ML17179A428

Submittal of Core Operating Limits Report (COLR) for Cycle 24 Reload Core

ML17179A428
Person / Time
Site:	Catawba
Issue date:	06/20/2017
From:	Simril T Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CNC-1553.05-00-0651, Rev. 0, CNS-17-030 CNEI-0400-310, Rev 0
Download: ML17179A428 (34)

Text

(~ DUKE ENERGY~

CNS-17-030 June 20, 2017 U.S. Nuclear Regulatory Commission Attention: Document Control Desk 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 Tom Simril Vice President Catawba Nuclear Station Duke Energy CN01VP I 4800 Concord Road York, SC 29745 o: 803.701.3340 f: 803. 701.3221 tom.simril@duke-energy.com Core Operating Limits Report (COLR) for Cycle 24 Reload Core Pursuant to Catawba Technical Specification 5.6.5d., please find attached an information copy and an electronic copy of the subject COLR. This COLR revision is being submitted to update the limits of the Unit 1 Cycle 24 reload core.

The electronic copy of this COLR is included with this letter in portable document format (PDF) on a digital versatile disc (DVD). The electronic copy includes the power distribution monitoring factors.

This letter, the enclosed COLR, and the included DVD COLR with Attachment A, do not contain any regulatory commitments.

Please direct any questions or concerns to Carrie Wilson, Sr. Engineer, at (803) 701-3014.

Sincerely, Tom Simril Vice President, Catawba Nuclear Station Enclosures (paper COLR and DVD COLR with Attachment A) www.duke-energy.com

U.S. Nuclear Regulatory Commission CNS-17-030 Page 12 June 20, 2017 xc (with enclosures):

C. Haney, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, GA 30303-1257 J. D. Austin, Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station M. Mahoney, Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mailstop 0-8H4A Rockville, MD 20852

Enclosures Catawba Unit 1 Cycle 24 COLR (paper COLR and DVD COLR with Attachment A)

Catawba I Cycle 24 Core Operating Limits Report Revision 0 Apri l 2017

Reference:

CNC-1553.05-00-0651, Rev. 0 Duke Energy Carolinas, LLC QA CONDITION I CNEI-0400-310 Page I 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 24 Core Operating Limits Report Implementation Instructions for Revision 0 Revision Description and CR Tracking CNEI-0400-310 Page 2 Revision 0 Revision 0 of the Catawba Unit 1 Cycle 24 Core Operating Limits Report (COLR) contains limits specific to the reload core.

There is no CR associated with this revision.

Implementation Schedule The Catawba Unit 1 Cycle 24 COLR requires the reload 50.59 be approved prior to implementation and fuel loading.

Revision 0 may become effective any time during No MODE between cycles 23 and 24 but must become effective prior to entering MODE 6 which starts cycle 24. The Catawba Unit 1 Cycle 24 COLR will cease to be effective during No MODE between cycle 24 and 25.

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

Revision 0

CNEI-0400-310 Page 3 Revision 0 Catawba 1 Cycle 24 Core Operating Limits Report Effective Date April 2017 REVlSION LOG Pages Affected 1-31, Appendix A*

COLR ClC24 COLR, Rev. 0

• Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. Appendix A is included only in the electronic COLR copy sent to the NRC.

Catawba 1 Cycle 24 Core Operating Limits Report CNEI-0400-3 10 Page 4 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 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 Lim its 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 I

6, 7, 8, 9, 10, 12, 15, Safety Limits 16, 19, 20 Sh ut~own Margin

~ S_!!utdown Margin 2.2 6, 7, ~ 12, 14! 15, 16, 19, 20 M~derat~r Tell]perature Coefficie!1t.

