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Sunday, July 26, 2020 | History

2 edition of New concepts for verification of seismic adequacy of equipment in operating plants found in the catalog.

New concepts for verification of seismic adequacy of equipment in operating plants

Pressure Vessels and Piping Conference (1985 New Orleans)

New concepts for verification of seismic adequacy of equipment in operating plants

presented at the 1985 Pressure Vessels and Piping Conference and Exhibition, New Orleans, Louisiana, June 23-26, 1985

by Pressure Vessels and Piping Conference (1985 New Orleans)

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  • 40 Currently reading

Published by American Society of Mechanical Engineers in New York, N.Y. (345 E. 47th St., New York 10017) .
Written in English

    Subjects:
  • Nuclear power plants -- Earthquake effects -- Congresses.

  • Edition Notes

    Includes bibliographies.

    Statementsponsored by Pressure Vessels and Piping Design and Analysis Committee ; edited by P.Y. Chen, G. Sliter.
    SeriesPVP ;, vol. 116, PVP (Series) ;, vol. 116.
    ContributionsChen, Pei-Ying., Sliter, George E., American Society of Mechanical Engineers. Pressure Vessels and Piping Division. Design and Analysis Committee.
    Classifications
    LC ClassificationsTK9152 .P66 1985
    The Physical Object
    Paginationv, 72 p. :
    Number of Pages72
    ID Numbers
    Open LibraryOL2748535M
    LC Control Number86081965

      Seismic safety of nuclear power plants became an eminent importance after the Great Tohoku earthquake on 11th of March, and subsequent disaster of the Fukushima Dai-ichi nuclear power plant. Intensive works are in progress all over the world that include review of the site seismic hazard assessment, revision of the design bases, evaluation of vulnerability, and development of . These concepts are still essential in a modern food control system by providing the basic environmental and operating conditions for production of safe food and thus being a requisite or foundation for HACCP in an overall food safety management programme (Figure ). What is new is the concept of formalising the prerequisite programme alongside.

      However, owing to lack of new construction orders for nuclear power plants in recent years, the LBB concept has been generally applied in a backfit mode rather than at .   – Verification of adequacy of all assumed dead and live loads. 2. Code analysis. – Building classification, required fire resistance of structural elements, identification of seismic zone, wind speed, etc. – Identification of special requirements, such as high rise. – Summary of special requirements resulting from applicable local codes. 3.

    The International Building Code requires the design team to review the facility and determine which systems and components are needed to maintain functionality and classify them as designated seismic systems, as appropriate. Example components that may be required to function include power systems, HVAC, controls and other critical equipment. user of electrical plants with a quick reference, immediate-use working tool. This is not intended to be a theoretical document, nor a technical catalogue, but, in addition to the latter, aims to be of help in the correct definition of equipment, in numerous practical installation situations.


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New concepts for verification of seismic adequacy of equipment in operating plants by Pressure Vessels and Piping Conference (1985 New Orleans) Download PDF EPUB FB2

Sincerely, Harold R. Denton, Director Office of Nuclear Reactor Regulation Enclosure: Seismic Adequacy Verification Procedure References: (1) NUREG, "Seismic Qualification of Equipment in Operating Nuclear Power Plants (USI A)," February (2) NUREG, "Regulatory Analysis for Resolution of Unresolved Safety Issue A, Seismic.

Get this from a library. New concepts for verification of seismic adequacy of equipment in operating plants: presented at the Pressure Vessels and Piping Conference and Exhibition, New Orleans, Louisiana, June[Pei-Ying Chen; George E Sliter; American Society of Mechanical Engineers.

Pressure Vessels and Piping Division. Book Reviews. New Concepts for Verification of Seismic Adequacy of Equipment in Operating Plants (Special Publication PVP) P.-Y. Chen, Editor, P.-Y.

Chen, Editor Search for other works by this author on: This Site. : P.-Y. Chen, G. Sliter, Pei-Ying Chen, George Sliter. @article{osti_, title = {Seismic verification of nuclear plant equipment anchorage: Volume 2, Anchorage inspection workbook: Final report}, author = {Czarnecki, R M}, abstractNote = {Guidelines have been developed to evaluate the seismic adequacy of the anchorage of various classes of electrical and mechanical equipment in nuclear power plants covered by NRC Unresolved Safety Issue A Abstract.

