Text

Core Operating Limits Report (Colr), Cycle 29, Revision 0
	ML16025A181
Person / Time
Site:	Prairie Island
Issue date:	01/25/2016
From:	Davison K; Northern States Power Co, Xcel Energy
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-PI-16-008
	Download: ML16025A181 (33)
	v • d • e

fl Xcel Energy*

L-PI-16-008 JAN 2 5 2016 TS 5.6.5.d U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Unit 2 Docket 50-306 Renewed License No. DPR-60 Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 2. Cycle 29, 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"),

submits the COLR for the PINGP Unit 2, Cycle 29, 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.

The COLR for PINGP Unit 2, Cycle 29, Revision 0, is provided in Enclosure 1.

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

Y.~~

K~avison Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company- Minnesota Enclosure cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC State of Minnesota 1717 Wakonade Drive East

Welch, Minnesota 55089-9642 Telephone: 651.388.1121

ENCLOSURE 1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT UNIT 2 - CYCLE 29 REVISION 0 Record of Revision (7 pages)

Unit 2- Cycle 29, Revision 0 (24 pages)

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

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

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

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

3 2/11/91 Incorporated revised Fa of 2.45 as a result of NRC approval of Westinghouse Topical Report WCAP-1 0924-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 Fa of 2.45 as a result of NRC approval of Westinghouse Topical Report WCAP-10924-P-A, Volume 1, Addendum 4, October 1990.

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

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

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

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

Page 1 of 7

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record of Revision Unit Revision Approval Cycle No. Date Remarks 2 16 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.

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 FM 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 FM limit to

1. 77. Updated Table 1 and Figures 2a through 2e with revised bounding V(z) values.

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

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

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

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

1 8/4/00 Technical Specification Amendment 151:

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

Page 2 of 7

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

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

1 8/4/00 Technical Specification Amendment 142:

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

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

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

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

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

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

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

Page 3 of 7

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

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

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

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

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

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

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

Page 4 of 7

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

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

2 23 0 Not used due to core redesign.

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

1 23 1 7/11/05 Revised lTC upper limit from < 0 pcmfOF 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 Band 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 Ft(z) penalty factors.

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

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

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

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

Page 5 of 7

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

1 25 0 2/24/08 Updated to Unit 1 Cycle 25 25 1 5/28/08 Updated Table 2 to reflect the correct W(z) at a burnup of 150 MWd/MTU and a core height of 6.20 feet 2 25 0 9/26/08 Updated for Unit 2 Cycle 25 1 26 0 9/24/09 Updated for Unit 1 Cycle 26 2 26 0 5/3/10 Updated for Unit 2 Cycle 26 2 26 1 5/17/10 Updated to include part power W(z) factors 1 26 1 9/2/10 Updated for second set of W(z) factors 2 26 2 9/30/10 Updated for Measurement Uncertainty Recapture power uprate to 1677 MWth and for a second set of W(z) factors 1 26 2 9/30/10 Updated for Measurement Uncertainty Recapture power uprate to 1677 MWth 1 26 3 12/17/10 Updated SDM in Table 1 for Mode 2 to say 1.9.

1 27 0 5/5/11 Updated for Unit 1 Cycle 27 1 27 1 6/2/11 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 Page 6 of 7

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record of Revision Unit Revision Approval Cycle No. Date Remarks 2 28 0 11/23/12 Updated for Unit 2 Cycle 28 1 29 0 10/23/14 Updated for Unit 1 Cycle 29 2 29 0 11/05/15 Updated for Unit 2 Cycle 29 Page 7 of 7

Core Operating Limits Report Unit 2, Cycle 29 Revision 0 PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT UNIT 2 - CYCLE 29 REVISIONO Reviewed By: !1Jc:z.~~J Date:

Mark Brossmi Supervisor, Reactor Systems Date: 10/23/2015 Darius Abrar Supervisor, Nuclear Analysis & Design Approved By:-~-"~"'--~"'-~---~-=----*-- Date:

Edward Blondin Director, Site Engineering Note: This report is not part of the Technical Specifications This report is refetenced in the Technical Specifications Page 1 of24

Core Operating Limits Report Unit 2, Cycle 29 Revision 0 PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT UNIT 2- CYCLE 29 REVISIONO This report provides the values of the limits for Unit 2 Cycle 29 as required by Technical Specification 5.6.5. These values have been established using NRC approved methodologies and are established such that all applicable limits of the 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 (lTC)

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:H)

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

11. 3.4.1 RCS Pressure, Temperature, and Flow - Departure from Nucleate Boiling (DNB) Limits

12. 3.9.1 Boron Concentration

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

Reference Technical Specification 2.1.1.

