L-PI-09-110, Core Operating Limits Report (Colr), Cycle 26, Revision 0

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Core Operating Limits Report (Colr), Cycle 26, Revision 0
ML092990463
Person / Time
Site: Prairie Island Xcel Energy icon.png
Issue date: 10/23/2009
From: Schimmel M
Xcel Energy
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-PI-09-110
Download: ML092990463 (26)
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@ Xcel Energye QCT 3 3 2009 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Unit 1 Docket 50-282 License No. DPR-42 Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 1, Cvcle 26, Revision 0 Pursuant to the requirements of Technical Specification 5.6.5.d, the COLR for the PINGP Unit 1, Cycle 26, Revision 0, is attached. The limits specified in the attached COLR have been established using Nuclear Regulatory Commission (NRC) approved methodologies.

The COLR has been updated for the Unit 1 Cycle 26 core reload. The update also incorporates changes to allow use of Westinghouse 0.422-inch OD 14x14 Vantage+

Fuel, which were approved by the NRC by issuance of License Amendments 192 and 181, dated July 1, 2009. The following changes were made:

Revised Section 3.1.3, Isothermal Temperature Coefficient, ITC Lower limit, for Unit 1, Cycle 26.

Revised Section 3.2.2, Nuclear Enthalpy Rise Hot Channel Factor limits for Unit 1, Cycle 26.

Revised Section 3.4.1, RCS (Reactor Coolant System) Pressure, Temperature, and Flow - Department from Nucleate Boiling (DNB) Limits, Pressurizer pressure limit, for Unit 1, Cycle 26.

Revised the References section to add WCAP-10924-P-A, WCAP-13677-P-A, NAD-PI-003, and NAD-PI-004. Removed the reference to deleted reference 6.c.

Replaced the previous reference to the 50.59 screening for Unit 1 Cycle 25 Core Reload, with the new reference to the 50.59 screening for Unit 1 Cycle 26 Core Reload.

Revised Table 1, Minimum Required Shutdown Margin, for Unit 1, Cycle 26.

Revised Table 2, W(z) Values, for Unit 1, Cycle 26.

Revised Table 3, F ~ ~ ( Penalty z) Factor, for Unit 1, Cycle 26.

Revised Figure 1, Reactor Core Safety Limits, for Unit 1, Cycle 26.

1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1121

Document Control Desk Page 2 Summarv of Commitments This letter contains no new commitments and no revisions to existing commitments.

Mark A. Schimmel Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC State of Minnesota

ENCLOSURE 1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT UNIT 1 - CYCLE 26 REVISION 0 Record of Revision (6 pages)

Unit 1 - Cycle 26, Revision 0 (17 pages)

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record of Revision Revision Approval Unit Cycle No. Date Remarks 2 13 0 3/22/90 Original Unit 2 Core Operating Limits Report, distributed with Technical Specification Revision 92.

1 14 0 3/22/90 Original Unit 1 Core Operating Limits Report, distributed with Technical Specification Revision 92.

1 7/27/90 Incorporated expanded V(z) curves.

2 9/27/90 Clarified rod insertion limit curve applicability.

3 2/11/91 Incorporated revised FQ of 2.45 as a result of NRC approval of Westinghouse Topical Report WCAP-10924-P-A, Volume 1, Addendum 4, October 1990.

2 14 0 - Not used.

1 9/27/90 Updated to Unit 2 Cycle 14, incorporated expanded V(z) curves and clarified rod insertion limit curve applicability.

2 2/11/91 Incorporated revised FQ of 2.45 as a result of NRC approval of Westinghouse Topical Report WCAP-10924-P-A, Volume 1, Addendum 4, October 1990.

1 15 0 6/25/91 Updated to Unit 1 Cycle 15.

2 15 0 3/9/92 Updated to Unit 2 Cycle 15 and clarified labeling of Figure 4. Clarified the actions to be taken if the nuclear enthalpy rise hot channel factor exceeds the Technical Specification limit.

1 16 0 12/28/92 Updated to Unit 1 Cycle 16, removed V(z) curves and replaced them with list of bounding V(z) values for three ranges of exposures.

2 16 0 12/8/93 Updated to Unit 2 Cycle 16. Removed the multiple V(z) curves and replaced them with a single figure with bounding V(z) curves for four ranges of exposures. Incorporated additional discussion related to V(z) and K(z).

