CPSES-200700691, Core Operating Limits Report, Cycle 13

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Core Operating Limits Report, Cycle 13
ML071000157
Person / Time
Site: Comanche Peak 
Issue date: 04/04/2007
From: Blevins M, Madden F
TXU Generation Co, LP, TXU Power
To:
Document Control Desk, NRC/NRR/ADRO
References
CPSES-200700691, TXX-07074
Download: ML071000157 (23)
v • d • e


Text

8V TXU v

Power I"w Power Comanche Peak Steam Bectric Stalion PR 0. Box 1002 (E01)

Glen Rose, TX 76043 Tel: 254 897 5209 Fax: 254 897 6652 mite-blevinsCxu.com I~m Bleieins Senior Vice President &

Chief Nuclear Officer Ref: Tech. Spec. 5.6.5 CPSES-200700691 Log # TXX-07074 April 4, 2007 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO. 50-445 CORE OPERATING LIMITS REPORTS

Dear Sir or Madam:

Enclosed is the Core Operating Limits Reports for CPSES Unit 1, Cycle 13. This report is prepared and submitted pursuant to Technical Specification 5.6.5.

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

Sincerely, TXU Generation Company LP By:

TXU Generation Management Company LLC Its General Partner Mike Blevins By: -A di fl§ i "Fred W. Madden Director, Oversight and Regulatory Affairs JDS Enclosure c -

B. S. Mallett, Region IV M. C. Thadani, NRR Resident Inspectors, CPSES A member of the STARS (Strategic Teaming and Resource Sharing) Alliance AD I Callaway e Comanche Peak

  • Diablo Canyon o Palo Verde o South Texas Project o Wolf Creek

ERX-07-001, Rev.

0 CPSES UNIT 1 CYCLE 13 CORE OPERATING LIMITS REPORT March 2007 Prepared:

Date:.2z/

Daniel E.

Brozak Principal Engineer, Westinghouse Electric Co.

Reviewed: §L u

Date:

3/28*/10 4ohn T.

Bosma Principal Engineer, Westinghouse Electric Co.

Reviewed:

Date:

/207 evin EN.R and Principal Engineer, Westinghouse Electric Co.

Approved:

Date:

___l"ý Jame"s BoatwrDt:

/2 CDSA Supervisor, Westinghouse Electric Co.

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

TXU Generation Company LP 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 Generation Company LP does not authorize its use by others, and any such use is forbidden except with the prior written approval of TXU Generation Company LP. 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 Generation Company LP 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-07-001, Rev.

0

COLR for CPSES Unit 1 Cycle 13 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-07-001, Rev.

0

COLR for CPSES Unit 1 Cycle 13 LIST OF TABLES TABLE 1

FQ(Z)

MARGIN DECREASES IN EXCESS OF 2 % PER 31 EFPD........

PAGE 9

iv ERX-07-001, Rev.

0

COLR for CPSES Unit 1 Cycle 13 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

ERX-07-001, Rev.

0

COLR for CPSES Unit 1 Cycle 13 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for CPSES UNIT 1 CYCLE 13 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 1

ERX-07-001, Rev.

0

COLR for CPSES Unit 1 Cycle 13 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 3, 6 through 16, 19 and 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 1.3% Ak/k in MODE 2 with Koff < 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-07-001, Rev.

0

COLR for CPSES Unit 1 Cycle 13 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-07-001, Rev.

0

COLR for CPSES Unit 1 Cycle 13 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))

FRTP FQ 2.8.1 FQ (Z)

[K(Z)]

for P

P (LCO 3.2.1)

> 0.5 FRTP F

FQ(Z)

0.5 where

P RAT]

[K(Z)] for P S 0.5 THERMAL POWER ED THERMAL POWER 4

ERX-07-001, Rev.

0

COLR for CPSES Unit 1 Cycle 13 FRTP 2.8.2 F

= 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

[ FJc(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.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 (F N (LCO 3.2.2) 2.9.1 FNAH S

FRTPAH

[1 + PFAH (1-P)I where:

P =

THERMAL POWER RATED THERMAL POWER 2.9.2 F.. AH =

1.55 2.9.3 PFAH

=

0.3 5

ERX-07-001, Rev.

0

COLR for CPSES Unit 1 Cycle 13 2.10 AXIAL FLUX DIFFERENCE (AFD)

(LCO 3.2.3) 2.10.1 The AFD target band is

+5%,

-12% at expanding to +20%,

-17% at 50% RTP.

AFD target band remains constant at 2.10.2 The AFD Acceptable Operation Limits Figure 8.

