ML19296D388

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Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 2, Cycle 31, Revision 0
ML19296D388
Person / Time
Site: Prairie Island Xcel Energy icon.png
Issue date: 10/23/2019
From: Sharp S
Northern States Power Company, Minnesota, Xcel Energy
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-Pl-19-043
Download: ML19296D388 (35)
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Text

Xcel Energy RES P O N S I B LE B V NAT UR E 1717 Wakonade Drive Welch, MN 55089 October 23, 2019 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Unit 2 Docket No. 50-306 Renewed Facility Operating License No. DPR-60 L-Pl-19-043 TS 5.6.5.d Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP)

Unit 2, Cycle 31, Revision 0 Pursuant to the requirements of Technical Specification 5.6.5.d, Northern States Power Company, a Minnesota Corporation (NSPM), doing business as Xcel Energy, hereby submits the COLR for the PINGP Unit 2, Cycle 31, Revision 0. The COLR provides the cycle-specific values of the limits established using NRG approved methodologies such that the applicable limits of the plant safety analysis are met.

The COLR for PINGP Unit 2 Cycle 31, Revision 0, is provided in Enclosure 1.

Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.

. fa~

Scott Sharp 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

Document Control Desk Page 2 ENCLOSURE 1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT UNIT 2 - CYCLE 31 REVISION 0 Unit 2 - Cycle 31, Revision 0 (33 pages)

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 Fq w(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 30 30 31 31 0

0 0

0 10/25/16 10/24/17 09/06/18 10/14/19 Updated for Unit 1 Cycle 30 Updated for Unit 2 Cycle 30 Updated for Unit 1 Cycle 31 Updated for Unit 2 Cycle 31

Core Operating Limits Report Unit 2, Cycle 31 Revision 0 PRAJRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT UNIT 2 ~ CYCLE 31 REVISION0 Reviewed By: _n_,___,.[C'---'--~.__,__y()"--"'---1,,JL'---'--=,

K"'-"--9 _

~athew Manager, Strategic Engineering Supervisor, Nuclear Analysis & Design

/~

~

Approved By: * *Lfd:2c~d,,o NateBibus Director, Fleet Engineering Date: ( 0 I 12._ I 20 l 9 Note:

Thls report is not part of the Technical Specifications This report is referenced in the Technical Specifications Page 1 of 26

Core Operating Limits Report Unit 2, Cycle 31 Revision O PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT UNIT 2 - CYCLE 31 REVISION0 This report provides the values of the limits for Unit 2 Cycle 31 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.

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 11T and Overpower 11T 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 2.1.1 Reactor Core Safety Limits Reactor Core Safety Limits are shown in Figure 1.

Reference Technical Specification 2.1.1.

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

Reference Technical Specification 3.1.1.

Page 2 of 26

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/°F at a power level= 70% RTP to ii. -1.5 pcm/°F at a power level= 100% RTP ITC Lower limit:
a. -43.15 pcm/°F Reference Technical Specification 3.1.3.

Core Operating Limits Report Unit 2, Cycle 31 Revision O

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

6.

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 BankD.

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

Reference Technical Specification 3.1.6.

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.

Page 3 of26

7.

3.2.1 Heat Flux Hot Channel Factor (FQ@

Core Operating Limits Report Unit 2, Cycle 31 Revision 0 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.

The HFP W(Z) values are provided in Table 2 and Table 4.

The W(Z) values in Table 2 and Table 4 are applicable to Figure 5.

The data in Tables 2 and 4 should be used independently; cross interpolation or extrapolation between W(Z) sets is prohibited.

The Part Power W(Z) values for 75%.'.SP < 85% and Part Power W(Z) values for 85.'.SP < 95% are provided in Table 6.

The W(Z) values in Table 6 are applicable to Figure 5.

The Fw Q(Z) Penalty Factors associated with Figure 5 and Table 2 are provided in Table 3.

The Fw Q(Z) Penalty Factors associated with Figure 5 and Table 4 are provided in Table 5.

The W(Z) values in Table 4 are based on a steady-state model with perturbed Axial Flux Difference (AFD) that simulates a Delta-Axial-Offset (D-AO) of -4%

for the entire cycle. D-AO is defined as the measured Axial Offset (AO) less the predicted AO from Table 2. The ranges of applicability for the Table 2 and 4 W(z) values are defined below:

1. Table 2 values should be used when D-AO is in the range of +/-3%

of the Table 2 supplied AO.

2. Table 4 values should be used when D-AO is more negative than

-3% and more positive than -7% of the Table 2 supplied AO.

Page 4 of26

Core Operating Limits Report Unit 2, Cyc;le 31 Revision 0 The HFP W(Z) values are generated assuming that they will be used for full power surveillance. Part power W(Z) values are only required to be used when the part power surveillance is performed using the moveable incore detector system.

When a part power surveillance is performed from BOC through 150 MWd/MTU and at a power level specified for Table 6, the W(Z) values provided in Table 6 should be used. When a part power surveillance is performed after 150 MWD/MIU, or at a power level other than those specified for Table 6, the HFP W(Z) values in Table 2 or Table 4 should be used.

W(Z) values should be multiplied by the factor 1/P, when P > 0.5. When Pis :S 0.5, the W(Z) values should be multiplied by the factor 1/(0.5), or 2.0. This is consistent with the adjustment in the FQ(Z) limit at part power conditions.

Reference Technical Specification 3.2.1.

8.

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F6.JLl

9.

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

F6.H :s; 1.77 x [1 + 0.3(1-P)]

where:

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

Reference Technical Specification 3.2.2.

3.2.3 Axial Flux Difference (AFD)

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

Reference Technical Specification 3.2.3.

Page 5 of26

Core Operating Limits Report Unit 2, Cycle 31 Revision 0

10.

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

Overtemperature Li T Setpoint Overtemperature LiT setpoint parameter values:

Li To

=

T T'

=

p

=

P'

=

Kr

~

K2

=

K3

=

'tr

=

't2

=

f(Lll)

=

Indicated LiT at RATED THERMAL POWER,%

Average temperature, °F 560.0 °F Pressurizer Pressure, psig 2235 psig 1.17 0.014 /°F 0.00100 /psi 30 seconds 4 seconds 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 RA TED THERMAL POWER, such that (a)

For qt - qb within-13, +8 % f(LiI) = 0 (b)

For each percent that the magnitude of qt - qb exceeds +8%

the Li T trip setpoint shall be automatically reduced by an equivalent of 1. 73 % of RA TED THERMAL POWER.

( c)

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

the Li T trip setpoint shall be automatically reduced by an equivalent of3.846 % of RATED THERMAL POWER.

Overpower Li T Setpoint Overpower LiT setpoint parameter values:

LiTo

=

Indicated LiT at RATED THERMAL POWER,%

T

=

Average temperature, °F T'

= 560.0 °F

~

~ 1.11 Ks

=

0.0275/°F for increasing T; 0 for decreasing T K6

=

0.002/°F for T > T'; 0 for T ~ T'

't3

=

10 seconds Reference Technical Specification 3.3.1.

