CP-201700932, Core Operating Limits Report

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Core Operating Limits Report
ML17321A080
Person / Time
Site: Comanche Peak Luminant icon.png
Issue date: 11/15/2017
From: Hope T
Luminant Power, TXU Energy, Vistra Energy
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CP-201700932, TXX-17091
Download: ML17321A080 (25)
v • d • e


Text

CP-201700932 TXX-17091 U.S. Nuclear Regulatory Commission

~t.rxu J

m If* energy Luminant 11/15/2017

SUBJECT:

COMANCHE PEAK NUCLEAR POWER PLANT DOCKET NO. 50-445 (UNIT 1)

CORE OPERATING LIMITS REPORT

Dear Sir or Madam:

Timothy A. Hope Manager, Regulatory Affairs Luminant P.O. Box 1002 6322 North FM 56 Glen Rose, TX 76043 o 254.897.6370 m 817.360.6882 Ref 10CFR50.36(c)(5)

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

Unit 1, Cycle 20. This report is prepared and submitted pursuant to Technical Specification 5.6.5.

This communication contains no new licensing basis commitments regarding CPNPP Unit 1.

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

  • VISTRAENERGY.COM

TXX-17091 Page 2 of 2 Should you have any questions, please contact Carl Corbin at {254) 897-0121.

Sincerely,

~~tb Timothy A. Hope Enclosure - Unit 1 Cycle 20 Core Operating Limits Report, Revision 0 c-Kriss Kennedy, Region IV Margaret Watford O'Banion, NRR Resident Inspectors, Comanche Peak

ERX-17-002, Rev. 0 CPNPP UNIT 1 CYCLE 20 CORE OPERATING LIMI?S REPORT September 2017 Preparfi:

  • Jo Pr.

>{<' ~-

re ~

Date:

Engineer1 Westinghouse Electric Company, LLC.

'\\.

Reviewed:

~

~

Date:

q/fl-1 /d,?t"i ChristopherM.riggs Principal Engineer, Westinghouse Electric Company, LLC.

Reviewed:

Westinghouse Electric Company, LLC.

Approved: ~-E:1 Date:

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-17-002, Rev. 0

COLR for CPNPP Unit 1 Cycle 20 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)...................... *.. *.........

2 2. 2 SHUTDOWN MARGIN ( SDM).... *................ *. *... *.....

2 2.3 2.4 2.5 2.6 2.7 2.8 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. 9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (FNAH)........

2.10 AXIAL FLUX DIFFERENCE (AFD) 2.11 REACTOR TRIP SYSTEM (RTS) INSTRUMENTATION............

2.12 RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING (DNB) LIMITS........................

2. 13 BORON CONCENTRATION..................................

REFERENCES 2

3 3

4 4

4 6

6 6

7 8

8 iii ERX-17-002, Rev. 0

TABLE COLR for CPNPP Unit 1 Cycle 20 LIST OF TABLES 1

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

iv ERX-17-002, Rev. 0

COLR for CPNPP Unit 1 Cycle 20 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, 0 0 0 MWD /MTU) 6 W(Z) AS A FUNCTION OF CORE HEIGHT -

(9, 000 MWD/MTU) 7 W(Z) AS A FUNCTION OF CORE HEIGHT -

(14, 000 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-17-002, Rev. 0

COLR for CPNPP Unit 1 Cycle 20 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for CPNPP UNIT 1 CYCLE 20 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 (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 (FQ(Z))

NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (F~H)

AXIAL FLUX DIFFERENCE (AFD)

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

ERX-17-002, Rev. 0

COLR for CPNPP Unit 1 Cycle 20 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 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-17-002, Rev. 0

COLR for CPNPP Unit 1 Cycle 20 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-17-002, Rev. 0

COLR for CPNPP Unit 1 Cycle 20 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

FQ(Z) s

[K ( Z) ] for P s 0.5

0.5 where

P =

THERMAL POWER RATED THERMAL POWER 4

ERX-17-002, Rev. 0

COLR for CPNPP Unit 1 Cycle 20 2. 8

  • 2 F /TP = 2
  • 5 0 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

[ 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-17-002, Rev. 0

--- ----~~-------------------------------------,

COLR for CPNPP Unit 1 Cycle 20

2. 9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (FN.ru:t.L (LCO 3. 2. 2) 2. 9. 1 FN aH
S FRTP aH [ 1 + PF aH ( 1-P ) ]

where:

P =

THERMAL POWER RATED THERMAL POWER

2. 9. 2 FRTPaH =
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

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

C pl

~ 2235 psig

  • 1

~ 10 sec

  • 2

~ 3 sec

= 0%

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

ERX-17-002, Rev. 0

COLR for CPNPP Unit 1 Cycle 20 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

588 °F (4 channels)

S 588 °F (3 channels)

The RCS average temperature limits correspond to the analytical limit of 591.9 °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-i7-002, Rev. 0

COLR for CPNPP Unit 1 Cycle 20 2.12.4 SR 3.4.1.3 The RCS total flow rate shall be~ 403,700 gpm.

