ML20203F542
| ML20203F542 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 11/14/1997 |
| From: | Flannigan R, Kennamore P, Morris M WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20203F516 | List: |
| References | |
| NUDOCS 9712170407 | |
| Download: ML20203F542 (14) | |
Text
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Wolf Creek Generating *!,w+ 'n Cycle 10 Com Opemung Limik R pod NOCEAR OPERATING CORPORATION Revisic.1 1
4 I
WOLF CREEK GENERATING STATION CYCLE 10 CORE OPERATING LIMITS REPORT Revision 1 November 14,1997 Prepared by:
[
Nighew K. Morrig' Reviewed by:
7 Pete Kennamore Approved by:
Mk,mus R. D. Flannid6n DR D
KO O 82 P
pm Page 1 of 14
Wolf Creek C:ncrating Station i
Cycb 10 Core Ope ting Lin its Report NUCLEAR OPERATING CORPORADON 1.0 CORE OFERATING LIMITS Rt' ' ORT The CORE OPERATING L!MIT3 REPORT (COLR) for Wolf Creek Generating Station Cycle 10 has beon preptwed in accordance with the requirements of Technical Specification t.9.1.9.
The core operating limits that are included in the COLR affect the following Technic il Specifications:
3.1.1.3.b Moderat 3r Temperature Coefficient (MTC) EOL Limit 3.1.3.5 Shutdown Rod insert!on Limit 3.1.3.6 Control Rod Insertion Limit 3.2.1 Axial Flux Difference (AFD) f 3.2.2 Heat Flux Hot Channel Factor-F (Z) e 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor - F" 3.9.1.b Refueling Boron Concentration Page 2 of 14
Wolf Creek Generating Station F CREEK c-4e Com Opem ng L mik Repod UCLEAR OPERATING CORPORATION 4
2.0 OPERATING hlMI'/G 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The 300 PPM MTC Surveillanco Limit is -41 pcm/deg F (all rods withdrawn, Rated Thermal Power condition).
Page 3 of 14
Wolf Creek C n: rating Stati:n Cycle 10 Core Operating Limits Report NUCLEAR OPERATING CORPORATION 2.2 Shutdown Rod Insertion Limit (Tech Spec 3.1.3.5)
The shutdown rods shall be fully withdrawn (i.e., positioned within the interval of > 222 and < 231 steps withdrawn).
2.3 Control Rod Insertion Limits (Tech Spec 3.1.3.6)
The Control Bank Insertion Limits are specified in Figure 1.
l Page 4 of 14 4
W:!f Creek Generating Stati:n e
Cy:b io Core Operating Limits Report NUCLEAR OPERATING CORPORATION Revision 1 (PULLY WITHDR AW N) hiY%Tf2Yf' 220
[28;7%" 2121~
^
..l...
.. +. - -. -
200
-+- --
= - -
. - =. --
SANK
.2..
9 3...,
i-i-180
~*-t..
s
+
+
..j..
. 3..
(100%.161 )
-i- -i-1608 w.; 3 g ry, S
. a...-
T E 140 P
..B A N K :.. -.... -..
- g..
120 l
.4..
T H 100 D
..e.
A 80 W
B AN K:
N g-60
' 0%.46) t 20 4
( 3 0.2%. 0 ) -
0 0
20 40 60 80 100 (MLLY INSERTED)
R ATED THERM AL POWER (Percent)
Figure 1 Rod Bank Insertion Limits Versus Thermal Power-Four Loop Operation FefWithdrawn shall be the condition where control rods are at a positen within the interval of 2 222 and s 231 steps withdrawn.
