ML041470400

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Core Operating Limits Report
ML041470400
Person / Time
Site: Callaway Ameren icon.png
Issue date: 05/14/2004
From: Keith Young
AmerenUE
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ULNRC-05007
Download: ML041470400 (18)


Text

AmerenUE CallawayPlant PO Box 620 Fulton, MO 65251 May 14, 2004 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 Ladies and Gentlemen:

ULNRC-05007 WAmerien UFE CALLA 'WAY PLANT DOCKET NUMBER 50-483 CORE OPERATING LIMITS REPORT Attached is the Callaway Plant Cycle 14 Core Operating Limits Report (COLR),

Revision 1. Because the core was redesigned prior to fuel reload, Revision 0 of the COLR was never used. This report is provided to the NRC Staff for information. It has been prepared in accordance with the requirements of Technical Specification 5.6.5. If you have any questions concerning this report, please contact us.

Sincerely, Keith D. Young Manager, Regulatory Affairs DJW/jdg

Attachment:

Appendix A, Callaway Cycle 14 Core Operating Limits Report, Rev. I C~ I a subsidiary ofAmeren Corporation

ULNRC-05007 May 14, 2004 Page 2 cc:

U.S. Nuclear Regulatory Commission (Original and 1 copy)

Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 Mr. Bruce S. Mallett Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Jack N. Donohew (2 copies)

Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 7E1 Washington, DC 20555-2738 Missouri Public Service Commission Governor Office Building 200 Madison Street PO Box 360 Jefferson City, MO 65102-0360 Deputy Director Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102

Callaway Cycle 14 COLR Rev. I I

Appendix A CALLAWAY CYCLE 14 CORE OPERATING LIMITS REPORT (Revision 1)

I May 2004

Callaway Cycle 14 COLR Rev. I I

1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Callaway Plant Cycle 14 has been prepared in accordance with the requirements of Technical Specification 5.6.5.

The Core Operating Limits affecting the following Technical Specifications are included in this report.

3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8 Shutdown Margin 3.1.3 Moderator Temperature Coefficient 3.1.5 Shutdown Bank Insertion Limits 3.1.6 Control Bank Insertion Limits 3.2.1 Heat Flux Hot Channel Factor 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor 3.2.3 Axial Flux Difference 1

Callaway Cycle 14 COLR Rev. I I 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the subsections which follow. These limits have been developed using the NRC-approved methodologies specified in Technical Specification 5.6.5.

2.1 Shutdown Margin (Specifications 3.1.1, 3.1.4, 3.1.5, 3.1.6, and 3.1.8) 2.1.1 The Shutdown Margin in MODES 1-4 shall be greater than or equal to 1.3% Ak/k.

2.1.2 The Shutdown Margin in MODE 5 shall be greater than or equal to 1.0% Ak/k.

2.2 Moderator Temperature Coefficient (Specification 3.1.3) 2.2.1 The Moderator Temperature Coefficient shall be less positive than the limits shown in Figure 1. These limits shall be referred to as upper limit.

The Moderator Temperature Coefficient shall be less negative than -47.9 pcrn'F.

This limit shall be referred to as the lower limit.

2.2.2 The MTC 300 ppm surveillance limit is -40.4 pcmn!F (all rods withdrawn, Rated Thermal Power condition).

2.2.3 The MTC 60 ppm surveillance limit is -45.5 pcm/0F (all rods withdrawn, Rated Thermal Power condition).

2

Callaway Cycle 14 COLR Rev. 1 1

N 0

H U

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10 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER Figure 1 Callaway Cycle 14 Moderator Temperature Coefficient Versus Power Level 3

Callawvay Cycle 14 COLR Rev. I I 2.3 Shutdown Bank Insertion Limits (Specification 3.1.5)

The shutdown banks shall be withdrawn to at least 225 steps.

