View source for RA-23-0083, Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core, Rev. 2

{{Adams
| number = ML23075A154
| issue date = 03/16/2023
| title = Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core, Rev. 2
| author name = Flippin N
| author affiliation = Duke Energy Carolinas, LLC
| addressee name = 
| addressee affiliation = NRC/NRR, NRC/Document Control Desk
| docket = 05000414
| license number = NPF-052
| contact person = 
| case reference number = RA-23-0083
| document type = Fuel Cycle Reload Report, Letter type:RA
| page count = 1
}}

=Text=
{{#Wiki_filter:Nicole Flippin d_., DUKE                                                                                        Vice President
~ ENERGY                                                                            Catawba Nuclear Station Duke Energy CN01VP I 4800 Concord Road Y ork , SC 29745 o: 80 3.701 .3340 f : 803. 701 . 3221 Nicole .Flippin@d uke-energy .com RA-23-0083 March 29, 2023 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington , DC 20555-0001

==Subject:==
Duke Energy Carolinas , LLC (Duke Energy)
Catawba Nuclear Station, Unit 2 Facility Operating License Number NPF-52 Docket Number 50-414 Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core, Rev. 2 Pursuant to Catawba Technical Specification 5.6.5.d , please find attached an information copy of the subject revised (Revision 2) COLR.
The power distribution monitoring factors from Appendix A of Revision O remain valid and are not transmitted as part of Revision 2.
This letter and enclosed COLR do not contain any regulatory commitments .
Please direct any questions or concerns to Ari Tuckman , Regulatory Affairs, at (803) 701-3771.
Sincerely, Nicole Flippin Vice President, Catawba Nuclear Station Enclosure (Catawba Unit 2 Cycle 26 COLR, Rev. 2) www .duke -energy.com

U.S. Nuclear Regulatory Commission RA-23-0083 March 29, 2023 Page 12 xc (with enclosure):
L. Dudes, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, GA 30303-1257 Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station S. Williams, Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mailstop O-8B1A Rockville, MD 20852

U.S. Nuclear Regulatory Commission RA-23-0083 March 29, 2023 Page 13 bxc (with enclosure):
ELL-EC2ZF bxc (without enclosure):
M.B. Hare W. Murphy NCMPA-1 NCEMC PMPA

Enclosure Catawba Unit 2 Cycle 26 COLR, Rev. 1
{excluding Attachment A)

CNEI-0400-392 Page 1 Revision 2 Catawba 2 Cycle 26 Core Operating Limits Report Revision 2 March 2023

==Reference:==
CNC-1553 .05-00-0724, Rev. 2 Reload 50.59 #: 02445131 QA Condition 1 The information presented in this report has been prepared and issued in accordance with Catawba Technical Specification 5.6.5 .

CNEI-0400-392 Page2 Revision 2 Catawba 2 Cycle 26 Core Operating Limits Report Implementation Instructions for Revision 2 Revision Description and CR Tracking Revision 2 of the Catawba 2 Cycle 26 COLR contains limits specific to the reload core and is being revised to allow adoption of revised EOC MTC test exemption criteria in Revision 1 of DPC-NE-1007-P-A (COLR Reference 18). The rod repositioning schedule was also updated from Revision 8 to 9 to reflect current guidance.
There are no CRs associated with this revision. Actions required for implementation the EOC MTC Elimination methodology are being tracked in NTM 02388615.
Implementation Schedule Revision 2 shall become effective and implemented concurrently with implementation of Revision 4 to the Catawba 1 Cycle 27 Core Operating Limits Report (CNEI-0400-379, Revision 4)
The Catawba 2 Cycle 26 COLR will cease to be effective during NO MODE between cycles 26 and 27.
Data files to be Implemented No data files are transmitted as part of this document.
Additional Information CNS Reactor Engineering performed a site impact review in accordance with AD-NF-ALL-0807 and AD-NF-NGO-0214.