Page 5 of 14
Wolf Creek Generating Stati:n c
Cycle 10 A
Core Operati g Limits Report NUCLEAR OPERATING CORPORATION 2.4 Axial Flux Difference (AFD)
The indicated Axial Flux Difference (AFD) allowed operational space is defined by Figure 2, Page 6 of 14
Wolf Creek Generating Station Cycle 10 Core Opemung Limik Repod NUCM 'ct OPERATING CORPORATION Revision 1 110 t is.ioo t ca $ee n
_ UNACCEPTABLE UNACCEPTABLE OP E R ATIO N O P E R ATION g
O F
90 R
A T
E 0 80 T
ACCEPTABLE q
O PE R ATIO N R 70 M
A L
P 60 W
E R
50
(.as, so i g a4,so 3 40 40 30 20
-10 0
10 20 30 40 AXlAL FLUX DIFFERENCE (DELTA l} %
Figure 2 Axial Flux Difference Limits as a Function of Rated Thermal Power Page 7 of 14 m
W$LF CREEK Wolf Creek Generating Station cs' -
Core Opemti g Limits Report NUCLEAR OPERATING CORPORATION 2.5 Heat Flux Hot Channel Factor - Fo(Z)
F" g
F (2)s
- K(2), for P > 0.5 g
p pm F (2)s
- K(2), for P 5 0.5 g
03 THERMAL POWER em' P
=
RATED THERMAL POWER '
the F (2) Limit at RATED THERMAL POWER (RTP)
F""'
=
g o
2.50, and
=
K(2) is defined in Figure 3.
(Tech Spec 4.2.2.2.c) l i
i Fl"
[K(Z)]
for P > 0.5 F7(Z) s p
Fl" (K(Z)] forP s 0.5 F7(Z)s l
l Ratio of the Fo from normal operation transients to the Fo at W(Z)
=
steady state conditions Page 8 of 14
r Wolf Creek Generating Station Cy:le 10
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 1 (Tech Spec 4.2.2.2.e.1)
Wdh measurements indicating maximum
'Ff(Z)'
NZ sK(7)s has increased since the previous determination of Ff(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) 1.
F Penalty Factor g
l l
l Page 9 of 14
Wolf Creek G:nerating Station i
Cycle 10 Core Operating 1.imits Report NUCLEAR OPERATING CORPORATION Revision 1 1.2 h 1.0 a-5 u
.8 i
i-i-
+
0 4b-i ht 0.6 bA O
- 0.4 4-h Fa' = 2.6 0 E00.2 ei.v.tlon (ft)
K(Z) t l
2 0.0 1.000 l
6.0 1.000 12.0 0.926 i
0.0 0
2 4
6 8
10 12 CORE HEIGHT (FT)
Figure 3 K(Z)- Normalized Peaking Factor Vs. Core Height l
l Page 10 of 14 l
l l
t
W;lf Creek G:nerating Stati:n Cycl]10 Core O ng m
.9e#
NUCLEAR OPERATING CORPORATION 2.6 Nuclear Enthalpy Rise Hot Channel Factor - F5 (Tech Spec 3.2.3)
F& shall be limited by the following relationship:
F5sF$" 'l.0 + PF,(1.0 - P)
- Where, F&"
= The FA limit at RATED THERMAL POWER (RTP) 1.59
=
PF,
= the power factor multiplier for F$
= 0.3 THERMAL POWER l
P
=
RATED THERMAL POWER FL = Measured values of FL obtained by using the movable incore detectors to obtain a power distribution map. The measured valJes of F& shall be used since an uncertainty of 4% for incore measurement of FL has been included in the above limit.
l Page 11 of 14 l
Wolf Creek Generating Stati:n Cycb 10 Core Operating Limits Report NN @mm mRmmum Revision 1 2.7 Refueling Boron Concentration (Tech Spec 3.9.1.b)
The refueling boron concentration shall be greater than o equal to 2300 PPM.
l Page 12 of 14
- ~
W$LF CREEK Wolf Creek Generating Stati:n c--
NUCLEAR OPERATING CORPORATION Com Ope g
m Re #
APPENDIX A A.
Input relating to Specification 4.2.2.2.c:
JV(2) = o(Z)" ****'
F These values are issued in a controlled report which will be provided on l
- request, Input relating to Specification 4.2.2.2.e.1 Cycle Bumup F7(Z) Penalty Factor 0
2.00 21000 2.00 Note: All cycle bumups outside of the above table shall use a 2% penalty factor for com sliance with 4.2.2.2.e Surveillance Requirement.
Linear interpo ation should be used for intermediate cycle bumups.
Page 13 of 14
W;lf Creek G:ntrating Stati:n-Cycla 10 Core Operati g Limits Report UCWAR OPERATING CORPCHATION Technical Specification BASES 3/4.2.5 Cycle 10 Safety Analysis DNB Limit 1.76 WRB-2 Design Limit DNBR 1.23 i
l l
Page 14 of 14
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