ML25295A685

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Nuclear Generating Plant Unit 2 - Core Operating Limits Report (COLR) Cycle 34, Revision 0
ML25295A685
Person / Time
Site: Prairie Island 
Issue date: 10/21/2025
From: Currier B
Nuclear Management Co, Xcel Energy
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
L-PI-25-045
Download: ML25295A685 (1)
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Text

Xcel Energy 1717Wakonade Drive Welch, MN 55089 October 21,2025 L-PI-25-045 TS 5.6.5.d 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 DPR-60 Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP)

Unit 2, Cycle 34, Revision 0 Pursuant to the reguirements of Technical Specification 5.6.5.d, Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter NSPM),

hereby submits Revision 0 of the PINGP Unit 2, Cycle 34 COLR.

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

Plant Manager, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc: Administrator, Region III, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC State of Minnesota Connected

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ENCLOSURE 1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT UNIT 2, CYCLE 34 REVISION 0 45 pages follow

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

Approval Date Remarks 2

13 0

3/22/90 Original Unit 2 Core Operating Limits Report, distributed with Technical Specification Revision

92.

1 14 0

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

92.

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

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

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

2 14 0

Not used.

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

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

1 15 0

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

2 15 0

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

1 16 0

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

2 16 0

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

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

Approval Date Remarks 2

16 1

11/3/94 The table containing the bounding V(z) values and Figure 2 updated to incorporate revised bounding V(z) values for the exposure range of 14-21.5 GWD/MTU. Figures 3 through 6 re-formatted.

1 17 0

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

2 17 0

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

1 18 0

2/7/96 Updated to Unit 1 Cycle 18. Incorporated revised H

F limit of 1.77. Incorporated Table 1 and updated Figure 2 with revised bounding V(z) values.

2 18 0

2/27/97 Updated to Unit 2 Cycle 18. Revised H

F limit to 1.77. Updated Table 1 and Figures 2a through 2e with revised bounding V(z) values.

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

1 19 0

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

2 19 0

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

1 20 0

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

1 8/4/00 Technical Specification Amendment 151:

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

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

Approval Date Remarks 2

20 0

5/31/00 Updated to Unit 2 Cycle 20. Updated Table 1 and Figures 2a through 2d with revised bounding V(z) values. Added new Table 2 and Figures 2e, 2f and 2g with additional bounding V(z) values.

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

1 8/4/00 Technical Specification Amendment 142:

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

1 20 2

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

1 21 0

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

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

21.

1 21 1

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

1 21 2

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

2 21 0

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

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

Approval Date Remarks 2

21 1

10/02/02 Revised to support License Amendment 149 changes, including revision of all references to TS, revision of FQ symbols, addition of Table 4, ITC limits, DNB limits and refueling boron concentrations. Also revised to include an additional V(z) curve to give greater FQ margin between 13.0 and 16.0 GWd/MTU.

1 22 0

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

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

2 22 0

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

1 22 1

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

2 22 1

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

2 22 2

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

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

Approval Date Remarks 1

22 2

7/16/04 Revised Fq limit form 2.4 to 2.5. Removed OP and OT delta-T setpoints based on NMC methodology and replaced with Westinghouse developed setpoints.

1 23 0

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

2 23 0

Not used due to core redesign.

2 23 1

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

1 23 1

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

1 24 0

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

1 24 1

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

2 24 0

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

2 24 1

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

2 24 2

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

1 24 2

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

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

Approval Date Remarks 2

24 3

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

1 25 0

2/24/08 Updated to Unit 1 Cycle 25 1

25 1

5/28/08 Updated Table 2 to reflect the correct W(z) at a burnup of 150 MWd/MTU and a core height of 6.20 feet 2

1 25 26 0

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

2 26 26 0

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

2 1

1 1

1 26 26 26 26 27 27 1

2 2

3 0

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

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

27 0

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

28 0

11/29/12 Updated for Unit 1 Cycle 28

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

Approval Date Remarks 2

28 0

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

2 29 29 0

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

2 1

2 2

30 30 31 31 31 0

0 0

0 1

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

2 2

32 32 32 0

0 1

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

1 1

33 33 34 34 0

0 0

1 10/13/22 10/26/23 10/22/24 03/05/25 Updated for Unit 1 Cycle 33 Updated for Unit 2 Cycle 33 Updated for Unit 1 Cycle 34 Updated burnup values on Table 2 2

34 0

10/21/25 Updated for Unit 2 Cycle 34

PRAIRIE ISLAND UNIT 2 CYCLE 34 CORE OPERATING LIMITS REPORT (COLR)

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Page 1 of 38 Note: This report is NOT part of the Technical Specifications but is referenced.

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Revision 0 Prepared by:

LDC 600001299653 Michael Young Senior Engineer, Nuclear Analysis and Design Verified by:

LDC 600001299651 Steve Winston Senior Engineer, Nuclear Analysis and Design Reviewed by:

LDC 600001299652 Reginald Glick Senior Engineer, Reactor Engineering Approved by:

LDC 600001299650 Melissa Limbeck Manager, Nuclear Analysis and Design

PRAIRIE ISLAND UNIT 2 CYCLE 34 CORE OPERATING LIMITS REPORT (COLR)

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  • Safe TABLE OF CONTENTS CORE OPERATING LIMITS REPORT (COLR)............................................................................. 4 1 [TS 2.1.1] REACTOR CORE SAFETY LIMITS......................................................................... 5 2 [TS 3.1.1] SHUTDOWN MARGIN REQUIREMENTS................................................................ 6 3 [TS 3.1.3] ISOTHERMAL TEMPERATURE COEFFICIENT (ITC)................................................. 7 4 [TS 3.1.5] SHUTDOWN BANK INSERTION LIMITS................................................................ 8 5 [TS 3.1.6] CONTROL BANK INSERTION LIMITS................................................................... 9 6 [TS 3.1.8] PHYSICS TESTS EXCEPTIONS - MODE 2............................................................. 10 7 [TS 3.2.1] HEAT FLUX HOT CHANNEL FACTOR FQ(Z)........................................................... 11 8 [TS 3.2.2] NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (FHN)..................................... 13 9 [TS 3.2.3] AXIAL FLUX DIFFERENCE (AFD)........................................................................ 14 10 [TS 3.3.1] REACTOR TRIP SYSTEM (RTS) INSTRUMENTATION............................................. 15 11 [TS 3.4.1] RCS PRESSURE, TEMPERATURE, AND FLOW - DEPARTURE FROM NUCLEATE BOILING (DNB) LIMITS................................................................................................................ 16 12 [TS 3.9.1] REFUELING BORON CONCENTRATION............................................................... 17 13 REFERENCES................................................................................................................ 18