Page 6 of26

Core Operating Limits Report Unit 2, Cycle 31 Revision 0

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 :s; 0.95 b) 2000 ppm c) The Shutdown Margin specified in Table 1 Reference Technical Specification 3.9.1.

Page 7 of26

REFERENCES Core Operating Limits Report Unit 2, Cycle 31 Revision O (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-P A, "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 Company's "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 Fw Q(Z) Penalty With Increasing [Fe Q(Z) / K(Z)

Trend," Revision 0, January 2001.

13.

WCAP-10216-P-A, Revision lA, "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.

Page 8 of26

Core Operating Limits Report Unit 2, Cycle 31 Revision 0

14.

WCAP-8745-P-A, "Design Bases for the Thennal Overpower l1T and Thermal Overtem.perature l1T Trip Functions," September 1986.

15.

WCAP-11397-P-A, "Revised Therm.al Design Procedure," April 1989.

16.

WCAP-14483-A, "Generic Methodology for Expanded Core Operating Lim.its Report," January 1999.

17.

WCAP-7588 Rev. 1-A, "An Evaluation of the Rod Ejection Accident m Westinghouse Pressurized Water Reactors Using Spatial Kinetics Methods," January 1975.

18.

WCAP-7908-A, "FACTRAN - A FORTRAN N 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 ReactorNon-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-SOP, "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, "Supplem.entto Topical Report ER-SOP: 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.

Page 9 of26

Core Operating Limits Report Unit 2, Cycle 31 Revision 0

31.

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

32.

Design Equivalent Change 601000001607 Rev.0 "2R31 Core Reload IFBA/GAD" 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.

Page 10 of26

Core Operating Limits Report Unit 2, Cycle 31 Revision 0 Table 1 Minimum Required Shutdown Margin, %Ap Number of Charging Pumps Running**

Mode 1*

0-1 Pump 2 Pumps 3 Pumps 0 - 25000 MWd/MTU Mode 2*

0-1 Pump 2 Pumps 3 Pumps 0 - 25000 MWd/MTU 1.7 1.7 1.7 Physics Testing in Mode 2 0-1 Pump 2 Pumps 3 Pumps 0 - 25000 MWd/MTU 0.5 0.5 0.5 Mode3 Tave~ 520°F (Most Reactive Rod Out) 0-1 Pump 2 Pumps 3 Pumps 0 - 25000 MWd/MTU 2.0 2.0 2.0 Mode3 350°F S Tave< 520°F (Most Reactive Rod Out) 0-1 Pump 2 Pumps 3 Pumps 0MWd/MTU 2.0 2.0 2.0 3500 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 25000 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.

Page 11 of 26

Core Operating Limits Report Unit 2, Cycle 31 Revision O Table 1, Continued Minimum Required Shutdown Margin, 3/4Ap Number of Charging Pumps Running**

Mode4 200°F <Tave< 350°F (Most Reactive Rod Out) 0-1 Pump 2 Pumps 3 Pumps 0MWd/MTU 2.0 3.5 5.5 3500 MWd/MTU 2.0 4.0 6.0 6000 MWd/MTU 2.0 4.0 6.0 11000 MWd/MTU 2.0 3.5 5.5 16000 MWd/MTU 2.0 3.0 4.5 25000 MWd/MTU 2.0 2.0 2.5 Modes 68°F S Tave S 200°F (Most Reactive Rod Out) 0-1 Pump 2 Pumps 3 Pumps 0 MWd/MTU***

2.0 4.0 6.5 3500 MWd/MTU 2.0 4.5 6.5 6000 MWd/MTU 2.0 4.5 6.5 11000 MWd/MTU 2.0 4.0 6.0 16000 MWd/MTU 2.0 3.5 5.5 25000 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 2 Cycle 30 end of cycle.

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

Page 12 of26

Core Operating Limits Report Unit 2, Cycle 31 Revision O Table 1, Continued Minimum Required Shutdown Margin, %Ap Number of Charging Pumps Running**

Mode6 68°F :s; Tave < 200°F (ARI) 0-1 Pump 2 Pumps 3 Pumps 0 MWd/MTU***

5.129 5.129 6.5 3500.MWd/MTU 5.129 5.129 6.5 6000 MWd/MTU 5.129 5.129 6.5 11000 MWd/MTU 5.129 5.129 6.0 16000 MWd/MTU 5.129 5.129 5.129 25000 MWd/MTU 5.129 5.129 5.129 Mode6 68°F :s; Tave< 200°F (ARO) 0-1 Pump 2 Pumps 3 Pumps 0 MWd/MTU ***

5.129 5.129 8.0 3500 MWd/MTU 5.129 5.129 8.5 6000 MWd/MTU 5.129 5.129 8.5 11000 MWd/MTU 5.129 5.129 8.0 16000 MWd/MTU 5.129 5.129 7.0 25000 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 2 Cycle 30 end of cycle.

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

Page 13 of26

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9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 fTOPl 61 Core Operating Limits Report Unit 2, Cycle 31 Revision 0 Table 2 - W(z) Values associated with Figure S(Top 10% and Bottom 8% excluded)*

Height BU [MWd/MTU]

150 1000 2000 3000 3500 4000 5000 7000 8000

[ft]