Page 1 of 6

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record of Revision Revision Approval Unit Cycle No. Date Remarks 2 16 1 11/3/94 The table containing the bounding V(z) values and Figure 2 updated to incorporate revised bounding V(z) values for the exposure range of 14-21.5 GWD/MTU. Figures 3 through 6 re-formatted.

1 17 0 6/17/94 Updated to Unit 1 Cycle 17. Removed the list of bounding V(z) values and replaced it with multiple V(z) curves. Incorporated additional discussion related to V(z) and K(z).

2 17 0 6/2/95 Updated to Unit 2 Cycle 17. Incorporated Table 1 and expanded Figure 2 with updated bounding V(z) values.

1 18 0 2/7/96 Updated to Unit 1 Cycle 18. Incorporated revised FH limit of 1.77. Incorporated Table 1 and updated Figure 2 with revised bounding V(z) values.

2 18 0 2/27/97 Updated to Unit 2 Cycle 18. Revised FH limit to 1.77. Updated Table 1 and Figures 2a through 2e with revised bounding V(z) values.

Incorporated new Figures 2f and 2g with additional bounding V(z) values.

1 19 0 9/25/97 Updated to Unit 1 Cycle 19. Updated Table 1 and Figures 2a through 2f with revised bounding V(z) values.

2 19 0 12/17/98 Updated to Unit 2 Cycle 19. Updated Table 1 and Figures 2a through 2d with revised bounding V(z) values. Deleted Figures 2e, 2f and 2g.

1 20 0 5/13/99 Updated to Unit 1 Cycle 20. Updated Table 1 and Figures 2a through 2f with revised bounding V(z) values.

1 8/4/00 Technical Specification Amendment 151:

Relocate shutdown margin (SDM) requirements from Tech Specs and incorporate additional SDM requirements for Modes 3-6 from revised analysis of Uncontrolled Dilution event.

Page 2 of 6

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record of Revision Revision Approval Unit Cycle No. Date Remarks 2 20 0 5/31/00 Updated to Unit 2 Cycle 20. Updated Table 1 and Figures 2a through 2d with revised bounding V(z) values. Added new Table 2 and Figures 2e, 2f and 2g with additional bounding V(z) values.

Added references to Tables 1 and 2 and to Figures 2e, 2f and 2g to discussion of heat flux hot channel factor limits. Added discussion clarifying applicability of axial flux difference limits when using Tables 1 and 2 and Figures 2a through 2g. Added discussion of two tier V(z) curve presented in Table 2 and Figure 2g.

1 8/4/00 Technical Specification Amendment 142:

Relocate shutdown margin (SDM) requirements from Tech Specs and incorporate additional SDM requirements for Modes 3-6 from revised analysis of Uncontrolled Dilution event.

1 20 2 9/1/00 Revised to change axial flux difference target band.

1 21 0 1/31/01 Updated to support refueling activities associated with Unit 1 Cycle 21. Revision 0 of the Unit 1 Cycle 21 COLR had to be issued prior to confirming the applicability of the LOCA analysis.

Therefore, Revision 0 of the Unit 1 Cycle 21 COLR does not contain all of the operating limits necessary to support operation of Unit 1 Cycle 21.

1 21 1 2/19/01 Updated to Unit 1 Cycle 21. Updated Tables 1 and 2 and Figures 2a through 2f with revised bounding V(z) values.

1 21 2 10/02/02 Revised to support License Amendment 158 changes, including revision of all references to TS, revision of FQ symbols, addition of Table 4, ITC limits, DNB limits and refueling boron concentrations.

2 21 0 2/06/02 Updated to Unit 2 Cycle 21.

Page 3 of 6

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record of Revision Revision Approval Unit Cycle No. Date Remarks 2 21 1 10/02/02 Revised to support License Amendment 149 changes, including revision of all references to TS, revision of FQ symbols, addition of Table 4, ITC limits, DNB limits and refueling boron concentrations. Also revised to include an additional V(z) curve to give greater FQ margin between 13.0 and 16.0 GWd/MTU.

1 22 0 11/25/02 Updated to Unit 1 Cycle 22. Updated Tables 1 and 2 and Figures 2a through 2f with revised bounding V(z) values. Incorporated new Figure 2g with additional bounding V(z) values.

Updated Table 3 with revised minimum shutdown margin limits. Deleted and revised text to eliminate duplication with the Technical Specifications and the Bases.

