ML080710412
| ML080710412 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/03/2008 |
| From: | Morris J Duke Energy Carolinas, Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CNEI-0400-149, Rev 1 | |
| Download: ML080710412 (34) | |
Text
Duke JAMES R. MORRIS, VICE PRESIDENT Energ Duke Energy Carolinas, LLC Carolinas Catawba Nuclear Station / CN01 VP 4800 Concord Road York, SC 29745 803-831-4251 803-831-3221 fax March 3, 2008 U.S. Nuclear Regulatory Commission ATTENTION:
Document Control Desk Washington, D.C. 20555-0001
Subject:
Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC.
Catawba Nuclear Station Unit 2 Docket No.: 50-414 Core Operating Limits Report (COLR)
Catawba Unit 2 Cycle 16, Revision 1 Attached, pursuant to Catawba Technical Specification 5.6.5, is an information copy of revision 1 of the Core Operating Limits Report for Catawba Unit 2 Cycle 16.
This letter and attached COLR do not contain any new commitments.
Please direct any questions or concerns to Marc Sawicki at (803) 831-5191.
Sincerely, James R. Morris Attachments 4orADD www. duke-energy. corn
U.
S.
Nuclear Regulatory Commission March 3, 2008 Page 2 xc:
(w/att)
Victor M. McCree (Acting),
Region II Administrator U.S. Nuclear Regulatory Commission Sam Nunn Atlanta Federal Center, 23 T85 61 Forsyth St.,
SW Atlanta, GA 30303-8931 J.
F.
Stang, Jr., Senior Project Manager (CNS & MNS)
U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 8 G9A Rockville, MD 20852-2738 A.
T. Sabisch Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station
I; CNEI-0400-149 Page 1 of 32 Revision 1 Catawba Unit 2 Cycle 16 Core Operating Limits Report Revision 1 February 2008 Duke Power Company Date Prepared By:
Checked By:
Checked By:
Approved By:
1~4 a/2I aozL?
g:42 Lev a I QA Condition 1 The information presented in this report has been prepared and issued in accordance with Catawba Technical Specification 5.6.5.
. I I,
CNEI-0400-149 Page 2 of 32 Revision 1 INSPECTION OF ENGINEERING INSTRUCTIONS keA~
Inspection Waived By:
Date:
2"za" cj (Sponsor) 0I CATAWBA Inspection Waived MCE (Mechanical& Civil) le-Inspected By/Date:
RES (Electrical Only)
L Inspected By/Date:
RES (Reactor)
L&.
Inspected By/Date:
MOD P"'
Inspected By/Date:
Other (
)
I]
Inspected By/Date:
OCONEE Inspection Waived MCE (Mechanical & Civil) 0 Inspected By/Date:
RES (Electrical Only).
0 Inspected By/Date:
RES (Reactor) 0 Inspected By/Date:
MOD U
Inspected By/Date:
Other ( _)
U Inspected By/Date:
MCGUIRE Inspection Waived MCE (Mechanical & Civil) 0 Inspected By/Date:
RES (Electrical Only)
Inspected By/Date:
RES (Reactor) 0 Inspected By/Date:
MOD 2
Inspected By/Date:
Other( _-
Inspected By/Date:
1<
CNEI-0400-149 Page 3 of 32 Revision 1 Catawba 2 Cycle 16 Core Operating Limits Report Implementation Instructions for Revision 1 Revision Description and PIP Tracking Revision I of the Catawba Unit 2 Cycle 16 COLR contains limits-specific to the reload core and was revised to include limits specific for completion of the RCCA movement test prior to 2/27/2008. Revision 1 was initiated by PIP #C-08-00765.
Implementation Schedule Revision 1 maybecome effective immediately but must become effective prior to 2/27/2008.
TheCatawba Unit 2 Cycle 16 COLR will cease to. be effective during No MODE between Cycle 16 and 17.
Data files to be Implemented No data files are transmitted as part of this document.
V.
CNEI-0400-149 Page 4 of 32 Revision I Catawba 2 Cycle 16 Core Operating Limits Report REVISION LOG Revision 0
1 Effective Date September 2007 February 2008.
COLR C2C16 COLR rev. 0 C2C16 COLR rev. 1 Insertion/Deletion Instructions Remove Insert pages 1-32, of rev 0 pages 1-32 of rev 1
CNEI-0400-149 Page 5 of 32 Revision 1 Catawba 2 Cycle 16.Core Operating Limits Report 1.0 Core Operating Limits Report This Core Operating Limits Report (COLR) has been prepared in accordance with the requirements of Technical Specification 5.6.5. The Technical Specifications that reference this report are listed below:
TS COLR COLR Section Technical Specifications j
CQLR Parameter Section.
Page 2.1.1 Reactor Core Safety Limits I RCS Temperature and Pressure 2.1 9
ISafety Limits 3.1.1 Shutdown Margin Shutdown Margin 2.2 9
3.1.3.
