ML24281A016

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Core Operating Limits Report (COLR) for Unit 1 Cycle 29 Reload Core
ML24281A016
Person / Time
Site: Catawba 
Issue date: 10/07/2024
From: Flippin N
Duke Energy Carolinas
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
RA-24-0247
Download: ML24281A016 (1)
v • d • e


Text

~ ~ DUKE

~ ENERG~

RA-24-0247 October 7, 2024 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Duke Energy Carolinas, LLC (Duke Energy)

Catawba Nuclear Station, Unit 1 Facility Operating License Number NPF-35 Docket Number 50-413 Nicole Flippin Vice President Catawba Nuclear Station Duke Energy CN01VP 14800 Concord Road York, SC 29745 o: 803.701.3340 f 803.701.3221 Nicole.Flippin@duke-energy.com Core Operating Limits Report (COLR) for Unit 1 Cycle 29 Reload Core Pursuant to Catawba Technical Specification 5.6.5.d, enclosed is the subject COLR. This COLR revision is being submitted to update the limits of the Catawba Unit 1 Cycle 29 reload core.

This letter, and the enclosed COLR, do not contain any regulatory commitments.

Please direct any questions to Sherry Andrews, Regulatory Affairs, at (803) 701-3424.

Sincerely, Nicole Flippin Vice President, Catawba Nuclear Station

Enclosure:

Catawba Unit 1, Cycle 29, Revision 0, Core Operating Limits Report www. duke-energy. com

U.S. Nuclear Regulatory Commission RA-24-0247 October 7, 2024 Page 12 xc (with enclosure; with attachment):

L. Dudes, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, GA 30303-1257 David Rivard, Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station Jack Minzer-Bryant, Project Manager U.S. Nuclear Regulatory Commission Catawba Nuclear Station

Enclosure Catawba Unit 1 Cycle 29, Revision 0, Core Operating Limits Report

Catawba 1 Cycle 29 Core Operating Limits Report Revision 0 September 2024

Reference:

CNC-1553.05-00-0762, Rev. 0 Reload 50.59 #02520369 QA Condition 1 CNEI-0400-416 Page 1 Revision 0 The information presented in this report has been prepared and issued in accordance with Catawba Technical Specification 5.6.5.

Catawba 1 Cycle 29 Core Operating Limits Report Implementation Instructions for Revision 0 Revision Description and CR Tracking CNEI-0400-416 Page2 Revision 0 Revision O of the Catawba 1 Cycle 29 COLR contains limits applicable to the cycle 29 core.

Implementation Schedule The Catawba 1 Cycle 29 COLR requires the reload 50.59 (AR #02520369) be approved prior to implementation and fuel loading.

Revision O may become effective any time during NO MODE between cycles 28 and 29 but must become effective prior to entering MODE 6 which starts cycle 29. The Catawba 1 Cycle 29 COLR will cease to be effective during NO MODE between cycles 29 and 30.

Data Files to be Implemented No data files are transmitted as part of this document.

Additional Information A CDR was performed by Safety Analysis for COLR Sections 1.1, 2.1, 2.9-2.11, 2.13 and 2.16-2.18.

CNS Reactor Engineering performed a site inspection in accordance with AD-NF-ALL-0807 and AD-NF-NGO-0214.

Revision 0

CNEI-0400-416 Page3 Revision 0 Catawba 1 Cycle 29 Core Operating Limits Report Effective Date September 2024 REVISION LOG Pages Affected 1-31, Appendix A*

COLR CIC29 COLR, Rev. 0

  • Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance and is not uploaded as part of the EI body. However, Appendix A (.pdf) is archived electronically for ease of transmittal to the NRC, upon request.

Catawba 1 Cycle 29 Core Operating Limits Report CNEI-0400-416 Page4 Revision 0 1.0 Core Operating Limits Report TS Section 2.1.1 3.1.1 3.1.3 3.1.4 3.1.5 3.1.6 3.1.8 3.2.1 3.2.2 3.2.3 3.3.1 3.3.9 3.4.1

-u*****-***--***-**"""'" --**.

