CP-201300297, Core Operating Limits Report

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Core Operating Limits Report
ML13094A405
Person / Time
Site: Comanche Peak Luminant icon.png
Issue date: 03/18/2013
From: Flores R, Madden F
Luminant Generation Co, Luminant Power
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CP-201300297, TXX-13054
Download: ML13094A405 (24)
v • d • e


Text

Rafael Flores Luminant Power Senior Vice President P 0 Box 1002

& Chief Nuclear Officer 6322 North FM 56 Glen Rose, TX 76043 Lum inant rafael.flores@Luminant.com T 254 897 5550 C 817 559 0403 F 254 897 6652 Ref: 10CFR50.36(c)(5)

CP-201300297 TXX-13054 March 18, 2013 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 2 of the Core Operating Limits Report for Comanche Peak Nuclear Power Plant (CPNPP)

Unit 2, Cycle 14. 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:  : _ _ _ _ _

Fred W. Madden Director, Oversight & Regulatory Affairs Enclosure - Unit 2 Cycle 14 Core Operating Limits Report, Revision 2 c- E. E. Collins, Region IV B. K. Singal, NRR Resident Inspectors, Comanche Peak A member of the STARS Alliance Callaway

  • Comanche Peak
  • Diablo Canyon
  • Palo Verde
  • San Onofre - South Texas Project - Wolf Creek

ERX-12-001, Rev. 2 CPNPP UNIT 2 CYCLE 14 CORE OPERATING LIMITS REPORT February 2013 Prepared: Date:

  • 1 A1* 3/

Daniel E. Broznk Principal Engineer, Westinghouse Electric Co.

Reviewed: Date: 2 / ý Somporn Srinilta Principal Engineer, Westinghouse Electric Co.

Reviewed: Date: Z,-W BzianLGuthr~ie Principal Engineer, Westinghouse Electric Co.

Approved: ___________________ Date: V/26 zo,7 Kevin N. Ro'tand, Acting Manager Westinghouse Engineering Services - Texas

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-12-001, Rev. 2

COLR for CPNPP Unit 2 Cycle 14 TABLE OF CONTENTS DISCLAIMER ...................................................... ji 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

................................................ 8 iii ERX-12-001, Rev. 2

COLR for CPNPP Unit 2 Cycle 14 LIST OF TABLES TABLE PAGE 1 FQ(Z) MARGIN DECREASES IN EXCESS OF 2% PER 31 EFPD .......... 9 iv ERX-12-001, Rev. 2

COLR for CPNPP Unit 2 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 -

(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 -

(12,000 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 V ERX-12-001, Rev. 2

COLR for CPNPP Unit 2 Cycle 14 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for CPNPP UNIT 2 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 SAFETY LIMITS LCO 3.1.1 SHUTDOWN MARGIN LCO 3.1.3 MODERATOR TEMPERATURE COEFFICIENT LCO 3.1.4 ROD GROUP ALIGNMENT LIMITS LCO 3.1.5 SHUTDOWN BANK INSERTION LIMITS LCO 3.1.6 CONTROL BANK INSERTION LIMITS LCO 3.1.8 PHYSICS TESTS EXCEPTIONS - MODE 2 LCO 3.2.1 HEAT FLUX HOT CHANNEL FACTOR LCO 3.2.2 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR LCO 3.2.3 AXIAL FLUX DIFFERENCE LCO 3.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LCO 3.4.1 RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING LIMITS LCO 3.9.1 BORON CONCENTRATION 1 ERX-12-001, Rev. 2

COLR for CPNPP Unit 2 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 through 4 and 7 through 15.

These limits have been determined such that all applicable limits of the safety analysis aremet.

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.f, < 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-12-001, Rev. 2

COLR for CPNPP Unit 2 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-12-001, Rev. 2

COLR for CPNPP Unit 2 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 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)

FRTP F0 2.8.1 F 0 (Z) -< [K(Z)] for P > 0.5 P

RTP F0 F9(Z) < _ [K(Z)] for P < 0.5

0.5 where

P = THERMAL POWER RATED THERMAL POWER 4 ERX-12-001, Rev. 2

COLR for CPNPP Unit 2 Cycle 14 T

2.8.2 F"RP = 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 [ FQC(Z) / K(Z) ],

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.a. A constant factor of 2% shall be used for all cycle burnups that are outside the range of Table 1.

5 ERX-12-001, Rev. 2

COLR for CPNPP Unit 2 Cycle 14 2.9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (FNH)i (LCO 3.2.2) 2.9.1 FNAH 5 FRT PAH [l + PFAH (l-P) where: P = THERMAL POWER RATED THERMAL POWER 2.9.2 F *PAH = 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, = 1.15 K2 = 0.0139 /0 F K3 = 0.00071 /psig TC° = indicated loop specific TC at Rated Thermal Power, OF P1 2235 psig T, 2 10 sec r2 5 3 sec f,(Aq) = -2.78 - {(q,-qb) + 18%} when (q,-qb) S -18% RTP

= 0% when -18% RTP < (q,-qb) < +10.0% RTP

= 2.34 {(q,-q,) - 10.0%) when (q,-qb) ý +10.0% RTP 6 ERX-12-001, Rev. 2

COLR for CPNPP Unit 2 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 2 2220 psig (4 channels) 2 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 °F (4 channels)

S 591 oF (3 channels)

The RCS average temperature limits correspond to the analytical limit of 595.2 '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-12-001, Rev. 2

COLR for CPNPP Unit 2 Cycle 14 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 2!1941 ppm.

