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{{Adams
#REDIRECT [[CP-201400397, Comanche Peak, Unit 2, Core Operating Limits Report, Cycle 15]]
| number = ML14107A036
| issue date = 04/08/2014
| title = Comanche Peak, Unit 2, Core Operating Limits Report, Cycle 15
| author name = Flores R, Madden F W
| author affiliation = Luminant Generation Co, LLC, Luminant Power
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000446
| license number =
| contact person =
| case reference number = CP-201400397, TXX-14047
| document type = Fuel Cycle Reload Report, Letter
| page count = 24
}}
 
=Text=
{{#Wiki_filter:Rafael Flores Luminant Power Senior Vice President P 0 Box 1002& Chief Nuclear Officer 6322 North FM 56 Lum inant rafael.flores@Luminant.com Glen Rose, TX 76043 T 254 897 5590 C 817 559 0403 F 254 897 6652 Ref: 10CFR50.36(c)(5)
CP-201400397 TXX-14047 April 8, 2014 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 .
 
==SUBJECT:==
COMANCHE PEAK NUCLEAR POWER PLANT DOCKET NO. 50-446 (UNIT 2)CORE OPERATING LIMITS REPORT
 
==Dear Sir or Madam:==
Enclosed is Revision 0 of the Core Operating Limits Report for Comanche Peak Nuclear Power Plant (CPNPP)Unit 2, Cycle 15. This report is prepared and submitted pursuant to Technical Specification 5.6.5.This communication contains no new licensing basis commitments regarding CPNPP Unit 2.Should you have any questions, please contact Mr. J. D. Seawright at (254) 897-0140.Sincerely, Luminant Generation Company LLC Rafael Flores By: 4Y"' 2K% A¶L B FreýdW. Madden -Director, External Affairs Enclosure
-Unit 2 Cycle 15 Core Operating Limits Report, Revision 0 c -Marc L. Dapas, Region IV Balwant K. Singal, NRR Resident Inspectors, Comanche Peak A member of the STARS Alliance 4k I /Callaway *Comanche Peak -Diablo Canyon *Palo Verde *Wolf Creek ERX-14-001, Rev. 0 CPNPP UNIT 2 CYCLE 15 CORE OPERATING LIMITS REPORT March 2014 Prepared: Reviewed: Reviewed: Approved:\. Jg/_ Date: Q1(K 2 41t0 Daniel E. Brozak /Principal Engineer, Westinghouse Electric Company, LLC._____ ____ Date: ;i/ ly Sompofn Srinilta Principal Engineer, Westinghouse Electric Company, LLC.~IA L &Ll~~J UOfA,~ ~ NA!'Date:
MP.Qe.6 Iq Brian L. Guthrie Principal Engineer, Westinghouse Electric Company, LLC.06/3 14. ROL-AiJb EMAIL" Date: MARCH A(DA pVi Kevin N. Roland, Manager Westinghouse Integrated Site Engineering
-TX/KS 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-14-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 15 TABLE OF CONTENTS DISCLAIMER
......................................................
ii TABLE OF CONTENTS ...............................................
iii LIST OF TABLES ..................................................
iv LIST OF FIGURES .................................................
v SECTION PAGE 1.0 CORE OPERATING LIMITS REPORT ..............................
1 2.0 OPERATING LIMITS ..........................................
2 2.1 SAFETY LIMITS ... ..................................
...... 2 2.2 SHUTDOWN MARGIN ......................................
2 2.3 MODERATOR TEMPERATURE COEFFICIENT
....................
2 2.4 ROD GROUP ALIGNMENT LIMITS ...........................
3 2.5 SHUTDOWN BANK INSERTION LIMITS .......................
3 2.6 CONTROL BANK INSERTION LIMITS ........................
4 2.7 PHYSICS TESTS EXCEPTIONS
-MODE 2 .........................
4 2.8 HEAT FLUX HOT CHANNEL FACTOR ..........................
4 2.9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR ..................
6 2.10 AXIAL FLUX DIFFERENCE
................................
6 2.11 REACTOR TRIP SYSTEM INSTRUMENTATION
..................
6 2.12 RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING LIMITS ..............................
7 2.13 BORON CONCENTRATION
-................................
8
 