MTC 2.3

~ :L 8, 14, 16, 18 Rod Group Alignment 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,.!_4, l5, 16, 19, 20 Control Bank Insertion Limit Shutdown Margin 2.2 2, 4, 6, 7, 8, 9, 10 Rod Insertion Limits 2.5

~~, _!J, 16, 19, 20 J~s~s Te~s Exceptions Shutdown Margin 2.2 6, 7, 8,Jl, 14, 15, 16, 19, 20 Heat Flux Hot Channel Factor Fo I

2.6 2, 4, 6, 7, 8, 9, 10, AFD 2.8 12, 15, 16, 19, 20 OT.t-.T 2.9 Penalty Factors I

2.6 Nuclear Enthalpy Rise Hot Channel FiiH 2.7 2, 4, 6, 7, 8, 9, 10 Factor Penalty Factors 2.7 12_,_!5!..16! 191 20 Axial Flux Difference AFD 2.8 2_, 42..6,_7, 8, ~5, 16 Reactor Trip System Instrumentation OT.t-.T 2.9 6, 7, 8, 9, 10, 12 OP.t.T 2.9 15, 16, 19, 20 Boron Dilution Mitigation System 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

)

1 9, ~0 Accumulators Max and Min Boron Cone.

2.12 6, 7 ~ !!., 14, 16 Refus:Iing Water Storage Tank Max and Min Boron Cone.

1 2. 13 6, 7, _8, 14, 16

~~ t Fuel Pool Boron Concentra~o n Min Boron Concentration J

2.14 2, 7, 8, 14, 16 Refueling Operations - Boron Min Boron Concentration 2.15 6, 7, 8, 14, 16 Concentration Core Operating Limits Report (COLR)

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

Standby Shutdown System Standby Makeup Pump Wate_r Supply 2.16 I

6, 7, 8, 14, 16 Boration Systems - Borated Water Borated Water Volume and Cone. for 2.17 I

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 24 Core Operating Limits Report 1.1 Analytical Methods CNEl-0400-310 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," (W Proprietary).

Revision 0 Report Date: July 1985 Not Used

2.

WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code, " (W 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 COS! Condensation Model," (W Proprietary). (Referenced in Duke Letter DPC I 01)

Revision I Report Date: July I 997

3.

WCAP-I 0266-P-A, "The I 981 Version of Westinghouse Evaluation Model Using BASH Code", (W Proprietary).

Revision 2 Report Date: March 1987 Not Used

4.

WCAP-12945-P-A, Volume I and Volumes 2-5, "Code Qualification Document for Best-Estimate Loss of Coolant Analysis," (W Proprietary).

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

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 I SER Date: January 22, 1991 Revision 2 SER Dates: August 22, 1996 and November 26, 1996 Revision 3 SER Date: June I 5, 1994 Not Used

Catawba 1 Cycle 24 Core Operating Limits Report 1.1 Analytical Methods (continued)

CNEI-0400-310 Page 6 Revision 0

6.

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

Revision Sa Report Date: October 2012

7.

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

Revision I Report Date: March 2015

8.

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

Revision 4b Report Date: September 201 0

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

Revision 2a Report Date: December 2008

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

Revision 5 Report Date: March 2016

11. DPC-NE-2008P-A, "Fuel Mechanical Reload Analysis Methodology Using T AC03," (DPC Proprietary).

Revision 0 Report Date: April 3, 1995 Not Used

12. DPC-NE-2009-PA, "Westinghouse Fuel Transition Report," (DPC Proprietary).

Revision 3c Report Date: March 2017

13. DPC-NE-1004-A, "Nuclear Design Methodology Using CASM0-3/SfMULATE-3P."

Revision la Report Date: January 2009 Not Used

Catawba 1 Cycle 24 Core Operating Limits Report 1.1 Analytical Methods (continued)

CNEI-0400-310 Page 7 Revision 0

14. DPC-NF-2010-A, "Duke Power Company McGuire Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design."

Revision 2a Report Date: December 2009

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

Revision la Report Date: June 2009

16. DPC-NE-1005-PA, "Nuclear Design Methodology Using CASM0-4 I SIMULATE-3 MOX",

(DPC Proprietary).

