CPSES-200401176, To the Core Operating Limits Reports

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To the Core Operating Limits Reports
ML041190624
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 04/21/2004
From: Madden F
TXU Electric
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CPSES-200401176, TXX-04081
Download: ML041190624 (46)
v • d • e


Text

{{#Wiki_filter:* TXU -.4w£kt I TXU Energy Comanche PeakSteam Electric Station P.O. Box 1002 (E01) Glen RoseTX 76043 Tel: 254 897 5209 Fax: 254 897 6652 mike.blevins@txu.com Mike Blevins Senior Vice President & Principal Nuclear Officer Ref: Tech. Spec. 5.6.5 CPSES-200401176 Log # TXX-04081 April 21, 2004 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) DOCKET NOS. 50-445 AND 50446 REVISION 1 TO THE CPSES UNITS 1 AND 2 CORE OPERATING LIMITS REPORTS Gentlemen: Enclosed are the Core Operating Limits Reports for CPSES Unit 1, Cycle 11 Revision I and Unit 2, Cycle 8, Revision 1. The original Unit 1, Cycle I1 Core Operating Limits Report was not issued for use. These reports are prepared and submitted pursuant to Technical Specification 5.6.5. (oo A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

  • Comanche Peak
  • Diablo Canyon
  • Palo Verde South Texas Project Wolf Creek

TXX-04081 Page 2 of 2 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 Mike Blevins By: jd 2 ) l2i Fred W. Madden Regulatory Affairs Manager JDS/js Enclosure(s) c - B. S. Mallett, Region IV W. D. Johnson, Region IV M. C. Thadani, NRR Resident Inspectors, CPSES

ERX-04-001, Revision 1 CPSES UNIT 1 CYCLE 11 CORE OPERATING LIMITS REPORT April 2004 Prepared: Reviewed: Reviewed: I>:) 'XDate: Daniel E. Brozak 5 Reactor Physics

_ S V

4 JN Date: S. Srinilta Reactor Physics /a C Date: Hugo basilva Safety Analysis

  • A//°1 O/

,4/1-/O 4 V/-z /a? Approved: Approved: ___/__ _ ____;_ Date:_______ Stephen M. Maier Rea for Physics Supervisor 5 Date: i~/ 2,/ C (J_ eG.cgoeI Safety Anlysis Manager

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 Rev. 1

COLR for CPSES Unit 1 Cycle 11 TABLE OF CONTENTS DISCLAIMER................................................... 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 A!

  • Rev. 1

COLR for CPSES Unit 1 Cycle 11 LIST OF TABLES TABLE PAGE 1 F,(Z) MARGIN DECREASES IN EXCESS OF 2 % PER 31 EFPD.... 9 iv Rev. 1

COLR for CPSES Unit 1 Cycle 11 LIST OF FIGURES FIGURE PAGE 1 REACTOR CORE SAFETY LIMITS 10 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER....... 11 3 K(Z) - NORMALIZED F.(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 Rev. 1

COLR for CPSES Unit 1 Cycle 11 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for CPSES UNIT 1 CYCLE 11 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 Rev. 1

COLR for CPSES Unit 1 Cycle 11 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 and 9 through 19, as supplemented by Items 20 and 21. 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 KRef < 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 Rev. 1

COLR for CPSES Unit 1 Cycle 11 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 Rev. 1

COLR for CPSES Unit 1 Cycle 11 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 MODE 2 during PHYSICS TESTS. 2.8 HEAT FLUX HOT CHANNEL FACTOR (F. (Z)) RTP FQ 2.8.1 F0(Z) [K(Z)] for P p or equal to 1.3% Ak/k in (LCO 3.2.1) > 0.5 FRTP F0 FQ(Z) [K(Z)] for P < 0.5