AO=

AO=

AO=

AO=

AO =

AO=

AO=

AO =

AO=

0.08%

0.29%

0.33%

0.15%

-0.04%

-0.20%

-0.60%

-1.38%

-1.70%

0.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.40 1.0000 1.0000 1.0000

1. 0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.60 1.0000 1.0000 1.0000
1. 0000 1.0000 1.0000
1. 0000 1.0000 1.0000 0.80 1.0000
1. 0000 1.0000
1. 0000
1. 0000 1.0000 1.0000 1.0000 1.0000 1.00 1.2163 1.2385 1.2493
1. 2510 1.2450 1.2447
1. 2336
1. 2297
1. 2135
1. 20 1.2089 1.2309 1.2412 1.2424 1.2365 1.2363 1.2254 1. 2217
1. 2060 1.40 1.2008
1. 2219 1.2316 1.2322 1.2263
1. 2263 1.2155 1. 2119 1.1968 1.60 1.1935
1. 2118
1. 2207 1.2210
1. 2151 1.2147 1.2043 1.2007 1.1862 1.80 1.1866
1. 2009 1.2090
1. 2092 1.2034 1. 2021 1.1926 1.1886 1. 17 48 2.00 1.1788 1.1892 1.1964 1. 1964 1. 1908 1.1885 1.1806 1.1755 1.1626 2.20 1.1710 1.1775 1.1837 1.1836 1.1782 1.1747 1.1683 1.1623 1.1502 2.40 1.1630 1.1659 1.1712 1.1708 1.1655 1.1612 1.1591 1.1488 1.1376 2.60 1.1553 1.1550 1.1596 1.1597 1.1553 1.1503 1.1510 1.1353 1.1248 2.80 1.1472 1.1434 1.1496 1.1501 1.1486 1.1403 1.1425 1.1231 1.1138 3.00 1.1401 1. 1341 1.1420 1.1422 1.1433 1.1315 1.1349 1.1154 1.1074 3.20 1.1349 1. 1308 1.1364 1.1363 1.1372 1.1269 1.1291 1.1130 1.1051 3.40 1.1290 1.1294 1.1307 1.1300 1.1308 1.1255 1. 1226 1.1097 1.1021 3.60 1.1238 1.1277 1.1279 1.1270 1.1250 1.1240 1.1176 1.1056 1.0983 3.80 1.1207 1.1254 1.1258 1.1253 1.1214 1.1218 1.1149 1.1032
1. 0959 4.00 1.1186 1.1226 1.1227 1.1223 1.1193 1.1192 1.1128 1.1022 1.0947 4.20 1.1155 1.1191 1.1191 1.1188 1.1161 1.1159 1.1100 1.1004 1.0934 4.40 1.1121 1.1153 1. 1151 1.1150 1.1126 1.1123 1.1069
1. 0984 1.0935 4.60 1.1085 1. 1112 1.1109 1.1109 1.1088 1.1084 1.1034 1.0958 1.0931 4.80 1.1050 1. 1071 1.1063 1. 1066 1. 1048 1.1043 1.0998 1. 0941 1.0923 5.00 1.1001 1.1020 1.1022 1.1018 1.1003 1.0995
1. 0953 1.0922 1.0920 5.20 1.0974 1.0980 1.0983
1. 0967 1.0954 1.0951
1. 0925 1.0913 1.0921 5.40 1. 1001 1.0978 1.0958
1. 0936
1. 0925 1.0936 1.0924 1.0920 1.0930 5.60 1.1020 1.1006 1.0985
1. 0962 1.0954 1.0953 1.0948 1.0935 1.0949 5.80 1.1048 1.1049 1.1023 1.1000 1.0995 1.0986 1.0978 1.0974 1.0983 6.00 1.1090 1.1093 1.1065 1.1042 1.1040 1.1031 1.1021 1.1025 1.1022 6.20 1.1133 1.1133 1.1103 1.1081 1.1084 1.1075 1.1071 1.1071 1.1056 6.40 1.1171 1.1165 1.1135 1. 1115 1.1121 1.1113 1. 1117 1. 1113 1.1098 6.61 1.1206 1.1195 1.1164 1.1145 1.1155 1.1147 1.1160 1.1151 1. 1169 6.81 1.1232 1.1221 1.1183 1.1165 1.1179 1.1171 1. 1191 1.1188 1.1227 7.01 1.1260 1.1255 1.1207 1.1192 1. 1208 1.1201 1.1228 1.1229 1.1277 7.21 1.1293 1.1288 1.1236 1.1222 1.1242 1.1235 1.1270 1.1267 1.1324 7.41 1.1327 1.1313 1. 1263 1.1250 1.1273 1.1267 1.1310 1.1310 1.1369 7.61 1.1355 1. 1334 1.1285 1.1273 1.1300 1.1295 1.1346 1.1369 1.1407 7.81 1.1371 1.1344 1.1297 1.1288 1.1318 1.1313 1.1371 1.1423 1.1434 8.01 1.1379 1.1340 1.1296 1.1289 1.1321 1.1316 1.1388 1.1470 1.1468 8.21 1.1370 1.1346 1.1305 1.1301 1.1338 1.1337 1.1389 1.1507 1.1518 8.41 1.1359 1.1377 1.1342 1. 1341 1.1381 1.1384 1.1389 1.1541 1.1573 8.61 1. 1357 1.1420 1.1389 1. 1390 1.1434 1.1434 1.1401 1.1584 1.1614
8. 81 1.1363 1.1458 1.1432 1. 1438 1. 1480 1.1483 1.1425 1. 1634 1.1649
9. 01 1.1429 1.1494 1.1489 1.1517 1. 1509 1.1563 1.1499 1.1682 1. 1711 9.21 1.1525 1.1515 1.1529 1.1583 1.1538 1.1632 1.1612 1.1780 1.1767 9.41 1.1610 1. 1567 1.1613 1.1686 1.1616 1.1731 1.1729 1.1878 1. 1855 9.61 1.1705 1. 1678 1.1724 1.1811 1.1729 1.1847 1.1827 1.1987 1. 1958 9.81 1.1838 1.1826 1.1836 1.1938 1.1848 1.1965 1. 1923
1. 2116 1.2056
10. 01 1. 1976 1.1974 1.1996 1.2119 1.1992 1.2126 1.2044 1.2207 1.2182
10. 21
1. 2114 1.2122 1.2156 1.2294 1.2157 1.2271 1.2160 1.2317 1. 2287
10. 41 1.2195 1.2214 1.2288
1. 2461 1.2301 1.2430 1.2298 1.2389 1. 2387 10.61 1.2288 1.2304
1. 2395 1.2627
1. 2440 1.2607 1.2482 1.2453 1.2482 10.81 1. 2421 1.2416 1.2473
1. 2684 1.2569 1.2714
1. 2665 1.2525 1.2508 11.01 1.0000 1.0000 1.0000
1. 0000 1.0000
1. 0000 1.0000 1.0000 1.0000 11.21 1.0000 1.0000 1.0000
1. 0000 1.0000
1. 0000 1.0000 1.0000 1.0000 11.41 1.0000 1.0000 1.0000
1. 0000 1.0000 1.0000 1.0000 1.0000 1.0000
11. 61 1.0000 1.0000 1.0000 1. 0000 1.0000
1. 0000 1.0000 1.0000 1.0000
11. 81 1.0000 1.0000 1.0000 1. 0000
1. 0000 1.0000 1.0000 1.0000 1.0000
12. 01 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 19,000 MWD/MTU and 22,000 MWD/MTU is adequate for addressing burnups beyond 22,000 MWD/MTU.

9000 AO=

-1.95%

1.0000 1.0000 1.0000 1.0000 1.0000 1.2189

1. 2112 1.2018 1.1911 1. 1796 1. 167 4 1.1550 1. 1423 1.1295 1.1180 1.1108 1.1090 1.1064 1. 1040 1.1026 1.1018 1.1007 1.0994 1.0974
1. 0950 1.0929 1.0925 1.0936 1.0944 1.0983 1.1032 1.1074 1.1113 1.1157 1.1201 1.1240 1.1271 1.1319 1.1393 1.1456 1.1510 1.1555 1. 1588 1. 1608 1.1618 1.1655 1.1748 1.1850 1.1931 1.2011 1.2115 1.2211 1.2320
1. 2454
1. 2553 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Page 14 of26

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[TOP] 61 Heiqht 10000

[ft]

