ML20137T156

Requests That Attachment 1 Info Be Considered as Proprietary.W/O Attachment

ML20137T156
Person / Time
Site:	Sequoyah
Issue date:	06/25/1996
From:	Taylor J FRAMATOME
To:	Rosalyn Jones NRC (Affiliation Not Assigned)
References
JHT-96-43, NUDOCS 9704160006
Download: ML20137T156 (28)

Text

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. F R AM ATO M E

' TECHHOLOGIE5-s June 25, 1996 JHT/96-43 Mr. R. C. Jones, Chief Reactor Systems Branch Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

References:

1. J. H. Taylor, B&W Nuclear Technologies to USNRC, B&W Topical report BAW-10159P-A, "BWCMV ll Correlation of Critical Heat Flux in Mixing Vane Fuel Assemblies," JHT/95-44, April 24, 1995.

2. J. H. Taylor, B&W Nuclear Technologies to ,

USNRC, Request for Extension of Applicability L of BWCMV to Vantage-5H Fuel Without Intermediate Flow Mixers," JHT/95-118, December 4, 1995.

3. J. H. Taylor, Framatome Technologies to USNRC, I Request for Extension of Applicability of BWCMV to Vantage-SH Fuel Without Intermediate Flow ,

Mixers, JHT/96-11, February 1, 1996. l

4. J. H. Taylor, Framatome Technologies to USNRC, l Request for Extension of Applicability of BWCMV i to Vantage-5H Fuel Without Intermediate Flow Mixers, JHT/96-32, May 6, 1996. ,

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Dear Mr. Jones:

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In reference 1 BWFC requested an extension of the applicability m.

l of the BWCMV critical heat flux correlation to Vantage-5H fuel. E.

References 2, 3 and 4 included additional information to support E that request. The correlation has previously been approved for gg use with the Mark-BW, Westinghouse Standard, and Westinghouse OFA m.

fuel assemblies. E.

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On June 20, 1996 representatives from TVA and FCF met with the NRC Project Manager and members of the Reactor Systems Branch to discuss that roquest. In that meeting FCF presented technical

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material that was proprietary. NRC requested that the material be submitted in both proprietary and non-proprietary versions so t

DOOK 27 l P PDR 3315 Old Forest Road, P.O. Box 10935, Lynchburg, Virginia 24506-0935 Fax: 804-832-3663 f ((M, Telephone: 804 832-3000

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i that it could be entered into the public record. Attachment 1 is l the proprietary version of the presentation and Attachment 2 is

the non-proprietary version. A discussion of the hydraulic flow testing that was performed for the Vantage-5H fuel is included in the Attachments.

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In the meeting all technical issues concerning the applicability of BWCMV to Vantage-5H fuel were resolved. The NRC agreed to 4

j issue an SER granting the extension of the correlation to

Vantage-5H for Sequoyah Units 1 and 2 by August 31, 1996. Since j the correlation will be used in design calculations that are i currently being performed, approval is needed by that date.

Questions related to the specific application to Sequoyah will be 3 addressed in the review of topical report BAW-10220P, " Mark-BW j Fuel Assembly Application for Sequoyah Units 1&2." FCF is i planning a submittal to address cross flow effects between

different types of fuel assemblies in support of that topical.

! Review of BAW-10220P is scheduled to be completed in February l 1997.

In accordance with 10CFR2.790, Framatome Technologies Inc.

1 requests that the information in Attachment i be considered j proprietary. An affidavit supporting this request was included

with the May 12, 1986 submittal of BAW-10159P.

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l Very truly yours, C/?!!cY & f i J. H. Taylor, Manager Licensing Services il i cc: L. E. Phillips, NRC l T. L. Huang, NRC C. P. Jackson, NRC jl R. W. Hernan, NRC J. F. Burrow, TVA i R. Huston, TVA i R. B. Borsum 4

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Attachment 2 Non-Proprietary Version of Material Presented at Meeting on June 20, 1996

-i Application of BWCMV CHF Correlation  !

to Westinghouse VANTAGE SH Fuel i

meeting - NRC/FCF/TVA .

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June 20,1996 l

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AGENDA Meeting Objectives George Meyer Summary of Licensing Activities Frank McPhatter The BWCMV CHF Correlation .

David Famsworth Application to Sequoyah Core Analysis Jeffrey Griffith Conclusions George Meyer l

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Objective  :

i Obtain NRC Approval for the Application of BWCMV to the  :

VANTAGE 5H Fuel Design (w/o /FMs) t i

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r Purpose l

Limitations .