Revision 1 Report Date: November 12, 2008

17. BA W-10231 P-A, "COPERN IC Fuel Rod Design Computer Code" (Framatome ANP Proprietary)

Revision I SER Date: January 14, 2004 Not Used

18. DPC-NE-1007-PA, "Conditional Exemption ofthe EOC MTC Measurement Methodology,

(DPC and W Proprietary)

Revision 0 Report Date: A pri I 2015

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

Revision 0 Report Date: April 1995

20. WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLO""," (W Proprietary).

Revision 0 Report Date: July 2006

Catawba 1 Cycle 24 Core Operating Limits Report 2.0 Operating Limits CNEI-0400-310 Page 8 Revision 0 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. l, SOM shall be greater than or equal to 1.3% ~K/K in MODE 2 with Keff < 1.0 and in MODES 3 and 4.

2.2.2 For TS 3.1.1, SOM shall be greater than or equal to 1.0%.6K/K in MODE 5.

2.2.3 For TS 3.1.4, SOM shall be greater than or equal to 1.3%.6K/K in MODE 1 and MODE2.

2.2.4 For TS 3.1.5, SOM shall be greater than or equal to 1.3%.6K/K in MODE 1 and MODE 2 with any control bank not fully inserted.

2.2.5 For TS 3.1.6, SOM shall be greater than or equal to 1.3%.6K/K in MODE 1 and MODE 2 with Keff ~ 1.0.

2.2.6 For TS 3.1.8, SOM shall be greater than or equal to 1.3%.6KIK in MODE 2 during PHYSICS TESTS.

660 500 580 0.0 Catawba 1 Cycle 24 Core Operating Limits Report Figure 1 Reactor Core Safety Limits Four Loops in Operation CNEI-0400-310 Page 9 Revision 0 DO NO OP RATE IN THIS AA. A ACC_PTABlE OPERATIC 02 0.4 0.6 0.8 1.0 1.2 Fraction of Rated Thermal Powe

Catawba 1 Cycle 24 Core Operating Limits Report 2.3 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.3.1 Moderator Temperature Coefficient (MTC) Limits are:

CNEI-0400-310 Page 10 Revision 0 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 LiK/K/°F.

EOC, ARO, RTP MTC shall be less negative than the -4.3E-04 LiKIK/°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 LiK/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-PA.

If the Revised Predicted MTC is less negative than or equal to the 300 ppm SR

3. l.3.2 Surveillance Limit, and all benchmark data contained in the surveillance procedure is satisfied, then a 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 LiK/K/°F.

Where:

BOC = Beginning of Cycle (burn up 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 Limits (TS 3.1.5) 2.4.1 Each shutdown bank shall be withdrawn to at least 222 steps. Shutdown banks are withdrawn in sequence and 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.

Catawba 1 Cycle 24 Core Operating Limits Report Figure 2 CNEI-0400-310 Page 11 Revision 0 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 Unacceptable Operation Acceptable Operation 0.1 0.0 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

~ 180

~

"O

.c 160

i Catawba 1 Cycle 24 Core Operating Limits Report Figure 3 CNEI-0400-310 Page 12 Revision 0 Control Bank Insertion Limits Versus Percent Rated Thermal Power Fully Withdrawn (Maximum = 23 l~

~

~ - ---- -- -- --

--~ - -

~

-~ -

/

/

/

/

/

/

/

/

Fully Withdrawn

/

/

Control Bank 8 (Minimum = 222)

/

/

/

/

c100%, 161) F

/

/

/

B (0%, 163) I

/

/

/

/

/

/

~ 140

/

/

/

1 ControlBa nk C 1

/

~

rfJ c:

0 E

0 Q.,

c:

0

'.C...

