CP-201800883, Core Operating Limits Report, Cycle 18, Revision 0

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Core Operating Limits Report, Cycle 18, Revision 0
ML18354A734
Person / Time
Site: Comanche Peak Luminant icon.png
Issue date: 12/18/2018
From: Hope T
Luminant, TXU Energy, Vistra Energy
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CP-201800883, TXX-18088
Download: ML18354A734 (25)
v • d • e


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I Luminant Timoth A. Hope Regulatory Affairs Manager Luminant P.O. Box 1002 6322 North FM 56 Glen Rose, TX 76043 o 254.897.6370 CP-201800883 TXX-18088 U.S. Nuclear Regulatory Commission Ref 10CFR50.36( c)(5)

ATIN: Document Control Desk Washington, DC 20555-0001 12/18/2018

SUBJECT:

Comanche Peak Nuclear Power Plant (CPNPP)

Docket No. 50-446 (Unit 2)

Core Operating Limits Report (COLR), Unit 2, Cycle 18, Revision 0

Dear Sir or Madam:

Enclosed is Revision O of the Core Operating Limits Report (COLR) for Comanche Peak Nuclear Power Plant (CPNPP) Unit 2, Cycle 18. 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.

6555 SIERRA DRIVE IRVING, TEXAS 75039 0214-812-4600 VISTRAENERGY.COM

TXX-18088 Page 2 of 2 Should you have any questions, please contact Carl Corbin at (254) 897-0121.

Sincerely, Enclosure - Unit 2 Cycle 18 Core Operating Limits Report, Revision 0 c- Kriss Kennedy, Region IV Margaret Watford O'Banion, NRR Resident Inspectors, Comanche Peak

ERX-18-001, Rev. 0 CPNPP UNIT 2 CYCLE 18 CORE OPERATING LIMITS REPORT December 2018 Date:

(2 -}-aJ/J" than M. Ralston ncipa~ Engineer, Westinghouse Electric Company, LLC.

Reviewed: ~ ~ Date: 12- /7/ lJ;lfb Christophe; ~ Briggs Principal Ehgineer, Westinghouse Electric Company, LLC.

Reviewed: Date: fZ.- 3-2.off?

Brian Principal En Westinghouse Electric Company, LLC.

Approved: ~ ~ D a t e , IZ-'/-(';i/ff' 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-18-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 18 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 (FN.t.H) * * * * * * *
  • 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-18-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 18 LIST OF TABLES TABLE PAGE 1 F0 (Z) MARGIN DECREASES IN EXCESS OF 2% PER 31 EFPD 9 iv ERX-18-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 18 LIST OF FIGURES FIGURE 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 -

( 15 0 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 -

( 8, 0 0 0 MWD /MTU) .**......**..**********.**.......****.**. 15 7 W(Z) AS A FUNCTION OF CORE HEIGHT -

(13, 000 MWD/MTU) *****.**.****.******....**.************* 16 8 W(Z) AS A FUNCTION OF CORE HEIGHT -

(18, 000 MWD/MTU) *.*******.*************.*.....*.******** 17 9 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 18 V ERX-18-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 18 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for CPNPP UNIT 2 CYCLE 18 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 (SLs)

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 (F"t.H)

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-18-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 18

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% 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-18-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 18 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 o*r 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-18-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 18 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 9 (Z)) (LCO 3. 2 .1)

FoRTP 2.8.1 F 0 (Z) s [K(Z)] for P > 0.5 p

F/TP F 0 (Z) s [K(Z)] for PS 0.5

0.5 where

P = THERMAL POWER RATED THERMAL POWER 4 ERX-18-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 18 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 Fg(Z) evaluations show an increase in the expression maximum over Z [ F/(Z) / K(Z) ] ,

the burnup dependent values in Table 1 shall be used instead of a constant 2% to increase Fgw (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-18-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 18

2. 9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (FNAJ::!.l (LCO 3. 2. 2) 2.9.1 F RTPAH [l + PF.o.H (1-P)]

where: P = THERMAL POWER RATED THERMAL POWER

2. 9. 2 FRT*.o.H = 1. 60 for all Fuel Assembly Regions 2.9.3 PF.o.H = 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. lr 2.11.1 The numerical values pertaining to the Overtemperature N-16 reactor trip setpoint are listed below; K1 = 1.15 K2 = 0.0139 /°F K3 = 0.00071 /psig T: = indicated loop specific T at Rated Thermal Power, OF 0

pl  ;:: 2235 psig T1  ;:: 10 sec T2 s 3 sec f 1 (Aq) = -2. 78 * { (qt-q,,) + 18%} when (qt-q,,) S -18% RTP

= 0% when -18% RTP < (qt-q,,) < +10. 0% RTP 6 ERX-18-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 18 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 :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-18-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 18 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 ~1839 ppm.