2.4 Control Bank Insertion Limits (Specification 3.1.6) 2.4.1 Control Bank insertion limits are specified by Figure 2.

2.4.2 Control Bank withdrawal sequence is A-B-C-D. The insertion sequence is the reverse of the withdrawal sequence.

2.4.3 The difference between each sequential Control Bank position is 115 steps when not fully inserted and not fully withdrawn.

4

Callaway Cycle 14 COLR 2251 1 1 1 i I I I I Rev.I I

X (28, 225)

V. (78,225) L I

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I 10 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER Figure 2 Callaway Cycle 14 Rod Bank Insertion Limits Versus Rated Thermal Power - Four Loop Operation 5

Callawvay Cycle 14 COLR Rev. I I 2.5 Heat Flux Hot Channel Factor - FQ(Z)

(Specification 3.2.1)

FQRTP FQ(Z) <

  • K(Z) for P > 0.5 p

FQRTl FQ(Z) <

  • K(Z) for P < 0.5 0.5 THERMAL POWER where:

P =

RATED THERMAL POWER 2.5.1 FQRTr = 2.45 for all Cycle 14 burnups less than 8000 MWD/MTU, and FQRTh = 2.50 for all Cycle 14 burnups greater than or equal to 8000 MWD/MTU.

2.5.2 K(Z) is provided in Figure 3.

2.5.3 The W(z) functions that are to be used in Technical Specification 3.2.1 and Surveillance Requirement 3.2.1.2 for determining FQ"'(z) are shown in Figures 4 through 8.

The W(z) values have been determined for several bumups up to 18000 MWD/MTU in Cycle 14. This permits determination of W(z) at any cycle burnup up to 18000 MWD/MTU through the use of three point interpolation. For cycle burnups greater than 18000 MWD/MTU, use of 18000 MWDIMTU W(z) values without interpolation or extrapolation is conservative.

The W(z) values were determined assuming Cycle 14 operates with RAOC strategy. Also included is a W(z) function that bounds the W(z) Curve for all Cycle 14 burnups. Use of the bounding W(z) curve will be conservative for any Cycle 14 burnup; however, additional margin may be gained by using the bumup dependent W(z) values.

The W(z) values are provided for 73 axial points within the core height boundaries of 0 and 12 feet at intervals of 0.167 feet.

Table A.1 shows the burnup dependent FQ penalty factors for Cycle 14. These values shall be used to increase FQW(z) when required by Technical Specification Surveillance Requirement 3.2.1.2. A 2% penalty factor should be used at all cycle bumups that are outside the range of Table A. 1.

6

Callaway Cycle 14 COLR Rev. I I TABLE A.I FQ PENALTY FACTORS AS A FUNCTION OF CYCLE BURNUP Cycle 14 Bumup All Cycle 14 Burnups FW(Z Penalty Factor (%)

2.00 7

Callaway Cycle 14 COLR Rev: I I

1.20 1.10

, 1.1 1.00 0.90 7

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1 l l.

2,

.924) 1 I N. 0.80 CY N 0.70 H

0 0.60 BOL until 8K Burnup FQ 2.45 2.45 2.26 Elevation 0.0 ft.

6.0 ft.

12.0 ft.

K(z) 1.00 1.00 0.924 0.5 N

I I

-H+H+H-H+/-HA111f-H-4 0.401

.1 8K Burnup until EOC 0.3 I I FQ 2.50 2.50 2.31 Elevation 0.0 ft.

6.0 ft.

12.0 ft.

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1 2

3 4

5 6

7 8

9 10 11 12 CORE HEIGHT (FEET)

Figure 3 Callaway Cycle 14 K(z) - Normalized FQ(z)

As a Function of Core Height 8

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HEIGHT (FEET) 0.000 0.167 0.333 0.500 0.667 0.833 1.000 1.167 1.333 1.500 1.667 1.833 2.000 2.167 2.333 2.500 2.667 2.833 3.000 3.167 3.333 3.500 3.6 67 3.833 4.000 4.167 4.333

4. 500 4.667 4.833 5.000 5.167 5.333 5.500 5.667 5.833
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  • Top and bottom 15% excluded as per Tech Spec SR 3.2.1.2 9

