ML22294A129

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Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 1, Cycle 33, Revision 0
ML22294A129
Person / Time
Site: Prairie Island 
Issue date: 10/21/2022
From: Hanson H
Northern States Power Company, Minnesota, Xcel Energy
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
L-Pl-22-043
Download: ML22294A129 (1)
v • d • e


Text

fl Xcel Energy October 21, 2022 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant, Unit 1 Docket No. 50-282 Renewed Facility Operating License No. DPR-42 1717 Wakonade Drive Welch, MN 55089 L-Pl-22-043 TS 5.6.5.d Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP)

Unit 1, Cycle 33, Revision 0 Pursuant to the requirements of Technical Specification 5.6.5.d, Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"),

hereby submits the COLR for the PINGP Unit 1, Cycle 33, Revision 0. The COLR provides the cycle-specific values of the limits established using NRC approved methodologies such that the applicable limits of the plant safety analysis are met.

If you have any questions about this submittal, please contact Carrie Seipp, Senior Regulatory Engineer, at 612-330-5576.

Summary of Commitments mmitments and no revisions to existing commitments.

ger, raI erating 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 33 REVISION 0 35 pages follow

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record of Revision Page 1 of 7 Unit Cycle Revision No.

Approval 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).

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record of Revision Page 2 of 7 Unit Cycle Revision No.

Approval 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 H

F 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 H

F 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.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record of Revision Page 3 of 7 Unit Cycle Revision No.

Approval 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.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record of Revision Page 4 of 7 Unit Cycle Revision No.

Approval 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.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record of Revision Page 5 of 7 Unit Cycle Revision No.

Approval 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.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record of Revision Page 6 of 7 Unit Cycle Revision No.

Approval 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

1 25 26 0

0 9/26/08 9/24/09 Updated for Unit 2 Cycle 25 Updated for Unit 1 Cycle 26 2

2 26 26 0

1 5/3/10 5/17/10 Updated for Unit 2 Cycle 26 Updated to include part power W(z) factors 1

2 1

1 1

1 26 26 26 26 27 27 1

2 2

3 0

1 9/2/10 9/30/10 9/30/10 12/17/10 5/5/11 6/2/11 Updated for second set of W(z) factors Updated for Measurement Uncertainty Recapture power uprate to 1677 MWth and for a second set of W(z) factors Updated for Measurement Uncertainty Recapture power uprate to 1677 MWth Updated SDM in Table 1 for Mode 2 to say 1.9.

Updated for Unit 1 Cycle 27 Updated for Unit 1 Cycle 27 Modes 1 through 6 2

27 0

3/28/12 Updated for Unit 2 Cycle 27 1

28 0

11/29/12 Updated for Unit 1 Cycle 28

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record of Revision Page 7 of 7 Unit Cycle Revision No.

Approval Date Remarks 2

28 0

11/23/13 Updated for Unit 2 Cycle 28 1

2 29 29 0

0 10/23/14 11/05/15 Updated for Unit 1 Cycle 29 Updated for Unit 2 Cycle 29 1

2 1

2 2

30 30 31 31 31 0

0 0

0 1

10/25/16 10/24/17 09/06/18 10/14/19 09/14/20 Updated for Unit 1 Cycle 30 Updated for Unit 2 Cycle 30 Updated for Unit 1 Cycle 31 Updated for Unit 2 Cycle 31 Updated to revise Table 2 and Table 3 due to Flexible Power Operation 1

2 2

32 32 32 0

0 1

09/21/20 10/11/21 10/25/21 Updated for Unit 1 Cycle 32 Updated for Unit 2 Cycle 32 Updated to clarify power value used in calculation of FQW(Z) 1 33 0

10/13/22 Updated for Unit 1 Cycle 33

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 1 of 28 PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT UNIT 1 - CYCLE 33 REVISION 0 Reviewed By: Reviewed per LDC 604000000633 Darius Ahrar Manager, Nuclear Analysis & Design Approved By: Reviewed per LDC 604000000633 Mark Brossart Manager, Engineering Note: This report is not part of the Technical Specifications This report is referenced in the Technical Specifications

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 2 of 28 PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT UNIT 1 - CYCLE 33 REVISION 0 This report provides the values of the limits for Unit 1 Cycle 33 as required by Technical Specification 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 Safety Limits

2.

3.1.1 Shutdown Margin Requirements

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 Technical Specification Table 3.3.1-1 (Note 1 and Note 2)

11.

3.4.1 RCS Pressure, Temperature, and Flow - Departure from Nucleate Boiling (DNB) Limits

12.

3.9.1 Refueling Boron Concentration

1.

2.1.1 Reactor Core Safety Limits Reactor Core Safety Limits are shown in Figure 1.

Reference Technical Specification 2.1.1.

2.

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

Reference Technical Specification 3.1.1.

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 3 of 28

3.

3.1.3 Isothermal Temperature Coefficient (ITC)

ITC Upper limit:

a. < 5 pcm/°F for power levels < 70% RTP; and
b. 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 3.1.3.
4.

3.1.5 Shutdown Bank Insertion Limits The shutdown rods shall be fully withdrawn.

Reference Technical Specification 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 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 3.1.8.

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 4 of 28

7.

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

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

(z) =

(z) *

  • 1.0815 for P > 0.5 (z) =

(z) *

  • 1.0815 for P 0.5 is the measured planar radial peaking factor.

P is the ratio of thermal power at the time of surveillance to rated thermal power.

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

The T(Z) values are provided in Tables 2 and 4.

The T(Z) values in Table 2 are applicable to Figure 5, which represents RAOC Operation Space #1 (ROS1).

The T(Z) values in Table 4 are applicable to Figure 6, which represents RAOC Operating Space #2 (ROS2). Through Table 6, Table 4 is also associated with Figures 7 and 8.

The Rj Penalty Factors associated with Figure 5 and Table 2 (ROS1) are provided in Table 3.

The Rj Penalty Factors associated with Figure 6 and Table 4 (ROS2) are provided in Table 5. Through Table 6, Table 5 is also associated with Figures 7 and 8.

The AXY(Z) factors adjust the surveillance to the reference conditions assumed in generating the T(z) factors. AXY(Z) may be assumed to equal 1.0 or may be determined for specific surveillance conditions using the approved methods listed in TS 5.6.5.

CFQ Ft{ (z) ~ p

  • K(z) for P > 0.5 CFQ Ft{ (z) ~
  • K(z) for P ~ 0.5
0.

