CP-201201209, Core Operating Limits Report
| ML12310A063 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 10/22/2012 |
| From: | Flores R Luminant Generation Co, Luminant Power |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CP-201201209, TXX-12147 | |
| Download: ML12310A063 (24) | |
Text
Rafael Flores Luminant Power Senior Vice President P 0 Box 1002
& Chief Nuclear Officer 6322 North FM 56 rafael.flores@Luminant.com Glen Rose, TX 76043 Luminant T 254 897 5550 C 817 559 0403 F 254 897 6652 CP-201201209 Ref: Tech. Spec. 5.6.5 TXX-12147 October 22, 2012 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT DOCKET NO. 50-446 CORE OPERATING LIMITS REPORT
Dear Sir or Madam:
Enclosed is 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: F W. Madden Director, Oversight & Regulatory Affairs Enclosure - Unit 2 Cycle 14 Core Operating Limits Report c- E. E. Collins, Region W 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 1J4,1
ERX-12-001, Rev. 0 CPNPP UNIT 2 CYCLE 14 CORE OPERATING LIMITS REPORT September 2012 Prepared: ** Date: 5-d-Daniel E. Brozak Principal Engineer, Westinghouse Electric Co.
Reviewed: 5- Date: 6/
Somporn Srinilta ,'
Principal Engineer, Westinghouse Electric Co.
Reviewed: e"ý Date: 2s / "
B~ian L. Gu~hrie
- rincipal Engineer, Westinghouse Electric Co.
Approved: W tg sr S Date:
q/2S/-Z.0/z Ie-vin N. RO'(ind, 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. 0
COLR for CPNPP Unit 2 Cycle 14 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
................................................ 8 iii ERX-12-001, Rev. 0
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. 0
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. 0
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. 0
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 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-12-001, Rev. 0
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. 0
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)
F0 RTP 2.8.1 FQ(Z) < [K(Z)] for P > 0.5 P
FItTP F0 F, (Z) < [K (Z)J for P 5 0.5
0.5 where
P = THERMAL POWER RATED THERMAL POWER 4 ERX-12-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 14 2.8.2 F.RTP Q
= 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 [ Fc(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. 0
COLR for CPNPP Unit 2 Cycle 14 2.9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (F"ANjI (LCO 3.2.2) 2.9.1 F"AH 5 FpRPAH [I + PFAH (1-P)]
where: P = THERMAL POWER RATED THERMAL POWER 2.9.2 FRT 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; KI = 1.15 K = 0.0139 /[F K3 = 0.00071 /psig T° = indicated loop specific T at Rated Thermal Power, OF P' a 2235 psig T ?* 10 sec T2 5 3 sec fj(Aq) = -2.78 * {(qý-q) + 18%) when (q,-q*) S -18% RTP
= 0% when -18% RTP < (qý-qb) < +10.0% RTP
= 2.34 *{(q.-,) - 10.0%) when (qt-q,) ? +10.0% RTP 6 ERX-12-001, Rev. 0
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 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 'F (4 channels)
S 591 °F (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. 0
COLR for CPNPP Unit 2 Cycle 14 2.12.4 SR 3.4.1.3 The RCS total flow rate shall be ý 408,000 gpm.
2.12.5 SR 3.4.1.4 The RCS total flow rate based on precision heat balance shall be ý 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 a1941 ppm.
3.0 REFERENCES
Technical Specification 5.6.5.
8 ERX-12-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 14 Table 1 F.(Z) MARGIN DECREASES IN EXCESS OF 2% PER 31 EFPD Cycle Maximum Decrease Burnup In F. (Z) MARGIN (MWD/MTU) (Percent) 0 2.48 150 2.48 365 2.66 580 2.71 794 2.62 1009 2.38 1224 2.19 1439 2.15 1654 2.01 1868 2.00 2513 2.00 2728 2.01 2942 2.00 Note: All cycle burnups outside the range of the table shall use a constant 2% decrease in F,(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. 0
COLR for CPNPP Unit 2 Cycle 14 Figure 1 Reactor Core Safety Limits 680 660 640 U-a F4 620 600 580 560 0 20 40 60 80 100 120 140 Percent of Rated Thermal Power 10 ERX-12-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 14 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 240 220 200 180
'4
- 4' 160 - 10,164) - - -
-,-I
- (100,146) w 140 44
- - -- BANK C o 120 H
H o 100 02 al 80 0 - B ANK*D 60 ozi 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. 0
COLR for CPNPP Unit 2 Cycle 14 FIGURE 3 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.1 1.0
-7T"t-0.9 0.8 0.7 N.