Moderator Temperature Coefficient MTC
""2.3 11 3.1.4 1 Rod Group Alignment Limits Shutdown Margin 2.2 9
3.1.5 Shutdown Bank Insertion Limit Shutdown Margin 2.2 Rod Insertion Limits.
2.4 11
.3.1.6 Control Bank Insertion Limit Shutdown Margin 2.2 9
_____Rod Insertion Limits 2.5_
15 3.1.8.
i PhysicsTestsExceptions..
Shutdown Margin 2.2 9
3.2.1 Heat Flux Hot ChannelFactor
- 26.
15 AFD 2.8 21 OTAT
.2.9 24 Penalty Factors 2.6 15 3.2.2 Nuclear Enthalpy Rise Hot Channel FAH 2.7 20 Factor
_Penalty Factors 1
2.7 20 3.2.3 Axial Flux Difference AFD 2.8 21 3.3.1 Reactor Trip System Instrumentation 1: OTAT 2.9 24 iOPAT 2.9 24
-3.3.9-Boron Dilution Mitigation System Reactor Makeup Water Flow Rate 2.10 26 3.4.1 RCS Pressure, Temperature and Flow RCS Pressure, Temperature and 2.11 26
- limits.for DNB
.Flow 3.5.1 Accumulators Max and Min Boron Cone.
2.12 26 3.5.4 Refueling Water Storage Tank Max and Min Boron. Conc.
2.13 26.
-3.715.
Spent Fuel Pool Boron Concentration Mi-n-Boron Concentration 2.14
.i 28 3.9.1 Refueling Operations - Boron i Mm Boron Concentration 2.15 28 Concentration
__i 5.6.5 iCore Operating Limits Report Analytical Methods i.1 6
(COLR)
The Selected License Commitments that reference"this report are listed below:
-COLR Parameter Section Page 16.7-9.3 Standby Shutdown System Standby Makeup Pump Water 2.16 29 S........
Supply 16.9-11 Boration Systems - Borated Water
. Borated.Water Volume and Conc.
2.17 29 i Source - Shutdown.
for BAT/RWST 16.9-12, Boration Systems - Borated Water I Borated Water Volume and Conc.
2.18 30
_ Source - Operating for BAT/RWST
CNEI-0400-149 Page 6 of 32 Revision I Catawba 2 Cycle 16 Core Operating Limits Report 1.1 Analytical Methods The analytical methods used to determine core operating limits for parameters identified in Technical Specifications and previously reviewed and approved by the NRC are as follows.
- 1. WCAP79272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," (W-Proprietary).
Revision 0 Report Date: July 1985 Not Used for C2C16
- 2. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code, "(W Proprietary).
Revision 0 Report Date: August 1985
- 3.
WCAP-10266-P-A, "THE 198.1 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE", (W Proprietary).
Revision 2 Report Date: March 1987 Not Used for C2C16
- 4.
WCAP-12945-P-A, Volume 1 and Volumes 2-5, "Code Qualification Document for Best-Estimate Loss of Coolant Analysis,'" (W. Proprietary).
Revision: Volume I (Revision 2) and Volumes 2-5 (Revision 1)
ReportDate: March 1998
- 5.
BAW-10168P-A, "B&W Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants," (B&W Proprietary).
Revision 1 SER Date: January 22, 1991 Revision 2 SER Dates: August 22, 1996 and November 26, 1996.
Revision 3 SER Date: June 15, 1994.
Not Used for C2C16
CNEI-0400-149 Page 7 of 32 Revision I Catawba 2 Cycle 16 Core Operating Limits Report 1.1 Analytical Methods (continued)
Revision 3 SER Date:. September 24, 2003
- 7.
DPC-NE-3001PA, "Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," (DPC Proprietary).
Revision 0 Report Date: November 15, 1991, republished December 2000
- 8.
DPC-NE-3002A, "UFSAR Chapter 15 System Transient Analysis Methodology".
Revision 4 SER Date: April 6, 2001
- 9. DPC-NE-2004P-A, 1"Duke Power Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-01," (DPC Proprietary).
Revision 1 SER Date: February 20, 1997
- 10. DPC-NE-2005P-A, "Thermal Hydraulic Statistical Core Design Methodology," (DPC Proprietary).
Revision 3 SER Date: September 16, 2002
- 11. DPC-NE-2008P-A, "Fuel Mechanical Reload Analysis Methodology Using TACO3," (DPC Proprietary).
Revision 0 SER Date: April 3, 1995 Not Used for. C2C16.
- 12. DPC-NE-2009-P-A, "Westinghouse Fuel Transition Report," (DPC Proprietary).
Revision 2 SER Date: December 18, 2002
- 13. DPC-NIE-1004A, "Nuclear Design Methodology Using CASMO-3/SIMULATE-3P.".
Revision I SER Date: April 26, 1996 Not Used for C2C16
CNEI-0400-149 Page 8 of 32 Revision I Catawba 2 Cycle 16 Core Operating Limits Report 1.1 Analytical Methods (continued)
- 14. DPC-NF-2010A, "Duke Power Company McGuire Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design."
Revision 2 SER Date: June 24, 2003
- 15. DPC-NE-201 IPA, "Duke Power Company NuclearDesign Methodology for Core Operating Limits of Westinghouse Reactors;" (DPC Proprietary).