CNEI-0400-392 Page3 Revision 2 Catawba 2 Cycle 26 Core Operating Limits Report REVISION LOG Revision        Effective Date       Pages Affected              COLR 0            August2022        1-31, Appendix A*     C2C26 COLR, Rev. 0 1           October 2022             1-3, 13         C2C26 COLR, Rev. 1 2            March 2023           1-3, 7 and 13      C2C26 COLR, Rev. 2
* 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 is uploaded into the document management system, for ease of transmittal to the NRC.

CNEI-0400-392 Page4 Revision 0 Catawba 2 Cycle 26 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. 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.
NRC Approved TS              Technical Specifications                                      COLR COLR Parameter                Methodology (Section Section                                                                          Section 1.1 Number) 2.1.1      Reactor Core Safety Limits                   RCS Temperature and         2.1     6, 7, 8, 9, 10, 12, 15, Pressure Safety Limits                     16, 19, 20 3.1.1      Shutdown Margin                              Shutdown Margin             2.2    6, 7, 8, 12, 14, 15, 16, 19, 20 3.1.3      Moderator Temperature Coefficient            MTC                         2.3       6, 7, 8, 14, 16, 18 3.1.4      Rod Group Alignment Limits                   Shutdown Margin             2.2    6, 7, 8, 12, 14, 15, 16, 19,20 3.1.5      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 3.1.6      Control Bank Insertion Limit                 Shutdown Margin             2.2       2, 4, 6, 7, 8, 9, IO Rod Insertion Limits        2.5    12, 14, 15, 16, 19, 20 3.1.8      Physics Tests Exceptions                     Shutdown Margin             2.2    6, 7, 8, 12, 14, 15, 16, 19,20 3.2.1      Heat Flux Hot Channel Factor                 FQ                          2.6      2, 4, 6, 7, 8, 9, 10, AFD                         2.8       12, 15, 16, 19, 20 OTAT                        2.9 Penalty Factors             2.6 3.2.2      Nuclear Enthalpy Rise Hot Channel            FMI                         2.7      2, 4, 6, 7, 8, 9, 10 Factor                                       Penalty Factors             2.7       12, 15, 16, 19, 20 3.2.3     Axial Flux Difference                        AFD                          2.8     2, 4, 6, 7, 8, 15, 16 3.3.1      Reactor Trip System Instrumentation          OT~T                        2.9       6, 7, 8, 9, 10, 12 OP~T                        2.9         15, 16, 19, 20 3.3.9     Boron Dilution Mitigation System             Reactor Makeup Water Flow   2.10         6, 7, 8, 14, 16 Rate 3.4.1     RCS Pressure, Temperature and Flow limits    RCS Pressure, Temperature   2.11       6, 7, 8, 9, 10, 12, forDNB                                       and Flow                                     19,20 3.5.1     Accumulators                                 Max and Min Boron Cone. 2.12         6, 7, 8, 14, 16 3.5.4     Refueling Water Storage Tank                 Max and Min Boron Cone. 2.13         6, 7, 8, 14, 16 3.7.15    Spent Fuel Pool Boron Concentration          Min Boron Concentration     2.14         6, 7, 8, 14, 16 3.9.1     Refueling Ooerations - Boron Concentration   Min Boron Concentration     2.15         6, 7, 8, 14, 16 5.6.5     Core Operating Limits Report (COLR)          Analytical Methods           1.1              None The Selected Licensee Commitments that reference this report are listed below NRC Approved SLC                                                                             COLR Selected Licensee Commitment                  COLR Parameter                    Methodology (Section Section                                                                           Section 1.1 Number) 16.7-9   Standby Shutdown System              Standby Makeup Pump Water Suooly    2.16         6, 7, 8, 14, 16 16.9-11   Boration Systems - Borated Water     Borated Water Volume and Cone. for  2.17         6, 7, 8, 14, 16 Source - Shutdown                    BAT/RWST 16.9-12   Boration Systems - Borated Water     Borated Water Volume and Cone. for  2.18         6, 7, 8, 14, 16 Source - Operating                   BAT/RWST