~

c: -

"O 0

~

/

/

I I

/

120

/

/

v

/

/

/

/

/

100

/

/

/

/

/

80 v

/

/

Control Bank D v

/

/

/

60

/

/

/

/

40

~ (0%, 47)

~

/

/

/

20

] Fully Inserted 1

/

/

~

I 1(30%, 0) I

~

/

0 -

I I/

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 be calculated by:

Bank CD RIL = 2.3(P) - 69 {30 <.::.P <.::.JOO}

Bank CC RIL = 2. 3(P) +47

{O <.::.P <.::. 76.J} for CC RIL = 222 {76.J < P <.::.JOO}

Bank CB RIL = 2.3(P) + J63 {O <.::. P <.::. 25. 7) for CB RIL = 222 {25. 7 < P <.::.JOO}

where P = %Rated Thermal Power NOTES: Compliance with Technical Specification 3.1.3 may require rod withdrawal limits.

Refer to the Unit 1 ROD manual for details.

Catawba 1 Cycle 24 Core Operating Limits Report Table 1 Control Bank Withdrawal Steps and Sequence Fully Withdrawn at 222 Steps Control Bank A 0 Start 11 6 222 Stop 222 222 222 222 Control Bank B 0

0 Start 106 11 6 222 Stop 222 222 Control Control Bank C Bank D 0

0 0

0 0

0 0 Start 0

106 0

11 6 0 Start 222 Stop 106 Fully Withdrawn at 224 Steps Control Bank A 0 Start 11 6 224 Stop 224 224 224 224 Control Bank B 0

0 Start 108 11 6 224 Stop 224 224 Control Control Ba nk C Ba nk D 0

0 0

0 0

0 0 Start 0

108 0

11 6 0 Start 224 Stop 108 Fully Withdrawn at 226 Steps Control Bank A O Start 11 6 226 Stop 226 226 226 226 Control Bank B 0

0 Start 110 11 6 226 Stop 226 226 Control Control Bank C Bank D 0

0 0

0 0

0 0 Start O

11 0 0

11 6 0 Start 226 Stop 11 0 Fully Withdrawn at 228 Steps Control Control Control Control Bank A Bank B Ba nk C Bank D 0 Start 11 6 228 Stop 228 228 228 228 0

0 Start 11 2 11 6 228 Stop 228 228 0

0 0

0 Start 11 2 11 6 228 Stop 0

0 0

0 0

0 Start 11 2 Fully Withdrawn at 230 Steps Control Bank A 0 Start 11 6 230 Stop 230 230 230 230 Control Bank B 0

0 Start 114 11 6 230 Stop 230 230 Control Control Bank C Ba nk D 0

0 0

0 0

0 0 Start 0

11 4 0

11 6 0 Start 230 Stop 11 4 Fully Withdrawn at 223 Steps Control BankA 0 Start 11 6 223 Stop 223 223 223 223 Control Bank B 0