2 22 0 9/19/03 Updated to Unit 2 Cycle 22. Updated Tables 1 and 2. A reduced number of exposure ranges were calculated in Table 1, therefore new Figures 2a through 2e with revised bounding V(z) values replaced Figures 2a through 2f. New Figure 2f replaced Figure 2g for the 2 tier band bounding V(z) values. Updated Table 3 with revised minimum shutdown margin limits. Deleted and revised text to eliminate duplication with the Technical Specifications and the Bases.

1 22 1 7/6/04 Revision to incorporate Westinghouse Safety Analysis Transition per LA 162/153. Revision 1 contains transitional values for the OP/OT T Trip setpoints that will be used while the physical changes are implemented.

2 22 1 7/6/04 Revision to incorporate Westinghouse Safety Analysis transition per LA 162/153. Revision 1 contains transitional values for the OP/OT T Trip setpoints that will be used while the physical changes are implemented.

2 22 2 7/12/04 Revised Fq limit from 2.4 to 2.5. Removed OP and OT delta-T setpoints based on NMC methodology and replaced with Westinghouse developed setpoints.

Page 4 of 6

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record of Revision Revision Approval Unit Cycle No. Date Remarks 1 22 2 7/16/04 Revised Fq limit form 2.4 to 2.5. Removed OP and OT delta-T setpoints based on NMC methodology and replaced with Westinghouse developed setpoints.

1 23 0 10/20/04 Updated to Unit 1 Cycle 23.

2 23 0 - Not used due to core redesign.

2 23 1 5/19/05 Updated to Unit 2 Cycle 23 and to support redesign of Unit 2 Cycle 23 core.

1 23 1 7/11/05 Revised ITC upper limit from < 0 pcm/°F for power levels > 70% RTP to less than a line that slopes linearly from 0 pcm/F at 70% RTP to -2.9 pcm/F at 100% RTP. Revised the title of Figure 3 to reference T.S. 3.1.4 Condition B and revised the title of Figure 4 to reference T.S. 3.1.4 Condition A. Added references 24 and 25 to include the 50.59 screenings written to issue revision 1.

1 24 0 5/10/06 Updated to Unit 1 Cycle 24.

1 24 1 8/7/06 Updated Table 3 to reflect the correct Fqw(z) penalty factors.

2 24 0 11/26/06 Updated to Unit 2 Cycle 24 Modes 5 and 6.

2 24 1 12/6/06 Updated to Unit 2 Cycle 24 for Modes 1-6.

2 24 2 9/4/07 Revised to support LA-179/169. Revised reference 24 to include the revision number (revision 0) and the correct date of the report (January 2005). Revised references 6a, 6b, 6c, and 8 to say Deleted. These references referred to the old LBLOCA methodology and model.

1 24 2 2/11/08 Updated Table 1 to reflect correct Shutdown Margin Requirements and added Figures 6A through 6H.

Page 5 of 6

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record of Revision Revision Approval Unit Cycle No. Date Remarks 2 24 3 2/11/08 Updated Table 1 to reflect correct Shutdown Margin Requirements and added Figures 6A through 6H.

1 25 0 2/24/08 Updated to Unit 1 Cycle 25 1 25 1 5/28/08 Updated Table 2 to reflect the correct W(z) at a burnup of 150 MWd/MTU and a core height of 6.20 feet 2 25 0 9/26/08 Updated for Unit 2 Cycle 25 1 26 0 9/24/09 Updated for Unit 1 Cycle 26 Page 6 of 6

Core Operating Limits Report Unit 1, Cycle 26 Revision 0 PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT UNIT 1 - CYCLE 26 REVISION 0 Reviewed By: Ad Date: 9 / ; ~ 3 / ~ ?

~dohnson Supervisor, NSSS Reviewed By: Date: f/L$/+&

Hank Hoelsch Supervisor, PWR Analyses Approved By: Date:

Note: This report is not part of the Technical Specifications This report is referenced in the Technical Specifications Page 1 of 17

Core Operating Limits Report Unit 1, Cycle 26 Revision 0 PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT UNIT 1 - CYCLE 26 REVISION 0 This report provides the values of the limits for Unit 1 Cycle 26 as required by Technical Specification Section 5.6.5. These values have been established using NRC approved methodology and are established such that all applicable limits of the plant safety analysis are met. The Technical Specifications affected by this report are listed below:

1. 2.1.1 Reactor Core SLs
2. 3.1.1 Shutdown Margin (SDM)
3. 3.1.3 Isothermal Temperature Coefficient (ITC)
4. 3.1.5 Shutdown Bank Insertion Limits
5. 3.1.6 Control Bank Insertion Limits
6. 3.1.8 Physics Tests Exceptions - MODE 2
7. 3.2.1 Heat Flux Hot Channel Factor (FQ(z))
8. 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor F ( )
9. 3.2.3 Axial Flux Difference (AFD)
10. 3.3.1 Reactor Trip System (RTS) Instrumentation Overtemperature T and Overpower T Parameter Values for Table 3.3.1-1
11. 3.4.1 RCS Pressure, Temperature, and Flow - Departure from Nucleate Boiling (DNB) Limits
12. 3.9.1 Boron Concentration
1. 2.1.1 Reactor Core Safety Limits Reactor Core Safety Limits are shown in Figure 1.

Reference Technical Specification section 2.1.1.

2. 3.1.1 Shutdown Margin Requirements Minimum Shutdown Margin requirements are shown in Table 1.

Reference Technical Specification section 3.1.1.

Page 2 of 17

Core Operating Limits Report Unit 1, Cycle 26 Revision 0

3. 3.1.3 Isothermal Temperature Coefficient (ITC)

ITC Upper limit:

a. < 5 pcm/°F for power levels < 70% RTP; and
b. less than a line which slopes linearly from
i. 0 pcm/oF at a power level = 70% RTP to ii. -1.5 pcm/oF at a power level = 100% RTP ITC Lower limit:
a. -43.15 pcm/°F Reference Technical Specification section 3.1.3.
4. 3.1.5 Shutdown Bank Insertion Limits The shutdown rods shall be fully withdrawn.

Reference Technical Specification section 3.1.5.

5. 3.1.6 Control Bank Insertion Limits The control rod banks shall be limited in physical insertion as shown in Figures 2, 3, and 4.

The control rod banks withdrawal sequence shall be Bank A, Bank B, Bank C, and finally Bank D.

The control rod banks shall be withdrawn maintaining 128 step tip-to-tip distance.

Reference Technical Specification section 3.1.6.

6. 3.1.8 Physics Tests Exceptions - MODE 2 Minimum Shutdown Margin requirements during physics testing are shown in Table 1.

Reference Technical Specification section 3.1.8.

Page 3 of 17

Core Operating Limits Report Unit 1, Cycle 26 Revision 0

7. 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

The Heat Flux Hot Channel Factor shall be within the following limits:

CFQ = 2.50 K(Z) is a constant value = 1.0 at all elevations.

W(Z) values are provided in Table 2.

FWQ(Z) Penalty Factors are provided in Table 3.

Applicability: MODE 1.

Reference Technical Specification section 3.2.1

8. 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FHN)

The Nuclear Enthalpy Rise Hot Channel Factor shall be within the following limits:

FH 1.77 x [1 + 0.3(1- P)] for all 422V+ type fuel assemblies, and FH 1.712 x [1 + 0.3(1- P)] for all OFA type fuel assemblies where: P is the fraction of RATED THERMAL POWER at which the core is operating.

Applicability: MODE 1.

Reference Technical Specification section 3.2.2

9. 3.2.3 Axial Flux Difference (AFD)

The indicated axial flux difference, in % flux difference units, shall be maintained within the allowed operational space defined by Figure 5.

Applicability: MODE 1 with RATED THERMAL POWER > 50% RTP.

Reference Technical Specification section 3.2.3.

Page 4 of 17

Core Operating Limits Report Unit 1, Cycle 26 Revision 0

10. 3.3.1 Reactor Trip System (RTS) Instrumentation Overtemperature T and Overpower T Parameter Values for Table 3.3.1-1; Overtemperature T Setpoint Overtemperature T setpoint parameter values:

T0 = Indicated T at RATED THERMAL POWER, %

T = Average temperature, °F T = 560.0 °F P = Pressurizer Pressure, psig P = 2235 psig K1 1.17 K2 = 0.014 /°F K3 = 0.00100 /psi 1 = 30 seconds 2 = 4 seconds f() = A function of the indicated difference between top and bottom detectors of the power range nuclear ion chambers. Selected gains are based on measured instrument response during plant startup tests, where qt and qb are the percent power in the top and bottom halves of the core respectively, and qt + qb is total core power in percent of RATED THERMAL POWER, such that (a) For qt - qb within -13, +8 % f() = 0 (b) For each percent that the magnitude of qt - qb exceeds +8%

the T trip setpoint shall be automatically reduced by an equivalent of 1.73 % of RATED THERMAL POWER.

