CP-200801523, Core Operating Limits Report
| ML083120427 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 10/28/2008 |
| From: | Blevins M Luminant Power |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CP-200801523, Tech. Spec. 5.6.5, TXX-08137 | |
| Download: ML083120427 (24) | |
Text
Lminant Mike Blevins Executive Vice President
& Chief Nuclear Officer Mike.Blevins@Luminant.com Luminant Power P 0 Box 1002 6322 North FM 56 Glen Rose, TX 76043 T 254 897 5209 C 817 559 9085 F 254 897 6652 CP-200801523 Log # TXX-08137 Ref. #
Tech. Spec. 5.6.5 October 28, 2008 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NO. 50-445 CORE OPERATING LIMITS REPORT
Dear Sir or Madam:
Pursuant to Technical Specification 5.6.5, Luminant Generation Company LLC (Luminant Power) hereby submits the Core Operating Limits Report for Comanche Peak Unit 1, Cycle 14.
This communication contains no new licensing basis commitments regarding Comanche Peak Unit 1.
Should you have any questions, please contact Mr. J. D. Seawright at (254) 897-0140.
Sincerely, Luminant Generation Company LLC Mike Blevins By: /& K'2L Fred W. Madden Director, Oversight & Regulatory Affairs Enclosure Unit 1, Cycle 14 Core Operating Limits Report (COLR) c -
E. E. Collins, Region IV B. K. Singal, NRR Resident Inspectors, Comanche Peak A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway - Comanche Peak
- Diablo Canyon - Palo Verde
- San Onofre South Texas Project Wolf Creek
ERX-08-003, Rev.
0 CPNPP UNIT 1 CYCLE 14.
CORE OPERATING LIMITS REPORT September 2008 Prepared:
Reviewed:
Reviewed:
Date:
6_.q-2Y
\\Jon than M. Ralston
ýrncipal Engineer, Westinghouse Electric Co.
Date:
9/29/zc.
Daniel E. Brozake" Principal Engineer, Westinghouse Electric Co.
/
c4
'Date:
ql/il9 zxy evin N.
Roland Principal Engineer, Westinghouse Electric Co.
Date:
2 */z /2y Jamd' Boatwright, Manager Westinghouse Engineering Services -
Texas Approved:
DISCLAIMER The information contained in this report was prepared for the specific requirement of Luminant Generation Company LLC and may not be appropriate for use in situations other than those for which it was specifically prepared.
Luminant Generation Company LLC PROVIDES NO WARRANTY HEREUNDER, EXPRESS OR IMPLIED, OR STATUTORY, OF ANY KIND OR NATURE WHATSOEVER, REGARDING THIS REPORT OR ITS USE, INCLUDING BUT NOT LIMITED TO ANY WARRANTIES ON MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE.
By making this report available, Luminant Generation Company LLC does not authorize its use by others, and any such use is forbidden except with the prior written approval of Luminant Generation Company LLC.
Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein.
In no event shall Luminant Generation Company LLC have any liability for any incidental or consequential damages of any type in connection with the use, authorized or unauthorized, of this report or of the information in it.
ii ERX-08-003, Rev.
0
COLR for CPNPP Unit 1 Cycle 14 TABLE OF CONTENTS DISCLAIMER TABLE OF CONTENTS.
LIST OF TABLES.......
LIST OF FIGURES SECTION 1.0 CORE OPERATING LIMITS REPORT 2.0 OPERATING LIMITS 2.1 SAFETY LIMITS 2.2 SHUTDOWN MARGIN 2.3 MODERATOR TEMPERATURE COEFFICIENT 2.4 ROD GROUP ALIGNMENT LIMITS 2.5 SHUTDOWN BANK INSERTION LIMITS I.......
2.6 CONTROL BANK INSERTION LIMITS 2.7 PHYSICS TESTS EXCEPTIONS MODE 2........
2.8 HEAT FLUX HOT CHANNEL FACTOR 2.9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR 2.10 AXIAL FLUX DIFFERENCE....................
2.11 REACTOR TRIP SYSTEM INSTRUMENTATION 2.12 'RCS PRESSURE, TEMPERATURE, AND FLOW DEPAR NUCLEATE BOILING LIMITS 2.13 BORON CONCENTRATION......................