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CORE HEIGHT (FEET) 10 11 12 TOP Figure 5 Callaway Cycle 14 W(z) at 4000 MWDIMTU

'Top and bottom 15% excluded as per Tech Spec SR 3.2.1.2 10

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Figure 6 T,

Callaway Cycle 14 W(z) at 10000 MWDIMTU

  • Top and bottom 15% excluded as per Tech Spec SR 3.2.1.2 1

1

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W(z)

1. 0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.3164 1.3 04 1 1.2914 1.2785 1.2654 1.2519 1.23 8 5 1.2292 1.2254 1.22 65 1.2316 1.2412 1.2491 1.2558
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1. 2798 1.2861 1.2984 1.3147
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1. 3 562
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Figure 7 Callaway Cycle 14 W(z) at 18000 MWDIMTU

  • Top and bottom 15% excluded as per Tech Spec SR 3.2.1.2 12

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8. 500 8.667 8.833 9.000 9.167 9.333 9.500 9.667 9.833
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  • 11.833
  • 12.000 MAX W(z) 1.o0000 1.o0000 1.o0000 1.0000
1. 0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.3877 1.3636 1.3398 1.3183 1.2995 1.2832
1. 2703 1.2643 1.2635 1.2617 1.2585 1.2560 1.2544 1.2558 1.2622 1.2684 1.2737 1.2776 1.2799 1.2809 1.2799 1.2767 1.2762 1.2798 1.2861 1.2984 1.3147 1.3280 1.3388 1.3475 1.3537 1.3575 1.3584 1.3562
1. 3534
1. 3505 1.3451 1.3391 1.333 9 1.3322 1.3303 1.3276 1.3283 1.3311 1.33 63 1.34 67 1.3587 1.3705 1.3855 1.4079 1.436 6 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
1. 0000 1.o0000 1.o0000 1.0000 1.o0000 1.

I.

I I.

I I.

I I 1

I 1

I.

. II 1 1 1 1

1..

I I I.

I I

I I.I I I 1

I.

I I I 1

1 I

I.

1.20 1.10 I I I I I I I I IIII II I

I I

I II II I

I I

I I I

I I

I II I

I l

l l

l l

l l

f I

I l

l I

l l

l l

l f

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11 1

. I 1.1111 1.

v 0

BOTTOM 1

2 3

4 5

6 7

8 9

CORE HEIGHT (FEET)

Figure 8 10 11 I

TO]

Callaway Cycle 14 Bounding W(z)

' Top and bottom 15% excluded as per Tech Spec SR 3.2.1.2 13

Callaway Cycle 14 COLR Rev. I I 2.6 Nuclear Enthalpy Rise Hot Channel Factor - F&,N (Specification 3.2.2)

FaiN < FMIRTP [I + PFAII(l-P)]

THERMAL POWER where:

P =

RATED THERMAL POWER 2.6.1 F ARTP = 1.59 2.6.2 PFAII = 0.3 2.7 Axial Flux Difference (Specification 3.2.3)

The Axial Flux Difference (AFD) Limits are provided in Figure 9.

14

Callaway Cycle 14 COLR Rlev. 1 l 120 110 I

1(-17, J

4

%) L

(+13, lOC P4 0

P4 10 vvrrrI l I I 1 7 1

-- f-

_ UNACCEPTABLE 90 o OPERATION 3UNACCEPTABLE OPERATION Nil ACCEPTABLE [

j OPERATION [

701 bI II I I I I I I I 5I I0 I

I I

I I I I I I I 1 I I I I I I I I 1 I I

_o 77 Ir67 /

I I I

^

I I rr § 17 1 §r

§§ r

r7 r-l

_ _ lT I

IT 11-1

(+26lI ttl{,

5096) [_

401 41I 20 10 U-5

-50

-40

-30

-20

-10 0

10 20 30 40 50 AXIAL FLUX DIFFERENCE (% DELTA-I)

Figure 9 Callaway Cycle 14 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC 15