ML20211P684
| ML20211P684 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 09/18/1997 |
| From: | Blair J, Flannigan R, Kennamore P WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20211P680 | List: |
| References | |
| NUDOCS 9710210110 | |
| Download: ML20211P684 (14) | |
Text
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Cycle 9 Cors Op; rating Limits Rsport
' NUCLEAR OPERATING CORPORATION Rsvi31on1 l
f-WOLF CREEK GENERATING STATION CYCLE 9 CORE OPERATING LIMITS REPORT Revision 1 September 18,1997 gM Prepared by:
~
Je)fT({alr Reviewed by:
2 Pete Kennamore 4
Approved by:
((khamm.,
R. D. Flannigan' Page 1 of 14 hbk kho$ 050 0 82 PDR p
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N@ ele 0GOL1 DOEO709030 E3080@@
"g Cycl 3 9 Csra Op;rcting Limits R2 port
' NUCLEAR OPERATING CORPORATION R:vl2 ion 1 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:
3.1.1.3.b Moderator Temperature Coefficient (MTC) EOL Limit 3.1.3.5 Shutdown Rod Insertiori Limit 3.1.3.6 Control Rod Insertion Limit 3.2.1 Axial Flux Differe.nce (AFD) 3.2.2 Heat Flux Hot Channel Factor - F (Z) y 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor - Fj, 3.9.1.b Refueling Boron Concentration Page 2 of 14
'3 Walf Crcek Gzn. rating Station j
7 vjg Cycl 39
' NUCLEAR OPERATING CORPORATION vCr0 Op rating Limits R port R7,vialon 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 5.1.1.3.b)
The EOL MTC shall be less negative than -50 pcm/deg F-(Tech Spec 4.1.1.3.b)
The 300 PPM MTC Surveillance Limit is -41 pcm/deg F (all rods withdrawn, Rated Thermal Power condition).
i 1
i Page 3 of 14 J
r foK@fnirasing @@Qion Cycla 9
' NUCLEAR OPERATING CORPORATION Cero Op:rcting Limits Report Rsvicion 1 2.2 Shutdown Rod Insertion Lirait (Tech Spec 3.1.3.5)
The shtitdown rods shall te fully withdrawn, as defined in Figure 1.
2.3 Control Rod insertion Limits (Tech Spec 3.1.3.6)
The Control Bank Insert;on Limits are specified in Figure 1.
4 Page 4 of 14
Wcif Crs:k G2n:rcting Stction Cycla 9 NUCLEAR OPERATING CORPORATION Core Op2rcting Limits R: port Revision 1 (FULLY WITHDRAWN )
220 (26 7 % 222);
(76.7 % 222) 200 BANK 100
...B........
160
~( 0%' 6 'i ' ' ' ' ' ' ' ' ' ' ' ' ' '
' ' ' ' ', ' ' l''''*'********'
S 140
. B AN K. '..... -.... -.........
t:
c p
S 120 W
I 4
4 T 100
_.....................,.......p.............
H D
R A 00 W
BANK N
~~'
~ '~~' ' '* ' " ',~' ' '
'D' "*"'----~~"*
g l
. 10% 4 6).......................
...e
. es
............=
......b.
.b.........
e
.............am l
(30 2 % 0) 0 0
20 40 60 80 100 (FULLY INSERTED)
RATED THERM AL POWER (Percent)
FlOURE 1 ROD BANK INSERTION LIMIT VERSUS THERMAL POWER.FOUR LOOP OPERATION Fully Withdrawn shall be sne condition where contret rc Js are at a position within the intervali 3222 anos 231 steps witndrawn.
Page 5 of 14
Wwit bak Gowvuting Station Cycis9
' NUCLEAR OPERATING CORPORATION Cor@ Op: rating Limits Report R; vision 1 f
'2.4 Axial Flux Difference (AFD) l (Tech Spec 3.2.1)
The indicated Axial Flux Difference (AFD) allowed operational space is defined by Figure 2.
