CP-200901404, Core Operating Limits

Core Operating Limits

ML093140096
Person / Time
Site:	Comanche Peak
Issue date:	11/02/2009
From:	Madden F Luminant Generation Co, Luminant Power
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CP-200901404, TXX-09129 ERX-09-001, Rev 0
Download: ML093140096 (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-200901404 Ref: Tech. Spec. 5.6.5 TXX-09129 November 2, 2009 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NO. 50-446 CORE OPERATING LIMITS REPORTS

Dear Sir or Madam:

Enclosed is the Core Operating Limits Reports for Comanche Peak Steam Electric Station, herein referred to as Comanche Peak Nuclear Power Plant (CPNPP) Unit 2, Cycle 12. This report is prepared and submitted pursuant to Technical Specification 5.6.5.

This communication contains no new licensing basis commitments regarding CPNPP Units 1 and 2. Should you have any questions, please contact Mr. J. D. Seawright at (254) 897-0140.

Sincerely, Luminant Generation Company LLC Rafael Flores By: A, 27 h,,

/Fred W. Madden "

Director, Oversight & Regulatory Affairs c- E. E. Collins, Region IV B. K. Singal, NRR Resident Inspectors, Comanche Peak A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

• Comanche Peak

• Diablo Canyon ' Palo Verde San Onofre

• South Texas Project ' Wolf Creek ACMY.ý I

ERX-09-001, Rev. 0 CPNPP UNIT 2 CYCLE 12 CORE OPERATING LIMITS REPORT September 2009 Prepared . - Date: _-__ 0oo0

\Jo than M. Ralston P ncipal Engineer, Westinghouse Electric Co.

Reviewed: '. 4 . Date: 9-23, Daniel E. Brozak Principal Engineer, Westinghouse Electric Co.

Reviewed: Date: q/*j' I evin N. RaTand Principal Engineer, Westinghouse Electric Co.

Approved: 41/_ Date: op/2J/O P.

W.4James Boq~wright, 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-09-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 12 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 ................ 5 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-09-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 12 LIST OF TABLES TABLE PAGE 1 FQ (Z) MARGIN DECREASES IN EXCESS OF 2% PER 31 EFPD .......... 9 iv ERX-09-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 12 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 -

(4,000 MWD/MTU) ......................................... 14 6 W(Z) AS A FUNCTION OF CORE HEIGHT -

(7,000 MWD/MTU) ......................................... 15 7 W(Z) AS A FUNCTION OF CORE HEIGHT -

(11,000 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-09-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 12 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for CPNPP UNIT 2 CYCLE 12 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 3.2.1.2 HEAT FLUX HOT CHANNEL FACTOR LCO 3.2.2 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR LCO 3.2.3.2 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-09-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 12 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, 2, 14, 16 and 21 through 29.

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 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-09-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 12 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-09-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 12 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)

RTP FQ 2.8.1 FQ(Z) -<(K (Z)] for P > 0.5 P

RTP FQ FQ (Z) -< [K(Z)] for P S 0.5

0.5 where

P = £HERMAL POWER RATE:D THERMAL POWER 4 ERX-09-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 12 2.8.2 F = 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. The burnup dependent values can be used to interpolate or extrapolate (via a three point fit) the W(Z) at a particular burnup.

2.8.5 SR 3.2.1.2.2 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 3.2.1.2.2.a. A constant factor of 2% shall be used for all cycle burnups that are outside the range of Table 1.

2.9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (FNAHI (LCO 3.2.2)

T 2.9.1 FNAH -5 FR PAH [1 + PFAH (l-P)]

where: P = THERMAL POWER RATED THERMAL POWER T

2.9.2 FR PAH = 1.60 for all Fuel Assembly Regions 2.9.3 PFAH = 0.3 5 ERX-09-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 12 2.10 AXIAL FLUX DIFFERENCE (AFD) (LCO 3.2.3.2) 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 /°F K3 = 0.00071 /psig T°o = indicated loop specific Tc at Rated Thermal Power, OF P'

• 2235 psig T, t 10 sec T2 3 sec f 1 (Aq) = -2.78 {(q,-qb) + 18%} when (q,-q,) < -18% RTP

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

= 2.34 - {(qt-qb) - 10.0%} when (qt-qb) 2 +10.0% RTP 6 ERX-09-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 12 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 Ž 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 5 592 *F (4 channels) 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-09-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 12 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 ý1881 ppm.

3.0 REFERENCES

Technical Specification 5.6.5.

