Calculation Cross-Reference Database

Author(s):  
Gregory C. Wilson ◽  
Keith D. Wooten

Calculations form the backbone of every design. Engineers and designers rely on calculations to support the technical adequacy of any system, structure or component (SSC). Without representative calculations, the design, construction, operation, maintenance or modification of any SSC would remain unanalyzed, non-configured and potentially unsafe. In today’s nuclear generating plants, calculations that form the design basis and how that design is translated into drawings and procedures are especially important. Federal regulations mandate that all nuclear generating plant licensees establish a method of design control to assure that regulatory requirements are met. The purpose of this paper is to describe one such method by which a nuclear plant licensee (Southern Nuclear) controls its calculations.

2021 ◽  
Author(s):  
Hoseon Choi ◽  
Seung Gyu Hyun

<p>According to strict criteria step by step for site selection, design, construction and operation, the seismic safety of nuclear power plant (NPP) sites in South Korea are secured by considering design basis earthquake (DBE) level capable of withstanding the maximum ground motions that can occur on the site. Therefore, it is intended to summarize DBE level and its evaluation details for NPP sites in several countries.</p><p>Similar but different terms are used for DBE from country to country, i.e. safe shutdown earthquake (SSE), design earthquake (DE), SL2, Ss, and maximum calculated earthquake (MCE). They may differ when applied to actual seismic design process, and only refer to approximate comparisons. This script used DBE as a representative term, and DBE level was based on horizontal values.</p><p>The DBE level of NPP sites depends on seismic activity of the area. Japan and Western United States, where earthquakes occur more frequently than South Korea, have high DBE values. The DBE level of NPP sites in South Korea has been confirmed to be similar or higher compared to that of Central and Eastern Unites Sates and Europe, which have similar seismic activity.</p>


Author(s):  
A. Lapina ◽  
A. Ponomarenko ◽  
K. Shencova ◽  
A. Kotesova

the article deals with the main causes of accidents of buildings and structures that occurred due to errors made at different stages of their life cycle (design, construction, operation). A brief analysis of the accidents that occurred from 2010 to 2017 in the Russian Federation is presented. The study of the causes of accidents makes it possible to understand better the laws of structures, buildings and structures, to identify errors that lead to emergencies. Such errors include: low quality of construction and installation works, deviation from the project in the construction of buildings and structures, the use of materials of inadequate quality, overload of load-bearing structures during operation. Also, the causes of accidents include defective engineering-geological and hydrogeological studies of the grounds. Analysis of accidents showed that the last few years there is no tendency to reduce the number of accidents of buildings and structures, which indicates an insufficient number of measures to prevent them. In the article the authors consider the examples of accidents in construction, which occurred due to the main reasons, and ways to prevent accidents in the future.


Author(s):  
Heidi C. Kim

In January of 2015, the Federal Aviation Administration (FAA) released an 80-page document outlining Safety Management Systems (SMS) for Title 14 of the Code of Federal Regulations (14 CFR) part 121 air carriers. This advisory circular provides a description of regulatory requirements, methods of development, and implementation of an SMS (Federal Aviation Administration, 2015). The release of this document began a race to implement SMS across aviation. An all-encompassing Safety Management System currently does not apply to the manufacturing of airplane parts. This research will examine current safety management processes in place for applicants and holders of supplemental type certificates (STC). Upon review of current procedures, a model for an SMS will be created specific to supplemental type certificate applicants and holders. This SMS process created for STC holders will ultimately improve aviation safety. The FAA should mandate this framework for all applicants pursuing and holding a supplemental type certificate.


Author(s):  
Lorna Harron ◽  
Dennis Attwood

Reduction of human error can have a significant impact on the potential for spills and leaks and translate into better safety performance and financial gains for an organization. As important as the technical components of a design, construction, operation, and maintenance program is the human component of the activities being performed. In the Pipeline Industry, human factors can create the potential for a human error at many points along the life cycle of a pipeline. Using a life cycle approach to manage human factors can provide an organization the capability to integrate human factors into programs, standards, procedures and processes using a disciplined approach. This paper reviews the life cycle of a pipeline and identifies areas where the potential for human error can have catastrophic results. Guidance is provided on the development of a human factors life cycle for the organization and illustrates available industry resources as well as opportunities for further research and development.