CNEI-0400-3 92 Page 5 Revision 0 Catawba 2 Cycle 26 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," (Yi_ Proprietary).
Revision 0 Report Date: July 1985 Not Used
: 2. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code," (Yi_ 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," (Yi_ Proprietary). (Referenced in Duke Letter DPC-06-101)
Revision 1 Report Date: July 1997
: 3. WCAP-10266-P-A, "The 1981 Version Of Westinghouse Evaluation Model Using BASH Code," (Yi_ 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," (Ji_ 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

CNEI-0400-392 Page6 Revision 0 Catawba 2 Cycle 26 Core Operating Limits Report 1.1  Analytical Methods (continued)
: 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: January 2019
: 9. DPC-NE-2004P-A, "Duke Power Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-01," (Duke Energy Proprietary).
Revision 2a 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-2008-PA, "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

CNEI-0400-392 Page?
Revision 2 Catawba 2 Cycle 26 Core Operating Limits Report 1.1  Analytical Methods (continued)
: 14. DPC-NF-2010-A, "Nuclear Physics Methodology for Reload Design."
Revision 2a Report Date: December 2009
: 15. DPC-NE-2011-PA, "Nuclear Design Methodology 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 / SIMULATE-3 MOX,"
(Duke Energy Proprietary).
Revision 1 Report Date: November 2008
: 17. BAW-1023 lP-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 1 Report Date: December 2022
: 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'," Cii_
Proprietary).
Revision 0 Report Date: July 2006

CNEI-0400-3 92 Page 8 Revision 0 Catawba 2 Cycle 26 Core Operating Limits Report 2.0  Operating Limits 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% Af</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~ 1.0% ~K/K in MODE 5.
2.2.3 For TS 3.1 .4, SDM shall be ~ 1.3% Af</K in MODE 1 and MODE 2.
2.2.4 For TS 3.1.5, SDM shall be~ 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~ 1.3% Af</K in MODE 1 and MODE 2 with Keff~
1.0.
2.2.6  For TS 3.1.8, SDM shall be~ 1.3% Af</K in MODE 2 during PHYSICS TESTS.

CNEI-0400-392 Page9 Revision 0 Catawba 2 Cycle 26 Core Operating Limits Report Figure 1 Reactor Core Safety Limits Four Loops in Operation 670 . - - - - - - - - . - - - - - - - , , - - - - - - . - - - - - - - , - - - - - - - . - - - - - - - ,
DO NOT OPERATE IN THIS AREA 660  1----------<~------+------+                                                            ----I 5"&deg;' 630     1----------t-----=--....::----t-----+--------"""'l.: :,---------+-~.--------1 bl)
  ~
E--
tZl
~ 620 590  1----------,-------+------+------+------+-------t ACCEPTABLE OPERATION 580 .___ _ ___._ _ _ ____.,_ _ _ ____.__ _ _ __.__ _ _ ___,___ _ _ ___,
0.0            0.2             0.4              0.6             0.8              1.0             1.2 Fraction of Rated Thermal Power

CNEI-0400-392 Page 10 Revision 0 Catawba 2 Cycle 26 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 Af</K/&deg;F.
EOC, ARO, RTP MTC shall be less negative than the -4.3E-04 Af</K/&deg;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 L1K./K/&deg;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 .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 Af(/K/&deg;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 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.

CNEI-0400-3 92 Page 11 Revision 0 Catawba 2 Cycle 26 Core Operating Limits Report Figure 2 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 0.9                              Unacceptable Operation
 ....=        0.8
 =
   ~
   ~
   ~          0.7 u
0,-..
        ~
i~
0.6 0.5
   ~-<I e;,
   ~"'1' 0.4                   Acceptable Operation
 ~~
:i.
* 00          0.3 ei::
:i.
  ~           0.2 "0
0
 ~            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 2 ROD manual for details.