PRAIRIE ISLAND UNIT 2 CYCLE 34 CORE OPERATING LIMITS REPORT (COLR)

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.................................................................................................................................................................... 29 Table 6: Required THERMAL POWER Limits and AFD Reductions............................................................ 30 LIST OF FIGURES Figure 1: Reactor Core Safety Limits.......................................................................................................... 31 Figure 2: Rod Insertion Limit, 128 Step Tip-to-Tip.................................................................................... 32 Figure 3: Rod Insertion Limit, 128 Step Tip-to-Tip, One Bottomed Rod.................................................. 33 Figure 4: Rod Insertion Limit, 128 Step Tip-to-Tip, One Inoperable Rod................................................. 34 Figure 5: Flux Difference Operating Envelope associated with ROS1 (Table 2 and Table 3)................... 35 Figure 6: Flux Difference Operating Envelope associated with ROS2 (Table 4 and Table 5)................... 36 Figure 7: Flux Difference Operating Envelope associated with ROS2 95% THERMAL POWER Required Action (Table 4, Table 5, and Table 6)....................................................................................................... 37 Figure 8: Flux Difference Operating Envelope associated with ROS2 90% THERMAL POWER Required Action (Table 4, Table 5, and Table 6)....................................................................................................... 38

PRAIRIE ISLAND UNIT 2 CYCLE 34 CORE OPERATING LIMITS REPORT (COLR)

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This report provides the values of the limits for Unit 2 Cycle 34 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

[TS 2.1.1]

Reactor Core Safety Limits 2

[TS 3.1.1]

Shutdown Margin Requirements 3

[TS 3.1.3]

Isothermal Temperature Coefficient (ITC) 4

[TS 3.1.5]

Shutdown Bank Insertion Limits 5

[TS 3.1.6]

Control Bank Insertion Limits 6

[TS 3.1.8]

Physics Tests Exceptions - Mode 2 7

[TS 3.2.1]

Heat Flux Hot Channel Factor FQ(z) 8

[TS 3.2.2]

Nuclear Enthalpy Rise Hot Channel Factor (FHN) 9

[TS 3.2.3]

Axial Flux Difference (AFD) 10

[TS 3.3.1]

Reactor Trip System (RTS) Instrumentation 11

[TS 3.4.1]

RCS Pressure, Temperature, and Flow - Departure from Nucleate Boiling (DNB) Limits 12

[TS 3.9.1]

Refueling Boron Concentration

PRAIRIE ISLAND UNIT 2 CYCLE 34 CORE OPERATING LIMITS REPORT (COLR)

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[TS 2.1.1]

REACTOR CORE SAFETY LIMITS Reactor Core Safety Limits are shown in Figure 1.

Reference Technical Specification 2.1.1.

PRAIRIE ISLAND UNIT 2 CYCLE 34 CORE OPERATING LIMITS REPORT (COLR)

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[TS 3.1.1]

SHUTDOWN MARGIN REQUIREMENTS Minimum Shutdown Margin requirements are shown in Table 1.

Reference Technical Specification 3.1.1.

PRAIRIE ISLAND UNIT 2 CYCLE 34 CORE OPERATING LIMITS REPORT (COLR)

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[TS 3.1.3]

ISOTHERMAL TEMPERATURE COEFFICIENT (ITC)

ITC Upper Limit:

a. < 5 pcm/°F for power levels < 70% RATED THERMAL POWER (RTP); and
b. a line which slopes linearly from
i.

0 pcm/°F for power levels = 70% RTP to ii. -1.5 pcm/°F for power levels = 100% RTP ITC Lower Limit:

a. -43.15 pcm/°F Reference Technical Specification 3.1.3.

PRAIRIE ISLAND UNIT 2 CYCLE 34 CORE OPERATING LIMITS REPORT (COLR)

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[TS 3.1.5]

SHUTDOWN BANK INSERTION LIMITS The shutdown rods shall be fully withdrawn.

Reference Technical Specification 3.1.5.

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[TS 3.1.6]

CONTROL BANK INSERTION LIMITS The control rod banks shall be limited in physical insertion as shown in Figure 2, Figure 3, and Figure 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.

PRAIRIE ISLAND UNIT 2 CYCLE 34 CORE OPERATING LIMITS REPORT (COLR)

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[TS 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.

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[TS 3.2.1]

HEAT FLUX HOT CHANNEL FACTOR FQ(Z)

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

()

() > 0.5

()

0.5 () 0.5

() = [()]

[()]

()

1.0815 for P > 0.5

() = [()]

[()]

0.5

()

1.0815 for P 0.5

[()]

is the measured planar radial peaking factor.

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

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

The T(z) values are provided in Table 2 and Table 4.

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

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

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

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

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

Either ROS1 or ROS2 may be implemented at any time during the cycle.

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

Reference Technical Specification 3.2.1.

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[TS 3.2.2]

NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (FHN)

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

FH 1.77 x [1 + 0.3(1 - P)]

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

Reference Technical Specification 3.2.2.

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[TS 3.2.3]

AXIAL FLUX DIFFERENCE (AFD)

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

Reference Technical Specification 3.2.3.

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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.

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.

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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.

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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.

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1.

NSPNAD-8101-A, Qualification of Reactor Physics Methods for Application to Prairie Island, Revision 2, October 2000.

2.

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

3.

NSPNAD-97002-PA, Northern States Power Companys Steam Line Break Methodology, Revision 1, October 2000.

4.

WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, July, 1985.

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

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

6.

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

7.

WCAP-10924-P-A, Volume 1, Revision 1, and Volume 2, Revision 2, Westinghouse Large Break LOCA Best Estimate Methodology, September 2005.

