CPSES-200700691, Core Operating Limits Report, Cycle 13

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)

Text

8V v TXU Power I"w Power I~m Bleieins Comanche Peak Steam Senior Vice President &

Bectric Stalion Chief Nuclear Officer PR 0. Box 1002 (E01)

Glen Rose, TX 76043 Ref: Tech. Spec. 5.6.5 Tel: 254 897 5209 Fax: 254 897 6652 mite-blevinsCxu.com 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 Callaway e Comanche Peak

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

ERX-07-001, Rev. 0 CPSES UNIT 1 CYCLE 13 CORE OPERATING LIMITS REPORT March 2007 Prepared: ____________

Daniel Principal E. Brozak Engineer, Date:.2z/

Westinghouse Electric Co.

Reviewed: §L u Date: 3/28*/10 4ohn T. Bosma Principal Engineer, Westinghouse Electric Co.

Reviewed: Date: /207 evin and EN.R 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 PAGE 1 FQ(Z) MARGIN DECREASES IN EXCESS OF 2 % PER 31 EFPD ........ 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 SAFETY LIMITS LCO 3.1.1 SHUTDOWN MARGIN LCO 3.1.3 MODERATOR TEMPERATURE COEFFICIENT 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 LCO 3.2.2 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR LCO 3.2.3 AXIAL FLUX DIFFERENCE LCO 3.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LCO 3.4.1 RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING LIMITS LCO 3.9.1 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)) (LCO 3.2.1)

FRTP FQ 2.8.1 FQ (Z) _ [K(Z)] for P > 0.5 P

FFRTP FQ(Z) < _ [K(Z)] for P S 0.5

0.5 where

P - THERMAL POWER RAT]ED THERMAL POWER 4 ERX-07-001, Rev. 0

COLR for CPSES Unit 1 Cycle 13 2.8.2 FFRTP = 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)

T 2.9.1 FNAH S FR PAH [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 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; K1 = 1.138 K2 = 0.0139 /'F K3 = 0.00071 /psig 1

TP = 555.2 'F p1 2235 psig T, 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 Maximum Decrease Burnup In FQ(Z) Margin (MWD/MTU) (Percent) 150 2.00 360 2.09 570 2.46 780 2.51 980 2.33 1190 2.04 1400 2.00 7030 2.00 7230 2.18 7440 2.71 7650 3.16 7860 3.63 8070 3.92 8280 4.08 8480 4.08 8690 4.19 8900 4.17 9110 4.03 9320 3.82 9530 3.58 9730 3.33 9940 3.14 10150 3.03 10360 2.94 10570 2.82 10780 2.69 10980 2.54 11190 2.33 11400 2.07 11610 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 80.0 100.0 116.4 Percent of Rated Thermal Power 10 ERX-07-001, Rev. 0

COLR for CPSES Unit 1 Cycle 13 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 240 (25.3,2 ,-(79.6,218 220 200 180 I I L i

$4

'a::

• 160 aP, 140 120 o -(,9  ; - # - 'I , 1, Il I i 0

H H 100 0

I- 170 164ill_ '

80 t- 1/1 ' (0 16 0

g 60 40 20 0

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 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 (0.0,i.0) (6. 0,1. 0) 1.0 0.9 (12.0,0.925)

II~I-WII 0.8 44 - TI 71 11 I

" 0.7 H H IIII III 11 H i IIH 1 1 11 N 0.6 H " IIIT1IH d 11 111 1 1 I!1'