CNEI-0400-392 Page 12 Revision 0 Catawba 2 Cycle 26 Core Operating Limits Report Figure3 Control Bank Insertion Limits Versus Percent Rated Thermal Power Fully Withdrawn (Maximum= 231-~
231 220   -           -        -              ., ....                 - -               '""       ....                 - ., ...          -                       -
200                     ,,                                                                                ,,
Ir
   ,,...._                                                                        Fully Withdrawn
     = 180                  ., i,
                                                                         -       (Minimum= 222)             1 Control Bank B
     ~
(100%, 161)    F
   ] 160         H (0%, 163)                                                               .,                                                                       ., .,
   .'i:                                                                              ., .,                                                                    ., ,,
   ~Q. 140                                                            ., ,,.                                                                         ./
cu
                                                                .,, .,                 Control Bank C                                           ,, .,
Ir 1
   ~ 120                                                     .,
    =                                                   ,.,                                                                               ,, .,
0 3 100                                                                                                                              ., J
    "'0                                                                                                                        .....
    =
  ~
80                         Ir 0                       ., ,.,                                                                            ,,. .,                Control Bank D t:cu      60
  ....=
R (0%,47)                                                                ., .,
i, "0
0 40                                                                       ,,.
i::i:
iFully Inserted                                         ./
20                                                          , ,,
                 ~
0   -                                  (30%, 0)        ,.,
0            10              20               30             40              50                60             70              80           90          100 Percent of Rated Thermal Power The Rod Insertion Limits (RIL) for Control Bank D (CD), Control Bank C (CC), and Control Bank B (CB) can 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.

CNEI-0400-392 Page 13 Revision 2 Catawba 2 Cycle 26 Core Operating Limits Report Table 1 Control Bank Withdrawal Sequence Equation Control         Control         Control       Control Bank A          Bank B          Bank C        Bank D 0 Start            0               0             0 116           0 Start            0             0 CBA Stop        CBA- 116             0             0 CBA              116           0 Start          0 CBA          CBB Stop        CBB -116           0 CBA             CBB             116          0 Start CBA             CBB             CBC        CBC- 116 Where:
CBA = Fully withdrawn position of Control Bank A CBB = Fully withdrawn position of Control Bank B CBC = Fully withdrawn position of Control Bank C Allowed Control Bank Fully Withdrawn Positions Range from 223 Steps to 231 Steps for frequent RCCA Reposition Required per CNEI-0400-091, Rev. 9, "RCCA Axial Repositioning Schedule for Catawba Nuclear Station."

CNEI-0400-392 Page 14 Revision 0 Catawba 2 Cycle 26 Core Operating Limits Report 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:
F ~TP *K(Z)IP                  for P > 0.5 F rP *K(Z)/0.5                 forP ,:s0.5 where, Thermal Power P= - - - - - - -
Rated Thermal Power 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.
2.6.2  F  ~TP  = 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 FQ(X,Y,Z) as a function ofburnup. F~TP with the K(BU) penalty for Westinghouse RF A fuel is analytically confirmed in cycle-specific reload calculation. 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 3.2.1:
L               Fg(X, Y,Z)
* M0(X, Y,Z) 2.6.5  [FQ(X,Y,Z)]OP =      UMT *MT* TILT where:
[FJ (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.
Ft (X,Y,Z) 0P includes allowances for calculation and measurement uncertainties.
Ft (X,Y,Z)    = 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.

CNEI-0400-3 92 Page 15 Revision 0 Catawba 2 Cycle 26 Core Operating Limits Report M 0(X,Y,Z) = Margin remaining in core location X,Y,Z to the LOCA limit in the transient power distribution. Mo(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. (TILT= 1.035)
L         RPS   Fg(X,Y,Z)
* Mc(X,Y,Z) 2*6*6 [Fo(X,Y,Z)]     =     UMT *MT* TILT where:
[F~(X, Y,Z)]RPS = Cycle dependent maximum allowable design peaking factor that ensures Fo(X,Y,Z) Centerline Fuel Melt (CFM) limit is not exceeded for operation within AFD, RIL, and QPTR limits.
[F~(X,Y,Z)]RPS includes allowances for calculation and measurement uncertainties.
Fg(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.

CNEI-0400-392 Page 16 Revision 0 Catawba 2 Cycle 26 Core Operating Limits Report 2.6. 7 KSLOPE = 0.0725 where:
KSLOPE = adjustment to K 1 value from OTLlT trip setpoint required to compensate for each 1% measured  Ft (X, Y,Z)
L         RPS exceeds [FQ (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.