8.

XN-NF-77-57-(A), XN-NF-77-57, Supplement 1 (A), Exxon Nuclear Power Distribution Control for Pressurized Water Reactors Phase II, May 1981.

9.

WCAP-13677-P-A, 10 CFR 50.46 Evaluation Model Report: W-COBRA/TRAC 2-Loop Upper Plenum Injection Model Update to Support ZIRLO' Cladding Options, February 1994.

10.

NSPNAD-93003-A, Prairie Island Units 1 and 2 Transient Power Distribution Methodology, Revision 0, April 1993.

11.

NAD-PI-003, Prairie Island Nuclear Power Plant Required Shutdown Margin During Physics Tests, Revision 0, January 2001.

12.

NAD-PI-004, Prairie Island Nuclear Power Plant FWQ(Z) Penalty With Increasing [FCQ(Z) /

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

13.

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

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

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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.

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31.

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

32.

ECR 601000005729 Rev.0 2R34 Core Reload

33.

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

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

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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 Mode 3 Tave 520°F (Most Reactive Rod Out) 0-1 Pump 2 Pumps 3 Pumps 0 - 25000 MWd/MTU 2.0 2.0 2.0 Mode 3 350°F Tave < 520°F (Most Reactive Rod Out) 0-1 Pump 2 Pumps 3 Pumps 0 MWD/MTU 2.0 2.0 2.0 3000 MWd/MTU 2.0 2.0 2.0 6000 MWd/MTU 2.0 2.0 2.0 11000 MWd/MTU 2.0 2.0 2.0 16000 MWd/MTU 2.0 2.0 2.0 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.

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Number of Charging Pumps Running**

Mode 4 200°F < Tave < 350°F (Most Reactive Rod Out) 0-1 Pump 2 Pumps 3 Pumps 0 MWD/MTU 2.0 4.0 6.0 3000 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 Number of Charging Pumps Running**

Mode 5 68°F Tave 200°F (Most Reactive Rod Out) 0-1 Pump 2 Pumps 3 Pumps 0 MWd/MTU***

2.0 4.5 6.5 3000 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 33 end of cycle.

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

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Number of Charging Pumps Running**

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

5.129 5.129 6.5 3000 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 Mode 6 68°F Tave < 200°F (ARO) 0-1 Pump 2 Pumps 3 Pumps 0 MWd/MTU***

5.129 5.5 8.0 3000 MWd/MTU 5.129 5.5 8.0 6000 MWd/MTU 5.129 5.5 8.0 11000 MWd/MTU 5.129 5.129 8.0 16000 MWd/MTU 5.129 5.129 7.5 25000 MWd/MTU 5.129 5.129 5.129

    • 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 33 end of cycle.

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

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  • Safe Table 2: T(z) Factors associated with Figure 5 (ROS1)

(Top 10% and Bottom 8% excluded)*

Height BU [MWd/MTU]

[ft]

150 1500 2000 2500 3000 4500 5500 6000 7000 8000

[BOTTOM]