2. 3 .1.1 Shutdown Margin Requirements The Minimum Shutdown Margin requirements are shown in Table 1.

Reference Technical Specification 3 .1.1.

Page 2 of24

Core Operating Limits Report Unit 2, Cycle 29 Revision 0

3. 3.1.3 Isothermal Temperature Coefficient (lTC)

The lTC Upper limit is:

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 The lTC Lower limit is:

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 a 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.

Page 3 of24

Core Operating Limits Report Unit 2, Cycle 29 Revision 0

7. 3.2.1 Heat Flux Hot Channel Factor (FQ@

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 are only applicable to Figure 5.

The W(Z) values in Table 4 are only applicable to Figure 6.

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 only applicable to Figure 5.

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

The F wq(Z) Penalty Factors associated with Figure 6 and Table 4 are provided in Table 5.

The Axial Flux Difference (AFD) Band in Figure 6 is more restrictive than the AFD Band in Figure 5. Prior to switching from Figure 6 to Figure 5, Fwq(Z) must be confirmed to meet Technical Specification requirements by one of the following methods:

1. Confirm Fwq(Z) meets the Technical Specification Limit with the Table 2 W(Z) values for the most recent surveillance performed.

2. Perform a new surveillance and confirm Fwq(Z) meets the Technical Specification Limit with the Table 2 W(Z) values.

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 Page 4 of24

Core Operating Limits Report Unit 2, Cycle 29 Revision 0 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 or Table 4 should be used.

W(Z) values should be multiplied by the factor 1/P, when P > 0.5. When P is :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 F0 (Z) limit at part power conditions.

Reference Technical Specification 3.2.1.

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

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

F~H::s:; 1.77x[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.

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 or the more restrictive operational space as defined by Figure 6.

Both Figures 5 and 6 can be used any time during the cycle.

Prior to switching to the more restrictive AFD envelope (Figure 6), it should be confirmed that the plant is within the specified AFD envelope.

Reference Technical Specification 3.2.3.

Page 5 of24

Core Operating Limits Report Unit 2, Cycle 29 Revision 0

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 The Overtemperature ~ T setpoint parameter values are:

~To Indicated ~Tat RATED THERMAL POWER(%), op T Average temperature, op T' 560.0 °F p Pressurizer Pressure, psig P' 2235 psig K1 s 1.17 K2 0.014 /°F K3 0.00100 /psi

'tJ 30 seconds

't2 4 seconds f(AI) 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 q1 and qb are the percent power in the top and bottom halves of the core respectively, and q1 + qb is total core power in percent of RATED THERMAL POWER, such that (a) For q1 - qb within -13, +8 % f(AI) = 0 (b) For each percent that the magnitude of q1 - 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 q1 - qb exceeds -13 % the

~ T trip setpoint shall be automatically reduced by an equivalent of 3.846

%of RATED THERMAL POWER.

Overpower ~ T Setpoint The Overpower ~ T setpoint parameter values are:

~To Indicated ~Tat RATED THERMAL POWER(%), op T Average temperature, op T' 560.0 °F K4 s 1.11 K5 0.0275/°F for increasing T; 0 for decreasing T K6 0.002/°F forT > T' ; 0 for T s T' 1:3 10 seconds Reference Technical Specification 3.3 .1 Page 6 of24

Core Operating Limits Report Unit 2, Cycle 29 Revision 0

11. 3 .4.1 RCS Pressure, Temperature, and Flow - Departure from Nucleate Boiling CDNB) Limits The DNB Limits are:

Pressurizer pressure limit = 2190 psia RCS average temperature limit = 564 op 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.

Page 7 of24

Core Operating Limits Report Unit 2, Cycle 29 Revision 0 REFERENCES (NRC Approved Methodologies for COLR Parameters)

1. NSPNAD-8101-A, "Qualification of Reactor Physics Methods for Application to Prairie Island,"

Revision 2, October 2000.

2. NSPNAD-8102-PA, "Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units," Revision 7, July 1999.

3. NSPNAD-97002-PA, "Northern States Power 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. Not used.

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 CPR 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, April1993.