3.0 REFERENCES
ii iii iv V
PAGE 1
2 2
2 2
3 3
4 4
4 5
6 6
CURE FROM 7
8 8
iii ERX-08-003, Rev.
0
COLR for CPNPP Unit 1 Cycle 14 LIST OF TABLES TABLE PAGE 1
FQ(Z)
MARGIN DECREASES IN EXCESS OF 2% PER 31 EFPD 9..........9 iv.
ERX-08-003, Rev.
0
COLR for CPNPP Unit 1 Cycle 14 LIST OF FIGURES FIGURE PAGE 1
REACTOR CORE SAFETY LIMITS 10 2
ROD BANK INSERTION LIMITS VERSUS THERMAL POWER...........
11 3
K(Z)
NORMALIZED FQ (Z),AS A FUNCTION OF CORE HEIGHT.............................
12
- 4.
W(Z)
AS A FUNCTION OF CORE HEIGHT (150 MWD/MTU) 13 5
W(Z). AS A FUNCTION OF CORE HEIGHT (3000 MWD/MTU) 14 6
W(Z)
AS A FUNCTION OF CORE HEIGHT (10,000 MWD/MTU) 15 7
W(Z) 'AS A FUNCTION OF CORE HEIGHT (14,000 MWD/MTU) 16 8
W(Z)
AS A FUNCTION OF CORE HEIGHT (20,000 MWD/MTU)..........................................
17 9
AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER.
18 ERX-08-003, Rev.
0 V
COLR for CPNPP Unit 1 Cycle 14 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for CPNPP UNIT 1 CYCLE 14 has been prepared in accordance with the requirements of Technical Specification 5.6.5.
The Technical Specifications affected by this report are listed below:
SL 2.1 LCO 3.1.1 LCO 3.1.3 LCO 3.1.4 LCO 3.1.5 LCO 3.1.6 LCO 3.1.8 LCO 3.2.1.2 LCO 3.2.2 LCO 3.2.3.2 LCO 3.3.1 LCO 3.4.1 LCO 3.9.1 SAFETY LIMITS SHUTDOWN MARGIN MODERATOR TEMPERATURE COEFFICIENT ROD GROUP ALIGNMENT LIMITS SHUTDOWN BANK INSERTION LIMITS CONTROL BANK INSERTION LIMITS PHYSICS TESTS EXCEPTIONS MODE 2 HEAT FLUX HOT CHANNEL FACTOR NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR AXIAL FLUX DIFFERENCE REACTOR TRIP SYSTEM INSTRUMENTATION RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING LIMITS BORON CONCENTRATION 1
ERX-08-003, Rev.
0
COLR for CPNPP Unit 1 Cycle 14 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections.
These limits have been developed using the NRC-approved methodologies specified in Technical Specification 5.6.5b, Items 1, 2, 14, 16, 17, 18 and 21 through 29.
These limits have been determined such that all applicable limits of the safety analysis are met.
2.1 SAFETY LIMITS (SL 2.1) 2.1.1 In MODES 1 and 2, the combination of thermal power, reactor coolant system highest loop average temperature, and pressurizer pressure shall not exceed the safety limits specified in Figure 1.
2.2 SHUTDOWN MARGIN (SDM)
(LCO 3.1.1) 2.2.1 The SDM shall be greater than or equal to 1.3% Ak/k in MODE 2 with Kef,
< 1.0, and in MODES 3, 4,
and 5.
2.3 MODERATOR TEMPERATURE COEFFICIENT (MTC)
(LCO 3.1.3) 2.3.1 The MTC upper and lower limits, respectively, are:
The BOL/ARO/HZP-MTC shall be less positive than +5 pcm/°F.
The EOL/ARO/RTP-MTC shall be less negative than -40 pcm/*F.
2 ERX-08-003, Rev.
0
COLR for CPNPP Unit 1 Cycle 14 2.3.2 SR 3.1.3.2 The MTC surveillance limit is:
The 300 ppm/ARO/RTP-MTC shall be less negative than or equal to -31 pcm/°F.
The 60 ppm/ARO/RTP-MTC shall be less negative than or equal to -38 pcm/°F.
where:
BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero THERMAL POWER EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER 2.4 ROD GROUP ALIGNMENT LIMITS (LCO 3.1.4) 2.4.1 The SDM shall be greater than or equal to 1;3% Ak/k in MODES 1 and 2.