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

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

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

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

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

1.00 1.1700 1.1289 1.1180 1.1178 1.1134 1.1020 1.1064 1.0994 1.0989 1.1003 7

1.20 1.2015 1.1675 1.1587 1.1605 1.1579 1.1505 1.1572 1.1511 1.1522 1.1550 8

1.40 1.2217 1.1940 1.1871 1.1905 1.1892 1.1846 1.1925 1.1869 1.1885 1.1916 9

1.60 1.2418 1.2198 1.2145 1.2193 1.2190 1.2166 1.2252 1.2200 1.2217 1.2247 10 1.80 1.2417 1.2249 1.2213 1.2272 1.2279 1.2274 1.2365 1.2318 1.2336 1.2364 11 2.00 1.2005 1.1889 1.1875 1.1937 1.1953 1.1969 1.2064 1.2024 1.2045 1.2074 12 2.20 1.1556 1.1488 1.1520 1.1557 1.1581 1.1614 1.1709 1.1676 1.1698 1.1725 13 2.40 1.1781 1.1737 1.1819 1.1825 1.1852 1.1889 1.1980 1.1948 1.1963 1.1978 14 2.60 1.2183 1.2206 1.2290 1.2260 1.2290 1.2326 1.2409 1.2376 1.2381 1.2417 15 2.80 1.2284 1.2391 1.2439 1.2380 1.2404 1.2443 1.2521 1.2492 1.2494 1.2591 16 3.00 1.2155 1.2313 1.2334 1.2262 1.2286 1.2335 1.2410 1.2386 1.2388 1.2528 17 3.20 1.2058 1.2230 1.2257 1.2194 1.2233 1.2289 1.2359 1.2334 1.2329 1.2455 18 3.40 1.2053 1.2232 1.2264 1.2241 1.2269 1.2309 1.2373 1.2347 1.2335 1.2454 19 3.60 1.2113 1.2298 1.2334 1.2350 1.2374 1.2404 1.2459 1.2424 1.2409 1.2506 20 3.80 1.2205 1.2387 1.2428 1.2485 1.2511 1.2539 1.2587 1.2542 1.2524 1.2582 21 4.00 1.2098 1.2286 1.2335 1.2420 1.2445 1.2475 1.2521 1.2475 1.2456 1.2463 22 4.20 1.1647 1.1866 1.1923 1.2004 1.2030 1.2067 1.2112 1.2068 1.2053 1.2020 23 4.40 1.1238 1.1466 1.1527 1.1607 1.1634 1.1677 1.1722 1.1681 1.1669 1.1648 24 4.60 1.1525 1.1750 1.1816 1.1894 1.1920 1.1959 1.1997 1.1968 1.1951 1.1926 25 4.80 1.1981 1.2197 1.2267 1.2346 1.2368 1.2398 1.2429 1.2417 1.2392 1.2357 26 5.00 1.2141 1.2347 1.2410 1.2477 1.2503 1.2545 1.2561 1.2558 1.2533 1.2497 27 5.20 1.2065 1.2272 1.2321 1.2371 1.2408 1.2463 1.2462 1.2464 1.2435 1.2399 28 5.40 1.2005 1.2223 1.2270 1.2312 1.2357 1.2398 1.2390 1.2393 1.2348 1.2315 29 5.60 1.2048 1.2269 1.2316 1.2354 1.2399 1.2434 1.2422 1.2412 1.2364 1.2332 30 5.80 1.2173 1.2393 1.2441 1.2482 1.2517 1.2551 1.2536 1.2519 1.2470 1.2429 31 6.00 1.2337 1.2550 1.2598 1.2657 1.2679 1.2704 1.2685 1.2670 1.2622 1.2554 32 6.20 1.2290 1.2515 1.2554 1.2624 1.2640 1.2652 1.2631 1.2620 1.2575 1.2499 33 6.40 1.1894 1.2158 1.2184 1.2239 1.2257 1.2253 1.2236 1.2232 1.2198 1.2155 34 6.61 1.1576 1.1858 1.1886 1.1931 1.1951 1.1892 1.1880 1.1882 1.1902 1.1869 35 6.81 1.1916 1.2217 1.2245 1.2283 1.2302 1.2239 1.2222 1.2226 1.2225 1.2193 36 7.01 1.2426 1.2746 1.2773 1.2805 1.2822 1.2730 1.2707 1.2713 1.2708 1.2674 37 7.21 1.2611 1.2943 1.2971 1.2997 1.3013 1.2896 1.2872 1.2881 1.2883 1.2853 38 7.41 1.2537 1.2876 1.2906 1.2925 1.2942 1.2820 1.2798 1.2813 1.2812 1.2791 39 7.61 1.2461 1.2804 1.2836 1.2849 1.2866 1.2763 1.2743 1.2763 1.2732 1.2722 40 7.81 1.2479 1.2808 1.2840 1.2847 1.2864 1.2785 1.2767 1.2792 1.2728 1.2722 41 8.01 1.2598 1.2875 1.2908 1.2907 1.2923 1.2871 1.2851 1.2880 1.2783 1.2794 42 8.21 1.2745 1.2946 1.2979 1.2971 1.2986 1.2966 1.2953 1.2988 1.2883 1.2905 43 8.41 1.2647 1.2777 1.2812 1.2797 1.2813 1.2826 1.2837 1.2879 1.2788 1.2815 44 8.61 1.2184 1.2261 1.2300 1.2281 1.2299 1.2341 1.2370 1.2418 1.2340 1.2378 45 8.81 1.1772 1.1833 1.1873 1.1848 1.1868 1.1938 1.1948 1.2002 1.1941 1.1988 46 9.01 1.2084 1.2128 1.2165 1.2132 1.2149 1.2226 1.2225 1.2285 1.2246 1.2300 47 9.21 1.2567 1.2588 1.2621 1.2579 1.2594 1.2667 1.2660 1.2725 1.2660 1.2719 48 9.41 1.2703 1.2698 1.2727 1.2680 1.2692 1.2765 1.2755 1.2825 1.2765 1.2831 49 9.61 1.2579 1.2540 1.2565 1.2511 1.2522 1.2598 1.2588 1.2663 1.2618 1.2693 50 9.81 1.2459 1.2397 1.2398 1.2320 1.2331 1.2417 1.2406 1.2485 1.2434 1.2517 51 10.01 1.2383 1.2317 1.2275 1.2169 1.2160 1.2254 1.2240 1.2320 1.2315 1.2403 52 10.21 1.2377 1.2326 1.2285 1.2156 1.2106 1.2138 1.2111 1.2190 1.2192 1.2279 53 10.41 1.2295 1.2309 1.2239 1.2115 1.2078 1.2019 1.1953 1.1991 1.2013 1.2101 54 10.61 1.1902 1.1851 1.1826 1.1752 1.1727 1.1650 1.1536 1.1558 1.1571 1.1660 55 10.81 1.1106 1.0834 1.0887 1.0806 1.0777 1.0839 1.0707 1.0745 1.0725 1.0810 56 11.01 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 57 11.21 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 58 11.41 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 59 11.61 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 60 11.81 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

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

  • Linear extrapolation based on a line between 20,500 MWD/MTU and 22,000 MWD/MTU is adequate for addressing burnups beyond 22,000 MWD/MTU.

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  • Safe Table 2: T(z) Factors associated with Figure 5 (ROS1) (Continued)

(Top 10% and Bottom 8% excluded)*

Height BU [MWd/MTU]

[ft]

9000 10000 11000 12000 12500 14500 17000 18500 20500 22000

[BOTTOM]

