ML20035E813

Rev 0 to Wolf Creek Generating Station Cycle 7 Colr

ML20035E813
Person / Time
Site:	Wolf Creek
Issue date:	03/31/1993
From:	Blair J, Gournelos D, Rathbun G WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20035E812	List: ML20035E811 ML20035E813
References
NUDOCS 9304190278
Download: ML20035E813 (14)

Text

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Attachment t ET 93-0046 Wolf Cre:k G:n:rtting Station Cycia 7 NUCLEAR OPERATING CORPORATION Core Operating Limits Report j

l Revision 0 i

E M

.7 WOLF CREEK GENERATING STATION CYCLE 7 CORE OPERATING LIMITS REPORT Revision 0 March 1993 i

i Prepared by:

Derlietrios T. Gournelos l

l Ff Jpff T/ Blair Reviewed by:

4 4 /\\

Elliot W. Jackson Approved by:

h Y

b G. P. Rathbun 4

Page 1 of 14 W22882 888:a P

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Wrif Crock G:n:rcting Stctirn Cycla 7 UCLEAR OPERATING CORPORATION Core Operating Limits R: port Revision 0 1.0 CORE OPERATING LIMITS REPORT The CORE OPERATING LIMITS REPORT (COLR) for Wolf Creek Generating Station Cycle 7 has been prepared in accordance with the requirements of Technical Specification 6.9.1.9.

The core operating limits that are included in the COLR affect the following Technical Specifications:

3.1.1.3.b Moderator Temperature Coefficient (MTC) EOL Limit 3.1.3.5 Shutdown Rod insertion Limit 3.1.3.6 Control Rod Insertion Limit 3.2.1 Axial Flux Difference (AFD) 3.2.2 Heat Flux Hot Channel Factor - F,(x, y, z )

3.2.3 Nuclear Enthalpy Rise Hot Channel Factor - F,(x, y) 3.9.1.b Refueling Boron Concentration F

Page 2 of 14

W:lf Cre:k G:n:rcting St-ti:n Cycia 7 NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 0 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the subsections below:

2.1 Moderator Temperature Coefficient (MTC) EOL Limit (Tech Spec 3.1.1.3.b)

The EOL MTC shall be less negative than -41 pcm/deg F.

(Tech Spec 4.1.1.3.b)

The 300 PPM MTC Surveillance Limit is -32 pcm/deg F (all rods withdrawn, Rated Thermal Power conditio'1).

Page 3 of 14

CREEK Welf Cr00k G:n:rcting Station Cycla 7 NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 0 2.2 Shutdown Rod insertion Limit (Tech Spec 3.1.3.5)

]

The shutdown rods shall be fully withdrawn, as defined in Figure 1.

2.3 Control Rod Insertion Limits (Tech Spec 3.1.3.6) i l

The Control Bank insertion Limits are specified in Figure 1.

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i Page 4 of 14

W lf Cre:k G:ncrc. ting St:ticn Cycia 7 NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 0 (FLN.LY WmCRAWN )

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20 40 60 80 100 RELATNE POWER (Percent)

(FLLLY INSERTED)

FIGURE 1 ROD BANK INSERTON UWT VERSUS THERMAL POWER-FOUR LOOP OPERATION Fully VIAthdrawn shaN be he condition wemre control rods are at a peaition within the interval of g 222 and 5 231 stape withdrawn.

1 Page 5 of 14 l

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Wolf Cro;k G:n:rcting St tien Cycla 7 NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 0 2.4 Axial Flux Difference (AFD)

(Tech Spec 3.2.1)

The indicated Axial Flux Difference (AFD) allowed operational space is defined by Figure 2.

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l Page 6 of 14

CREEK Wclf Cro:k G:n:rcting Stctirn i

Cycia 7 NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 0 110

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(a,100) 100 umccEPTABLE UNACCEPTABLE OPERATM OPERATM 90 l

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10 20 30 FLUX DIFFERENCE (DELTA I) %

FIGURE 2 WOLF CREEK UNIT 1 AX1AL FLUX DIFFERENCE LINTS AS A FUNCTION OF RATED THERMAL POWER Page 7 of 14 l

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Wrif Cre:k G:n:rcting Stctirn l

Cycl 37 l

UCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 0 2.5 Heat Flux Hot Channel Factor - F,(x, y, z)

(Tech Spec 3.2.2) paw Fj"( x, y, z ) s

• K(z),

for P

0. 5 g

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F;* ( x, y, z ) s

• K(z),

for P s

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THERMAL POWER RATED THERMAL POWER F,""

= the F, at RATED THERMAL POWER

= 2.50, and K(z) is defined in Figure 3.

