ML16356A277

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Catawba 2 Cycle 22, Core Operating Limits Report, Rev 0, QA Condition 1, Part 1 of 2
ML16356A277
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Issue date: 09/30/2016
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Office of Nuclear Reactor Regulation
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References
CNC-1553.05-00-0645, Rev 0, CNEI-0400-304, CNS-16-070
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CNEI-0400-304 Page 1 Revision 0

Catawba 2 Cycle 22 Core Operating Limits Report Revision 0

September 2016

Reference:

CNC-1553.05-00-0645, Rev. 0

QA CONDITION 1

The information presented in this report has been prepared and issued in accordance with Cata wba Technical Specification 5.6.5.

CNEI-0400-304 Page 2 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

Implementation Instructions for Revision 0

Revision Description and CR Tracking

Revision 0 of the Catawba Unit 2 Cycle 22 COLR contains limits specific to the reload core.

There is no CR associated with this revision.

Implementation Schedule

The Catawba Unit 2 Cycle 22 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 21 and 22 but must become effective prior to entering MODE 6 wh ich starts cycle 22. The Catawba Unit 2 Cycle 22 COLR will cease to be e ffective during No MODE between cycle 22 and 23.

Data files to be Implemented

No data files are transmitted as part of this document.

CNEI-0400-304 Page 3 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

REVISION LOG Revision Effective Date Pages Affected COLR 0 September 2016 1-31, Appendix A* C2C22 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.

CNEI-0400-304 Page 4 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

1.0 Core Operating Limits Report

This Core Operating Limits Report (COLR) has been prepared in accordance with requirements of Technical Specification 5.6.5. Te chnical 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. TS Section Technical Specifications COLR Parameter COLR Section NRC Approved Methodology (Section 1.1 Number) 2.1.1 Reactor Core Safety Limits RCS Temperature and Pressure Safety Limits 2.1 6, 7, 8, 9, 10, 12, 15, 16 3.1.1 Shutdown Margin Shutdown Margin 2.2 6, 7, 8, 12, 14, 15, 16 3.1.3 Moderator Temperature Coefficient MTC 2.3 6, 7, 8, 12, 14, 16, 18 3.1.4 Rod Group Alignment Limits Shutdown Margin 2.2 6, 7, 8, 12, 14, 15, 16 3.1.5 Shutdown Bank Insertion Limit Shutdown Margin 2.2 2, 4, 6, 7, 8, 9, Rod Insertion Limits 2.4 10, 12, 14, 15, 16 3.1.6 Control Bank Insertion Limit Shutdown Margin 2.2 2, 4, 6, 7, 8, 9, Rod Insertion Limits 2.5 10, 12, 14, 15, 16 3.1.8 Physics Tests Exceptions Shutdown Margin 2.2 6, 7, 8, 12, 14, 15, 16 3.2.1 Heat Flux Hot Channel Factor F Q 2.6 2, 4, 6, 7, 8, 9, 10, AFD 2.8 12, 15, 16 OTT 2.9 Penalty Factors 2.6 3.2.2 Nuclear Enthalpy Rise Hot Channel FH 2.7 2, 4, 6, 7, 8, 9, Factor Penalty Factors 2.7 10, 12, 15, 16 3.2.3 Axial Flux Difference AFD 2.8 2, 4, 6, 7, 8, 15, 16 3.3.1 Reactor Trip System Instrumentation OTT 2.9 6, 7, 8, 9, 10, 12, OPT 2.9 15, 16 3.3.9 Boron Dilution Mitigation System Reactor Makeup Water Flow Rate 2.10 6, 7, 8, 12, 14, 16 3.4.1 RCS Pressure, Temperature and Flow limits for DNB RCS Pressure, Temperature and Flow 2.11 6, 7, 8, 9, 10, 12 3.5.1 Accumulators Max and Min Boron Conc. 2.12 6, 7, 8, 12, 14, 16 3.5.4 Refueling Water Storage Tank Max and Min Boron Conc. 2.13 6, 7, 8, 12, 14, 16 3.7.15 Spent Fuel Pool Boron Concentration Min Boron Concentration 2.14 6, 7, 8, 12, 14, 16 3.9.1 Refueling Operations - Boron Concentration Min Boron Concentration 2.15 6, 7, 8, 12, 14, 16 5.6.5 Core Operating Limits Report (COLR) Analytical Methods 1.1 None