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 5 of 28 Either ROS1 or ROS2 may be implemented at any time during Cycle 33.

If ROS1 is implemented and entering LCO 3.2.1 Condition B for FWQ(Z) not within limits, EITHER take Action B.1.1 by implementing ROS2, OR take Action B.2.1 by using Table 6 to determine required THERMAL POWER and AFD limits based on Required FWQ(Z) margin improvement available in ROS1.

If ROS2 is implemented and entering LCO 3.2.1 Condition B for FWQ(Z) not within limits, take Action B.2.1 by using Table 6 to determine required THERMAL POWER and AFD limits based on Required FWQ(Z) margin improvement available in ROS2.

Reference Technical Specification 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)]

where:

P is the fraction of RATED THERMAL POWER at which the core is operating.

Reference Technical Specification 3.2.2.

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 6 of 28

9.

3.2.3 Axial Flux Difference (AFD)

The indicated axial flux difference shall be maintained within the allowed operational space defined by either Figure 5, if ROS1 is implemented, or Figure 6 if ROS2 is implemented. If implementing TS 3.2.1 Required Action B.2.1. the AFD shall be maintained within the allowed spaced defined by Figure 7 or 8, as determined by Table 6 and the condition that led to the required action.

Reference Technical Specification 3.2.3.

10.

3.3.1 Reactor Trip System (RTS) Instrumentation Overtemperature T and Overpower T Parameter Values for Technical Specification Table 3.3.1-1 (Note 1 and Note 2):

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(I)

=

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(I) = 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.

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 7 of 28 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 Reference Technical Specification 3.3.1.

11.

3.4.1 RCS Pressure, Temperature, and Flow - Departure from Nucleate Boiling (DNB)

Limits The DNB Limits are:

Pressurizer pressure limit = 2190 psia RCS average temperature limit = 564°F RCS total flow rate limit = 178,000 gpm Reference Technical Specification 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 3.9.1.

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 8 of 28 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.

WCAP-16045-P-A Addendum 1-A, Qualification of the NEXUS Nuclear Data Methodology, August 2007.

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 ZIRLO' 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 Power 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.

ZIRLO' is a registered trademark of Westinghouse Electric Company LLC, its Affiliates and/or its Subsidiaries in the United States of America and may be registered in other countries throughout the world. All rights reserved. Unauthorized use is strictly prohibited.

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 9 of 28

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-16045-P-A, Qualification of the Two-Dimensional Transport Code PARAGON, August 2004.

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.

Caldon, Inc. Engineering Report-80P, Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM ' System, Revision 0, March 1997.

29.

Caldon, Inc. Engineering Report-157P, Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFM ' Check or CheckPlus' System, Revision 5, October 2001.

30.

WCAP-12610-P-A, VANTAGE+ Fuel Assembly Reference Core Report, April 1995.

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 10 of 28

31.

WCAP-12610-P-A and CENPD-404-P-A, Addendum 1-A, Optimized ZIRLO', July 2006.

32.

Design Equivalent Change 601000003539 Rev. 0 1R33 Core Reload.

33.

WCAP-17661-P-A, Improved RAOC and CAOC FQ Surveillance Technical Specifications, February 2019.

Optimized ZIRLO' is a trademark of Westinghouse Electric Company LLC, its Affiliates and/or its Subsidiaries in the United States of America and may be registered in other countries throughout the world. All rights reserved. Unauthorized use is strictly prohibited.

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 11 of 28 Table 1 Minimum Required Shutdown Margin, %

Number of Charging Pumps Running**

Mode 1*

0-1 Pump 2 Pumps 3 Pumps 0 - 24750 MWd/MTU Mode 2*

0-1 Pump 2 Pumps 3 Pumps 0 - 24750 MWd/MTU 1.7 1.7 1.7 Physics Testing in Mode 2 0-1 Pump 2 Pumps 3 Pumps 0 - 24750 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 - 24750 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 2.0 3000 MWd/MTU 2.0 2.0 2.0 6000 MWd/MTU 2.0 2.0 2.0 11000 MWd/MTU 2.0 2.0 2.0 16000 MWd/MTU 2.0 2.0 2.0 24750 MWd/MTU 2.0 2.0 2.0 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.

Note: Linear interpolation between burnup steps is allowed. Extrapolation is not allowed.

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 12 of 28 Table 1, Continued Minimum Required Shutdown Margin, %

Number of Charging Pumps Running**

Mode 4 200°F < Tave < 350°F (Most Reactive Rod Out) 0-1 Pump 2 Pumps 3 Pumps 0 MWD/MTU 2.0 3.5 5.5 3000 MWd/MTU 2.0 3.5 5.5 6000 MWd/MTU 2.0 3.5 5.5 11000 MWd/MTU 2.0 3.5 5.5 16000 MWd/MTU 2.0 3.0 4.5 24750 MWd/MTU 2.0 2.0 2.5 Mode 5 68°F Tave 200°F (Most Reactive Rod Out) 0-1 Pump 2 Pumps 3 Pumps 0 MWd/MTU***

2.0 4.0 6.0 3000 MWd/MTU 2.0 4.0 6.5 6000 MWd/MTU 2.0 4.0 6.5 11000 MWd/MTU 2.0 4.0 6.0 16000 MWd/MTU 2.0 3.5 5.5 24750 MWd/MTU 2.0 2.0 3.0 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 32 end of cycle.

Note: Linear interpolation between burnup steps is allowed. Extrapolation is not allowed.

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 13 of 28 Table 1, Continued Minimum Required Shutdown Margin, %

Number of Charging Pumps Running**

Mode 6 68°F Tave < 200°F (ARI) 0-1 Pump 2 Pumps 3 Pumps 0 MWd/MTU***

5.129 5.129 6.0 3000 MWd/MTU 5.129 5.129 6.0 6000 MWd/MTU 5.129 5.129 6.0 11000 MWd/MTU 5.129 5.129 6.0 16000 MWd/MTU 5.129 5.129 5.129 24750 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 5.129 8.0 3000 MWd/MTU 5.129 5.129 8.0 6000 MWd/MTU 5.129 5.5 8.0 11000 MWd/MTU 5.129 5.129 8.0 16000 MWd/MTU 5.129 5.129 7.0 24750 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 32 end of cycle.

Note: Linear interpolation between burnup steps is allowed. Extrapolation is not allowed.