0.5 where

P = THERMAL POWER RATED THERMAL POWER 4 Rev. 1

COLR for CPSES Unit 1 Cycle 11 RT? 2.8.2 Fo = 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 F,(Z) evaluations show an increase in the expression maximum over Z [ Foc(z) / K(Z) ], the burnup dependent values in Table 1 shall be used instead of a constant 2% to increase Fw (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"AHI (LCO 3.2.2) 2.9.1 F 1 AH F'T AH [I + PFAH (I-P)J where: P = THERMAL POWER RATED THERMAL POWER 2.9.2 FET AH = 1.55 2.9.3 PFAH = 0.3 5 Rev. 1

COLR for CPSES Unit 1 Cycle 11 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; = 1.138 K2 K3 = 0.0139 /0F = 0.00071 /psig = 559.7 OF k 2235 psig P1 Tl 2 10 sec T2 S9 3 sec f1 (Aq) = 0.00 - {(qt-qb) + 65%) when (qt-qb)* -65% RTP = 0% when -65% RTP < (qt-qb) < +7.4% RTP = 2.335 * {(qt-qb) - 7.4%) when (qt-qb) 2 +7.4% RTP 6 Rev. 1

COLR for CPSES Unit 1 Cycle 11 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 2 2220 psig (4 channels) 2 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 592 0F (4 channels) < 592 OF (3 channels) The RCS average temperature limits correspond to the analytical limit of 595.7 °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 Rev. 1

COLR for CPSES Unit 1 Cycle 11 2.12.4 SR 3.4.1.3 The RCS total flow rate based on precision heat balance shall be a 397,200 gpm 2.12.5 SR 3.4.1.4 The RCS total flow rate based on precision heat balance shall be > 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 1985 ppm.

3.0 REFERENCES

Technical Specification 5.6.5. 8 Rev. 1

COLR for CPSES Unit 1 Cycle 11 Table 1 F,(Z) MARGIN DECREASES IN EXCESS OF 2 % PER 31 EFPD Cycle Burnup (MWD/MTU) 150 360 570 780 7870 8080 8290 8490 8700 8910 9120 9330 9540 Maximum Decrease In F. (Z) Margin (Percent) 2.00 2.03 2.12 2.00 2.00 2.22 2.39 2.48 2.45 2.36 2.21 2.06 2.00 Note: All Cycle burnups outside the range of the table shall use a constant 2% decrease in F,(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 Rev. 1

COLR for CPSES Unit 1 Cycle 11 FIGURE 1 REACTOR CORE SAFETY LIMITS 670 Unacceptable Operation 660 650 640 o 620 610 1845 psig Acceptable Operation 600 590 580 0.0 20.0 40.0 60.0 80.0 100.0 116.4 Percent of Rated Thermal Power 10 Rev. 1

COLR for CPSES Unit 1 Cycle 11 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 240 220 200 3 180 .1 160 .-4 3 Qz 140 a1) .LJ 120 z0 H H 100 En Un, Pa 4 80 Q 60 0 IJ 1. I I I I I I I I I I I (25.3,218 (7.6, 18) BANK B TT_ (,164 I I l i l t I I-10,146) 4 (10 I l i l i l t I ' 1 1 1 I I I 1 1 I I I BANK C J I i f I I I 1 1- _T_ .(0,49) -44 -LL Ili I I I I I v I I I I 1 1 I l i l t l i l t I 1 1 I I I I I I I I.I. - (31.0) -M 11'T I II I I FT7_FI 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. 311 Rev. 1

COLR for CPSES Unit 1 Cycle 11 FIGURE 3 K(Z) NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.1 1.0 0.9 0.8 N 0 N H 0.6 0 H~ 0. 6 z 1li 1ll llT X Ill II II llrT 114 t1i f i II I L< HLL X IIIII H 10 1 ll itI l t11 + ILL ft tIt tH+ I0 tH+t eIt i Wt~~~~ M W 11 -H T+XttX~ N 0.4 0.3 0.2 0.1 0.0 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) 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. 9 675
0. 9700
0. 9725
0. 9750 0.9775
0. 9800
0. 9825 Axial Node 37 36 35 34 33 32 1 -

31 TOP K (z) 0.9850 0.9875 0.9900 0.9925 0.9950 0.9975

1. 0000 Core Height (ft)

= (Node

1)
  • 0.2 12 Rev.

