ML20209E034

Provides NRC with Siemens Power Corp (SPC) Fuel & GE Fuel MCPR Data for LaSalle Unit 1 Cycle 9.LaSalle Unit 1 Is Currently Scheduled to Start Cycle 9 in 991101

ML20209E034
Person / Time
Site:	LaSalle
Issue date:	07/09/1999
From:	Jamie Benjamin COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9907140125
Download: ML20209E034 (7)

Text

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• Commonwc.ild i lison (Wim[uny i;tsalle Goncr.iting Station i 2601 North list Road

. Ma rscilles,11. 61,4 I N5" Tcl H j 445NC6I i

July 9,1999 United States Nuclear Regulatory Commission Attention: Document Control Desk l Washington, D.C. 20555  ;

1 LaSalle County Station, Units 1 and 2 l Facility Operating License Nos. NPF-11 and NPF-18 j NRC Docket Nos. 50-373 and 50-374  ;

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Subject:

ANFB Critical Power Correlation to Co-Resident GE Fuel LaSalle Unit 1 i

References:

(a) "ANFB Critical Power Correlation Applicatlon for Co- 1 Resident Fuel," EMF-1125(P)(A), Supplement 1, Appendix C, Siemens Power Corporation, August 1997.

(b) " Application of Siemen's Power Corporation ANFB Critical Power Corre!ation to Coresident General Electric Fuel for LaSalle Unit 2 Cycle 8," G.G. Benes to U.S.

NRC, dated March 8,1996 transmitting Application of the ANFB Critical Power Correlation to Coresident GE Fuel for LaSalle Unit 2 Cycle 8, EMF-96-021 (P),

Revision 1, February 1996.

(c) " Safety Evaluation for Topical Report EMF-96-021(P),

Revision 1, Application of the ANFB Critical Power Correlation to Coresident GE Fuel for LaSalle Unit 2 Cycle 8,' " D. M Skay to I. Johnson, dated September 26,1996. )/

(d) "ANFB Critical Power Correlation to Co-resident GE Fuel- Quad Cities, Unit 1 (TAC No. MA2478)," R. M.

Pulsifer to O. D. Kingsley, dated August 18,1998. o\

9907140125 990709 PDR ADOCK 05000373 P PDR I

A t'nkom Comtun) ,

h 1, -t July 9,1999

' U.S. Nuclear Regulatory Commission Page 2 In Reference (a), NRC Safety Evaluation Report (SER), it was stated that "a table comparing MCPR data throughout the first reload exposure must be sihmitted to the NRC to justify each plant application of ANFB critical power correlation to co-resident General Electric (GE) fuel." The purpose of this letter is to satisfy this condition by providing the NRC with the Siemens Power Corporation (SPC) fuel and GE fuel Minimum Critical Power Ratio

- (MCPR) data for LaSalle Unit 1 Cycle 9.

LaSalle Unit 1 Cycle 9 (L1C9) will be the first cycle with (SPC) ATRIUM-9B reload fuel in the core. The remainder of the core contains GE fuel. The

SPC ANFB critical power correlation will be used to determine the MCPR for both the SPC fuel and the co-resident GE fuel for that cycle. The NRC has previously generically approved the use of the SPC ANFB critical power correlation to determine the critical power of the co-resident GE fuel

[ Reference (a)].

Table 1 of Attachment A provides a comparison of the difference in MCPR between the fresh SPC fuel and the once bumed (or greater) co-resident GE fuel for the L1C9 licensing loading pattem. The MCPR for the SPC fuel is based on the ANFB correlation while the MCPR for the once bumed GE fuel is based on the GEXL correlation. This information is provided in the same form as previously provided on a cycle specific basis for LaSalle Unit 2 Cycle 8 [ References (b) and (c)). Attachments B and C (Figures 1 and 2)

. graphically present the information in Table 1. For comparison, the supportable MCPR safety limit of 1.11 is also presented in Figure 1.

With the exception of non-limiting conditions very early in the cycle, the fresh SPC fuel has a lower MCPR than the once bumed GE fuel and hence is more restrictive throughout the limiting portion of the cycle. This is especially true at end-of-cycle conditions where transients are generally most limiting (i.e.,- minimum margin to the safety limit). Therefore, consistent with the -

implementation clarifications and NRC concurrence on pages A-35/A-39 in

, the~ Attachment to Reference (a), applying the ANFB correlation to the co-resident GE fuel in L1C9 is justified. 1 I

. LaSalle Unit 1'is currently scheduled to start Cycle 9 in November,1999. l The NRC is requested to provide written confirmation by November 1,1999 )

- (in a form similar to that previously provided for Quad Cities Unit 1 Cycle 16 )

. in Reference (d)) that the attached information satisfies the condition of the  !

Reference (a) SER for application of the ANFB correlation to GE fuelin l LaSalle Unit 1 Cycle 9.

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e l July 9,1999 U.S. Nuclear Regulatory Commission  !

Page 3 ,

J Should you have any questions conceming this letter, please contact Mr. Frank A. Spangenberg Ill, Regulatory Assurance Manager, at (815) 357-6761, axtension 2383.

