CP-201700977, Core Operating Limits Report, Rev. 1

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Core Operating Limits Report, Rev. 1
ML17348A072
Person / Time
Site: Comanche Peak Luminant icon.png
Issue date: 12/12/2017
From: Sewell S
Vistra Energy
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CP-201700977, TXX-17099
Download: ML17348A072 (25)
v • d • e


Text

CP-201700977 TXX-17099 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 V!S!~l\\

ENE R G*v

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If* energy Luminant Steven K. Sewell Senior Director, Engineering & Regulatory Affairs Luminant P.O. Box 1002 6322 North FM 56 Glen Rose, TX 76043 o 254.897.6113 m 817.776.0798 Ref 10CFR50.36( c)(5) 12/12/2017

SUBJECT:

COMANCHE PEAK NUCLEAR POWER PLANT DOCKET NO. 50-446 (UNIT 2)

CORE OPERATING LIMITS REPORT

Dear Sir or Madam:

Enclosed is Revision 1 of the Core Operating Limits Report for Comanche Peak Nuclear Power Plant (CPNPP)

Unit 2, Cycle 17. 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.

1601 BRYAN STREET DALLAS, TEXAS 75201 o 214-81 2-4600 VISTRAENERGY.COM

TXX-17099 Page 2 of 2 Should you have any questions, please c~ntact Carl Corbin at (254} 897-0121.

Sincerely,

_':{~-/£~.£ Steven K. Sewell Enclosure - Unit 2 Cycle 17 Core Operating Limits Report, Revision 1 c-Kriss Kennedy, Region IV Margaret Watford O'Banion, NRR Resident Inspectors, Comanche Peak

ERX-17-001, Rev. l CPNPP.UNIT 2 CYCLE 17 CORE OPERATING LIMITS REPORT December 2017 Prepar...,----, ~

I!.

1 ~ - Date,

/ z_ - ') -,!tJ/ J

\\.~*

'2iibnathan M. Ralston

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rincipal }l:ngineer, Westinghouse Electric Company, LLC.

Reviewed:

Reviewed:

Approved:

Date:

12/ r../z_ot'.'.}-

Christopher M. Briggs Principal Engineer, Westinghouse Electric Company, LLC.

~rian L. G Principal Date:

I '2. - 4,- 2,s 11-Westinghouse Electric Company, LLC, Date:

\\z..-1o-z.o l q.

Engineering - TX/KS

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"T!a:W,:S(C:,-1\\l A>I!-

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DISCLAIMER The information contained in this report was prepared for the specific requirement of Comanche Peak Power Company LLC and may not be appropriate for use in situations other than those for which it was specifically prepared.

Comanche Peak Power 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, Comanche Peak Power Company LLC does not authorize its use by others, and any such use is forbidden except with the prior written approval of Comanche Peak Power 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 Comanche Peak Power 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-17-001, Rev. 1

COLR for CPNPP Unit 2 Cycle 17 TABLE OF CONTENTS DISCLAIMER ii TABLE OF CONTENTS iii LIST OF TABLES iv LIST OF FIGURES v

SECTION PAGE 1

1.0 CORE OPERATING LIMITS REPORT

2. 0 OPERATING LIMITS 2

3.0

2. 1 SAFETY LIMITS ( SLs) * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

MODERATOR TEMPERATURE COEFFICIENT (MTC)

ROD GROUP ALIGNMENT LIMITS ***************************

SHUTDOWN BANK INSERTION LIMITS ***********************

CONTROL BANK INSERTION LIMITS ************************

PHYSICS TESTS EXCEPTIONS -

MODE 2.********************

HEAT FLUX HOT CHANNEL FACTOR (FQ(Z)) ******************

2 2

3 3

4 4

4

2. 9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (FNt.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 **********************************

REFERENCES 8

8 iii ERX-17-001, Rev. 1

TABLE COLR for CPNPP Unit 2 Cycle 17 LIST OF TABLES 1

FQ(Z) MARGIN DECREASES IN EXCESS OF 2% PER 31 EFPD PAGE 9

iv ERX-17-001, Rev. 1

COLR for CPNPP Unit 2 Cycle 17 LIST OF FIGURES FIGURE 1

REACTOR CORE SAFETY LIMITS 2

ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 3

K (Z) -

NORMALIZED FQ (Z) AS A FUNCTION OF CORE HEIGHT 4

W(Z) AS A FUNCTION OF CORE HEIGHT -

( 15 0 MWD/MTU) 5 W(Z) AS A FUNCTION OF CORE HEIGHT -

(3, 000 MWD/MTU) 6 W(Z) AS A FUNCTION OF CORE HEIGHT -

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

( 12, 0 0 0 MWD /MTU) 8 W(Z) AS A FUNCTION OF CORE HEIGHT -

(20, 000 MWD/MTU) 9 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 10 11 12 13 14 15 16 17 18 V

ERX-17-001, Rev. 1

COLR for CPNPP Unit 2 Cycle 17

1. 0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for CPNPP UNIT 2 CYCLE 17 has been prepared in accordance with the requirements of Technical Specification 5.6.5.

