decommissioning Authority, a new public body which took over ownership of BNFL's facilities including the duty to manage their decommissioning and how it expects to carry out and fund decommissioning of its sites; how the re-launched British Energy will contribute to decommissioning its eight plants; and government plans for collecting decommissioning provisions for any new plants.JEL classifications: L50, L38, H23, H44, L71Key words: Nuclear power, decommissioning cost, funding and polluter pays.

Cyber Security Assessment of NPP I&C Systems

2020 ◽  
pp. 221-238
Author(s):  
Oleksandr Klevtsov ◽  
Artem Symonov ◽  
Serhii Trubchaninov
Keyword(s):  
Control Systems ◽  
Cyber Security ◽  
Nuclear Power ◽  
Power Plants ◽  
Cyber Attacks ◽  
Security Assessment ◽  
Nuclear Facilities ◽  
Security Risks ◽  
Cyber Threats ◽  
And Control

The chapter is devoted to the issues of cyber security assessment of instrumentation and control systems (I&C systems) of nuclear power plants (NPP). The authors examined the main types of potential cyber threats at the stages of development and operation of NPP I&C systems. Examples of real incidents at various nuclear facilities caused by intentional cyber-attacks or unintentional computer errors during the maintenance of the software of NPP I&C systems are given. The approaches to vulnerabilities assessment of NPP I&C systems are described. The scope and content of the assessment and periodic reassessment of cyber security of NPP I&C systems are considered. An approach of assessment to cyber security risks is described.

INTERCOMPARISON ON INTERNAL DOSE ASSESSMENT FOR NUCLEAR POWER PLANTS IN KOREA

2019 ◽  
Vol 186 (4) ◽  
pp. 524-529
Author(s):  
Si Young Kim
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Evaluation Method ◽  
Dose Assessment ◽  
Assessment Procedure ◽  
Internal Dose ◽  
Nuclear Facilities ◽  
International Intercomparison ◽  
Selection Of

Abstract The intercomparison test is a quality assurance activity performed for internal dose assessment. In Korea, the intercomparison test on internal dose assessment was carried out for nuclear facilities in May 2018. The test involved four nuclear facilities in Korea, and seven exposure scenarios were applied. These scenarios cover the intake of 131I, a uranium mixture, 60Co and tritium under various conditions. This paper only reviews the participant results of three scenarios pertinent to the operation of nuclear power plants and adopts the statistical evaluation method, used in international intercomparison tests, to determine the significance values of the results. Although no outliers were established in the test, improvements in the internal dose assessment procedure were derived. These included the selection of intake time, selection of lung absorption type according to the chemical form and consideration of the contribution of previous intake.

scholarly journals Importance of Advanced Planning of Manufacturing for Nuclear Industry

2016 ◽  
Vol 7 (2) ◽  
pp. 42-49
Author(s):  
Nick Shykinov ◽  
Robert Rulko ◽  
Dariusz Mroz
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Regulatory Compliance ◽  
Pressure Vessels ◽  
Nuclear Industry ◽  
Project Schedule ◽  
Nuclear Facilities ◽  
Project Completion ◽  
Advanced Planning ◽  
And Performance

Abstract In the context of energy demands by growing economies, climate changes, fossil fuel pricing volatility, and improved safety and performance of nuclear power plants, many countries express interest in expanding or acquiring nuclear power capacity. In the light of the increased interest in expanding nuclear power the supply chain for nuclear power projects has received more attention in recent years. The importance of the advanced planning of procurement and manufacturing of components of nuclear facilities is critical for these projects. Many of these components are often referred to as long-lead items. They may be equipment, products and systems that are identified to have a delivery time long enough to affect directly the overall timing of a project. In order to avoid negatively affecting the project schedule, these items may need to be sourced out or manufactured years before the beginning of the project. For nuclear facilities, long-lead items include physical components such as large pressure vessels, instrumentation and controls. They may also mean programs and management systems important to the safety of the facility. Authorized nuclear operator training, site evaluation programs, and procurement are some of the examples. The nuclear power industry must often meet very demanding construction and commissioning timelines, and proper advanced planning of the long-lead items helps manage risks to project completion time. For nuclear components there are regulatory and licensing considerations that need to be considered. A national nuclear regulator must be involved early to ensure the components will meet the national legal regulatory requirements. This paper will discuss timing considerations to address the regulatory compliance of nuclear long-lead items.

scholarly journals ASPiH standards for simulation-based education: process of consultation, design and implementation

2017 ◽  
Vol 4 (3) ◽  
pp. 117-125 ◽  
Author(s):  
Makani Purva ◽  
Jane Nicklin
Keyword(s):  
Best Practice ◽  
Evidence Base ◽  
Development Project ◽  
Full Potential ◽  
Guidance Document ◽  
Consultation Process ◽  
For Profit ◽  
Simulation Based ◽  
Literature Evidence ◽  
The Uk

There is widespread enthusiasm and emerging evidence of the efficacy of simulation-based education (SBE) but the full potential of SBE has not been explored. The Association for Simulated Practice in Healthcare (ASPiH) is a not-for-profit membership association with members from healthcare, education and patient safety background. ASPiH’s National Simulation Development Project in 2012 identified the lack of standardisation in the approach to SBE with failure to adopt best practice in design and delivery of SBE programmes. ASPiH created a standards project team in 2015 to address this need. The article describes the iterative process modelled on implementation science framework, spread over six stages and 2 years that resulted in the creation of the standards. The consultation process supported by Health Education England resulted in a unique document that was driven by front line providers while also having strong foundations in evidence base. The final ASPiH document consisting of 21 standards for SBE has been extensively mapped to regulatory and professional bodies in the UK and abroad ensuring that the document is relevant to a wide healthcare audience. Underpinning the standards is a detailed guidance document that summarises the key literature evidence to support the standard statements. It is envisaged the standards will be widely used by the simulation community for quality assurance and improving the standard of SBE delivered.