==3.0 REFERENCES==
 
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8 liii ERX-14-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 15 LIST OF TABLES TABLE PAGE 1 F (Z) MARGIN DECREASES IN EXCESS OF 2% PER 31 EFPD ............
9 iv ERX-14-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 15 LIST OF FIGURES FIGURE PAGE I 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 -(3,000 MWD/MTU) .........................................
14 6 W(Z) AS A FUNCTION OF CORE HEIGHT -(6,000 MWD/MTU) .........................................
15 7 W(Z) AS A FUNCTION OF CORE HEIGHT -(10,000 MWD/ITU) ........................................
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 V ERX-14-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 15 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for CPNPP UNIT 2 CYCLE 15 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 2.21 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 LCO 3.2.2 LCO 3.2.3 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-14-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 15 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 through 4 and 7 through 15.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 K.,, < 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-14-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 15 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 BOL 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-14-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 15 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 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)) (LCO 3.2.1)F 0 R 2.8.1 F (Z) S __ [K(Z)] for P > 0.5 P F. B FO (Z) S -EK(Z)] for P S 0.5 0.5 wheres P = THERMAL POWER RATED THERMAL POWER 4 ERX-14-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 15 2.8.2 FQ" = 2.50 2.8.3 K(Z) is provided in Figure 3.2.8.4 Elevation and burnup dependent W(Z) values are provided in Figures 4, 5, 6, 7 and 8. For W(Z) data at a desired burnup not listed in the figures, but less than the maximum listed burnup, values at 3 or more burnup steps should be used to interpolate the W(Z) data to the desired burnup with a polynomial type fit that uses the nearest three burnup steps. For W(Z) data at a desired burnup outside of the listed burnup steps, a linear extrapolation of the W(Z) data for the nearest two burnup steps can be used.2.8.5 SR 3.2.1.2 If the two most recent FQ(Z) evaluations show an increase in the expression maximum over Z F F (Z) / K(Z) 3, the burnup dependent values in Table 1 shall be used instead of a constant 2% to increase Fw(Z) per Surveillance Requirement 3.2.1.2.a.
A constant factor of 2% shall be used for all cycle burnups that are outside the range of Table 1.5 ERX-14-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 15 2.9 NUCLEAR ENTHALPY RISE NOT CHANNEL FACTOR (I"AH) (LCO 3.2.2)2.9.1 FgAH S F m 4 El[ + PFAH (1-P)]where: P = THERMAL POWER RATED THERMAL POWER 2.9.2 F"AH = 1.60 for all Fuel Assembly Regions 2.9.3 PFAH = 0.3 2.10 AXIAL FLUX DIFFERENCE (AFD) (LCO 3.2.3)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;K 1  = 1.15 Ka = 0.0139 /OF K3 = 0.00071 /psig TO = indicated loop specific TO at Rated Thermal Power, OF P1 k 2235 puig T 10 sec ,: S 3 sec f 1 (Aq) = -2.78 * {(qj-qb) + 18%) when (q,-q 0) S -18% RTP= 0% when -18% RTP < (%-q.) < +10.0% RTP= 2.34 -{(q,-qb) -10.0%) when (q,-q%) 2 +10.0% RTP 6 ERX-14-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 15 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 a 2220 psig (4 channels)a 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 592 &deg;F (4 channels)9 591 OF (3 channels)The RCS average temperature limits correspond to the analytical limit of 595.2 &deg;F 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-14-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 15 2.12.4 SR 3.4.1.3 The RCS total flow rate shall be 2 408,000 gpm.2.12.5 SR 3.4.1.4 The RCS total flow rate based on precision heat balance shall be 2 408,000 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 ?-1950 ppm.
 