0 Start 107 11 6 223 Stop 223 223 Control Bank C 0

0 0

0 Start 107 11 6 223 Stop Control Bank D 0

0 0

0 0

0 Start 107 Fully Withdrawn at 225 Steps Control Ba nk A 0 Start 11 6 225 Stop 225 225 225 225 Control Bank B 0

O Start 109 11 6 225 Stop 225 225 Control Bank C 0

0 0

0 Start 109 11 6 225 Stop Control Bank D 0

0 0

0 0

0 Start 109 Fully Withdrawn at 227 Steps Control Ba nk A 0 Start 11 6 227 Stop 227 227 227 227 Control Bank B 0

0 Start I l l 11 6 227 Stop 227 227 Control Bank C 0

0 0

0 Start Ill 11 6 227 Stop Control Bank D 0

0 0

0 0

0 Start II I Fully Withdrawn at 229 Steps Control Bank A 0 Start 11 6 229 Stop 229 229 229 229 Control Bank B 0

0 Start 113 11 6 229 Stop 229 229 Control BankC 0

0 0

0 Start 11 3 11 6 229 Stop Control Bank D 0

0 0

0 0

0 Start 11 3 Fully Withdrawn at 231 Steps Control Bank A 0 Start 11 6 23 1 Stop 23 1 23 1 23 1 23 1 Control Bank B 0

0 Start 11 5 11 6 23 1 Stop 23 1 23 1 Control BankC 0

0 0

O Start 11 5 11 6 23 1 Stop Control Bank D 0

0 0

0 0

0 Start 115 CNEI-0400-310 Page 13 Revision 0

Catawba 1 Cycle 24 Core Operating Limits Report CNEI-0400-310 Page 14 Revision 0 2.6 Heat Flux Hot Channel Factor - FQ(X,Y,Z) (TS 3.2.1) 2.6.1 FQ(X,Y,Z) steady-state limits are defined by the following relationships:

where, F RTP *K(Z)/P Q

F ~TP *K(Z)/0.5 P = (Thermal Power)/(Rated Power) for P > 0.5 for P ~ 0.5 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 limit. The manufacturing tolerance and measurement uncertainty are implicitly included in the FQ surveillance limits as defined for COLR Sections 2.6.5 and 2.6.6.

RTP 2.6.2 F Q

= 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 of burnup. 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 burnups.

The following parameters are required for core monitoring per the Surveillance Requirements of Technical Specification 3.2. l:

2.6.5 L

Fg(X,Y,Z)

• MQ(X,Y,Z)

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

UMT *MT* TILT where:

[F~, (X,Y,Z)]OP = Cycle dependent maximum allowable design peaking factor Ft (X,Y,Z) that ensures FQ(X,Y,Z) LOCA limit is not exceeded for operation within the AFD, RIL, and QPTR limits.

F~ (X,Y,Z) 0 r includes allowances for calculation and measurement uncertainties.

Design power distribution for FQ. Ft (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.

2.6.6 CNEI-0400-310 Page 15 Revision 0 Catawba 1 Cycle 24 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 that accounts for allowable quadrant power tilt ratio of 1.02. (TILT = 1.035)

L RPS Fg(X,Y,Z)

• Mc(X,Y,Z)

[FQ(X,Y,Z)]

=

UMT

• MT* TILT where:

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

[F~(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 24 Core Operating Limits Report 2.6.7 KSLOPE = 0.0725 where:

CNEI-0400-310 Page 16 Revision 0 KSLOPE = Adjustment to Ki value from OT~T trip setpoint required to RPS compensate for each 1 % F;1 (X,Y,Z) exceeds F~ (X,Y,Z) 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.

Catawba 1 Cycle 24 Core Operating Limits Report Figure 4 K(Z), Normalized FQ(X,Y,Z) as a Function of Core Height for Westinghouse RFA Fuel CNEI-0400-310 Page 17 Revision 0 1.200 ~---------------------------

(0.0, 1.00)

( 4.0, 1.00) 1.000..,__ ______

0.800

@: 0.600

~

0.400 0.200 0.000 0.0 Core Height (ft~

0.0

4

>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 24 Core Operating Limits Report Table 2 FQ(X,Y,Z) and F6tt(X,Y) Penalty Factors CNEI-0400-3 I 0 Page 18 Revision 0 For Technical Specification Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2 Burn up (EFPD) 4 12 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 400 425 450 475 490 506 516 521 531 541 FQ(X,Y,Z)

Penalty Factor(%)

2.00 2.01 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 2.00 2.00 F,rn(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 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 FQ(X,Y,Z) and F L\\H(X,Y) for compliance with the Technical Specification Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2.

Catawba 1 Cycle 24 Core Operating Limits Report CNEI-0400-310 Page 19 Revision 0 2.7 Nuclear Enthalpy Rise Hot Channel Factor - F AfI(X,Y) (TS 3.2.2)

F ~H steady-state limits referred to in Technical Specification 3.2.2 are defined by the fo llowing relationship.

where:

[F; H (X, Y)]Lco is 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.