(c) For each percent that the magnitude of qt - qb exceeds -13 %

the T trip setpoint shall be automatically reduced by an equivalent of 3.846 % of RATED THERMAL POWER.

Overpower T Setpoint Overpower T setpoint parameter values:

T0 = Indicated T at RATED THERMAL POWER, %

T = Average temperature, °F T = 560.0 °F K4 1.11 K5 = 0.0275/°F for increasing T; 0 for decreasing T K6 = 0.002/°F for T > T ; 0 for T T 3 = 10 seconds Page 5 of 17

Core Operating Limits Report Unit 1, Cycle 26 Revision 0

11. 3.4.1 RCS Pressure, Temperature, and Flow - Departure from Nucleate Boiling (DNB) Limits Pressurizer pressure limit = 2190 psia RCS average temperature limit = 564°F RCS total flow rate limit = 178,000 gpm Reference Technical Specification section 3.4.1.
12. 3.9.1 Refueling Boron Concentration.

The boron concentration of the reactor coolant system and the refueling cavity shall be sufficient to ensure that the more restrictive of the following conditions is met:

a) Keff 0.95 b) 2000 ppm c) The Shutdown Margin specified in Table 1 Reference Technical Specification section 3.9.1.

Page 6 of 17

Core Operating Limits Report Unit 1, Cycle 26 Revision 0 REFERENCES (NRC Approved Methodologies for COLR Parameters)

1. NSPNAD-8101-A, Qualification of Reactor Physics Methods for Application to Prairie Island, Revision 2, October 2000.
2. NSPNAD-8102-PA, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units, Revision 7, July 1999.
3. NSPNAD-97002-PA, Northern States Power Companys Steam Line Break Methodology, Revision 1, October 2000.
4. WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, July, 1985.

5.a WCAP-10054-P-A, Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code, August, 1985.

5.b WCAP-10054-P-A, Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code, Addendum 2 Revision 1, July 1997.

6.a Deleted.

6.b Deleted.

7. WCAP-10924-P-A, Volume 1, Revision 1, and Volume 2, Revision 2, Westinghouse Large Break LOCA Best Estimate Methodology, September 2005.
8. XN-NF-77-57-(A), XN-NF-77-57, Supplement 1 (A), Exxon Nuclear Power Distribution Control for Pressurized Water Reactors Phase II, May 1981.
9. WCAP-13677-P-A, 10 CFR 50.46 Evaluation Model Report: W-COBRA/TRAC 2-Loop Upper Plenum Injection Model Update to Support ZIRLOTM Cladding Options, February 1994.
10. NSPNAD-93003-A, Prairie Island Units 1 and 2 Transient Power Distribution Methodology, Revision 0, April 1993.
11. NAD-PI-003, Prairie Island Nuclear Power Plant Required Shutdown Margin During Physics Tests, Revision 0, January 2001.
12. NAD-PI-004, Prairie Island Nuclear Plant FWQ(Z) Penalty With Increasing

[FCQ(Z)/K(Z)] Trend, Revision 0, January 2001.

13. WCAP-10216-P-A, Revision 1A, Relaxation of Constant Axial Offset Control/ FQ Surveillance Technical Specification, February 1994.

Page 7 of 17

Core Operating Limits Report Unit 1, Cycle 26 Revision 0

14. WCAP-8745-P-A, Design Bases for the Thermal Overpower T and Thermal Overtemperature T Trip Functions, September 1986.
15. WCAP-11397-P-A, Revised Thermal Design Procedure, April 1989.
16. WCAP-14483-A, Generic Methodology for Expanded Core Operating Limits Report, January 1999.
17. WCAP-7588 Rev. 1-A, An Evaluation of the Rod Ejection Accident in Westinghouse Pressurized Water Reactors Using Spatial Kinetics Methods, January 1975.
18. WCAP-7908-A, FACTRAN - A FORTRAN IV Code for Thermal Transients in a UO2 Fuel Rod, December 1989.
19. WCAP-7907-P-A, LOFTRAN Code Description, April 1984.
20. WCAP-7979-P-A, TWINKLE - A Multidimensional Neutron Kinetics Computer Code, January 1975.
21. WCAP-10965-P-A, ANC: A Westinghouse Advanced Nodal Computer Code, September 1986.
22. WCAP-11394-P-A, Methodology for the Analysis of the Dropped Rod Event, January 1990.
23. WCAP-11596-P-A, Qualification of the PHOENIX-P/ANC Nuclear Design System for Pressurized Water Reactor Cores, June 1988.
24. WCAP-12910 Rev. 1-A, Pressurizer Safety Valve Set Pressure Shift, May 1993.
25. WCAP-14565-P-A, VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis, October 1999.
26. WCAP-14882-P-A, RETRAN-02 Modeling and Qualification for Westinghouse Pressurized Water Reactor Non-LOCA Safety Analyses, April 1999.
27. WCAP-16009-P-A, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment Of Uncertainty Method (ASTRUM)," Revision 0, January 2005.
28. 50.59 Evaluation 1072, Unit 1 Cycle 26 Core Reload.