11. NAD-PI-003, "Prairie Island Nuclear Power Plant Required Shutdown Margin During Physics Tests," Revision O,January 2001.

12. NAD-PI-004, "Prairie Island Nuclear Power Plant FwQ(Z) Penalty With Increasing [FcQ(Z) I 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 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 of24

Core Operating Limits Report Unit 2, Cycle 29 Revision 0

14. WCAP-8745-P-A, "Design Bases for the Thermal Overpower fl.T and Thermal Overtemperature fl.T Trip Functions," September 1986.

15. WCAP-11397-P-A, "Revised Thermal Design Procedure," April1989.

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 U0 2 Fuel Rod," December 1989.

19. WCAP-7907-P-A, "LOFTRAN Code Description," April1984.

20. WCAP-7979-P-A, "TWINKLE - A Multidimensional Neutron Kinetics Computer Code,"

January 1975.

21. WCAP-10965-P-A, "ANC: A Westinghouse Advanced Nodal Computer Code," September 1986.

22. WCAP-11394-P-A, "Methodology for the Analysis of the Dropped Rod Event," January 1990.

23. WCAP-11596-P-A, "Qualification of the PHOENIX-P/ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988.

24. WCAP-12910 Rev. 1-A, "Pressurizer Safety Valve Set Pressure Shift," May 1993.

25. WCAP-14565-P-A, "VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis," October 1999.

26. WCAP-14882-P-A, "RETRAN-02 Modeling and Qualification for Westinghouse Pressurized Water Reactor Non-LOCA Safety Analyses," April1999.

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 --./TM System," Revision 0, March 1997.

29. Caldon, Inc. Engineering Report-157P, "Supplement to Topical Repott 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," Aprill995.

Page 9 of24

Core Operating Limits Report Unit 2, Cycle 29 Revision 0

31. WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLOTM," July 2006.

32. 50.59 Evaluation 1123, Revision 0 "Unit 2 Cycle 29 Core Reload Modification."

Optimized ZIRLO' is a trademark of Westinghouse Electric Company LLC, its Affiliates and/or 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 of24

Core Operating Limits Report Unit 2, Cycle 29 Revision 0 Table 1 Minimum Required Shutdown Margin, %Ap 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 Mode2 0-1 Pump 2 Pumps 3 Pumps 0 - 24750 MWd/MTU 0.5 0.5 0.5 Tave;:: 520°F (Most Reactive Rod Out)

Mode3 0-1 Pump 2 Pumps 3 Pumps 0 - 24750 MWd/MTU 2.0 2.0 2.0 350°F :S Tave < 520°F (Most Reactive Rod Out)

Mode3 0-1 Pump 2 Pumps 3 Pumps OMWd/MTU 2.0 2.0 2.0 14000 MWd/MTU 2.0 2.0 2.0 24750 MWd/MTU 2.0 2.0 2.0 200°F < Tave < 350°F (Most Reactive Rod Out)

Mode4 0-1 Pump 2 Pumps 3 Pumps OMWd/MTU 2.0 4.0 6.5 14000 MWd/MTU 2.0 3.0 . 5.0 24750 MWd/MTU 2.0 2.0 2.5 Operational Mode Definitions, as per TS Table 1.1-1.

For Mode 1 and Mode 2 with Keff;:: 1.0, the minimum shutdown margin requirements are provided by the Rod Insertion Limits.

- Charging pump(s) in service only pertains to steady state operations. It does not include transitory operations. For example, operations such as starting a second charging pump in order to secure the operating pump would fall under the one pump in service column.

Page 11 of24

Core Operating Limits Report Unit 2, Cycle 29 Revision 0 Table 1, Continued Minimum Required Shutdown Margin, %Ap Number of Charging Pumps Running**

68°F :STave :S 200°F (Most Reactive Rod Out)

ModeS 0-1 Pump 2 Pumps 3 Pumps 0 MWd/MTU*** 2.5 4.5 7.0 14000 MWd/MTU 2.0 3.5 5.5 24750 MWd/MTU 2.0 2.0 3.0 68°F :STave< 200oF (ARI}

Mode6 0-1 Pump 2 Pumps 3 Pumps 0 MWd/MTU*** 5.129 5.129 7.0 14000 MWd/MTU 5.129 5.129 5.129 24750 MWd/MTU 5.129 5.129 5.129 68°F :STave< 200°F (ARO)

Mode6 0-1 Pump 2 Pumps 3 Pumps 0 MWd/MTU*** 5.129 5.5 8.5 14000 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 2 Cycle 28 end of cycle.

