CP-202300201, (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 0)
| ML23124A117 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 05/04/2023 |
| From: | Hicks J Luminant, Vistra Operating Co. (VistraOpCo) |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| CP-202300201, TXX-23028 ERX-23-001, Rev.. 0 | |
| Download: ML23124A117 (1) | |
Text
m Jack C. Hicks Manager, Regulatory Affairs Comanche Peak Nuclear Power Plant (Vistra Operations Luminant Company LLC)
P.O. Box 1002 6322 North FM 56 Glen Rose, TX 76043 T 254.897.6725 CP-202300201 TXX-23028 May 4th, 2023 A TIN: Document Control Desk Ref 10 CFR 50.36(c)(5)
U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Comanche Peak Nuclear Power Plant (CPNPP)
Docket No. 50-446 Core Operating Limits Report (COLR), Unit 2 Cycle 21, (ERX-23-001, Revision 0)
Dear Sir of Madam:
Enclosed is the Core Operating Limits Report (COLR) for Comanche Peak Nuclear Power Plant (CPNPP) Unit 2, Cycle 21, (ERX-23-001, Rev. 0). This report is prepared and submitted pursuant to Technical Specification 5.6.5.
This communication contains no new commihnents regarding CPNPP Unit 2.
Should you have any questions, please contact Nie Boehmisch at (254) 897-5064 or nicholas.boelunisch@luminant.com.
TXX-23028 Page 2 of 2 Sincerely,
Enclosure:
Unit 2 Cycle 21 Core Operating Limits Report, (ERX-23-001, Rev. 0) c (email) - Robert Lewis, Region IV [Robert.Lewis@nrc.gov]
Dennis Galvin, NRR [Dennis.Galvin@nrc.gov]
John Ellegood, Senior Resident Inspector, CPNPP Uohn.Ellegood@nrc.gov]
David Nani, Resident Inspector, CPNPP [David.Nani@nrc.gov]
ZRX-29-001, Rev. 0 G9N2P UNIT 2 CyCU8 21 CORE OPERATING LD£ITS REPORT Niril 2023
,;,.= q-/?'-ZaZ3 Engineer , Westinghouse Electric Gang>any, LLC .
,,,,,, Daniel
\:sSCS#b E . Brozak
,b, . 't/it/zoea Principal Engineer , Westinghouse Electric Con>any , LLC .
Ga%%
,,, Parvez Salih M'HJ , ,,b, 44//7/2023 Principal Engineer , Westinghouse Electric Conpany , T,Tn .
Approved, K&M /&hZ Date , 4/1 8/2023 Kevin N, Roland, Manager Westinghouse Integrated Site Engineering - TX/KS
DISCLAIMER The information contained in this report was prepared for the specific requirement of Vistra Operations Company LLC and may not be appropriate for use in situations other than those for which it was specifically prepared. Vistra Operations 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, Vistra Operations Company LLC does not authorize its use by others, and any such use is forbidden except with the prior written approval of Vistra Operations 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 Vistra Operations 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-23-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 21 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 (SLs) ................................... 2 2.2 SHUTDOWN MARGIN (SDM) ................................. 2 2.3 MODERATOR TEMPERATURE COEFFICIENT (MTC) .............. 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 (FQ(Z)) .................. 4 2.9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (FNH) ........ 6 2.10 AXIAL FLUX DIFFERENCE (AFD) .......................... 6 2.11 REACTOR TRIP SYSTEM (RTS) INSTRUMENTATION ............ 6 2.12 RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING (DNB) LIMITS ........................ 7 2.13 BORON CONCENTRATION .................................. 8
3.0 REFERENCES
................................................ 8 iii ERX-23-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 21 LIST OF TABLES TABLE PAGE 1 FQ(Z) MARGIN DECREASES IN EXCESS OF 2% PER 31 EFPD .......... 9 iv ERX-23-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 21 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 -
(5,000 MWD/MTU) ......................................... 14 6 W(Z) AS A FUNCTION OF CORE HEIGHT -
(11,000 MWD/MTU) ........................................ 15 7 W(Z) AS A FUNCTION OF CORE HEIGHT -
(14,000 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-23-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 21 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for CPNPP UNIT 2 CYCLE 21 has been prepared in accordance with the requirements of Technical Specification 5.6.5.