Page 8 of 17

Core Operating Limits Report Unit 1, Cycle 26 Revision 0 Table 1 Minimum Required Shutdown Margin, %

Number of Charging Pumps Running**

Mode 1*

0-1 Pump 2 Pumps 3 Pumps 0 - 22000 MWd/MTU - - -

Mode 2*

0-1 Pump 2 Pumps 3 Pumps 0 - 22000 MWd/MTU 2.0 2.0 2.0 Physics Testing in Mode 2 0-1 Pump 2 Pumps 3 Pumps 0 - 22000 MWd/MTU 0.5 0.5 0.5 Mode 3 Tave 520 °F (Most Reactive Rod Out) 0-1 Pump 2 Pumps 3 Pumps 0 - 22000 MWd/MTU 2.0 2.0 2.0 Mode 3 350 °F Tave < 520°F (Most Reactive Rod Out) 0-1 Pump 2 Pumps 3 Pumps 0 MWd/MTU 2.0 2.0 2.5 12000 MWd/MTU 2.0 2.0 2.0 22000 MWd/MTU 2.0 2.0 2.0 Mode 4 200 °F < Tave < 350°F (Most Reactive Rod Out) 0-1 Pump 2 Pumps 3 Pumps 0 MWd/MTU 2.0 4.0 6.5 12000 MWd/MTU 2.0 3.0 4.5 22000 MWd/MTU 2.0 2.0 2.5 Operational Mode Definitions, as per TS Table 1.1-1.

  • For Mode 1 and Mode 2 with Keff 1.0, the minimum shutdown margin requirements are provided by the Rod Insertion Limits.
    • Charging pump(s) in service only pertains to steady state operations. It does not include transitory operations. For example, operations such as starting a second charging pump in order to secure the operating pump would fall under the one pump in service column.

Page 9 of 17

Core Operating Limits Report Unit 1, Cycle 26 Revision 0 Table 1, Continued Minimum Required Shutdown Margin, %

Number of Charging Pumps Running**

Mode 5 68°F Tave 200°F (Most Reactive Rod Out) 0-1 Pump 2 Pumps 3 Pumps 0 MWd/MTU*** 2.5 4.5 7.0 12000 MWd/MTU 2.0 3.5 5.0 22000 MWd/MTU 2.0 2.0 3.0 Mode 6 68°F Tave < 200°F (ARI) 0-1 Pump 2 Pumps 3 Pumps 0 MWd/MTU*** 5.129 5.129 7.0 12000 MWd/MTU 5.129 5.129 5.129 22000 MWd/MTU 5.129 5.129 5.129 Mode 6 68°F Tave < 200°F (ARO) 0-1 Pump 2 Pumps 3 Pumps 0 MWd/MTU*** 5.129 5.5 8.5 12000 MWd/MTU 5.129 5.129 7.0 22000 MWd/MTU 5.129 5.129 5.129 Operational Mode Definitions, as per TS Table 1.1-1.

    • Charging pump(s) in service only pertains to steady state operations. It does not include transitory operations. For example, operations such as starting a second charging pump in order to secure the operating pump would fall under the one pump in service column.
      • These values are also applicable for the Unit 1 Cycle 25 end of cycle.

Page 10 of 17

Core Operating Limits Report Unit 1, Cycle 26 Revision 0 Table 2 - W(z) Values (Top 10% and Bottom 8% excluded)*

Height BU [MWd/MTU]