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

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

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

2.7.2 L

SURV

[F~1-1 (X,Y)]

F~~ (X, Y)

• M ~H (X, Y)

UMR *TILT where:

SURV

[F~ (X,Y)]

=

Cycle dependent maximum allowable design peaking factor that ensures the F tt<X,Y) limit is not exceeded for operation SURV withi n the AFD, RIL, and QPTR limits. F~ (X,Y) includes allowances for calculation and measurement uncertainty.

F~H (X,Y) = Design radial power distribution for F ~H* 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.

Catawba 1 Cycle 24 Core Operating Limits Report CNEI-0400-310 Page 20 Revision 0 M H(X, Y) =Margin remaining in core location X, Y relative to Operational DNB limits in the transient power distribution.

MAfI(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 = I.0).

UMR is set to 1.0 since a factor of I.04 is implicitly included in the variable M ~iX, 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 0Ti6.T K 1 setpoint required to compensate for each 1 % that the measured radial peak, F:H (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 Axial Flux Difference (AFD) Limits are provided in Figure 5.

Core Height ft 1.05 I.I 0.12 1.8092 1.8553 1.20 1.8102 1.8540 2.40 1.8093 1.8525 3.60 1.8098 1.85 14 4.80 1.8097 1.85 14 6.00 1.8097 1.85 14 7.20 1.8070 1.8438 8.40 1.8073 1.83 19 9.60 1.8072 1.8 102 10.80 1.7980 1.7868 11.40 1.7892 1.7652 Catawba 1 Cycle 24 Core Operating Limits Report Table 3 Maximum Allowable Radial Peaks (MARPs)

RFAMARPs Axial Peak 1.2 1.3 J.4 1.5 1.6 1.7 1.8 1.9248 1.9146 1.9 179 2.062 1 2.0498 2.0090 1.9333 1.9248 1.9 146 1.9179

2. 1073 2.019 1 1.9775 1.9009 1.93 12 1.9146 1.9179 2.0735 1.9953 1.95 19 1.8760 1.9204 1.9146 1.9 179 2.0495 1.9656 1.9258 1.8524 1.9058 1.9146 1.9179 2.0059 1.9441 1.9233 1.8538 1.892 1 1.92 12 1.9179 1.9336 1.8798 1.8625 1.8024 1.87 16 1.8930 1.8872 1.8723 1.8094 1.7866 1.7332 1.8452 1.857 1 1.8156 I. 7950 1.7359 1.7089 1.6544 1.8093 1.7913 1.7375 1.7182 1.6572 1.6347 1.5808 I. 76 11 1.71 63 1.6538 1.63 15 1.5743 1.5573 1.5088 1.7250 1.6645 1.6057 1.5826 1.5289 1.5098 1.4637 1.9 1.8625 1.8306 1.8054 1.7855 1.7836 1.7472 1.68 12 1.60 I 0 1.530 I 1.4624 1.42 18 CNEI-0400-3 10 Page 21 Revision 0 2.1 3

1.7780 1.3 151 1.7852 1.3007 I. 7320 1.4633 1.6996 1.4675 1.67 14 1.2987 1.6705 1.3293 1.5982 1.2871 1.5127 1.2182 1.4444 1.1 43 1 1.3832 I.I 009 1.3458 1.0670 3.25 1.246 1 1.2235 1.46 16 1.3874 1.2579 1.2602 1.2 195 1.1 578 1.09 14 1.0470 1.0142

Q)

i

:

0

'1..

Cii E Q)

...c:

f-

-0 Q)

'(;J 0:::

'+-<

0 E

Q)

(.)

Q)

'1..