3.0 REFERENCES

Technical Specification 5.6.5.

8 ERX-12-001, Rev. 2

COLR for CPNPP Unit 2 Cycle 14 Table 1 FQ(Z) MARGIN DECREASES IN EXCESS OF 2% PER 31 EFPD Cycle Maximum Decrease Burnup In F0 (Z) MARGIN (MWD/MTU) (Percent) 794 2.00 1009 2.30 1224 2.00 7238 2.00 7453 2.10 7668 2.24 7883 2.03 8097 2.00 Note: All cycle burnups outside the range of the table shall use a constant 2% decrease in FQ(Z) margin for compliance with the 3.2.1.2.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-12-001, Rev. 2

COLR for CPNPP Unit 2 Cycle 14 Figure 1 Reactor Core Safety Limits 680O 2445 psig 660 ___ncepa _

SpUnacceptable 640 ____

01985 psig CD W 1845 psig C0 E

620 I600 600 50)-

560 0 20 40 60 80 100 120 140 Percent of Rated Thermal Power 10 ERX-12-001, Rev. 2

COLR for CPNPP Unit 2 Cycle 14 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 240 I I 17TT . i ', m  ! ,i I

', 'i i II I I I ; [ I ;

220 (25.3,218) I / I / / J J ] / ] l / I J l l l(79.6,218)

I I I I i i I I I  ; I - I i ! i i i i i i . . . . . . . . I I ý I . , - j.

I I I I I I [ I* I I ~ ~ .1 ~I I . I . . I . - i I I I - iI i Ii i I i 200 IIVI BANK EB 180 "o I I A I II 1 1:1 0,, 46

-,- 160

' 140 o 120 IDI H

H o 100 (0,34,0 21 ....

rn 80 0

60 40 20 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-12-001, Rev. 2

COLR for CPNPP Unit 2 Cycle 14 FIGURE 3 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.1 I] I I 1.0 0.9 0.8 0.7 z0 0.6 0.5 Core Height (ft) KW 0.4 0.0 1 .0000 6.0 1.0000

-- -- 12.0 0.9250 0.3 I Jj I I 0.2 -I-ti-0.1 0.0 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) TOP 12 ERX-12-001, Rev. 2

COLR for CPNPP Unit 2 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 N 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) TOP Axial Axial Axial Axial Node W (Z) Node w(Z) Node W(Z) Node w(Z) 58 - 61 --- 44 1.1218 30 1.1473 16 1.2604 57 1.2759 43 1.1313 29 1.1477 15 1.2833 56 1.2770 42 1.1411 28 1.1564 14 1.3085 55 1.2659 41 1.1490 27 1.1682 13 1.3330 54 1.2640 40 1.1556 26 1.1795 12 1.3571 53 1.2510 39 1.1614 25 1.1896 11 1.3804 52 1.2328 38 1. 1649 24 1.1988 10 1.4026 51 1.2114 37 1.1687 23 1.2070 9 1.4236 50 1.1877 36 1.1709 22 1.2142 8 1.4427 49 1.1612 35 1.1707 21 1.2205 7 1.4594 48 1.1329 34 1.1686 20 1.2261 6 1.4726 47 1.1192 33 1.1646 19 1.2306 5 1.4840 46 1.1137 32 1.1590 18 1.2345 1 - 4 45 1.1142 31 1.1524 17 1.2436 Core Height (ft) = (Node - 1)
  • 0.2013133 13 ERX-12-001, Rev. 2

COLR for CPNPP Unit 2 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 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) TOP Axial Axial Axial Axial Node w (Z) Node W (Z) Node w(Z) Node w (Z) 58 - 61 44 1.1312 30 1.1320 16 1.2742 57 1.3314 43 1 .1434 29 1.1405 15 1.2901 56 1.3182 42 1.1512 28 1.1552 14 1.3146 55 1.3036 41 1.1550 27 1.1689 13 1.3392 54 1.2841 40 1.1547 26 1.1812 12 1.3675 53 1.2616 39 1 .1508 25 1.1927 11 1.3962 52 1.2359 38 1.1487 24 1.2031 10 1.4233 51 1.2078 37 1.1489 23 1.2131 9 1.4491 50 1.1763 36 1.1483 22 1.2226 8 1.4728 49 1.1504 35 1.1455 21 1.2313 7 1.4938 48 1.1438 34 1.1419 20 1.2390 6 1.5105 47 1.1385 33 1.1388 19 1.2458 5 1.5252 46 1.1321 32 1.1354 18 1.2526 1 - 4 45 1.1294 31 1.1317 17 1.2636 Core Height (ft) = (Node - 1)