2.5 SHUTDOWN BANK INSERTION LIMITS (LCO 3.1.5) 2.5.1 The shutdown rods shall be fully withdrawn.
Fully withdrawn shall be the condition where shutdown rods are at a position within the interval of 218 and 231 steps withdrawn, inclusive.
3 ERX-08-003, Rev.
0
COLR for CPNPP Unit 1 Cycle 14 2.6 CONTROL BANK INSERTION LIMITS (LCO 3.1.6) 2.6.1 The control banks shall be limited in physical insertion as shown in Figure 2.
2.6.2 The control banks shall always be withdrawn and inserted in the prescribed sequence.
For withdrawal, the sequence is control bank A, control bank B, control bank C, and C
control bank D.
The insertion sequence is the reverse of the withdrawal sequence.
2.6.3 A 115 step Tip-to-Tip relationship between each sequential control bank shall be maintained.
2.7 PHYSICS TESTS EXCEPTIONS-MODE 2 (LCO 3.1.8) 2.7.1 The SDM shall be greater than or equal to 1.3% Ak/k in MODE 2 during PHYSICS TESTS.
2.8 HEAT FLUX HOT CHANNEL FACTOR (F, (Z)
FRTP FQ 2.8.1 FQ(Z) 5
[K(Z)] for P > 0.5 P
RTP FQ FQ (Z)
[K(Z)] for P S5 0.5
0.5 where
P =
THERMAL POWER RATED THERMAL POWER 4
ERX-08-003, Rev.
0
COLR for CPNPP Unit 1 Cycle 14 RTP 2.8.2 FQ
= 2.50 2.8.3 2.8.4 K(Z) is provided in Figure 3.
Elevation and burnup dependent W(Z) values are provided in' Figures 4, 5,
6, 7 and 8.
The burnup dependent values can be used to interpolate or extrapolate (via a three point fit) the W(Z) at a particular burnup.
2.8.5 SR 3.2.1.2.2 If the two most recent FQ(Z) evaluations show an increase in the expression maximum over Z
[ FQC(Z)
/ K(Z) I, the burnup dependent values in Table 1 shall be used instead of a constant 2% to increase FQw(Z) per Surveillance Requirement 3.2.1.2.2.a. A constant factor of 2% shall be used for all cycle burnups that are outside the range of Table 1.
2.9 NUCLEAR-ENTHALPY RISE HOT CHANNEL FACTOR (FNHI (LCO 3.2.2)
.2.9.1 FNAH 5
FR TPAH
[1 + PFAH (l-P)]
where:
P =
THERMAL POWER RATED THERMAL POWER 2.9.2 FRTPAH =
1.35 for Region 13B Fuel Assemblies F
RTPAH =
1.60 for all other Fuel Assembly Regions 2.9.3 PFAH
=
0.3 5
ERX-08-003, Rev.
0
COLR for CPNPP Unit 1 Cycle 14 2.10 AXIAL FLUX DIFFERENCE (AFD)
(LCO 3.2.3.2) 2.10.1 The AFD Acceptable Operation Limits are provided in Figure 9.
2.11 REACTOR TRIP SYSTEM (RTS)
INSTRUMENTATION (LCO 3.3.1) 2.11.1 The numerical values pertaining to the Overtemperature N-16 reactor trip setpoint are listed below; K1
= 1.15 K2
= 0.0139 /°F K3
= 0.00071 /psig Tc
= indicated loop specific Tc at Rated Thermal Power, OF P'
2 2235 psig T,
- 10 sec T,
5 3 sec f,(Aq) = -2.78
{(q,-qb)
+ 18%)
when (q,-qb) 5 -18% RTP
= 0%
when -18% RTP < (qt-qb)
< +10.0% RTP
= 2.34
{(q,-qb) 10.0%)
when (q,-qb) 2 +10.0% RTP 6
ERX-08-003, Rev.