The Technical Specifications affected by this report are listed below:
LCO 3.1.1 SHUTDOWN MARGIN (SDM)
LCO 3.1.3 MODERATOR TEMPERATURE COEFFICIENT (MTC)
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 (FQ(Z))
LCO 3.2.2 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (FNH)
LCO 3.2.3 AXIAL FLUX DIFFERENCE (AFD)
LCO 3.3.1 REACTOR TRIP SYSTEM (RTS) INSTRUMENTATION LCO 3.4.1 RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING (DNB) LIMITS LCO 3.9.1 BORON CONCENTRATION 1 ERX-23-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 21 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 (SLs) (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% k/k in MODE 2 with Keff < 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-23-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 21 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% k/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.
2.5.2 The SDM shall be greater than or equal to 1.3% k/k in MODE 1, MODE 2 with any control bank not fully inserted.
3 ERX-23-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 21 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.
2.6.4 The SDM shall be greater than or equal to 1.3% k/k in MODE 1, MODE 2 with keff 1.0.
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% k/k in MODE 2 during PHYSICS TESTS.
2.8 HEAT FLUX HOT CHANNEL FACTOR (FQ(Z)) (LCO 3.2.1)
FQRTP 2.8.1 FQ(Z) [K(Z)] for P > 0.5 P
FQRTP FQ(Z) [K(Z)] for P 0.5
0.5 where
P = THERMAL POWER RATED THERMAL POWER 4 ERX-23-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 21 2.8.2 FQRTP = 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, Note a. A constant factor of 2% shall be used for all cycle burnups that are outside the range of Table 1.
5 ERX-23-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 21 2.9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (FNH) (LCO 3.2.2) 2.9.1 FNH FRTPH [1 + PFH (1-P)]
where: P = THERMAL POWER RATED THERMAL POWER 2.9.2 FRTPH = 1.60 for all Fuel Assembly Regions 2.9.3 PFH = 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; K1 = 1.15 K2 = 0.0139 /oF K3 = 0.00071 /psig Tc o = indicated loop specific Tc at Rated Thermal Power, °F P1 2235 psig 1 10 sec 2 3 sec f1(q) = -2.78 {(qt-qb) + 18%} when (qt-qb) -18% RTP
= 0% when -18% RTP < (qt-qb) < +10.0% RTP
= 2.34 {(qt-qb) - 10.0%} when (qt-qb) +10.0% RTP 6 ERX-23-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 21 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 2220 psig (4 channels) 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 592 oF (4 channels) 591 oF (3 channels)
The RCS average temperature limits correspond to the analytical limit of 595.2 oF 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-23-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 21 2.12.4 SR 3.4.1.3 The RCS total flow rate shall be 408,000 gpm.
2.12.5 SR 3.4.1.4 The RCS total flow rate based on precision heat balance shall be 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 1915 ppm.
3.0 REFERENCES
Technical Specification 5.6.5.
8 ERX-23-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 21 Table 1 FQ(Z) MARGIN DECREASES IN EXCESS OF 2% PER 31 EFPD Cycle Maximum Decrease Burnup In FQ(Z) MARGIN (MWD/MTU) (Percent) 0 3.11 150 3.11 366 5.76 581 7.82 797 8.28 1012 8.17 1228 7.51 1444 6.54 1659 5.45 1875 4.52 2091 4.40 2306 4.05 2522 3.47 2737 2.86 2953 2.27 3169 2.00 6834 2.00 7050 2.22 7265 2.58 7481 2.95 7697 3.24 7912 3.37 8128 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 Surveillance Requirement 3.2.1.2, Note a. Linear interpolation is acceptable to determine the FQ(Z) margin decrease for cycle burnups which fall between the specified burnups.