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 14 of 28 Table 2 - T(z) Factors associated with Figure 5 (ROS1) (Top 10% and Bottom 8% excluded)*

Height BU [MWd/MTU]

[ft]

150 1000 2000 2500 3000 4000 5000 6000 7000 8000

[BOTTOM]

1 0.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 2

0.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 3

0.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 4

0.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 5

0.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 6

1.00 1.0981 1.0692 1.0290 1.0262 1.0024 1.0205 1.0238 1.0415 1.0478 1.0822 7

1.20 1.1430 1.1194 1.0838 1.0829 1.0598 1.0809 1.0857 1.1047 1.1111 1.1465 8

1.40 1.1738 1.1555 1.1245 1.1253 1.1029 1.1258 1.1313 1.1502 1.1557 1.1900 9

1.60 1.2040 1.1904 1.1638 1.1660 1.1443 1.1684 1.1740 1.1923 1.1964 1.2289 10 1.80 1.2140 1.2048 1.1825 1.1860 1.1654 1.1899 1.1955 1.2128 1.2153 1.2457 11 2.00 1.1825 1.1775 1.1602 1.1648 1.1460 1.1700 1.1757 1.1916 1.1931 1.2203 12 2.20 1.1468 1.1456 1.1372 1.1420 1.1252 1.1481 1.1534 1.1677 1.1703 1.1882 13 2.40 1.1768 1.1785 1.1725 1.1750 1.1621 1.1805 1.1878 1.1974 1.2020 1.2158 14 2.60 1.2243 1.2282 1.2280 1.2259 1.2222 1.2336 1.2416 1.2452 1.2520 1.2578 15 2.80 1.2387 1.2447 1.2510 1.2507 1.2526 1.2581 1.2632 1.2611 1.2703 1.2687 16 3.00 1.2292 1.2374 1.2495 1.2544 1.2561 1.2591 1.2609 1.2562 1.2643 1.2580 17 3.20 1.2259 1.2365 1.2494 1.2561 1.2582 1.2596 1.2602 1.2562 1.2607 1.2528 18 3.40 1.2306 1.2430 1.2576 1.2644 1.2667 1.2676 1.2670 1.2633 1.2632 1.2535 19 3.60 1.2433 1.2582 1.2738 1.2804 1.2826 1.2830 1.2809 1.2777 1.2710 1.2594 20 3.80 1.2583 1.2753 1.2917 1.2979 1.3000 1.2996 1.2962 1.2932 1.2811 1.2676 21 4.00 1.2532 1.2716 1.2884 1.2949 1.2971 1.2962 1.2918 1.2884 1.2733 1.2581 22 4.20 1.2121 1.2320 1.2483 1.2558 1.2581 1.2575 1.2530 1.2485 1.2336 1.2183 23 4.40 1.1729 1.1940 1.2109 1.2184 1.2210 1.2205 1.2159 1.2101 1.1953 1.1815 24 4.60 1.2039 1.2267 1.2443 1.2517 1.2541 1.2529 1.2470 1.2387 1.2223 1.2089 25 4.80 1.2519 1.2760 1.2941 1.3016 1.3038 1.3016 1.2942 1.2830 1.2658 1.2516 26 5.00 1.2684 1.2931 1.3112 1.3177 1.3199 1.3173 1.3090 1.2959 1.2802 1.2649 27 5.20 1.2600 1.2844 1.3028 1.3077 1.3099 1.3073 1.2990 1.2860 1.2714 1.2551 28 5.40 1.2524 1.2769 1.2964 1.3004 1.3025 1.2998 1.2922 1.2797 1.2643 1.2476 29 5.60 1.2536 1.2798 1.2997 1.3035 1.3056 1.3029 1.2945 1.2808 1.2658 1.2494 30 5.80 1.2641 1.2908 1.3107 1.3140 1.3161 1.3136 1.3048 1.2908 1.2761 1.2589 31 6.00 1.2789 1.3052 1.3247 1.3284 1.3304 1.3272 1.3185 1.3050 1.2907 1.2718 32 6.20 1.2717 1.2972 1.3163 1.3217 1.3238 1.3190 1.3108 1.2985 1.2855 1.2650 33 6.40 1.2283 1.2524 1.2707 1.2781 1.2805 1.2745 1.2677 1.2575 1.2465 1.2262 34 6.61 1.1886 1.2113 1.2291 1.2381 1.2407 1.2344 1.2289 1.2200 1.2110 1.1964 35 6.81 1.2224 1.2427 1.2638 1.2701 1.2728 1.2687 1.2633 1.2514 1.2431 1.2285 36 7.01 1.2713 1.2905 1.3139 1.3178 1.3191 1.3178 1.3124 1.2980 1.2903 1.2763 37 7.21 1.2862 1.3044 1.3289 1.3320 1.3324 1.3326 1.3278 1.3126 1.3062 1.2935 38 7.41 1.2752 1.2919 1.3173 1.3200 1.3208 1.3215 1.3180 1.3025 1.2982 1.2879 39 7.61 1.2655 1.2808 1.3066 1.3088 1.3098 1.3113 1.3094 1.2937 1.2918 1.2842 40 7.81 1.2651 1.2786 1.3054 1.3069 1.3082 1.3103 1.3092 1.2933 1.2932 1.2882 41 8.01 1.2702 1.2820 1.3100 1.3108 1.3122 1.3149 1.3150 1.2980 1.3004 1.2993 42 8.21 1.2796 1.2887 1.3150 1.3149 1.3166 1.3198 1.3211 1.3064 1.3082 1.3115 43 8.41 1.2689 1.2754 1.2960 1.2954 1.2974 1.3013 1.3039 1.2958 1.2935 1.3011 44 8.61 1.2217 1.2273 1.2407 1.2395 1.2419 1.2469 1.2512 1.2509 1.2456 1.2561 45 8.81 1.1795 1.1837 1.1912 1.1897 1.1924 1.1980 1.2035 1.2102 1.2049 1.2151 46 9.01 1.2087 1.2116 1.2168 1.2180 1.2205 1.2229 1.2258 1.2379 1.2306 1.2416 47 9.21 1.2491 1.2503 1.2539 1.2584 1.2604 1.2588 1.2612 1.2756 1.2719 1.2830 48 9.41 1.2577 1.2575 1.2566 1.2628 1.2644 1.2605 1.2659 1.2818 1.2802 1.2909 49 9.61 1.2415 1.2399 1.2345 1.2383 1.2398 1.2396 1.2479 1.2622 1.2611 1.2737 50 9.81 1.2235 1.2197 1.2125 1.2114 1.2133 1.2202 1.2289 1.2389 1.2391 1.2553 51 10.01 1.2151 1.2086 1.1988 1.1956 1.1975 1.2041 1.2132 1.2224 1.2192 1.2365 52 10.21 1.2099 1.1990 1.1860 1.1828 1.1841 1.1900 1.1993 1.2048 1.2040 1.2207 53 10.41 1.1999 1.1852 1.1689 1.1631 1.1638 1.1691 1.1782 1.1807 1.1835 1.1999 54 10.61 1.1562 1.1396 1.1204 1.1149 1.1149 1.1192 1.1279 1.1284 1.1342 1.1506 55 10.81 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 56 11.01 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 57 11.21 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 58 11.41 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 59 11.61 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 60 11.81 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

[TOP] 61 12.01 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

  • Linear extrapolation based on a line between 20,000 MWD/MTU and 22,000 MWD/MTU is adequate for addressing burnups beyond 22,000 MWD/MTU.