0
COLR for CPNPP Unit 1 Cycle 14 2.12 RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING (DNB)
LIMITS (LCO 3.4.1) 2.12.1 RCS DNB parameters for pressurizer pressure, RCS average
/
temperature, and RCS total flow rate shall be within the surveillance limits specified below:
2.12.2 SR 3.4.1.1 Pressurizer pressure 2220 psig (4 channels) 2222 psig (3 channels)
The pressurizer pressure limits correspond to the analytical limit of 2205 psig used in the safety analysis with allowance for measurement uncertainty.
These uncertainties are based on the use of control board indications and the number of available channels.
2.12.3 SR 3.4.1.2 RCS average temperature S 588 0F (4 channels) 5 588 'F (3 channels)
The RCS average temperature limits correspond to the analytical limit 'of 591.9 0F which is bounded by that used in the safety analysis with allowance for measurement uncertainty.
These uncertainties are based on the use of control-board indications and the number of available channels.
7 ERX-08-003, Rev.
0
COLR for CPNPP Unit 1 Cycle 14 2.12.4 SR 3.4.1.3 The RCS total flow rate shall be ? 403,700 gpm.
C 2.12.5 SR 3.4.1.4 The RCS total flow rate based on precision heat balance shall be
- 403,700 gpm.
The required RCS flow, based on an elbow tap differential pressure instrument measurement prior to MODE 1 after the refueling outage, shall be greater than 327,000 gpm.
2.13 BORON CONCENTRATION (LCO 3.9.1) 2.13.1 The required refueling boron concentration is 1854 ppm.
3.0 REFERENCES
Technical Specification 5.6.5.
8 ERX-08-003, Rev.
0
COLR for CPNPP Unit 1 Cycle 14 Table 1 FQ(Z)
MARGIN DECREASES IN EXCESS OF 2% PER 31 EFPD Cycle Maximum Decrease Burnup In F,(Z) MARGIN (MWD/MTU)
(Percent) 9016 2.00 9232 2.22 9448 2.37 9665 2.53 9881 2.52 10097 2.46 10313 2.33 10530 2.19 10746 2.04 10962 2.00 Note: All Cycle burnups outside the range of the table shall use a constant 2% decrease in F0 (Z) margin for compliance with the 3.2.1.2.2.a Surveillance Requirements.
Linear interpolation is acceptable to determine the FQ(Z) margin decrease for cycle burnups which fall between the specified burnups.
9 ERX-08-003, Rev.
0
COLR for CPNPP Unit 1 Cycle 14 Figure 1 Reactor Core Safety Limits 680 660 640 I( 620 60 4) 4-(U 600 580 560 0
20 40 60 80 100 120 Percent of Rated Thermal Power 140 10 ERX-08-003, Rev.
0
240 220 200 180
.c 160 4.)
-rI
- 140 120 20 H
m 100 0
. 80 0
60 40 20 0
COLR for CPNPP Unit 1 Cycle 14 FIGURE '2 ROD BANK INSERTION LIMITS VERSUS* THERMAL POWER (25.3,218)
(79.6,218)
/4-- -- -++-- -- ----
- (0,164) -
- (00 146)
- _/ _ ~
B A N K C 1
4N D--
-+--------......
(0 4 9 --
31,0),
0 10 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER NOTES:
- 1.
Fully withdrawn shall be the condition where control rods are at a position within the interval of 218 and 231 steps withdrawn, inclusive.
- 2.
Control Bank A shall be fully withdrawn.
11 ERX-08-003, Rev.
0
COLR for CPSES Unit 1 Cycle 14 FIGURE 3 K(Z)
NORMALIZED FQ(Z)
AS A FUNCTION OF CORE HEIGHT 1.1 1.0 0.9 0.8 C 0.7 N
0.6 0
0.5 z
0.4 0.3 0.2 0.1 0.0 0
1 BOTTOM 2
3 4
5 6
7 8
9 10
.11 12 CORE HEIGHT (FEET)
TOP Axial Node K (Z) 61 0.9250 60 0.9275 59 0.9300 58 0.9325 57 0.9350 56 0.9375 55 0.9400 54 0.9425 Axial Node 53 52 51 50 49 48 47 46 K(Z) 0.9450 0.9475.