The application of BWCMV to VANTAGE SH fuel will be limited to:

Other considerations

Expected Conclusion

The Application of BWCMV to the VANTAGE 5H Fuel Design (wlo IFMs) is Acceptable within the limitations discussed.

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CHRONOLOGY FOR APPLICATION OF .

BWCMV TO VANTAGE 5H Application to V5H for Sequoyah Requested April 24,1995 ,

Telecon to Discuss April 24 Submittal August 17,1995 Basis for Application to V5H Submitted Dec. 4,1995 Additional Basis for Application Submitted Feb.1,1996 Limitations of Applicability Submitted May 6,1996 I

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_..______...____.________.____________-_.___.__._.____________________________________________m__

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Critical Heat Flux Correlation Applicability INTRODUCTION l

1 i l l

l CORRELATION COMPATIBILITY

. Number and Types of Tests l

! Distribution of Data Correlated i Variable Ranges Correlated i j DESIGN COMPATIBILITY l Dimensional Parameters

Previous Testing l Proposed Application i

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REPRESENTATION of VANTAGE SH by BWCMV Based on the Demonstrated Compatibility between BWCMV and WRB-1 and the Approved Representation of the Vantage 5H Design by WRB-1, Applicability of the BWCMV Correlation to the Vantage 5H Design Follows

a ,

critical Heat Flux Correlation Applicability TEST CONFIGURATIONS BWCMV WRB-1 (BAW-10159-A) (WCAP-8763-A)

Number of Tests 26 24 W-H Tests 22 24 NFI Tests 4 0 Heated Lengths 3 2 Grid Spacings 6 5 Grid Designs 5 3 Axial Flux Shapes 6 4 Geometries 4 4

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Critical Heat Flux Correlation Applicability j DISTRIBUTION OF DATA 4 BWCMV WRB-1 2

(BAW-10159-A) (WCAP-8763-A)

^

l 1147 Number of Data 1418 Non-Uniform 1091 748 Uniform 327 399

, Unit Cell 878 895 i

Guide Tube 540 252 Large Pin 783 646 l Small Pin 635 501 8 Ft Length 464 411 12 Ft Length 468 0 j

! 14 Ft Length 486 736 l 1

< Design Limit DNBR 1.21 1.17 j i I k

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Critical Heat Flux Correlation Applicability .

l VARIABLE RANGES 1

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i BWCMV WRB-1 (BAW-10159-A) (WCAP-8763-A) i

_ Pressure, psia 1485 to 2455 1440 to 2490 1

I Mass Velocity, alb/hr-ft2 0.95 to 3.74 0.9 to 3.7 i

j Thermodynamic Quality 9 CHF -22 to +22 -20 to +30 Hydraulic Diameter, inches .3747 to .5355 .37 to .60 i

Grid Spacing, inches 13 to 32 13 to 32 1

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i i Critical Heat Flux

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f Correlation Applicability

DESIGN COMPATIBILITY I "from a DNB perspective the VANTAGE SH Zircaloy j grid design incorporated in the VANTAGE 5H assembly l is virtually identical to the 17x17 inconel j R-grid design in that the rod size, rod pitch,

{ heated length and grid spacing are unchanged."

! Addendum 2a to WCAP-10444-A, VANTAGE SH Fuel l Assembly, Westinghouse Electric Corporation, February,1989.

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' WP vs Mass Ualocits BHCMU Non-Uniforn 0.374" Data nib /hr-ft2 ,

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N/P vs Quaiits M/P vs Pressure at CHF psia

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_ -5.0 i 10.0 25.0 _1000 2000 i 3000_

_ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _______ _ ___ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ + -

. -. . _._-. -- - - --. - -. - - . . _ -.= _ - -

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Critical Heat Flux l i Correlation Applicability

SUMMARY

and CONCLUSIONS SINCE l In Number and Type of Test Configurations WRB-1 is a Subset of BWCMV i AND in the Distribution of Data Correlated  ;

WRB-1 is a Subset of BWCMV l

AND l

The NRC Approved independent Variable Ranges of WRB-1 and BWCMV are Virtually identical THEN If a Design is Represented by WRB-1 That Design can be Represented by BWCMV

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Critical Heat Flux  :

j Correlation Applicability

SUMMARY

and CONCLUSIONS (Continued) 1 l

4 SINCE

! The WRB-1 Correlation has been Shown to Represent the Vantage SH Design AND The BWCMV Correlation has been Shown l to Represent Designs Described by WRB-1 I

THEN

) The BWCMV Correlation can be Used j to Represent the Vantage 5H Design 1

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Key Constraints Related to V5H Licensing 6

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Existing Safety Limit Benchmark

= DNB Limit Statepoints Taken From Existing .