8 ERX-09-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 12 Table 1 FQ(Z) MARGIN DECREASES IN EXCESS OF 2% PER 31 EFPD Cycle Maximum Decrease Burnup In FQ (Z) MARGIN (MWD/MTU) (Percent) 1233 2.00 1449 2.15 1666 2.00 4698 2.00 4914 2.05 5131 2.43 5347 2.53 5564 2.48 5780 2.39 5997 2.29 6214 2.18 6430 2.05 6647 2.00 8379 2.00 8596 2.06 8812 2.21 9029 2.37 9245 2.51 9462 2.57 9678 2.60 9895 2.61 10111 2.59 10328 2.55 10545 2.47 10761 2.31 10978 2.14 11194 2.04 11411 2.00 Note: All Cycle burnups outside the range of the table shall use a constant 2% decrease in F0 (Z) margin for compliance with the 3.2.1.2.2.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-09-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 12 Figure 1 Reactor Core Safety Limits 680 660 640 S620 I-0 600 580 560 0 20 40 60 80 100 120 140 Percent of Rated -Thermal Power 10 ERX-09-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 12 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 240

'.15.32 8 (79.6,21 8) 220 200 180 i-o 4J 160

.c --10,164)3 o-/

- ~~ - ~---- P -.

---

. -(1 00,146)

• 140 BBANKC 4.3 120

---

vi'.... -, x z

0 H

E-1 H 100 0

80

--- - - - - -- --- - - - - -BANK D 80 S60 --- - - --

H0,49) 40

-~~~ ------

20 I

ý31, 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-09-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 12 FIGURE 3 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.1 1.0 (0.01 1 '0) (6.0,1.0) 0.9

(,12.-,01,0.925) 0.8 0.7 N

0 0.6 rz 0.5 0.4 0.3 0.2 ---- H 0.1 0.0 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) TOP Axial Axial Axial Axial Node K(Z) Node K (Z) Node K (Z) Node K (Z) 61 0.9250 53 0.9450 45 0.9650 37 0.9850 60 0.9275 52 0.9475 44 0.9675 36 0.9875 59 0.9300 51 0.9500 43 0.9700 35 0.9900 58 0.9325 50 0.9525 42 0.9725 34 0.9925 57 0.9350 49 0.9550 41 0.9750 33 0.9950 56 0.9375 48 0.9575 40 0.9775 32 0.9975 55 0.9400 47 0.9600 39 0.9800 1 - 31 1.0000 54 0.9425 46 0.9625 38 0.9825 Core Height (ft) = (Node - 1)

• 0.2 12 ERX-09-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 12 FIGURE 4 W(Z) AS A FUNCTION OF CORE HEIGHT (150 MWD/MTU) 1.650 1.600 1.550 1 I1 1.500 m t

1.450

-Iz N 1.400 1=11-1 1 1z~cz 1.350

• 1.300 1.250 Eý 1.200 S.

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 1.1542 30 1.1577 16 1.2306 57 1.3589 43 1.1632 29 1.1570 15 1.2516 56 1.3421 42 1.1699 28 1.1628 14 1.2702 55 1.3280 41 1 .1774 27 1.1725 13 1.2892 54 1.3156 40 1.1839 26 1.1813 12 1.3090 53 1.3027 39 1.1880 25 1.1888 11 1.3297 52 1.2845 38 1.1903 24 1.1953 10 1.3501 51 1.2606 37 1.1918 23 1.2006 9 1.3691 50 1.2336 36 1.1920 22 1.2050 8 1.3865 49 1.2054 35 1.1901 21 1.2085 7 1.4014 48 1.1763 34 1.1862 20 1.2111 6 1.4133 47 1.1511 33 1.1804 19 1.2130 5 1.4237 46 1.1460 32 1.1728 18 1.2142 1 - 4 45 1.1469 31 1.1640 17 1.2156 Core Height (ft) = (Node - 1)

• 0.2 13 ERX-09-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 12 FIGURE 5 W(Z) AS A FUNCTION OF CORE HEIGHT (4,000 MWD/MTU) 1.650 1.600 I

1.550 I I I 1.500 1.450 VH\

N 1.400 - I --4 \

1.350

• 1.300 111- IF-

-A 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 1.1598 30 1.1239 16 1.2487 57 1.4243 43 1.1600 29 1.1317 15 1.2734 56 1.4114 42 1.1601 28 1.1433 14 1.3036 55 1.3933 41 1.1609 27 1.1535 13 1.3331 54 .1.3704 40 1.1611 26 1.1628 12 1.3626 53 1.3444 39 1.1600 25 1.-1713 11 1.3916 52 1.3155 38 1.1574 24 1.1788 10 1.4197 51 1.2847 37 1.1532 23 1.1854 9 1.4462 50 1.2523 36 1.1474 22 1.1912 8 1.4707 49 1.2272 35 1.1413 21 1.1958 7 1.4922 48 1.2106 34 1.1363 20 1.2012 6 1.5094 47 1.1923 33 1.1322 19 1.2088 5 1.5247 46 1.1732 32 1.1277 18 1.2188 1 - 4 45 1.1619 31 1.1233 17 1.2316 Core Height (ft) = (Node- 1)

