CP-201201209, Core Operating Limits Report

From kanterella
Revision as of 04:15, 12 May 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search
Core Operating Limits Report
ML12310A063
Person / Time
Site: Comanche Peak Luminant icon.png
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)
v • d • e


Text

Luminant Rafael Flores Senior Vice President& Chief Nuclear Officer rafael.flores@Luminant.com Luminant Power P 0 Box 1002 6322 North FM 56 Glen Rose, TX 76043 T 254 897 5550 C 817 559 0403 F 254 897 6652 CP-201201209 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 Ref: Tech. Spec. 5.6.5

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
  • 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.5-Date: 6/Reviewed: Reviewed: Somporn Srinilta , 'Principal Engineer, Westinghouse Electric Co.e"ý Date: 2s / " B~ian L. Gu~hrie Engineer, Westinghouse Electric Co.Approved: W tg sr S Date: Ie-vin N. RO'(ind, Acting Manager Westinghouse Engineering Services -q/2S/-Z.0/z 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 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. 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 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. 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)2.8.1 FQ(Z) <F 0 RTP P[K(Z)] for P > 0.5 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 = 2.50 Q 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 FR T 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 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-F4 620 a 600 580 560 0 20 40 60 80 100 120 Percent of Rated Thermal Power 140 10 ERX-12-001, Rev. 0 240 220 200 180'4*4' 160-,-I w 140 44 o 120 H H 02 o 100 al 80 0 60 COLR for CPNPP Unit 2 Cycle 14 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER-10,164) ----(100,146)-- ---- BANK C-B D 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 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-12-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 14 FIGURE 3 K(Z) -NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT N.0 U 1.1 1.0 0.9 0.8 0.7 0.6 0.5 0.4----------

-7T"t- fill Core Height [ft) KW 0 0 1.0000 6:0 1 0000 12.0 0:9250 Lj-.-I...J I I 1 -1 L 0.3 0.2 0.1 0.0 0 1 2 BOTTOM 3 4 5 6 7 8 9 10 11 12 TOP CORE HEIGHT (FEET)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)Ri 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 m--tT-i t-i -I--0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET)TOP Axial Node w( z)58 --57 1.2209 56 1.2162 55 1.1967 54 1.1904 53 1.1714 52 1.1532 51 1.1428 50 1.1360 49 1.1274 48 1.1192 47 1.1173 46 1.1143 45 1.1140 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 1.1523 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 w(z)1.1477 1.1473 1.1503 1.1587 1.1675 1.1746 1.1810 1.1864 1.1910 1.1947 1.1979 1.2002 1.2019 1. 2079 Axial Node 16 15 14 13 12 11 10 9 8 7 6 5 1 -4 w W)1. 2191 1.2369 1.2596 1. 2814 1.3029 1. 3238 1.3439 1.3629 1.3802 1.3954 1.4073 1.4175 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)N3 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 13 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)1.2384 1.2307 1.2240 1.2149 1.2039 1.1913 1. 1771 1.1626 1.1511 1.1441 1.1382 1.1322 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)1.1322 1.1401 1.1519 1.1627 1.1721 1.1807 1.1883 1.1949 1.2005 1.2053 1.2093 1.2123 1.2146 1.2210 Axial Node 16 15 14 13 12 11 10 9 8 7 6 5 1 -4 w(Z)1.2341 1.2564 1.2853 1.3133 1.3412 1.3686 1.3950 1.4200 1.4428 1.4631 1.4791 1.4932 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 1.450 1.400 1.350 1.300 1.250 1.200 1.150 1.100 1.050 1.000 I I I .I ..0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET)TOP Axial Node W(Z)58 --57 1.2768 56 1.2670 55 1.2605 54 1.2535 53 1.2419 52 1.2340 51 1.2266 50 1.2177 49 1.2084 48 1.1978 47 1.1857 46 1.1780 45 1.1766 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 1.1323 1.1267 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 w(z)1.1250 1.1235 1.1235 1.1278 1.1334 1.1379 1.1417 1.1450 1.1476 1.1497 1.1515 1.1545 1.1609 1.1677 Axial Node 16 15 14 13 12 11 10 9 8 7 6 5 1 -4 w(z)1.1759 1.1884 1.2061 1.2271 1.2481 1.2689 1.2892 1.3086 1.3271 1.3438 1.3567 1.3678 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)X 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-n 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)1.2963 1.2905 1.2854 1.2795 1.2719 1.2647 1.2580 1.2542 1.2540 1.2528 1.2475 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 1.1750 1.1606 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 w (z)1.1486 1. 1448 1.1467 1.1482 1.1484 1.1475 1.1456 1.1428 1.1393 1.1350 1.1305 1.1253 1.1199 1.1198 Axial Node 16 15 14 13 12 11 10 9 8 7 6 5 1 -4 TOP w(z)1.1254 1. 1367 1.1518 1.1663 1.1808 1.1951 1.2090 1.2221 1.2342 1.2448 1.2526 1.2584 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 Axial Node W(Z)58 --57 1.2696 56 1.2757 55 1.2692 54 1.2631 53 1.2594 52 1.2559 51 1.2512 50 1.2455 49 1.2393 48 1.2332 47 1.2280 46 1.2256 45 1.2252 CORE HEIGHT (FEET)TOP 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 1.2119 1.2120 1.2099 1.2057 1.1996 1.1918 1.1823 1.1716 1.1596 1.1473 1.1380 1.1348 Axial Node 16 15 14 13 12 11 10 9 8 7 6 5 1 -4 w(z)1.1369 1.1443 1.1519 1.1619 1.1721 1.1822 1.1925 1.2027 1.2126 1.2217 1.2288 1.2339 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 0 0 100 90 80 70 60 50 40 30 (-12,100)-

f-I ,(0'00 UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION*_ IACCEPTABLE

--OPERATION

--(25 (05 20 10 0-40 20 -10 0 10 20 30 40 AXIAL FLUX DIFFERENCE

(%)18 ERX-12-001, Rev. 0

Retrieved from "https://kanterella.com/w/index.php?title=CP-201201209,_Core_Operating_Limits_Report&oldid=1608833"