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 15 of 28 Table 2 (cont.) - T(z) Factors associated with Figure 5 (ROS1) (Top 10% and Bottom 8% excluded)*

Height BU [MWd/MTU]

[ft]

9000 10000 11000 12000 13000 14000 16000 18000 20000 22000

[BOTTOM]

1 0.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 2

0.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 3

0.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 4

0.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 5

0.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 6

1.00 1.0989 1.1072 1.1418 1.1482 1.1743 1.2066 1.2282 1.2520 1.2726 1.2705 7

1.20 1.1631 1.1707 1.2054 1.2105 1.2354 1.2660 1.2823 1.3013 1.3172 1.3103 8

1.40 1.2052 1.2110 1.2436 1.2462 1.2681 1.2951 1.3044 1.3177 1.3283 1.3171 9

1.60 1.2421 1.2457 1.2756 1.2753 1.2936 1.3166 1.3194 1.3273 1.3333 1.3184 10 1.80 1.2570 1.2585 1.2853 1.2826 1.2977 1.3169 1.3147 1.3186 1.3214 1.3047 11 2.00 1.2299 1.2299 1.2532 1.2490 1.2612 1.2770 1.2722 1.2738 1.2754 1.2594 12 2.20 1.1959 1.1943 1.2138 1.2080 1.2173 1.2299 1.2231 1.2231 1.2242 1.2101 13 2.40 1.2211 1.2170 1.2327 1.2239 1.2296 1.2384 1.2283 1.2251 1.2245 1.2105 14 2.60 1.2608 1.2539 1.2656 1.2535 1.2558 1.2608 1.2485 1.2409 1.2389 1.2254 15 2.80 1.2693 1.2609 1.2698 1.2560 1.2548 1.2572 1.2423 1.2342 1.2311 1.2178 16 3.00 1.2563 1.2470 1.2535 1.2389 1.2345 1.2350 1.2186 1.2119 1.2092 1.1969 17 3.20 1.2496 1.2384 1.2417 1.2251 1.2191 1.2167 1.2025 1.1949 1.1944 1.1857 18 3.40 1.2489 1.2361 1.2355 1.2173 1.2117 1.2046 1.1927 1.1867 1.1855 1.1803 19 3.60 1.2538 1.2414 1.2362 1.2177 1.2132 1.2039 1.1921 1.1867 1.1837 1.1811 20 3.80 1.2628 1.2510 1.2409 1.2219 1.2173 1.2048 1.1932 1.1891 1.1828 1.1855 21 4.00 1.2546 1.2424 1.2305 1.2108 1.2056 1.1913 1.1809 1.1777 1.1712 1.1785 22 4.20 1.2144 1.2029 1.1898 1.1712 1.1664 1.1514 1.1432 1.1417 1.1402 1.1478 23 4.40 1.1760 1.1652 1.1510 1.1356 1.1291 1.1138 1.1074 1.1074 1.1114 1.1185 24 4.60 1.2002 1.1886 1.1735 1.1574 1.1477 1.1320 1.1249 1.1234 1.1309 1.1361 25 4.80 1.2394 1.2269 1.2104 1.1932 1.1800 1.1637 1.1571 1.1509 1.1621 1.1662 26 5.00 1.2508 1.2371 1.2217 1.2033 1.1875 1.1714 1.1670 1.1597 1.1717 1.1761 27 5.20 1.2409 1.2262 1.2124 1.1931 1.1759 1.1609 1.1578 1.1531 1.1630 1.1686 28 5.40 1.2328 1.2185 1.2039 1.1854 1.1672 1.1532 1.1486 1.1455 1.1540 1.1603 29 5.60 1.2331 1.2193 1.2053 1.1875 1.1681 1.1550 1.1476 1.1448 1.1530 1.1574 30 5.80 1.2424 1.2279 1.2146 1.1957 1.1761 1.1640 1.1530 1.1497 1.1570 1.1584 31 6.00 1.2563 1.2394 1.2274 1.2079 1.1909 1.1782 1.1664 1.1615 1.1658 1.1682 32 6.20 1.2512 1.2344 1.2224 1.2055 1.1920 1.1781 1.1686 1.1622 1.1658 1.1720 33 6.40 1.2147 1.2029 1.1878 1.1763 1.1651 1.1507 1.1440 1.1372 1.1462 1.1521 34 6.61 1.1845 1.1763 1.1596 1.1521 1.1432 1.1284 1.1243 1.1168 1.1301 1.1361 35 6.81 1.2151 1.2077 1.1890 1.1824 1.1745 1.1608 1.1539 1.1444 1.1602 1.1648 36 7.01 1.2611 1.2540 1.2353 1.2290 1.2194 1.2088 1.1959 1.1863 1.2022 1.2050 37 7.21 1.2773 1.2717 1.2570 1.2515 1.2384 1.2318 1.2155 1.2065 1.2211 1.2227 38 7.41 1.2722 1.2691 1.2586 1.2536 1.2390 1.2343 1.2177 1.2087 1.2214 1.2222 39 7.61 1.2696 1.2690 1.2588 1.2541 1.2401 1.2362 1.2191 1.2102 1.2208 1.2205 40 7.81 1.2742 1.2751 1.2659 1.2613 1.2487 1.2443 1.2265 1.2174 1.2253 1.2237 41 8.01 1.2856 1.2880 1.2799 1.2753 1.2644 1.2592 1.2404 1.2310 1.2356 1.2322 42 8.21 1.2970 1.3010 1.2941 1.2893 1.2804 1.2744 1.2548 1.2452 1.2462 1.2406 43 8.41 1.2865 1.2922 1.2871 1.2824 1.2762 1.2697 1.2502 1.2414 1.2388 1.2321 44 8.61 1.2421 1.2497 1.2472 1.2431 1.2406 1.2341 1.2168 1.2103 1.2051 1.1991 45 8.81 1.2017 1.2114 1.2114 1.2077 1.2104 1.2039 1.1903 1.1873 1.1804 1.1735 46 9.01 1.2291 1.2395 1.2424 1.2373 1.2420 1.2358 1.2226 1.2179 1.2082 1.1981 47 9.21 1.2736 1.2810 1.2842 1.2790 1.2853 1.2784 1.2684 1.2572 1.2469 1.2325 48 9.41 1.2867 1.2893 1.2935 1.2867 1.2954 1.2889 1.2884 1.2727 1.2605 1.2479 49 9.61 1.2720 1.2734 1.2786 1.2747 1.2843 1.2823 1.2860 1.2742 1.2582 1.2517 50 9.81 1.2536 1.2592 1.2631 1.2688 1.2764 1.2817 1.2819 1.2783 1.2580 1.2586 51 10.01 1.2401 1.2507 1.2543 1.2640 1.2718 1.2821 1.2861 1.2848 1.2684 1.2688 52 10.21 1.2273 1.2432 1.2463 1.2600 1.2676 1.2833 1.2928 1.2927 1.2815 1.2812 53 10.41 1.2078 1.2276 1.2288 1.2479 1.2543 1.2764 1.2923 1.2932 1.2885 1.2900 54 10.61 1.1605 1.1817 1.1831 1.2052 1.2113 1.2383 1.2610 1.2642 1.2680 1.2744 55 10.81 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 56 11.01 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 57 11.21 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 58 11.41 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 59 11.61 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 60 11.81 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