CNEI-0400-3 92 Page 17 Revision 0 Catawba 2 Cycle 26 Core Operating Limits Report Figure 4 K(Z), Normalized FQ(X,Y,Z) as a Function of Core Height for RFA Fuel 1.200 1.000 .,_(0.0,
__   1.00)
____          (4.0,
_ 1.00)
__ i                                 (12 .0, 0.9259)
(4.0, 0.9259) 0.800
~ 0.600 Core Height (ft)     K(Z) 0.400              0.0      1.000
                     ~4       1.000
                      >4      0.9259 12      0.9259 0.200 0.000  +----~-----.-----..--------.-----....-------,
0.0               2.0            4.0              6.0       8.0 10.0             12 .0 Core Height (ft)

CNEI-0400-392 Page 18 Revision 0 Catawba 2 Cycle 26 Core Operating Limits Report Table 2 Fo(X,Y,Z) and FLm(X,Y) Penalty Factors For Tech Spec Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2 Burnup                   Fo(X,Y,Z)                   FLm(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                       2.00 502                       2.00                       2.00 505                       2.00                       2.00 515                       2.00                       2.00 525                       2.00                       2.00 Note: Linear interpolation is adequate for intermediate cycle bumups.
All cycle bumups outside the range of the table shall use a 2%
penalty factor for both F Q(X, Y,Z) and FL\H(X, Y) for compliance with Tech Spec Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2.

CNEI-0400-3 92 Page 19 Revision 0 Catawba 2 Cycle 26 Core Operating Limits Report 2.7  Nuclear Enthalpy Rise Hot Channel Factor - Fm(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)tco 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.
Thermal Power P= - - - - - - - -
Rated Thermal Power RRH = Thermal Power reduction required to compensate for each 1% measured radial peak, F~ (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)*MAH(X,Y)
UMR *TILT where:
              ;,, (X,Y)]SURV -- Cye1e d ependent maximum
[ F=                                         .      a11owable des1gn
                                                                              . peak'mg f:actor that ensures FAH(X, Y) limit is not exceeded for operation within AFD , RIL , and QPTR limits
* pL LlH (X ' Y)sURv includes allowances for calculation and measurement uncertainty.
F~H (X, Y) = Design power distribution for FAH, 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-0400-392 Page 20 Revision 0 Catawba 2 Cycle 26 Core Operating Limits Report MllH(X, Y) = Margin remaining in core location X, Y relative to the Operational DNB limits in the transient power distribution.
MLlH(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 M,,m(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 OTLlT K 1 setpoint required to compensate for each 1% that the measured radial peak, F! (X, Y) exceeds its limit.
2.7.5  FllH(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-0400-392 Page 21 Revision 0 Catawba 2 Cycle 26 Core Operating Limits Report Table3 Maximum Allowable Radial Peaks (MARPs)
RFA Steady State Limiting Value Between Loss of Flow Accident (LOFA) MARPs and FMlwcA 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 l.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

CNEI-0400-392 Page 22 Revision 0 Catawba 2 Cycle 26 Core Operating Limits Report Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits
(-20, 100)
Unacceptable Operation                                        Unacceptable Operation 90 80 70 Acceptable o8gra ion 50
(-36, 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 3.2.1 may require more restrictive AFD limits. Refer to the Unit 2 ROD manual for operational AFD limits.

