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

{{#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 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: Reviewed: Daniel E. Brozn k Principal Engineer, Date: 1 3/Westinghouse Electric Co.Date: 2 / ýWestinghouse Electric Co.Somporn Srinilta Principal Engineer, Reviewed: Date: Z,-W BzianLGuthr~ie Principal Engineer, Westinghouse Electric Co.___________________

Date: V/26 zo,7 Kevin N. Ro'tand, Acting 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-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 1 FQ(Z) MARGIN DECREASES IN EXCESS OF 2% PER 31 EFPD .......... PAGE 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 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-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 ARO HZP EOL RTP stands for Beginning of Cycle Life stands for All Rods Out stands for Hot Zero THERMAL POWER stands for End of Cycle Life 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))FRTP F0 2.8.1 F 0 (Z) -< [K(Z)] for P P (LCO 3.2.1)> 0.5 RTP F 0 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 2.8.2 F"R T P = 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 FR T PAH [l + PFAH (l-P)where: P = THERMAL POWER RATED THERMAL POWER 2.9.2 F = 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 K 2 = 0.0139 /0 F K 3 = 0.00071 /psig TC° = indicated loop specific TC at Rated Thermal Power, OF P 1 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 F 0 (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 680 O 2445 psig 660 ___ncepa _SpUnacceptable 640 ____01985 psig I600 CD W 1845 psig C0 E 620 600 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 240 220 I I 17TT (25.3,218) .', i m ', 'i ! , i I I i I I I I ;l(79.6,218) [ I ;I / I / / J J ] / ] l / I J l l 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 .~ ~ ~ I I ..1 I .I I I I .I -I i -i i i i i 200 180"o-' 160-,-' 140 o 120 H H o 100 rn 80 0 60 II VI BANK EB ..I A I II I 1 1:1 0,, 4 6 IDI (0,34,0 21 ....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 z0 1.1 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 I] I I Core Height (ft) K W 0.0 1 .0000 6.0 1.0000----12.0 0.9250 I Jj I I-I-ti-0 1 BOTTOM 2 3 4 5 6 7 CORE HEIGHT (FEET)8 9 10 11 12 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 1.3001.250 1.200 1.150 1.100 1.050 1.000 0 9 1 2 3 4 5 6 7 8 10 11 12 BOTTOM CORE HEIGHT (FEET)TOP Axial Node W (Z)58 --57 1.2759 56 1.2770 55 1.2659 54 1.2640 53 1.2510 52 1.2328 51 1.2114 50 1.1877 49 1.1612 48 1.1329 47 1.1192 46 1.1137 45 1.1142 Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 w(Z)1.1218 1.1313 1.1411 1.1490 1.1556 1.1614 1. 1649 1.1687 1.1709 1.1707 1.1686 1.1646 1.1590 1.1524 Axial Node W(Z)30 1.1473 29 1.1477 28 1.1564 27 1.1682 26 1.1795 25 1.1896 24 1.1988 23 1.2070 22 1.2142 21 1.2205 20 1.2261 19 1.2306 18 1.2345 17 1.2436 Axial Node 16 15 14 13 12 11 10 9 8 7 6 5 1 -4 w(Z)1.2604 1.2833 1.3085 1.3330 1.3571 1.3804 1.4026 1.4236 1.4427 1.4594 1.4726 1.4840 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)N 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)Axial Node 58 -61 57 56 55 54 53 52 51 50 49 48 47 46 45 w (Z)1.3314 1.3182 1.3036 