AO=

-2.10%

0.00 1.0000 0.20 1.0000 0.40 1.0000 0.60 1.0000 0.80 1.0000 1.00 1.2087

1. 20 1.2014 1.40 1.1924 1.60 1.1823 1.80 1.1714 2.00 1. 1599 2.20 1.1482 2.40 1.1361 2.60 1.1240 2.80 1.1133 3.00 1.1069 3.20 1.1051 3.40 1.1027 3.60 1.1010 3.80 1.1006 4.00 1.1004 4.20 1.0998 4.40 1.0988 4.60 1.0972 4.80 1.0951 5.00 1.0937 5.20 1.0931 5.40 1.0929 5.60 1.0941 5.80 1.0969 6.00 1.1012 6.20 1.1070 6.40 1.1138 6.61 1.1202 6.81 1.1252 7.01 1.1292 7.21 1. 1335 7.41 1.1396 7.61 1.14 75 7.81 1. 1540 8.01 1.1596 8.21 1.1641 8.41 1.1673 8.61 1.1692 8.81 1.1701 9.01 1.1721 9.21 1.1800 9.41 1.1881 9.61 1.1970 9.81 1.2079
10. 01 1.2163 10.21 1.2255
10. 41 1.2329
10. 61
1. 2411
10. 81 1.2494
11. 01 1.0000 11. 21 1.0000 11. 41 1.0000 11. 61 1.0000
11. 81 1.0000
12. 01 1.0000 Core Operating Limits Report Unit 2, Cycle 31 Revision 0 Table 2 (cont.) - W(z) Values associated with Figure 5 (Top 10% and Bottom 8% excluded)*

BU [MWd/MTU]

10500 11000 12000 14000 15000 16000 17000 19000 AO=

AO=

AO=

AO=

AO=

AO=

AO =

AO=

-2.10%

-2.04%

-1.79%

-1.13%

-0.94%

-0.91%

-0.96%

-1.18%

1.0000 1.0000

1. 0000 1.0000 1.0000 1.0000 1.0000 1. 0000
1. 0000 1.0000
1. 0000 1.0000 1.0000 1.0000 1.0000
1. 0000
1. 0000 1.0000
1. 0000 1.0000 1.0000 1.0000 1.0000 1.0000
1. 0000
1. 0000
1. 0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
1. 0000
1. 0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2010 1.2140 1.2017 1.2053 1. 1956 1.1968 1.2128 1.1881 1.1937 1.2067 1.1947 1.1988 1. 1893 1.1906 1.2062 1.1817 1.1849 1.1976 1. 1861 1.1910 1.1816 1.1832 1.1983 1.1740 1.1749 1.1874 1.1763 1.1821 1.1729 1.1749 1.1896 1.1657 1.1642 1.1764 1.1660 1.1727 1.1640 1.1665 1.1806 1. 157 4 1.1530 1.1648 1.1551 1.1630 1.1547 1.1578 1.1715 1. 1491 1.1415 1.1530 1.1440 1.1530 1.1451 1. 1490 1.1620 1.1405 1.1297 1.1407 1.1323 1.1422 1.1346 1.1390 1.1515 1.1308 1.1177 1.1280 1.1201 1.1309 1.1237 1.1299 1.1405 1.1206 1.1075 1.1177 1.1106 1.1213 1. 1143 1.1207 1.1302 1.1112 1.1018 1.1120 1.1056 1.1155 1.1088 1.1143 1.1215 1.1066 1.1003 1.1093 1.1031 1.1129 1.1070 1.1139 1.1153 1.1065 1.0983 1.1059 1.1000 1.1095 1.1059 1.1132 1.1108 1.1091 1.0980 1.1025
1. 0979 1.1083 1.1058 1.1138 1.1108 1. 1116 1.0988 1.1007
1. 0973 1.1078 1.1072 1.1149 1.1126 1.1137 1.0991 1.1000
1. 0968 1.1068 1.1106 1.1154 1.1139 1.1156 1.0992 1.0987
1. 0962 1.1056 1.1137 1.1157 1.1149 1. 1171 1.0990 1.0970
1. 0972 1.1042 1.1163 1.1156 1.1154 1.1180 1.0979 1.0963
1. 0974 1.1035 1.1174 1.1140 1.1146 1.1171 1.0965 1.0954 1.0971 1.1024 1.1178 1.1139 1.1131 1. 1171 1.0946 1.0939
1. 0962 1.1009 1.1178 1.1147 1. 1113 1.1173 1.0933
1. 0931
1. 0959 1.1002 1.1171 1. 1151 1.1089 1.1170
1. 0932 1.0935
1. 0972 1.1010 1.1161 1.1150 1.1066 1.1160 1.0949 1.0957
1. 0981 1.1018 1.1154 1.1153 1.1074 1.1145 1.0984 1.0997 1.1005 1.1054 1.1153 1.1159 1.1128 1.1168 1.1020 1.1039 1.1044 1. 1115 1.1179 1.1188 1.1193 1.1237 1.1052 1.1076 1.1098 1.1179 1.1247 1.1234 1.1267 1.1331 1.1096 1.1118 1.1163 1.1237 1.1311 1.1295 1.1383 1.1437 1.1168 1.1171 1.1223 1.1300 1.1369 1.1396 1.1490 1.1535 1.1222 1.1207 1.1263 1.1386 1.1407 1.1476 1.1573 1.1608 1.1293 1.1261 1.1339 1.1467 1.1431 1.1544 1.1644 1.1668 1.1381 1.1339 1.1425 1.1538 1.1479 1.1605 1.1707 1. 1720 1.1469 1.1422 1.1497 1.1601 1.1544 1.1655 1.1758 1.1761 1.1547 1.1497 1. 1561 1.1653 1.1593 1.1693 1.1797 1.1788 1.1615 1.1564 1.1613 1.1691 1.1631 1.1717 1.1820 1. 1800 1. 1672 1.1620 1.1654 1.1716 1.1656 1.1725 1.1827 1.1794 1.1718 1.1666 1.1682 1.1726 1.1669 1.1720 1.1819 1. 177 4 1.1751 1.1702 1.1696 1.1720 1.1666 1.1694 1.1789 1. 1728 1.1770 1.1724 1.1694 1.1699 1.1654 1.1657 1.1748 1.1681 1.1777 1.1737 1.1681 1.1674 1.1656 1.1645 1.1722 1.1690 1.1798 1.1778 1.1684 1.1676 1. 1670 1.1630 1.1665 1. 1661 1.1875 1.1818 1.1742 1.1711 1.1668 1.1648 1.1641 1.1662 1.1954 1.1889 1.1802 1. 17 46 1.1687 1.1666 1.1619 1.1672 1.2040 1.1973 1.1868 1.1790 1.1721 1.1686 1.1605 1. 1676 1.2147
1. 2052 1.1955 1.1851 1.1749 1.1725 1.1616 1.1681
1. 2227 1.2162 1.2016 1.1886 1.1809 1.1759 1.1660 1.1726 1.2331
1. 2250 1.2086 1.1935 1.1837 1.1829 1.1668 1.1795
1. 2423 1.2350 1.2144 1.1963 1.1866 1.1904 1.1731 1.1863
1. 2478
1. 2427 1.2214 1.1997 1.1912 1.1980 1.1870 1. 1938 1.2469 1.2421 1.2284 1.2004 1.1945
1. 2037 1.1962 1.1995 1.0000 1.0000
1. 0000 1.0000 1.0000 1. 0000 1.0000 1.0000 1.0000
1. 0000
1. 0000 1.0000 1.0000
1. 0000 1.0000 1.0000 1.0000
1. 0000
1. 0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
1. 0000 1.0000 1.0000 1.0000
1. 0000 1.0000 1.0000
1. 0000
1. 0000 1.0000 1.0000 1.0000
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 19,000 MWD/MTU and 22,000 MWD/MTU is adequate for addressing burnups beyond 22,000 MWD/MTU.

