CPSES-200602137, Submittal of Unit 2, Cycle 10 Core Operating Limits Report

Submittal of Unit 2, Cycle 10 Core Operating Limits Report

ML063050523
Person / Time
Site:	Comanche Peak
Issue date:	10/25/2006
From:	Madden F TXU Power
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CPSES-200602137
Download: ML063050523 (23)

Text

i QAý 7 TXU Power TXU Power Mike Blevins Comanche Peak Steam Senior Vice President &

Electric Station Chief Nuclear Officer P. 0. Box 1002 (EO1)

Glen Rose, TX 76043 Ref: Tech. Spec. 5.6.5 Tel: 254 897 5209 Fax: 254 897 6652 mike.blevins@lxu.com CPSES-200602137 Log # TXX-06176 October 25, 2006 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO.'50-446 SUBMITTAL OF UNIT 2, CYCLE 10 CORE OPERATING LIMITS REPORT

Dear Sir or Madam:

Enclosed is Revision 0 of the Core Operating Limits Reports for CPSES Unit 2, Cycle 10. 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.

/Ao/

A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

• Comanche Peak

• Diablo Canyon

• Palo Verde

• South Texas Project e Wolf Creek

TXX-06176 Page 2 of 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:

,4 re~1 W. Madden Director, Oversight and Regulatory Affairs RAS Enclosure c- B. S. Mallett, Region IV M. C. Thadani, NRR Resident Inspectors, CPSES

ERX-06-002, Rev. 0 CPSES UNIT 2 CYCLE 10 CORE OPERATING LIMITS REPORT October 2006 Prepared: ________________ Date: zoo__

Daniel H. Brozak Principal Engineer, Westinghouse Electric Co.

Reviewed: ________________ Date: ISio John T. Bosma Principal Engineer, Westinghouse Electric Co.

Reviewed:

Dave Principal Engineer, Westinghouse Electric Co.

Approved: Date: //so Ja *S BoatwrigoEe 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-06-002, Rev. 0

COLR for CPSES Unit 2 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 ERX-06-002, Rev. 0

COLR for CPSES Unit 2 Cycle 10 LIST OF TABLES TABLE PAGE No Tables Listed iv ERX-06-002, Rev. 0

COLR for CPSES Unit 2 Cycle 10 LIST OF FIGURES FIGURE PAGE 1 REACTOR CORE SAFETY LIMITS ............................... 9 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER ............. 10 3 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT ............................................. 11 4 W(Z) AS A FUNCTION OF CORE HEIGHT -

(MAXIMUM) ............................................... 12 5 W(Z) AS A FUNCTION OF CORE HEIGHT -

(150 MWD/MTU) ............................................ 13 6 W(Z) AS A FUNCTION OF CORE HEIGHT -

(10,000 MWD/MTU) ......................................... 14 7 W(Z) AS A FUNCTION OF CORE HEIGHT -

(20,000 MWD/MTU) ......................................... 15 8 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER ................................... 16 V ERX-06-002, Rev. 0

COLR for CPSES Unit 2 Cycle 10 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for CPSES UNIT 2 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 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-06-002, Rev. 0

COLR for CPSES Unit 2 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, Item 3 and Items 6 through 16. 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 Kof < 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-06-002, Rev. 0

COLR for CPSES Unit 2 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/°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-06-002, Rev. 0

COLR for CPSES Unit 2 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 CHANNEL FACTOR (F.(Z)) (LCO 3.2.1)

RTP FQ 2.8.1 FQ(Z) - [K(Z)] for P > 0.5 P

FRTP F0 FQ (Z) (K(Z)] for P < 0.5

0.5 where

P = THERMAL POWER RATED THERMAL POWER 4 ERX-06-002, Rev. 0

COLR for CPSES Unit 2 Cycle 10 RTP 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 FQ(Z) evaluations show an increase in the expression maximum over Z [ FJc(Z) / K(Z) I, F "(Z) shall be increased by a constant factor of 2% per Surveillance Requirement 3.2.1.2.a. This requirement is for all cycle burnups.

2.9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (FNAH) (LCO 3.2.2) 2.9.1 FNAH 5 FRTPH (1 + PFA (1-P)]

where: P = THERMAL POWER RATED THERMAL POWER T

2.9.2 FR PAH = 1.55 2.9.3 PFAH = 0.3 5 ERX-06-002, Rev. 0

COLR for CPSES Unit 2 Cycle 10 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, = 1.13 K2 = 0.0145 /-F K3 = 0.00075 /psig T°0 = 560.5 °F P1 a 2235 psig T, a 10 sec T=2 5 3 sec f 1 (Aq) = 0.00 * {(qý-q) + 65%} when (q,-q*) 5 -65% RTP

= 0% when -65% RTP < (qt-q,) < +8.5% RTP

= 2.27 {(qt-q,) - 8.5%} when (q,-q,) 2 +8.5% RTP 6 ERX-06-002, Rev. 0

COLR for CPSES Unit 2 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 Ž 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 S 592 °F (4 channels)

S 592 'F (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 ERX-06-002, Rev. 0

COLR for CPSES Unit 2 Cycle 10 2.12.4 SR 3.4.1.3 The RCS total flow rate shall be Ž 408,000 gpm.

2.12.5 SR 3.4.1.4 The RCS total flow rate based on precision heat balance shall be Ž 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 22063 ppm.

3.0 REFERENCES

Technical Specification 5.6.5.