-M

ý I-M--II I - U I- ý 1 0 0.5 I -FII f 0.4 4440- 7--N-T#-#-7L N

IIIMIIIIIIIH IIII IIH I I M 1 II I Hl 0.3 H I I W I I t4#t t 0.2 0.1 0.0 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) TOP Axial Axial Axial Axial Node K(Z) Node K(Z) Node K(Z) Node K(Z) 61 0.9250 53 0.9450 45 0.9650 37 0.9850 60 0.9275 52 0.9475 44 0.9675 36 0.9875 59 0.9300 51 0.9500 43 0.9700 35 0.9900 58 0.9325 50 0.9525 42 0.9725 34 0.9925 57 0.9350 49 0.9550 41 0.9750 33 0.9950 56 0.9375 48 0.9575 40 0.9775 32 0.9975 55 0.9400 47 0.9600 39 0.9800 1 - 31 1.0000 54 0.9425 46 0.9625 38 0.9825 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 -V- 4 1.100 _-------~-..-v< I zK 1.050 1.000 0 1 I 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) 52 - 61 41 1.130 30 1.127 19 1.148 51 1.138 40 1.132 29 1.135 18 1.150 50 1.140 39 1.132 28 1.142 17 1.153 49 1.137 38 1.132 27 1.146 16 1.159 48 1.130 37 1.131 26 1.149 15 1.171 47 1.124 36 1.129 25 1.152 14 1.182 46 1.124 35 1.125 24 1.153 13 1.193 45 1.126 34 1.117 23 1.154 12 1.202 44 1.127 33 1.111 22 1.154 11 1.211 43 1.127 32 1.110 21 1.153 1 - 10 42 1.128 31 1.116 20 1.151 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 Axial Axial Axial Node w(z) Node w(Z) Node W(Z) Node w (Z) 52 - 61 41 1.119 30 1.110 19 1.148 51 1.116 40 1.122 29 1.115 18 1.150 50 1.108 39 1.121 28 1.122 17 1.153 49 1.103 38 1.117 27 1.128 16 1.158 48 1.103 37 1.112 26 1.132 15 1.163 47 1.105 36 1.108 25 1.135 14 1.167 46 1.108 35 1.106 24 1.138 13 1.171 45 1.111 34 1.106 23 1.141 12 1.174 44 1.112 33 1.106 22 1.144 11 1.177 43 1.113 32 1.107 21 1.145 1 - 10 42 1.115 31 1.108 20 1.147 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) TOP Axial Axial Axial Axial Node w(Z) Node w(Z) Node w(z) Node w(Z) 52 - 61 41 1.118 30 1.105 19 1.141 51 1.138 40 1.117 29 1.112 18 1. 144 50 1.140 39 1.116 28 1.118 17 1.150 49 1.137 38 1.115 27 1.123 16 1.157 48 1. 130 37 1.113 26 1.127 15 1.164 47 1,124 36 1.111 25 1. 130 14 1.171 46 1.123 35 1.107 24 1.133 13 1.176 45 1.123 34 1.102 23 1.136 12 1.180 44 1. 122 33 1.098 22 1.137 11 1.185 43 1.120 32 1.097 21 1.139 1 - 10 42 1.119 31 1.100 20 1.140 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) TOP Axial Axial Axial Axial Node 1.7(Z) Node w(Z) Node w(Z) Node W (Z) 52 - 61 41 1.130 30 1.127 19 1.148 51 1.131 40 1.132 29 1.135 18 1.147 50 1.133 39 1.132 28 1.142 17 1.150 49 1.131 38 1.132 27 1.146 16 1.159 48 1.127 37 1.131 26 1.149 15 1.171 47 1.124 36 1.129 25 1.152 14 1.182 46 1.124 35 1. 125 24 1.153 13 1.193 45 1.126 34 1.117 23 1.154 12 1.202 44 1.127 33 1.111 22 1.154 11 1.211 43 1.127 32 1.110 21 1.153 1 - 10 42 1.128 31 1.116 20 1.151 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

(-15 (9_0)7

-15,90) -, - (12, (1,9) 90 -

90 I I I I I I _

UNACCEPTABLE OPERATION L7~UNACCEPTABLE OPERATION 80

, ,----- ----- ACCEPTABLE - -- --

1111! - OPERATION - I

-i 70

. .. j ij... ,1- - ,!

0 60

--+--+

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- t- -~- -- -- - -- - --..-

i -

+--- -

t 50 40 0

O 30 -- -i- --

20

-F

---

T-10 A3

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

17 ERX-07-001, Rev. 0