==3.0 REFERENCES==
 
Technical Specification 5.6.5.8 ERX-14-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 15 Table 1 F.(Z) MARGIN DECREASES IN EXCESS OF 2% PER 31 EFPD Cycle Maximum Decrease Burnup In F,(Z) NARGIN (MWD/NMT) (Percent)0 3.80 150 3.80 365 4.15 580 4.07 794 3.75 1009 3.25 1224 2.65 1439 2.04 1653 2.00 Note: All cycle burnups outside the range of the table shall use a constant 2% decrease in F 0 (Z)margin for compliance with the 3.2.1.2.a Surveillance Requirements.
Linear interpolation is acceptable to determine the F,(Z) margin decrease for cycle burnups which fall between the specified burnups.9 ERX-14-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 15 Figure 1 Reactor Core Safety Limits 680 660 2235 sig Unacceptable
: 0. 1985 psig E 62--Accepal 600, 580 --I 560 , __0 20 40 60 80 100 120 140 Percent of Rated Thermal Power 3.0 ERX-14-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 15 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 240 220 200 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1(25.3.2161
-" (79.6,218)4-III111 WmHWnH+H-I
'liii ill I I 1111 1 ---------------
II B I: i i i i ii i i i 180 160 o 140 43 Zo 120 H E-4 H o0 100 80 60 E..II.........--. .-I-(00,146)-BANK C Jo.J 40 20 0 0 10 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER I NOTES: 1. Fully withdrawn shall be the condition where are at a position within the interval of 218 withdrawn, inclusive.
control rods and 231 steps 2. Control Bank A shall be fully withdrawn.
11 ERX-14-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 15 FIGURE 3 K(Z) -NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT H I 1.1 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0.....................................................
4LLW LH I I I I I.I...::: :: : ::: : : : : : : : :: : : : : ; : ' :.................
....................J.1 I I I LLL 1111 1111 Core Height (ft) K(Z)0 0 2 0000 6:0 2:0000 22.0 0.9250 Iii 1 1111 II I 11( 11.........................lii II 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET)TOP 12 ERX-14-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 15 FIGURE 4 w(Z) AS A FUNCTION OF CORE HEIGHT (150 MWD/MTU)1.650 1.600 1.550 1.500 1.450 N 1.400 1.350 1.3001.250 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 W(Z)58 --57 1.2196 56 1.1918 55 1.1817 54 1.1679 53 1.1665 52 1.1661 51 1.1661 50 1.1659 49 1.1646 48 1.1641 47 1.1605 46 1.1544 45 1.1524 Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 W(Z)1.1550 1.1618 1.1648 1.1660 1.1690 1.1734 1.1770 1.1801 1.1820 1.1820 1.1799 1.1760 1.1703 1.1632 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 w(Z)1.1580 1.1579 1.1625 1. 1707 1. 1787 1. 1851 1.1905 1.1948 1.1981 1.2005 1.2019 1. 2025 1.2025 1. 2033 Axial Node 16 15 14 13 12 11 10 9 8 7 6 5 1-4 TOP w(Z)1.2147 1.2377 1.2578 1.2783 1.2984 1.3179 1.3367 1.3545 1.3708 1.3851 1.3964 1.4062 Core Height (ft) = (Node -1)
* 0.2013133 13 ERX-14-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 15 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,4 1.400 1.350 1.300 1.250 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 Nods W(Z)58 --57 1.2944 56 1.2811 55 1.2660 54 1.2473 53 1.2276 52 1.2170 51 1.2129 50 1.2082 49 1.2000 48 1.1901 47 1.1808 46 1.1748 45 1.1691 Axial Nods 44 43 42 41 40 39 38 37 36 35 34 33 32 31 W(Z)1.1648 1.1682 1.1668 1.1623 1.1563 1.1495 1.1460 1.1467 1.1470 1.1450 1.1422 1.1399 1.1373 1.1343 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 w(Z)1.1356 1.1446 1.1570 1.1685 1.1787 1.1879 1.1962 1.2042 1.2116 1.2180 1.2234 1.2284 1.2333 1.2355 Axial Nods 16 15 14 13 12 11 10 9 8 7 6 5 1 -4 TOP w(Z)1.2508 1.2770 1. 3029 1.3292 1. 3552 1.3814 1.4077 1.4329 1.4560 1.4764 1.4927 1.5071 Core Height (ft) = (Node -1)
