CPSES-200203517, Cycle 10 Core Operating Limits Report

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Cycle 10 Core Operating Limits Report
ML022910062
Person / Time
Site: Comanche Peak Luminant icon.png
Issue date: 10/10/2002
From: Madden F
TXU Energy
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
10010, 916(COLR), RN-48, CPSES-200203517, TXX-02183
Download: ML022910062 (24)
v • d • e


Text

t TXU TXU Energy Comanche Peak Steam Electric Station P.O Box 1002 (E01)

Glen Rose, TX 76043 Tel 254 897 8920 Fax 254 897 6652 lance terry@txu corn C. Lance Terry Senior Vice President &

Principal Nuclear Officer Ref: 10CFR50.36 CPSES-200203517 Log # TXX-02183 File # 10010, 916(COLR), RN-48 October 10, 2002 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO. 50-445 THE UNIT 1, CYCLE 10 CORE OPERATING LIMITS REPORT Gentlemen:

Enclosed is the Core Operating Limits Report for Unit 1, Cycle 10 prepared and submitted pursuant to Technical Specification 5.6.5.

This communication contains no new licensing basis commitments regarding CPSES Units 1 and 2.

Sincerely, TXU Generation Company LP By:

TXU Generation Management Company LLC, Its General Partner C. L. Terry Senior Vic President and Principal Nuclear Officer By:

/2'p 2jmý.'J Fred W. Madden Nuclear Licensing Manager JDS/js Enclosure A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway Comanche Peak Diablo Canyon Palo Verde South Texas Project Wolf Creek

ATXU TXX-02183 Page 2 of 2 c -

E. W. Merschoff, Region IV W. D. Johnson, Region IV D. H. Jaffe, NRR Resident Inspectors, CPSES

ERX-02-004, Revision 0 CPSES UNIT 1 CYCLE 10 CORE OPERATING LIMITS REPORT October 2002 Prepared:

n/Ractor M. Ralston eatrPhysi cs Reviewed:

ý &

Wý'

/'ohn T. Bosma Reactor Physics Reviewed:

Parvez Salim Safety Analysis Approved:

52 "/mE //

a, Stephen M. Maier Reactor Physics Supervisor Approved:

/

Wh'eVG. Choe Safety Analsi Manager Date:

/P__z -__

Date:

/0 2-2 Date:

10/-202 Date:

_/_

_/0_

Date:

_/

7 Z.

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

TXU Energy 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, TXU Energy does not authorize its use by others, and any such use is forbidden except with the prior written approval of TXU Energy.

Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein.

In no event shall TXU Energy 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

COLR for CPSES Unit 1 Cycle 10 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

COLR for CPSES Unit I Cycle 10 LIST OF TABLES TABLE PAGE 1

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

.9 iv

COLR for CPSES Unit 1 Cycle 10 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 (MAXIMUM) 13 5

W(Z) AS A FUNCTION OF CORE HEIGHT (150 MWD/MTU) 14 6

W(Z) AS A FUNCTION OF CORE HEIGHT (10,000 MWD/MTU) 15 7

W(Z) AS A FUNCTION OF CORE HEIGHT (20,000 MWD/MTU) 16 8

AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER.............................................

17 V

COLR for CPSES Unit 1 Cycle 10 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for CPSES UNIT 1 CYCLE 10 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 SHUTDOWN MARGIN MODERATOR TEMPERATURE COEFFICIENT ROD GROUP ALIGNMENT LIMITS SHUTDOWN BANK INSERTION LIMITS CONTROL BANK INSERTION LIMITS PHYSICS TESTS EXCEPTIONS - MODE 2 HEAT FLUX HOT CHANNEL FACTOR NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR AXIAL FLUX DIFFERENCE REACTOR TRIP SYSTEM INSTRUMENTATION RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING LIMITS BORON CONCENTRATION I

COLR for CPSES Unit 1 Cycle 10 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 5, 9 through 19, and 21. as supplemented by Item 20.

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 1.3X 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/ 0F.

The EOL/ARO/RTP-MTC shall be less negative than -40 pcm/ 0F.

2

COLR for CPSES Unit 1 Cycle 10 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/ 0F.

The 60 ppm/ARO/RTP-MTC shall be less negative than or equal to -38 pcm/°F.

where:

BOL stands for Beginning of Cycle L ARO stands for All Rods Out HZP stands for Hot Zero THERMAL POW EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER i

f(

ER 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 e

COLR for CPSES Unit 1 Cycle 10 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 2.8.1 FO(Z)

CHANNEL FACTOR (F4(Z))

(LCO 3.

F RT

[K(Z)] for P > 0.5 P

2.1)

FQRTP FQ(Z)

[K(Z)] for P < 0.5

0.5 where

P =

THERMAL POWER RATED THERMAL POWER 4

COLR for CPSES Unit 1 Cycle 10 2.8.2 Foul = 2.42 2.8.3 K(Z) is provided in Figure 3.

2.8.4 Maximum elevation dependent W(Z) values are given in Figure 4.

Figures 5. 6. and 7 give burnup dependent values for W(Z).