Page 12 of24

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

Height BU [MWd/MTU]

[ft]

150 7000 13000 16000 18000 20000 22000 AO =-3.21 AO =-3.73 AO =-5.39 AO =0.85 AO =2.23 AO =1.27 AO =-0.13

[BOTTOM] 1 0.00 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 3 0.40 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 5 0.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 6 1.00 1.1998 1.1680 1.1660 1.2506 1.2618 1.2373 1.2204 7 1.20 1.1918 1.1613 1.1581 1.2428 1.2542 1.2297 1. 2124 8 1.40 1.1822 1.1533 1.1489 1. 2336 1. 2453 1.2208 1. 2033 9 1.60 1.1716 1.1445 1.1387 1.2234 1. 2356 1. 2113 1.1938 10 1.80 1.1602 1.1351 1.1278 1.2124 1. 2251 1.2012 1.1839 11 2.00 1.1482 1.1251 1.1165 1.2008 1.2140 1.1905 1.1737 12 2.20 1.1359 1.1150 1.1049 1.1886 1.2024 1.1795 1.1631 13 2.40 1.1233 1.1047 1.0934 1.1762 1.1904 1.1679 1.1524 14 2.60 1.1109 1.0959 1.0821 1.1635 1.1784 1.1562 1.1415 15 2.80 1.1008 1. 0931 1.0704 1.1505 1.1672 1.1479 1.1298 16 3.00 1.0967 1. 0915 1.0641 1.1401 1.1544 1.1383 1.1233 17 3.20 1.0960 1.0901 1.0633 1.1358 1.1472 1.1348 1.1227 18 3.40 1.0952 1.0893 1.0643 1.1356 1.1467 1.1391 1.1260 19 3.60 1.0940 1.0878 1.0684 1.1343 1.1446 1.1421 1.1317 20 3.80 1.0941 1.0869 1.0736 1.1325 1.1422 1.1446 1.1370 21 4.01 1.0952 1.0877 1.0785 1.1303 1.1415 1.1464 1.1413 22 4.21 1. 0961 1.0894 1.0828 1.1275 1.1412 1.1474 1.1448 23 4.41 1.0966 1.0908 1.0866 1.1241 1.1398 1.1473 1.1474 24 4.61 1.0966 1.0932 1.0899 1.1201 1.1378 1.1465 1.1489 25 4.81 1. 0962 1.0958 1.0927 1.1156 1.1349 1.1488 1.1493 26 5.01 1.0951 1.0980 1.0950 1.1105 1.1317 1.1530 1.1489 27 5.21 1.0950 1.0996 1.0967 1.1091 1.1265 1.1565 1.1472 28 5.41 1.0972 1.1010 1.0983 1.1117 1.1233 1.1588 1.1458 29 5.61 1.1007 1.1035 1.1016 1.1137 1.1299 1.1600 1.1480 30 5.81 1.1054 1.1087 1.1067 1.1214 1.1368 1.1597 1.1561 31 6.01 1.1114 1.1155 1.1121 1.1312 1.1426 1.1623 1.1650 32 6.21 1.1172 1.1221 1.1165 1.1402 1.1476 1.1691 1.1722 33 6.41 1.1227 1.1283 1.1213 1.1483 1.1515 1.1756 1.1785 34 6.61 1.1298 1.1359 1.1293 1.1554 1.1543 1.1807 1.1836 35 6.81 1.1383 1.1430 1.1376 1.1616 1.1560 1.1845 1.1873 36 7.01 1.1463 1.1494 1.1450 1.1665 1.1567 1.1869 1.1900 37 7.21 1.1532 1.1546 1.1519 1.1703 1.1568 1.1878 1.1919

Lmear extrapolatiOn based on a lme between 20,000 MWD/MTU and 22,000 MWD/MTU IS adequate for addressmg burnups beyond 22,000 MWD/MTU.