8 ERX-06-002, Rev. 0

COLR for CPSES Unit 2 Cycle 10 FIGURE 1 REACTOR CORE SAFETY LIMITS 670 660 650 640 14 630 14 62 4) 14620 610 600 590 580 '

0.0 20.0 40.0 60.0 80.0 100.0 116.4 Percent of Rated Thermal Power 9 ERX-06-002, Rev. 0

COLR for CPSES Unit 2 Cycle 10 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 240

-- (25.3,218) - (9628**

220 200 BANK B ------

180

.r 160

--Il 2 1100,146)

• 140 BANK C* /

120 o

0 H -- - - - - - - - - - - - - - --

E-1 aC 100 0

04 - - - - - - - - BANK D 80 --- - - - - - - -+ " -

P0 60 - )-0 -- -------

40 I E [j 20 FFF~LI =--IF -J- -L 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.

10 ERX-06-002, Rev. 0

COLR for CPSES Unit 2 Cycle 10 FIGURE 3 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.1 (o0o0l.O) (6.01.0) 1.0 0.9 (12.0, .2 )

0.8 a0.7 N 0.6 o 0.5 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) 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 11 ERX-06-002, Rev. 0

COLR for CPSES Unit 2 Cycle 10 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 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 1.132 30 1.111 19 1.147 51 1.137 40 1.131 29 1.118 18 1.151 50 1.138 39 1.130 28 1.124 17 1 .155 49 1.136 38 1.128 27 1.130 16 1.160 48 1.130 37 1.125 26 1.136 15 1.169 47 1.128 36 1.122 25 1.140 14 1.181 46 1.129 35 1.117 24 1.143 13 1.191 45 1.131 34 1.111 23 1.144 12 1.200 44 1.132 33 1.105 22 1.145 11 1.209 43 1.132 32 1.103 21 1.146 1 - 10 42 1.132 31 1.106 20 1.145 Core Height (ft) = (Node - 1)

• 0.2 12 ERX-06-002, Rev. 0

COLR for CPSES Unit 2 Cycle 10 FIGURE 5 W(Z) AS A FUNCTION OF CORE HEIGHT (150 MWD/MTU) 1.300

} z~:

_ ~ ___ _

-:_4~

1.250 1.200 I~ -

j - - -

• 1.150 __ _ I_ - - - -

1.100 I~Z2~Th ~Z.IlL __ _-

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 1.113 30 1.107 19 1.147 51 1.116 40 1.111 29 1.111 18 1.151 50 1.111 39 1.110 28 1.115 17 1.155 49 1.108 38 1.107 27 1.119 16 1.160 48 1.107 37 1.104 26 1.124 15 1.165 47 1.107 36 1.101 25 1.129 14 1.169 46 1.108 35 1.098 24 1.133 13 1.173 45 1.110 34 1.098 23 1.137 12 1.176 44 1.111 33 1.100 22 1.140 11 1.178 43 1.112 32 1.103 21 1.142 1 - 10 42 1.113 31 1.105 20 1.144 Core Height (ft) = (Node - 1)

• 0.2 13 ERX-06-002, Rev. 0

COLR for CPSES Unit 2 Cycle 10 FIGURE 6 W(Z) AS A FUNCTION OF CORE HEIGHT (10,000 MWD/MTU) 1.300 1.250 1.200

" 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 1.122 30 1.103 19 1.139 51 1.137 40 1.120 29 1.107 18 1.142 50 1.138 39 1.118 28 1.111 17 1.148 49 1.136 38 1.116 27 1.116 16 1.155 48 1.130 37 1.112 26 1.122 15 1.162 47 1.126 36 1.107 25 1.127 14 1.169 46 1.125 35 1.103 24 1.130 13 1.174 45 1 .125 34 1.100 23 1.132 12 1.179 44 1 .125 33 1.098 22 1.133 11 1.183 43 1.124 32 1.098 21 1.135 1 - 10 42 1.123 31 1.100 20 1.136 Core Height (ft) = (Node - 1)

• 0.2 14 ERX-06-002, Rev. 0

COLR for CPSES Unit 2 Cycle 10 FIGURE 7 W(Z) AS A FUNCTION OF CORE HEIGHT (20,000 MWD/MTU) 1.300 1.250 1.200 D 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 1.132 30 1.111 19 1.143 51 1.134 40 1.131 29 1.118 18 1.142 50 1.134 39 1.130 28 1.124 17 1.146 49 1.132 38 1 .128 27 1.130 16 1.156 48 1.129 37 1.125 26 1.136 15 1.169 47 1.128 36 1.122 25 1.140 14 1.181 46 1.129 35 1.117 24 1.143 13 1.191 45 1.131 34 1.111 23 1.144 12 1.200 44 1.132 33 1.105 22 1.145 11 1.209 43 1.132 32 1.103 21 1.146 1 - 10 42 1.132 31 1.106 20 1.145 Core Height (ft) = (Node - 1)

• 0.2 15 ERX-06-002, Rev. 0

COLR for CPSES Unit 2 Cycle 10 FIGURE 8 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER

(-15. 90) (11,90) --- -

90 UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION 80 -- 7 zzz

-V.--7 ACCEPTABLE ---

NOPERATION 70 6o-- --------------------------

+-- ACPABE I~iI~i.

od *---J-j. -- ---

0 --- - - - - - - -- I- -

, (-27,50)--------------------. - - (25,50) 20 -- i - - --

-40 - 0 1 2 0 0I pd 30,i i i - ' -- - -I~--

-*50 -

--- ji -------. i z .

20,  :

i0,

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

16 ERX-06-002, Rev. 0