Revision 1..
SER Date: October 1, 2002.
- 16. DPC-NE-1005-P-A, "Nuclear Design Methodology Using CASMO-4 / SIMULATE-3 MOX", (DPC Proprietary).
Revision 0 SER Date: August 20; 2004
Revision 1 SER Date: January 14, 2004 Not Used for C2C16
CNEI-0400-149 Page 9 of 32 Revision 1 Catawba 2 Cycle 16 Core Operating Limits Report 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 NRC approved methodologies specified in Section 1.1.
2.1 Reactor Core Safety Limits (TS 2.1.1)
The Reactor Core Safety Limits are shown in Figure 1.
2.2 Shutdown Margin - SDM (TS 3.1.1, TS 3.1.4, TS 3.1.5, TS 3.1.6, TS 3.1.8) 2.2.1 For TS 3.1.1, shutdown margin shall be greater than or equal to 1.3% AK/K in mode 2with Keff < 1.0 and in modes 3 and4.
2.2.2 For TS 3.1.1, shutdown margin shall be greater than or equal to 1.0% AK/K in mode 5.
2.2.3 For TS 3.1.4, shutdown margin shall be greater than or equal to 1.3% AK/K in mode I and mode 2.
2.2.4 For TS 3.1.5, shutdown margin shall be greater than or equal to 1.3% AK/K in mode 1 and mode 2 with any control bank not fully inserted.
2.2.5 For TS 3.1.6, shutdown.margin shall be greater than or equal to 1.3% AK/K in mode I and mode 2 with Keff > 1.0.
2.2.6*
For TS 3.1.8, shutdown margin shall be greater than or equal to 1.3% AK/K in mode 2 during Physics Testing.
CNEI-0400-149 Page 10 of 32 Revision I Catawba.2 Cycle 16 Core Operating Limits Report Figure 1 Reactor Core Safety Limits Four Loops in Operation 670 DO NOT OPERATE IN THIS AREA 660 650 6000 630 02280 psia (9 620 610 600 590 ACCEPTABLE OPERATION 580 I
0.0 0.2 0.4 0.6 0.8 1.0.
1.2 Fraction of Rated Thermal Power '
CNEI-0400-149 Page II of 32 Revision 1 Catawba 2 Cycle 16 Core Operating Limits Report 2.3 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) Limits are:
The MTC shall be less positive than the upper limits shown in Figure 2. The BOC, ARO, HZP MTC shall be less positive than 0.7E-04 AK/K/°F.
The EOC, ARO, RTP MTC shall be less negative than the -4.3E-04 AK/K/IF lower MTC limit.
2.3.2 The 300 ppm MTC Surveillance Limit is:
The measured 300 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to -3.65E-04 AK/K/°F.
2.3.3 The 60 PPM MTC Surveillance Limit is:
The 60 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to
-4.125E-04 AK/KI0F.
Where:
BOC = Beginning of Cycle (bumup corresponding to most positive MTC)
EOC = End of Cycle ARO = All Rods Out HZP = Hot Zero Thermal Power RTP = Rated Thermal Power PPM - Parts per million (Boron) 2.4 Shutdown Bank Insertion Limit (TS 3.1.5) 2.4.1 Each shutdown bank shall be withdrawn to at least 222 steps except under the special conditions listed-below. Shutdown banks are withdrawn in sequence and with no overlap.
Special conditions Shutdown Banks C, D, and E can be inserted to 212 steps withdrawn individually with the following restrictions.
The cycle average burnup must be between 100.5 and 102.5 EFPD Steady state operation near 100%FP prior to entering special conditions
CNEI-0400-149 Page 12 of 32 Revision I Catawba 2 Cycle 16 Core Operating Limits Report Figure 2 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 W
W Z
W Q.*
0.9 -
0.8 -
0.7 0.6 -
Unacceptable Operation 0
C?
0.5 --
0.4 -
0.3 0.2-0.1 Acceptable Operation 0.0 I
I 0
10 20 30 40 50 60 70 80 90 100 Percent.of Rated Thermal Power NOTE: Compliance with Technical Specification 3.1.3 may require rod withdrawal limits.
Refer to the Unit 2 ROD manual for details.
CNEI-0400-149 Page 13 of 32 Revision 1 Catawba 2 Cycle 16 Core Operating Limits Report Figure 3 Control Bank Insertion Limits Versus Percent Rated Thermal Power Fully Withdrawn (Maximum = 231)
(29.6%, 231)
(80.0%, 231) 231 220 200 180 160 140.
"* 120 100
.2 80 60 40
'Fully Withdrawn.
(Minimum =222)'
Control Bank B (0%, 163)(10,6)-
Control Bank C Control Bank D (0%, 47)
(300, 0)
(30%, 0) 20 0
0 10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power The Rod Insertion Limits (RIL) for Control Bank D (CD), Control Bank C (CC), and Control Bank B (CB) can becalculated by:
Bank CD RIL= 2.3(P)-69 {30< P51O0}0.