The objective of technical studies being performed under the Task Action Plan for Unresolved Safety Issue (USI) A is to establish an explicit set of guidelines and acceptance criteria to judge the adequacy of the seismic qualification of equipment at all operating plants, in lieu of requiring current qualification criteria which are applied to new plants.

Example for the first type of seismic safety programme is the resolution of USI A seismic issues of older, operating nuclear power plants in the U.S. (NRC, ). This programme was aimed to demonstrate the seismic adequacy of essential equipment at older operating plants by the use of available seismic experience data for similar equipment.

An earthquake experience and test based judgmental procedure to verify the seismic adequacy of the specified safety-related equipment in operating NPPs using seismic experience methods, was developed in the USA to address regulatory requirements for requalification of older plants.

On the Scope of Computational-and-Experimental Evaluation of the Seismic Adequacy of NPP Equipment Article in Power Technology and Engineering 48(2) July with 9 Reads. develop a complete and practical Guide to help engineers evaluate and qualify the seismic adequacy of mechanical equipment relied upon to perform critical functions in case of earthquake.

For example, how to seismically qualify a pump that must provide fire suppression. The data have been used to develop a procedure for the verification of the seismic adequacy of cable tray and conduit systems in operating nuclear plants.

The procedure is discussed in this paper. It will result in substantial savings, such as reduced engineering effort, fewer modifications of existing hardware, and simpler documentation.

Seismic design of new nuclear facilities is a well established discipline. However, seismic re-evaluation programmes for existing facilities generally rely on equipment qualification procedures that vary from those applied in the design of new plants. Differences. Subject: Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors, Unresolved Safety Issue (USI) A (Generic Letter ) Notification of Commitment Completion and Status for Crystal River Unit 3 (TAC No.

M) References: 1. FPC letter 3F to NRC, dated Decem 2. Seismic design and qualification for nuclear power ptants: a safety guide.

— Vienna: International Atomic Energy Agency, p. ; 24 cm. — (Safety series, ISSN ; SG-DI5) STI/PUB/ ISBN Includes bibliographical references.

Nuclear power plants—Earthquake effects. Nuclear engineering—. proper seismic action, the suitable numerical model and analysis method and the verification format to be used. The European (EN) and the American standards (ASME. A newcomer to the field of seismic data processing needs to know the fundamental principles as well as common technical terms in their new field.

In this book, phrases in boldface denote where special terms or concepts are defined or discussed. To comprehend each new term or concept, a reader should try to define the term in his or her own. items of equipment which meet certain generic, seismic adequacy criteria. The screening evaluation is based mainly on the use of seismic experience data.

If the equipment does not pass the screens, other more refined or sophisticated methods for evaluating the seismic adequacy of the equipment may be used. Capacity-versus-Demand Evaluation. equipment must prove its seismic adequacy to withstand the effects of the earthquake corresponding to the maximum design earthquake (SSE, S2, SL‐2).

One part of the seismic adequacy verification is the demonstration the equipment is capable to withstand the cumulative. validation component of the verification HACCP principle.

The recommendations in the verification principle form the basis for the requirements in 9 CFR This section requires that every establishment validate the HACCP plan’s adequacy in controlling the food safety hazards identified in the hazard analysis, verify that the plan is being.

LOVA, Loss of He, etc. as well as Seismic event (SL-II) in order to reduce the complexity of the text.

An important concept in equipment qualification is the recognition that significant degradation could be caused by aging mechanisms occurring from the environments during the service life, and therefore PIC.

Seismic Design Category The requirements for a suspended ceiling are determined by the buildings Seismic Design Category. Determination of the Seismic Design Category is complex and must be determined by a Registered Architect or Professional Engineer and should be found in.

EARTHQUAKE-RESISTANT DESIGN CONCEPTS. Chapter 5 DESIGN REQUIREMENTS. Seismic Design Categories. The NEHRP Recommended Seismic Provisions. recognizes that, independent of the quality of their design and construction, not all buildings pose the same seis-mic risk. Factors that affect a structure’s seismic risk include.

The sOUG methodology is currently being used at older operating nuclear power plants to show the seisml adequacy of mecnantcal and electrical equipment for resolution of USJ A SQUG has also develope a procedure for using the experience based methodology for seismic quatification of new and replacemer equipment and parts.The DG, entitled, “Seismic Qualification of Electrical and Active Mechanical Equipment and Functional Qualification of Active Mechanical Equipment for Nuclear Power Plants,” is proposed revision 4 of RG of the same name.

It is temporarily identified by its task number, DG