The Selected License Commitments that reference this report are listed below SLC Section Selected Licensing Commitment COLR Parameter COLR Section NRC Approved Methodology (Section 1.1 Number) 16.7-9 Standby Shutdown System Standby Makeup Pump Water Supply 2.16 6, 7, 8, 12, 14, 1616.9-11 Boration Systems - Borated Water Source - Shutdown Borated Water Volume and Conc. for BAT/RWST 2.17 6, 7, 8, 12, 14, 1616.9-12 Boration Systems - Borated Water Source - Operating Borated Water Volume and Conc. for BAT/RWST 2.18 6, 7, 8, 12, 14, 16

CNEI-0400-304 Page 5 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

1.1 Analytical

Methods

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 for C2C22

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 COSI Condensation Model," (W 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", (W Proprietary).

Revision 2 Report Date: March 1987 Not Used for C2C22

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 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 for C2C22 CNEI-0400-304 Page 6 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

1.1 Analytical

Methods (continued)

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

Revision 5a Report Date: October 2012

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

Revision 1 Report Date: March 2015

Note: The dropped rod accident remains evaluated under the previous version of DPC-NE-3001:

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

Revision 0a Report Date: May 2009

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

Revision 4b Report Date: September 2010

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 4a Report Date: December 2008

11. DPC-NE-2008-PA, "Fuel Mechanical Reload Analysis Methodology Using TACO3," (DPC Proprietary).

Revision 1a Report Date: December 2008 Not Used for C2C22

CNEI-0400-304 Page 7 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

1.1 Analytical

Methods (continued)

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

Revision 3b Report Date: September 2016

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

Revision 1a Report Date: January 2009 Not Used for C2C22

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 for Core Operating Limits of Westinghouse Reactors," (DPC Proprietary).

Revision 1a Report Date: June 2009

16. DPC-NE-1005-PA, "Duke Power Nuclear Design Methodology Using CASMO-4 / SIMULATE-3 MOX", (DPC Proprietary).

Revision 1 Report Date: November 12, 2008

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

Revision 1 SER Date: January 14, 2004 Not Used for C2C22

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

(DPC and W Proprietary)

Revision 0 Report Date: April 2015

CNEI-0400-304 Page 8 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

2.0 Operating

Limits

Cycle-specific parameter limits for specificati ons 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 grea ter 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, SDM shall be grea ter than or equal to 1.0% K/K in MODE 5.

2.2.3 For TS 3.1.4, SDM shall be grea ter than or equal to 1.3% K/K in MODE 1 and MODE 2. 2.2.4 For TS 3.1.5, SDM shall be grea ter than or equal to 1.3% K/K in MODE 1 and MODE 2 with any control bank not fully inserted.

2.2.5 For TS 3.1.6, SDM shall be grea ter than or equal to 1.3% K/K in MODE 1 and MODE 2 with Keff > 1.0.

2.2.6 For TS 3.1.8, SDM shall be grea ter than or equal to 1.3% K/K in MODE 2 during PHYSICS TESTS.

CNEI-0400-304 Page 9 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

Figure 1 Reactor Core Safety Limits Four Loops in Operation 580 590 600 610 620 630 640 650 660 6700.00.20.40.60.81.01.2Fraction of Rated Thermal PowerRCS Tavg (°F)DO NOT OPERATE IN THIS AREA2100 psia2280 psia2400 psia1945 psiaACCEPTABLE OPERATION CNEI-0400-304 Page 10 Revision 0 Catawba 2 Cycle 22 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 K/K/°F. EOC, ARO, RTP MTC shall be less negative than the -4.3E-04 K/K/°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 K/K/°F. 2.3.3 The Revised Predicted near-EOC 300ppm 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 3.1.3.2 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 K/K/°F. Where: BOC = Beginning of Cycle (burnup 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. Shutdown banks are withdrawn in sequence and with no overlap.

2.5 Control

Bank Insert ion Limits (TS 3.1.6)

2.5.1 Control

banks shall be with in 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.

CNEI-0400-304 Page 11 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

Figure 2 Moderator Temperature Coefficient Upper Limit Versus Power Level NOTE: Compliance with Technical Specification 3.1.3 may require rod withdrawal limits. Refer to the Unit 2 ROD manual for details.

0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.00102030405060708090100Moderator Temperature Coefficient (1.0E-04 K/K/F)Percent of Rated Thermal Power Unacceptable Operation Acceptable Operation CNEI-0400-304 Page 12 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

Figure 3 Control Bank Insertion Limits Versus Percent Rated Thermal Power The Rod Insertion Limits (RIL) for Cont rol 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 < 100}

Bank CC RIL = 2.3(P) +47 {0 < P < 76.1} for CC RIL = 222 {76.1 < P < 100}

Bank CB RIL = 2.3(P) +163 {0 < P < 25.7} for CB RIL = 222 {25.7 < P < 100}

where P = % 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.