The Technical 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 Specifications affected by this report are listed below:

SAFETY LIMITS (SLs)

SHUTDOWN MARGIN (SDM)

MODERATOR TEMPERATURE COEFFICIENT (MTC)

ROD GROUP ALIGNMENT LIMITS SHUTDOWN BANK INSERTION LIMITS CONTROL BANK INSERTION LIMITS PHYSICS TESTS EXCEPTIONS -

MODE 2 HEAT FLUX HOT CHANNEL FACTOR (F0 (Z))

NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (FN.6H)

AXIAL FLUX DIFFERENCE (AFD)

REACTOR TRIP SYSTEM (RTS) INSTRUMENTATION RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING (DNB) LIMITS BORON CONCENTRATION 1

ERX-17-001, Rev. 1

COLR for CPNPP Unit 2 Cycle 17 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) 2.2 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.

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-17-001, Rev. 1

COLR for CPNPP Unit 2 Cycle 17 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) 2.5 2.4.1 The SDM shall be greater than or equal to 1.3% ak/k in MODES 1 and 2.

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-17-001, Rev. 1

COLR for CPNPP Unit 2 Cycle 17 2.6 CONTROL BANK INSERTION LIMITS (LCO 3.1.6) 2.7 2.8 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.

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.

HEAT FLUX HOT CHANNEL FACTOR (F~ (LCO 3.2.1)

F RTP Q

2.8.1 FQ(Z) s

[K ( Z) ] for P > 0.5 p

F RTP Q

F0 (Z) s

[K ( Z) ] for P s 0.5

0.5 where

P =

THERMAL POWER RATED THERMAL POWER 4

ERX-17-001, Rev. 1

COLR for CPNPP Unit 2 Cycle 17 2.8.2 F/TP = 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 extrapolat.ion 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 F0 (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 F/(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-17-001, Rev. 1

COLR for CPNPP Unit 2 Cycle 17 2. 9 NUCLEAR ENTHALPY RI SE HOT CHANNEL FACTOR ( FN I\\HL

( LCO 3. 2. 2) 2.9.1 FRTP AH [l + PFAH (1-P)]

where:

P =

THERMAL POWER RATED THERMAL POWER

2. 9. 2 FRTP AH =
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;*

K1

= 1.15 K2

= 0.0139 /°F K3

= 0.00071 /psig To

=

C indicated loop specific T C at Rated Thermal Power, OF pl

~ 2235 psig

,: 1

~ 10 sec

,: 2

S 3 sec

= 0%

when -18% RTP < (qt-qb) < +10.0% RTP 6

ERX-17-001, Rev. 1

COLR for CPNPP Unit 2 Cycle 17 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-17-001, Rev. 1

COLR for CPNPP Unit 2 cycle 17 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 ~1938 ppm.

3. 0 REFERENCES Technical Specification 5.6.5.

8 ERX-17-001, Rev. 1

COLR for CPNPP Unit 2 Cycle 17 Table 1 F0 (Z) MARGIN DECREASES IN EXCESS OF 2% PER 31 EFPD Cycle Maximum Decrease Burnup In F0 (Z) MARGIN (MWD/MTU)

(Percent) 365 2.00 580 2.38 796 3.30 1011 4.01 1226 4.18 1441

3. 71 1657 3.21 1872
2. 71 2087 2.30 2302 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 F0 (Z) margin decrease for cycle burnups which fall between the specified burnups.

9 ERX-17-001, Rev. 1

COLR for CPNPP Unit 2 Cycle 17 Figure 1 Reactor Core Safety Limits 2445 psig Unacceptable G:'

0 -

Acceptable 560 +-~~~-+-~~~---i'--~~~+-~~~-+~~~~1---~~~-+-~~~--1 0

20 40 60 80 100 120 140 Percent of Rated Thermal Power 10 ERX-17-001, Rev. 1

240 220 200

~

180

~

'O

.c: 160

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  • ri

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tll P, 140 (I)

.j..l tll z 120 0

H E-1 H

Ul 0

100 p..

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j Ill 80 A

0 i:t:

60 40 20 0

NOTES:

/

V

/

--(0,164)

/

V II' I/

~ (0,49) 0 10

1.

COLR for CPNPP Unit 2 Cycle 17 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER (25.3,218)

(79.6,218) -,-

I/

I/

V

/

V

,I I/

I BANK B I

,I I

I

/

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(100,146)

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BANK C

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V V

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II' I'

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I BANK D

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V I/

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(31,0)

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I I I I 20 30 40 50 60 70 80 90 PERCENT OF RATED THERMAL POWER Fully withdrawn shall be the condition where control rods are at a position within the interval of 218 and 231 steps withdrawn, inclusive.