Bank CC RIL 2.3(P)+ 47 {0:< P* 80}
Bank CB RIL =2.3(P)+ 163.{0 < P* 29.6}
where P = %Rated Thermal Power NOTE: Compliance with Technical Specification 3.1.3 may require rod withdrawal limits.
Refer to the Unit 2 ROD manual for details.
Anytime the shutdown banks are inserted below 222 steps withdrawn control bank D insertion is limited to 200 steps withdrawn (see Section 2.4.1 special conditions)
CNEI-0400-149 Page 14 of 32 Revision I Catawba 2 Cycle 16 Core Operating Limits Report Table 1 Control Bank Withdrawal Steps and Sequence Fully Withdrawn at 222 Steps Control Control Control Control Bank A Bank B Bank C Bank D 0 Start 0
0 0
116 0 Start 0
0 222 Stop 106 0
0 222 116 0 Start 0
222 222 Stop 106 0
222 222 116
.0 Start 222 222 222 Stop 106 Fully Withdrawn at 224 Steps Control Control Control Control
- BankA, BankB BankC BanklD Fully Withdrawn at 223 Steps Control Control' Control Control Bank A Bank B Bank C Bank D 0 Start 0
0 0
116 0 Start 0
0 223 Stop
' 07 0
0 223 116 0 Start 0
223 223 Stop 107 0
- 223 223 116 0 Start 223 223 223 Stop 107 Fully Withdrawn at 225 Steps Control Control Control Control Bank A Bank B Bank C Bank D, 0 Start 0
0 0
- 116, 0 Start 0
0 225 Stop' 109 0
0 225 116 0 Start 0
225 225 Stop 109 0
225 225 116 0 Start 225 225 225 Stop 109 Fully Withdrawn at 227 Steps Control Control Control Control Bank A Bank B.
Bank C Bank D 0 Start.
0 0
0 116 0 Start 0
0 224 Stop 108.
0 0
224 116
-0 Start 0
224 224 Stop 108 0
.. 224 224
" 1.16 0 Start 224 224 224 Stop.
108 Fully Withdrawn at 226 Steps Control Control. Control Control Bank A Bank B Bank C Bank D 0 Start 0
0 0
116 0Start 0.*
0 226 Stop 110 0
0 226 116 0 Start 0
226 226 Stop 110 0
226 226 116 0 Start 226 226 226 Stop 110 Fully Withdrawn at 228 Steps Control Control Control Control Bank A Bank'B Bank C Bank D 0 Start 0
0 0
116 0 Start 0
0 228 Stop 112'.
0 01 228 116.
Start 0
228 228 Stop 112
- 0 228 228 116.
0 Start 228 228
. 228 Stop 112 0 Start 0
0 0
116 0 Start 0
0 227 Stop 111 '
0 0
227 116 0 Start 0
227 2 2 7 Stop 111 0
227 227 116 0 Start 227
.227 227 Stop IlI Fully Withdrawn at229 Steps Control Control Control Control BankAX Bank B Bank C Bank D 0 Start 0
"0 0
116 0 Start 0
0 229 Stop 113.
0 0
229 116' 0 Start 0
229 229 Stop 113 0
229 229 116 0 Start 229 229 229 Stop, 113 Fully Withdrawn at 230 Steps Control
- Control Control Control Bank A Bank B Bank C Bank D 0 Start 0
0 0
116 0 Start 0'
0 230 Stop 114 0
0 230 116 0 Start 0
230 230 Stop 114 0
230 230 116
,O Start 230 230 230 Stop 114 Fully Withdrawn at 231 Steps Control Control Control Control Bank A Bank B Bank C Bank D 0 Start 0
0 0
116 0 Start 0
0 231 Stop 115 0
0 231 116 0 Start 0
231' 231 Stop 115 0
231 231 116 0 Start 231 231,
231 Stop 1.15,
. 11 CNEI-0400-149 Page 15 of 32 Revision I Catawba 2 Cycle 16 Core Operating Limits Report 2.5 Control Bank Insertion Limits (TS 3.1.6) 2.5.1 Control banks shall be within the insertion, sequence, and overlap limits shown in Figure 3. Specific control bank withdrawal and overlap limits as a function of the fully withdrawn position are shown in Table 1.
2.6 Heat Flux Hot Channel Factor - FQ(X,Y,Z) (TS 3.2.1) 2.6.1 FQ(X,YZ) steady-state limits are defined by the following relationships:
F rP*K(Z)/P.
for P > 0.5 F RTP *K(Z)/0.5 for P < 0.5
- where, P = (Thermal Power)/(Rated Power)
Note: The measured FQ(X,Y,Z). shall be increased by 3%.to account for manufacturing tolerances and 5% to account for measurement uncertainty when comparing against the LCO limits. The manufacturing tolerance and measurement uncertainty are implicitly included in the FQ surveillance limits as defined in COLR Sections 2.6.5 and 2.6.6.
2.6.2 F R 2.60 x K(BU)
-Q 2.6.3 K(Z) is the normalized FQ(X,Y,Z) as a function of core height.
K(Z) for Westinghouse RFA fuel is provided in Figure 4.