22000 AO=

-1.48%

1.0000 1.0000 1.0000 1.0000 1.0000 1.1984 1.1910 1.1825 1.1734 1. 1645 1.1558 1.1467 1.1362 1.1251 1.1149 1.1103 1.1109 1. 1113 1.1107 1.1123 1.1179 1.1226 1.1267 1.1287 1.1295 1.1298 1.1298 1.1289 1.1275 1.1315 1.1416 1.1529 1.1635 1.1734 1.1803 1.1856 1.1901 1.1933 1.1950 1. 1949 1.1929 1.1889 1.1835 1.1802 1. 1809 1.1773 1. 1761 1. 17 49 1.1734 1.1735 1.1775 1. 1841 1.1908 1.1983 1.2045 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Page 15 of26

Table 3 Core Operating Limits Report Unit 2, Cycle 31 Revision O Fw Q(Z) Penalty Factor associated with Figure 5 and Table 2**

Cycle Burnup (MWD/MTU)

FQ (z) Penalty Factor 0

1.0200 1695 1.0200 1867 1.0203 2039 1.0210 2210 1.0200 10109 1.0200 10280 1.0216 10452 1.0216 10624 1.0200 25000 1.0200

    • Linear interpolation is adequate for intermediate cycle burnups.

Page 16 of26

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9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60

[TOP] 61 Core Operating Limits Report Unit 2, Cycle 31 Revision O Table 4-Negative Delta AO W(z) Values associated with Figure 5 (Top 10% and Bottom 8% excluded)*

Height BU [MWd/MTU]

150 1000 2000 3000 3500 4000 5000 7000 8000

[ft]

AO =

AO=

AO=

AO=

AO=

AO=

AO=

AO=

AO=

-3.91%

-3.70%

-3.68%

-3.85%

-4.04%

-4.20%

-4.59%

-5.38%

-5.70%

0.00 1.0000

1. 0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
1. 0000 0.20 1.0000 1.0000
1. 0000 1.0000
1. 0000 1.0000 1.0000
1. 0000 1. 0000 0.40 1.0000
1. 0000
1. 0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.60 1.0000 1.0000
1. 0000 1.0000 1.0000
1. 0000 1.0000
1. 0000 1.0000 0.80 1.0000 1.0000
1. 0000 1.0000 1.0000 1. 0000 1.0000
1. 0000 1.0000
1. 00 1.1790 1.1799 1. 1911 1.1940 1.1887 1.1921 1.1861 1.1595 1.1415 1.20 1.1720 1.1724 1.1834 1.1862 1.1810 1.1843 1.1785 1.1526 1.1350 1.40 1.1637 1.1635 1. 17 42 1.1770 1. 1718 1.1749 1.1694 1.1442 1.1272 1.60 1.1544 1.1535 1. 1637 1.1664 1. 1614 1.1642 1.1589 1.1347 1.1182 1.80 1.1444 1.1427 1.1524 1.1549 1.1500 1.1526 1.1477 1.1246 1.1087 2.00 1. 1338 1.1312 1.1403 1.1427 1.1379 1. 1403 1.1357 1.1141 1.0988 2.20 1. 1232 1.1197 1.1282 1.1304 1.1258 1. 1278 1.1237 1. 1034 1.0889 2.40 1.1127 1.1082 1. 1161 1.1180 1.1136 1.1153 1. 1115
1. 0926 1.0787 2.60 1.1026 1.0970 1.1044 1.1061 1.1018 1.1033 1.0998 1. 0821
1. 0685 2.80 1.0928 1.0867 1.0927 1.0941 1.0900 1. 0912 1.0882 1. 0723 1.0605 3.00 1.0868 1.0815 1.0855
1. 0863 1.0825 1.0835 1.0811
1. 0673 1.0576 3.20 1.0868 1.0809 1.0853 1.0859 1.0823
1. 0831
1. 0809 1.0674 1.0579 3.40 1.0859 1.0813 1.0839 1.0845 1. 0811
1. 0818 1.0796 1.0678 1. 0581 3.60 1.0845 1.0823
1. 0836 1.0833 1.0793 1.0800
1. 0777 1.0707 1.0598 3.80 1.0834 1.0834 1.0839 1.0835
1. 0789 1.0799
1. 0774 1.0745
1. 0633 4.00 1.0835 1.0843
1. 0846
1. 0842
1. 0801
1. 0811 1.0789 1.0776
1. 0666 4.20 1.0854 1.0862
1. 0860 1.0844
1. 0814 1.0825 1.0806 1.0804 1. 0699 4.40 1.0879 1.0882
1. 0878 1.0860 1.0835 1.0847 1.0830 1.0831 1. 07 44 4.60 1.0901
1. 0898
1. 0891 1.0873
1. 0851 1.0863 1.0848 1.0849 1. 0784 4.80 1.0919 1.0909 1.0902
1. 0883 1.0863 1.0876 1.0864 1.0865
1. 0819 5.00 1.0933 1.0926
1. 0907 1.0888 1.0877 1.0884 1.0873 1. 0875
1. 0851 5.20 1.0949 1.0950 1. 0912 1.0893
1. 0898 1.0892 1.0886 1.0888 1.0880 5.40 1.0975
1. 0971
1. 0931 1.0911 1. 0921
1. 0912 1.0907 1.0912 1.0906 5.60 1.1001 1.0990
1. 0963
1. 0942
1. 0938 1.0946 1.0926 1.0935 1.0929 5.80 1.1050 1.1034 1.1009
1. 0987
1. 0982 1.0994 1.0974 1.0971
1. 0965 6.00 1.1104 1.1085 1.1056 1.1035 1.1034 1.1045 1.1030 1.1023 1.1006 6.20 1.1148 1.1125 1.1095 1.1073 1.1078 1.1089 1.1077 1.1076 1.1059 6.40 1.1188 1.1160 1.1129 1.1110 1.1117 1.1128 1. 1121 1.1125 1.1133
6. 61 1.1230 1.1193 1.1175 1.1177 1.1153 1.1165 1.1162 1.1183 1.1202
6. 81 1. 1278 1.1225 1. 1236 1.1240 1.1191 1. 1191 1.1204 1. 1238 1.1258 7.01 1.1322 1.1264 1.1296 1.1298 1.1232 1. 1226 1.1250 1. 1288 1.1305
7. 21 1.1359 1.1299 1.1347 1.1350 1.1270 1.1263 1.1291 1. 1334 1.1363 7.41 1.1400 1.1338 1.1403 1.1406 1. 1311 1.1305 1.1337 1. 1404 1; 1445 7.61 1.1456 1.1392 1.1473 1.1475 1.1368 1.1364 1.1406 1. 1505 1. 1543 7.81 1.1524 1.1458 1.1539 1.1541 1. 1437 1.1435 1.1495 1.1594 1.1631 8.01 1.1599 1.1523 1.1599 1.1601 1.1514 1.1513 1.1579 1.1675 1.1710 8.21 1.1667 1.1577 1.1650 1.1652 1.1590 1.1590 1.1656 1.1749 1.1782
8. 41 1.1722 1.1637 1.1691 1.1693 1.1656 1.1657 1. 1720 1.1810 1. 1841 8.61 1.1775 1.1716 1.1721 1.1724 1.1721 1.1723 1.1779 1.1866 1. 1895 8.81 1.1860 1.1805 1.1769 1. 1771 1.1820 1. 1820 1.1875 1.1952 1.1976 9.01 1. 1982 1.1932 1. 1901 1.1905 1.1961 1.1959 1.2014 1.2073
1. 2088 9.21 1.2103
1. 2061 1.2037
1. 2050 1. 2102
1. 2100 1.2153 1.2200 1.2204 9.41 1.2214 1.2180 1.2172 1.2207 1.2240
1. 2258
1. 2309 1.2347
1. 2343 9.61 1.2304 1.2281 1.2316 1.2373 1. 2383
1. 2426
1. 2478 1.2506 1.2494 9.81 1.2391 1.2385 1.2458 1.2529 1.2533 1.2583
1. 2635 1.2653
1. 2633
10. 01 1. 2516 1.2543
1. 2592 1.2678 1.2673 1.2733 1. 2785 1.2793 1.2764
10. 21 1.2635
1. 2700 1.2711 1.2820 1.2797 1.2876 1.2928 1.2925 1. 2888 10.41
1. 2773 1.2834 1.2842 1.2926 1.2937 1.2983
1. 3036 1.3027
1. 2982 10.61 1.2957 1.2993 1.3029 1.3072 1.3130 1.3128 1.3177 1.3153
1. 3102 10.81
1. 3116
1. 3151 1.3206 1.3249 1.3313 1.3304 1.3348 1.3299 1.3240 11.01 1.0000 1.0000 1.0000 1.0000
1. 0000 1.0000 1.0000 1.0000 1.0000
11. 21 1.0000 1.0000 1.0000 1.0000
1. 0000 1.0000 1.0000 1.0000
1. 0000 11.41 1.0000 1.0000 1.0000 1.0000
1. 0000 1.0000 1.0000
1. 0000
1. 0000 11. 61 1.0000 1.0000 1.0000 1.0000
1. 0000 1. 0000 1.0000 1.0000 1.0000
11. 81 1.0000 1.0000
1. 0000 1.0000
1. 0000 1.0000 1.0000 1.0000 1.0000
12. 01 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 19,000 MWD/MTU and 22,000 MWD/MTU is adequate for addressing burnups beyond 22,000 MWD/MTU.