[ft] 150 4000 8000 13000 16000 18000 20000 AO = 0.70 AO = -1.71 AO = -3.30 AO = -4.80 AO = -0.04 AO = 0.81 AO = -0.10

[BOTTOM] 1 0.0 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 2 0.2 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 3 0.4 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 4 0.6 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 5 0.8 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 6 1.0 1.2964 1.2134 1.1709 1.1640 1.2375 1.2516 1.2658 7 1.2 1.2842 1.2042 1.1626 1.1552 1.2283 1.2411 1.2540 8 1.4 1.2702 1.1938 1.1534 1.1455 1.2182 1.2297 1.2411 9 1.6 1.2549 1.1825 1.1437 1.1353 1.2078 1.2178 1.2278 10 1.8 1.2383 1.1708 1.1336 1.1250 1.1972 1.2057 1.2141 11 2.0 1.2226 1.1581 1.1236 1.1146 1.1864 1.1932 1.2001 12 2.2 1.2083 1.1468 1.1129 1.1043 1.1755 1.1805 1.1855 13 2.4 1.1944 1.1388 1.1033 1.0942 1.1646 1.1677 1.1707 14 2.6 1.1802 1.1312 1.0995 1.0843 1.1536 1.1547 1.1558 15 2.8 1.1662 1.1236 1.0973 1.0746 1.1430 1.1404 1.1378 16 3.0 1.1513 1.1159 1.0955 1.0664 1.1308 1.1313 1.1319 17 3.2 1.1430 1.1109 1.0946 1.0643 1.1254 1.1313 1.1372 18 3.4 1.1423 1.1108 1.0945 1.0675 1.1290 1.1377 1.1464 19 3.6 1.1409 1.1115 1.0994 1.0752 1.1344 1.1471 1.1599 20 3.8 1.1389 1.1135 1.1047 1.0827 1.1389 1.1560 1.1730 21 4.0 1.1363 1.1158 1.1091 1.0893 1.1427 1.1636 1.1845 22 4.2 1.1328 1.1172 1.1130 1.0955 1.1455 1.1701 1.1947 23 4.4 1.1288 1.1181 1.1161 1.1008 1.1472 1.1753 1.2033 24 4.6 1.1264 1.1184 1.1185 1.1053 1.1479 1.1791 1.2102 25 4.8 1.1243 1.1178 1.1203 1.1104 1.1476 1.1815 1.2153 26 5.0 1.1216 1.1181 1.1210 1.1160 1.1461 1.1825 1.2190 27 5.2 1.1187 1.1212 1.1221 1.1214 1.1447 1.1822 1.2198 28 5.4 1.1151 1.1264 1.1263 1.1260 1.1451 1.1807 1.2163 29 5.6 1.1120 1.1314 1.1321 1.1292 1.1507 1.1816 1.2125 30 5.8 1.1167 1.1378 1.1386 1.1390 1.1595 1.1893 1.2191 31 6.0 1.1275 1.1459 1.1470 1.1543 1.1684 1.2016 1.2348 32 6.2 1.1358 1.1544 1.1583 1.1700 1.1759 1.2109 1.2459 33 6.4 1.1438 1.1618 1.1713 1.1848 1.1823 1.2191 1.2559 34 6.6 1.1509 1.1680 1.1833 1.1985 1.1876 1.2258 1.2639 35 6.8 1.1570 1.1751 1.1942 1.2111 1.1915 1.2307 1.2699 36 7.0 1.1621 1.1827 1.2039 1.2224 1.1941 1.2339 1.2736 37 7.2 1.1659 1.1891 1.2122 1.2321 1.1959 1.2351 1.2742 38 7.4 1.1684 1.1946 1.2189 1.2400 1.1971 1.2342 1.2713 39 7.6 1.1708 1.1995 1.2237 1.2460 1.1965 1.2311 1.2657 40 7.8 1.1720 1.2030 1.2266 1.2497 1.1941 1.2257 1.2573 41 8.0 1.1713 1.2046 1.2272 1.2511 1.1897 1.2179 1.2462 42 8.2 1.1690 1.2042 1.2255 1.2500 1.1835 1.2078 1.2321 43 8.4 1.1648 1.2018 1.2213 1.2462 1.1753 1.1952 1.2152 44 8.6 1.1590 1.1976 1.2149 1.2391 1.1640 1.1806 1.1972 45 8.8 1.1502 1.1902 1.2047 1.2327 1.1573 1.1689 1.1805 46 9.0 1.1482 1.1882 1.1999 1.2311 1.1576 1.1581 1.1586 47 9.2 1.1564 1.1945 1.2018 1.2328 1.1603 1.1481 1.1359 48 9.4 1.1612 1.1972 1.2056 1.2364 1.1612 1.1473 1.1334 49 9.6 1.1695 1.2032 1.2073 1.2379 1.1608 1.1454 1.1300 50 9.8 1.1774 1.2089 1.2117 1.2381 1.1588 1.1406 1.1224 51 10.0 1.1839 1.2132 1.2194 1.2412 1.1562 1.1401 1.1240 52 10.2 1.1896 1.2166 1.2259 1.2480 1.1560 1.1470 1.1379 53 10.4 1.1900 1.2158 1.2311 1.2528 1.1602 1.1524 1.1446 54 10.6 1.1937 1.2170 1.2374 1.2582 1.1656 1.1599 1.1542 55 10.8 1.2010 1.2154 1.2436 1.2639 1.1711 1.1688 1.1666 56 11.0 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Page 11 of 17