2.6.4 K(BU) is the normalized FQ(X,Y,Z) as a function of burnup. K(BU) for Westinghouse RFA fuel is 1.0 at all burnups.
The following parameters are required for core monitoring per the Surveillance Requirements of Technical Specification 3.2.1:
FQ(X,Y,Z)
MQ(X,Y,Z) 2.6.5
[FQ(X,Y,Z)]OP UMT
- TILT where:
[Q.(X,Y,Z)]°P Cycle dependent maximum allowable design peaking factor that ensures that the FQ(X,Y,Z) LOCA limitis not exceeded for operation within.the.AFD, RIL, and QPTR limits.
CNEI-0400-149 Page 16 of 32 Revision I Catawba 2 Cycle 16 Core Operating Limits Report F
OP QF (X,Y,Z)] includes allowances for calculational and measuremenV uncertainties.
F(,YZ
=
M(X,Y,Z)
=
Design power distribution for FQ. FQD.(X,Y,Z) is provided in Appendix Table A-I for normal operating conditions and in
.Appendix Table A-4 for power escalation testing during initial startup operation.
Margin remaining in core location X,Y,Z to the LOCA limit in the transient power distribution. MQ(X,Y,Z) is. provided in..
Appendix Table A-I for normal operating conditions and in
.Appendix Table A-4 for power escalation testing during..initial startup operation.
UMT =
Total Peak Measurement Uncertainty. (UMT = 1.05)
MT "
Engineering Hot Channel Factor. (MT = 1.03)
TILT Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02. (TILT = 1.035) 2.6.6
[FPQ(X,Y,Z)I RS =
FIQ (X,YZ)
- Mc(X,Y,Z)
UMT
- TILT where:
[-Fý(X,Y,Z)]RPS Cycle dependent maximum allowable design peaking factor that ensures that the FQ(X,Yz) Centerline Fuel Melt (CFM) limit is not exceeded for operation within the.AFD, RIL, and QPTR limits. [F6(X,Y,Z)]RPS1includes allowances for calculational and measurement uncertainties.
Design power distributions for-FQ. FQ(XY,Z) is provided in Appendix Table A-1 for normal operating conditions and in Appendix Table A-4 for power escalation testing during initial startup operations.
FQ(X,Y,Z)=
Mc(X,Y,Z) =
Margin remaining to the CFM limit in core location X,Y,Z from the transient power distribution. Mc(X,Y,Z) is provided in Appendix Table A-2 for normal operating conditions and in Appendix Table A-5 for power escalation testing during initial startup operations.
CNEI-0400- 149 Page 17 of 32 Revision I Catawba 2 Cycle 16 Core Operating Limits Report UMT Measurement Uncertainty (UMT = 1.05)
MT Engineering Hot Channel Factor (MT = 1.03)
TILT Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02. (TILT = 1.035) 2.6.7 KSLOPE = 0.0725 where:
KSLOPE = the adjustment to the K1 value from OTAT trip setpoint required to k
L RPS compensate for each 1%. that Ff (X,Y,Z) exceeds [F Q (X,Y,Z)J 2.6.8 FQ(X,Y,Z) Penalty Factors. for Technical Specification Surveillances 3.2.1.2 and 3.2.1.3 are provided in Table 2.
CNEI-0400-149 Page 18 of 32 Revision I Catawba 2 Cycle 16 Core Operating Limits Report Figure 4 K(Z), Normalized FQ(X,Y,Z) as a Function of Core Height for RFA Fuel 1.200 1.000 0.800 No.6oo0 0.400 (0.0, 1.00)
.(4.0, 1.00)
(12.0, 0.9615)
(4.0, 0.9615)
Core Height (ft)
K(Z)
.0.0 1.0000
< 4.0 1.0000
> 4.0.
0.9615 12.0 0-9615 0.200 -
0.000 0.0 2.0 4.0 6.0 Core Height (ft) 8.0 10.0 12.0
CNEI-0400-149 Page 19 of 32 Revision I Catawba 2 Cycle 16 Core Operating Limits Report Table 2
-FQ(X,Y,Z) and FtH(X,Y) Penalty Factors For Tech Spec Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2 Burnup (EFPD) 4 12 25 50 75 100 125.
150 175 200 225 250 275 300 325 350 375 400 425 447 456 471 486 FQ(X,Y,Z)
Penalty Factor(%)
2.00 2.00 2.00 2.00 2.00 2.00 2.10 2.00 2.00 2.00
-9 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 FAH(X,Y)
Penalty Factor (%)
2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 Note: Linear interpolation is adequate for intermediate cycle bumups.
All cycle burnups outside therange of thetable shall use a 2%
-penalty factor for both FQ(X,Y,Z) and FAH(X,Y) for compliance with the Tech Spec Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2.
CNEI-0400- 149 Page 20 of 32 Revision 1 Catawba 2 Cycle 16 Core Operating Limits Report 2.7 Nuclear Enthalpy Rise Hot Channel Factor - FAH(X,Y) (TS 3.2.2)
The FAH steady-state limits referred to in Technical Specification 3.2.2 are defined by the following relationship.