3.5.1 3.5.4 3.7.15 3.9.1 5.6.5 SLC Section 16.7-9 16.9-11 16.9-12 This Core Operating Limits Report (COLR) has been prepared in accordance with requirements of Technical Specification 5.6.5. Technical Specifications that reference this report are listed below along with the NRC approved analytical methods used to develop and/or determine COLR parameters identified in Technical Specifications.

COLR NRC Approved Technical Specifications COLR Parameter Section Methodology (Section 1.1 Number)

Reactor Core Safety Limits RCS Temperature and Pressure 2.1 6, 7, 8, 9, 10, 12, 15, Safetv Limits 16, 19,20 Shutdown Margin Shutdown Margin 2.2 6, 7, 8, 12, 14, 15, 16, 19, 20 Moderator Temperature Coefficient MTC 2.3 6, 7, 8, 14, 16, 18 Rod Group Alilm11lent Limits Shutdown Margin 2.2 6, 7, 8, 12, 14, 15, 16, 19, 20 Shutdown Bank Insertion Limit Shutdown Margin 2.2 2, 4, 6, 7, 8, 9, 10 Rod Insertion Limits 2.4 12, 14, 15, 16, 19 20 Control Bank Insertion Limit Shutdown Margin 2.2 2, 4, 6, 7, 8, 9, 10 Rod Insertion Limits 2.5 12, 14, 15, 16, 19, 20 Phvsics Tests Exceptions Shutdown Margin 2.2 6, 7, 8, 12, 14, 15, 16, 19 20 Heat Flux Hot Channel Factor FQ 2.6 2, 4, 6, 7, 8, 9, 10, AFD 2.8 12, 15, 16, 19, 20 OTL\.T 2.9 Penalty Factors 2.6 Nuclear Enthalpy Rise Hot Channel FL\.H 2.7 2, 4, 6, 7, 8, 9, 10 Factor OT.1.T 2.9 12, 15, 16, 19, 20 Penalty Factors 2.7 Axial Flux Difference AFD 2.8 2, 4, 6, 7, 8 15 16 Reactor Trip System Instrumentation OT.1.T 2.9 6, 7, 8, 9, 10, 12 OPL\.T 2.9 15, 16, 19, 20 Boron Dilution Mitigation Svstem Reactor Makeup Water Flow Rate 2.10 6, 7, 8, 14, 16 RCS Pressure, Temperature and Flow RCS Pressure, Temperature and 2.11 6, 7, 8, 9, 10, 12, limits for DNB Flow 19,20 Accumulators Max and Min Boron Cone.

2.12 6, 7, 8, 14, 16

~---~

Refueling Water Storage Tank Max and Min Boron Cone.

I 2.13 6, 7, 8, 14, 16 Spent Fuel Pool Boron Concentration Min Boron Concentration 2.14 6, 7, 8, 14, 16 Refueling Operations - Boron Min Boron Concentration 2.15 6, 7, 8, 14, 16 Concentration Core Operating Limits Report (COLR)

Analvtical Methods 1.1 None The Selected Licensee Commitments that reference this report are listed below COLR NRC Approved Selected Licensee Commitment COLR Parameter Section Methodology (Section 1.1 Number)

Standby Shutdown System Standby Makeup Pump Water Sup_ply 2.16 6, 7, 8, 14, 16 Boration Systems - Borated Water Borated Water Volume and Cone. for 2.17 6, 7, 8, 14, 16 Source - Shutdown BAT/RWST Boration Systems - Borated Water Borated Water Volume and Cone. for 2.18 6, 7, 8, 14, 16 Source - Operating BAT/RWST

Catawba 1 Cycle 29 Core Operating Limits Report 1.1 Analytical Methods CNEI-0400-416 Page 5 Revision 0 Analytical methods used to determine core operating limits for parameters identified in Technical Specifications and previously reviewed and approved by the NRC as specified in Technical Specification 5.6.5 are as follows.

1. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," 0ff... Proprietary).

Revision 0 Report Date: July 1985 Not Used

2. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code," (5ff_ Proprietary).

Revision 0 Report Date: August 1985 Addendum 2, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSI Condensation Model," (5ff_ Proprietary). (Referenced in Duke Letter DPC-06-101)

Revision 1 July 1997

3. WCAP-10266-P-A, "The 1981 Version of Westinghouse Evaluation Model Using BASH Code," (5ff_ Proprietary).

Revision 2 Report Date: March 1987 Not Used

4. WCAP-12945-P-A, Volume 1 and Volumes 2-5, "Code Qualification Document for Best-Estimate Loss of Coolant Analysis," 0ff... Proprietary).