[TOP] 61 12.01 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

  • Linear extrapolation based on a line between 20,000 MWD/MTU and 22,000 MWD/MTU is adequate for addressing burnups beyond 22,000 MWD/MTU.

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 16 of 28 Table 3: RJ Margin Decrease Factors associated with Figure 5 (ROS1) and Table 2 Cycle Burnup (MWD/MTU)

RJ Penalty Multiplier Cycle Burnup (MWD/MTU)

RJ Penalty Multiplier Cycle Burnup (MWD/MTU)

RJ Penalty Multiplier 150 1.017 7183 1.013 14216 1.002 322 1.017 7354 1.014 14387 1.001 493 1.016 7526 1.017 14559 1.000 665 1.015 7697 1.017 14730 1.000 836 1.013 7869 1.016 14902 1.000 1008 1.011 8041 1.014 15073 1.000 1179 1.009 8212 1.012 15245 1.000 1351 1.007 8384 1.010 15416 1.000 1522 1.006 8555 1.007 15588 1.000 1694 1.004 8727 1.006 15760 1.000 1865 1.002 8898 1.007 15931 1.000 2037 1.001 9070 1.008 16103 1.000 2208 1.001 9241 1.014 16274 1.000 2380 1.000 9413 1.015 16446 1.000 2551 1.000 9584 1.020 16617 1.000 2723 1.000 9756 1.022 16789 1.000 2895 1.000 9927 1.023 16960 1.000 3066 1.000 10099 1.023 17132 1.000 3238 1.000 10270 1.021 17303 1.000 3409 1.000 10442 1.018 17475 1.000 3581 1.000 10614 1.012 17646 1.000 3752 1.000 10785 1.011 17818 1.000 3924 1.000 10957 1.010 17989 1.000 4095 1.000 11128 1.011 18161 1.000 4267 1.004 11300 1.011 18333 1.000 4438 1.008 11471 1.012 18504 1.000 4610 1.012 11643 1.018 18676 1.000 4781 1.015 11814 1.019 18847 1.001 4953 1.017 11986 1.020 19019 1.000 5124 1.018 12157 1.022 19190 1.000 5296 1.017 12329 1.022 19362 1.000 5468 1.016 12500 1.020 19533 1.000 5639 1.014 12672 1.019 19705 1.000 5811 1.012 12843 1.018 19876 1.000 5982 1.010 13015 1.017 20048 1.000 6154 1.007 13187 1.015 20219 1.000 6325 1.006 13358 1.013 20391 1.000 6497 1.007 13530 1.008 20562 1.000 6668 1.008 13701 1.006 6840 1.009 13873 1.004 7011 1.011 14044 1.003 Values may be interpolated to the surveillance cycle burnup. The Rj factor value for the last burnup step shall be used for all burnups greater than the last burnup step.

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 17 of 28 Table 4 - T(z) Factors associated with Figures 6, 7, and 8 (ROS2) (Top 10% and Bottom 8% excluded)*

Height BU [MWd/MTU]

[ft]

150 1000 2000 2500 3000 4000 5000 6000 7000 8000

[BOTTOM]