9000 AO=

-5.95%

1. 0000

1. 0000 1.0000
1. 0000 1.0000 1.1351 1.1287 1.1209 1.1120 1.1027 1.0930
1. 0832 1.0733
1. 0631 1.0555 1.0531 1.0535 1.0536 1.0565 1. 0610
1. 0648 1.0685 1.0719 1.0760 1.0799
1. 0834 1.0867 1.0896 1.0924 1.0965 1.1007 1.1047 1.1104 1.1180 1.1240 1. 1321 1.1423 1.1528 1.1627 1.1718 1.1800 1.1873 1.1931 1.1982 1.2066 1.2177 1. 2290 1.2419 1.2559
1. 2691 1. 2816 1.2932 1.3019 1.3132 1.3264 1.0000
1. 0000 1.0000 1.0000
1. 0000 1.0000 Page 17 of26

[BOTTOM]

1 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 rroP1 61 Height

[ft]

0.00 0.20 0.40 0.60 0.80 1.00

1. 20 1.40 1.60
1. 80 2.00 2.20 2.40 2.60 2.80 3.00 3.20 3.40 3.60 3.80 4.00 4.20 4.40 4.60 4.80 5.00 5.20 5.40 5.60 5.80 6.00 6.20 6.40 6.61 6.81 7.01 7.21 7.41
7. 61
7. 81
8. 01
8. 21
8. 41 8.61 8.81 9.01 9.21 9.41 9.61 9.81
10. 01
10. 21
10. 41 10.61 10.81
11. 01
11. 21
11. 41 11.61
11. 81 12.01 Core Operating Limits Report Unit 2, Cycle 31 Revision 0 Table 4 (cont.)-Negative Delta AO W(z) Values associated with Figure 5 (Top 10% and Bottom 8% excluded)*

BU [MWd/MTU]

