ML20065A944
| ML20065A944 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 02/28/1994 |
| From: | Blair J, Gournelos D WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20065A937 | List: |
| References | |
| NUDOCS 9404010116 | |
| Download: ML20065A944 (15) | |
Text
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WOLF CREEK
' NUCLEAR OPERATING CORPORATION
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Core Operating Limits Report Revision 1
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WOLF CREEK GENERATING STATION CYCLE 7 CORE OPERATING LIMITS REPORT Revision 1 February 1994 j
Prepared by- /A/ l bemetrios T. Gourneios. j
()dfyTlBlair Reviewed by: 2 ___
Elliott W. Ja Rson f ;7 j Approved by: '['#;f) j W. B. Norton
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-,, Page 1 of 15 9404010116 940328 2 DR ADOCK 0500
, r Wolf Cronk G:ntrcting Station ;
- Cycle 7 l
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 1 KNF-17, REV.10/92 l
l Revision Log )
Page 1 of 1 ;
REVISION LOG l y p'h>
(For instructions See KP-1533) l l
TITLE: WOLF CREEK GENERATING STATION CYCLE 7 CORE OPERATING LIMITS REPORT l
Revision Date i No. Description of Revision Approved j 1 Revise Figure 2, page 8, to revise operating limits for February 1994 increased moderator temperature planned to uprate electrical j output.
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t, 4 4 WOLF CREEK
' NUCLEAR OPERATING CORPORATION
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Core Operating Limits Report Revision 1 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 o (x , y , z) 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor - F,(x , y) 3.9.1.b Refueling Boron Concentration Page 3 of 15
W6LF CREEK
' NUCLEAR OPERATING CORPORATION
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Core Operating Limits Report Revision 1 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.
The 300 PPM MTC Surveillance Limit is -32 pcm/deg F (all rods withdrawn, Rated Thermal Power condition).
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WOLF CREEK
' NUCLEAR OPERATING CORPORATION
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Core Operating Limits Report Revision 1 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)
The Control Bank Insertion Limits are specified in Figure 1.
Page 5 of 15
e W6LF CREEK
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report r ""'"'"
' Revision 1 (FULLY WITFORAWN )
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FIGURE 1 ROD BANK INSERTION LIMIT VERSUS THERMAL POWER-FOUR LOOP OPERATION Fully Withdrawn shall be the condition valere control rod s are at a position Wthin the interval of a 222 and 5 231 steps withdrawn.
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- r g Cycle 7
NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 1 2.4 Axial Flux Difference (AFD)
The indicated Axial Flux Difference (AFD) allowed operational space is defined by Figure 2.
Page 7 of 15
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WeLF CREEK ' NUCLEAR OPERATING CORPORATION
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Core Opera i Revision 1 110 ,
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UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION
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-30 -20 -10 0 10 20 30 FLUX DIFFERENCE (DELTA l} %
FIGURE 2 WOLF CREEK UNIT 1 AX1AL FLUX DIFFERENCE LIMITS AS A FUNCTION OF THERMAL POWER PAGE 8 OF 15
Wolf Crt:k G::n: rating Station
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 1 2.5 Heat Flux Hot Channel Factor - F o (x , y , z)
F"(x , y, z) s F;"
- K(z), frP > 0. 5 o
P F*(x,y,Z) 5 F;"
- K(z), frP s 0. 5 o
- 0. 5
=
THERMAL POWER e ere* P RATED THERMAL POWER Ff" = the Fo at RATED THERMAL POWER
= 2.50, and K(z) is defined in Figure 3.
See Appendix Afor:
- 1. [ Fo ( x , y , z ) f " , ( Fj ( x , y , z ) f' , and
( Fj ( x , y , z ) f"'
- 2. Op Mar NSLOPE and Op Mar PSLOPE
'E woir crack onnerating st: tion Y g Cycle 7
' ' NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 1 FmuRE3 M(Z). NORMALIZED PEAK!NO FACTOR VS. CORE HOOHT 1.2
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core HecHT (PT) j l
FQT=2.50 l Devadon (R) K(Z) 0.0 1.0 8.0 1.0 12.0 0 925 Page 10 of 15
g Wolf Crock G:n= rating Station Cg Cycle 7
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 1 2.6 Nuclear Enthalov Rise Hot Channel Factor -3yF (x , y)
F3y(x , y) shall be limited by the relationship FAHR" ( x , y ) s FAHR' ( x , y )
See Appendix A for array FAHR'(x , y).
(ACTIONS a, b)
See Appendix A for RRH (ACTION c)
See Appendix A for TRH (Tech Spec 4.2.3.2.b)
See Appendix A for array FAHR" "(x , y) l l
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- Wolf Crs:k G:n:rcting St: tion Q. -
Cycle 7
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 1 Definitions - FAHR (x , y )
Limit:
4 FAHR'(x , y) = MAP .h* ( x , y ), AX* ( x , y } } l AX* ( x , y ) MH(x , y )
where, I FD = Design F, for the assembly at location (x,y),
MAP = Design Maximum Allowable Peak at h (x , y) and AX (x , y),
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 ) = Minimurn available margin ratio at (x,y) i Measurement:
p^u FAHR" { x , y ) = MAP" [h" (x , y ), AX" ( x , y )} l AX"(x , y )
where, F"y = Measured F, for the assembly at location (x,y),
MAP" = Maximum Allowable Peak at h"(x , y) and AX"(x , y), l 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.
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t E Wolf Crook Gan rating Station g Cycle 7
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision'1 2.7 Refuelina Boron Concentration (Tech Spec 3.9.1.b)
The refueling boron concentration shall be greater than or equal to 2300 PPM.
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l E wolf Crack c:n::reting St:. tion !
Yg Cycle 7
! NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 1 APPENDIX A A. Input relating to Specification 4.2.2.2.d:
- 1. ( Fo ( x , y , z )f" Nominal design peaking
[ Fj ( x , y , z ) f" Operational design peaking limit
[ Fj ( x , y , z ) f"8 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
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- .' *5 Wolf Crsck Gan:r.* ting St tion
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 1 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.
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