1 0.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 2

0.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 3

0.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 4

0.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 5

0.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 6

1.00 1.0614 1.0330 1.0086 0.9913 0.9884 0.9993 1.0022 1.0058 1.0336 1.0440 7

1.20 1.1054 1.0821 1.0627 1.0466 1.0452 1.0588 1.0631 1.0674 1.0964 1.1066 8

1.40 1.1359 1.1176 1.1031 1.0883 1.0879 1.1033 1.1082 1.1121 1.1405 1.1494 9

1.60 1.1659 1.1523 1.1422 1.1286 1.1290 1.1456 1.1507 1.1536 1.1809 1.1878 10 1.80 1.1766 1.1672 1.1613 1.1489 1.1501 1.1674 1.1725 1.1744 1.2000 1.2050 11 2.00 1.1472 1.1419 1.1402 1.1294 1.1312 1.1488 1.1539 1.1550 1.1782 1.1817 12 2.20 1.1137 1.1157 1.1178 1.1085 1.1107 1.1282 1.1331 1.1330 1.1534 1.1518 13 2.40 1.1442 1.1454 1.1505 1.1416 1.1438 1.1612 1.1652 1.1632 1.1808 1.1799 14 2.60 1.1916 1.1950 1.2026 1.1948 1.1986 1.2128 1.2155 1.2108 1.2258 1.2220 15 2.80 1.2078 1.2129 1.2225 1.2216 1.2253 1.2323 1.2339 1.2291 1.2402 1.2348 16 3.00 1.2010 1.2091 1.2203 1.2257 1.2277 1.2302 1.2309 1.2274 1.2333 1.2269 17 3.20 1.1996 1.2091 1.2220 1.2290 1.2311 1.2323 1.2322 1.2286 1.2319 1.2236 18 3.40 1.2064 1.2168 1.2315 1.2391 1.2414 1.2422 1.2404 1.2367 1.2356 1.2262 19 3.60 1.2230 1.2352 1.2500 1.2563 1.2587 1.2587 1.2560 1.2522 1.2459 1.2338 20 3.80 1.2419 1.2565 1.2718 1.2765 1.2787 1.2786 1.2751 1.2689 1.2585 1.2451 21 4.00 1.2400 1.2563 1.2731 1.2775 1.2795 1.2799 1.2754 1.2660 1.2537 1.2402 22 4.20 1.2022 1.2198 1.2374 1.2415 1.2438 1.2446 1.2400 1.2294 1.2169 1.2044 23 4.40 1.1660 1.1847 1.2062 1.2101 1.2126 1.2137 1.2059 1.1957 1.1827 1.1712 24 4.60 1.1994 1.2197 1.2389 1.2423 1.2447 1.2453 1.2393 1.2280 1.2138 1.2011 25 4.80 1.2495 1.2713 1.2914 1.2941 1.2963 1.2963 1.2888 1.2761 1.2603 1.2461 26 5.00 1.2672 1.2908 1.3105 1.3133 1.3154 1.3147 1.3064 1.2933 1.2772 1.2622 27 5.20 1.2584 1.2839 1.3029 1.3064 1.3085 1.3067 1.2982 1.2851 1.2705 1.2545 28 5.40 1.2506 1.2769 1.2964 1.3004 1.3025 1.2998 1.2912 1.2775 1.2643 1.2476 29 5.60 1.2532 1.2798 1.2997 1.3035 1.3056 1.3029 1.2943 1.2801 1.2658 1.2494 30 5.80 1.2641 1.2908 1.3107 1.3140 1.3160 1.3136 1.3049 1.2908 1.2761 1.2589 31 6.00 1.2783 1.3052 1.3247 1.3284 1.3304 1.3272 1.3185 1.3050 1.2907 1.2717 32 6.20 1.2707 1.2972 1.3162 1.3217 1.3238 1.3190 1.3108 1.2985 1.2855 1.2651 33 6.40 1.2268 1.2524 1.2707 1.2781 1.2805 1.2745 1.2677 1.2575 1.2465 1.2261 34 6.61 1.1867 1.2113 1.2287 1.2380 1.2406 1.2343 1.2280 1.2199 1.2110 1.1919 35 6.81 1.2201 1.2425 1.2588 1.2701 1.2727 1.2685 1.2577 1.2513 1.2430 1.2260 36 7.01 1.2684 1.2903 1.3046 1.3164 1.3188 1.3175 1.3027 1.2978 1.2900 1.2738 37 7.21 1.2828 1.3041 1.3170 1.3298 1.3323 1.3324 1.3157 1.3125 1.3061 1.2913 38 7.41 1.2716 1.2917 1.3035 1.3174 1.3200 1.3208 1.3038 1.3017 1.2973 1.2850 39 7.61 1.2616 1.2805 1.2910 1.3039 1.3066 1.3081 1.2931 1.2900 1.2876 1.2782 40 7.81 1.2608 1.2783 1.2875 1.2977 1.3004 1.3025 1.2909 1.2851 1.2854 1.2781 41 8.01 1.2661 1.2821 1.2898 1.2984 1.3011 1.3037 1.2942 1.2862 1.2885 1.2837 42 8.21 1.2721 1.2864 1.2925 1.2985 1.3012 1.3044 1.2991 1.2910 1.2913 1.2900 43 8.41 1.2548 1.2672 1.2718 1.2744 1.2769 1.2809 1.2824 1.2770 1.2728 1.2758 44 8.61 1.2028 1.2134 1.2171 1.2162 1.2184 1.2234 1.2309 1.2281 1.2230 1.2296 45 8.81 1.1585 1.1679 1.1703 1.1688 1.1714 1.1773 1.1835 1.1834 1.1784 1.1871 46 9.01 1.1836 1.1918 1.1926 1.1911 1.1938 1.1988 1.2048 1.2078 1.2006 1.2107 47 9.21 1.2254 1.2328 1.2316 1.2301 1.2328 1.2364 1.2426 1.2433 1.2403 1.2497 48 9.41 1.2337 1.2404 1.2370 1.2359 1.2387 1.2404 1.2470 1.2484 1.2485 1.2565 49 9.61 1.2176 1.2228 1.2172 1.2139 1.2161 1.2188 1.2257 1.2285 1.2289 1.2390 50 9.81 1.2030 1.2058 1.1977 1.1914 1.1916 1.1967 1.2036 1.2050 1.2060 1.2202 51 10.01 1.1917 1.1917 1.1810 1.1736 1.1729 1.1769 1.1832 1.1883 1.1888 1.2013 52 10.21 1.1871 1.1819 1.1682 1.1598 1.1574 1.1606 1.1661 1.1707 1.1725 1.1858 53 10.41 1.1742 1.1656 1.1487 1.1388 1.1377 1.1363 1.1405 1.1468 1.1508 1.1629 54 10.61 1.1279 1.1168 1.0978 1.0901 1.0905 1.0824 1.0870 1.0955 1.1026 1.1124 55 10.81 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 56 11.01 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 57 11.21 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 58 11.41 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 59 11.61 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 60 11.81 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

[TOP] 61 12.01 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

  • Linear extrapolation based on a line between 20,000 MWD/MTU and 22,000 MWD/MTU is adequate for addressing burnups beyond 22,000 MWD/MTU.