Respectfully,

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b

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Jeffrey A. Benjamin Site Vice President LaSailo County Station Attachment A Table 1 GE Fuel (GEXL) and SPC Fuel (ANFB) MCPR Data for LaSalle Unit 1 Cycle 9 Attachment B Figure 1 GE Fuel (GEXL) MCPR, SPC Fuel (ANFB)

MCPR, and Supportable MCPR Safety Limit Data for LaSalle Unit 1 Cycle 9 Attachment C Figure 2 Delta MCPH (GE Fuel (GEXL) MCPR minus SPC Fuel (ANFB) MCPR) for LaSalle Unit 1 Cycle 9 cc: Regional Administrator - NRC Region til NRC Senior Resident inspector - LaSalle County Station 1

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July 9,1999 l

. U.S. Nuclear Regulatory Commission Page 4 ATTACHMENT A TABLE 1 GE FUEL (GEXL) AND SPC FUEL (ANFB) MCPR DATA FOR LASALLE UNIT 1 CYCLE 9 (Page 1 of 2)

Exposure MCPR MCPR AMCPR GWd/MT GE Fuel SPC Fuel (GE - SPC) 0.00 1.793 1.806 -0.013 0.25 1.770 1.812 -0.042 1 0.50 1.736 1.814 -0.079 1

1.00 1.724 1.812 -0.089

{

1.50 1.740 1.808 -0.068

)

2.00 1.794 1.788 0.005 2.50 1.806 1.790 0.017 3.00 1.820 1.790 0.030 3.00 (swap) 1.837 1.767 0.070 3.50 1.854 1.771 0.083 4.00 1.894 1.794 0.101 4.50 1.935 1.816 0.119 5.00 1.975 1.832 0.143 l 5.00 1.839 1.710 0.129 1

5.50 1.880 1.730 0.150 6.00 1.928 1.736 0.191 6.00 (swap) 1.807 1.719 0.088 6.50 1.841 1.718 0.123 7.00 1.732 1.704 0.028 7.50 1.779 1.696 0.084 8.00 1.785 1.703 0.082 8.50 1.840 1.694 0.146 9.00 1.857 1.681 0.177 l

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l July 9,1999

, US. Nuclear Regulatory Commission Page 5 j

A1TACHMENT A TABLE 1 -

GE FUEL (GEXL) AND SPC FUEL (ANFB) MCPR DATA FOR LASALLE UNIT 1 CYCLE 9 (Page 2 of 2) 9.00 (swap) 1.911 1.702 0.209 9.50 1.920 1.681 0.239

.10.00 1.833 1.668 0.165 10.50 1.837 1.667 0.170 11.00 1.836 1.665 0.170 11.50 1.834 1.648 0.186 12.00 1.828 1.642 0.186 12.00 (swap) 1.987 1.580 0.408 12.50 1.986 1.573 0.413 13.00 1.982 1.569 0.413

'13.50 1.981 1.568 0.412 14.00 1.987 1.589 0.398 14.50 1.999 1.601 0.398 15.00 2.016 1.618 0.398 15.00 (swap) 2.027 1.614 0.413 15.50 2.047 1.634 0.414 16.00 2.060 1.645 0.415 ,

16.50 1.966 1.576 0.389 17.00 2.027 1.617 0.411 17.50 1.939 1.555 0.384 18.00 2.014 1.611 0.403 18.30 2.024 1.616 0.408 18.30 2.054 1.637 0.418 Notes: The last column represents how much MCPR m :rgin there is between the once bumed GE fuel and the fresh SPC fuel. A positive number in the last column means that the fresh SPC fuel is limiting at that exposure.

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c July 9,1999

. U,S. Nuclear Regulatory Commissior Page 6 ATTACHMENT B FIGURE 1 GE FUEL (GEXL) MCPR, SPC FUEL (ANFB) MCPR, AND SUPPORTABLE l MCPR SAFETY LIMIT DATA FOR LASALLE UNIT 1 CYCLE 9 (Page 1 of 1)

I L1C9 MCPR Vs Cycle Exposure

";)

2 ,,

... ,-.s 1.90 ,

' l!

.\

/ I,"l" ' '- i l 1.80 1 ,

1.70 e

% , -- e - GE Fuel

• 4 GEXL

{ 1.60 1.50

-*-- SPC Fuel 1.40 ANFB 1.30

-e-- Supportable 1.20 MCPR SL i 1.10 '

1.00 0 2 4 6 8 10 12 14 16 18 20 $

Cycle Exposure (Gwd/Mt)

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July 9,1999

. U:S. Nuclear Regulatory Commission "

Page 7 i

ATTACHMENT C  !

FIGURE 2 DELTA MCPR (GE FUEL (GEXL) MCPR MINUS SPC FUEL (ANFB) MCPR) ,

FOR LASALLE UNIT 1 CYCLE 9 I (Page 1 of 1) l I

L1C9 Delta MCPR Vs Cycle Exposure I 0.45 -

0.40 '

fk 4 0.35 0.30 0.25 I I

0.20 5 0.15 / ', )g *

.-+-Delta MCPR (GE-SPC) 0.10 - A O.05

/ "\r ' '

0.00 '

-0.05 -1 / l'

-0.10 0 2 4 6 8 10 12 14 16 18 20 Cycle Exposure (Gwd/Mt) l l

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