0 20 40 60 80100 120 140 160 180 200 2200102030405060708090100 Rod Insertion Position (Steps Withdrawn)Percent of Rated Thermal Power Fully Withdrawn(Maximum = 231) 231Control Bank BControl Bank CControl Bank D(0%, 163)(0%, 47)(30%, 0)(100%, 161)Fully Inserted Fully Withdrawn(Minimum = 222)

CNEI-0400-304 Page 13 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

Table 1 Control Bank Withdrawal Steps and Sequence ControlControlControlControlControlControlControlControlBank ABank BBank CBank DBank ABank BBank CBank D0 Start0000 Start0001160 Start001160 Start00222 Stop10600223 Stop107002221160 Start02231160 Start0 222222 Stop1060223223 Stop1070 2222221160 Start2232231160 Start 222222222 Stop106223223223 Stop107ControlControlControlControlControlControlControlControlBank ABank BBank CBank DBank ABank BBank CBank D0 Start0000 Start0001160 Start001160 Start00224 Stop10800225 Stop109002241160 Start02251160 Start0 224224 Stop1080225225 Stop1090 2242241160 Start2252251160 Start 224224224 Stop108225225225 Stop109ControlControlControlControlControlControlControlControlBank ABank BBank CBank DBank ABank BBank CBank D0 Start0000 Start0001160 Start001160 Start00226 Stop11000227 Stop111002261160 Start02271160 Start0 226226 Stop1100227227 Stop1110 2262261160 Start2272271160 Start 226226226 Stop110227227227 Stop111ControlControlControlControlControlControlControlControlBank ABank BBank CBank DBank ABank BBank CBank D0 Start0000 Start0001160 Start001160 Start00228 Stop11200229 Stop113002281160 Start02291160 Start0 228228 Stop1120229229 Stop1130 2282281160 Start2292291160 Start 228228228 Stop112229229229 Stop113ControlControlControlControlControlControlControlControlBank ABank BBank CBank DBank ABank BBank CBank D0 Start0000 Start0001160 Start001160 Start00230 Stop11400231 Stop115002301160 Start02311160 Start0 230230 Stop1140231231 Stop1150 2302301160 Start2312311160 Start 230230230 Stop114231231231 Stop115Fully Withdrawn at 222 StepsFully Withdrawn at 223 Steps Fully Withdrawn at 224 StepsFully Withdrawn at 225 Steps Fully Withdrawn at 226 StepsFully Withdrawn at 227 Steps Fully Withdrawn at 230 StepsFully Withdrawn at 231 Steps Fully Withdrawn at 228 StepsFully Withdrawn at 229 Steps

CNEI-0400-304 Page 14 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

2.6 Heat Flux Hot Channel Factor - F Q(X,Y,Z) (TS 3.2.1)

2.6.1 F Q(X,Y,Z) steady-state limits are defined by the following relationships:

F*K(Z)/P for P > 0.5 F*K(Z)/0.5 for P < 0.5

where, Note: Measured F Q(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 F Q surveillance limits as defined in COLR Sections 2.6.5 and 2.6.6.

2.6.2 F = 2.70 x K(BU) 2.6.3 K(Z) is the normalized F Q (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 F Q (X,Y,Z) as a function of burnup. F RTP Q with the K(BU) penalty for Westinghouse RFA fuel is analytically confirmed in cycle-specific reload calculation. K(BU) is set to 1.0 at all burnups.

RTP Q RTP QP = Thermal PowerRated Thermal Power RTP Q CNEI-0400-304 Page 15 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

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

2.6.5 [F L Q (X,Y,Z)]OP = F D Q (X,Y,Z)

  • M Q (X,Y,Z)UMT
  • TILT where: [(X,Y,Z)]OP = Cycle dependent maximum a llowable design peaking factor that ensures F Q(X,Y,Z) LOCA limit is not exceeded for operation within AFD, RIL, and QPTR limits.

L Q F (X,Y,Z)OP includes allowances for calculation and measurement uncertainties.

(X,Y,Z) = Design power distribution for F Q. (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.

