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Technical Brief

Nonproprietary Flow-Induced Vibration Analysis of San Onofre Nuclear Generating Station Replacement Steam Generators to ASME Code Section III Appendix N

[+] Author and Article Information
R. D. Blevins

San Diego, CA 92103

Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received August 14, 2017; final manuscript received January 25, 2018; published online April 5, 2018. Assoc. Editor: Tomomichi Nakamura.

J. Pressure Vessel Technol 140(3), 034502 (Apr 05, 2018) (5 pages) Paper No: PVT-17-1154; doi: 10.1115/1.4039391 History: Received August 14, 2017; Revised January 25, 2018

Flow-induced vibration analysis of the San Onofre Nuclear Generating Station (SONGS) replacement steam generators (RSG) is made using nonproprietary public data for these steam generators on the Nuclear Regulatory Commission public web site (www.NRC.gov). The analysis uses the methodology of Appendix N Section III of the ASME Boiler and Pressure Vessel Code, Subarticle N-1300 Flow-Induced Vibration of Tubes and Tube Banks. First, the tube geometry is assembled, and overall flow and performance parameters are developed at 100% design flow; then, the analysis is made to determine the flow velocity in the gap between tubes and tube natural frequencies and mode shapes. Finally, the mass damping and reduced velocity for tubes on the U bend are assembled and plotted on the ASME code Figure N-11331-4 fluid elastic stability diagram.

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References

USNRC, 2013, “San Onofre Nuclear Generating Station—NRC Confirmatory Action Letter Response, Non-Proprietary,” U.S. Nuclear Regulatory Commission, Rockville, MD, Adams Accession No. ML13263A271, pp. 1, 2, 7, 8, 12, 20, 21, 28, 29, 34–37, 40, 41, 43.
USNRC, 2013, “Mitsubishi Heavy Industries, Root Cause Analysis Report for Tube Wear Identified in Unit 2 and Unit 3 Steam Generator of San Onofre Nuclear Generating Station, UES-20120254, Non-Proprietary,” U.S. Nuclear Regulatory Commission, Rockville, MD, Adams Accession No. ML13065A097, pp. 9–11, 53, 55, 85, 118, 124.
Chan, J. K. , and Calhoun, D. J. , 2010, “Steam Generator Replacement at San Onofre Nuclear Generating Station Unit 2,” ASME Paper No. PCVP2010-25897.
Southern California Edison, 2002, “Non-Proprietary Responses to NRC question on Proposed Change NPF-10/15-543 SONGS Units 2 and 3,” Southern California Edison, Rosemead, CA, accessed, June 10, 2002, https://www.nrc.gov/docs/ML0216/ML021650059.pdf
ASME, 1998, “ASME Boiler and Pressure Vessel Code Section III, Nonmandatory Appendix N, Subarticle N-1300, Flow-Induced Vibration of Tubes and Tube Banks, 1998 With 2000 Addendum (Retained in 2017 Code),” American Society of Mechanical Engineers, New York.
USNRC, 2012, “Songs-Steam-Generator-Internal-Diagram,” U.S. Nuclear Regulatory Commission, Rockville, MD, Adams Accession No. ML12194A122.
USNRC, 2012, “AREVA/Intertek APTECH/Westinghouse, Appendix A, Estimates of FEI-Induced Rates, 51-9187230, AES 12068150-2Q1,” U.S. Nuclear Regulatory Commission, Rockville, MD, Adams Accession No. ML12285A269, pp. 13, 21, 39, 95, 188, 202.
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Morgan, L. , 2013, “What Went Wrong at San Onofre,” San Diego Union-Tribune, San Diego, CA, June 7.
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Southern California Edison, 2012, “Root Cause Evaluation, Steam Generator Tube Wear NN 201843216,” Southern California Edison, Rosemead, CA, accessed Apr. 2, 2012, https://www.songscommunity.com/docs/nrc/Root_Cause_Eval_U2_SG_R0_Final_Redacted.pdf
USNRC, 2012, “Areva, SONGS U2C17 Steam Generator Operational Assessment for Tube-to-Tube Wear, Also Areva 51-9182833-002,” U.S. Nuclear Regulatory Commission, Rockville, MD, Adams Accession ML12285A268, pp. 2, 3.
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Janzen, V. P. , Hagberg, E. G. , Pettigrew, M. J. , and Taylor, C. E. , 2005, “ Fluidelastic Instability and Work Rate Measurements of Steam Generator U-Tubes in Air-Water Cross-Flow,” ASME J. Pressure Vessel Technol., 127(1), pp. 84–91.
Feenstra, P. , Sawadogo, T. , Smith, B. , Janzen, V. , and Cothron, H. , 2017, “Investigations of in-Plane Fluidelastic Instability in a Multi Span U-Bend Rig-Tests in Air Flow,” ASME Paper No. PVP2017-66068.
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Figures

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Fig. 1

San onofre replacement steam generator. Cutaway shows central tube column [6].

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Fig. 2

San Onofre RSG showing three tubes in the central tube column [7]. Dimensions are in inches. 1 in = 25.4 mm.

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Fig. 3

Tube bundle cross section perpendicular to tube axes at U-tube AVBs

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Fig. 4

Flow exits the hemispherical tube U bend region at top of steam generator. The transverse cut in plane of U bends exposes central tube column [10].

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Fig. 5

Tube pattern and gap flow between U tubes [1]

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Fig. 6

Large amplitude deformation of a U-tube in first mode that is entirely within the plane of U-bend [2]

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Fig. 7

ASME instability plot showing SONGS tube rows 100 and 142 inplane instability in comparison with experimental observations of instability (Figure N-1331-4 with Eqs. 9 and 10 in Ref. [5])

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