CPSES-200302202, Cycle 8 Core Operating Limits Report

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Cycle 8 Core Operating Limits Report
ML032950513
Person / Time
Site: Comanche Peak Luminant icon.png
Issue date: 10/14/2003
From: Blevins M, Walker R
TXU Electric
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CPSES-200302202, TXX-03181 ERX-03-005, Rev 0
Download: ML032950513 (24)
v • d • e


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{{#Wiki_filter:A TXU tow4,00 TXU Energy Comanche Peak Steam Electric Station P.O.Box 1002 (E01) Glen Rose,TX 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-200302202 Log # TXX-03181 October 14, 2003 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) DOCKET NO. 50-446 UNIT 2, CYCLE 8 CORE OPERATING LIMITS REPORT Gentlemen: Enclosed is the Core Operating Limits Report for Unit 2, Cycle 8 prepared and submitted pursuant to Technical Specification 5.6.5. A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

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

9 TXU TXX-03181 Page 2 of 2 This communication contains no new licensing basis commitments regarding CPSES Units I and 2. Sincerely, TXU Generation Company LP By: TXU Generation Management Company LLC, Its General Partner M. R. Blevins Senior Vice President and Principal Nuclear Officer By: e4 vaa Ro D. Walker Regulatory Affairs Manager JDS/js Enclosure c - B. S. Mallett, Region IV WV. D. Johnson, Region IV M. C. Thadani, NRR Resident Inspectors, CPSES

ERX-03-005, Revision 0 CPSES UNIT 2 CYCLE 8 CORE OPERATING LIMITS REPORT September 2003 Prepared-if, t Pr r Jnathan M. Ralston actor Physics Reviewed: Reviewed: Approved: Approved: ohn T. Bosma Reactor Physics Walter J. Boatwz'ght Safety Analysis Stephen M. Maier React r Physics Supervisor CtA. Whee G. Ch e Safety An ysis Manager Date: 7/Z Z03 -Date: - 03 Date: 9 3 Date: 7_-_3 -°3

  • Date:

30c}-3

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

i I. 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

COLR for CPSES Unit 2 Cycle 8 LIST OF TABLES TABLE 1 F.(Z) MARGIN DECREASES IN EXCESS OF 2 % PER 31 EFPD.... PAGE 9 iv

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 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

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 1

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

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

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 MODE 2 during PHYSICS TESTS. 2.8 HEAT FLUX HOT CHANNEL FACTOR (FAZ)) RT? F0 2.8.1 FQ (Z) [K(Z)J for P P or equal to 1.3% Ak/k in (LCO 3.2.1) > 0.5 FQ (Z) RTP F. 0.5 [K(Z)] for P < 0.5 where: P = THERMAL POWER RATED THERMAL POWER 4

COLR for CPSES Unit 2 Cycle 8 2.8.2 FQ = 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 [ F0c(Z) / K(Z) J, the burnup dependent values in Table 1 shall be used instead of a constant 2% to increase FQ"(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 A (LCO 3.2.2) 2.9.1 FNAH S F'T AH [1 + PFAH (1-P)J where: P = THERMAL POWER RATED THERMAL POWER 2.9.2 FTP AH = 1.55 2.9.3 PFAH = 0.3 5

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 P1 2235 psig Ti Ž 10 sec T2 3 sec fI(Aq) = 0.00-{(q,-q) + 65%) when (qt-q 1) < -65% RTP = 0% when -65% RTP c (q-qb) < +6.55% RTP = 2.27{(q-qb) 6.55%) when (q,-q) 2 +6.55% RTP 6

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 S 592 F (4 channels) 5 592 0F (3 channels) The RCS average temperature limits correspond to the analytical limit of 595.7 OF 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 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

COLR for CPSES Unit 2 Cycle 8 Table 1 F,(Z) MARGIN DECREASES IN EXCESS OF 2 % PER 31 EFPD Cycle Maximum Decrease Burnup In F,(Z) Margin (MWD/MTU) (Percent) 2640 2.00 2850 2.22 3050 2.60 3260 2.78 3470 2.76 3680 2.62 3880 2.42 4090 2.20 4300 2.00 4510 2.00 4710 2.07 4920 2.01 5130 2.00 5340 2.00 5540 2.04 5750 2.14 5960 2.26 6170 2.39 6370 2.50 6580 2.56 6790 2.59 7000 2.57 7200 2.51 7410 2.46 7620 2.38 7830 2.28 8030 2.20 8240 2.16 8450 2.07 8660 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 2 Cycle 8 FIGURE 1 REACTOR CORE SAFETY LIMITS 680 670 Unacceptable Operation 660 650 640 P 25s 630 -__ M 620 a) P -1845 psig 600 Acceptable 590 Operation 580. 570-560-550 0.0 20.0 40.0 60.0 80.0 100.0 116.4 Percent of Rated Thermal Power 10