9 ERX-23-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 21 Figure 1 Reactor Core Safety Limits 680 2445 psig 660 Unacceptable 2235 psig 640 RCS Average Temperature (°F) 1985 psig 1845 psig 620 Acceptable 600 580 560 0 20 40 60 80 100 120 140 Percent of Rated Thermal Power 10 ERX-23-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 21 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 240 220 (25.3,218) (79.6,218) 200 BANK B ROD BANK POSITION (steps withdrawn) 180 160 (0,164)
(100,146) 140 BANK C 120 100 80 BANK D 60 (0,49) 40 20 (31,0) 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-23-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 21 FIGURE 3 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.1 1.0 0.9 0.8 K(Z) - NORMALIZED FQ(Z) 0.7 0.6 0.5 Core Height (ft) K(Z) 0.4 0.0 1.0000 6.0 1.0000 12.0 0.9250 0.3 0.2 0.1 0.0 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) TOP 12 ERX-23-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 21 FIGURE 4 W(Z) AS A FUNCTION OF CORE HEIGHT (150 MWD/MTU) 1.650 1.600 1.550 1.500 1.450 MAXIMUM W(Z) 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 1.1660 30 1.1462 16 1.1844 57 1.2133 43 1.1707 29 1.1459 15 1.2017 56 1.2121 42 1.1730 28 1.1483 14 1.2212 55 1.2093 41 1.1788 27 1.1534 13 1.2399 54 1.2112 40 1.1842 26 1.1569 12 1.2588 53 1.2159 39 1.1864 25 1.1595 11 1.2774 52 1.2135 38 1.1871 24 1.1611 10 1.2954 51 1.2085 37 1.1853 23 1.1623 9 1.3120 50 1.1991 36 1.1819 22 1.1629 8 1.3274 49 1.1916 35 1.1769 21 1.1630 7 1.3409 48 1.1837 34 1.1698 20 1.1622 6 1.3518 47 1.1753 33 1.1617 19 1.1648 5 1.3617 46 1.1720 32 1.1553 18 1.1714 1 - 4 ---
45 1.1651 31 1.1486 17 1.1762 Core Height (ft) = (Node - 1)
- 0.2012 13 ERX-23-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 21 FIGURE 5 W(Z) AS A FUNCTION OF CORE HEIGHT (5,000 MWD/MTU) 1.650 1.600 1.550 1.500 1.450 1.400 MAXIMUM W(Z) 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 1.1529 30 1.1156 16 1.2041 57 1.2355 43 1.1547 29 1.1172 15 1.2148 56 1.2320 42 1.1558 28 1.1207 14 1.2380 55 1.2276 41 1.1548 27 1.1280 13 1.2640 54 1.2205 40 1.1534 26 1.1347 12 1.2902 53 1.2124 39 1.1487 25 1.1408 11 1.3160 52 1.2071 38 1.1451 24 1.1464 10 1.3412 51 1.1993 37 1.1397 23 1.1515 9 1.3647 50 1.1916 36 1.1330 22 1.1560 8 1.3865 49 1.1852 35 1.1267 21 1.1638 7 1.4059 48 1.1763 34 1.1226 20 1.1740 6 1.4220 47 1.1684 33 1.1198 19 1.1827 5 1.4355 46 1.1598 32 1.1185 18 1.1907 1 - 4 ---
45 1.1533 31 1.1166 17 1.1980 Core Height (ft) = (Node - 1)