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 18 of 28 Table 4 (cont.) - T(z) Factors associated with Figures 6, 7 and 8 (ROS2) (Top 10% and Bottom 8% excluded)*

Height BU [MWd/MTU]

[ft]

9000 10000 11000 12000 13000 14000 16000 18000 20000 22000

[BOTTOM]

1 0.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 2

0.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 3

0.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 4

0.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 5

0.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 6

1.00 1.0596 1.0666 1.0994 1.1221 1.1550 1.1587 1.2048 1.2273 1.2303 1.2378 7

1.20 1.1222 1.1285 1.1613 1.1834 1.2154 1.2165 1.2583 1.2758 1.2739 1.2771 8

1.40 1.1636 1.1681 1.1989 1.2190 1.2479 1.2453 1.2804 1.2922 1.2854 1.2841 9

1.60 1.2002 1.2025 1.2307 1.2482 1.2734 1.2671 1.2955 1.3020 1.2908 1.2860 10 1.80 1.2156 1.2160 1.2412 1.2562 1.2777 1.2685 1.2913 1.2940 1.2803 1.2734 11 2.00 1.1906 1.1896 1.2115 1.2242 1.2422 1.2315 1.2501 1.2508 1.2373 1.2303 12 2.20 1.1589 1.1564 1.1747 1.1851 1.1993 1.1875 1.2023 1.2017 1.1893 1.1829 13 2.40 1.1847 1.1799 1.1944 1.2018 1.2118 1.1972 1.2075 1.2044 1.1914 1.1841 14 2.60 1.2245 1.2162 1.2276 1.2322 1.2378 1.2204 1.2263 1.2210 1.2078 1.1994 15 2.80 1.2350 1.2288 1.2339 1.2356 1.2380 1.2192 1.2219 1.2147 1.2015 1.1934 16 3.00 1.2248 1.2229 1.2208 1.2193 1.2194 1.2003 1.2009 1.1902 1.1801 1.1733 17 3.20 1.2196 1.2169 1.2110 1.2072 1.2037 1.1845 1.1840 1.1683 1.1660 1.1612 18 3.40 1.2210 1.2184 1.2079 1.2054 1.1946 1.1760 1.1735 1.1566 1.1590 1.1604 19 3.60 1.2303 1.2253 1.2115 1.2098 1.1958 1.1771 1.1719 1.1578 1.1590 1.1656 20 3.80 1.2435 1.2345 1.2197 1.2172 1.2004 1.1810 1.1712 1.1627 1.1616 1.1738 21 4.00 1.2381 1.2268 1.2118 1.2085 1.1891 1.1708 1.1658 1.1543 1.1556 1.1692 22 4.20 1.2013 1.1896 1.1745 1.1712 1.1511 1.1362 1.1321 1.1236 1.1266 1.1414 23 4.40 1.1660 1.1551 1.1407 1.1356 1.1170 1.1038 1.1001 1.0952 1.0990 1.1147 24 4.60 1.1927 1.1811 1.1659 1.1574 1.1381 1.1249 1.1195 1.1162 1.1189 1.1348 25 4.80 1.2343 1.2217 1.2055 1.1932 1.1729 1.1592 1.1516 1.1492 1.1521 1.1661 26 5.00 1.2483 1.2349 1.2185 1.2033 1.1830 1.1699 1.1609 1.1602 1.1644 1.1762 27 5.20 1.2403 1.2261 1.2104 1.1931 1.1739 1.1612 1.1517 1.1530 1.1588 1.1686 28 5.40 1.2328 1.2185 1.2037 1.1854 1.1672 1.1532 1.1423 1.1455 1.1528 1.1603 29 5.60 1.2331 1.2193 1.2053 1.1875 1.1681 1.1550 1.1413 1.1448 1.1527 1.1578 30 5.80 1.2424 1.2279 1.2145 1.1957 1.1761 1.1640 1.1508 1.1497 1.1574 1.1591 31 6.00 1.2563 1.2394 1.2274 1.2079 1.1909 1.1783 1.1671 1.1615 1.1643 1.1655 32 6.20 1.2512 1.2344 1.2224 1.2055 1.1920 1.1780 1.1684 1.1622 1.1593 1.1636 33 6.40 1.2147 1.2028 1.1878 1.1762 1.1650 1.1506 1.1440 1.1372 1.1335 1.1415 34 6.61 1.1844 1.1763 1.1595 1.1520 1.1431 1.1283 1.1242 1.1167 1.1121 1.1230 35 6.81 1.2150 1.2076 1.1890 1.1824 1.1743 1.1574 1.1537 1.1442 1.1387 1.1490 36 7.01 1.2609 1.2537 1.2330 1.2268 1.2191 1.1994 1.1958 1.1862 1.1775 1.1863 37 7.21 1.2775 1.2715 1.2498 1.2448 1.2384 1.2172 1.2145 1.2054 1.1945 1.2014 38 7.41 1.2709 1.2666 1.2446 1.2419 1.2374 1.2154 1.2146 1.2057 1.1942 1.1986 39 7.61 1.2639 1.2612 1.2396 1.2384 1.2357 1.2132 1.2139 1.2053 1.1931 1.1951 40 7.81 1.2649 1.2624 1.2447 1.2413 1.2402 1.2192 1.2192 1.2106 1.1974 1.1964 41 8.01 1.2740 1.2688 1.2558 1.2508 1.2515 1.2321 1.2310 1.2221 1.2076 1.2022 42 8.21 1.2850 1.2774 1.2676 1.2624 1.2628 1.2452 1.2433 1.2339 1.2183 1.2088 43 8.41 1.2741 1.2664 1.2590 1.2538 1.2542 1.2391 1.2370 1.2278 1.2120 1.1982 44 8.61 1.2300 1.2224 1.2182 1.2136 1.2144 1.2030 1.2023 1.1944 1.1802 1.1644 45 8.81 1.1901 1.1825 1.1816 1.1774 1.1789 1.1710 1.1726 1.1652 1.1556 1.1441 46 9.01 1.2143 1.2073 1.2099 1.2041 1.2087 1.2005 1.1997 1.1887 1.1807 1.1709 47 9.21 1.2475 1.2460 1.2496 1.2480 1.2501 1.2461 1.2338 1.2277 1.2129 1.2056 48 9.41 1.2500 1.2549 1.2586 1.2631 1.2610 1.2642 1.2514 1.2413 1.2302 1.2222 49 9.61 1.2330 1.2377 1.2427 1.2527 1.2472 1.2585 1.2557 1.2361 1.2368 1.2233 50 9.81 1.2177 1.2176 1.2235 1.2385 1.2322 1.2489 1.2554 1.2349 1.2412 1.2235 51 10.01 1.2042 1.2058 1.2092 1.2270 1.2265 1.2409 1.2579 1.2407 1.2493 1.2349 52 10.21 1.1916 1.1969 1.1994 1.2156 1.2215 1.2364 1.2617 1.2481 1.2595 1.2507 53 10.41 1.1705 1.1804 1.1813 1.1990 1.2074 1.2276 1.2566 1.2483 1.2631 1.2616 54 10.61 1.1226 1.1350 1.1361 1.1563 1.1653 1.1904 1.2239 1.2198 1.2399 1.2468 55 10.81 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 56 11.01 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 57 11.21 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 58 11.41 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 59 11.61 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 60 11.81 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

[TOP] 61 12.01 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Linear extrapolation based on a line between 20,000 MWD/MTU and 22,000 MWD/MTU is adequate for addressing burnups beyond 22,000 MWD/MTU.