CNEI-0400-3 92 Page 23 Revision 0 Catawba 2 Cycle 26 Core Operating Limits Report 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 Value Nominal Tavg at RTP                                                 T',::: 590.8 &deg;F Nominal RCS Operating Pressure                                      P' = 2235 psig Overtemperature AT reactor trip setpoint                            K1 = 1.1953 Overtemperature AT reactor trip heatup setpoint                     K2 = 0.03163/&deg;F penalty coefficient Overtemperature AT reactor trip depressurization                     K3 = 0.001414/psi setpoint penalty coefficient Time constants utilized in the lead-lag compensator                 1:1 = 8 sec.
for AT                                                              1:2 = 3 sec.
Time constant utilized in the lag compensator for AT                1:3 :::; 1.8 sec.
Time constants utilized in the lead-lag compensator                 1:4 = 22 sec.
for Tavg                                                            't'5 = 4 sec.
Time constant utilized in the measured Tav8 lag                     't'6:::; 1.8 sec.
compensator f1(AI) "positive" breakpoint                                        =3.0%M f1(AI) "negative" breakpoint                                        =NIA*
f1(M) "positive" slope                                              = 1.525 %ATol %AI f1(M) "negative" slope                                              =NIA*
* f1 (Al) negative breakpoint and slope for OTLlT are less restrictive than OPLlT fz (Al) negative breakpoint and slope. Therefore, during a transient which challenges negative imbalance limits, OPdT fz (Al) limits will result in a reactor trip before OTdT f1 (dl) limits are reached. This makes implementation of an OTdT f1 (M) negative breakpoint and slope unnecessary.

CNEI-0400-392 Page 24 Revision 0 Catawba 2 Cycle 26 Core Operating Limits Report 2.9.2        Overpower L'.1T Setpoint Parameter Values Parameter                          Nominal Value Nominal Tavg at RTP                                    T" ,:S590.8 &deg;F Overpower LiT reactor trip setpoint                    K4::;; 1.0909 Overpower LiT reactor trip penalty                      Ks :2:: 0.0 / &deg;F for increasing Tavg Ks= 0.00 I &deg;F for decreasing Tavg Overpower LiT reactor trip heatup setpoint              K6 = 0.001291/&deg;F for T > T" penalty coefficient                                     K6 = 0.0 /&deg;F for T :ST" Time constants utilized in the lead-lag                 *q = 8 sec.
compensator for LiT                                     *2 = 3 sec.
Time constant utilized in the lag compensator           *3 ::: 1.8 sec.
for LiT Time constant utilized in the measured Tavg lag        *6::: 1.8 sec.
compensator Time constant utilized in the rate-lag controller      *7 = 10 sec.
for Tavg f2(M) "positive" breakpoint                            =27.03/4M fi(Lil) "negative" breakpoint                          =-27.0 %Lil f2(M) "positive" slope                                 = 7.0 %LiToi %Lil fi(M) "negative" slope                                 = 7.0 %LiToi %Lil

CNEI-0400-392 Page 25 Revision 0 Catawba 2 Cycle 26 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                   ::: 80 gpm MODE4or5                  ::: 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 I and 2, and MODE 3 with RCS pressure > 1000 psi:
Parameter                          Applicable Bumup       Limit Accumulator minimum boron concentration.              0- 200 EFPD          2,500ppm Accumulator minimum boron concentration.          200.l - 300 EFPD         2,500ppm Accumulator minimum boron concentration.          300.1 - 400 EFPD         2,355 ppm Accumulator minimum boron concentration.          400.1 - 515 EFPD         2,204ppm Accumulator minimum boron concentration.          515.1 - 525 EFPD         2,046 ppm Accumulator maximum boron concentration.              0-525 EFPD          3,075 ppm

CNEI-0400-392 Page 26 Revision 0 Catawba 2 Cycle 26 Core Operating Limits Report Table 4 Reactor Coolant System DNB Parameters No. Operable PARAMETER                      INDICATION     CHANNELS          LIMITS
: 1. Indicated RCS Average Temperature       meter                  4      :5 591.3 &deg;F meter                  3      :5 591.1 &deg;F computer               4      :5 591.8 &deg;F computer               3      :5 591.6 &deg;F
: 2. Indicated Pressurizer Pressure          meter                  4      2: 2206.9 psig meter                  3      2: 2208.7 psig computer               4      2: 2204.0 psig computer               3      2: 2205.4 psig
: 3. RCS Total Flow Rate                                                   > 387,000 gpm

CNEI-0400-392 Page 27 Revision 0 Catawba 2 Cycle 26 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.                                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 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 Keffremains within MODE 6 reactivity requirement ofKeff:':: 0.95.
Parameter Minimum boron concentration of the Reactor Coolant              2,700 ppm System, the refueling canal, and the refueling cavity.