- 0.2012 14 ERX-23-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 21 FIGURE 6 W(Z) AS A FUNCTION OF CORE HEIGHT (11,000 MWD/MTU) 1.650 1.600 1.550 1.500 1.450 MAXIMUM W(Z) 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 1.2481 30 1.1362 16 1.1410 57 1.3135 43 1.2444 29 1.1313 15 1.1492 56 1.3104 42 1.2421 28 1.1329 14 1.1613 55 1.3125 41 1.2341 27 1.1336 13 1.1744 54 1.3119 40 1.2271 26 1.1338 12 1.1880 53 1.3127 39 1.2193 25 1.1341 11 1.2005 52 1.3092 38 1.2167 24 1.1338 10 1.2145 51 1.3061 37 1.2138 23 1.1329 9 1.2285 50 1.2998 36 1.2074 22 1.1313 8 1.2416 49 1.2901 35 1.1994 21 1.1307 7 1.2532 48 1.2816 34 1.1893 20 1.1322 6 1.2625 47 1.2721 33 1.1772 19 1.1344 5 1.2699 46 1.2645 32 1.1634 18 1.1361 1 - 4 ---
45 1.2564 31 1.1483 17 1.1372 Core Height (ft) = (Node - 1)
- 0.2012 15 ERX-23-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 21 FIGURE 7 W(Z) AS A FUNCTION OF CORE HEIGHT (14,000 MWD/MTU) 1.650 1.600 1.550 1.500 1.450 MAXIMUM W(Z) 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 1.2348 30 1.1597 16 1.1426 57 1.3002 43 1.2299 29 1.1590 15 1.1560 56 1.2952 42 1.2302 28 1.1621 14 1.1695 55 1.3029 41 1.2266 27 1.1638 13 1.1833 54 1.3003 40 1.2265 26 1.1641 12 1.1973 53 1.2922 39 1.2248 25 1.1633 11 1.2099 52 1.2899 38 1.2259 24 1.1613 10 1.2218 51 1.2861 37 1.2261 23 1.1582 9 1.2334 50 1.2787 36 1.2226 22 1.1543 8 1.2444 49 1.2722 35 1.2173 21 1.1500 7 1.2541 48 1.2654 34 1.2096 20 1.1440 6 1.2618 47 1.2675 33 1.1997 19 1.1377 5 1.2679 46 1.2615 32 1.1875 18 1.1363 1 - 4 ---
45 1.2495 31 1.1739 17 1.1360 Core Height (ft) = (Node - 1)
- 0.2012 16 ERX-23-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 21 FIGURE 8 W(Z) AS A FUNCTION OF CORE HEIGHT (20,000 MWD/MTU) 1.650 1.600 1.550 1.500 1.450 MAXIMUM W(Z) 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 -- 44 1.2311 30 1.2194 16 1.1321 57 1.2456 43 1.2370 29 1.2161 15 1.1381 56 1.2463 42 1.2477 28 1.2116 14 1.1493 55 1.2506 41 1.2529 27 1.2086 13 1.1613 54 1.2460 40 1.2599 26 1.2038 12 1.1736 53 1.2388 39 1.2649 25 1.1988 11 1.1840 52 1.2359 38 1.2717 24 1.1922 10 1.1938 51 1.2367 37 1.2761 23 1.1841 9 1.2039 50 1.2355 36 1.2758 22 1.1758 8 1.2139 49 1.2334 35 1.2733 21 1.1688 7 1.2231 48 1.2304 34 1.2680 20 1.1606 6 1.2308 47 1.2425 33 1.2597 19 1.1506 5 1.2373 46 1.2525 32 1.2481 18 1.1403 1 - 4 ---
45 1.2390 31 1.2346 17 1.1330 Core Height (ft) = (Node - 1)
- 0.2012 17 ERX-23-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 21 FIGURE 9 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 100
(-12,100) (10,100) 90 UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION 80 ACCEPTABLE OPERATION 70 PERCENT OF RATED THERMAL POWER 60 50
(-25,50) (20,50) 40 30 20 10 0
-40 -30 -20 -10 0 10 20 30 40 AXIAL FLUX DIFFERENCE (%)
18 ERX-23-001, Rev. 0