2.12.5 SR 3.4.1.4 The RCS total flow rate based on precision heat balance shall be~ 403,700 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 ~1820 ppm.

3.0 REFERENCES

Technical Specification 5.6.5.

8 ERX-17-002, Rev. 0

COLR for CPNPP Unit 1 Cycle 20 Table 1 FQ(Z) MARGIN DECREASES IN EXCESS OF 2% PER 31 EFPD Cycle Maximum Decrease Burnup In F0 (Z) MARGIN (MWD/MTU)

(Percent) 8101 2.00 8316 2.20 8531 2.50 8746 2.73 8961 3.00 9176 2.89 9391 2.72 9606 2.56 9820 2.40 10035 2.24 10250 2.13 10465 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-17-002, Rev. 0

COLR for CPNPP Unit 1 Cycle 20 Figure 1 Reactor Core Safety Limits 2445 psig Unacceptable ii:'

0 -

Acceptable 560 --l--~~~--'-~~~~1--~~~-+-~~~----,..~~~~+--~~~-+-~~~---1 0

20 40 60 80 100 120 140 Percent of Rated Thermal Power 10 ERX-17-002, Rev. 0

240 220 200

~

180 1-1

'O

..c:

160

.u

  • n

~

tll p.. 140 Q)

.u tll z 120 0

H E-l H

tll 0

100 p..

~

P'.l 80 A

0 r:i::

60 40 20 0

NOTES:

/

V

/

--(0,164)

/

'/

- (0,49) 0 10

1.

COLR for CPNPP Unit 1 Cycle 20 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER (25.3,218)

(79.6,218) ---

I/

/

/

/

/

/

/

I/

I BANK B I

/

I I

I/'

/

/

/

/

.I V

/

(100,146) ii

/

BANK C

/

V

/

V

/

/

V

/

I/

I/

/

/

/

/

/

I/

/

LI

/

BANK D

/

/

/

'/

/

I/

/

(31,0)

V 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.

100

2.

Control Bank A shall be fully withdrawn.

11 ERX-17-002, Rev. 0

1.1

1. 0 0.9 0.8

~

t..:l QI Ii, 0.7 A

r:il t..:l H

0.6

,-'.I i 0 z 0.5 I

t..:l 0.4 0.3 0.2 0.1 o.o COLR for CPNPP Unit 1 Cycle 20 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-17-002, Rev. 0

~

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 1 Cycle 20 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 1.1755 30 1.1473 57

1. 3873 43 1.1828 29 1.1453 56 1.3758 42 1.1875 28 1.1442 55
1. 3619 41 1.1927 27 1.1464 54
1. 3417 40 1.1977 26 1.1519 53 1.3088 39 1.1996 25 1.1582 52 1.2725 38 1.1992 24 1.1638 51 1.2371 37 1.1965 23 1.1688 50 1.2071 36 1.1918 22 1.1729 49 1.1880 35 1.1850 21 1.1771 48 1.1845 34 1.1768 20 1.1843 47 1.1821 33 1.1687 19 1.1943 46 1.1775 32 1.1607 18
1. 2029 45 1.1748 31 1.1527 17 1.2132 10 Axial Node 16 15 14 13 12 11 10 9

8 7

6 5

  • 1 -

4 11 12 TOP W(Z) 1.2236 1.2404 1.2668 1.2945 1.3221 1.3493

1. 3754 1.4002 1.4231
1. 4439
1. 4615 1.4744 Core Height (ft) = (Node -
1)
  • 0.2013236 13 ERX-17-002, Rev. 0

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 1 Cycle 20 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 1.1574 30 1.1320 57 1.4231 43 1.1638 29 1.1354 56 1.4105 42 1.1670 28 1.1474 55

1. 3970 41 1.1670 27 1.1584 54
1. 3792 40 1.1671 26 1.1677

)

53

1. 3576 39 1.1669 25 1.1768 52 1.3330 38 1.1648 24 1.1854 51 1.3044 37 1.1637 23 1.1929 50 1.2732 36 1.1611 22 1.1996 49 1.2402 35 1.1563 21
1. 2052 48
1. 2075 34 1.1495 20 1.2103 47 1.1873 33 1.1411 19 1.2154 46 1.1735 32 1.1358 18
1. 2217 45 1.1618 31 1.1324 17
1. 2326 10 11 12 TOP Axial Node W(Z) 16 1.2464 15
1. 2692 14
1. 3020 13 1.3336 12
1. 3652 11 1.3963 10
1. 4263 9