a 4
l:
4
\\
Page 6 of 14
E weit crack c:n:rcting stttien g
Cycla9 Cero Opcrcting Limits Rsport
' NUCLEAR OPERATING CORPORATION Revision 1 1
110
(-15,100)
(5,100) 100
$Ekf dN OPERAT N 0
p 90 R
A T
E 80 D
T
~
ACCEPTABLE E
70 R
opgn,ying M
A L
p 60 0
W E
R
( 29.50)
(24,50) 40
-30 20 10 0
10 20 30 FLUX DIFFERENCE (DELTA I) %
FIGURE 2 WOLF CREEK AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL Page 7 of 14
W6LF K
C ""
~"
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 1 2.5 Heat Flux Hot Channel Factor Fe(Z)
F""
F (2) s 'p
- K(Z). for P > 0.5 j
p hit F (Z)5 p' K(2),
for P s 0.5 g
TilERMAL POWER
- wnere, P
r RATED THERMAL POWER '
7" the F (Z) Limit at RATED THERMAL POWER (RTP)
=
y 2.50, and
=
K(2) is defined in Figure 3.
Fj" (K(Z))
for P > 0.5 Ff(Z) s g,
Fl" (K(Z)) '
F7(Z) s W(Z)) [0.5)
Ratio of the Fo from normal operation transients to the Fo at W(Z)
=
steady state conditions Page 8 of 14
Cycle 9
' NUCLEAR OPERATING CORPORATION Ccro Op rating Limits R: pert a
Rovial:n 1 (Tech Spec 4.2.2.2.e.1) 9 With measurements indicating
' F,;'(Z)'
manmum over z K(Z),
(
has increased since the previous determination of F7(Z),
Ff(Z) shall be increased over that specified in 4.2.2.2.c by an appropriate factor, the F, Penalty Factor.
t 4
See Appendix A for:
1, 11'(2) 1.
E, Penalty Factor t
Page 9 of 14
W6URcir535 @cncrating St tion s
Cyclo 9 w
' NUCLEAR OPERATING CORPORATION Ccra Op rcting Limits R: port R::vislen 1 FIGURE 3 K(Z) NORMAllZED PEAKING FACTOR VS, CORE HEIGHT 1.2 b
M D'
1 0
0.8 O
E M
y0.6 Q.
O Lu
[S 0.4
.l4 E
FQT42.50 h0.2 tiev.uon ieti n<zi z
i:
12.0 0.92$
0 0
2 4
6 8
10 12 CORE HEIGHT (FT)
Page 10 of 14
---____.-.____.--_~m
MME k G5nf rating Stati:n Cycis9 w
' NUCLEAR OPERATING CORPORATION Ccro Op: rating Limits R:p3rt R:visi:n 1 2.6 Nuclear Enthalpy Rise Hot Channel Factor Fj, (Tech Spec 3.2.3)
Fln shall be limited by the following relationship:
Fj, s Fj" 1.0 + PF,(1.0 - P) i
- Where, The Fj, limit at RATED THERMAL POWER kRTP)
Fj'
=
1,59
=
the power factor multiplier for Fj, PF,
=
0.3
=
4 T11ERMAL POWER p
RATED TiiERMAL POWER Fln = Measured values of Ffu obtained by using the movable incore detectors to obtain a power distribution map. The measured values of rln shall be used since an uncertainty of 4% for incore measurement of Fln has been included in the above limit.
Page 11 of 14 j
r N/oWWrcolh(fcn: rating SQction ~~ ~
Cycla9 v
' NUCLEAR OPERATING CORPORATION Cero Oporcting Limits R0 port R3 vision 1 2.7 Refueling Boron Concentration (Tech Spec 3.9.1.b)
The refueling boron concentration shall be greater than or equal to 2300 PPM.
Page 12 of 14
Cycla9 v
' NUCLEAR OPERATING CORPORATION Ccro Op; rating Limits R:p:rt Revision 1 APPENDIX A A.
Input relating to Specification 4.2.2.2.c:
It'( Z) =,e( Z)"*' """"
F q ( 7),,,,,
These values are issued in a controlled report which will be provided on request.
Input relating to Specification 4.2.2.2.e.1 Cycle Burnup F7(Z) Penalty Factor 0
2.00 21400 2.00 Note: All cycle burnups outside of the above table shall use a 2% penalty factor for com sliance with 4.2.2.2.e Surveillance Requirement.
Lhiear interpo ation should be used for intermediate cycle burnups.
Page 13 of 14
W6LF CREEK
"" "'=* n= "' "" * "
' NUCLEAR OPERATING CORPORATION Care Op: rating Limits Rep rt Revision 1 Technical Specification BASES 3/4.2.5 l
Cycle 9 Safety Analysis DNB Limit 1,76 WRB 2 Decign Limit DNBR 1.23 Page 14 of 14
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