2.7.1
[FkH (X,y)]LCO= MARP (X,Y)*
1.0+ RR (1.0 - P where:
[FkL (X, y)]LCO is defined as the steady-state, maximum allowed radial peak and includes allowances for calculation/measurement uncertainty.
MARP(X,Y) =
Cycle-specific operating limit Maximum Allowable Radial Peaks.: MARP(X,Y) radial peaking limits are provided in Table 3.
=
Thermal Power Rated Thermal Power RRH =Thermal Power reduction required-to compensate for each 1% that the measured radial peak, FL (X,Y), exceeds the limit.
(RRH =3.34, 0.0 < P < 1.0)
The following parameters are required for core monitoring per the Surveillance requirements of Technical Specification 3.2.2.
SSURV FL (X, Y)
- Ma,, (X, Y) 2.7.2
[F6Ll (X,Y)]
=
T UMR
- TILT where:
I SURV
[FL (X,Y) I Cycle dependent maximum allowable design peaking factor that ensures that the FAH(X,Y) limit is not exceeded for operation within the AFD, RIL, and QPTR limits.
FL [ (X,y)SU'v includes allowances for calculational and FA r (X,Y)=
measurement uncertainty.
D ""
Design power distribution for FAH" FAH (X,Y) is provided in Appendix Table A-3 for normal operation and in Appendix Table A-6 for power escalation testing during initial startup operation.
CNEI-0400-149 Page 21 of 32 Revision 1 Catawba 2 Cycle 16 Core Operating Limits Report MAH(XY) =Themargin remaining in core location X,Y relative to the Operational DNB limits in the transient power distribution.
MAH(X,Y) is provided in Appendix Table A-3 for normal operation and in Appendix Table A-6 for power escalation testing during initial startup operation.
UMR Uncertainty value for measured radial peaks. UMIR.is set to 1.0 since a factor of 1.04 is implicitly included. in the variable MAH(XY).
TILT =Peaking penalty that accounts for allowable quadrant power
- tilt ratio of 1.02. (TILT= 1.035) 2.7.3 RRH = 3.34 where:
RRH Thermal Power reduction required to compensate for each 1% that the measured radial peak, FA (X,Y) exceeds its limit. (0 < P < 1.0) 2.7.4 TRH = 0.04 where:
TRH=
Reduction in OTAT K1 setpoint required to compensate for each 1% that the measured radial peak, FAH(X,Y) exceeds its limit.
2.7.5 F&H(X,Y) Penalty Factors for Technical Specification Surveillance 3.2.2.2 are provided in Table 2.
2.8 Axial Flux Difference - AFD (TS 3.2.3) 2.8.1 The Axial Flux Difference (AFD).Limits are provided in Figure 5.
CNEI-0400-149 Page 22 of 32 Revision 1 Catawba 2 Cycle 16 Core Operating Limits Report Table 3 Maximum Allowable Radial Peaks (MARPS)
RFA Fuel MARPs 100% Full Power Axial Peak Core Height (ft) 1.05 1.1 1.2 1.3 1.4 1.5
- 1.6 1.7 1.8 1.9 2.1.
3.0 3.25 0.12 1.20 2.4C 3.6C 4.8C 6.00 7.2C 8.4C 9.6C 10.8C 11.40 1.8092 1.8553 1.9489 1.9953:
1.8102
- 1.854 1.9401
.1.9953 1.8093 1.8525 1.9312 1.9779 1.8098 1.8514 1.9204 1.9641 1.8097 1.8514 1.9058 1.9449 1.8097 1.8514
.1:8921 1.9212 1.807 1.8438 1,8716 1.893 1.8073 1.8319 1.8452" 1.8571 1.8072 1.8102 1.8093 1.7913 1.798 1.7868 1.7611 1.7163 1.7892 1.7652 1.725 1.6645 1.9741 1.9741 1.9741 1.9741 1.9741
.1.9455 1.8872 1.8156 1.7375
- 1. 6538 1.6057 2.1073
.2.1073 2.0735 2.0495 2.0059 1.9336 1.8723 1.795 1.71.82 1.6315 1.5826 2.0498 2.009 1.9333 1.8625 1L778 2.0191 1.9775 1.9009 1.8306 1.7852 1.9953.
1.9519 1.876 1.8054 1.732 1.9656 1.9258' 1.8524 1.7855 1.6996 1.9441 1.9233 1.8538 1.7836 1.6714 1.8798 1.8625.
1.8024 1.7472 1.6705 1.8094
-1.7866 1.7332 1.6812 1.5982 1.7359 1.7089 1.6544
.1.601 1.5127 1.6572 1.6347 1.5808 1.5301 1.4444 1.5743 1.5573 1.5088 1.4624 1.3832 1.5289 1.5098 "1.4637 1.4218 1.3458 1.3151 1.2461 1.3007 1.2235 1,4633 1.4616 1.4675 1.3874 1.2987 1.2579 1.3293 1.2602 1.2871 1.2195 1.2182 1.1578 1.1431 1.0914 1.1009
.1.047 1.067- "1.0142
CNEI-0400-149 Page 23 of 32 Revision 1 Catawba 2 Cycle 16 Core Operating Limits Report Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits 0
.0
-t=
F-
-50
-40
-30
-20
-10 0
10 20 30 40 50 Axial Flux Difference (% Delta I)
NOTE: Compliance with Technical Specification 3.2.1 may require more restrictive AFD limits. Refer to the Unit 2 ROD manual for operational AFD limits.