1

COLR for CPSES Unit 1 Cycle 11 FIGURE 4 W(Z) AS A FUNCTION OF CORE HEIGHT (MAXIMUM) 1.300 1.250 1.200 BRi D 1.150 1.100 1.050 1.000 - _ I  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) 1.145 1.152 1.151 1.142 1.134 1.132 1.133 1.134 1.134 1.135 Axial Node 41 40 39 38 37 36 35 34 33 32 31 W(Z) 1.13 6 1.13 6 1.13 6 1.134 1.132 1.13 0 1.125 1.119 1.116 1.115 1.114 Axial Node 30 29 28 27 26 25 24 23 22 21 20 W (Z) 1.119 1.125 1.131 1.135 1.139 1.143 1.146 1.148 1.149 1.150 1.149

  • Axial Node 19 18 17 16 15 14 13 12 11 1 -

10 W (Z) 1.147 1.146 1.151 1.160 1.173 1.185 1.195 1.204 1.213 13 Rev. 1

COLR for CPSES Unit 1 Cycle 11 FIGURE 5 W(Z) AS A FUNCTION OF CORE HEIGHT (150 MWDIMTU) 1.300 1.250 1.200 N D 1.150 1.100 1.050 1.000 I I t=. X-t < -4X-t 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) 1.130 1.121 1.115 1.113 1.113 1.114 1.115 1.115 1.117 1.122 Axial Node 41 40 39 38 37 36 35 34 33 32 31 W(Z) 1.129 1.135 1.134 1.128 1.123 1.121 1.120 1.119 1.116 1.115 1.114 Axial Node 30 29 28 27 26 25 24 23 22 21 20 W(Z) 1.115 1.118 1.121 1.125 1.12 8 1.131 1.134 1.137 1.13 8 1.14 0 1.141 Axial Node 19 18 17 16 15 14 13 12 11 1 - 10 TOP W(Z) 1.142 1.144 1.147 1.151 1.157 1.162 1.167 1.172 1.176 14 Rev. 1

COLR for CPSES Unit 1 Cycle 11 FIGURE 6 W(Z) AS A FUNCTION OF CORE HEIGHT (10,000 MWD/MTU) 1.300 1.250 1.200 v 1.150 1.100 1.050 I I

t i.-tz.ii.zi -Vzz+/- II I

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 (2) 1.145 1.152 1.151 1.142 1.134 1.131 1.13 0 1.129 1.127 1.126 Axial Node 41 40 39 38 37 36 35 34 33 32 31 w (Z) 1.124 1.123 1.122 1.119 1.116 1.112 1.108 1.106 1.106 1.108 1.111 Axial Node 30 29 28 27 26 25 24 23 22 21 20 W(Z) 1.114 1.117 1.12 0 1.123 1.126 1.130 1.133 1.136 1.137 1.139 1.141 Axial Node 19 18 17 16 15 14 13 12 11 1 - 10 TOP W (Z) 1.142 1.145 1.151 1.158 1.167 1.175 1.181 1.186 1.191 15 Rev. 1

COLR for CPSES Unit 1 Cycle II FIGURE 7 W(Z) AS A FUNCTION OF CORE HEIGHT (20,000 MWD/MTU) 1.300 1.250 1.200 N D 1.150 1.100 1.050 1.000 If 1 11111 -K------ iiiihj. 0 1 2 3 4 5 6 7 8 9 10 I BOTTOM CORE HEIGHT (FEET) Axial Node 52 - 61 51 50 49 48 47 46 45 44 43 42 W(Z) 1.144 1.146 1.143 1.138 1.133 1.132 1.133 1.134 1.134 1.135 Axial Node 41 40 39 38 37 36 35 34 33 32 31 W (Z) 1.136 1.136 1.136 1.134 1.132 1.130 1.125 1.119 1.112 1.110 1.113 Axial Node 30 29 28 27 26