2015 ◽  
Vol 773-774 ◽  
pp. 1220-1225
Author(s):  
Sulzakimin Mohamed ◽  
Seow Ta Wee ◽  
Goh Kai Chen ◽  
Md Asrul Nasid Masrom ◽  
Mohd Hilmi Izwan Abd Rahim

Sustainable development has become an important aspect of the construction industries. There are many ways sustainability elements can be incorporated in the design, construction, operation and deconstruction of a building. Importantly sustainability represents the link between society and built environment professionals. In relation to that, this study involves a look at the stakeholders outlook and interaction with sustainability. In this study, the focus will be aimed on the role of the Local Governments and how the perception of the stakeholders. Therefore, this study intend to look into the sustainable development and better understanding the strength and weaknesses and other relevant factors that promote or hinder the Sustainable Development. This study is to contribute to the enrichment of knowledge on the role of Local Governments in Sustainable Development. Therefore, this research seeks to find out whether sustainable development is being practiced and seeks to find out what is happening with respect to issues of what, how and why things are being done with the development of Sustainable Development globally and in Malaysia in general.


Author(s):  
Ralph S. Hill

Current American Society of Mechanical Engineers (ASME) nuclear codes and standards rely primarily on deterministic and mechanistic approaches to design. The design code is a separate volume from the code for inservice inspections and both are separate from the standards for operations and maintenance. The ASME code for inservice inspections and code for nuclear plant operations and maintenance have adopted risk-informed methodologies for inservice inspection, preventive maintenance, and repair and replacement decisions. The American Institute of Steel Construction and the American Concrete Institute have incorporated risk-informed probabilistic methodologies into their design codes. It is proposed that the ASME nuclear code should undergo a planned evolution that integrates the various nuclear codes and standards and adopts a risk-informed approach across a facility life-cycle — encompassing design, construction, operation, maintenance and closure.


Author(s):  
C. K. Paulson

A clear distinction between advanced plants, such as the Westinghouse AP1000 and AP600, and evolutionary plants is the policy in the latter to use current systems’ and buildings’ configurations. This approach does not promote simplification or streamlining, especially in the mechanical systems of the plant. The most significant simplification in evolutionary designs has arguably been in the plant electronics where compact digital components and multiplexing have led to improvements, especially in the areas of information display, installation, and testing. The Westinghouse advanced, passive plants take a different approach. Their design engineers presume that if regulatory requirements can be satisfied by using passive systems, then active plant systems that are only designed to meet plant control functions and not burdened with meeting a safety pedigree can be implemented. This separation of safety and control allows the plant designer to focus on systems’ optimization and reliability by reducing complexity and its associated cost. This design policy has led Westinghouse to the AP600 and AP1000 plant configurations, both of which incorporate significant improvements in areas of plant simplification and enhanced safety.


Author(s):  
Manuela Triay ◽  
Benoit Lefever ◽  
Julien Quéré ◽  
Jean-Luc Gobert ◽  
Emmanuel Chantelat ◽  
...  

The paper will cover the general approach followed by nuclear code RCC-M [1] of AFCEN, the French Society for Design, Construction and In-Service Inspection Rules for Nuclear Island Components, in codes and standards setting, from the technical and organizational points of view. After reminding the main modifications introduced in the 2016 & 2017 editions, the main evolutions expected in the 2018 edition of RCC-M code will be explained and commented, as well as the main new topics of activity of RCC-M subcommittee. The presentation highlights how the industrial experience is currently integrated into the RCC-M code. It also develops how the substantial effort carried out by AFCEN for the last three years, to demonstrate the conformity with European and French regulatory requirements, led not only to the development of dedicated guides and modifications in regulatory appendices of the code, but also to improvements in the main parts of the code.


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