Revision: Volume 1 (Revision 2) and Volumes 2-5 (Revision 1)

Report Date: 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

Catawba 1 Cycle 29 Core Operating Limits Report 1.1 Analytical Methods (continued)

CNEI-0400-416 Page6 Revision 0

6. DPC-NE-3000-PA, "Thermal-Hydraulic Transient Analysis Methodology," (Duke Energy Proprietary).

Revision Sa Report Date: October 2012

7. DPC-NE-3001-PA, "Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," (Duke Energy Proprietary).

Revision 1 Report Date: March 2015

8. DPC-NE-3002-A, "UFSAR Chapter 15 System Transient Analysis Methodology".

Revision 4c Report Date: February 2019

9. DPC-NE-2004P-A, "Duke Power Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-01," (Duke Energy Proprietary).

Revision2a Report Date: December 2008

10. DPC-NE-2005P-A, "Thermal Hydraulic Statistical Core Design Methodology," (Duke Energy Proprietary).

Revision 6 Report Date: September 2020

11. DPC-NE-2008P-A, "Fuel Mechanical Reload Analysis Methodology Using TACO3," (Duke Energy Proprietary).

Revision 0 Report Date: April 1995 Not Used

12. DPC-NE-2009-P-A, "Westinghouse Fuel Transition Report," (Duke Energy Proprietary).

Revision 3c Report Date: March 2017

13. DPC-NE-1004-A, "Nuclear Design Methodology Using CASMO-3/SIMULATE-3P."

Revision la Report Date: January 2009 Not Used

Catawba 1 Cycle 29 Core Operating Limits Report 1.1 Analytical Methods (continued)

14. DPC-NF-2010-A, "Nuclear Physics Methodology for Reload Design."

Revision2a Report Date: December 2009 CNEI-0400-416 Page7 Revision 0

15. DPC-NE-2011-PA, "Nuclear Design Methodology Report for Core Operating Limits of Westinghouse Reactors," (Duke Energy Proprietary).

Revision la Report Date: June 2009

16. DPC-NE-1005-PA, "Nuclear Design Methodology Using CASMO-4 / SIMULA TE-3 MOX,"

(Duke Energy Proprietary).

Revision 1 Report Date: November 2008

17. BAW-10231P-A, "COPERNIC Fuel Rod Design Computer Code" (Framatome ANP Proprietary)

Revision 1 SER Date: January 14, 2004 Not Used

18. DPC-NE-1007-P-A, "Conditional Exemption of the EOC MTC Measurement Methodology,"

(Duke Energy and W Proprietary)

Revision I Report Date: December 2022

19. WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report," CTf... Proprietary).

Revision 0 Report Date: April 1995

20. WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLO1M," CTf...

Proprietary).

Revision 0 Report Date: July 2006

Catawba 1 Cycle 29 Core Operating Limits Report 2.0 Operating Limits CNEI-0400-416 Page 8 Revision 0 Cycle-specific parameter limits for 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)

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, SDM shall be:::: 1.3% &/kin MODE 2 with Keff< 1.0 and in MODES 3 and 4.

2.2.2 For TS 3.1.1, SDM shall be:::: 1.0% &/kin MODE 5.

2.2.3 For TS 3.1.4, SDM shall be:::: 1.3% &/kin MODE 1 and MODE 2.

2.2.4 For TS 3.1.5, SDM shall be:::: 1.3% &/kin MODE 1 and MODE 2 with any control bank not fully inserted.

2.2.5 For TS 3.1.6, SDM shall be:::: 1.3% &/kin MODE 1 and MODE 2 with Keff::::

1.0.