  • 25 24 23 22 21 20 W (Z) 1.119 1.125 1.131 1.13 5 1.13 9 1.143 1.14 6 1.148 1.149 1.150 1.149 Axial Node 19 18 17 16 15 14 13 12 11 1 -

10 11 12 TOP W(Z) 1.147 1.146 1.150 1.160 1.173 1.185 1.195 1.204 1.213 16 Rev. 1

COLR for CPSES Unit 1 Cycle 11 FIGURE 8 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 100 90 80 70 C4 3 0 aE H E4 9 UZ 0 Pi4 60 50 40 3 0 ( (1 690 l11 I I I I I I UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION -I--- I- -/-__________----A 4-h1-11 ACCEPTABLE ~- OPERATION I ILI (-28,50) (29,50) -3EH 1J*1 11+T-I I I I Ijr 111 1 20 10 A -40 -30 -20 -10 0 10 20 30 40 DEVIATION FROM TARGET AXIAL FLUX DIFFERENCE (%) 17 Rev. 1

a ERX-03-005, Revision I CPSES UNIT 2 CYCLE 8 CORE OPERATING LIMITS REPORT April 2004 Prepared: Reviewed: Reviewed: Daniel E. Brozak e Reactor Physics S. Srinilta Reactor Physics Hug8 C. DaSilva Safety Analysis Date: ___ ___5_/ Date: i/f / Ot5 4 Date: _//__/_ Approved: <X< M 4_:, -Date: 4 /S5/o Y Steplwn M. Maier Rea or Physics Supervisor Approved: X Date: /Co Safety I alysis Manager

i 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. ii3 April 15 2004

i COLR for CPSES Unit 2 Cycle 8 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 April 15 2004

COLR for CPSES Unit 2 Cycle 8 LIST OF TABLES TABLE 1 FQ (Z) MARGIN DECREASES IN EXCESS OF 2 % PER 31 EFPD.... PAGE 9 is April 15 2004

COLR for CPSES Unit 2 Cycle 8 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 A, April 15 2004

COLR for CPSES Unit 2 Cycle 8 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for CPSES UNIT 2 CYCLE 8 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 April 15, 2004

COLR for CPSES Unit 2 Cycle 8 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 and 9 through 19, as supplemented by Items 20 and 21. 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 K.ff < 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 April 15, 2004

COLR for CPSES Unit 2 Cycle 8 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 April 15, 2004

COLR for CPSES Unit 2 Cycle 8 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) F KTV 2.8.1 F0(Z) S [K(Z)J for P > 0.5 P F0s F0(Z) [K(Z)] for P < 0.5

0.5 where

P = THERMAL POWER RATED THERMAL POWER 4 April 15, 2004

COLR for CPSES Unit 2 Cycle 8 2.8.2 Fork = 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 Fa(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 Fo"(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!&mH_ (LCO 3.2.2) 2.9.1 F"&H < F"AH [1 + PFAH (I-P)J where: P 2 THERMAL POWER RATED THERMAL POWER 2.9.2 FETCAH = 1.55 2.9.3 PFAH = 0.3 5 April 15, 2004

COLR for CPSES Unit 2 Cycle 8 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 = 1.13 K2 = 0.0145 /0F K3 = 0.00075 /psig T.- = 560.5 0F pI 2235 psig T1 10 sec T. S 3 sec fI(Aq) = 0.00-{(q,-q,) + 65%) when (q,-qg) S -65% RTP = 0% when -65% RTP < (q,-q,) < +6.55% RTP = 2.27 {(qg-qg) 6.55%) when (q.-q,) 2 +6.55% RTP 6 April 15, 2004

COLR for CPSES Unit 2 Cycle 8 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 2 2220 psig (4 channels) 2 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 5 592 0F (4 channels) S 592 OF (3 channels) The RCS average temperature limits correspond to the analytical limit of 595.7 0F 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 April 15, 2004

COLR for CPSES Unit 2 Cycle 8 2.12.4 SR 3.4.1.3 The RCS total flow rate based on precision heat balance shall be 2 408,000 gpm 2.12.5 SR 3.4.1.4 The RCS total flow rate based on precision heat balance shall be 2 408,000 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 317,000 gpm. 2.13 BORON CONCENTRATION (LCO 3.9.1) 2.13.1 The required refueling boron concentration is 2044 ppm.