- 0. 9500
- 0. 9525
- 0. 9550 0.9575
- 0. 9600
- 0. 9625 Axial Node 45 44
.43' 42 41 40 39 38 K (Z)
- 0. 9650 0.9675 -
0.9700
- 0. 9725
- 0. 9750 0.9775
- 0. 9800
- 0. 9825 Axial Node 37 36 35 34 33 32 1 -
31 K (Z) 0.9850 0.9875 0.9900 0.9925 0.9950 0.9975 1.0000 Core Height (ft)
= (Node -
- 1)
- 0.2 12 ERX-08-003, Rev.
0
COLR for CPNPP Unit 1 Cycle 14 FIGURE 4 W(Z)
AS A FUNCTION OF CORE HEIGHT (150 MWD/MTU) 1.650 1.600 1.550 1.500 1.450 S1.400 1.350 1.300 1.250 1.200 1.150 1.100 1.050 1.000 r
-rz IffI
/-I I
m
-t
-ý--l
-/
I i
/-
0
- 1.
2 3
4 5
6 7
8 9
10 11 12 BOTTOM Axial Node W(Z) 58 -
61 57 1.5283 56 1.5150 55 1.4972 54 1.4746 53 1.4489 52 1.4225 51 1.3923 50 1.3592 49 1.3245 48 1.2878 47 1.2502 46 1.2198 45 1.2077 CORE HEIGHT (FEET)
TOP Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 w(Z) 1.2070 1.2062 1.2032 1.1996 1.1969 1.1934 1.1885 1.1840 1.1774 1.1689 1.1585 1.1469 1.1365 1.1291 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18' 17 w(Z) 1.1233 1.1212 1.1245 1.1289 1.1326 1.1352 1.1377 1.1405 1.1431 1.1491 1.1562 1.1620 1.1674 1.1734 Axial Node 16 15 14 13 12 11 10 9
8 7
6 5
1 -4 w(Z) 1.1836 1.2038 1.2312 1.2576 1.2842 1.3104
- 1. 3357 1.3595 1.3815 1.4013 1.4178 1.4294 Core Height (ft)
(Node -
- 1)
- 0.2 13 ERX-08-003, Rev.
0
COLR for CPNPP Unit 1 Cycle 14 FIGURE 5 W(Z)
AS A FUNCTION OF CORE HEIGHT (3,000 MWD/MTU) 1.650 1.600 1.550 1.500 1.450 N 1.400 1.350 1.300 1.250
.1.200 1.150 1.100 1.050 1.000 J
7: T:
ý ý It
ýý V
Pol 4E 0
1 2
3 4
5 6
7 8
9 10 11 12 BOTTOM Axial CORE HEIGHT (FEET)
Node 58 -
61 57 56 55 54 53 52 51 50 49 48 47 46 45 w(Z) 1.4844 1.4694 1.4561 1.4449 1.4302 1.4080 1.3798 1.3486 1.3166 1.2833
- 1. 2498 1.2314 1.2206 Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 w (Z) 1.2164 1.2150 1.2081 1.1992 1.1864 1.1759 1.1707 1.1637 1.1552 1.1453 1.1346 1.1250 1.1184 1.1150 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 w(Z) 1.1149 1.1176 1.1266 1.1340 1.1406 1.1464 1.1515 1.1557 1.1591 1.1629 1.1673 1.1714 1.1747 1.1785 Axial Node 16 15 14 13 12 11 10 9
8 7
6 5
1 -
4 TOP w(Z) 1.1924 1.2171 1.2466 1.2758 1.3051 1.3342 1.3623 1.3889 1.4134 1.4355 1.4545 1.4685 Core Height (ft)
= (Node -
- 1)
- 0.2 14 ERX-08-003, Rev.
