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) | |
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Wolf Creek G2nerating Station CREEK Cycle 9 r
' NUCLEAR OPERATING CORPORATION Core Opemti g Limits Report i
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WOLF CREEK GENERATING STATION l
CYCLE 9 CORE OPERATING LIMITS REPORT Revision 0 t
j February 29,1996 i
Prepared by:
l MfyT. Beir Reviewed by:
i Pete Kennamore Approved by:
R. D. Flannigan //
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0 9605140327 960509 PDR ADOCK 05000402 P
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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 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 (Z) g J
i 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor - F5 3.9.1.b Refueling Boron Concentration Page 2 of 14
F CREEK Wolf Creek Generating Station Cycle 9 v
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 0 4
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The 300 PPM MTC Surveillance Limit is -41 pcm/deg F~(all rods withdrawn, Rated Thermal Power condition).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 Cycle 9 we
' NUCLEAR OPERATING CORPORATION Core Ope g
m Repod 4
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The shutdown rods shall be fully withdrawn, as defined in Figure 1.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.
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Wolf Creek Generating Station w
Cycle 9
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report 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 Funy Withdrawn shall be the condition where control rods are at a position within the iriterval of
,1222 and 1231 steps withdrawn.
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Wolf Creek Generating Station CREEK Cycle 9 v
' NUCLEAR OPERATING CORPORADON 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 CREEK Wolf Creek Generating Station Cycle 9 v
' NUCLEAR OPERATING CORPORATION ore OpeMng Um Repod Revision 0 110
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8 IL J 80
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ACCEPTABLE h 70 o,,,,,,
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-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
i W:lf Creek G:ner: ting Staticn CREEK Cycle 9 v
' NUCLEAR OPERATING CORPORATION ore Opera ng m
Repon 1
2.5 Heat Flux Hot Channel Factor-Fo(Z)
(Tech Spec 3.2.2) pm F (Z)s A
- K(Z), for P > 0.5 g
f pm F (Z)s K(Z), frPs0.5 o
03 THERMAL POWER RATED THERMAL POWER '
F,""'
the F (Z) Limit at RATED THERMAL POWER (RTP)
=
g 2.50, and
=
K(2) is defined in Figure 3.
Ff(Z) s
. (K(Z)] for P > 0.5 Fj" p
F7(Z) s. l" )[K(Z)]
F W(Z) (0.5]
W(Z)
Ratio of the Fo from normal operation transients to the Fo at
=
steady state conditions Page 8 of 14
f Wclf Creek G:ntrating Station CREEK Cycle 9 Core Operating Limits Report UCLEAR OPERATING CORPORATION 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 F Penalty Factor.
g See Appendix A for.
1.
W(Z) i 1.
F Penalty Factor g
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i Wolf Creek Generating Station LF CREEK o
Cycle 9
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report '
Revision 0 4
FIGURE 3 K(Z)-NORMALIZED PEAKING FACTOR VS. CORE HEIGHT i
1.2
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g 3
O g-04u. 9,g
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-u.
O Z
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h0.6
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- "+"
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d 0.4
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E FQT=2.50 E
4 "i -
O 0.2 EW W g
0.0 1.0 8.0 1.0 12.0 0.925 i
0 O
2 4
6 8
10 12 CORE HEIGHT (PT)
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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 + Pf.(1.0- P))
a
- Where, F5"
= The F5 limit at RATED THERMAL POWER (RTP) 1.59
=
PF,
= the power factor multiplier for F5
= 0.3 P _
'IIIERMAL POWER 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 Cycle 9
' NUCLEAR OPERAT1NG CORPORATION Core Operating Limits Report Revision 0 i
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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Wsif Creek G:nerating Stati:n F CRE Cycle 9 v
' NUCLEAR OPERAT1NG CORPORATION Core Operati g Limits Report APPENDIX A 1
A.
Input relating to Specification 4.2.2.2.c:
1 W(Z) = o(Z)** '""~'
F 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
Cycle 9
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report 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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