1.2841 1.2616 1.2359 1.2078 1.1763 1.1504 1.1438 1.1385 1.1321 1.1294 Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 W (Z)1.1312 1 .1434 1.1512 1.1550 1.1547 1 .1508 1.1487 1.1489 1.1483 1.1455 1.1419 1.1388 1.1354 1.1317 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 w(Z)1.1320 1.1405 1.1552 1.1689 1.1812 1.1927 1.2031 1.2131 1.2226 1.2313 1.2390 1.2458 1.2526 1.2636 Axial Node 16 15 14 13 12 11 10 9 8 7 6 5 1 -4 TOP w (Z)1.2742 1.2901 1.3146 1.3392 1.3675 1.3962 1.4233 1.4491 1.4728 1.4938 1.5105 1.5252 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 Axial Node W(Z)58 --57 1.3242 56 1.3266 55 1.3249 54 1.3192 53 1.3049 52 1.2850 51 1.2635 50 1.2395 49 1.2153 48 1.1981 47 1.1854 46 1.1781 45 1.1766 CORE HEIGHT (FEET)Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 w (Z)1.1777 1.1810 1.1847 1.1858 1.1850 1.1835 1.1796 1.1760 1.1708 1.1633 1.1541 1.1433 1.1322 1.1270 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 w(Z)1.1243 1.1242 1.1351 1.1451 1.1535 1.1615 1.1684 1.1745 1.1799 1.1842 1.1885 1.1936 1.1991 1.2068 Axial Node 16 15 14 13 12 11 10 9 8 7 6 5 1 -4 TOP w(Z)1.2153 1.2280 1.2478 1.2715 1.2967 1.3218 1.3459 1.3688 1.3898 1.4084 1.4230 1.4355 Core Height (ft) = (Node -1)
  • 0.2013133 15 ERX-12-001, Rev. 2 COLR for CPNPP Unit 2 Cycle 14 Rr 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 FIGURE 7 W(Z) AS A FUNCTION OF CORE HEIGHT (12,000 MWD/MTU)07 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET)TOP Axial Node 58 -61 57 56 55 54 53 52 51 50 49 48 47 46 45 w (Z)1.3611 1.3552 1.3438 1.3330 1.3223 1.3094 1.2950 1.2767 1.2591 1.2529 1.2474 1.2398 1.2316 Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 w(Z)1.2259 1.2252 1.2224 1.2190 1.2178 1.2175 1.2152 1.2141 1.2112 1.2054 1.1974 1.1871 1.1751 1.1605 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 w(Z)1.1489 1.1468 1.1522 1.1562 1.1582 1.1599 1.1615 1.1620 1.1615 1.1604 1.1585 1.1564 1.1549 1.1567 Axial Node 16 15 14 13 12 11 10 9 8 7 6 5 1 -4 w(Z)1.1627 1.1737 1.1889 1.2047 1 .220.4 1.2358 1.2507 1. 2648 1.2779 1.2893 1.2979 1.3044 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):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 CORE HEIGHT (FEET)Axial Node 58 -61 57 56 55 54 53 52 51 50 49 48 47 46 45 w(Z)1.3319 1.3372 1.3258 1.3153 1.3064 1.2954 1.2813 1.2627 1.2439 1.2334 1.2278 1.2256 1.2252 Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 w(Z)1.2249 1.2258 1.2336 1.2421 1.2500 1.2577 1.2625 1.2670 1.2689 1.2673 1.2626 1.2551 1.2449 1.2312 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 w(Z)1.2181 1.2118 1.2118 1.2149 1.2169 1.2167 1.2147 1.2108 1.2052 1.1981 1.1900 1.1807 1.1708 1.1649 Axial Node 16 15 14 13 12 11 10 9 8 7 6 5 1 -4 TOP w(Z)1.1650 1.1706 1.1862 1.2004 1.2144 1.2283 1.2418 1.2548 1.2670 1.2782 1.2867 1.2932 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 90 80 70 0 (3.0 E-m.60 50 40 30 (- 15,100) (10,100 I I Il UNACCEPTABLE

-UNACCEPTABLE OPERATION OPERATION I I- -i -ACCEPTABLE

-- A'- 'OPERATION i--.. .. .- -I-K I " ' -I I , j , (-30,50) -30,50)r --' '20 10 0-40-30 10 0 10 20 AXIAL FLUX DIFFERENCE (%)30 40 18 ERX-12-001, Rev. 2}}

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