3.0 REFERENCES

Technical Specification 5.6.5.

8 ERX-18-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 18 Table 1 Fg(Z) MARGIN DECREASES IN EXCESS OF 2% PER 31 EFPD Cycle Maximum Decrease Burnup In F0 (Z) MARGIN (MWD/MTU) (Percent) 580 2.00 795 2.73 1011 3.38 1226 3.49 1441 3.24 1656 2.79 1871 2.25 2086 2.00 4238 2.00 4453 2.37 4668 2.41 4883 2.43 5098 2.66 5313 2.86 5529 3.01 5744 2.83 5959 2.60 6174 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-18-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 18 Figure 1 Reactor Core Safety Limits 2445 psig Unacceptable L1.

0 Acceptable 0 20 40 60 80 100 120 140 Percent of Rated Thermal Power 10 ERX-18-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 18 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 240 220 (25.3,218) (79.6,218) _,_

I/ /

,, / /

I/

200 I/ " I I "

/ I BANK B I 1..1 "

,, V ,, /

1

'C 1-1 180

.c: " /

.µ 160 --(0,164) /

  • ri

~

,, / (100,146)

Ill 0.

Q) 140 v

.µ I/

Ill 1..1 BANK C I/

/ /

z0 120

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,, /

H E-1 H /

C/l 1..1 0

p., 100 / / "

,, / ,, /

~

III 80 1..1 /

Q V /

0 BANK D P: ,, V /

/

60

" / "

- (0,49) /

40 /

/

I/

20 1..1 V

(31,0) /

I I I I ,r 0

0 10 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER NOTES: l. 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-18-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 18 FIGURE 3 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.1 1.0

~

0.9 0.8 N

QI l'<I 0.7 Q

M N

H 0.6 i

0 z 0.5 Core Height (ft} K(Z}

N 0.0 1. 0000 0.4

,,:; 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-18-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 18 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 2

J 2 1.300

~

2 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 1.1842 30 1.1664 16 1.1873 57 1.3001 43 1.1926 29 1.1618 15 1.2037 56 1.2896 42 1.1977 28 1.1639 14 1.2223 55 1. 2833 41 1.2014 27 1.1684 13 1.2406 54 1.2755 40 1.2038 26 1.1718 12 1.2586 53 1.2670 39 1. 2037 25 1.1740 11 1.2763 52 1.2597 38 1.2033 24 1.1750 10 1.2935 51 1.2523 37 1.1998 23 1.1752 9 1.3099 50 1.2432 36 1.1998 22 1.1755 8 1.3251 49 1.2326 35 1.2007 21 1.1758 7 1.3386 48 1. 2219 34 1.1978 20 1.1769 6 1.3493 47 1. 2108 33 1.1928 19 1.1792 5 1.3586 46 1.1981 32 1.1857 18 1.1804 1 - 4 45 1.1862 31 1.1761 17 1.1809 Core Height (ft) = (Node - 1)

  • 0.201317 I

13 ERX-18-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 18 FIGURE 5 W(Z) AS A FUNCTION OF CORE HEIGHT (4,000 MWD/MTU) 1.650 1.600 1.550 1.500 1.450

........ 1.400 N

$ 1.350

\

2

)

2 1.300 x<( 1.250 2

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 1.1671 30 1.1378 16 1.2046 57 1.2945 43 1.1677 29 1.1360 15 1.2236 56 1. 2793 42 1.1696 28 1.1358 14 1.2486 55 1.2675 41 1.1718 27 1.1402 13 1.2752 54 1.2552 40 1.1736 26 1.1465 12 1.3018 53 1. 2504 39 1.1739 25 1.1520 11 1.3279 52 1.2443 38 1.1726 24 1.1566 10 1.3532 51 1.2384 37 1.1694 23 1.1604 9 1.3773 50 1.2314 36 1.1641 22 1.1648 8 1.3996 49 1.2218 35 1.1581 21 1.1713 7 1.4196 48 1. 2121 34 1.1529 20 1.1783 6 1.4355 47 1.1979 33 1.1487 19 1.1841 5 1.4496 46 1.1828 32 1.1445 18 1.1891 1 - 4 45 1.1715 31 1.1407 17 1.1940 Core Height (ft) = (Node - 1)

