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Technical Briefs

Critical Section Selection Methodology for the U.S. EPRTM Standard Nuclear Power Plant

[+] Author and Article Information
Se-Kwon Jung

e-mail: sekwon.jung@areva.com

Nawar Alchaar

AREVA Inc.,
7207 IBM Drive,
Charlotte, NC 28262

Specific elevation, thickness, and column line information is not presented and designated “X” for any critical section with this information.

This is identified as a critical section by both the qualitative and quantitative approaches.

These are shield structures for SB23 and FB.

1Corresponding author.

Contributed by the Pressure Vessel and Piping Division of ASME for publication in the Journal of Pressure Vessel Technology. Manuscript received May 24, 2011; final manuscript received February 11, 2013; published online June 11, 2013. Assoc. Editor: Tomoyo Taniguchi.

J. Pressure Vessel Technol 135(4), 044501 (Jun 11, 2013) (7 pages) Paper No: PVT-11-1131; doi: 10.1115/1.4023737 History: Received May 24, 2011; Revised February 11, 2013

A three-tier critical section selection methodology that is used to identify critical sections for the U.S. EPRTM standard nuclear power plant (NPP) is presented. The critical section selection methodology includes three complementary approaches: qualitative, quantitative, and supplementary. These three approaches are applied to Seismic Category I structures in a complementary fashion to identify the most critical portions of the building whose structural integrity needs to be maintained for postulated design basis events and conditions. Once the design of critical sections for a particular Seismic Category I structure is complete, the design for that structure is essentially complete for safety evaluation purposes. Critical sections, taken as a whole, are analytically representative of an “essentially complete” U.S. EPRTM design; their structural design adequacy provides reasonable assurance of overall U.S. EPRTM structural design adequacy.

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References

NRC Regulations Title 10, Code of Federal Regulation Part 52—Licenses, Certifications, and Approvals for Nuclear Power Plants.
NRC Office of Public Affairs, 2005, “Backgrounder on Nuclear Power Plant Licensing Process,” July, Nuclear Regulatory Commission, Washington, DC.
NRC Office of Public Affairs, 2008, “Backgrounder on New Nuclear Plant Designs,” June, Nuclear Regulatory Commission, Washington, DC.
NRC NUREG/BR-0298 Revision 2, 2004, “Nuclear Power Plant Licensing Process,” July, Nuclear Regulatory Commission, Washington, DC.
NRC RG 1.29 Revision 4, 2007, “Seismic Design Classification,” March, Nuclear Regulatory Commission, Washington, DC.
EPRTM Brochure, FRAMATOME ANP, March 2005.
ANSYS, Version 10.0 Service Pack 1.

Figures

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Fig. 1

U.S. EPRTM standard nuclear power plant arrangement

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Fig. 2

Miscellaneous elevation view of EPRTM nuclear island building arrangement [6]

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Fig. 3

Miscellaneous plan view of EPRTM nuclear island structures [6]

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Fig. 4

Schematic plan and elevation views for emergency power generating building (EPGB) and essential service water building (ESWB)

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Fig. 5

Shell-type element forces and moments in a local element coordinate system

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Fig. 6

Schematic representation of a hypothetical building with applicable independent loads and general load combinations

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Fig. 7

Critical elements for load combinations and unique critical elements

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Fig. 8

Projection of centroidal locations of N number of unique critical elements onto XY plane

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Fig. 9

XY scatter plots for subsets of critical elements, expansion of N/10 XY scatter plot at key elevations and resulting critical section identification

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