Core Operating Limits Report Unit 1, Cycle 26 Revision 0 Table 2 - Continued Height BU [MWd/MTU]

[ft] 150 4000 8000 13000 16000 18000 20000 AO = 0.70 AO = -1.71 AO = -3.30 AO = -4.80 AO = -0.04 AO = 0.81 AO = -0.10 57 11.2 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 58 11.4 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 59 11.6 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 60 11.8 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

[TOP] 61 12.0 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

  • Linear extrapolation based on a line between 18,000 MWD/MTU and 20,000 MWD/MTU is adequate for addressing burnups beyond 20,000 MWD/MTU.

Table 3 FWQ(Z) Penalty Factor Cycle Burnup (MWD/MTU) FWQ(Z) Penalty Factor 14632 1.0200 14779 1.0203 14925 1.0202 15071 1.0200 W

F Q(Z) = 1.020 for all burnups except those listed above. Linear interpolation is adequate for intermediate cycle burnups.

Page 12 of 17

Core Operating Limits Report Unit 1, Cycle 26 Revision 0 Figure 1 Reactor Core Safety Limits 680 2425 psia 660 2250 psia Unacceptable 640 1850 psia RCS Tavg (°F) 620 600 Acceptable 580 560 540 0 0.2 0.4 0.6 0.8 1 1.2 1.4 Fraction of 1650 MWt Rated Thermal Power Page 13 of 17

Core Operating Limits Report Unit 1, Cycle 26 Revision 0 Figure 2 Rod Insertion Limit, 128 Step Tip-to-Tip Bank B 200 150 Bank Position, Steps Bank C 100 Bank D 50 0

0 20 40 60 80 100 Power Level, % of Rated Thermal Power Bank Positions Given By:

  • Bank D = (150 / 63) * (P - 100) + 185
  • Bank C = (150 / 63) * (P - 100) + 185 + 128
  • Bank B = (150 / 63) * (P - 100) + 185 + 128 + 128 NOTE: The top of the active fuel height corresponds to 224 steps. The ARO parking position may be any position above 224 steps.

Page 14 of 17

Core Operating Limits Report Unit 1, Cycle 26 Revision 0 Figure 3 Rod Insertion Limit, 128 Step Tip-to-Tip, One Bottomed Rod (Technical Specification 3.1.4, Condition B) 224 200 Bank C 150 Operation Bank Position, Steps Forbidden in this Region 100 Bank D 50 0

0 20 40 60 80 100 Power Level, % of Rated Thermal Power Bank Positions Given By:

  • Bank D = (150 / 63) * (P - 90) + 224
  • Bank C = (150 / 63) * (P - 90) + 224 + 128 NOTE: The top of the active fuel height corresponds to 224 steps. The ARO parking position may be any position above 224 steps.

Page 15 of 17

Core Operating Limits Report Unit 1, Cycle 26 Revision 0 Figure 4 Rod Insertion Limit, 128 Step Tip-to-Tip, One Inoperable Rod (Technical Specification 3.1.4, Condition A) 224 200 Bank C 150 Bank Position, Steps Operation Forbidden in this Region Bank D 100 50 0

0 20 40 60 80 100 Power Level, % of Rated Thermal Power Bank Positions Given By:

  • Bank D = (150 / 63) * (P - 70) + 224
  • Bank C = (150 / 63) * (P - 70) + 224 + 128 NOTE: The top of the active fuel height corresponds to 224 steps. The ARO parking position may be any position above 224 steps.

Page 16 of 17

Core Operating Limits Report Unit 1, Cycle 26 Revision 0 Figure 5 Flux Difference Operating Envelope 110

-9 8 100 Unacceptable Unacceptable 90 80 Acceptable 70 60

% Power 50

-22 21 40 30 20 10 0

-25 -20 -15 -10 -5 0 5 10 15 20 25 I %

Page 17 of 17

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