Figures 5.

6. and 7 can be used in place of Figure 4 to interpolate or extrapolate (via a three point fit) the W(Z) at a particular burnup.

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 F*(Z) per Surveillance Requirement 3.2.1.2.a.

A constant factor of 2% shall be used at all cycle burnups that are outside the range of Table 1.

2.9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (FNA1) (LCO 3.2.2) 2.9.1 FNAH g FAH [1 + PFH (1-P)]

where:

P =

THERMAL POWER RATED THERMAL POWER 2.9.2 FRTPAH

=

1.55 5

COLR for CPSES Unit 1 Cycle 10 2.9.3 PFH

= 0.3 2.10 AXIAL FLUX DIFFERENCE (AFD)

(LCO 3.2.3) 2.10.1 The AFD target band is

+5%.

-12% at 100% RTP linearly expanding to

+20%.

-17% at 50% RTP.

Below 50% RTP, the AFD target band remains constant at +20%,

-17%.

2.10.2 The AFD Acceptable Operation Limits are provided in Figure 8.

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,

K2 K3 Tro PI T2

= 1.138

= 0.0139 /OF

= 0.00071 /psig

= 559.7 OF 2 2235 psig 2 10 sec

! 3 sec fl(Aq) =

0.00

{(qt-qb) + 65%)

= 0%

2.335. {(qt-qb) - 7.4%)

6 when (qt-qb) < -65% RTP when -65% RTP < (qt-qb) < +7.4% RTP when (qt-qb) > +7.4% RTP

COLR for CPSES Unit 1 Cycle 10 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

> 2222 psig (4 channels)

(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 'F S592 F (4 channels)

(3 channels)

The RCS average temperature limits correspond to the analytical limit of 595.7 TF 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

COLR for CPSES Unit 1 Cycle 10 2.12.4 SR 3.4.1.3 The RCS total flow rate based on precision heat balance shall be > 397,200 gpm 2.12.5 SR 3.4.1.4 The RCS total flow rate based on precision heat balance shall be z 397,200 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 317,000 gpm.

2.13 BORON CONCENTRATION (LCO 3.9.1) 2.13.1 The required refueling boron concentration is 2055 ppm.

3.0 REFERENCES

Technical Specification 5.6.5.

8

COLR for CPSES Unit 1 Cycle 10 Table 1 FQ(Z) MARGIN DECREASES IN EXCESS OF 2 % PER 31 EFPD Cycle Maximum Decrease Burnup In F,(Z) Margin (MWD/MTU)

(Percent) 8460 2.00 8670 2.06 8870 2.17 9080 2.26 9290 2.30 9500 2.29 9700 2.24 9910 2.24 10120 2.28 10330 2.24 10540 2.10 10740 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 the 3.2.1.2.a Surveillance Requirements.

Linear interpolation is acceptable to determine the FQ(Z) margin decrease for cycle burnups which fall between the specified burnups.

9

COLR for CPSES Unit 1 Cycle 10 FIGURE 1 REACTOR CORE SAFETY LIMITS 120 0

20 40 60 80 100 PERCENT OF RATED THERMAL POWER 10 670 660 650 640 630 r*>n 610 600 590 580 570 560 550

COLR for CPSES Unit 1 Cycle 10 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 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.

11 240 220 200 180 I

160 160 U) c-140 U,

z 0

120 0

100 z

r 80 0 0 n,60 40 20 0

    • (25.3,218 i

(79.6,218)

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BANK B II N#

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i l I I i I 1

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+

BANK C I

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COLR for CPSES Unit 1 Cycle 10 FIGURE 3 k(Z)

NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 11

  • FH+

111 1 II1.1.

IIIH+

+111++t++

+F.0.1.

(F6, 0I+

+/- 1 +/-+/-..

(o~~o11111,7,,

-14 II1 L

,,,IIIIIL (120..25 II IIII li t I Ii m

_M.. _

HttiM

-W W,,*,,

~I i 1 1 1l l l l L I-L i l i

l i 2

3 4

5 6

7 8

9 10 11 12 CORE HEIGHT (FEET)

TOP Axial Node 53 52 51 50 49 48 47 46 K(Z) 0.9450 0.9475 0.9500 0.9525 0.9550 0.9575 0.9600 0.9625 Axial Node 45 44 43 42 41 40 39 38 K(Z) 0.9650 0.9675 0.9700 0.9725 0.9750 0.9775 0.9800 0.9825 Axial Node 37 36 35 34 33 32 1 - 31 K(Z) 0.9850 0.9875 0.9900 0.9925 0.9950 0.9975 1.0000

1)
  • 0.2 Core Height (ft) = (Node -

12 1.1 1.0 0.9 0.8 ue 0.7 0 w N0.6 0n, 0.5 0 z 0.4 N

0.3 0.2 0.1 0.0 0

-1 BOTTOM Axial Node 61 0

60 0

59 0

58 0

57 0

56 0

55 0

54 0

KMZ)