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

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

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

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

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

1.00 1.1105 1.1191 1.1350 1.1415 1.1478 1.1871 1.2126 1.2421 1.2573 1.2634 7

1.20 1.1668 1.1768 1.1941 1.2013 1.2075 1.2450 1.2650 1.2913 1.3019 1.3046 8

1.40 1.2037 1.2139 1.2310 1.2373 1.2426 1.2747 1.2872 1.3094 1.3149 1.3142 9

1.60 1.2367 1.2464 1.2626 1.2674 1.2715 1.2974 1.3028 1.3209 1.3218 1.3181 10 1.80 1.2482 1.2574 1.2725 1.2759 1.2788 1.2992 1.2993 1.3142 1.3119 1.3062 11 2.00 1.2188 1.2275 1.2412 1.2437 1.2456 1.2619 1.2595 1.2719 1.2684 1.2623 12 2.20 1.1834 1.1914 1.2034 1.2049 1.2058 1.2180 1.2137 1.2241 1.2199 1.2139 13 2.40 1.2080 1.2148 1.2248 1.2239 1.2230 1.2290 1.2204 1.2284 1.2221 1.2149 14 2.60 1.2496 1.2532 1.2606 1.2569 1.2542 1.2537 1.2421 1.2465 1.2381 1.2306 15 2.80 1.2621 1.2616 1.2678 1.2623 1.2582 1.2528 1.2384 1.2414 1.2320 1.2242 16 3.00 1.2515 1.2487 1.2544 1.2476 1.2427 1.2336 1.2173 1.2195 1.2114 1.2037 17 3.20 1.2439 1.2410 1.2448 1.2366 1.2309 1.2184 1.2036 1.2020 1.1971 1.1912 18 3.40 1.2437 1.2404 1.2417 1.2314 1.2250 1.2093 1.1963 1.1907 1.1887 1.1842 19 3.60 1.2492 1.2453 1.2439 1.2331 1.2264 1.2091 1.1959 1.1878 1.1870 1.1875 20 3.80 1.2572 1.2540 1.2512 1.2387 1.2317 1.2127 1.1989 1.1863 1.1852 1.1943 21 4.00 1.2476 1.2456 1.2430 1.2292 1.2221 1.2016 1.1889 1.1805 1.1782 1.1872 22 4.20 1.2076 1.2053 1.2032 1.1895 1.1829 1.1634 1.1531 1.1469 1.1463 1.1567 23 4.40 1.1693 1.1668 1.1653 1.1515 1.1455 1.1270 1.1191 1.1149 1.1160 1.1274 24 4.60 1.1944 1.1909 1.1887 1.1747 1.1681 1.1450 1.1367 1.1331 1.1343 1.1456 25 4.80 1.2349 1.2305 1.2269 1.2126 1.2056 1.1777 1.1665 1.1632 1.1643 1.1751 26 5.00 1.2461 1.2421 1.2373 1.2235 1.2172 1.1867 1.1739 1.1711 1.1726 1.1830 27 5.20 1.2355 1.2321 1.2266 1.2132 1.2071 1.1768 1.1640 1.1605 1.1630 1.1734 28 5.40 1.2277 1.2242 1.2186 1.2051 1.1980 1.1690 1.1552 1.1499 1.1530 1.1628 29 5.60 1.2277 1.2243 1.2188 1.2066 1.1999 1.1689 1.1544 1.1498 1.1513 1.1584 30 5.80 1.2367 1.2334 1.2271 1.2158 1.2079 1.1774 1.1623 1.1598 1.1609 1.1639 31 6.00 1.2505 1.2467 1.2394 1.2284 1.2197 1.1918 1.1757 1.1745 1.1754 1.1776 32 6.20 1.2446 1.2413 1.2337 1.2230 1.2166 1.1911 1.1739 1.1736 1.1756 1.1797 33 6.40 1.2075 1.2061 1.1986 1.1887 1.1860 1.1629 1.1474 1.1478 1.1546 1.1587 34 6.61 1.1782 1.1777 1.1709 1.1617 1.1604 1.1396 1.1305 1.1263 1.1379 1.1414 35 6.81 1.2087 1.2084 1.2011 1.1906 1.1899 1.1714 1.1622 1.1530 1.1672 1.1691 36 7.01 1.2547 1.2543 1.2457 1.2362 1.2361 1.2188 1.2065 1.1938 1.2084 1.2083 37 7.21 1.2710 1.2710 1.2649 1.2575 1.2576 1.2408 1.2266 1.2127 1.2264 1.2248 38 7.41 1.2661 1.2670 1.2642 1.2584 1.2582 1.2423 1.2272 1.2134 1.2257 1.2228 39 7.61 1.2639 1.2655 1.2624 1.2582 1.2575 1.2426 1.2270 1.2132 1.2239 1.2199 40 7.81 1.2687 1.2702 1.2672 1.2646 1.2632 1.2493 1.2325 1.2187 1.2272 1.2219 41 8.01 1.2813 1.2818 1.2788 1.2779 1.2757 1.2625 1.2443 1.2302 1.2360 1.2283 42 8.21 1.2942 1.2933 1.2902 1.2913 1.2880 1.2760 1.2565 1.2424 1.2449 1.2349 43 8.41 1.2851 1.2830 1.2803 1.2837 1.2795 1.2697 1.2497 1.2363 1.2362 1.2251 44 8.61 1.2424 1.2391 1.2370 1.2436 1.2386 1.2328 1.2150 1.2040 1.2032 1.1936 45 8.81 1.2041 1.1996 1.1982 1.2078 1.2020 1.2006 1.1897 1.1831 1.1810 1.1740 46 9.01 1.2303 1.2279 1.2287 1.2342 1.2316 1.2326 1.2205 1.2151 1.2094 1.2027 47 9.21 1.2702 1.2713 1.2711 1.2678 1.2750 1.2763 1.2634 1.2561 1.2494 1.2399 48 9.41 1.2825 1.2840 1.2834 1.2788 1.2881 1.2896 1.2779 1.2720 1.2631 1.2542 49 9.61 1.2703 1.2709 1.2713 1.2727 1.2769 1.2799 1.2719 1.2675 1.2604 1.2508 50 9.81 1.2538 1.2551 1.2557 1.2624 1.2638 1.2716 1.2685 1.2614 1.2601 1.2494 51 10.01 1.2432 1.2447 1.2454 1.2549 1.2552 1.2717 1.2743 1.2635 1.2671 1.2612 52 10.21 1.2343 1.2380 1.2392 1.2490 1.2488 1.2731 1.2823 1.2697 1.2768 1.2765 53 10.41 1.2203 1.2258 1.2274 1.2344 1.2369 1.2669 1.2830 1.2695 1.2798 1.2864 54 10.61 1.1763 1.1830 1.1852 1.1911 1.1957 1.2299 1.2540 1.2419 1.2566 1.2702 55 10.81 1.0882 1.0959 1.0988 1.1075 1.1101 1.1475 1.1806 1.1744 1.1946 1.2134 56 11.01 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 57 11.21 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 58 11.41 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 59 11.61 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 60 11.81 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

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

  • Linear extrapolation based on a line between 20,500 MWD/MTU and 22,000 MWD/MTU is adequate for addressing burnups beyond 22,000 MWD/MTU.