CNEI-0400-392 Page 28 Revision 0 Catawba 2 Cycle 26 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               2,700 ppm 16.7-9-3.
2.17 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~ 210&deg;P, and MODES 5 and 6.
Parameter BAT minimum boron concentration                             7,000 ppm Volume of7,000 ppm boric acid solution required            2000 gallons to maintain SOM at 68 &deg;P NOTE: When cycle burn up is > 449 EFPD, Figure 6 may be used to determine required BAT minimum level.
BAT Minimum Shutdown Volume (Includes the                 13,086 gallons additional volumes listed in SLC 16.9-11)                  (14.9% level)
RWST minimum boron concentration                             2,700 ppm Volume of 2,700 ppm boric acid solution required           7,000 gallons to maintain SDM at 68 &deg;P RWST Minimum Shutdown Volume (Includes the                48,500 gallons additional volumes listed in SLC 16.9-11)                   (8. 7% level)

CNEI-0400-392 Page 29 Revision 0 Catawba 2 Cycle 26 Core Operating Limits Report 2.18  Borated Water Source - Operating       (SLC 16.9-12) 2.18.1 Volume and boron concentrations for the Boric Acid Tank (BAT) and the Refueling Water Storage Tank (RWST) during MODES 1, 2, and 3 and MODE 4 with all RCS cold leg temperatures > 210 &deg;P *.
* NOTE: The SLC 16.9-12 applicability is down to MODE 4 temperatures of
      > 210&deg;F. The minimum volumes calculated support cooldown to 200&deg;F to satisfy UFSAR Chapter 9 requirements.
Parameter BAT minimum boron concentration                              7,000ppm Volume of 7,000 ppm boric acid solution required          13,500 gallons to maintain SDM at 210&deg;P NOTE: When cycle burnup is > 449 EFPD, Figure 6 may be used to determine required BAT minimum level.
BAT Minimum Shutdown Volume (Includes the                 25,200 gallons additional volumes listed in SLC 16.9-12)                  (45.8% level)
R WST minimum boron concentration                           2,700 ppm Volume of 2,700 ppm boric acid solution required          57,107 gallons to maintain SDM at 210 &deg;P R WST Minimum Shutdown Volume (Includes the               98,607 gallons additional volumes listed in SLC 16.9-12)                 (22.0% level)

CNEI-0400-392 Page 30 Revision 0 Catawba 2 Cycle 26 Core Operating Limits Report Figure 6 Boric Acid Storage Tank Indicated Level Versus Primary Coolant Boron Concentration (Valid When Cycle Burn up is> 449 EFPD)
This figure includes additional volumes listed in SLC 16.9-11 and 16.9-12 50.0 I
RCS Boron 45.0 Concentration  BAT Level 40.0 I                                                    (ppm) 0 < 300
(%level)
I                                          300 < 500 43.0 40.0 35.0                                                             500 < 700       37.0 I                       700 < 1000       30.0 I
l    3o.o                                                            1000 < 1300      14.9 QI
...J 1300 < 2700       9.8
~                                                                       > 2700         9.8
~ 25.0 QI Unacceptable
~                 Operation                       Acceptable Operation
~ 20.0 al 15.0 10.0 5.0 0.0 0    200    400     600   800   1000   1200   1400  1600     1800  2000 2200    2400  2600 Primary Coolant Boron Concentration (ppmb)

CNEI-0400-392 Page 31 Revision 0 Catawba 2 Cycle 26 Core Operating Limits Report Appendix A Power Distribution Monitoring Factors Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. This data was generated in the Catawba 2 Cycle 26 Maneuvering Analysis calculation file, CNC-1553.05-00-0721, Rev 0. Due to the size of the monitoring factor data, Appendix A is controlled electronically within the Duke document management system and is not included in the Duke internal copies of the COLR. The Plant Reactor Engineering section will control this information via computer file(s) and should be contacted ifthere is a need to access this information.
Appendix A is available to be transmitted to the NRC.
Filename                  Checksum / File Size c2c26_AppendixA.pdf 2198190725 / 3534570}}