2.2.6 For TS 3.1.8, SDM shall be:::: 1.3% &/kin MODE 2 during PHYSICS TESTS.

CNEI-0400-416 Page9 Revision 0 Catawba 1 Cycle 29 Core Operating Limits Report Figure 1 Reactor Core Safety Limits (Four Loops in Operation) 670.-------.-----........ ----.....------,-------.-------,

DO NOT OPERATE IN THIS AREA 660 1------+-----+------t

I

~ 630 1------+-----=---.::--1-----+----=-,,j;;::------+-----'r-------l Oil

~

E-<

CIJ

~ 620 590 1------+-----+-----+---------1------+-------t ACCEPTABLE OPERATION 580 ----------------~-----------~---~

0.0 0.2 0.4 0.6 0.8 1.0 1.2 Fraction of Rated Thermal Power

Catawba 1 Cycle 29 Core Operating Limits Report 2.3 Moderator Temperature Coefficient-MTC (TS 3.1.3) 2.3.1 Moderator Temperature Coefficient (MTC) Limits are:

MTC shall be less positive than the upper limits shown in Figure 2.

BOC, ARO, HZP MTC shall be less positive than 0.7E-04 dk/k/°F.

CNEI-0400-416 Page 10 Revision 0 EOC, ARO, RTP MTC shall be less negative than the -4.3E-04 Afdk/°F lower MTC limit.

2.3.2 300 ppm MTC Surveillance Limit is:

Measured 300 ppm ARO, equilibrium RTP MTC shall be less negative than or equal to -3.65E-04 dk/k/°F.

2.3.3 The Revised Predicted near-EOC 300 ppm ARO RTP MTC shall be calculated using the procedure contained in DPC-NE-1007-P-A.

If the Revised Predicted MTC is less negative than or equal to the 300 ppm SR 3.1.3.2 Surveillance Limit, and all benchmark data contained in the surveillance procedure is satisfied, then an MTC measurement in accordance with SR 3.1.3.2 is not required to be performed.

2.3.4 60 ppm MTC Surveillance Limit is:

Measured 60 ppm ARO, equilibrium RTP MTC shall be less negative than or equal to -4.125E-04 dk/k/°F.

Where:

BOC = Beginning of Cycle (burnup corresponding to most positive MTC)

EOC = End of Cycle ARO = All Rods Out HZP = Hot Zero Power R TP = 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. Shutdown banks are withdrawn with no overlap.

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.

1.0 0.9 0.8 0.3 0.2 0.1 0.0 CNEI-0400-416 Page 11 Revision 0 Catawba 1 Cycle 29 Core Operating Limits Report Figure 2 Moderator Temperature Coefficient Upper Limit Versus Power Level Unacceptable Operation Acceptable Operation 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 1 ROD manual for details.

231 220 200 f 180 f

'C ! 160

~

cS. 140 l = 120 Q :e

~ 100 i:l,; =

]

80 GI

,S 60

'C.s 40 20 0

CNEI-0400-416 Page 12 Revision 0 Catawba 1 Cycle 29 Core Operating Limits Report Figure3 Control Bank Insertion Limits Versus Percent Rated Thermal Power Fully Withdr~~

(Maximum=231) ""-

~

/

V ControlBankB

/

E::I (0%, 163)

/

/

V V

E:j (0%, 47)

Fully Inserted

~

(30%,0) 0 10 20 30 r

/

Fully Withdrawn (Minimum=222)

/

c100%, 161) F V

V

/

'V V

/

1 ControlBank C L/

1 ControlBankD 1

/

I/

/

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 be calculated by:

BankCDRIL =2.3(P)-69

{30'5':.P'5':.100}

Bank CC RIL = 2.3(P) + 47

{O '5':.P '5':. 76.1) for CC RIL = 222 {76.1 < P '5':. JOO}

Bank CB RIL = 2.3(P) + 163 {O '5':. P '5':. 25. 7) for CB RIL = 222 {25. 7 < P '5':. 100) where P = % of Rated Thermal Power NOTE:

Compliance with Technical Specification 3.1.3 may require rod withdrawal limits.

Refer to the Unit 1 ROD manual for details.

Catawba 1 Cycle 29 Core Operating Limits Report Table 1 Control Bank Withdrawal Sequence Equation Control Control Control Control Bank A Bank B Bank C Bank D O Start 0

0 116 O Start 0

CBA Stop CBA-116 0

CBA 116 0 Start CBA CBB Stop CBB - 116 CBA CBB 116 CBA CBB CBC Stop Where:

CEA = Fully withdrawn position of Control Bank A CBB = Fully withdrawn position of Control Bank B CBC = Fully withdrawn position of Control Bank C 0

0 0

0 0

0 Start CBC-116 CNEI-0400-416 Page 13 Revision 0 Allowed Control Bank Fully Withdrawn Positions are provided in CNEI-0400-091, "RCCA Axial Repositioning Schedule for Catawba Nuclear Station."