CNEI-0400-149 Page 24 of 32 Revision 1 Catawba 2 Cycle 16 Core Operating Limits Report 2.9 Reactor Trip System Instrumentation Setpoints (TS 3.3.1) Table 3.3.1-1 2.9.1 Overtemperature AT Setpoint Parameter Values Parameter Nominal Value Nominal Tavg at RTP Nominal RCS Operating Pressure Overtemperature AT reactor trip setpoint Overtemperature AT reactor trip heatup setpoint penalty coefficient Overtemperature AT reactor trip depressurization setpoint penalty coefficient Time constants utilized in the. lead-lag compensator for AT Time constant utilized in the lag compensator for AT Time constants utilized in the. lead-lag compensator for-Tavg Time constant utilized in the measured Tavg lag compensator f(AI) "positive" breakpoint fl(AI). "negative" breakpoint fl(AI) "positive' slope fl(AI) '.'negative" slope T'< 590.8 OF P' = 2235 psig KI = 1.1953 K2 = 0.03163/°F' K3 = 0.001414/psi T1 = 8 sec.
T2 = 3 sec.
T3 = 0 sec.
'4 = 22 sec.
'C5 = 4 sec.
'6 =0 sec.
- 3.0 %AI
=N/A
- L525 %AT0/ %AI
=N/A*
The fl(AI) negative breakpoints and slopes for OTATare less restrictive than the OPAT f2(AI) negative breakpoint and slope. Therefore, during a transient which challenges the negative imbalance limits the OPAT f2(AI).limits will result in a reactor trip before the OTAT fl(AI) limits are reached.. This makes implementation of an OTAT fl(AI) negative breakpoint and slope unnecessary.
CNEI-0400-149 Page 25 of 32 Revisionl1 Catawba 2 Cycle 16 Core Operating Limits Report 2.9.2 Overpower AT Setpoint Parameter Values Parameter Nominal Tavg at RTP Overpower AT reactor trip setpoint Overpower AT reactor trip penalty Overpower AT reactor trip heatup setpoint penalty coefficient Time, constants utilized in the lead-lag compensator for AT Time constant utilized in the lag compensator for AT Time constant utilized in the measured Tavg lag compensator Time constant utilized in the rate-lag controller for Tavg f2(AI) "positive" breakpoint f2(AI) "negative'! breakpoint f2(AI) "positive" slope f2(AI) "negative" slope Nominal Value T" < 590.8 'F K4 = 1.0.819
.K5 0.02 / 'F for increasing Tavg K 5 = 0.00 / 'F for decreasing Tavg.
K6 = 0.001291/OF for T > T" K6 = 0.0 i°F for T < T"
-1 8 sec.
= 3 sec.
3= 0 sec.
-6= 0 sec.
7: 10 sec.
= 35.0 %AI
=-35.0 %AI
- 7.0 %ATO %AI
- 7.0 %AT/ %AI
i ý
ý' j CNEI-0400- 149 Page 26 of 32 Revision 1 Catawba 2 Cycle 16 Core Operating Limits Report 2.10 Boron Dilution Mitigation System (TS 3.3.9) 2.10.1 Reactor Makeup Water Pump flow rate limits:
Applicable Mode Limit Mode 3
< 150 gpm Mode 4 or 5
< 70 gpm 2.11 RCS Pressure, Temperature and Flow Limits for DNB (TS 3.4.1)
The RCS pressure, temperature and flow limits for DNB are shown in Table 4.
2.12 Accumulators (TS 3.5.1) 2.12.1 Boron concentration limits during modes 1 and 2, and mode 3 with RCS pressure
>1000 psi:
Parameter Limit Cold Leg Accumulator minimum boron concentration.
2,500 ppm Cold Leg Accumulator maximum boron concentration.
3,075 ppm 2.13 Refueling Water Storage Tank - RWST (TS 3.5.4) 2.13.1 Boron concentration limits during modes 1, 2, 3, and 4:
Parameter Limit Refueling Water Storage Tank minimum boron 2,700 ppm concentration.
Refueling Water Storage Tank maximum boron 3,075 ppm concentration.
CNEI-0400-149 Page 27 of 32 Revision 1 Catawba 2 Cycle 16 Core Operating Limits Report Table 4 Reactor Coolant System DNB Parameters No. Operable PARAMETER INDICATION
- CHANNELS, LIMITS
- 1. Indicated RCS Average Temperature meter 4
< 589.6 'F meter
- 3.