* 0.2013133 14 ERX-14-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 15 FIGURE 6 W(Z) AS A FUNCTION OF CORE HEIGHT (6,000 MWD/MTU)1.650 1.600 1.550 1.500 1.450 N 1.400 1.3501.3001.250 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 W (Z)58 --57 1.3458 56 1.3396 55 1.3331 54 1.3234 53 1.3115 52 1.2981 51 1.2841 50 1.2697 49 1.2555 48 1.2422 47 1.2277 46 1.2123 45 1.2018 Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 w(Z)1.1980 1.1945 1.1895 1.1832 1.1779 1.1738 1.1692 1.1664 1.1626 1.1564 1.1484 1.1389 1.1308 1.1250 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 W(Z)1.1223 1.1217 1.1211 1.1242 1.1285 1. 1325 1.1364 1. 1395 1.1441 1.1502 1. 1564 1. 1615 1. 1660 1. 1730 Axial Node 16 15 14 13 12 11 10 9 8 7 6 5 1 -4 TOP w(Z)1.1815 1.1975 1.2221 1.2457 1.2693 1.2928 1.3154 1.3369 1.3568 1.3743 1.3881 1.3999 Core Height (ft) = (Node -1)
* 0.2013133 is ERX-14-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 15 FIGURE 7 W(Z) AS A FUNCTION OF CORE HEIGHT (10,000 MWD/MTU)N D 1.650 1.600 1.550 1.500 1.450 1.400 1.350 1.300 1.250 1.200 1.150 1.100 1.050 1.000 I mI IEL. LU -U I 12 -I -I I 2T~2~; ~ ~me ".. I I~I~I. I -I -!I1~I -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. 3601 1.3551 1. 3490 1.3408 1.3315 1.3219 1.3123 1.3026 1.2927 1.2828 1.2733 1.2710 1.2701 Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 w(Z)1.2657 1.2601 1.2531 1.2441 1.2362 1.2306 1.2232 1.2175 1.2103 1.2003 1.1882 1.1742 1.1584 1.1418 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 1IZ)1.1315 1.1309 1.1326 1.1333 1.1329 1.1322 1.1313 1.1297 1.1273 1.1246 1.1228 1.1219 1.1207 1.1196 Axial Node 16 15 14 13 12 11 10 9 a 7 6 5 1 -4 TOP w(Z)1. 1235 1. 1368 1. 1535 1. 1701 1. 1867 1. 2031 1. 2191 1.2343 1.2482 1.2606 1.2699 1.2774 Core Height (ft) = (Node -1)
* 0.2013133 16 ERX-14-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 15 FIGURE 8 W(Z) AS A FUNCTION OF CORE HEIGHT (20,000 JWD/MTU)Ni D 1.650 1.600 1.550 1.500 1.450 1.400 1.350 1.300 1.250 1.200 1.150 1.100 1.050 1.000 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM Axial Node w (Z)58 --57 1.2795 56 1.2808 55 1.2806 54 1.2782 53 1.2747 52 1.2706 51 1.2662 50 1.2619 49 1.2575 48 1.2532 47 1.2523 46 1.2522 45 1.2494 CORE HEIGHT (FEET)Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 W(Z)1.2431 1.2396 1.2420 1.2458 1.2505 1.2561 1. 2591 1.2629 1.2645 1.2624 1.2574 1.2495 1.2391 1.2249 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 w(Z)1.2125 1.2075 1.2065 1.2063 1.2045 1.2006 1.1949 1.1875 1.1786 1.1685 1.1572 1.1456 1.1368 1.1330 Axial Node 16 15 14 13 12 11 10 9 8 7 6 5 1-4 TOP w (Z)1.1333 1.1361 1.1442 1.1533 1.1626 1. 1721 1.1819 1.1917 1.2012 1. 2100 1.2170 1.2221 Core Height (ft) = (Node -1)
* 0.2013133 17 ERX-14-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 15 FIGURE 9 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 100 90 80 70 A.I E4 0 I N p.60 50 40 30 UNACCEPTABLE OOPERATION 20 10 0-40 20 -10 AXIAL FLUX DII 0 10'BERENCE (%)20 30 40 is ERX-14-001, Rev. 0}}

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