3.0 REFERENCES

Technical Specification 5.6.5. 8 April 15, 2004

COLR for CPSES Unit 2 Cycle 8 Table 1 F,(Z) MARGIN DECREASES IN EXCESS OF 2 % PER 31 EFPD Cycle Burnup (MWD/MTU) 2670 2880 3090 3300 3510 3730 3940 4150 4360 4570 6040 6250 6460 6670 6880 7090 7300 7510 7720 7930 8140 8350 8560 Maximum Decrease In F.(Z) Margin (Percent) 2.00 2.25 2.40 2.47 2.52 2.56 2.55 2.36 2.14 2.00 2.00 2.04 2.27 2.46 2.57 2.58 2.55 2.48 2.36 2.23 2.11 2.01 2.00 Note: All Cycle burnups outside the range of the table shall use a constant 2% decrease in F(Z) margin for compliance with the 3.2.1.2.a Surveillance Requirements. Linear interpolation is acceptable to determine the F,(Z) margin decrease for cycle burnups which fall between the specified burnups. 9 Rev. 1

COLR for CPSES Unit 2 Cycle 8 FIGURE 1 REACTOR CORE SAFETY LIMITS 680 670 Unacceptable Operation 660 650._l 60 P 2445 psig 630 0 620. 0 P =1985 psg A610.- 600 \\ Acceptable 590 Operation 580 570. 560. 550 V 0.0 20.0 40.0 60.0 80.0 100.0 116.4 Percent of Rated Thermal Power lo April 15, 2004

COLR for CPSES Unit 2 Cycle 8 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 240 220 200 3 180 si 160 .,l 3 A 140 a) CQl 120 za H H 100 C/I 0 M4 80 m g 60 0 I I I I I I I I I I I I _1 1 I L I I 1.1. I I I I I I I I I I I I I I I I H I I (25.3,218 9.6, 1 -1. H I -LB .-I A-L I JLl I I I I I I J.+/- I 1 A_ J-1-1-L I I 1. I till 164 till (100,146) BANK C I I I I I I I I I t i l l 1 1 1 1 I I I I I I I 1 x i t i l l_ I L H 44:FF - III J ILtill A - 1 1 1 . 1 1 i t I t i l l f i l l l i l l 1 1 1 1 1 1 t i l l 1 1 1 1 1 (0,49) -l 1 IfW 4U 20 0 .1.1.111, .11-1. I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I .1 I I I = I 11 11 - I I Ij TTIT_ I I till_ FT-FF i i 41 TI l IF ' I I I -z II I II 1 1 I I I I I I I I I I I I I I I I - I II Yj_ -IIAJ__ I I I I A-I.A.-L 1 -, (31,O) 1 1, l i f e t i l l t i l l 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 April 15, 2004

COLR for CPSES Unit 2 Cycle 8 FIGURE 3 K (Z) NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT N N H N 1.1 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 i i i1 i1i i i i i F T i I ~ I I i r 1 i 1 1 1 1 1 1 1 1i I I I I I(0.0,1.0) j--lj (6. 0,1.0) III T IIII m m 1 0. 9 T rr TTTT - I0 I I Ii m W1 1 XI I I I fR IIIr rr g1m1 .I

  • 1 0.0 0

1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM 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 12 April 15, 2004

COLR for CPSES Unit 2 Cycle 8 FIGURE 4 W(Z) AS A FUNCTION OF (MAXIMUM) CORE HEIGHT 1.300 1.250 1.200 1.150 H 1.100 1.050 1.000 If 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) 1.139 1.143 1.141 1.135 1.129 1.129 1.131 1.133 1.134 1.135 Axial Node 41 40 39 38 37 36 35 34 33 32 31 W (Z) 1.137 1.137 1.136 1.134 1.132 1.130 1.126 1.120 1.116 1.114 1.113 Axial Node 30 29 28 27 26 25 24 23 22 21 20 W (Z) 1.120 1.127 1.133 1.138 1.143 1.147 1.150 1.151 1.151 1.151 1.150 Axial Node 19 18 17 16 15 14 13 12 11 1 10 TOP W (Z) 1.149 1.152 1.156 1.160 1.170 1.180 1.189 1.197 1.205 13 April 15, 2004