Catawba 1 Cycle 29 Core Operating Limits Report 2.6 Heat Flux Hot Channel Factor-FQ(X,Y,Z) (TS 3.2.1)

CNEI-0400-416 Page 14 Revision 0 2.6.1 FQ(X,Y,Z) steady-state limits are defined by the following relationships:

F RTP *K(Z)IP Q

F ~TP *K(Z)/0.5

where, p =

Thermal Power Rated Thermal Power for P > 0.5 forP :::;0.5 Note:

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.

RTP 2.6.2 FQ

= 2.70 x K(BU) 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 ofbumup. F~TP with the K(BU) penalty for Westinghouse RF A fuel is analytically confirmed in cycle-specific reload calculations. K(BU) is set to 1.0 at all bumups.

The following parameters are required for core monitoring per the Surveillance Requirements of Technical Specification 3.2.1:

1 Fg(X,Y,Z)

  • M0(X,Y,Z) 2.6.5

[FQ(X,Y,Z)]OP =

UMT *MT* TILT where:

[Fa(X,Y,Z)]OP = Cycle dependent maximum allowable design peaking factor that ensures FQ(X,Y,Z) LOCA limit is not exceeded for operation within AFD, RIL, and QPTR limits. Fa(X, Y,Z)°p includes allowances for calculation and measurement uncertainties.

F8(X,Y,Z) = Design power distribution for FQ. F8(X,Y,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 operation.

CNEI-0400-416 Page 15 Revision 0 Catawba 1 Cycle 29 Core Operating Limits Report MQ(X,Y,Z) = 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-1 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 to account for allowable quadrant power tilt ratio of 1.02. (TIL T = 1.035)

L RPS Fg(X, Y,Z)

  • McCX, Y,Z) 2*6*6

[FQ(X,Y,Z)]

=

UMT *MT* TILT where:

[Ft(X,Y,Z)]RPS = Cycle dependent maximum allowable design peaking factor that ensures F Q(X,Y,Z) Centerline Fuel Melt (CFM) limit is not exceeded for operation within AFD, RIL, and QPTR limits.

[Ft(x, Y,Z) ]RPS includes allowances for calculation and measurement uncertainties.

D FQ(X,Y,Z) = Defined in Section 2.6.5.

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.

UMT = Defined in Section 2.6.5.

MT

= Defined in Section 2.6.5.

TILT = Defined in Section 2.6.5.

Catawba 1 Cycle 29 Core Operating Limits Report 2.6.7 KSLOPE = 0.0725 where:

CNEI-0400-416 Page 16 Revision 0 KS LOPE = Adjustment to K 1 value from OT~ T trip setpoint required to compensate for each 1 % F~(X, Y,Z) exceeds [F~(X, Y,Z)]RPs.

2.6.8 Fo(X,Y,Z) Penalty Factors for Technical Specification Surveillances 3.2.1.2 and 3.2.1.3 are provided in Table 2.

Catawba 1 Cycle 29 Core Operating Limits Report Figure 4 K(Z), Normalized F Q(X, Y,Z) as a Function of Core Height forRFAFuel CNEI-0400-416 Page 17 Revision 0 1.200 -,-----------------------------,

(0.0, 1.00)

(4.0, 1.00) 1.000..... --------,

0.800 g 0.600

~

0.400 0.200 0.000 0.0 Core Height

{ft}

0.0

~

>4 12.0 2.0 (4.0, 0.9259)

K(Z}

1.000 1.000 0.9259 0.9259 4.0 6.0 Core Height (ft)

(12.0, 0.9259) 8.0 10.0 12.0

Catawba 1 Cycle 29 Core Operating Limits Report Table2 FQ(X,Y,Z) and FMI(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 75 100 125 150 175 200 225 250 275 300 325 350 375 400 425 450 475 490 507 511 520 530 540 FQ(X,Y,Z)

Penalty ],factor(%)

2.00 2.00 2.00 3.84 2.34 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 F1m(X,Y)

Penalty Factor (%)

2.00 2.00 2.00 2.00 2.00 2.66 2.02 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 burnups.