  • 0.201317 14 ERX-18-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 18 FIGURE 6 W(Z) AS A FUNCTION OF CORE HEIGHT (8,000 MWD/MTU) 1.650 1.600 1.550 1.500 1.450

......... 1.400 N

$ 1.350

~

J

~

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 1.2514 30 1.1437 16 1.1420 57 1.3347 43 1.2523 29 1.1425 15 1.1516 56 1.3262 42 1.2492 28 1.1422 14 1.1700 55 1.3153 41 1.2434 27 1.1426 13 1.1893 54 1.3012 40 1.2353 26 1.1421 12 1.2088 53 1. 2857 39 1.2256 25 1.1408 11 1.2281 52 1. 2815 38 1.2171 24 1.1395 10 1.2470 51 1.2794 37 1.2058 23 1.1375 9 1.2650 50 1.2746 36 1.1992 22 1.1343 8 1.2817 49 1.2696 35 1.1944 21 1.1338 7 1.2968 48 1.2659 34 ~.1859 20 1.1348 6 1. 3085 47* 1.2619 33 1.1753 19 1.1363 5 1.3183 46 1.2587 32 1.1622 18 1.1370 1 - 4 45 1.2547 31 1.1503 17 1.1391 Core Height (ft) = (Node - 1)

  • 0.201317 15 ERX-18-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 18 FIGURE 7 W(Z) AS A FUNCTION OF CORE HEIGHT (13,000 MWD/MTU) 1.650 1.600 1.550 1.500 1.450 N 1.400 2

1.350

J 2 1.300

<( 1.250 2

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 1.2146 30 1.1836 16 1.1330 57 1.2666 43 1.2229 29 1.1820 15 1.1431 56 1. 2582 42 1.2299 28 1.1823 14 1.1555 55 1. 2519 41 1.2373 27 1.1823 13 1.1677 54 1.2454 40 1.2445 26 1.1809 12 1.1799 53 1. 2384 39 1.2483 25 1.1778 11 1.1920 52 1.2371 38 1.2494 24 1.1734 10 1.2038 51 1.2374 37 1.2477 23 1.1676 9 1.2153 50 1.2357 36 1.2434 22 1.1607 8 1.2260 49 1.2316 35 1.2368 21 1.1528 7 1.2356 48 1. 2285 34 1.2275 20 1.1462 6 1.2430 47 1.2232 33 1.2160 19 1.1419 5 1.2485 46 1.2216 32 1.2056 18 1.1374 1 - 4 45 1.2185 31 1.1930 17 1.1313 Core Height (ft) = (Node - 1)

  • 0.201317 16 ERX-18-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 18 FIGURE 8 W(Z) AS A FUNCTION OF CORE HEIGHT (18,000 MWD/MTU) 1.650 1.600 1.550 1.500 1.450 N' 1.400

~ 1.350 2

J 2 1.300

~ 1.250 2

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 1.2177 30 1.2297 16 1.1369 57 1. 2358 43 1. 2287 29 1.2248 15 1.1459 56 1.2326 42 1.2409 28 1.2229 14 1.1590 55 1.2294 41 1.2518 27 1.2224 13 1.1714 54 1.2262 40 1.2602 26 1. 2205 12 1.1838 53 1. 2226 39 1.2661 25 1. 2161 11 1.1961 52 1. 2200 38 1.2693 24 1.2100 10 1.2083 51 1.2170 37 1.2695 23 1. 2019 9 1.2202 50 1.2130 36 1.2695 22 1.1922 8 1.2316 49 1.2087 35 1.2696 21 1.1811 7 1.2421 48 1. 2037 34 1.2677 20 1.1686 6 1.2504 47 1.1966 33 1.2621 19 1.1556, 5 1.2568 46 1.1981 32 1.2536 18 1.1438 1 - 4 45 1.2075 31 1.2409 17 1.1362 Core Height (ft) = (Node - 1)

  • 0.201317 17 ERX-18-001, Rev. 0

COLR for CPNPP Unit 2 Cycle 18 FIGURE 9 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 100 j

(-12,100) (10,100)

I I '\,

90 I -

I- f-UNACCEPTABLE I \ UNACCEPTABLE OPERATION j

\

, OPERATION

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~

80 ,I ACCEPTABLE \

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p::

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60

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f-1 A

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~- (-25,50)

~-

' (20, SO) f-1

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40 r:..

0 f-1

z; r,::i up:: 30 r,::i p.,

20 10 0

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

18 ERX-18-001, Rev. 0

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