10000 10500 11000 12000 14000 15000 16000 17000 19000 AO=

AO=

AO=

AO=

AO=

AO =

AO=

AO=

AO=

-6.09%

-6.10%

-6.04%

-5.79%

-5.13%

-4.95%

-4.92%

-4.96%

-5.18%

1.0000 1.0000 1.0000

1. 0000 1.0000 1.0000 1.0000 1.0000
1. 0000 1.0000 1.0000
1. 0000 1.0000 1.0000 1.0000 1.0000
1. 0000
1. 0000 1.0000 1.0000 1.0000 1.0000
1. 0000 1.0000 1.0000 1.0000
1. 0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
1. 0000 1.0000
1. 0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
1. 0000 1.0000 1.0000 1.1410 1.1250 1.1241 1.1243 1.1347 1.1168
1. ~320 1.1200 1.1211 1.1347 1.1194 1.1185 1.1189 1.1297 1.1125 1.1274 1.1156 1. 1166 1.1270 1.1126 1.1116 1.1122 1.1236 1.1072 1.1216 1. 1101 1.1113 1.1184 1.1049 1.1039 1.1046 1.1169 1.1014 1.1153 1.1043 1.1057 1.1093 1.0969 1.0959
1. 0968 1.1100 1.0957 1.1090
1. 0986 1.1006 1.1000 1.0887 1.0878 1.0889 1.1031 1.0901 1.1028
1. 0930
1. 0958 1.0906 1.0805 1.0796 1.0808 1.0960 1.0843 1.0964 1. 087 4
1. 0910 1.0808 1.0720
1. 0711 1.0722 1.0882 1.0778 1.0890
1. 0807 1. 0851 1.0711 1.0634 1.0624 1.0634 1.0805
1. 0711 1.0816 1.0737
1. 0789 1.0631 1.0565 1.0555 1.0566 1.0724 1.0653 1.0738
1. 0671
1. 0730 1.0596 1.0538 1.0529
1. 0539 1.0677 1.0623
1. 0681 1.0622
1. 0680 1.0597 1.0543 1.0535 1.0538 1.0675 1.0620 1.0672 1.0615
1. 0657 1.0617 1.0570 1.0565
1. 0556 1.0677 1.0655 1.0675 1.0660
1. 0662 1.0657 1.0615 1.0612
1. 0596 1.0678 1.0703
1. 0677
1. 0711
1. 0666 1.0701 1.0664 1. 0662 1.0643 1.0680 1.0753
1. 0698 1.0758 1.0694 1. 07 41 1.0709 1.0709 1.0685 1.0693 1.0803
1. 0758 1.0807 1.0768
1. 0779 1.0753 1.0754 1.0727 1.0741 1.0853 1. 0812 1.0855 1.0834 1.0815 1.0794 1.0797 1.0767 1.0786 1.0900 1.0865 1.0900 1.0897 1. 0841 1.0825 1.0829 1.0794 1.0835 1.0934 1.0904 1. 0931
1. 0944 1.0862 1.0852 1.0857 1.0829 1.0880 1.0962 1.0935 1.0952
1. 0980 1.0881 1.0875 1.0882 1.0867
1. 0921 1.0986 1.0965
1. 0980 1.1021 1.0896 1.0896 1.0903
1. 0901 1.0959 1.1007 1.0990 1. 1011 1.1068 1.0909 1.0913 1.0922
1. 0932 1.0994 1.1023 1.1013 1. 1041 1.1110 1.0925 1.0934 1.0942
1. 0963 1. 1031 1.1043 1.1056 1.1084 1.1153 1.0968 1.0982 1.0975 1.1007 1.1071 1.1097 1.1127 1. 1171 1.1271 1.1017 1.1037 1.1026 1.1048 1.1142 1. 1196 1.1253 1.1298 1.1410 1.1060 1.1085 1.1086 1.1113 1.1257 1.1329 1.1414 1.1439 1.1532 1.1113 1.1143 1.1159 1.1242 1.1395 1.1476 1.1566 1.1571 1.1652 1.1200 1.1234 1.1273 1.1398 1.1528 1.1616 1.1713 1.1698 1.1764 1.1313 1.1354 1.1396 1.1534 1.1637 1.1731 1. 1833 1.1798 1.1847 1.1422 1.1468 1.1510 1.1660 1.1734 1.1835 1.1941 1.1884 1.1917 1.1530 1.1582 1.1625 1.1780 1.1832 1.1930
1. 2039 1.1971 1.1985 1.1639 1.1696 1.1740 1.1889 1.1928
1. 2012 1.2124 1.2053
1. 2048 1.1741 1.1803 1.1848 1.1988 1.2011 1.2080 1. 2194
1. 2120
1. 2095 1.1833 1.1900 1.1944 1.2073 1.2080 1.2133
1. 2247
1. 2172
1. 2126 1.1914 1.1987 1.2030 1.2144 1. 2135 1.2168 1.2282
1. 2208 1.2142 1.1986 1.2062 1.2103 1.2200 1.2175 1.2188 1. 2299 1.2224 1.2133 1.2042 1.2124 1.2163 1.2238
1. 2195 1.2181
1. 2295
1. 2231 1.2128 1.2089 1.2171 1.2207 1.2258 1.2205 1. 2167 1.2287
1. 2250
1. 2156 1. 2168 1.2209
1. 2242 1.2264 1.2240 1. 2192 1.2286
1. 2281
1. 2188 1.2275 1.2255
1. 2286 1.2281 1.2268 1.2184 1.2246 1.2275 1.2179 1.2386 1.2290
1. 2323 1.2344 1.2273 1.2212 1.2237
1. 2244 1.2173
1. 2488 1.2394
1. 2390
1. 2405 1.2303 1.2255 1.2227 1.2239
1. 2164
1. 2573 1.2548
1. 2467
1. 2467 1.2343
1. 2272
1. 2216
1. 2247 1.2138
1. 2650 1.2688
1. 2537 1.2553 1. 2375 1.2290 1.2222 1.2269 1.2125 1.2751 1.2825 1.2637
1. 2638
1. 2436 1.2363 1.2237 1. 2315 1.2168 1.2881 1.2957 1.2717 1. 27 46 1.2470 1.2444 1.2258 1.2357 1.2218 1.3007 1.3078
1. 2790 1.2851
1. 2493 1.2517 1.2272 1. 2375
1. 2263 1.3127 1.3196
1. 2892 1.2953
1. 2563 1.2594 1.2326 1.2425 1. 2319 1.3215 1.3282
1. 2986 1.3026
1. 2651 1.2648
1. 2403 1.2500
1. 2358 1.0000
1. 0000 1.0000 1.0000 1.0000 1.0000
1. 0000
1. 0000 1.0000 1.0000
1. 0000 1.0000 1.0000
1. 0000 1.0000 1.0000
1. 0000
1. 0000 1.0000
1. 0000 1.0000 1.0000
1. 0000 1.0000
1. 0000
1. 0000
1. 0000 1.0000
1. 0000 1.0000 1.0000
1. 0000 1.0000
1. 0000
1. 0000
1. 0000 1.0000 1.0000 1.0000 1.0000
1. 0000 1.0000
1. 0000
1. 0000 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 19,000 MWD/MTU and 22,000 MWD/MTU is adequate for addressing burnups beyond 22,000 MWD/MTU.

22000 AO=

-5.48%

1.0000 1.0000 1.0000 1.0000 1.0000 1.1159 1. 1110 1.1053 1.0995 1. 0943 1.0897 1.0849 1.0788 1.0725 1.0660 1.0622 1.0623

1. 0658 1. 0687
1. 0742 1. 0831 1. 0921 1.1005 1.1069 1.1120 1.1169 1.1211 1. 1249 1.1314 1.1458 1.1622 1.1767 1.1910
1. 2044
1. 2142 1.2223 1. 2303 1.2375
1. 2428
1. 2463 1.2478 1.2473
1. 2447
1. 2407 1.2371
1. 2329 1.2312 1.2299 1.2271 1.2262 1.2323
1. 2389 1.2447
1. 2516 1.2570 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Page 18 of 26

Table 5 Core Operating Limits Report Unit 2, Cycle 31 Revision 0 Negative Delta AO Fw Q(Z) Penalty Factor associated with Figure 5 and Table 4**

Cycle Burnup (MWD/MTU)

FQ(z) Penalty Factor 0

1.0200 1352 1.0200 1524 1.0219 1695 1.0233 1867 1.0235 2039 1.0225 2210 1.0208 2382 1.0200 25000 1.0200

    • Linear interpolation is adequate for intermediate cycle burnups.