100% RTP linearly Below 50% RTP, the

+20%,

-17%.

are provided in 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 K2 K3 TP 1

p 1 T,

=

1.138

=

0.0139 /'F

=

0.00071 /psig

=

555.2 'F 2235 psig 10 sec T,

-5 3 sec f 1 (Aq) = 0.00 - {(q,-q,)

+ 65%)

when (q,-q 1 ) 5 -65% RTP

= 0%

when -65% RTP <

(q 1 -qb)

< +8.0% RTP

= 2.335 - {(qt-q1 ) -

8.0%)

when (q,-qb) > +8.0% RTP 6

ERX-07-001, Rev.

0

COLR for CPSES Unit 1 Cycle 13 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)

Ž 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

587 'F (4 channels) 5 587 'F (3 channels)

The RCS average temperature limits correspond to the analytical limit of 590.7 'F 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-07-001, Rev. 0

COLR for CPSES Unit 1 Cycle 13 2.12.4 SR 3.4.1.3 The RCS total flow rate shall be 2 403,700 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 t1985 ppm.

3.0 REFERENCES

Technical Specification 5.6.5 (through Amendment 136).

8 ERX-07-001, Rev.

0

COLR for CPSES Unit 1 Cycle 13 Table 1 F,(Z)

MARGIN DECREASES IN EXCESS OF 2 % PER 31 EFPD Cycle Burnup (MWD/MTU) 150 360 570 780 980 1190 1400 7030 7230 7440 7650 7860 8070 8280 8480 8690 8900 9110 9320 9530 9730 9940 10150 10360 10570 10780 10980 11190 11400 11610 Maximum Decrease In FQ(Z)

Margin (Percent) 2.00 2.09 2.46 2.51 2.33 2.04 2.00 2.00 2.18 2.71 3.16 3.63 3.92 4.08 4.08 4.19 4.17 4.03 3.82 3.58 3.33 3.14 3.03 2.94 2.82 2.69 2.54 2.33 2.07 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 ERX-07-001, Rev.

0

COLR for CPSES Unit 1 Cycle 13 FIGURE 1 REACTOR CORE SAFETY LIMITS 670 660 650 640 4) 41 630 ty) s4 620 610 600 590 580 '

0.0 20.0 40.0 60.0 80.0 Percent of Rated Thermal Power 100.0 116.4 10 ERX-07-001, Rev.

0

240 220 200 180

$4

'a::

160 a 140 P,

120 o0 H

H 100 0

80 0

g 60 40 20 COLR for CPSES Unit 1 Cycle 13 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER (25.3,2

,-(79.6,218 I

I L i

-(,9

' I 1,

Il I

i I-170 164ill_

t-1/1 (0

16 00 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-07-001, Rev.

0

COLR for CPSES Unit 1 Cycle 13 FIGURE 3 K(Z)

NORMALIZED FQ(Z)

AS A FUNCTION OF CORE HEIGHT 1.1 1.0 0.9 0.8

" 0.7 N

0.6 0

0.5 0.4 N

0.3 0.2 0.1 0.0 (0.0,i.0)

(6. 0,1. 0)

(12.0,0.925)

II~I-WII 44

- TI 71 11 I

H III III H I 11 H i IIH 1 1 11 H "

IIIT1IH d

11 111 1

1 I!1'

-M -M

ý I --II I -

U I- ý 1

I f

-FII 4440-7--N-T#-#-7L III II IIH M III IIII IIH I I M 1 I I I H l H I I

W I I t t4#

t 0

1 BOTTOM 2

3 4

5 6

7 8

9 10 11 12 CORE HEIGHT (FEET)

TOP Axial Node 61 60 59 58 57 56 55 54 K(Z) 0.9250 0.9275 0.9300 0.9325 0.9350 0.9375 0.9400 0.9425 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 Core Height (ft)

= (Node -

1)
  • 0.2 12 ERX-07-001, Rev.

0

COLR for CPSES Unit 1 Cycle 13 FIGURE 4 W(Z)

AS A FUNCTION OF CORE HEIGHT (MAXIMUM) 1.300 1.250 1.200 1.150 1.100 1.050 1.000

-~---------~--~-~-

-1

-V-4

_-------~-..-v<

I zK I

0 1

2 3

4 5

6 7

8 9

10 11 12 BOTTOM CORE HEIGHT (FEET)

Axial Node 52 -

61 51 50 49 48 47 46 45 44 43 42 w(Z) 1.138 1.140 1.137 1.130 1.124 1.124 1.126 1.127 1.127 1.128 Axial Node 41 40 39 38 37 36 35 34 33 32 31 w(Z) 1.130 1.132 1.132 1.132 1.131 1.129 1.125 1.117 1.111 1.110 1.116 Axial Node 30 29 28 27 26 25 24 23 22 21 20 w(Z) 1.127 1.135 1.142 1.146 1.149 1.152 1.153 1.154 1.154 1.153 1.151 Axial Node 19 18 17 16 15 14 13 12 11 1 -

10 TOP w(Z) 1.148 1.150 1.153 1.159 1.171 1.182 1.193 1.202 1.211 Core Height (ft)

= (Node -

1)
  • 0.2 13 ERX-07-001, Rev.