M Q(X,Y,Z) = Margin remaining in core location X,Y,Z to the LOCA limit in the transient power distribution. M Q (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 accoun t for allowable quadrant power tilt ratio of 1.02. (TILT = 1.035) 2.6.6 [F L Q (X,Y,Z)]RPS = F D Q (X,Y,Z)

  • M C (X,Y,Z)UMT
  • TILT where: [F L Q (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.

[F L Q (X,Y,Z)]RPS includes allowances for calculation and measurement uncertainties.

L Q F D Q F D Q F CNEI-0400-304 Page 16 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

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

M C(X,Y,Z) = Margin remaining to the CFM limit in core location X,Y,Z from the transient power distribution. M C (X,Y,Z) is provided in Appendix Table A-2 for norma l 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.

2.6.7 KSLOPE

= 0.0725

where:

KSLOPE = adjustment to K 1 value from OTT trip setpoint required to compensate for each 1% measured (X,Y,Z) exceeds [(X,Y,Z)]

RPS. 2.6.8 F Q (X,Y,Z) Penalty Factors for Technical Specification Surv eillances 3.2.1.2 and 3.2.1.3 are provided in Table 2.

M Q F L Q F CNEI-0400-304 Page 17 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

Figure 4 K(Z), Normalized F Q(X,Y,Z) as a Function of Core Height for RFA Fuel (0.0,1.00)(4.0,1.00)(4.0,0.9259)(12.0,0.9259)0.000 0.200 0.400 0.600 0.800 1.000 1.2000.02.04.06.08.010.012.0 K(Z)CoreHeight(ft)CoreHeight (ft)

K(Z)______________________________________________________________________________________

0.0 1.000<41.000>40.9259 12 0.9259______________________________________________________________________________________

CNEI-0400-304 Page 18 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

Table 2 F Q(X,Y,Z) and FH(X,Y) Penalty Factors For Tech Spec Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2

Burnup F Q(X,Y,Z) FH (X,Y) (EFPD) Penalty Factor(%) Penalty Factor (%) 4 2.00 2.00 12 2.00 2.00 25 2.00 2.00 50 2.00 2.00 75 2.00 2.00 100 2.00 2.00 125 2.00 2.00 150 2.00 2.00 175 2.00 2.00 200 2.00 2.00 225 2.00 2.00 250 2.00 2.00 275 2.00 2.00 300 2.00 2.00 325 2.00 2.00 350 2.00 2.00 375 2.00 2.00 400 2.00 2.00 425 2.00 2.00 450 2.00 2.00 475 2.00 2.00 485 2.00 2.00 499 2.00 2.00 504 2.00 2.00 514 2.00 2.00 524 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 F Q (X,Y,Z) and FH(X,Y) for compliance with Tech Spec Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2.

CNEI-0400-304 Page 19 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

2.7 Nuclear

Enthalpy Rise Hot Channel Factor - FH (X,Y) (TS 3.2.2)

FH steady-state limits referred to in Tec hnical Specification 3.2.2 are defined by the following relationship.

2.7.1 = MARP (X,Y)

  • 1.0 + 1 RRH * (1.0 - P)

where: 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. RRH = Thermal Power reduction required to compensate for each 1% measured radial peak, (X,Y), exceeds the limit. (RRH = 3.34, 0.0 < P < 1.0)

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

2.7.2 [(X,Y)]SURV =

where:

[(X,Y)]SURV = Cycle dependent maximum allowable design peaking factor that ensures FH(X,Y) limit is not exceeded for operation within AFD, RIL, and QPTR limits. (X,Y)

SURV includes allowances for calculational and measurement uncertainty.

F D H (X,Y) = Design power distribution for FH. F DH (X,Y) is provided in Appendix Table A-3 for norma l operation and in Appendix Table A-6 for power escalation testing during initial startup operation.

LCO L H Y)](X,[FLCO L H Y)](X,[FP = Thermal PowerRated Thermal Power M H FL H FTILT*UM R Y)(X, M*Y)(X, F H D HL H FL H F CNEI-0400-304 Page 20 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

MH(X,Y) = Margin remaining in core location X,Y relative to the Operational DNB limits in th e transient power distribution.

MH(X,Y) is provided in Appendix Table A-3 for normal operation and in Appendix Table A-6 for power escalation testing during initia l 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 MH (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 OTT K 1 setpoint required to compensate for each 1% measured radial peak, (X,Y) exceeds its limit.

2.7.5 FH (X,Y) Penalty Factors for Technical Specification Surv eillance 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) Lim its are provided in Figure 5.