< 589.3 OF computer 4
< 590.1 OF computer 3
< 589.9 °F
- 2. Indicated Pressurizer Pressure meter 4
> 2219,8 psig meter 3
> 2222.1 psig computer 4
> 2215.8 psig computer 3
> 2217.5 psig
- 3. RCS Total Flow Rate
> 390,000 gpm
II CNEI-0400-149 Page 28 of 32 Revision 1 Catawba 2 Cycle 16 Core Operating Limits Report 2.14 Spent Fuel Pool Boron Concentration (TS 3.7.15) 2.14.1 Minimum boron concentration limit for the spent fuel pool. Applicable when fuel assemblies are stored in the spent fuel pool.
Parameter Limit Spent fuel pool minimum boron concentration.
. 2,700 ppm 2.15 Refueling Operations - Boron Concentration (TS 3.9.1) 2.15.1. Minimum boron concentration limit for the filled portions of the Reactor Coolant System, refueling. canal, and refueling cavity for mode6 conditions. The minimum boron concentration limit and plant refueling procedures ensure that the Keff of the core will remain within the mode 6 reactivity requirement of Keff <
0.95.
Parameter Limit Minimum Boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity.
2,700 ppm
CNEI-0400-149 Page 29 of 32 Revision 1 Catawba 2 Cycle 16 Core Operating Limits Report 2.16 Standby Shutdown System - Standby Makeup Pump Water Supply - (SLC-16.7-9.3) 2.16.1 Minimum boron concentration limit for the spent fuel pool. Applicable for modes 1, 2, and 3.
Parameter Limit Spent fuel pool minimum boron concentration for surveillance SLC-16.7-9.3.
2,700 ppm 2.17 Borated Water Source -Shutdown (SLC i6.9-11) 2.17.1 Volume and boron concentrations for the Boric Acid Tank (BAT) and the Refueling Water Storage Tank (RWST) during Mode 4 with any RCS cold leg temperature < 2100F, and Modes 5 and 6.
Parameter Boric Acid Tank minimum boron concentration Volume of 7,000 ppm boric acid solution required to maintain SDM at 680F Boric Acid Tank Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-11)
Limit 7,000 ppm 2000 gallons 13,086 gallons (14.9%)
NOTE: When cycle burnup is > 450 EFPD, Figure 6 may be used to determine the required Boric Acid Tank Minimum Level.
Refueling Water Storage Tank minimum boron concentration Volur'me of 2,700 ppm boric acid solution required to maintain SDM at 68 T Refueling Water Storage Tank Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-11) 2,700 ppm 7,000 gallons 48,500 gallons (8.7%)
0 CNEI-0400-149 Page 30 of 32 Revision I Catawba 2 Cycle 16 Core.Operating Limits Report 2.18 Borated Water Source - Operating (SLC 16.9-12) 2.18.1 Volume and boron concentrations for the Boric Acid Tank (BAT) and the Refueling Water Storage Tank (RWST) during Modes 1, 2, and 3 and Mode 4 with all RCS cold leg temperatures > 210 0F.
Parameter Boric Acid Tank minimum boron concentration Volume of 7,000 ppm boric acid solution required to maintain SDM at 210'F Boric Acid Tank Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-12)
Limit 7,000 ppm 13,500 gallons 25,200 gallons (45.80%)
NOTE: When cycle burnup is > 450 EFPD, Figure 6 may be used to determine the required Boric Acid Tank Minimum Level.
Refueling Water Storage Tank minimum boron concentration Volume of 2,700 ppm boric acid solution required to maintain SDM at 210'F Refueling Water Storage Tank Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-12) 2,700 ppm 57,107 gallons 98,607 gallons.
(22.0%)
0 p 1 CNEI-0400-149 Page 31 of 32 Revision 1 Catawba 2 Cycle 16.Core Operating Limits Report Figure 6 Boric Acid Storage Tank Indicated Level Versus Primary Coolant Boron Concentration (Valid When Cycle Burnup is > 450 EFPD)
This figure includes additional volumes listed in SLC 16.9-11 and 16.9-12 50.0
.R C S B o ro n Concentration BAT Level 40.0 i "
(ppm)
(%level) 0 < 300 43.0 300o< 500 40.0 35.0 500<700 37.0
,1,..
700 < 1000 30.0
- "30.0 1000 <.1300 14.9
'1300<2700 9.8 25.0
> 2700 9.8 Unacceptable
" 20.0 Operation Acceptable Operation 15.0 i
10.0
- Aiý A.. ON "k
0.0 0
200 400 600 800 1000 1200
. 1400 1600 1800 2000 2200 2400 2600 Primary Coolant Boron Concentration (ppmb)
CNEI-0400-149 Page 32 of 32 Revision 1 Catawba 2 Cycle 16 Core Operating Limits Report Appendix A Power Distribution Monitoring Factors Appendix A contains power dis.tribution monitoring factors used in Technical Specification Surveillance. Due to the size of the monitoring factor data, Appendix A is-controlled electronically within Duke and is not included in the Duke internal copies of the COLR. The Catawba Reactor and Electrical Systems Engineering Section controls this information via computer fl~es and should be contacted if there is a*need to access, this information.
Appendix A is included in the COLR copy transmitted to the NRC.