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 19 of 28 Table 5: RJ Margin Decrease Factors associated with Figures 6, 7, and 8 (ROS2) and Table 4 Cycle Burnup (MWD/MTU)

RJ Penalty Multiplier Cycle Burnup (MWD/MTU)

RJ Penalty Multiplier Cycle Burnup (MWD/MTU)

RJ Penalty Multiplier 150 1.020 7183 1.001 14216 1.012 322 1.019 7354 1.000 14387 1.013 493 1.018 7526 1.000 14559 1.013 665 1.016 7697 1.000 14730 1.012 836 1.014 7869 1.000 14902 1.012 1008 1.011 8041 1.000 15073 1.003 1179 1.009 8212 1.003 15245 1.002 1351 1.007 8384 1.004 15416 1.001 1522 1.004 8555 1.005 15588 1.001 1694 1.002 8727 1.005 15760 1.000 1865 1.001 8898 1.004 15931 1.000 2037 1.000 9070 1.004 16103 1.000 2208 1.000 9241 1.007 16274 1.000 2380 1.000 9413 1.008 16446 1.000 2551 1.000 9584 1.007 16617 1.000 2723 1.000 9756 1.008 16789 1.000 2895 1.000 9927 1.011 16960 1.000 3066 1.000 10099 1.015 17132 1.000 3238 1.000 10270 1.017 17303 1.000 3409 1.000 10442 1.020 17475 1.000 3581 1.000 10614 1.020 17646 1.000 3752 1.000 10785 1.021 17818 1.000 3924 1.000 10957 1.023 17989 1.000 4095 1.000 11128 1.028 18161 1.000 4267 1.003 11300 1.029 18333 1.000 4438 1.006 11471 1.028 18504 1.000 4610 1.009 11643 1.027 18676 1.000 4781 1.011 11814 1.024 18847 1.000 4953 1.012 11986 1.021 19019 1.000 5124 1.014 12157 1.017 19190 1.000 5296 1.015 12329 1.014 19362 1.000 5468 1.015 12500 1.007 19533 1.000 5639 1.014 12672 1.004 19705 1.000 5811 1.013 12843 1.002 19876 1.000 5982 1.012 13015 1.000 20048 1.000 6154 1.010 13187 1.000 20219 1.000 6325 1.009 13358 1.000 20391 1.000 6497 1.007 13530 1.000 20562 1.000 6668 1.004 13701 1.008 6840 1.003 13873 1.010 7011 1.002 14044 1.011 Values may be interpolated to the surveillance cycle burnup. The Rj factor value for the last burnup step shall be used for all burnups greater than the last burnup step.

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 20 of 28 Table 6: Required THERMAL POWER Limits and AFD Reductions RAOC Operating Space Required FQW(z)

Margin Improvement

(%)

Required THERMAL POWER Limit

(%RTP)

Reference AFD Figure ROS1 (Figure 5)

> 0

< 50 N/A ROS2 (Figure 6) 2.8 95 Use Figure 7

> 2.8 and 6.1 90 Use Figure 8

> 6.1

< 50 N/A

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 21 of 28 Figure 1 Reactor Core Safety Limits 540 560 580 600 620 640 660 680 0

0.2 0.4 0.6 0.8 1

1.2 1.4 Fraction of 1677 MWt Rated Thermal Power RCS Tavg (°F) 1850 psia 2250 psia 2425 psia Acceptable Unacceptable I~

I

~

7..... I"'-.

H I

I I

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..... - -r--,......

1,11,.

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Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 22 of 28 Figure 2 Rod Insertion Limit, 128 Step Tip-to-Tip Bank D Bank C Bank B 0

50 100 150 200 0

20 40 60 80 100 Power Level, % of Rated Thermal Power Bank Position, Steps 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.

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 23 of 28 Figure 3 Rod Insertion Limit, 128 Step Tip-to-Tip, One Bottomed Rod (Technical Specification 3.1.4, Condition B)

Bank C Bank D Operation Forbidden in this Region 0

50 100 150 200 224 0

20 40 60 80 100 Power Level, % of Rated Thermal Power Bank Position, Steps 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.

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 24 of 28 Figure 4 Rod Insertion Limit, 128 Step Tip-to-Tip, One Inoperable Rod (Technical Specification 3.1.4, Condition A)

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.

Operation Forbidden in this Region 0

50 150 200 224 0

20 40 60 80 100 Power Level, % of Rated Thermal Power Bank C Bank D Bank Position, Steps 100

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 25 of 28 Figure 5 Flux Difference Operating Envelope associated with ROS1 (Tables 2 and 3)

-22

-9 21 8

0 10 20 30 40 50 60 70 80 90 100 110

-25

-20

-15

-10

-5 0

5 10 15 20 25 I %

% Power Acceptable Unacceptable Unacceptable I

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Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 26 of 28 Figure 6 Flux Difference Operating Envelope associated with ROS2 (Tables 4 and 5) 110

-7 6

100 Unacceptable Unacceptable 90 Acceptable 80 70 60 CJ) 3:

0 a..

  • 50

-20 19 40 30 20 10 0

-25

-20

-15

-10

-5 0

5 10 15 20 25

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 27 of 28 Figure 7 Flux Difference Operating Envelope associated with ROS2 95% THERMAL POWER Required Action (Tables 4, 5, and 6) 110 100 Unacceptable

-7, 95 90 80 70 60 I...

Q)

~

0 a..

  • so

-18.7 40 30 20 10 0

-25

-20

-15

-10

-5 Acceptable 0

lll %

6,95 5

10 r

Unacceptable 17.7 15 20 25

Core Operating Limits Report Unit 1, Cycle 33 Revision 0 Page 28 of 28 Figure 8 Flux Difference Operating Envelope associated with ROS2 90% THERMAL POWER Required Action (Tables 4, 5, and 6) 110 100 Unacceptable 90 80 70 60 I...

QJ 3

0 a..

  • so

-17.4 40 30 20 10 0

-25

-20

-15

-10

-7, 90

-5 Acceptable 0

61%

6,90 5

Unacceptable 16.4 10 15 20 25

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