M H F CNEI-0400-304 Page 21 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

Table 3 Maximum Allowable Radial Peaks (MARPs)

RFA Fuel MARPs 100% Full Power

1.051.11.21.31.41.51.61.71.81.92.133.250.121.80921.85531.92481.91461.91792.06212.04982.00901.93331.86251.77801.31511.24611.201.81021.85401.92481.91461.91792.10732.01911.97751.90091.83061.78521.30071.22352.401.80931.85251.93121.91461.91792.07351.99531.95191.87601.80541.73201.46331.46163.601.80981.85141.92041.91461.91792.04951.96561.92581.85241.78551.69961.46751.38744.801.80971.85141.90581.91461.91792.00591.94411.92331.85381.78361.67141.29871.25796.001.80971.85141.89211.92121.91791.93361.87981.86251.80241.74721.67051.32931.26027.201.80701.84381.87161.89301.88721.87231.80941.78661.73321.68121.59821.28711.21958.401.80731.83191.84521.85711.81561.79501.73591.70891.65441.60101.51271.21821.15789.601.80721.81021.80931.79131.73751.71821.65721.63471.58081.53011.44441.14311.091410.801.79801.78681.76111.71631.65381.63151.57431.55731.50881.46241.38321.10091.047011.401.78921.76521.72501.66451.60571.58261.52891.50981.46371.42181.34581.06701.0142Axial PeakCore Height (ft)

CNEI-0400-304 Page 22 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits

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.

0 10 20 30 40 50 60 70 80 90 100-50-40-30-20-1001020304050Percent of Rated Thermal PowerAxial Flux Difference (% Delta I)

(+10, 100)

(-20, 100)

(-36, 50)(+21, 50)Acceptable Operation Unacceptable Operation Unacceptable Operation CNEI-0400-304 Page 23 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

2.9 Reactor

Trip System Instrumentat ion Setpoints (TS 3.3.1) Table 3.3.1-1

2.9.1 Overtemperature

T Setpoint Parameter Values Parameter Nominal Value Nominal Tavg at RTP T' < 590.8 °F

Nominal RCS Operating Pressure P' = 2235 psig

Overtemperature T reactor trip setpoint K 1 = 1.1953 Overtemperature T reactor trip heatup setpoint penalty coefficient

K 2 = 0.03163/

o F Overtemperature T reactor trip depressurization setpoint penalty coefficient

K 3 = 0.001414/psi Time constants utilized in the lead-lag compensator

for T 1 = 8 sec. 2 = 3 sec.

Time constant utilized in the lag compensator for T 3 = 0 sec.

Time constants utilized in the lead-lag compensator

for T avg 4 = 22 sec. 5 = 4 sec. Time constant utilized in the measured T avg lag compensator

6 = 0 sec.

f 1 (I) "positive" breakpoint

= 3.0 %I f 1 (I) "negative" breakpoint

= N/A* f 1 (I) "positive" slope

= 1.525 %T 0/ %I f 1 (I) "negative" slope

=

  • f 1 (I) negative breakpoints and slopes for OTT are less restrictive than OPT f 2 (I) negative breakpoint and slope. Therefore, during a transient which challenges negative imbalance limits, OPT f 2 (I) limits will result in a reactor trip before OTT f 1 (I) limits are reached. This makes implementation of an OTT f 1 (I) negative breakpoint and slope unnecessary.

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2.9.2 Overpower

T Setpoint Parameter Values Parameter Nominal Value Nominal Tavg at RTP T" < 590.8 ºF

Overpower T reactor trip setpoint K 4 = 1.0819 Overpower T reactor trip penalty K 5 = 0.02 / °F for increasing Tavg K 5 = 0.00 / °F for decreasing Tavg

Overpower T reactor trip heatup setpoint penalty coefficient

K 6 = 0.001291/

o F for T > T

K 6 = 0.0 /°F for T < T Time constants utilized in the lead-lag compensator for T 1 = 8 sec. 2 = 3 sec.

Time constant utilized in the lag compensator for T 3 = 0 sec. Time constant utilized in the measured T avg lag compensator

6 = 0 sec. Time constant utilized in the rate-lag controller for T avg 7 = 10 sec.

f 2 (I) "positive" breakpoint

= 35.0 %I f 2 (I) "negative" breakpoint

= -35.0 %I f 2 (I) "positive" slope

= 7.0 %T 0/ %I f 2 (I) "negative" slope

= 7.0 %T 0/ %I

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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 < 80 gpm MODE 4 or 5 < 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)

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 2,435 ppm Accumulator minimum boron concentration. 300.1 - 350 EFPD 2,330 ppm Accumulator minimum boron concentration. 350.1 - 400 EFPD 2,251 ppm Accumulator minimum boron concentration. 400.1 - 450 EFPD 2,176 ppm Accumulator minimum boron concentration. 450.1 - 485EFPD 2,105 ppm Accumulator minimum boron concentration. 485.1 - 514 EFPD 2,057 ppm Accumulator minimum boron concentration. 514.1 - 524 EFPD 2,013 ppm Accumulator maximum boron concentration.