(Tech Spec 4.2.2.2.d)

See Appendix A for j

1.

[ F,( x, y, z )f*", ( Fj (x, y, z )f', and

[ Fj (x, y, z ) f'*

2.

Op Mar NSLOPE and Op Mar PSLOPE 3.

RPS Mar NSLOPE and RPS Mar PSLOPE

\\

Page 8 of 14

Wolf Creek G:n:rcting St tien NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 0 i

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Page 9 of 14 1

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i Wolf Cro:k G:n:rcting Stcticn Cycla 7 i

NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 0 1

)

2.6 Nuclear Enthalov Rise Hot Channel Factor - F,(x, y)

I (Tech Spec 3.2.3)

F,(x, y) shall be limited by the relationship FAHR"( x, y ) s FAHR'( x, y )

See Appendix A for array FAHR'(x, y).

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(ACTIONS a, b) l See Appendix A for RRH (ACTION c)

See Appendix A for TRH l

(Tech Spec 4.2.3 2.b)

See Appendix A for array FAHR" "(x, y) 1 A

Page 10 of 14

Wclf Creek G:n:rcting St-tirn Cycb 7 Core Operating Limits Report UCLEAR OPERATING CORPORATION Revision 0 Definitions - FAHR (x, y)

Limit:

F^"

1 FAHR' (x, y) = MAP *. * ( x, y ), AX* ( x, y )

/ AX* ( x, y )

MH(x, y) h

where, F

= Design F, for the assembly at location (x,y),

MAP

= Design Maximum Allowable Peak at h (x, y) and AX (x, y),

D h (x, y)

= Axial location of the design axial power peak at (x,y),

AX (x, y) = Ratio of the peak to average axial power at (x,y) for the design power distribution, and MH(x,y)

= Minimum available margin ratio at (x,y)

Measurement:

F^""

FAHR"(x, y) = MAP"[h"(x, y), AX"(x, y / AX"(x, y)

where, F"

= Measured F, for the assembly at location (x,y), MAP" = Maximum Allowable Peak at h"(x, y) and AX"(x, y), h"(x, y) = Axial location of the measured axial power peak at (x,y), and AX"(x,y) = Ratio of the peak to average axial power at (x,y) for the measured power distribution. Page 11 of 14

Wclf Crc:k G:n:rcting Stction Cycla 7 NUCLEAR OPERATING CORPORATION Core Operating Limits Report i l Revision 0 2.7 Refuelina Boron Concentration (Tech Spec 3.9.1.b) The refueling boron concentration shall be greater than or equal to 2300 PPM. i l t t t i Page 12 of 14

Wolf Creek G:n:rcting Station Cycia 7 NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 0 APPENDIX A l A. Input relating to Specification 4.2.2.2.d. J l 1. [ F ( x, y, z )f" - Nominal design peaking o [Fj (x, y, z )f

Operational design peaking limit

[Ff(x, y, z)f"

Reactor Protection Setpoint (RPS) design peaking limit.

These are a large number of large arrays. They are issued in a controlled report which will be provided on request. The design peaking limits include all uncertainties. 2. Op Mar NSLOPE = 1.5% / % margin Op Mar PSLOPE = 2.0% / % margin 3. RPS Mar NSLOPE = 1.32% / % margin RPS Mar PSLOPE = 2.82% / % margin Page 13 of 14

~ W;lf Creek G:n rcting Stntien Cycb 7 l NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 0 APPENDIX A (Continued) B. Input relating to Specification 3.2.3: 1. FAHR' (x, y )

The maximum allowable radial peak ratio These are a large number of large arrays. They are issued in a controlled report which will be provided on request.

The design peaking limits include all uncertainties. 2. RRH = 3.33 3. TRH = 0.038 C. Input relating to Specification 4.2.3.2.b: 1. FAHR * " ( x, y )

Nominal design radial peak ratio These are a large number of large arrays. They are issued in a controlled report which will be provided on request.

Page 14 of 14}}