Page 13 of24

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

Height BU [MWd/MTU]

[ft]

150 7000 13000 16000 18000 20000 22000 AO =-3.21 AO = -3.73 AO = -5.39 AO = 0.85 AO =2.23 AO = 1.27 AO = -0.13 38 7.41 1.1595 1.1600 1.1596 1.1726 1.1561 1.1871 1.1926 39 7.61 1.1656 1.1677 1.1689 1.1735 1.1541 1.1847 1.1916 40 7.81 1.1706 1.1748 1.1774 1.1729 1.1506 1.1806 1.1888 41 8.01 1.1742 1.1806 1.1848 1.1707 1.1457 1.1745 1.1842 42 8.21 1.1765 1.1853 1.1911 1.1667 1.1396 1.1669 1.1777 43 8.41 1.1774 1.1888 1.1962 1.1612 1.1318 1.1572 1.1695 44 8.61 1.1790 1.1910 1. 2002 1.1540 1.1225 1.1461 1.1621 45 8.81 1.1857 1.1927 1.2034 1.1441 1.1171 1.1422 1.1599 46 9.01 1.1938 1. 2005 1.2128 1.1400 1.1146 1.1387 1.1584 47 9.21 1. 2036 1.2126 1. 2266 1.1398 1.1104 1.1338 1.1531 48 9.41 1.2168 1.2225 1.2382 1.1423 1.1060 1.1311 1.1475 49 9.61 1.2290 1. 2316 1.2499 1.1433 1.1111 1.1285 1.1481 50 9.81 1. 2453 1.2375 1. 2633 1.1456 1.1172 1.1328 1.1517 51 10.01 1.2616 1. 2495 1.2767 1.1488 1.1225 1.1409 1.1563 52 10.21 1.2776 1. 2662 1.2881 1.1521 1.1280 1.1475 1.1598 53 10.41 1.2958 1.2780 1. 2987 1.1560 1.1334 1.1544 1.1630 54 10.61 1. 3102 1.2902 1.3131 1.1627 1.1389 1.1611 1.1676 55 10.81 1.3236 1. 2986 1.3228 1.1666 1.1420 1.1658 1.1718 56 11.01 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 58 11.41 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 60 11.81 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

Lmear extrapolatton based on a hne between 20,000 MWD/MTU and 22,000 MWD/MTU IS adequate for addressmg burnups beyond 22,000 MWD/MTU.

Table 3 FwQ(Z) Penalty Factor associated with Figure 5 and Table 2**

Cycle Burnup (MWD/MTU) Fw0 (z) Penalty Factor 0 1.0200 13692 1.0200 13829 1.0212 13966 1.0221 14102 1.0212 14239 1.0202 14376 1.0200 24750 1.0200

- Linear interpolation is adequate for intermediate cycle burn ups.

Page 14 of24

Core Operating Limits Report Unit 2, Cycle 29 Revision 0 T a bie 4 - W() z Va Iues associated wit . hF'1gure 6(T op 10%o an dB 0 ttom 8%o excIu d ed)*

Height BU [MWd/MTU]

[ft]