All cycle burnups outside the range of the table shall use a 2%

penalty factor for both Fo(X,Y,Z) and FL1H(X,Y) for compliance with Tech Spec Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2.

CNEI-0400-416 Page 18 Revision 0

CNEI-0400-416 Page 19 Revision 0 Catawba 1 Cycle 29 Core Operating Limits Report 2.7 Nuclear Enthalpy Rise Hot Channel Factor - F MJ(X,Y) (TS 3.2.2)

Fm steady-state limits referred to in Technical Specification 3.2.2 are defined by the following relationship.

where:

[FkH(X,Y)]LCO = 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.

P= Rated Thermal Power Thermal Power RRH = Thermal Power reduction required to compensate for each 1 % measured radial peak, FrH(X, Y), exceeds the limit.

(RRH = 3.34, 0.0 < P.:S 1.0)

The following parameters are required for core monitoring per surveillance requirements of Technical Specification 3.2.2.

2.7.2

[FkH(X,Y)J8URV = F~(X, Y)*M~H(X,Y)

UMR *TILT where:

[F~H(X,Y)]SURV --

C 1 d d

11 bl d

  • aki
c.

L.l ye e epen ent maximum a owa e es1gn pe ng 1actor that ensures F LlH(X,Y) limit is not exceeded for operation within AFD, RIL, and QPTR limits. FkH(X,Y/URV includes allowances for calculation and measurement uncertainty.

F~H (X, Y) = Design power distribution for F LlH, F~H (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-0400-416 Page 20 Revision 0 Catawba 1 Cycle 29 Core Operating Limits Report M,m(X, Y) = Margin remaining in core location X, Y relative to the Operational DNB limits in the transient power distribution.

Mm(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 (UMR = 1.0).

UMR is 1.0 since a factor of 1.04 is implicitly included in the variable ML\H(X, Y).

TILT = Defined in Section 2.6.5.

2.7.3 RRH is defined in Section 2.7.1.

2.7.4 TRH = 0.04 where:

TRH = Reduction in OT d T K1 setpoint required to compensate for each 1 % that the measured radial peak, FfH(X,Y) exceeds its limit.

2.7.5 Fim(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 Axial Flux Difference (AFD) Limits are provided in Figure 5.

CNEI-0400-416 Page 21 Revision 0 Catawba 1 Cycle 29 Core Operating Limits Report Table3 Maximum Allowable Radial Peaks (MARPs)

RFA Steady State Limiting Value Between Loss of Flow Accident (LOFA) MARPs and F8HLOcA Core Axial Peak 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

3.25 0.12 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.3151 1.2461 1.20 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.3007 1.2235 2.40 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.4633 1.4616 3.60 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.4675 1.3874 4.80 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.2987 1.2579 6.00 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.3293 1.2602 7.20 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.5982 1.2871 1.2195 8.40 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6010 1.5127 1.2182 1.1578 9.60 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.5808 1.5301 1.4444 1.1431 1.0914 10.80 1.6058 1.6058 1.6058 1.6058 1.6058 1.6058 1.5743 1.5573 1.5088 1.4624 1.3832 1.1009 1.0470 11.40 1.6058 1.6058 1.6058 1.6058 1.6057 1.5826 1.5289 1.5098 1.4637 1.4218 1.3458 1.0670 1.0142

lo ;

0 g,.

-; e lo Q

-=

E--<

"'C

~ "

~

0

.... =

Q Q

g,.

-50 CNEI-0400-416 Page 22 Revision 0 Catawba 1 Cycle 29 Core Operating Limits Report Figures Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits

(-18, 100)

(+10, 100)

Unacceptable Operation 90 Unacceptable Operation 80 Acceptable Operation 70 60 50

(-36, 50)

(+21, 50) 40 30 20 10

-40

-30

-20

-10 0

10 20 30 40 50 Axial Flux Difference (% Delta I)

NOTE: Compliance with Technical Specification 3.2.l may require more restrictive AFD limits. Refer to the Unit 1 ROD manual for operational AFD limits.