0

COLR for CPSES Unit 1 Cycle 13 FIGURE 5 W(Z) AS A FUNCTION OF CORE HEIGHT (150 MWD/MTU) 1.300 1.250 1.200 1.150 X

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 Node 52 -

61 51 50 49 48 47 46 45 44 43 42 w(z) 1.116 1.108 1.103 1.103 1.105 1.108 1.111 1.112 1.113 1.115 Axial Node 41 40 39 38 37 36 35 34 33 32 31 w(Z) 1.119 1.122 1.121 1.117 1.112 1.108 1.106 1.106 1.106 1.107 1.108 Axial Node 30 29 28 27 26 25 24 23 22 21 20 W(Z) 1.110 1.115 1.122 1.128 1.132 1.135 1.138 1.141 1.144 1.145 1.147 Axial Node 19 18 17 16 15 14 13 12 11 1 -

10 w (Z) 1.148 1.150 1.153 1.158 1.163 1.167 1.171 1.174 1.177 Core Height (ft)

= (Node -

1)
  • 0.2 14 ERX-07-001, Rev.

0

COLR for CPSES Unit 1 Cycle 13 FIGURE 6 W(Z)

AS A FUNCTION OF CORE HEIGHT (10,000 MWD/MTU) 1.300 1.250 1.200 2

D 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)

Axial Node 52 -

61 51 50 49 48 47 46 45 44 43 42 w(Z) 1.138 1.140 1.137

1. 130 1,124 1.123 1.123
1. 122 1.120 1.119 Axial Node 41 40 39 38 37 36 35 34 33 32 31 w(Z) 1.118 1.117 1.116 1.115 1.113 1.111 1.107 1.102 1.098 1.097 1.100 Axial Node 30 29 28 27 26 25 24 23 22 21 20 w(z) 1.105 1.112 1.118 1.123 1.127
1. 130 1.133 1.136 1.137 1.139 1.140 Axial Node 19 18 17 16 15 14 13 12 11 1 -

10 TOP w(Z) 1.141

1. 144 1.150 1.157 1.164 1.171 1.176 1.180 1.185 Core Height (ft)

= (Node -

1)
  • 0.2 15 ERX-07-001, Rev.

0

COLR for CPSES Unit 1 Cycle 13 FIGURE 7 W(Z)

AS A FUNCTION OF CORE HEIGHT (20,000 MWD/MTU) 1.300 1.250 1.200 z

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)

Axial Node 52 -

61 51 50 49 48 47 46 45 44 43 42 1.7(Z) 1.131 1.133 1.131 1.127 1.124 1.124 1.126 1.127 1.127 1.128 Axial Node 41 40 39 38 37 36 35 34 33 32 31 w(Z) 1.130 1.132 1.132 1.132 1.131 1.129

1. 125 1.117 1.111 1.110 1.116 Axial Node 30 29 28 27 26 25 24 23 22 21 20 w(Z) 1.127 1.135 1.142 1.146 1.149 1.152 1.153 1.154 1.154 1.153 1.151 Axial Node 19 18 17 16 15 14 13 12 11 1 -

10 TOP W (Z) 1.148 1.147 1.150 1.159 1.171 1.182 1.193 1.202 1.211 Core Height (ft)

= (Node -

1)
  • 0.2 16 ERX-07-001, Rev.

0

COLR for CPSES Unit 1 Cycle 13 FIGURE 8

AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 100 90 80 70 0

0 O

60 50 40 30

(-15 9_0)7 (12, 90

( -15,90)

(1,9)

I I

I I

I I

UNACCEPTABLE L7~UNACCEPTABLE OPERATION OPERATION ACCEPTABLE 1111!

OPERATION I

-i j ij...

,1-

---1 <--..

+-- ---

--+--+

t- -~- --

i t

-F T-

-i -

20 10 A3

-40

-30

-20

-10 0

10 20 DEVIATION FROM TARGET AXIAL FLUX DIFFERENCE (%)

30 40 17 ERX-07-001, Rev.

0

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