PRAIRIE ISLAND UNIT 2 CYCLE 34 CORE OPERATING LIMITS REPORT (COLR)

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  • Safe Table 3: RJ Margin Decrease Factors associated with Figure 5 (ROS1) and Table 2 Cycle Burnup (MWD/MTU)

RJ Penalty Multiplier Cycle Burnup (MWD/MTU)

RJ Penalty Multiplier Cycle Burnup (MWD/MTU)

RJ Penalty Multiplier 150 1.042 7179 1.006 14209 1.001 321 1.038 7351 1.006 14380 1.000 493 1.034 7522 1.004 14552 1.000 664 1.030 7694 1.002 14723 1.000 836 1.026 7865 1.001 14895 1.000 1007 1.022 8037 1.001 15066 1.000 1179 1.019 8208 1.000 15238 1.000 1350 1.016 8380 1.000 15409 1.000 1522 1.014 8551 1.000 15581 1.000 1693 1.011 8723 1.000 15752 1.000 1865 1.010 8894 1.000 15923 1.000 2036 1.010 9065 1.000 16095 1.001 2207 1.009 9237 1.002 16266 1.001 2379 1.007 9408 1.005 16438 1.005 2550 1.006 9580 1.008 16609 1.005 2722 1.005 9751 1.010 16781 1.006 2893 1.005 9923 1.012 16952 1.006 3065 1.005 10094 1.012 17124 1.005 3236 1.006 10266 1.010 17295 1.005 3408 1.006 10437 1.009 17467 1.005 3579 1.006 10609 1.007 17638 1.004 3750 1.009 10780 1.007 17809 1.001 3922 1.011 10951 1.007 17981 1.000 4093 1.013 11123 1.007 18152 1.000 4265 1.013 11294 1.008 18324 1.000 4436 1.012 11466 1.009 18495 1.000 4608 1.012 11637 1.011 18667 1.000 4779 1.011 11809 1.011 18838 1.000 4951 1.009 11980 1.011 19010 1.000 5122 1.008 12152 1.014 19181 1.000 5294 1.007 12323 1.013 19353 1.000 5465 1.006 12494 1.013 19524 1.000 5636 1.006 12666 1.012 19695 1.000 5808 1.004 12837 1.012 19867 1.000 5979 1.005 13009 1.011 20038 1.000 6151 1.008 13180 1.010 20210 1.000 6322 1.008 13352 1.009 20381 1.000 6494 1.008 13523 1.004 20553 1.000 6665 1.008 13695 1.003 6837 1.008 13866 1.002 7008 1.007 14038 1.002 Values may be interpolated to the surveillance cycle burnup. The Rj factor value for the last burnup step shall be used for all burnups greater than the last burnup step.

PRAIRIE ISLAND UNIT 2 CYCLE 34 CORE OPERATING LIMITS REPORT (COLR)

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  • Safe Table 4: T(z) Factors associated with Figure 6, Figure 7, and Figure 8 (ROS2)

(Top 10% and Bottom 8% excluded)*

Height BU [MWd/MTU]

[ft]

150 1500 2000 2500 3000 4500 5500 6000 7000 8000

[BOTTOM]