  • 0.2013133 14 ERX-12-001, Rev. 2

COLR for CPNPP Unit 2 Cycle 14 FIGURE 6 W(Z) AS A FUNCTION OF CORE HEIGHT (6,000 MWD/MTU) 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 CORE HEIGHT (FEET) TOP Axial Axial Axial Axial Node W(Z) Node w (Z) Node w(Z) Node w(Z) 58 - 61 --- 44 1.1777 30 1.1243 16 1.2153 57 1.3242 43 1.1810 29 1.1242 15 1.2280 56 1.3266 42 1.1847 28 1.1351 14 1.2478 55 1.3249 41 1.1858 27 1.1451 13 1.2715 54 1.3192 40 1.1850 26 1.1535 12 1.2967 53 1.3049 39 1.1835 25 1.1615 11 1.3218 52 1.2850 38 1.1796 24 1.1684 10 1.3459 51 1.2635 37 1.1760 23 1.1745 9 1.3688 50 1.2395 36 1.1708 22 1.1799 8 1.3898 49 1.2153 35 1.1633 21 1.1842 7 1.4084 48 1.1981 34 1.1541 20 1.1885 6 1.4230 47 1.1854 33 1.1433 19 1.1936 5 1.4355 46 1.1781 32 1.1322 18 1.1991 1 - 4 45 1.1766 31 1.1270 17 1.2068 Core Height (ft) = (Node - 1)

  • 0.2013133 15 ERX-12-001, Rev. 2

COLR for CPNPP Unit 2 Cycle 14 FIGURE 7 W(Z) AS A FUNCTION OF CORE HEIGHT (12,000 MWD/MTU) 1.650 1.600 1.550 1.500 1.450 Rr 1.400 1.350 D

1.300 1.250 1.200 1.150 1.100 1.050 1.000 07 01 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) TOP Axial Axial Axial Axial Node w (Z) Node w(Z) Node w(Z) Node w(Z) 58 - 61 44 1.2259 30 1.1489 16 1.1627 57 1.3611 43 1.2252 29 1.1468 15 1.1737 56 1.3552 42 1.2224 28 1.1522 14 1.1889 55 1.3438 41 1.2190 27 1.1562 13 1.2047 54 1.3330 40 1.2178 26 1.1582 12 1 .220.4 53 1.3223 39 1.2175 25 1.1599 11 1.2358 52 1.3094 38 1.2152 24 1.1615 10 1.2507 51 1.2950 37 1.2141 23 1.1620 9 1. 2648 50 1.2767 36 1.2112 22 1.1615 8 1.2779 49 1.2591 35 1.2054 21 1.1604 7 1.2893 48 1.2529 34 1.1974 20 1.1585 6 1.2979 47 1.2474 33 1.1871 19 1.1564 5 1.3044 46 1.2398 32 1.1751 18 1.1549 1 - 4 45 1.2316 31 1.1605 17 1.1567 Core Height (ft) = (Node - 1)

  • 0.2013133 16 ERX-12-001, Rev. 2

COLR for CPNPP Unit 2 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 1.400 1.350

D 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) TOP Axial Axial Axial Axial Node w(Z) Node w(Z) Node w(Z) Node w(Z) 58 - 61 44 1.2249 30 1.2181 16 1.1650 57 1.3319 43 1.2258 29 1.2118 15 1.1706 56 1.3372 42 1.2336 28 1.2118 14 1.1862 55 1.3258 41 1.2421 27 1.2149 13 1.2004 54 1.3153 40 1.2500 26 1.2169 12 1.2144 53 1.3064 39 1.2577 25 1.2167 11 1.2283 52 1.2954 38 1.2625 24 1.2147 10 1.2418 51 1.2813 37 1.2670 23 1.2108 9 1.2548 50 1.2627 36 1.2689 22 1.2052 8 1.2670 49 1.2439 35 1.2673 21 1.1981 7 1.2782 48 1.2334 34 1.2626 20 1.1900 6 1.2867 47 1.2278 33 1.2551 19 1.1807 5 1.2932 46 1.2256 32 1.2449 18 1.1708 1 - 4 45 1.2252 31 1.2312 17 1.1649 Core Height (ft) = (Node - 1)
  • 0.2013133 17 ERX-12-001, Rev. 2

COLR for CPNPP Unit 2 Cycle 14 FIGURE 9 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 100

(- 15,100) (10,100 90 I I Il UNACCEPTABLE - - - - - -- - UNACCEPTABLE OPERATION OPERATION 80 I I- -

i -ACCEPTABLE -- A

'- 'OPERATION i 70

-I 0

(3.

60 - K" I ' -

II , , j 50

(-30,50) - 30,50) 40 0

E- r - -' '

m. 30 20 10 0

-40 -30 -20 -10 0 10 20 30 40 AXIAL FLUX DIFFERENCE (%)

18 ERX-12-001, Rev. 2

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