CNEI-0400-310 Page 22 Revision 0 Catawba 1 Cycle 24 Core Operating Limits Report Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits

(-20, 100)

(+10, 100)

Unacceptable Operation Unacceptable Operation 90 80 70 Acceptable Operation 60

(-36, 50) 50

(+21, 50) 40 30 20 10

-50

-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 24 Core Operating Limits Report CNEI-0400-310 Page 23 Revision 0 2.9 Reactor Trip System Instrumentation Setpoints (TS 3.3.1) Table 3.3.1-1 2.9.1 Overtemperature LiT Setpoint Parameter Values Parameter Nominal Tavg at RTP Nominal RCS Operating Pressure Overtemperature.0.T reactor trip setpoint Overtemperature.0.T reactor trip heatup setpoint penalty coefficient Overtemperature.0.T reactor trip depressurization setpoint penalty coefficient Time constants utilized in the lead-lag compensator for.0.T Time constant utilized in the lag compensator for.0.T Time constants utilized in the lead-lag compensator for Tavg Time constant util ized in the measured Tavs lag compensator ft (.0.1) "positive" breakpoint ft (.0.1) "negative" breakpoint ft (.0.l) "positive" slope ft (.0.1) "negative" slope Nominal Value T' :S 585.1 °f P' = 2235 psig K1=1.1978 K2 = 0.033401°F K3 = 0.001 6011psi

• 1 = 8sec.

'2 = 3 sec.

• 3 = 0 sec.

<:4 = 22 sec.

<:5 = 4 sec.

'6 = 0 sec.

= 19.0%.0.l

= NIA*

= 1.769 %.0.T01 %.0.l

= NIA*

f1 (61) negative breakpoints and slopes for OT6T are less restrictive than the OP~T f2(~1) negative breakpoint and slope. Therefore, during a transient which challenges the negative imbalance limits, OP6T f2(6J) limits wi ll result in a reactor trip before OT~T f1 (61) limits are reached. This makes implementation of an OT ~T f1 (M) negative breakpoint and slope unnecessary.

CNEI-0400-310 Page 24 Revision 0 Catawba 1 Cycle 24 Core Operating Limits Report 2.9.2 Overpower ~T Setpoint Parameter Values Parameter Nominal Tavg at RTP Overpower ~T reactor trip setpoint Overpower ~T reactor trip penalty Overpower ~T reactor trip heatup setpoint penalty coefficient Time constants utilized in the lead-lag compensator for ~T Time constant utilized in the lag compensator for ~T Time constant utilized in the measured Tavg lag compensator Time constant utilized in the rate-lag controller for Tavg fz(~I) "positive" breakpoint fz(M) "negative" breakpoint fz(~I) "positive" slope fz(~I) "negative" slope Nominal Value T" :S 585.1 °P

~

= 1.0864 Ks = 0.02 I 0 P for increasing Tavg Ks= 0.00 I 0 P for decreasing Tavg K6 = 0.001l79/

0 P for T > T" K6 = 0.0 !

0 P for T :::; T"

'tt = 8 sec.

't2 = 3 sec.

't3 = 0 sec.

't6 = 0 sec.

't7 = 10 sec.

= 35.0 %~1

= -35.0 %~1

= 7.0 %~Toi %~1

= 7.0 %~Toi %~1

Catawba 1 Cycle 24 Core Operating Limits Report 2.10 Boron Dilution Mitigation System - BDMS (TS 3.3.9) 2.10.1 Reactor Makeup Water Pump combined flow rate limits:

Applicable MODE MODE 3 MODE 4 or 5

< 80 gpm

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

CNEI-0400-310 Page 25 Revision 0 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 Applicable Burnup Limit Accumulator minimum boron concentration.

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

200.1 - 250 EFPD 2,500 ppm Accumulator minimum boron concentration.

250.1 - 300 EFPD 2,466 ppm Accumulator minimum boron concentration.

300.1 - 350 EFPD 2,349 ppm Accumulator minimum boron concentration.

350.1 - 400 EFPD 2,260 ppm Accumulator minimum boron concentration.