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

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

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

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

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

1.00 1.1475 1.1093 1.0980 1.0787 1.0745 1.0633 1.0675 1.0605 1.0762 1.0771 7

1.20 1.1787 1.1476 1.1384 1.1206 1.1180 1.1108 1.1171 1.1110 1.1288 1.1311 8

1.40 1.1988 1.1742 1.1668 1.1503 1.1490 1.1444 1.1519 1.1463 1.1649 1.1675 9

1.60 1.2189 1.2001 1.1944 1.1790 1.1787 1.1762 1.1844 1.1791 1.1981 1.2006 10 1.80 1.2192 1.2059 1.2017 1.1876 1.1883 1.1877 1.1964 1.1916 1.2106 1.2129 11 2.00 1.1791 1.1713 1.1688 1.1564 1.1579 1.1593 1.1684 1.1643 1.1830 1.1853 12 2.20 1.1353 1.1327 1.1316 1.1207 1.1230 1.1262 1.1352 1.1319 1.1498 1.1520 13 2.40 1.1577 1.1586 1.1584 1.1479 1.1507 1.1539 1.1629 1.1599 1.1769 1.1783 14 2.60 1.1979 1.2018 1.2022 1.1933 1.1945 1.2028 1.2059 1.2080 1.2193 1.2195 15 2.80 1.2070 1.2130 1.2145 1.2139 1.2078 1.2233 1.2190 1.2276 1.2312 1.2309 16 3.00 1.1930 1.2011 1.2045 1.2117 1.1989 1.2181 1.2107 1.2221 1.2214 1.2211 17 3.20 1.1836 1.1955 1.2010 1.2066 1.1953 1.2144 1.2075 1.2181 1.2174 1.2166 18 3.40 1.1825 1.1977 1.2048 1.2096 1.1996 1.2179 1.2108 1.2210 1.2208 1.2193 19 3.60 1.1889 1.2060 1.2147 1.2186 1.2125 1.2272 1.2200 1.2295 1.2299 1.2292 20 3.80 1.1999 1.2171 1.2275 1.2304 1.2273 1.2391 1.2330 1.2404 1.2413 1.2426 21 4.00 1.1915 1.2088 1.2205 1.2219 1.2226 1.2310 1.2284 1.2316 1.2337 1.2371 22 4.20 1.1499 1.1680 1.1788 1.1792 1.1835 1.1891 1.1914 1.1904 1.1931 1.1991 23 4.40 1.1143 1.1323 1.1390 1.1424 1.1469 1.1526 1.1569 1.1563 1.1553 1.1629 24 4.60 1.1461 1.1642 1.1704 1.1741 1.1785 1.1842 1.1879 1.1875 1.1855 1.1904 25 4.80 1.1940 1.2127 1.2191 1.2223 1.2268 1.2319 1.2346 1.2341 1.2318 1.2335 26 5.00 1.2124 1.2320 1.2372 1.2413 1.2457 1.2510 1.2519 1.2515 1.2483 1.2470 27 5.20 1.2064 1.2270 1.2314 1.2361 1.2407 1.2459 1.2452 1.2453 1.2410 1.2378 28 5.40 1.2005 1.2223 1.2270 1.2312 1.2357 1.2398 1.2390 1.2393 1.2344 1.2310 29 5.60 1.2048 1.2269 1.2316 1.2354 1.2399 1.2434 1.2422 1.2412 1.2364 1.2331 30 5.80 1.2173 1.2393 1.2441 1.2475 1.2519 1.2551 1.2536 1.2518 1.2470 1.2429 31 6.00 1.2337 1.2550 1.2598 1.2628 1.2670 1.2704 1.2685 1.2670 1.2622 1.2554 32 6.20 1.2290 1.2515 1.2554 1.2591 1.2623 1.2652 1.2631 1.2620 1.2575 1.2499 33 6.40 1.1894 1.2158 1.2183 1.2232 1.2251 1.2253 1.2236 1.2232 1.2198 1.2154 34 6.61 1.1575 1.1857 1.1885 1.1929 1.1949 1.1890 1.1879 1.1881 1.1901 1.1868 35 6.81 1.1915 1.2214 1.2243 1.2281 1.2300 1.2237 1.2221 1.2225 1.2224 1.2191 36 7.01 1.2424 1.2743 1.2771 1.2803 1.2819 1.2727 1.2704 1.2710 1.2706 1.2672 37 7.21 1.2607 1.2936 1.2965 1.2990 1.3006 1.2896 1.2871 1.2880 1.2880 1.2850 38 7.41 1.2533 1.2858 1.2888 1.2907 1.2924 1.2811 1.2788 1.2803 1.2809 1.2787 39 7.61 1.2456 1.2764 1.2796 1.2810 1.2827 1.2717 1.2697 1.2717 1.2728 1.2719 40 7.81 1.2455 1.2752 1.2785 1.2792 1.2809 1.2702 1.2683 1.2708 1.2724 1.2718 41 8.01 1.2520 1.2798 1.2832 1.2832 1.2848 1.2744 1.2725 1.2755 1.2775 1.2776 42 8.21 1.2590 1.2848 1.2882 1.2874 1.2889 1.2787 1.2768 1.2801 1.2824 1.2836 43 8.41 1.2432 1.2655 1.2690 1.2676 1.2692 1.2611 1.2595 1.2636 1.2665 1.2675 44 8.61 1.1935 1.2096 1.2133 1.2114 1.2131 1.2112 1.2105 1.2157 1.2197 1.2173 45 8.81 1.1509 1.1588 1.1626 1.1602 1.1621 1.1673 1.1672 1.1727 1.1776 1.1718 46 9.01 1.1792 1.1830 1.1868 1.1861 1.1872 1.1925 1.1931 1.1981 1.2034 1.1986 47 9.21 1.2250 1.2265 1.2298 1.2290 1.2294 1.2343 1.2347 1.2398 1.2451 1.2378 48 9.41 1.2373 1.2363 1.2392 1.2388 1.2386 1.2429 1.2436 1.2486 1.2540 1.2473 49 9.61 1.2243 1.2200 1.2224 1.2201 1.2197 1.2256 1.2260 1.2318 1.2377 1.2326 50 9.81 1.2118 1.2052 1.2055 1.1994 1.1992 1.2072 1.2060 1.2138 1.2198 1.2144 51 10.01 1.2038 1.1967 1.1927 1.1892 1.1882 1.1915 1.1902 1.1971 1.2031 1.2023 52 10.21 1.2025 1.1971 1.1933 1.1839 1.1822 1.1839 1.1820 1.1833 1.1900 1.1892 53 10.41 1.1942 1.1942 1.1878 1.1766 1.1746 1.1713 1.1693 1.1673 1.1705 1.1713 54 10.61 1.1550 1.1512 1.1486 1.1386 1.1363 1.1315 1.1260 1.1255 1.1223 1.1250 55 10.81 1.0733 1.0498 1.0554 1.0499 1.0468 1.0512 1.0398 1.0423 1.0414 1.0392 56 11.01 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 57 11.21 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 58 11.41 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 59 11.61 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 60 11.81 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

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

  • Linear extrapolation based on a line between 20,500 MWD/MTU and 22,000 MWD/MTU is adequate for addressing burnups beyond 22,000 MWD/MTU.

PRAIRIE ISLAND UNIT 2 CYCLE 34 CORE OPERATING LIMITS REPORT (COLR)

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  • Safe Table 4: T(z) Factors associated with Figure 6, Figure 7, and Figure 8 (ROS2) (Continued)

(Top 10% and Bottom 8% excluded)*

Height BU [MWd/MTU]

[ft]

9000 10000 11000 12000 12500 14500 17000 18500 20500 22000

[BOTTOM]

