Text

Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 1, Cycle 32, Revision 0
	ML20273A222
Person / Time
Site:	Prairie Island
Issue date:	09/28/2020
From:	Sharp S; Northern States Power Company, Minnesota, Xcel Energy
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-Pl-20-040
	Download: ML20273A222 (38)
	v • d • e

~

Xcel Energy September 28, 2020 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant, Unit 1 Docket Nos. 50-282 Renewed Facility Operating License Nos. DPR-42 1717 Wakonade Drive Welch, MN 55089 L-Pl-20-040 TS 5.6.5.d Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP)

Unit 1, Cycle 32, 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 32, 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 This letter makes no new commitments and no revisions to existing commitments.

~

Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure (1) 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 32 REVISION 0 36 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 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 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

32 0

09/21/20 Updated for Unit 1 Cycle 32

Core Operating Limits Report Unit 1, Cycle 32 Revision 0 Page 1 of 29 PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT UNIT 1 - CYCLE 32 REVISION 0 Reviewed By: _Reviewed per 600000776151______________________9/21/20___________

Date: ________________

Heather Sturgeon Manager, Strategic Engineering Reviewed By: _Reviewed per 600000776150_____________________9/18/20____________

Date: ________________

Darius Ahrar Supervisor, Nuclear Analysis & Design Approved By: _Approved per 600000776149________________________________

Date: _9/21/20_______________

Nate Bibus Director, Fleet 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 32 Revision 0 Page 2 of 29 PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT UNIT 1 - CYCLE 32 REVISION 0 This report provides the values of the limits for Unit 1 Cycle 32 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 32 Revision 0 Page 3 of 29

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 32 Revision 0 Page 4 of 29

7.

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

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

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

The HFP W(Z) values are provided in Tables 2, 4 and 7.

The W(Z) values in Tables 2, 4 and 7 are applicable to Figure 5.

The data in Tables 2, 4 and 7 should be used independently; cross interpolation or extrapolation between W(Z) sets is prohibited.

The Part Power W(Z) values for 75% P < 85% and Part Power W(Z) values for 85 P < 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 FW Q(Z) Penalty Factors associated with Figure 5 and Table 7 are provided in Table 8.

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 Tables 2, 4 and 7 W(z) values are defined below:

1. Table 2 or Table 7 values should be used when D-AO is in the range of +/-3% of the applicable tables 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.

Core Operating Limits Report Unit 1, Cycle 32 Revision 0 Page 5 of 29

3. Table 4 values should not be used upon exceeding the 250 MWd/MTU of reduced power cycle burnup criterion for Flexible Power Operation (FPO).

The W(Z) values in Table 7 and the FW Q(Z) Penalty Factors in Table 8 are to be used upon exceeding the 250 MWd/MTU reduced power cycle burnup criterion for FPO, but may be used for the entire cycle. The Table 7 W(Z) values replace those in Table 2. The Table 8 FW Q(Z) Penalty Factors replace those in Table 3.

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/MTU, or at a power level other than those specified for Table 6, the HFP W(Z) values in Table 2, 4, or 7 should be used.

W(Z) values should be multiplied by the factor 1/P, when P > 0.5. When P is 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 (FH N)

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 32 Revision 0 Page 6 of 29

9.

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.

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 32 Revision 0 Page 7 of 29 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 = 564F 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 32 Revision 0 Page 8 of 29 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 FW Q(Z) Penalty With Increasing [FC Q(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 32 Revision 0 Page 9 of 29

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 32 Revision 0 Page 10 of 29

31.

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

32.

Design Equivalent Change 601000002047 Rev. 0 1R32 Core Reload 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 32 Revision 0 Page 11 of 29 Table 1 Minimum Required Shutdown Margin, %

NumberofChargingPumpsRunning**

Mode1*

01Pump 2Pumps 3Pumps 026000MWd/MTU

Mode2*

01Pump 2Pumps 3Pumps 026000MWd/MTU 1.7 1.7 1.7 PhysicsTestinginMode2 01Pump 2Pumps 3Pumps 026000MWd/MTU 0.5 0.5 0.5 Mode3 Tave520°F(MostReactiveRodOut) 01Pump 2Pumps 3Pumps 026000MWd/MTU 2.0 2.0 2.0 Mode3 350°FTave<520°F(MostReactiveRodOut) 01Pump 2Pumps 3Pumps 0MWd/MTU 2.0 2.0 2.0 3500MWd/MTU 2.0 2.0 2.0 6500MWd/MTU 2.0 2.0 2.0 10500MWd/MTU 2.0 2.0 2.0 15000MWd/MTU 2.0 2.0 2.0 26000MWd/MTU 2.0 2.0 2.0 OperationalModeDefinitions,asperTSTable1.11.