Page 19 of 26

Core Operating Limits Report Unit 2, Cycle 31 Revision 0 Table 6 - W(z) Values Associated with Figure 5 for Part Power Surveillances*

(Top 10% and Bottom 8% excluded)

Height Part Power W(z) Functions (% of Hot Full Power) sot 90tt D-Bank@ 197 Steps:t:

D-Bank @ 206 Steps:t:

[ft]

HFP AO= 0.13%

[BOTTOM]

1 0.00 1.0000 2

0.20

1. 0000 3

0.40 1.0000 4

0.60 1.0000 5

0.80 1.0000 6

1. 00 1.2293 7
1. 20
1. 2200 8

1.40 1.2099 9

1. 60 1. 2015 10
1. 80 1. 1937 11 2.00 1. 1858 12 2.20 1. 1751 13 2.40 1. 1667 14 2.60 1. 1582 15 2.80 1. 1486 16 3.00 1.1408 17 3.20 1.1349 18 3.40 1. 1270 19 3.60 1. 1211 20 3.80 1. 1167 21 4.00 1. 1133 22 4.20 1. 1096 23 4.40 1. 1036 24 4.60 1.0994 25 4.80 1. 0961 26 5.00 1.0906 27 5.20 1.0867 28 5.40
1. 0894 29 5.60
1. 0900 30 5.80
1. 0922
  • W(z) values only valid for core average burnups :5 150 MWd/MTU t 80% of full power W(z) values are applicable for powers 75% :5 P < 85%

tt 90% of full power W(z) values are applicable for powers 85% :5 P < 95%

HFP AO= 0.13%

1.0000 1.0000 1.0000 1.0000 1.0000 1. 2163 1. 2081 1. 1992 1. 1927 1.1858 1. 1788 1. 1710 1. 1637 1. 1560 1.1479 1.1415 1. 1363 1.1304 1.1252 1. 1220 1. 1199 1. 1168 1. 1128 1.1092 1.1063 1.1020 1.0987 1. 1020 1. 1039 1. 1067

+ Rod insertion is given as a target value. Use control rods as necessary to control to target AO Page 20 of26

Core Operating Limits Report Unit 2, Cycle 31 Revision O Table 6 (cont.) - W(z) Values Associated with Figure 5 for Part Power Surveillances*

(Top 10% and Bottom 8% excluded)

Height Part Power W(z) Functions (% of Hot Full Power) sot 90tt D-Bank@. 197 Steps*

D-Bank @. 206 Steps*

[ft]

HFP AO= 0.13%

31 6.00 1.0958 32 6.20 1.0994 33 6.40 1. 1030 34 6.61 1.1052 35

6. 81 1. 1083 36 7.01 1.1119 37 7.21 1. 1158 38 7.41 1. 1191 39 7.61 1. 1231 40 7.81 1. 1247 41 8.01 1. 1267 42 8.21 1. 1271 43 8.41 1.1266 44 8.61 1. 1276 45 8.81 1. 1289 46 9.01 1. 1380 47 9.21 1.1504 48
9. 41 1. 1610 49 9.61 1. 1734 50 9.81 1.1892 51
10. 01 1.2037 52
10. 21 1.2208 53
10. 41 1.2305 54 10.61 1. 2413 55
10. 81 1. 2556 56 11. 01 1.0000 57 11. 21 1.0000 58 11. 41 1.0000 59 11. 61 1.0000 60 11. 81
1. 0000 rTOPl 61
12. 01 1. 0000
  • W(z) values only valid for core average burnups :,; 150 MWd/MTU t 80% of full power W(z) values are applicable for powers 75% :,; P < 85%

tt 90% of full power W(z) values are applicable for powers 85% :,; P < 95%

HFP AO= 0.13%

1.1116 1. 1159 1. 1203 1. 1234 1.1265 1. 1299 1. 1339 1.1373 1.1415 1. 1431 1.1446 1.1444 1.1440 1.1439 1. 1446 1. 1527 1. 1638 1. 1732 1.1844 1. 1983 1. 2122 1.2272

1. 2346
1. 2447
1. 2573 1. 0000 1.0000 1.0000 1.0000 1.0000 1.0000
j: Rod insertion is given as a target value. Use control rods as necessary to control to target AO
j: Rod insertion is given as a target value. Use control rods as necessary to control to target AO Page 21 of26

680 660 640

u.

620 0 -

C) ctl I-U)

{.)

600

~

580 560 540 W A'>'- nc ;i;: I

.... I',..,_

H *>?,i:::n n,,i:: I

... i,...,

I',-.. I'----

l1sso osia I

.. I'---i-..

-I'---,..,_

0 0.2 Figure 1 Core Operating Limits Report Unit 2, Cycle 31 Revision O Reactor Core Safety Limits i Unacceptable i

~ I',..,_

I""', I"'--,..,__

I~

I\\.

1-..... I'---

j\\

I'\\"

I'\\ "

Ill,.

I\\.

"ii

'j\\

~

i\\ \\

I"-,.

I'\\ \\

I\\

~

~

1-.....

1, '

I Acceptable I I"'-- r--..

\\.

[\\

~ '

I\\

\\ ' I\\.

\\

\\ \\

\\

\\ '

\\

~

' \\

' ' ' ' \\

0.4 0.6 0.8 1

1.2 1.4 Fraction of 1677 MWt Rated Thermal Power Page 22 of26

tn 150

a.

Q) -

en C:

0

'cij 0 100

a.

.lil::

C:

ct!

al 0

Figure 2 Core Operating Limits Report Unit 2, Cycle 31 Revision O Rod Insertion Limit, 128 Step Tip-to-Tip 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 I 63) * (P - 100) + 185 + 128 + 128 NOTE: The top of the active fuel height corresponds to 224 steps.

Page 23 of26

Figure 3 Core Operating Limits Report Unit 2, Cycle 31 Revision O Rod Insertion Limit, 128 Step Tip-to-Tip, One Bottomed Rod (Technical Specification 3.1.4, Condition B) 224 200 150 en Operation 0..

Q)

Forbidden in this Region Cl)

C:

0 100 "ui 0 a..

~

C cu Ill 50 0

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

BankD=(l50/63)*(P-90)+224 Bank C = (150 / 63) * (P - 90) + 224 + 128 NOTE: The top of the active fuel height corresponds to 224 steps.

Page 24 of26

Figure 4 Core Operating Limits Report Unit 2, Cycle 31 Revision 0 Rod Insertion Limit, 128 Step Tip-to-Tip, One Inoperable Rod (Technical Specification 3.1.4, Condition A) 224 -----------~----------------

200 150 (I)

0.

Operation Q)

Forbidden in Cf) c this Region 0

100

  • w 0

Cl.

...\\,C C

C\\1 co 50 0

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

BankD=(l50/63)*(P-70)+224 Bank C = (150 / 63) * (P - 70) + 224 + 128 NOTE: The top of the active fuel height corresponds to 224 steps.

Page 25 of26

Core Operating Limits Report Unit 2, Cycle 31 Revision O Figure 5 Flux Difference Operating Envelope associated with Table 2, Table 4, and Table 6 110 100 90 80 70 60 0 a.

50 40 30 20 10 0

-25

-9 I Unacceptable I/ I I

I

/

I I

I J

T

-22

-20

-15

-10

-5 Acceptable 0

Al%

I 5

8

-\\ I Unacceptable I

\\ \\ \\

\\ \\

\\

r\\.

21 10 15 20 25 Page 26 of26

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