1.4547 8

1. 4809 7

1.5045 6

1.5250 5

1.5407 1 -

4 Core Height (ft) = (Node -

1)
  • 0.2013236 14 ERX-17-002, Rev. 0

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 1 Cycle 20 FIGURE 6 W(Z) AS A FUNCTION OF CORE HEIGHT (9,000 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 1.2108 30 1.1330 57

1. 3797 43 1.2155 29 1.1337 56 1.3764 42 1.2163 28 1.1401 55 1.3717 41
1. 2151 27 1.1455 54
1. 3608 40 1.2119 26 1.1494 53
1. 3432 39 1.2062 25 1.1531 52 1.3217 38 1.2003 24 1.1569 51 1.2982 37 1.1913 23 1.1596 50 1.2726 36 1.1857 22 1.1612 49
1. 2498 35 1.1813 21 1.1638 48
1. 2373 34 1.1733 20 1.1679 47
1. 2265 33 1.1634 19 1.1725 46
1. 2166 32 1.1514 18 1.1763 45 1.2106 31 1.1387 17 1.1803 10 11 12 TOP Axial Node W(Z) 16 1.1885 15 1.2045 14 1.2263 13
1. 2474 12
1. 2683 11 1.2890 10
1. 3088 9
1. 3276 8

1.3448 7

1.3604 6

1.3735 5

1. 3826 1 -

4 Core Height (ft) = (Node -

1)
  • 0.2013236 15 ERX-17-002, Rev. 0

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

COLR for CPNPP Unit 1 Cycle 20 FIGURE 7 W(Z) AS A FUNCTION OF CORE HEIGHT (14,000 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 1.2070 30 1.1882 57 1.3130 43

1. 2132 29 1.1839 56 1.3115 42
1. 2201 28 1.1862 55
1. 3083 41
1. 2286 27 1.1904 54
1. 3003 40
1. 2374 26 1.1931 53
1. 2883 39 1.2429 25 1.1941 52
1. 2742 38 1.2458 24 1.1935 51 1.2599 37
1. 2460 23 1.1916 50 1.2420 36 1.2435 22 1.1884 49 1.2261 35 1.2385 21 1.1842 48
1. 2246 34
1. 2308 20 1.1789 47 1.2205 33
1. 2207 19 1.1736 46
1. 2179 32
1. 2107 18 1.1704 45 1.2128 31 1.1991 17 1.1705 10 11 12 TOP Axial Node W(Z) 16 1.1762 15 1.1884 14
1. 2006 13 1.2138 12 1.2267 11 1.2393 10
1. 2516 9
1. 2632 8
1. 2740 7
1. 2839 6
1. 2920 5
1. 2967 1 -

4 Core Height (ft) = (Node -

1)
  • 0.2013236 16 ERX-17-002, Rev. 0

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 1 Cycle 20 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. 2509 30 1.2435 57
1. 3159 43 1.2585 29 1.2356 56 1.3109 42
1. 2666 28
1. 2365 55
1. 3062 41
1. 2738 27 1.2385 54 1.3005 40 1.2779 26
1. 2379 53 1.2827 39
1. 2798 25
1. 2356 52
1. 2742 38 1.2817 24 1.2324 51
1. 2676 37
1. 2796 23 1.2274 50 1.2577 36
1. 2817 22 1.2207 49 1.2462 35
1. 2849 21
1. 2123 48 1.2330 34 1.2830 20 1.2025 47 1.2278 33 1.2778 19 1.1916 46 1.2325 32
1. 2692 18 1.1800 45 1.2442 31 1.2571 17 1.1741 10 Axial Node 16 15 14 13 12 11 10 9

8 7

6 5

1 -

4 11 12 TOP W(Z) 1.1774 1.1896 1.1994

1. 2097
1. 2217 1.2339 1.2459 1.2577
1. 2690
1. 2798 1.2889
1. 2948 Core Height (ft) = (Node - 1)
  • 0.2013236 17 ERX-17-002, Rev. 0

i:i::

l':il 0

fl,

..:I !

l':il lil E-1 Q

l':il E-1

~

1%,

0 E-1 z l':il CJ i:i::

l':il fl, 100 90 f-I-

f-80 70 60 50

~f-1 40 30 20 10 0

-40 COLR for CPNPP Unit 1 Cycle 20 FIGURE 9 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER

(-15,100)

I

\\

(10,100) j I

\\

1

\\

UNACCEPTABLE I

UNACCEPTABLE OPERATION OPERATION

\\

1 I/

\\

ACCEPTABLE OPERATION I

\\

'l I

\\

1 I

\\

j I

\\

(-30,50)

(30, 50)

-30

-20

-10 0

10 20 30 AXIAL FLUX DIFFERENCE (%)

I-

~

~

40 18 ERX-17-002, Rev. 0

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