0.6 U
0 0.5 fill Core Height [ft) KW 0.4 0 0 1.0000 6:0 1 0000 12.0 0:9250 0.3 Lj 0.2 0.1
-.- I...J I I 1-1 L 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. 0
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 m--tT 1.450 Ri 1.400 1.350 1.300 1.250 1.200 - i t-i -I--
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 W) 58 - 61 --- 44 1.1218 30 1.1477 16 1. 2191 57 1.2209 43 1.1313 29 1.1473 15 1.2369 56 1.2162 42 1.1411 28 1.1503 14 1.2596 55 1.1967 41 1.1490 27 1.1587 13 1. 2814 54 1.1904 40 1.1556 26 1.1675 12 1.3029 53 1.1714 39 1.1614 25 1.1746 11 1. 3238 52 1.1532 38 1.1649 24 1.1810 10 1.3439 51 1.1428 37 1.1687 23 1.1864 9 1.3629 50 1.1360 36 1.1709 22 1.1910 8 1.3802 49 1.1274 35 1.1707 21 1.1947 7 1.3954 48 1.1192 34 1.1686 20 1.1979 6 1.4073 47 1.1173 33 1.1646 19 1.2002 5 1.4175 46 1.1143 32 1.1590 18 1.2019 1 - 4 45 1.1140 31 1.1523 17 1. 2079 Core Height (ft) = (Node - 1)
- 0.2013133 13 ERX-12-001, Rev. 0
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 1.400 13 N3 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 1.1322 16 1.2341 57 1.2384 43 1.1434 29 1.1401 15 1.2564 56 1.2307 42 1.1512 28 1.1519 14 1.2853 55 1.2240 41 1.1550 27 1.1627 13 1.3133 54 1.2149 40 1.1547 26 1.1721 12 1.3412 53 1.2039 39 1.1508 25 1.1807 11 1.3686 52 1.1913 38 1.1487 24 1.1883 10 1.3950 51 1. 1771 37 1.1489 23 1.1949 9 1.4200 50 1.1626 36 1.1483 22 1.2005 8 1.4428 49 1.1511 35 1.1455 21 1.2053 7 1.4631 48 1.1441 34 1.1419 20 1.2093 6 1.4791 47 1.1382 33 1.1388 19 1.2123 5 1.4932 46 1.1322 32 1.1354 18 1.2146 1 - 4 45 1.1294 31 1.1317 17 1.2210 Core Height (ft) = (Node - 1)
- 0.2013133 14 ERX-12-001, Rev. 0
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 I I 1.450 1.400 1.350 1.300 1.250 1.200 1.150 1.100 1.050 1.000 I . I . .
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 1.1250 16 1.1759 57 1.2768 43 1.1810 29 1.1235 15 1.1884 56 1.2670 42 1.1847 28 1.1235 14 1.2061 55 1.2605 41 1.1858 27 1.1278 13 1.2271 54 1.2535 40 1.1850 26 1.1334 12 1.2481 53 1.2419 39 1.1835 25 1.1379 11 1.2689 52 1.2340 38 1.1796 24 1.1417 10 1.2892 51 1.2266 37 1.1760 23 1.1450 9 1.3086 50 1.2177 36 1.1708 22 1.1476 8 1.3271 49 1.2084 35 1.1633 21 1.1497 7 1.3438 48 1.1978 34 1.1541 20 1.1515 6 1.3567 47 1.1857 33 1.1433 19 1.1545 5 1.3678 46 1.1780 32 1.1323 18 1.1609 1 - 4 45 1.1766 31 1.1267 17 1.1677 Core Height (ft) = (Node - 1)
- 0.2013133 is ERX-12-001, Rev. 0
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
-n 1.500 1.450 1.400 1.350 1.300 X
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 1.2259 30 1.1486 16 1.1254 57 1.2963 43 1.2252 29 1. 1448 15 1. 1367 56 1.2905 42 1.2224 28 1.1467 14 1.1518 55 1.2854 41 1.2190 27 1.1482 13 1.1663 54 1.2795 40 1.2178 26 1.1484 12 1.1808 53 1.2719 39 1.2175 25 1.1475 11 1.1951 52 1.2647 38 1.2152 24 1.1456 10 1.2090 51 1.2580 37 1.2141 23 1.1428 9 1.2221 50 1.2542 36 1.2112 22 1.1393 8 1.2342 49 1.2540 35 1.2054 21 1.1350 7 1.2448 48 1.2528 34 1.1974 20 1.1305 6 1.2526 47 1.2475 33 1.1871 19 1.1253 5 1.2584 46 1.2398 32 1.1750 18 1.1199 1 - 4 45 1.2316 31 1.1606 17 1.1198 Core Height (ft) = (Node - 1)
- 0.2013133 16 ERX-12-001, Rev. 0
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 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 1.1369 57 1.2696 43 1.2258 29 1.2118 15 1.1443 56 1.2757 42 1.2336 28 1.2119 14 1.1519 55 1.2692 41 1.2421 27 1.2120 13 1.1619 54 1.2631 40 1.2500 26 1.2099 12 1.1721 53 1.2594 39 1.2577 25 1.2057 11 1.1822 52 1.2559 38 1. 2625 24 1.1996 10 1.1925 51 1.2512 37 1.2670 23 1.1918 9 1.2027 50 1.2455 36 1. 2689 22 1.1823 8 1.2126 49 1.2393 35 1. 2673 21 1.1716 7 1.2217 48 1.2332 34 1.2626 20 1.1596 6 1.2288 47 1.2280 33 1.2551 19 1.1473 5 1.2339 46 1.2256 32 1.2449 18 1.1380 1 - 4 45 1.2252 31 1.2312 17 1.1348 Core Height (ft) = (Node - 1)
- 0.2013133 17 ERX-12-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 14 FIGURE 9 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 100
(-12,100)- f-I ,(0'00 90 UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION 80
- _ IACCEPTABLE
- - OPERATION --
70 0 60 50 (05 (25 40 0
30 20 10 0
-40 -30 -20 -10 0 10 20 30 40 AXIAL FLUX DIFFERENCE (%)
18 ERX-12-001, Rev. 0