150 7000 13000 16000 18000 20000 22000 AO =-3.21 AO =-3.73 AO =-5.39 AO =0.85 AO =2.23 AO =1.27 AO =-0.13

[BOTTOM] 1 e.ee 1.eeee 1.eeee 1.eeee 1.eeee 1.eeee 1.eeee 1.eeee 2 e.2e 1.eeee 1.eeee 1.eeee 1.eeee 1.eeee 1.eeee 1.eeee 3 e.4e 1.eeee 1.eeee 1.eeee 1.eeee 1.eeee 1.eeee 1. eeee 4 e.6e 1.eeee 1.eeee 1.eeee 1.eeee 1.eeee 1.eeee 1.eeee 5 e.8e 1.eeee 1.eeee 1.eeee 1.eeee 1.eeee 1.eeee 1.eeee 6 1.ee 1.15e1 1.1124 1.1e37 1.1839 1.1987 1.1742 1.1817 7 1.2e 1.1434 1.1e73 1.e979 1.1779 1.1923 1.1677 1.1745 8 1.4e 1.1352 1.1e11 1.e91e 1.17e6 1.1847 1.16e1 1.1662 9 1.6e 1.1263 l.e944 1.e834 1.1626 1.1766 1.1519 1.1575 1e 1.8e 1.1166 l.e871 1. e753 1.1541 1.1678 1.1434 1.1484 11 2.ee 1.1e65 1.e796 1. e67e 1.1451 1.1587 1.1344 1.139e 12 2.2e 1. e962 l.e719 1.e585 1.1358 1.1492 1.1253 1.1294 13 2.4e l.e858 1.e644 l.e5e3 1.1266 1.1397 1.1158 1.1198 14 2.6e l.e756 1.e57e l.e423 1.1172 1.13e9 1.1e71 1.1e99 15 2.8e 1.e659 l.e494 1.e341 1.1e73 1.1222 1.1e18 l.e992 16 3.ee 1.e557 l.e48e 1.e323 1.1e21 1.1132 l.e965 l.e939 17 3.2e 1.e527 1.e5e5 1.e328 1.1e22 1.11e4 l.e97e 1.e939 18 3.4e 1.e58e 1.e569 l.e368 1.1e41 1.1114 1.1e41 l.e97e 19 3.6e l.e626 l.e626 1.e451 1.1e54 1.1118 1.1e96 1.1e28 2e 3.8e 1.e669 l.e68e 1.e529 1.1e64 1.1126 1.1145 1.1e78 21 4.e1 1.e71e l.e73e 1.e6e1 1.1e7e 1.1149 1.12e3 1.1141 22 4.21 1. e747 1.e776 1.e67e 1.1e72 1.1173 1.1278 1.12e9 23 4.41 l.e78e l.e817 1.e734 1.1e68 1.1189 1.136e 1.1264 24 4.61 l.e815 1.e852 1.e793 1.1e59 1.1198 1.1428 1.131e 25 4.81 l.e86e l.e883 1.e847 1.1e52 1.12e2 1.1485 1.1346 26 5.e1 l.e9e4 l.e923 1.e896 1.1e59 1.1195 1.153e 1.1376 27 5.21 l.e94e l.e968 1.e941 1.1e88 1.1193 1.1565 1.1389 28 5.41 l.e972 1.1ee3 l.e981 1.1117 1.1225 1.1588 1.14e7 29 5.61 1.1ee7 1.1e35 1.1e16 1.1137 1.1299 1.1599 1.1473 3e 5.81 1.1e54 1.1e87 1.1e67 1.1178 1.1368 1.1597 1.1561 31 6.e1 1.1114 1.1155 1.1121 1.1236 1.1426 1.1584 1.1649 32 6.21 1.1172 1.1221 1.1165 1.1299 1.1476 1.1577 1.1722 33 6.41 1.1227 1.1283 1.1213 1.1352 1.1515 1.1598 1.1785 34 6.61 1.1298 1.1359 1.1293 1.1397 1.1543 1.1621 1.1836 35 6.81 1.1383 1.143e 1.1376 1.1433 1.156e 1.1632 1.1873 36 7.e1 1.1463 1.1493 1.145e 1.1458 1.1565 1.1634 1.1897 37 7.21 1.1532 1.1546 1.1518 1.1479 1.1557 1.163e 1.19e6

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

Page 15 of24

Core Operating Limits Report Unit 2, Cycle 29 Revision 0 Table 4 (cont.)- W(z) Values associated with Figure 6 (Top 10% and Bottom 8% excluded)*

Height BU [MWd/MTU]

[ft]

150 7000 13000 16000 18000 20000 22000 AO =-3.21 AO =-3.73 AO =-5.39 AO =0.85 AO =2.23 AO =1.27 AO =-0.13 38 7.41 1.1595 1.1598 1.1587 1.1495 1.1536 1.1616 1.1898 39 7.61 1.1656 1.1641 1.1678 1.1497 1.1581 1.1586 1.1873 48 7.81 1.1786 1.1671 1.1757 1.1487 1.1451 1.1542 1.1829 41 8.81 1.1742 1.1684 1.1834 1.1464 1.1387 1.1482 1.1767 42 8.21 1.1765 1.1695 1.1899 1.1425 1.1389 1.1489 1.1685 43 8.41 1.1774 1.1724 1.1951 1.1374 1.1214 1.1317 1.1584 44 8.61 1.1768 1.1749 1.1998 1.1318 1.1183 1.1288 1.1478 45 8.81 1.1729 1.1753 1.2882 1.1219 1.1821 1.1166 1.1434 46 9.81 1.1754 1.1766 1. 2851 1.1175 1.8963 1.1148 1.1391 47 9.21 1.1839 1.1835 1.2123 1.1165 1.8918 1.1884 1.1332 48 9.41 1.1922 1.1958 1.2183 1.1142 1.8985 1.1828 1.1298 49 9.61 1.2862 1.2868 1. 2384 1.1166 1.8947 1.8994 1.1265 58 9.81 1.2288 1.2223 1.2419 1.1181 1.8989 1.1813 1.1261 51 18.81 1.2364 1.2363 1.2544 1.1197 1.1825 1.1855 1.1287 52 18.21 1.2544 1.2477 1.2675 1.1286 1.1855 1.1882 1.1351 53 18.41 1.2782 1.2599 1.2791 1.1194 1.1882 1.1189 1.1488 54 18.61 1.2888 1. 2663 1.2928 1.1228 1.1138 1.1152 1.1469 55 18.81 1.2994 1.2698 1.2976 1.1339 1.1157 1.1185 1.1515 56 11.81 1.0000 1.0000 1.0000 1.8888 1.0000 1.0000 1.0000 57 11.21 1.0000 1.0000 1.0000 1.8888 1.0000 1.0000 1.0000 58 11.41 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 59 11.61 1.0000 1.8888 1.0000 1.8888 1.0000 1.0000 1.0000 68 11.81 1.0000 1.0000 1.0000 1.8888 1.0000 1.8888 1.0000