0
COLR for CPNPP Unit 1 Cycle 14 FIGURE 6 W(Z)
AS A FUNCTION OF CORE HEIGHT (10,000 MWD/MTU) 1.650 1.600 1.550 1.500 1.450 N 1.400 1.350 1.300 1.250 1.200 1.150 1.100 1.050 1.000 t
- I k-I i i I
I I
EIETEN 0
1 2
3 4
5 6
7 8
9 10 11 12 BOTTOM CORE HEIGHT (FEET)
Axial Node 58 -
61 57 56 55 54 53 52 51 50 49 48 47 46 45 W (Z)
- 1. 3897 1.3829 1.3730 1.3603 1.3448ý 1.3246 1.3009 1.2728 1.2502 1.2371 1.2250 1.2120 1.2069 Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 w(Z) 1.2066 1.2043 1.2006 1.1970 1.1949 1.1924 1.1886 1.1855 1.1801 1.1726 1.1633 1.1523 1.1397 1.1258 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 w(Z) 1.1195 1.1196 1.1285 1.1360 1.1425 1.1483 1.1531 1.1572 1.1606 1.1633 1.1657 1.1694 1.1756 1.1826 Axial Node 16 15 14 13 12 11 10 9
8 7
6 5
1 -
4 TOP w(Z) 1.1908 1.2056 1.2269 1.2488 1.2707 1.2921 1.3128 1.3321 1.3498 1.3657 1.3788 1.3875 Core Height (ft)
=
(Node -
- 1)
- 0.2 15 ERX-08-003, Rev.
0
COLR for CPNPP Unit'l Cycle 14 FIGURE 7 W(Z)
AS A FUNCTION OF CORE HEIGHT (14,000 MWD/MTU) 1.650 1.600 1.550 1.500 1.450 N 1.400 1.350
=
1.300 S1.250 1.200 1.150 1.100 1.050 1.000 0
1 2
3 4
5 6
7 8
9 10 11 12 BOTTOM CORE HEIGHT (FEET)
Axial Node 58 -
61 57 56 55 54 53 52 51 50 49 48 47 46 45 w(Z) 1.3500 1.3469 1.3362 1.3261 1.3197 1.3093 1.2971 1.2815 1.2625 1.2398 1.2169 1.2080 1.1984 Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 w(Z) 1.1943 1.1968 1.1984 1.1999 1.2027 1.2046
- 1. 2050 1.2053 1.2032 1.1986 1.1916 1.1826 1.1717 1.1571 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 w (Z) 1.1526 1.1542 1.1598 1.1664 1.1718 1.1758 1.1786 1.1804 1.1811 1.1809 1.1803 1.1789 1.1779 1.1842 Axial Node 16 15 14 13 12 11 10 9
8 7
6 5
1 -
4 TOP w(Z) 1.1928 1.2050 1.2208 1.2357 1.2504 1.2649 1.2787 1.2916 1.3034 1.3139 1.3223 1.3267 Core Height (ft)
= (Node -
- 1)
- 0.2 16 ERX-08-003, Rev.
0
COLR for CPNPP Unit 1 Cycle 14 FIGURE 8 W(Z)
AS A FUNCTION OF CORE HEIGHT (20,000 MWD/MTU) 1.650 1.600 1.550 1.500 1.450 N 1.400 1.350 1.300 1.250
-I hHftTh1r II
_ I _ _ _ _ _ _
-V-I 1.200 1.150 1.100 1.050 1.000 7 -7 0
1 2
3 4
5 6
7 8'
9 10 11 12 BOTTOM Axial Node W(Z) 58 -
61 57 1.3307 56 1.3334 55 1.3326 54 1.3273 53 1.3195 52 1.3085 51 1.2937 i50 1.2767 49 1.2569 48 1.2376 47 1.2256 46 1.2212 45 1.2171 CORE HEIGHT (FEET)
Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 w(Z) 1.2166 1.2232 1.2312 1.2387 1.2472 1.2549 1.2604 1.2658 1.2680 1.2669 1.2627 1.2555 1.2454 1.2321 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 W (Z)
- 1. 2189
- 1. 2127 1.2124 1.2163 1.2186 1.2186 1.2169 1.2133 1.2082 1.2017 1.1943 1.1859 1.1774 1.1754 Axial Node 16 15 14 13 12 11 10 9
8 7
6 5
1 -
4 TOP w (Z) 1.1785 1.1904 1.2069 1.2221 1.2372 1.2519 1.2660 1.2793 1.2917 1.3029 1.3121 1.3171 Core Height (ft)
= (Node -
- 1)
- 0.2 17 ERX-08-003 Rev.
0
COLR for CPNPP Unit 1 Cycle 14 FIGURE 9 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 100 90 80 70 0
0 U
N 60 50 "40 30 20 10 0 I
-40
-30
-20
-10 10 20 30 40 AXIAL FLUX DIFFERENCE
(%)
18 ERX-08-003, Rev.
0