ML20078J033
| ML20078J033 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 09/14/1994 |
| From: | Blair J, Howard M, Neises G WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20078J017 | List: |
| References | |
| TR-94-0015, TR-94-0015-R00, TR-94-15, TR-94-15-R, NUDOCS 9411180264 | |
| Download: ML20078J033 (14) | |
Text
,
TR-94-0015 W01 E
woir Crook ocnnrcting station g
Cycle 8
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 0 WOLF CREEK GENERATING STATION CYCLE 8 CORE OPERATING LIMITS REPORT Revision 0 September 1,1994 1
Prepared by:
AlfI/
h- /3 -5/
'Michdel L. Howard
? 3 fh
~
~
ppy Blair Reviewed by:
hw /
g 9/A7/9</
Glenn,lTNeises Approved by:
71 CS*
y/fy /,y y.B. Norton y118ggg4 g Page 1 of 14
__.PDR _
4 4
g Wsif Crsck G:n:rcting Statinn g
Cycle 8
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 0 1.0 CORE OPERATING LIMITS REPORT The CORE OPERATING LIMITS REPORT (COLR) for Wolf Creek Generating Station Cycle 8 has been prepared in accordance with the requirements of Technicaf 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 - Fe(x, y, z) 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor - Fm(x, y) 3.9.1.b Refueling Boron Concentration l
l Page 2 of 14
Wcif Crs:k G:n rsting Stati n Cycle 8
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 0 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are 1
presented in the subsections below:
2.1 Moderator Temoerature 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The 300 PPM MTC Surveillance Limit is -32 pcm/deg F (all rods withdrawn, Rated Thermal Power condition).
1, 1
a l
l Page 3 of 14
Wolf Crsek G:ntreting Station L
CREEK-Cycle 8
' NUCLEAR OPERATING CORPORATION Core Operating Lirnits Report Revision 0 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The shutdown rods shall be fully withdrawn, as defined in Figure 1.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 4 of 14
4 LF CREEK Wolf Creek Generating Station Cycle 8
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report Rev..asion 0 (FULLY WITHDRAWN )
5 i
, [
h, kh,,hfi I
, s (76.7%,.222),,
/
1 D0
, w J, -.
1, L,
j
... ;-.. ;. --;_ _ _;_..;- - -;...;-..; - - q -. 4. 4 - - 4. 1 -p..p..;-.-;_-.;..-
200
- - l- - - l - -l-
- -:- - -l - - -l -. -l -..' - - i.. i - '. t, - - F - - l- - - l- - - l. -. l- - -
BANK i
e,--,,--,--,,--,,--,--,,-,'-T-T-
r-r,-
r,-
r-180 r-7,._,..,-
i
--,-.,_,.-,-.,..,r-_,...c--
(100%,161) ?
160 "-.(0%.161) i i
i i
s l
..we., = - *, - =
,e -, -.. -,. -..,. -
.,p..a.
--g--g
..e--+
.,..p.
-p 5
s t
5 d
t 140
.--...-.----.--e s
4.-._-4......_----_
BA.NK C.
i s_.a..s-...-....__.,-..,..,..s
-u..-..
120
s, -. a, -
s, -
2, -. 2 -
2,.
4, - * -
t, 2,-
2,.
1, _1,-.t,.
.u-......
t_.u..........
a f
8 l
i 100
'--L-'.-,'-.
s, - -, -
J,.. a, -
2, -. 2,.
1, -.,
_-. ;- - - - _ ;- - - -. - - -; _ :...; - _ _;.. 4 - _, _ - 4. - -.. p - _ p.. ;.. - ;-......
80 l
l
, BANK D l
l 7..,-.r-r-
r s
j 60
=.. -=.., - -
,----.e,.
9--
9ee3-_g ay-y..yo.y.
p-.(.
pe.. -..
I i
i
,......,-..i.--.i.-,..,,..,,-.,,
-,.,i..,i.,i.,,-,i..,-,r-,,-.
i r,
ll 1
(o%.46).,-,-.. - - -, -., - -, - -, -, - -,. -, _ _. - -. -. - -... -. -.
40 4
j
/.
20
- -------,--,------,--,/--,--,--,.-,..*--,--.--,--,-- --.-,---
-u..u...-,......,_-
,--a.-a--s.-,-.s.-.-,--r--.-_-.--_.-
.(302%.o),
l
)
0 0
20 40 60 80 100
~l RELATIVE POWER (Percent)
(FULLY INSERTED)
FIGURE 1 ROD BANK INSERTION LIMIT VERSUS l
THERMAL POWER-FOUR LOOP OPERATION l
Fully Withdrawn sha2 be the condition wnere control rods are at a position within the interval of
& 222 and 5 231 steps withdrawet 1
l Page 5 of 14
Wolf Crask Gsnarating Station
- LF CREEK Cycle 8
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 0 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 Crxk G:n: rating Station wfL CREEK Cycle 8
' NUCLEAR OPERATING CORPORATIOt1 Core Operating Limits Report Revision 0 110
{15,100)
(4,100) 100 UNACCEPT*BLE UNACCEPTABLE OPERA M d OPERATION Oe
/
a
?