[TOP] 61 12.81 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

Lmear extrapolation based on a lme between 20,000 MWD/MTU and 22,000 MWD/MTU IS adequate for addressmg burn ups beyond 22,000 MWD/MTU.

Table 5 FwQ(Z) Penalty Factor associated with Figure 6 and Table 4**

Cycle Burnup (MWD/MTU) Fw0 (z) Penalty Factor 0 1.020 24750 1.020

- Linear interpolation is adequate for intermediate cycle burnups.

Page 16 of24

Core Operating Limits Report Unit 2, Cycle 29 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 sott D*Bank @ 195 Stepst D*Bank@ 204 Stepst

[ft] HFP AO = *3.21 HFP AO = -3.21

[BOTTOM]

1 0.00 1.0000 1. 0000 2 0.20 1.0000 1.0000 3 0.40 1. 0000 1.0000 4 0.60 1.0000 1. 0000 5 0.80 1.0000 1.0000 6 1.00 1. 2268 1.2136 7 1. 20 1. 2165 1.2045 8 1,40 1.2043 1.1935 9 1.60 1.1910 1.1816 HI 1. 80 1.1768 1.1687 11 2.00 1.1620 1.1554 12 2.20 1.1473 1.1422 13 2.40 1.1324 1.1287 14 2.60 1.1178 1.1153 15 2.80 1.1056 1.1039 16 3.00 1. 0993 1.0986 17 3.20 1. 0961 1. 0967 18 3.40 1. 0927 1.0948 19 3.60 1. 0891 1.0924 20 3.80 1.0870 1. 0914 21 4.01 1.0858 1.0914 22 4.21 1.0846 1. 0912 23 4.41 1. 0832 1.0906 24 4.61 1. 0812 1.0894 25 4.81 1.0788 1.0879 26 5.01 1.0758 1.0857 27 5.21 1.0737 1.0845 28 5.41 1. 0740 1.0858 29 5.61 1.0757 1.0884 30 5.81 1.0785 1. 0921

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%

j: Rod insertion is given as a target value. Use control rods as necessary to control to target AO Page 17 of24

Core Operating Limits Report Unit 2, Cycle 29 Revision 0 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 gott D-Bank @ 195 Steps+ D-Bank @ 204 Steps+

[ft] HFP AO = -3.21 HFP AO = -3.21 31 6.01 1.0827 1.0970 32 6.21 1.0867 1.1018 33 6.41 1.0906 1.1063 34 6.61 1. 0962 1.1126 35 6.81 1.1033 1.1202 36 7.01 1.1099 1.1274 37 7.21 1.1158 1.1339 38 7.41 1.1217 1.1400 39 7.61 1.1277 1.1460 40 7.81 1.1330 1.1512 41 8.01 1.1372 1.1552 42 8.21 1.1406 1.1580 43 8.41 1.1430 1.1596 44 8.61 1.1466 1.1618 45 8.81 1.1554 1.1694 46 9.01 1.1662 1.1788 47 9.21 1.1792 1.1902 48 9.41 1.1960 1.2051 49 9.61 1. 2126 1.2197 50 9.81 1. 2335 1. 2385 51 10.01 1.2550 1. 2574 52 10.21 1.2768 1. 2763 53 10.41 1.3008 1.2977 54 10.61 1. 3195 1. 3143 55 10.81 1.3373 1. 3301 56 11.01 1.0000 1.0000 57 11.21 1.0000 1.0000 58 11.41 1.0000 1.0000 59 11.61 1.0000 1.0000 60 11.81 1.0000 1.0000