• 0.2 14 ERX-09-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 12 FIGURE 6 W(Z) AS A FUNCTION OF CORE HEIGHT (7,000 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 1.2224 30 1.1192 16 1.1986 57 1.4158 43 1.2166 29 1.1181 15 1.2187 56 1.4057 42 1.2082 28 1.1228 14 1.2447 55 1.3898 41 1.1998 27 1.1310 13 1.2699 54 1.3731 40 1.1941 26 1.1386 12 1.2952 53 1.3601 39 1.1888 25 1.1451 11 1.3202 52 1.3468 38 1.1824 24 1.1511 10 1.3443 51 1.3310 37 1.1776 23 1.1562 9 1.3673 50 1.3118 36 1.1708 22 1.1608 8 1.3884 49 1.2899 35 1.1619 21 1.1649 7 1.4069 48 1.2656 34 1.1514 20 1.1682 6 1.4213 47 1.2419 33 1.1394 19 1.1723 5 1.4338 46 1.2294 32 1.1275 18 1.1791 1 -4 45 1.2253 31 1.1223 17 1.1869 Core Height (ft) = (Node - 1)

• 0.2 15 ERX-09-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 12 FIGURE 7 W(Z) AS A FUNCTION OF CORE HEIGHT (11,000 MWD/MTU) 1.650 1.600 iý 1.550 1.500 1.450 7

N 1.400 1.350

/

• 1.300 -- T- I I I I hi~7'~ I I r4z1/I I-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 1.2523 30 1.1285 16 1.1711 57 1.4639 43 1.2517 29 1.1292 15 1.1844 56 1.4579 42 1.2459 28 1.1343 14 1.2014 55 1.4415 41 1.2383 27, 1. 1380 13 1.2176 54 1.4274 40 1.2283 26 1.1409 12 1.2338 53 1.4183 39 1.2181 25 1.1437 11. 1.2496 52 1.4014 38 1. 2083 24 1.1460 10 1.2651 51 1.3796 37 1.1966 23 1.1474 9 1.2807 50 1.3560 36 1.1909 22 1.1486 8 1.2956 49 1.3297 35 1.1851 21 1.1524 7 1.3085 48 1.3013 34 1.1757 20 1.1566 6 1.3181 47 1.2770 33 1.1646 19 1.1599 5 1.3259 46 1.2644 32 1.1515 18 1.1627 1 - 4 45 1.2558 31 1.1370 17 1.1646 Core Height (ft) = (Node - 1)

• 0.2 16 ERX-09-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 12 FIGURE 8 W(Z) AS A FUNCTION OF CORE HEIGHT (20,000 MWD/MTU) 1.650 1.600 1.550 I I 1.500 1.450 1.400 i I M '

1.350

1. i_

• 1.300

/_

1.250

_X 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 1.2188 30 1.2023 16 1.1760 57 1.3907 43 1.2170 29 1.1988 15 1.1940 56 1.3903 42 1.2238 28 1.2002 14 1.2094 55 1.3811 41 1.2304 27 1.2007 13 1.2252 54 1.3673 40 1.2374 26 1.1992 12 1.2406 53 1.3519 39 1.2436 25 1.1972 11 1.2556 52 1.3342 38 1.2477 24 1.1942 10 1.2702 51 1.3137 37 1.2516 23 1.1895 9 1.2841 50 1.2919 36 1.2526 22 1.1847 8 1.2969 49 1.2669 35 1.2504 21 1.1808 7 1.3079 48 1.2450 34 1.2454 20 1.1769 6 1.3161 47 1.2367 33 1.2376 19 1.1722 5 1.3225 46 1.2335 32 1.2273 18 1.1671 1 - 4 45 1.2268 31 1.2138 17 1.1659 Core Height (ft) = (Node - 1)

• 0.2 17 ERX-09-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 12 FIGURE 9 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 100 . . . . . .

S(-15,100) -- -- - -

90 UNACCEPTABLE OPERATION 80 ACCEPTAI

--- OPERATI 70 -j~i1------

W.

60 F -

-- 0 , 10 - .. . . . . . .

60 ll--4 30 (3,0----------------------- ,

0 E

30 711 0 ------- ----- -------

10-.-.----------------

- --------- 1 .....

-t

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

18 ERX-09-001, Rev. 0