.9250

.9275

.9300

.9325

.9350

.9375

.9400

.9425

COLR for CPSES Unit 1 Cycle 10 FIGURE 4 W(Z) AS A FUNCTION OF CORE HEIGHT (MAXIMUM) 0 1

2 3

4 5

6 7

8 9

10 11 12 BOTTOM CORE HEIGHT (FEET)

TOP Axial Node W(Z) 52 - 61 51 1.152 50 1.158 49 1.155 48 1.145 47 1.135 46 1.130 45 1.133 44 1.134 43 1.134 42 1.134 Axi al Node 41 40 39 38 37 36 35 34 33 32 31 W(Z) 1.134 1.134 1.133 1.131 1.128 1.126 1.122 1.117 1.111 1.107 1.106 Axial Node W(Z) 30 1.108 29 1.114 28 1.121 27 1.129 26 1.134 25 1.137 24 1.140 23 1.142 22 1.144 21 1.146 20 1.147 Axial Node W(Z) 19 1.150 18 1.154 17 1.158 16 1.163 15 1.168 14 1.176 13 1.186 12 1.194 11 1.202 1 - 10 Core Height (ft) = (Node - 1)

  • 0.2 13 1.300 1.250 1.200 S1.150 1.100 1.050 1.000

COLR for CPSES Unit 1 Cycle 10 FIGURE 5 W(Z) AS A FUNCTION OF CORE HEIGHT (150 MWD/MTU)

I I.I I

i

~

eI

'F' 0 1 3

4 5

6 7

8 10 1 1 CORE HEIGHT (FEET)

Axial Node W(Z) 52 - 61 51 1.152 50 1.152 49 1.146 48 1.138 47 1.131 46 1.128 45 1.126 44 1.124 43 1.121 42 1.118 Axial Node 41 40 39 38 37 36 35 34 33 32 31 W(Z) 1.117 1.115 1.111 1.107 1.103 1.099 1.096 1.095 1.096 1.097 1.100 Axial Node 30 29 28 27 26 25 24 23 22 21 20 W(Z) 1.103 1.107 1.113 1.118 1.124 1.130 1.134 1.138 1.142 1.145 1.147 Axial Node W(Z) 19 1.150 18 1.154 17 1.158 16 1.163 15 1.168 14 1.172 13 1.177 12 1.181 11 1.185 1 - 10 Core Height (ft) = (Node - 1)

  • 0.2 14 1.300 1.250 1.200 D 1.150 1.100 1.050 1.000 BOTTOM TOP

COLR for CPSES Unit 1 Cycle 10 FIGURE 6 W(Z) AS A FUNCTION OF CORE HEIGHT (10,000 MWD/MTU) 1.300 1

1 1.250 1.200 f

D1.150 l/

1.100

/

I 1.050 1.000 0

1 2

3 4

5 6

7 8

9 10 11 12 BOTTOM Axial Node 52 - 61 51 50 49 48 47 46 45 44 43 42 W(Z) 1.151 1.158 1.155 1.145 1.135 1.130 1.128 1.127 1.125 1.123 CORE HEIGHT (FEET)

Axi al Node 41 40 39 38 37 36 35 34 33 32 31 W(Z) 1.121 1.119 1.116 1.113 1.110 1.106 1.102 1.098 1.094 1.093 1.095 Axial Node 30 29 28 27 26 25 24 23 22 21 20 W(z) 1.099 1.104 1.110 1.115 1.121 1.125 1.129 1.131 1.133 1.135 1.137 Axial Node 19 18 17 16 15 14 13 12 11 1 - 10 TOP W(z) 1.141 1.146 1.152 1.158 1.165 1.172 1.178 1.183 1.188 Core Height (ft) = (Node - 1)

  • 0.2 15

COLR for CPSES Unit 1 Cycle 10 FIGURE 7 W(Z) AS A FUNCTION OF CORE HEIGHT (20,000 MWD/MTU) 0 1

2 3

4 5

6 7

8 9

10 11 12 CORE HEIGHT (FEET)

Axial Node W(Z) 52 - 61 51 1.143 50 1.141 49 1.137 48 1.132 47 1.130 46 1.130 45 1.133 44 1.134 43 1.134 42 1.134 Axial Node W(Z) 41 1.134 40 1.134 39 1.133 38 1.131 37 1.128 36 1.126 35 1.122 34 1.117 33 1.111 32 1.107 31 1.106 Axial Node W(Z) 30 1.108 29 1.114 28 1.121 27 1.129 26 1.134 25 1.137 24 1.140 23 1.142 22 1.144 21 1.146 20 1.146 Axial Node W(Z) 19 1.145 18 1.145 17 1.148 16 1.156 15 1.166 14 1.176 13 1.186 12 1.194 11 1.202 1 - 10 Core Height (ft) = (Node - 1)

  • 0.2 16 1.300 1.250 1.200

= 1.150 1.100 1.050 1.000 BOTTOM TOP

COLR for CPSES Unit 1 Cycle 10 FIGURE 8 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 100 90 80

-30

-20

-10 0

10 20 DEVIATION FROM TARGET AXIAL FLUX DIFFERENCE (%)

30 40 17

-17904 I

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