[TOP] 61 12.01 1.0000 1.0000

W(z) values only valid for core average burnups s 150 MWd/MTU t 80% of full power W(z) values are applicable for powers 75% s P < 85%

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

j: Rod insertion is given as a target value. Use control rods as necessary to control to target AO Page 18 of24

Core Operating Limits Report Unit 2, Cycle 29 Revision 0 Figure 1 Reactor Core Safety Limits 2425 psia

-~---

660~~~~~~~~~~~~~~~~~~~~~~~~~

tllli-;t+/-=:ti::+/-;;:t;:-HIItlllilli Unacceptable 1 1 H-11-+-+-t-+-l f--+r-----T'--t::---l-----i 2250 psia rf-1-~--+~--~d-----jl--+--t-+-l-+--l-+-+-+-+-+-+--+-+-f-1--t-+-1---1 r-- ~ 1---. I--I--I--

11850 psia I 1"'- "~

LL.

0 1"'- \

\ \

I'\ \ \

\ \

\

0 0.2 0.4 0.6 0.8 1 1.2 1.4 Fraction of 1677 MWt Rated Thermal Power Page 19 of24

Core Operating Limits Report Unit 2, Cycle 29 Revision 0 Figure 2 Rod Insertion Limit, 128 Step Tip-to-Tip Cl) 150 c.

.s en c

0 ECl) 0

a. 100

.:a.:

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

Bank D = (150 I 63) * (P- 100) + 185

Bank C = (150 I 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. The ARO parking position may be any position above 224 steps.

Page 20 of24

Core Operating Limits Report Unit 2, Cycle 29 Revision 0 Figure 3 Rod Insertion Limit, 128 Step Tip-to-Tip, One Bottomed Rod (Technical Specification 3.1.4, Condition B) 224

/ /i 200 v I I

/

Banke I I

I I

I 150 v

Ill c..

Q)

( /)

c-0 "iii 100 /

/ Operation Forbidden in this Region 4

0 a..

..1<:

c

<1l (Q

50 /

v I

I I

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

Bank D = (150 I 63) * (P- 90) + 224

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

Page 21 of24

Core Operating Limits Report Unit 2, Cycle 29 Revision 0 Figure 4 Rod Insertion Limit, 128 Step Tip-to-Tip, One Inoperable Rod (Technical Specification 3.1.4, Condition A) 224 200

/ V1 I Va'ankC I I

I I

I 150

~

C/)

a. Operation

<1.) Forbidden in (j) this Region c0 ./

+' 100 "ii) v 0

0..

~

t:

ro co 50 I

I I

I

~

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

Bank D = (150 I 63) * (P -70) + 224

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

Page 22 of24

Core Operating Limits Report Unit 2, Cycle 29 Revision 0 Figure 5 Flux Difference Operating Envelope associated with Table 2 and Table 6 110

-9 8 100 IUnacceptable IJ 17 90

\I 1\

Unacceptable I 80 I 1/

\

I I Acceptable I \ \

70

~

60 I \\

0 a.

'*' 50 I ~

-22 21 40 30 20 10 0

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

Page 23 of24

Core Operating Limits Report Unit 2, Cycle 29 Revision 0 Figure 6 Flux Difference Operating Envelope associated with Table 4 110

-6 6 100 90 I Unacceptable III IAcceptable I

\\ I Unacceptable I 80 J 1\

70 Iv \\

... 60 I 1\

~

0 c..

?ft.

50

-19 I \ 19 40 30 20 10 0

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

Page 24 of24

fl Xcel Energy*

L-PI-16-008 JAN 2 5 2016 TS 5.6.5.d U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Unit 2 Docket 50-306 Renewed License No. DPR-60 Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 2. Cycle 29, 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"),

submits the COLR for the PINGP Unit 2, Cycle 29, 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.

The COLR for PINGP Unit 2, Cycle 29, Revision 0, is provided in Enclosure 1.

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

Y.~~

K~avison Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company- Minnesota Enclosure cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC State of Minnesota 1717 Wakonade Drive East

Welch, Minnesota 55089-9642 Telephone: 651.388.1121