.I 100

2.

Control Bank A shall be fully withdrawn.

11 ERX-17-001, Rev. 1

1.1 1.0 0.9 0.8

~

N

~

()I r:c.

0.7 Q

r:il N

H i 0.6 0 z 0.5 I

N

~

0.4 0.3 0.2 0.1 0.0 COLR for CPNPP Unit 2 Cycle 17 FIGURE 3 K(Z) -

NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT Core Height (ft) 0.0 6.0 12.0 0

1 2

3 4

5 6

7 BOTTOM CORE HEIGHT (FEET) 12 8

K(Z) 1.0000

1. 0000 0.9250 9

10 11

~

12 TOP ERX-17-001, Rev. 1

N

s

~

~

~

~

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 COLR for CPNPP Unit 2 Cycle 17 FIGURE 4 W(Z) AS A FUNCTION OF CORE HEIGHT (150 MWD/MTU) 2 3

4 5

6 7

8 9

BOTTOM CORE HEIGHT (FEET)

Axial Axial Axial Node W(Z)

Node W(Z)

Node W(Z) 58 -

61 44 1.1563 30 1.1618 57

1. 2792 43 1.1620 29 1.1612 56 1.2638 42 1.1660 28 1.1654 55
1. 2529 41 1.1692 27 1.1769 54
1. 2394 40 1.1739 26 1.1894 53 1.2253 39 1.1789 25 1.2000 52 1.2139 38 1.1821 24 1.2099 51 1.2073 37 1.1860 23 1.2188 50 1.1991 36 1.1883 22
1. 2266 49 1.1829 35 1.1879 21 1.2334 48 1.1645 34 1.1857 20
1. 2393 47 1.1594 33 1.1814 19 1.2442 46 1.1575 32 1.1754 18 1.2484 45 1.1556 31 1.1676 17 1.2528 10 Axial Node 16 15 14 13 12 11 10 9

8 7

6 5

1 -

4 11 12 TOP W(Z) 1.2646 1.2840 1.3064

1. 3292 1.3514 1.3729 1.3934 1.4127 1.4304 1.4458 1.4581 1.4689 Core Height (ft) = (Node -
1)
  • 0.201317 13 ERX-17-001, Rev. 1

1.650 1.600 1.550 1.500 1.450 1.200 1.150 1.100 1.050 1.000 0

COLR for CPNPP Unit 2 Cycle 17 FIGURE 5 W(Z) AS A FUNCTION OF CORE HEIGHT (3,000 MWD/MTU) 2 3

4 5

6 7

8 9

BOTTOM CORE HEIGHT (FEET)

Axial Axial Axial Node W(Z)

Node W(Z)

Node W(Z) 58 -

61 44 1.1310 30 1.1341 57 1.3194 43 1.1308 29 1.1463 56 1.3190 42 1.1303 28 1.1618 55 1.3169 41 1.1318 27 1.1764 54

1. 3066 40 1.1367 26 1.1898 53 1.2927 39 1.1416 25 1.2022 52
1. 2746 38 1.1445 24 1.2140 51 1.2531 37 1.1457 23 1.2255 50 1.2292 36 1.1454 22
1. 2362 49 1.2024 35 1.1434 21 1.2454 48 1.1738 34 1.1404 20
1. 2546 47 1.1528 33 1.1380 19
1. 2657 46 1.1423 32 1.1353 18
1. 2785 45 1.1360 31 1.1318 17
1. 2926 10 11 12 TOP Axial Node W(Z) 16 1.3087 15 1.3274 14 1.3501 13
1. 3785 12 1.4071 11 1.4348 10
1. 4617 9

1.4871 8

1.5106 7

1.5315 6

1.5483 5

1. 5634 1 -

4 Core Height (ft) = (Node -

1)
  • 0.201317 14 ERX-17-001, Rev. 1

1.650 1.600 1.550 1.500 1.450 1.200 1.150 1.100 1.050 1.000 0

1 COLR for CPNPP Unit 2 Cycle 17 FIGURE 6 W(Z) AS A FUNCTION OF CORE HEIGHT (7,000 MWD/MTU) 2 3

4 5

6 7

8 9

BOTTOM CORE HEIGHT (FEET)