The Regulatory Framework for Safe Decommissioning of Nuclear Power Plants in Korea

2013 ◽  
Author(s):  
Sangmyeon Ahn ◽  
Jungjoon Lee ◽  
Chanwoo Jeong ◽  
Kyungwoo Choi
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Regulatory Framework ◽  
International Standards ◽  
Current Status ◽  
Nuclear Facilities ◽  
Safety Requirement ◽  
Regulatory Review ◽  
Safety Standards

We are having 23 units of nuclear power plants in operation and 5 units of nuclear power plants under construction in Korea as of September 2012. However, we don’t have any experience on shutdown permanently and decommissioning of nuclear power plants. There are only two research reactors being decommissioned since 1997. It is realized that improvement of the regulatory framework for decommissioning of nuclear facilities has been emphasized constantly from the point of view of IAEA’s safety standards. It is also known that IAEA will prepare the safety requirement on decommissioning of facilities; its title is the Safe Decommissioning of Facilities, General Safety Requirement Part 6. According to the result of IAEA’s Integrated Regulatory Review Service (IRRS) mission to Korea in 2011, it was recommended that the regulatory framework should require decommissioning plans for nuclear installations to be constructed and operated and these plans should be updated periodically. In addition, after the Fukushima nuclear disaster in Japan in March of 2011, preparedness for early decommissioning caused by an unexpected severe accident became important issues and concerns. In this respect, it is acknowledged that the regulatory framework for decommissioning of nuclear facilities in Korea need to be improved. First of all, we focus on identifying the current status and relevant issues of regulatory framework for decommissioning of nuclear power plants compared to the IAEA’s safety standards in order to achieve our goal. And then the plan is established for improvement of regulatory framework for decommissioning of nuclear power plants in Korea. It is expected that if the things will go forward as planned, the revised regulatory framework for decommissioning could enhance the safety regime on the decommissioning of nuclear power plants in Korea in light of international standards.

Study on a Methodology of Human Factor Engineering Operating Experience Review for Nuclear Power Plant

2010 ◽  
Author(s):  
Danying Gu ◽  
Shuhui Zhang ◽  
Zhonghe Ning
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Human Factor ◽  
Operating Experience ◽  
Sources Of Information ◽  
Nuclear Facilities ◽  
Human Factor Engineering ◽  
Design Procedures ◽  
Function Allocation ◽  
Review Criterion

The reviewing of operating experience at nuclear power plants (NPP) is not only critically important to safe and reliable operations, but also useful to guide the design of new plants which are similar to the current one under review. How to identify and analyze the safety-related operating experience and then implement a more extensive review is a vital and challengeable issue. In this paper, a methodology of human factor engineering (HFE) operating experience review (OER) is proposed for NPP. The need for the application of HFE in the life cycle activities of NPP and other nuclear facilities has been demonstrated by plant operating histories and regulatory and industry reviews. As a very important element of HFE, the OER is performed from the beginning of the design process. The main purpose of performing an OER is to verify that the applicant has identified and analyzed HFE-related safety problems and issues in previous designs that are similar to the current one. In this way, negative features associated with predecessor designs may be avoided in the current NPP design while retaining positive features. The research of OER concentrates on the aspect of review criterion, scope and implementation procedure of the HFE-related operating experience. As the NRC requirement, the scope of operating experience can be divided into six types in accordance with sources of information. The implementation procedures of USA and China are introduced, respectively. The resolution of HFE OER issues involve function allocation, changes in automation, HSI equipment design, procedures, training, and so forth. The OER conclusions can contribute to other HFE activities and improve the safety, reliability and usability of the HSI design in NPP.

Thermal Design Options Using Uranium Carbide and Uranium Dicarbide in SCWR Uniformly-Heated Fuel Channel

2009 ◽  
Author(s):  
Leyland J. Allison ◽  
Lisa Grande ◽  
Sally Mikhael ◽  
Adrianexy Rodriguez Prado ◽  
Bryan Villamere ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Reactor ◽  
Operating Conditions ◽  
Thermal Design ◽  
Nuclear Fuels ◽  
Viable Option ◽  
Bulk Fluid ◽  
Fuel Channel ◽  
Uranium Carbide

SuperCritical Water-cooled nuclear Reactor (SCWR) options are one of the six reactor options identified in Generation IV International Forum (GIF). In these reactors the light-water coolant is pressurized to supercritical pressures (up to approximately 25 MPa). This allows the coolant to remain as a single-phase fluid even under supercritical temperatures (up to approximately 625°C). SCW Nuclear Power Plants (NPPs) are of such great interest, because their operating conditions allow for a significant increase in thermal efficiency when compared to that of modern conventional water-cooled NPPs. Direct-cycle SCW NPPs do not require the use of steam generators, steam dryers, etc. allowing for a simplified NPP design. This paper shows that new nuclear fuels such as Uranium Carbide (UC) and Uranium Dicarbide (UC2) are viable option for the SCWRs. It is believed they have great potential due to their higher thermal conductivity and corresponding to that lower fuel centerline temperature compared to those of conventional nuclear fuels such as uranium dioxide, thoria and MOX. Two conditions that must be met are: 1) keep the fuel centreline temperature below 1850°C (industry accepted limit), and 2) keep the sheath temperature below 850°C (design limit). These conditions ensure that SCWRs will operate efficiently and safely. It has been determined that Inconel-600 is a viable option for a sheath material. A generic SCWR fuel channel was considered with a 43-element bundle. Therefore, bulk-fluid, sheath and fuel centreline and HTC profiles were calculated along the heated length of a fuel channel.

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