ForMode1andMode2withKeff1.0,theminimumshutdownmarginrequirementsare providedbytheRodInsertionLimits.

- Chargingpump(s)inserviceonlypertainstosteadystateoperations.Itdoesnotinclude transitoryoperations.Forexample,operationssuchasstartingasecondchargingpumpin ordertosecuretheoperatingpumpwouldfallundertheonepumpinservicecolumn.

Note:Linearinterpolationbetweenburnupstepsisallowed.Extrapolationisnotallowed.

Ii==================!

I l============;======;=========;========I lt-----------------------1 I ~----~--~-~-~

!I>-----------------------1 I

11============;======;=========;==========1 11--------------+-----+-------+-------t I ~----~--~-~-~

!I>-----------------------1 II========~====;=====;=====

11--------------+-----+-------+-------t 11--------------+-----+-------+-------t I t-----------------------1 I t-----------------------1 I t-----------------------1 11--------------+-----+-------+-------t

Core Operating Limits Report Unit 1, Cycle 32 Revision 0 Page 12 of 29 Table 1, Continued Minimum Required Shutdown Margin, %

NumberofChargingPumpsRunning**

Mode4 200°F<Tave<350°F(MostReactiveRodOut) 01Pump 2Pumps 3Pumps 0MWd/MTU 2.0 3.5 5.0 3500MWd/MTU 2.0 3.5 5.5 6500MWd/MTU 2.0 4.0 6.0 10500MWd/MTU 2.0 4.0 6.0 15000MWd/MTU 2.0 3.5 5.5 26000MWd/MTU 2.0 2.0 2.5 NumberofChargingPumpsRunning**

Mode5 68°FTave200°F(MostReactiveRodOut) 01Pump 2Pumps 3Pumps 0MWd/MTU***

2.0 4.0 6.0 3500MWd/MTU 2.0 4.0 6.5 6500MWd/MTU 2.0 4.5 6.5 10500MWd/MTU 2.0 4.0 6.5 15000MWd/MTU 2.0 4.0 6.0 26000MWd/MTU 2.0 2.0 3.5 OperationalModeDefinitions,asperTSTable1.11.

- Chargingpump(s)inserviceonlypertainstosteadystateoperations.Itdoesnotinclude transitoryoperations.Forexample,operationssuchasstartingasecondchargingpumpin ordertosecuretheoperatingpumpwouldfallundertheonepumpinservicecolumn.

- - ThesevaluesarealsoapplicablefortheUnit1Cycle31endofcycle.

Note:Linearinterpolationbetweenburnupstepsisallowed.Extrapolationisnotallowed.

Core Operating Limits Report Unit 1, Cycle 32 Revision 0 Page 13 of 29 Table 1, Continued Minimum Required Shutdown Margin, %

NumberofChargingPumpsRunning**

Mode6 68°FTave<200°F(ARI) 01Pump 2Pumps 3Pumps 0MWd/MTU***

5.129 5.129 5.5 3500MWd/MTU 5.129 5.129 6.0 6500MWd/MTU 5.129 5.129 6.5 10500MWd/MTU 5.129 5.129 6.5 15000MWd/MTU 5.129 5.129 6.0 26000MWd/MTU 5.129 5.129 5.129 Mode6 68°FTave<200°F(ARO) 01Pump 2Pumps 3Pumps 0MWd/MTU***

5.129 5.129 7.5 3500MWd/MTU 5.129 5.129 8.0 6500MWd/MTU 5.129 5.129 8.0 10500MWd/MTU 5.129 5.129 8.0 15000MWd/MTU 5.129 5.129 7.5 26000MWd/MTU 5.129 5.129 5.129

- Chargingpump(s)inserviceonlypertainstosteadystateoperations.Itdoesnotinclude transitoryoperations.Forexample,operationssuchasstartingasecondchargingpumpin ordertosecuretheoperatingpumpwouldfallundertheonepumpinservicecolumn.

- - ThesevaluesarealsoapplicablefortheUnit1Cycle31endofcycle.

Note:Linearinterpolationbetweenburnupstepsisallowed.Extrapolationisnotallowed.

Core Operating Limits Report Unit 1, Cycle 32 Revision 0 Page 14 of 29 Table 2 - W(z) Values associated with Figure 5 (Top 10% and Bottom 8% excluded)*

Height BU [MWd/MTU]

[ft]

150 1000 2000 3000 4000 6000 6500 7000 8000 9000 AO =

-2.05%

ML20273A222

Text

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