Axial Axial Axial Node W(Z}

Node W(Z}

Node W(Z}

58 -

61 44 1.2268 30 1.1173 57 1.4478 43 1.2268 29 1.1172 56

1. 4376 42 1.2235 28 1.1228 55 1.4236 41
1. 2181 27 1.1306 54
1. 4042 40 1.2104 26 1.1378 53
1. 3813 39 1.2003 25 1.1444 52
1. 3556 38 1.1908 24 1.1510 51
1. 3257 37 1.1784 23 1.1568 50
1. 2989 36 1.1706 22 1.1617 49
1. 2813 35 1.1651 21 1.1666 48
1. 2679 34 1.1562 20 1.1717 47 1.2547 33 1.1457 19 1.1760 46
1. 2413 32 1.1329 18 1.1796 45
1. 2309 31 1.1227 17 1.1862 10 11 12 TOP Axial Node W(Z) 16 1.1932 15 1.2052 14 1.2256 13 1.2479 12 1.2704 11 1.2927 10 1.3144 9

1.3353 8

1.3551 7

1. 3728 6
1. 3867 5

1.3986 1 -

4 Core Height (ft) = (Node - 1)

  • 0.201317 15 ERX-17-001, Rev. 1

1.650 1.600 1.550 1.500 1.450 Ki' 1.400

........ s

~

~

~

~

1.350 1.300 1.250 1.200 1.150 1.100 1.050 1.000 0

1 COLR for CPNPP Unit 2 Cycle 17 FIGURE 7 W(Z) AS A FUNCTION OF CORE HEIGHT (12,000 MWD/MTU) 2 3

4 5

6 7

8 9

BOTTOM CORE HEIGHT (FEET)

Axial Axial Axial Node W(Z)

Node W(Z)

Node W(Z) 58 -

61 44 1.2468 30 1.1504 57 1.4081 43 1.2440 29 1.1450 56 1.4058 42 1.2390 28 1.1494 55 1.3934 41 1.2338 27 1.1524 54 1.3804 40 1.2313 26 1.1537 53

1. 3655 39 1.2298 25 1.1549 52 1.3490 38 1.2263 24 1.1556 51
1. 3319 37 1.2241 23 1.1552 50
1. 3119 36
1. 2203 22 1.1539 49 1.2924 35 1.2133 21 1.1520 48 1.2828 34 1.2042 20 1.1492 47
1. 2753 33 1.1928 19 1.1466 46 1.2664 32 1.1795 18 1.1462 45
1. 2557 31 1.1641 17 1.1482 10 11 12 TOP Axial Node W(Z) 16 1.1507 15 1.1578 14 1.1717 13 1.1859 12 1.2001 11 1.2143 10 1.2282 9

1.2414 8

1.2537 7

1.2647 6

1.2729 5

1.2793 1 -

4 Core Height (ft) = (Node - 1)

  • 0.201317 16 ERX-17-001, Rev. 1

N

._... s

~

)

~

~

~

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 COLR for CPNPP Unit 2 Cycle 17 FIGURE 8 W(Z) AS A FUNCTION OF CORE HEIGHT (20,000 MWD/MTU) 2 3

4 5

6 7

8 9

BOTTOM CORE HEIGHT (FEET)

Axial Axial Axial Node W(Z)

Node W(Z)

Node W(Z) 58 -

61 44

1. 2493 30 1.2197 57
1. 3229 43 1.2527 29 1.2130 56 1.3224 42
1. 2572 28 1.2126 55 1.3169 41
1. 2609 27
1. 2146 54 1.3131 40
1. 2661 26 1.2155 53
1. 3049 39 1.2716 25 1.2141 52 1.2956 38 1.2744 24 1.2108 51
1. 2844 37 1.2777 23
1. 2057 50 1.2761 36 1.2786 22 1.1989 49 1.2729 35
1. 2757 21 1.1909 48
1. 2689 34 1.2698 20 1.1810 47
1. 2648 33
1. 2608 19 1.1717 46 1.2622 32 1.2492 18 1.1674 45
1. 2559 31
1. 2339 17 1.1642 10 Axial Node 16 15 14 13 12 11 10 9

8 7

6 5

1 -

4 11 12 TOP W(Z) 1.1657 1.1726 1.1830 1.1959 1.2100 1.2239 1.2375

1. 2506 1.2630
1. 2743 1.2831
1. 2897 Core Height (ft) = (Node -
1)
  • 0.201317 17 ERX-17-001, Rev. 1

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f:i:l Jl, 100 90 --

I-80 70 60 50 I-40 30 20 10 0

-40 COLR for CPNPP Unit 2 Cycle 17 FIGURE 9 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER

(-15,100)

I

\\

(10,100) j I

\\

1 j

\\

UNACCEPTABLE I

UNACCEPTABLE OPERATION OPERATION

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I 1

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ACCEPTABLE j

OPERATION I

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j

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I 1

I

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j I

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(-30,50)

(30, 50)

-30

-20

-10 0

10 20 30 AXIAL FLUX DIFFERENCE (%)

40 18 ERX-17-001, Rev. 1

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