COLR for CPSES Unit 2 Cycle 8 FIGURE 5 W(Z) AS A FUNCTION OF CORE HEIGHT (150 MWD/MTU) 1.300 1.250 1.200 N 6 1.150 H 1.100 1.050 1.000 *1*-- 4--- z 41-1=-- EJE EAEEE  -- 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) 1.120 1.112 1.108 1.107 1.108 1.110 1.112 1.113 1.114 1.116 Axial Node 41 40 39 38 37 36 35 34 33 32 31 W (Z) 1.118 1.119 1.116 1.111 1.109 1.112 1.116 1.117 1.116 1.114 1.113 Axial Node 30 29 28 27 26 25 24 23 22 21 20 W(Z) 1.114 1.118 1.122 1.127 1.132 1.135 1.138 1.140 1.141 1.143 1.144 Axial Node 19 18 17 16 15 14 13 12 11 1 - 10 W (Z) 1.148 1.152 1.156 1.160 1.164 1.168 1.171 1.175 1.178 14 April 15, 2004

COLR for CPSES Unit 2 Cycle 8 FIGURE 6 W(Z) AS A FUNCTION OF CORE HEIGHT (10,000 MWD/MTU) 1.300 1.250 1.200 N K 1.150 1.100 1.050 1.000 0 1 2 3 4 5 6 7 B 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) 1.139 1.143 1.141 1.135 1.129 1.127 1.126 1.125 1.125 1.124 Axial Node 41 40 39 38 37 36 35 34 33 32 31 W (Z) 1.124 1.123 1.122 1.119 1.115 1.111 1.108 1.106 1.105 1.106 1.109 Axial Node 30 29 28 27 26 25 24 23 22 21 20 W (Z) 1.112 1.116 1.119 1.123 1.128 1.132 1.135 1.138 1.139 1.140 1.142 Axial Node 19 18 17 16 15 14 13 12 11 1 10 W (Z) 1.143 1.146 1.151 1.158 1.166 1.173 1.180 1.185 1.191 1.5 April 15, 2004

COLR for CPSES Unit 2 Cycle 8 FIGURE 7 W(Z) AS A FUNCTION OF CORE HEIGHT (20,000 MWD/MTU) 1.300 1.250 1.200 N

3 1.150 H

1.100 1.050 1.000 t*-I~-- I Wt4 f 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) 1.134 1.136 1.135 1.131 1.129 1.129 1.131 1.133 1.134 1.135 Axial Node 41 40 39 38 37 36 35 34 33 32 31 W (Z) 1.137 1.137 1.136 1.134 1.132 1.130 1.126 1.120 1.113 1.110 1.113 Axial Node 30 29 28 27 26 25 24 23 22 21 20 W (Z) 1.120 1.127 1.133 1.138 1.143 1.147 1.150 1.151 1.151 1.151 1.150 Axial Node 19 18 17 16 15 14 13 12 11 1 - 10 TOP W (z) 1.149 1.148 1.151 1.160 1.170 1.180 1.189 1.197 1.205 16 April 15, 2004

COLR for CPSES Unit 2 Cycle 8 FIGURE 8 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 100 90 80 70 04 a

3i 0

p4 3.

1 P

60 50 40 30 iJi I iI 7T (-11115_9 UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION ACCEPTABLE OPERATION -26,50)1 IL4l (27,50 ) Xlzti~ < IX~F>Itt=1l 20 10 0 -40 -30 -20 -10 0 10 20 DEVIATION FROM TARGET AXIAL FLUX DIFFERENCE (%) 30 40 17 April 15, 2004}}

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