Catawba 1 Cycle 29 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 Tavg at RTP Nominal RCS Operating Pressure Overtemperature ~ T reactor trip setpoint Overtemperature ~ T reactor trip heatup setpoint penalty coefficient Nominal Value T' ::=; 585.1°F P' = 2235 psig K1 = 1.1978 K2 = 0.033401°F CNEl-0400-416 Page 23 Revision 0 Overtemperature ~ T reactor trip depressurization setpoint penalty coefficient K3 = 0.00160llpsi Time constants utilized in the lead-lag compensator for~T Time constant utilized in the lag compensator for ~ T Time constants utilized in the lead-lag compensator for Tavg Time constant utilized in the measured Tav8 lag compensator f1 (M) "positive" breakpoint f I (Al) "negative" breakpoint f1 (M) "positive" slope f 1 (M) "negative" slope i:1 = 8 sec.

i:2 = 3 sec.

i:3 ::S 1.8 sec.

i:4 = 22 sec.

i:5 = 4 sec.

't6 ::S 1.8 sec.

= 19.0 %Al

=NIA*

= 1.769 %ATol %M

=NIA*

f1 (AI) negative breakpoints and slopes for OTLff are less restrictive than OPAT f2(AI) negative breakpoint and slope. Therefore, during a transient which challenges negative imbalance limits, OPAT f2(AI) limits will result in a reactor trip before OTAT f1 (AI) limits are reached. This makes implementation of an OTAT f1 (AI) negative breakpoint and slope unnecessary.

CNEI-0400-416 Page 24 Revision 0 Catawba 1 Cycle 29 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 T avg lag compensator Time constant utilized in the rate-lag controller for Tavg fz(AI) "positive" breakpoint fz(AI) "negative" breakpoint fz(AI) "positive" slope fz(AI) "negative" slope Nominal Value T" :S 585.1 °P K4 :S 1.0909 Ks = 0.02 I 0P for increasing Tavg Ks= 0.00 I 0P for decreasing Tavg K6=0.001179/0P for T > T" K6 = 0.0 /0P for T :ST"

-c1 = 8 sec.

-c2 = 3 sec.

-c3 ~ 1.8 sec.

-c7 = 10 sec.

=27.0 %AI

=-27.0 %Al

= 7.0 %ATof %AI

Catawba 1 Cycle 29 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 MODE3 MODE4 or5

< 80 gpm

< 70 gpm 2.11 RCS Pressure, Temperature, and Flow Limits for DNB (TS 3.4.1)

RCS pressure, temperature and flow limits for DNB are shown in Table 4.

2.12 Accumulators (TS 3.5.1)

CNEI-0400-416 Page 25 Revision 0 2.12.1 Boron concentration limits during MODES 1 and 2, and MODE 3 with RCS pressure > 1000 psi:

Parameter Annlicable Burnun Limit Accumulator minimum boron concentration.

0-200 EFPD 2,500 ppm Accumulator minimum boron concentration.

200.1 - 300 EFPD 2,500 ppm Accumulator minimum boron concentration.

300.1 - 400 EFPD 2,368 ppm Accumulator minimum boron concentration.

400.1 - 490 EFPD 2,186 ppm Accumulator minimum boron concentration 490.1 - 530 EFPD 2,045 ppm Accumulator minimum boron concentration 530.1 - 540 EFPD 1,982 ppm Accumulator maximum boron concentration.

0-540 EFPD 3,075 ppm

Catawba 1 Cycle 29 Core Operating Limits Report Table4 Reactor Coolant System DNB Parameters No. Operable PARAMETER INDICATION CHANNELS

1. Indicated RCS Average Temperature meter 4

meter 3

computer 4

computer 3

2. Indicated Pressurizer Pressure meter 4

meter 3

computer 4

computer 3

3. RCS Total Flow Rate CNEI-0400-416 Page 26 Revision 0 LIMITS
S 587.5 °F
S 587.3 °F
S 588.0 °F
S 587.9 °F

~ 2206.9 psig

~ 2208.7 psig

~ 2204.0 psig

~ 2205.4 psig

> 384,000 gpm

Catawba 1 Cycle 29 Core Operating Limits Report 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 RWST minimum boron concentration.

RWST maximum boron concentration.

2.14 Spent Fuel Pool Boron Concentration (TS 3.7.15)

CNEI-0400-416 Page 27 Revision 0 Limit 2,700 ppm 3,075 ppm 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.