$ 80
=i 5
iE
~
\\
Lg ACCEPTABLE OPERATION O
/
60 50
(-21,60)
(24.50) i i
40
-30
-20
-10 0
10 20 30 FLUX DIFFERENCE (DELTA l} %
FIGURE 2 WOLF CREEK UNIT 1 AX1AL FLUX Dif/ERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER Page 7 of 14
Wolf Crack Gsn: rating Station LF CREEK Cycle 8
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 0 2.5 Heat Flux Hot Channel Fsetor - Fo(x, y, z)
F"'(x,y,z) s Fo"*
- K(z), f r P > 0.5 o
P F"'(x,y,z) $ o "
F" o
0.5 THERMAL POWER M ere, P_
RATED THERMAL POWER F*"
= the F at RATED THERMAL POWER o
o
= 2.50, and K(z) is defined in Figure 3.
See Appendix A for:
1.
F (x, y, z)f ", Fj (x, y, z)} ", and o
Fj ( x, y, z ) }""
~
2.
Op Mar NSLOPE and Op Mar PSLOPE 3.
RPS Mar NSLOPE and RPS Mar PSLOPE Page 8 of 14
Wolf Creek G3n: rating Station yL CREEK Cycle 8
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 0 FGURE 3 K{Z)40RM ALIZEO PEAKING FACTOR VS. CORE HEIGHT 1.2 i,
i f
I i
I 9
1 1
i 1
1
+-----------------------
g o.
4 E 0.8
s,-----------t-----------;-----------j-----------p-----------
5 W
o a 0.6 b
,u f0.4 ----------'----------'-----------l----------'----------'-----------
7
=
4 4
0.2 - - - - - - - - - -, - - - - - - - - - - - -, - - - - - - - - - -, - - - - - - - - - - -, - - - - - - - - - - -, - - - - - - - - - - -
8 I
I t
I I
O 0
2 4
6 8
10 12 CORE HEIGHT (FT)
FQT=2.5_0 Elevation (ft)
K(2) 0.0 10 6.0 10 j
12.0 0 925 1
I Page 9 of 14 I
I
Wolf Crack G:nsrating Station LF CREEK Cycle 8
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 0 2.6 Nuclear Enthalov Ris.e_ Hot Channel Factor - Fm(x, y)
Fm(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)
Page 10 of 14
Walf Cr:ck G:n:rc. ting Station
- L CREEK Cycle 8
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 0 Definitions - FAHR (x,y)
Limit:
FAHR'(x,y) = MAP *h*(x,y), AX*(x,y) I AX*(x,y) MH(x,y)
~
- whero, Design F, for the assembly at location (x,y),
F
=
D D
Design Maximum Allowable Peak at h (x,y) and AX (x,y),
MAP
=
h (x,y)
= Axiallocation 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)
= Minimum available margin ratio at (x,y)
Measurement:
i FAHR"(x,y) = MAP" h"(x,y), AX"(x, v) I AX"(x,y)
- where, F"
= Measured F, for the assembly at location (x,y),
MAP"
= Maximum Allowable Peak at h"(x,y) and AX"(x,y),
h"(x,y)
= Axial location of tlifrhiasured axia' 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.
Page 11 of 14
Wolf Crssk Gsnarating Station LF CREEK Cycle 8
' NUCLEAR OPERATING CORPORATION Core Operating Limits Report Revision 0 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
LF CREEK W6) NUCLEAR OPERATING CORPORA Wolf Crs:k Gan:rcting Statisn c-e Core Operating Limits Report Revision 0 APPENDIX A A.
Input relating to Specification 4.2.2.2.d:
1.
F (x, y, z)f "
- Nominal design peaking o
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 = 2.0% / % margin Op Mar PSLOPE = 2.4% / % margin 3.
RPS Mar NSLOPE = 1.20% / % margin RPS Mar PSLOPE = 1.92% / % margin l
l Page 13 of 14
Wolf Creek G:n:rsting Station L
Cycle 8 we
' NUCLEAR OPERATING CORPORATIOtJ Core Operating Limits Report Revision 0 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 oflarge arrays. Tney 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.
Page 14 of 14