0 - 524 EFPD 3,075 ppm

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Table 4 Reactor Coolant System DNB Parameters PARAMETER INDICATION No. Operable CHANNELS LIMITS 1. Indicated RCS Average Temperature meter 4 589.6 ûF meter 3 589.3 ûF computer 4 590.1 ûF computer 3 589.9 ûF 2. Indicated Pressurizer Pressure meter 4 2209.8 psig meter 3 2212.1 psig computer 4 2205.8 psig computer 3 2207.5 psig 3. RCS Total Flow Rate 390,000 gpm

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2.13 Refueling Water Storage Ta nk - RWST (TS 3.5.4)

2.13.1 Boron concentration limits during MODES 1, 2, 3, and 4:

Parameter Limit RWST minimum boron concentration.

2,700 ppm RWST maximum boron concentration. 3,075 ppm

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 filled portions of the Reactor Coolant System, refueling canal, and refuelin g cavity for MODE 6 conditions. The minimum boron concentration limit and pl ant refueling procedures ensure that core Keff remains within 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

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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 Limit Spent fuel pool minimum boron concentration for TR

16.7-9.3.

2,700 ppm

2.17 Borated Water Source - Shutdown (SLC 16.9-11) 2.17.1 Volume and boron concentrations fo r the Boric Acid Tank (BAT) and the Refueling Water Storage Tank (RWST) dur ing MODE 4 with any RCS cold leg temperature < 210 o F, and MODES 5 and 6.

Parameter Limit BAT minimum boron concentration

7,000 ppm Volume of 7,000 ppm bori c acid solution required to maintain SDM at 68 o F 2000 gallons NOTE: When cycle burnup is > 453 EFPD, Figure 6 may be used to

determine required BAT minimum level. BAT Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-11) 13,086 gallons (14.9% level)

RWST minimum boron concentration

2,700 ppm Volume of 2,700 ppm bori c acid solution required to maintain SDM at 68 o F 7,000 gallons RWST Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-11) 48,500 gallons (8.7% level)

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2.18 Borated Water Source - Operating (SLC 16.9-12)

2.18.1 Volume and boron concentrations fo r 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 o F *.

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

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

Parameter Limit BAT minimum boron concentration

7,000 ppm Volume of 7,000 ppm bori c acid solution required to maintain SDM at 210 o F 13,500 gallons NOTE: When cycle burnup is > 453 EFPD, Figure 6 may be used to

determine required BAT minimum level. BAT Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-12) 25,200 gallons (45.8% level)

RWST minimum boron concentration

2,700 ppm Volume of 2,700 ppm bori c acid solution required to maintain SDM at 210 o F 57,107 gallons RWST Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-12) 98,607 gallons (22.0% level)

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Figure 6 Boric Acid Storage Tank Indicated Level Versus Primary Coolant Boron Concentration (Valid When Cycle Burnup is > 453 EFPD)

This figure includes additional volumes listed in SLC 16.9-11 and 16.9-12 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.00200400600800100012001400160018002000220024002600BAT Level (% Level)Primary Coolant Boron Concentration (ppmb)

Acceptable Operation Unacceptable Operation RCS BoronConcentrationBAT Level(ppm)(%level)0 < 30043.0300 < 50040.0 500 < 70037.0700 < 1000 30.01000 < 130014.9 1300 < 27009.8> 2700 9.8 CNEI-0400-304 Page 31 Revision 0 Catawba 2 Cycle 22 Core Operating Limits Report

Appendix A Power Distribution Monitoring Factors

Appendix A contains power distribution monitori ng factors used in T echnical Specification Surveillance. This data was generated in the Catawba 2 Cycle 22 Maneuvering Analysis calculation file, CNC-1553.05-00-0641. Due to the size of monitoring factor data, Appendix A is controlled electronically within Duke and is not included in Duke internal copies of the COLR.

Catawba Reactor and Electrical Systems Engineering controls monitoring factor via computer files and should be contacted if questions concerning this information arise.

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

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