400.1 - 450 EFPD 2, 186 ppm Accumulator minimum boron concentration.

450.1 - 490 EFPD 2, 111 ppm Accumulator minimum boron concentration.

490.1-531 EFPD 2,053 ppm Accumulator minimum boron concentration.

531.1 - 541 EFPD 1,988 ppm Accumulator maximum boron concentration.

0 - 541 EFPD 3,075 ppm I

Catawba 1 Cycle 24 Core Operating Limits Report Table 4 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-0400-310 Page 26 Revision 0 LIMITS

'S 587.2 °F

'S 586.9 °F

'S 587.7 °F

'S 587.5 °F 2: 2209.8 psig 2: 2212.1 psig 2: 2205.8 psig 2: 2207.5 psig 2: 388,000 gpm

Catawba 1 Cycle 24 Core Operating Limits Report 2.13 Refueling Water Storage Tank - RWST (TS 3.5.4) 2.13.1 Boron concentration limits during MODES l, 2, 3, and 4:

Parameter R WST minimum boron concentration.

R WST maximum boron concentration.

2.14 Spent Fuel Pool Boron Concentration (TS 3.7.15)

CNEI-0400-310 Page 27 Revision 0 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 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 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 the MODE 6 reactivity requirement of Keff :'.S 0.95.

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

2,700 ppm

CNEI-0400-310 Page 28 Revision 0 Catawba 1 Cycle 24 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°F, and MODES 5 and 6.

Parameter Limit NOTE: When cycle burnup is ~ 481 EFPD, Figure 6 may be used to determine the required BAT Minimum Level.

BAT minimum boron concentration Volume of 7,000 ppm boric acid solution required to maintain SOM at 68°F BAT Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-11)

R WST minimum boron concentration Volume of 2,700 ppm boric acid solution required to maintain SDM at 68 °F RWST Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-11) 7,000 ppm 2,000 gallons 13,086 gallons (14.9%)

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

CNEI-0400-310 Page 29 Revision 0 Catawba 1 Cycle 24 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 l, 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 NOTE: When cycle burnup is 2: 481 EFPD, Figure 6 may be used to determine the required BAT Minimum Level.

BAT minimum boron concentration Volume of 7,000 ppm boric acid solution required to maintain SOM at 210°F BAT Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-12)

R WST minimum boron concentration Volume of 2,700 ppm boric acid solution required to maintain SDM at 210 °F R WST Minimum Shutdown Volume (lncludes the additional volumes listed in SLC 16.9-12) 7,000 ppm 13,500 gallons 25,200 gallons (45.8%)

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

50.0 45.0 40.0 35.0

~ 30.0

~

~

~ 25.0 Q) >

Q)

_J

!;;: 20.0 III 15.0 10.0 5.0 0.0 Catawba 1 Cycle 24 Core Operating Limits Report Figure 6 Boric Acid Storage Tank Indicated Level Versus Primary Coolant Boron Concentration (Valid When Cycle Burnup is;::: 481 EFPD)

CNEI-0400-310 Page 30 Revision 0 This figure includes additional volumes listed in SLC 16.9-11 and 16.9-12 RCS Boron Concentration BAT Level I

(ppm)

(%level)

I 0 < 300 43.0 300 < 500 40.0 500 < 700 37.0 700 < 1000 30.0 1000 < 1300 14.9 1300 < 2700 9.8

> 2700 9.8 Unacceptable Operation Acceptable Operation 0

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

Catawba 1 Cycle 24 Core Operating Limits Report Appendix A Power Distribution Monitoring Factors CNEI-0400-310 Page 31 Revision 0 Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. This data was generated in the Catawba I Cycle 24 Maneuvering Analysis calculation file, CNC-1553.05-00-0650. 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 Electrical and Reactor Systems Engineering Section controls monitoring factors via computer files and should be contacted ifthere is a need to access this information.

Appendix A is included in the COLR copy transmitted to the NRC.