ML20111B321
| ML20111B321 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 02/29/1996 |
| From: | Blair J, Flannigan R, Kennamore P WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20111B313 | List: |
| References | |
| NUDOCS 9605140327 | |
| Download: ML20111B321 (14) | |
Text
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. l Wolf Creek G2nerating Station r
CREEK
' NUCLEAR OPERATING CORPORATION Cycle 9 Core Opemti g Limits Report i
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! f b WOLF CREEK GENERATING STATION l CYCLE 9 !
! CORE OPERATING LIMITS REPORT
! Revision 0 l t ,
j February 29,1996 I i
Prepared by:
l MfyT. Beir Reviewed by:
i Pete Kennamore Approved by: _
R. D. Flannigan //
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' 9605140327 960509 PDR ADOCK 05000402
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Wolf Creek Generating Station
. Cycle 9
' NUCLEAR OPERATING CORPORATION Core Operadng Limits Report Revision 0 1.0 CORE OPERATING LIMITS REPORT The CORE OPERATING LIMITS REPORT (COLR) for Wolf Creek Generating Station Cycle 9 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:
j 3.1.1.3.b Moderator Temperature Coefficient (MTC) EOL Limit I 3.1.3.5 Shutdown Rod Insertion Limit l 3.1.3.6 Control Rod Insertion Limit 3.2.1 Axial Flux Difference (AFD) 1 3.2.2 Heat Flux Hot Channel Factor- Fg (Z)
J i 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor - F5 !
3.9.1.b Refueling Boron Concentration 1
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Wolf Creek Generating Station v
F CREEK
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report Cycle 9 4
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 -50 pcm/deg F.
The 300 PPM MTC Surveillance Limit is -41 pcm/deg F~(all rods withdrawn, Rated Thermal Power condition).
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Welf Creek GInerating Station we Cycle 9
' NUCLEAR OPERATING CORPORATION Core Ope g m Repod 4
- 2.2 Shutdown Rod Insertion Limit ;
The shutdown rods shall be fully withdrawn, as defined in Figure 1.
l 2.3 Control Rod Insertion Limits (Tech Spec 3.1.3.6)
The Control Bank Insertion Limits are specified in Figure 1.
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Wolf Creek Generating Station w -
Cycle 9
' Core Operating Limits Report
' NUCLEAR OPERATING CORPORATION Revision 0
, (FULLY WITHDRAWN )
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RATED THERMAL POWER (Percent)
FIGURE 1 ROD BANK lNSERTION LIMIT VERSUS l THERMAL POWER.FOUR LOOP OPERATION l Funy Withdrawn shall be the condition where control rods are at a position within the iriterval of
,1222 and 1231 steps withdrawn.
Page 5 of 14
Wolf Creek Generating Station v
CREEK
' NUCLEAR OPERATING CORPORADON Cycle 9 Core Operati g Limits Report 2.4 Axial Flux Difference :(AFD)
The indicated Axial Flux Difference (AFD) allowed operational space is defined by Figure 2.
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l Wolf Creek Generating Station v
CREEK
' NUCLEAR OPERATING CORPORATION Cycle 9 ore OpeMng Um Repod Revision 0 110
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90 E -
/
8 IL J 80 -
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E ACCEPTABLE o,,,,,,
h 70 2i -
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60
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50
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( as,so cu.so i i i i i 4g 30 -20 -10 0 10 20 30 FLUX DIFFERENCE (DELTA I)%
FIGURE 2 WOLF CREEK UNTT 1 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER Page 7 of 14
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,.. i W:lf Creek G:ner: ting Staticn v
CREEK
' NUCLEAR OPERATING CORPORATION Cycle 9 ore Opera ng m Repon 1
1 2.5 Heat Flux Hot Channel Factor- Fo(Z)
(Tech Spec 3.2.2) pm Fg (Z)s A
- K(Z), for P > 0.5 f
pm Fo (Z)s 03 K(Z), frPs0.5 THERMAL POWER RATED THERMAL POWER '
F,""' = the Fg(Z) Limit at RATED THERMAL POWER (RTP)
= 2.50, and i
K(2) is defined in Figure 3.
Fj" Ff(Z) s p
. (K(Z)] for P > 0.5
. I F
F7(Z) s
.W(Z) l" (0.5])[K(Z)] I W(Z) = Ratio of the Fo from normal operation transients to the Fo at steady state conditions l
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l Wclf Creek G:ntrating Station CREEK UCLEAR OPERATING CORPORATION Cycle 9 Core Operating Limits Report Revision 0 (Tech Spec 4.2.2.2.e.1)
With measurements indicating r.,aximum Ff(Z)'
over z sK(Z)s has increased since the previous determination of F7(Z),
F7(Z) shall be increased over that specified in 4.2.2.2.c by an appropriate factor, the Fg Penalty Factor.
See Appendix A for.
- 1. W(Z) i
- 1. FgPenalty Factor 1
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Wolf Creek Generating Station o
LF CREEK
' NUCLEAR OPERATING CORPORATION Cycle 9 Core Operating Limits Report '
Revision 0 4
FIGURE 3
! K(Z)-NORMALIZED PEAKING FACTOR VS. CORE HEIGHT l i 1.2 )
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E FQT=2.50 E -"
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O 0.2
- EW W 4
g 0.0 1.0 8.0 1.0 12.0 0.925
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0 O 2 4 6 8 10 12 CORE HEIGHT (PT) l Page 10 of 14 I
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W lf Cr2ck G:n:rcting Stati:n o Cycle 9
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report
- 2,6 Nuclear Enthalov Rise Hot Channel Factor- F5 (Tech Spec 3.2.3)
- FL shall be limited by the following relationship:
- F$ s Ff(1.0 + Pfa.(1.0- P))
Where, F5" = The F5 limit at RATED THERMAL POWER (RTP)
= 1.59 PF, = the power factor multiplier for F5
= 0.3
'IIIERMAL POWER P _
RATED THERMAL POWER FL = Measured values of FE obtained by using the movable incore detectors to obtain a power distribution map. The measured values of FL shall be used since an uncertainty of 4% for incore measurement of FL has been included in the above limit.
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W lf Creek G:n:rcting Stati:n CREEIK
' NUCLEAR OPERAT1NG CORPORATION Cycle 9 Core Operating Limits Report Revision 0 i
2.7 Refuelina Boron Concentration (Tech Spec 3.9.1.b)
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Wsif Creek G:nerating Stati:n v
F CRE
' NUCLEAR OPERAT1NG CORPORATION Cycle 9 Core Operati g Limits Report APPENDIX A 1
A. Input relating to Specification 4.2.2.2.c:
1 F
, W(Z) = o(Z)** e, '""~'
These values are issued in a controlled report which will be provided on request.
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Input relating to Specification 4.2.2.2.e.1 Cycle Bumup Ff(Z) Penalty Factor o 2.00 21400 2.00 Note: All cycle bumups outside of the above table shall use a 2% penalty factor for compliance with 4.2.2.2.e Surveillance Requirement.
Linear interpo ation should be used for intermediate cycle burnups.
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. -- W:lf Creek G:nerating Station L
' NUCLEAR OPERATING CORPORATION Cycle 9 Core Operating Limits Report l
Revision 0 Technical Specification BASES 3/4.2.5 Cycle 9 Safety Analysis DNB Limit 1.76 WRB-2 Design Limit DNBR 1.23 d
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