2,700ppm 2.15 Refueling Operations -Boron Concentration (TS 3.9.1) 2.15.1 Minimum boron concentration limit for filled portions of the Reactor Coolant System, refueling canal, and refueling cavity for MODE 6 conditions. The minimum boron concentration limit and plant refueling procedures ensure that core Keff remains within MODE 6 reactivity requirement ofKeff::; 0.95.

Parameter Minimum boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity.

Limit 2,700 ppm

CNEI-0400-416 Page 28 Revision 0 Catawba 1 Cycle 29 Core Operating Limits Report 2.16 Standby Shutdown System (SLC-16.7-9) 2.16.1 Minimum boron concentration limit for the spent fuel pool required for Standby Makeup Pump Water Supply. Applicable for MODES 1, 2, and 3.

Parameter Spent fuel pool minimum boron concentration for TR 16.7-9-3.

Limit 2,700 ppm 2.17 Boration Systems Borated Water Source-Shutdown (SLC 16.9-11) 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 :S 210 °P, and MODES 5 and 6.

Parameter BAT minimum boron concentration Volume of 7,000 ppm boric acid solution required to maintain SDM at 68°P Limit 7,000 ppm 2,000 gallons NOTE: When cycle burn up is > 488 EFPD, Figure 6 may be used to determine the required BAT minimum level.

BAT Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-11)

R WST minimum boron concentration Volume of2,700 ppm boric acid solution required to maintain SDM at 68 °P RWST Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-11) 13,086 gallons (14.9%)

2,700 ppm 7,000 gallons 48,500 gallons (8.7%)

CNEI-0400-416 Page 29 Revision 0 Catawba 1 Cycle 29 Core Operating Limits Report 2.18 Boration Systems 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 °F*.

  • NOTE: The SLC 16.9-12 applicability is down to MODE 4 temperatures of

> 210°F. The minimum volumes calculated support cooldown to 200°F to satisfy UFSAR Chapter 9 requirements.

Parameter BAT minimum boron concentration Volume of 7,000 ppm boric acid solution required to maintain SDM at 210 °F 7,000 ppm 13,500 gallons NOTE: When cycle burn up is > 488 EFPD, Figure 6 may be used to determine the required BAT minimum level.

BAT Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-12)

RWST minimum boron concentration Volume of 2,700 ppm boric acid solution required to maintain SDM at 210 °F RWST Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-12) 25,200 gallons (45.8%)

2,700 ppm 57,107 gallons 98,607 gallons (22.0%)

50.0 45.0 40.0 35.0

-J 30.0 j

~

i 25.0 j

~ 20.0 m

15.0 10.0 5.0 0.0 0

Catawba 1 Cycle 29 Core Operating Limits Report Figure 6 Boric Acid Storage Tank Indicated Level Versus Primary Coolant Boron Concentration (Valid When Cycle Burnup is> 488 EFPD)

CNEI-0400-416 Page 30 Revision 0 This figure includes additional volumes listed in SLC 16.9-11 and 16.9-12 i

I I

I I

RCS Boron Concentration BAT Level I

(ppm)

(%level)

I 0 < 300 43.0 I

300 < 500 40.0 500 < 700 37.0 I

700 < 1000 30.0 i

1000 < 1300 14.9 1300 < 2700 9.8

> 2700 9.8 I

I Unacceptable Operation Acceptable Operation 200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 2600 Primary Coolant Boron Concentration (ppmb)

Catawba 1 Cycle 29 Core Operating Limits Report Appendix A Power Distribution Monitoring Factors CNEI-0400-416 Page 31 Revision 0 Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. This data was generated in the Catawba 1 Cycle 29 Maneuvering Analysis calculation file, CNC-1553.05-00-0759, Rev 0. Due to the size of the monitoring factor data, Appendix A is controlled electronically within Duke Energy and therefore is not included in the Duke Energy internal copies of the COLR EI. Nuclear Fuels Engineering will control this information via computer file(s) and should be contacted if there is a need to access this information.

Appendix A is available to be transmitted to the NRC upon request.

Filename Cksum I File Size clc29colrei_rO_AppendixA.pdf 3388807101 I 1368908

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