Safety Limits.

= Existing Design Power Distribution Employed Fdh = 1.62 Fz = 1.55 @ Midplane i

Deterministic Treatment of Uncertainties

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Existing Sequoyah Core Safety Limits Benchmark l Source: Tech Spec Figure 2.1-1 1

670.0 i

660.0 -

2400 psia j 650.0 --

2250 psia 1

640.0 --

630.0 -

2000 psia 620.0 --

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I P' h - 610.0 --

4 600.0 -

590.0 --

+ = DNB Limited Point 580.0 --

570.0 -

Data labels Reoresent (BWC e / DNBR, % Margin to 1.21 BWCMV Limit) 560.0 --

550.0  : l l l l l l  : l l l 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 1.1 1.2 Fraction of Rated Thermal Power Framatome Cogema Fuels

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Conclusions

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The BWCMV CHF correlation is an acceptable correlation for use in the thermal-hydraulic analysis of fuel designs having VANTAGE SH Spacer Grids,

1. For fuel assembly geometries without Intermediate Flow Mixers (IFMs),

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3.3 Hydraulic Flow Testing

! . A'peries of flow tests was performed, using a transportable flow i test rig (TFTR), to verify the compatibility between the Mark-BW fuel design and the Westinghouse VANTAGE SH resident design. The l TFTR is a " cold flow" loop, with typical test conditions l encompassing water flow rates,of ( ) gpm at pressures from ( ) psig and temperatures from ( ).

i Pressure drop testing was performed on individual fuel l assemblies, providing pressure drop characteristics.for the

VANTAGE SH fuel design, as well as for the Mark-BW.

! The TFTR was validated as a' viable source for determining fuel j assembly hydraulic characteristics in 1988, when, as part of the effort to license Mark-BW fuel for Duke Power Company's McGuire j and Catawba Plants and for P.h:tland General Electric Company's j

Trojan Plant, a preliminary eet of flow tests was performed to

{ qualify the TFTR and establish a benchmark for comparison to i later tests. .These tests were performed with the same Mark-BW ,

. prototype assembly that had been previously tested at the B&W j l Alliance Research Center, Alliance, Ohio, in the Control Rod- .

! Drive Line (CRDL) flow loop. The CRDL test spanned a wide range l

. of pressure, temperature, and flow conditions encompassing those  !

i that occur during reactor operation. Core thermal-hydraulic

! analysis models for the Mark-BW fuel assembly design, including j form loss coefficients for individual components, were developed

from the CRDL test results. The measurements obtained with the  !

TFTR demonstrated that the TFTR reproduces the CRDL results at ,

] comparable Reynolds numbers.

i For the current test program, the goal was to first verify loop

! performance and then to hydraulicly characterize the VANTAGE 5H fuel through a series of lift and pressure drop tests. [ ]

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t i Using the' measured pressure drops, form loss coefficients for the i- fuel assembly subcomponents were determined. These form loss

! coefficients were then incorporated into a LYNXT hydraulic model j which chowed that the total pressure drop of the Westinghouse i i VANTAGE SH design is approximately ( ) than that of the

Mark-BW. A plot of unrecoverable pressure drop versus axial l elevation for the two designs at typical in-reactor conditions is provided on Figure 3-2.

. -. -- - - . , ~ . . . . . . . . . ..-- .- . ._ . . - . . . . - . . . _ _ . .

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Summary of Ksy Points Discucced at 6/20/96 Msating j

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Axial Pressure Drop Variation Figure (Mark-BW Versus Vantage SH) i

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F Physical Differences Grid Height i

End Grid Mixing Grid Mark-BW l Vantage SH i

• Approximate Height based on FCF Inspection

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Figure 3-2 Mark-BW Versus Vantage 5H  !

Unrecoverable Pressure Drop Comparison  ;

FullCore Analysis 1 25.00 Vantage 5H Mark-BW 20.00 -

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2 15.00 -

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5.00 -

0.00 -  :  :  :  :  ;

0.0 20.0 40.0 60.0 80.0 100.0 120.0 140.0 160.0 180.0 Axial Location, in