COLR for CPSES Unit 2 Cycle 8 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 240 220 200 3 180 i 160 .,lBH U) o 140 .-J a) 120 0H E-4"- 100 (n 0 40 S4 80 ci 60 0 40 20 0 X X L ~~~(25.3,218) i _(79.6,218 X X E~t t mBANK B T (07 TTTTl,164T X T Y iL 1TT 0 j~~~~~~~ A-V I I It It I1XX T I I I 1 1 I2 71 fFTI4441 i~ 0 10 20 30 40 50 60 70 PERCENT OF RATED THERMAL POWER 80 90 100 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

a COLR for CPSES Unit 2 Cycle 8 FIGURE 3 K(Z) - NORMALIZED FQ (Z) AS A FUNCTION OF CORE HEIGHT 1.1 1.0 0.9 0.8 i3 a rL4 0.7 (0. 011.0) (6.011 0 t-- --t -- --I l-1 -I II I.I I.. 1 I....T~ I!I1 .1 0wm H 4 C4 0 z 0.6 0.5 I!.I I...;I...iIII, ,I. ,I ,IIiiiII I-.I-4-4-J. .-.-. 4. 4.-4--4-.. 4--4--4--4-~4-4.-44--+-I--4IIIII .......I . 1-l' I..., I.... 1--11-11. 1-0.4 0.3 0.2 . ' ' I 1 1 1T1I. 1. . 1.... .......... 1 1...... ....... I...... -.. I...........- 4- -4 -I--I .III lil'I I .1.. 1-1- 1.1.1'... .1-0.1 0.0 I.... 1111.11 -Tltifltili III III III II 11 11 11 III I11111 I1111 II III III III I 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 W 0.9250 0.9275

0. 93 00
0. 9325
0. 93 50 0.9375
0. 94 00
0. 9425 Axial Node 53 52 51 so 49 4 8 47 46 K (z) 0.9450 0.9475 0.9500 0.9525 0.9550
0. 9575 0.9 600
0. 9625 Axial Node 45 44 43 42 41 40 39 3 8 K (z) 0.9650 0.9675 0.9700 0.9725
0. 9750
0. 9775 0.9800 0.9825 Axial Node 37 3 6 35 3 4 3 3 32 1 -

31 K (z) 0.9850 0.9875 0.9900 0.9925 0.9950 0.9975

1. 0 00 0 12

COLR for CPSES Unit 2 Cycle 8 F FIGURE 4 W(Z) AS A FUNCTION OF (MAXIMUM) CORE HEIGHT 1.300 1.250 1.200 R

3 6

1.150 H-1.100 1.050 1.000 I I I I I I I I I T= 1 I I~~~~ I~~~ I z~~~z~ I = = = + ^ + e + +~~~~- =-- 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) 1.1339 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 W(Z) 1.149 1.152 1.156 1.160 1.170 1.180 1.189 1.197 1.205 13

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 R

3

£ 1.150 H X 1.100 1.050 1.000 I I I I I - f 1 1 I I -T I 1 1 I II I .~~~~~~ ..1. 1, T ____X====_I==V13-0 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 W (Z) 1.120 1.112 1.108 1.107 1.108 1.110 1.112 1.113 1.114 Axial Node 41 40 39 38 37 36 35 34 33 32 W(Z) 1.118 1.119 1.116 1.111 1.109 1.112 1.116 1.117 1.116 1.114 Axial Node 30 29 28 27 26 25 24 23 22 21 W (Z) 1.114 1.118 1.122 1.127 1.132 1.135 1.138 1.140 1.141 1.143 Axial Node 19 18 17 16 15 14 13 12 11 1 - 10 TOP W(Z) 1.148 1.152 1.156 1.160 1.164 1.168 1.171 1.175 1.178 42 1.116 31 1.113 20 1.144 14

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

3 1.150 H

1.100 1.050 1.000 WX~~~I tW I1 I I ~1II t II 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) 1.139 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 1.14 6 1.151 1.158 1.166 1.173 1.180 1.185 1.191 15

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 R 6 1.150 1.100 1.050 1.000 1Xt '* t 1 1A-3t At~~- X t-t _ I I 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 1.134 50 1.136 49 1.135 48 1.131 47 1.129 46 1.129 45 1.131 44 1.133 43 1.134 42 1.135 Axial Node W (Z) 41 1.137 40 1.137 39 1.136 38 1.134 37 1.132 36 1.130 35 1.126 34 1.120 33 1.113 32 1.110 31 1.113 Axial Node W(Z) 30 1.120 29 1.127 28 1.133 27 1.138 26 1.143 25 1.147 24 1.150 23 1.151 22 1.151 21 1.151 20 1.150 Axial Node W(Z) 19 1.149 18 1.148 17 1.151 16 1.160 15 1.170 14 1.180 13 1.189 12 1.197 11 1.205 1 - 10 16

COLR for CPSES Unit 2 Cycle 8 FIGURE 8 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 100 90 80 70 3 w

rW Ez 0

H z cwz p 60 50 40 30 UNACCEPTABLE 1 r I UNACCEPTABLE OPERATION OPERATION I t / ACCEPTABLE 11 ~OPERATION _65 1 I27I5 0I iE I :I:IA I I T I I IIII I I II IIII111 20 10 0 -40 -30 -20 -10 0 10 20 DEVIATION FROM TARGET AXIAL FLUX DIFFERENCE 30 40 (%) 17}}

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