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

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

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

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

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

1.00 1.0783 1.0784 1.0852 1.0984 1.1041 1.1398 1.1892 1.1884 1.2008 1.2046 7

1.20 1.1335 1.1347 1.1425 1.1566 1.1622 1.1961 1.2410 1.2364 1.2442 1.2448 8

1.40 1.1701 1.1712 1.1788 1.1921 1.1967 1.2256 1.2632 1.2547 1.2577 1.2550 9

1.60 1.2028 1.2035 1.2104 1.2221 1.2255 1.2484 1.2789 1.2669 1.2656 1.2600 10 1.80 1.2149 1.2152 1.2213 1.2314 1.2336 1.2514 1.2760 1.2618 1.2575 1.2502 11 2.00 1.1873 1.1875 1.1930 1.2016 1.2030 1.2169 1.2373 1.2228 1.2174 1.2098 12 2.20 1.1539 1.1538 1.1585 1.1654 1.1658 1.1759 1.1928 1.1784 1.1725 1.1652 13 2.40 1.1791 1.1780 1.1810 1.1853 1.1840 1.1881 1.2000 1.1842 1.1764 1.1681 14 2.60 1.2191 1.2165 1.2177 1.2187 1.2155 1.2135 1.2206 1.2034 1.1935 1.1841 15 2.80 1.2301 1.2270 1.2269 1.2262 1.2218 1.2149 1.2183 1.2010 1.1906 1.1812 16 3.00 1.2201 1.2171 1.2164 1.2147 1.2096 1.1988 1.1997 1.1837 1.1741 1.1658 17 3.20 1.2149 1.2116 1.2100 1.2059 1.2000 1.1856 1.1855 1.1708 1.1626 1.1560 18 3.40 1.2172 1.2141 1.2114 1.2037 1.1973 1.1788 1.1775 1.1651 1.1597 1.1548 19 3.60 1.2266 1.2236 1.2200 1.2083 1.2015 1.1823 1.1767 1.1681 1.1629 1.1593 20 3.80 1.2395 1.2364 1.2321 1.2175 1.2104 1.1892 1.1788 1.1738 1.1695 1.1670 21 4.00 1.2338 1.2310 1.2264 1.2105 1.2033 1.1806 1.1715 1.1658 1.1628 1.1618 22 4.20 1.1962 1.1943 1.1902 1.1742 1.1675 1.1458 1.1397 1.1336 1.1327 1.1336 23 4.40 1.1603 1.1592 1.1555 1.1413 1.1353 1.1146 1.1093 1.1028 1.1038 1.1066 24 4.60 1.1874 1.1859 1.1814 1.1673 1.1608 1.1374 1.1298 1.1213 1.1228 1.1261 25 4.80 1.2294 1.2277 1.2221 1.2075 1.2002 1.1732 1.1627 1.1532 1.1531 1.1568 26 5.00 1.2438 1.2412 1.2352 1.2215 1.2139 1.1850 1.1728 1.1639 1.1626 1.1668 27 5.20 1.2359 1.2322 1.2263 1.2133 1.2059 1.1770 1.1641 1.1562 1.1553 1.1606 28 5.40 1.2277 1.2242 1.2186 1.2051 1.1980 1.1690 1.1552 1.1487 1.1485 1.1542 29 5.60 1.2277 1.2243 1.2188 1.2066 1.1999 1.1689 1.1544 1.1496 1.1505 1.1537 30 5.80 1.2366 1.2334 1.2263 1.2158 1.2076 1.1774 1.1623 1.1599 1.1611 1.1615 31 6.00 1.2498 1.2468 1.2387 1.2284 1.2189 1.1918 1.1756 1.1745 1.1756 1.1731 32 6.20 1.2435 1.2410 1.2338 1.2230 1.2154 1.1910 1.1741 1.1736 1.1749 1.1713 33 6.40 1.2059 1.2045 1.1985 1.1886 1.1843 1.1628 1.1469 1.1478 1.1505 1.1479 34 6.61 1.1761 1.1757 1.1709 1.1616 1.1582 1.1395 1.1241 1.1263 1.1328 1.1281 35 6.81 1.2061 1.2058 1.2011 1.1906 1.1873 1.1678 1.1499 1.1529 1.1610 1.1531 36 7.01 1.2515 1.2510 1.2461 1.2340 1.2306 1.2093 1.1896 1.1938 1.2010 1.1895 37 7.21 1.2675 1.2674 1.2629 1.2501 1.2470 1.2257 1.2067 1.2117 1.2179 1.2044 38 7.41 1.2601 1.2608 1.2572 1.2448 1.2425 1.2233 1.2052 1.2105 1.2162 1.2020 39 7.61 1.2522 1.2531 1.2508 1.2406 1.2392 1.2216 1.2032 1.2085 1.2138 1.1987 40 7.81 1.2524 1.2527 1.2508 1.2450 1.2444 1.2260 1.2071 1.2121 1.2166 1.2004 41 8.01 1.2609 1.2572 1.2570 1.2551 1.2553 1.2369 1.2161 1.2216 1.2240 1.2067 42 8.21 1.2713 1.2642 1.2653 1.2659 1.2670 1.2480 1.2262 1.2315 1.2320 1.2136 43 8.41 1.2599 1.2517 1.2535 1.2563 1.2584 1.2400 1.2182 1.2232 1.2229 1.2043 44 8.61 1.2154 1.2061 1.2091 1.2148 1.2184 1.2021 1.1828 1.1885 1.1874 1.1721 45 8.81 1.1755 1.1651 1.1691 1.1778 1.1828 1.1684 1.1555 1.1633 1.1562 1.1497 46 9.01 1.2041 1.1901 1.1943 1.2071 1.2074 1.1976 1.1834 1.1900 1.1780 1.1749 47 9.21 1.2438 1.2324 1.2366 1.2469 1.2393 1.2406 1.2237 1.2280 1.2138 1.2087 48 9.41 1.2541 1.2456 1.2495 1.2581 1.2471 1.2567 1.2418 1.2395 1.2283 1.2188 49 9.61 1.2403 1.2347 1.2364 1.2462 1.2383 1.2500 1.2427 1.2319 1.2229 1.2175 50 9.81 1.2228 1.2219 1.2201 1.2310 1.2280 1.2400 1.2418 1.2278 1.2176 1.2203 51 10.01 1.2114 1.2119 1.2091 1.2215 1.2201 1.2341 1.2438 1.2336 1.2231 1.2279 52 10.21 1.1989 1.2040 1.1996 1.2104 1.2137 1.2287 1.2477 1.2421 1.2316 1.2385 53 10.41 1.1811 1.1883 1.1851 1.1932 1.1990 1.2189 1.2438 1.2443 1.2341 1.2434 54 10.61 1.1349 1.1446 1.1420 1.1480 1.1567 1.1823 1.2126 1.2190 1.2118 1.2241 55 10.81 1.0471 1.0620 1.0570 1.0622 1.0756 1.1025 1.1413 1.1525 1.1517 1.1687 56 11.01 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 57 11.21 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 58 11.41 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 59 11.61 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 60 11.81 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

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

  • Linear extrapolation based on a line between 20,500 MWD/MTU and 22,000 MWD/MTU is adequate for addressing burnups beyond 22,000 MWD/MTU.

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  • Safe Table 5: RJ Margin Decrease Factors associated with Figure 6, Figure 7, and Figure 8 (ROS2) and Table 4 Cycle Burnup (MWD/MTU)

RJ Penalty Multiplier Cycle Burnup (MWD/MTU)

RJ Penalty Multiplier Cycle Burnup (MWD/MTU)

RJ Penalty Multiplier 150 1.044 7179 1.000 14209 1.005 321 1.039 7351 1.001 14380 1.012 493 1.034 7522 1.000 14552 1.012 664 1.030 7694 1.000 14723 1.012 836 1.026 7865 1.000 14895 1.011 1007 1.022 8037 1.000 15066 1.010 1179 1.019 8208 1.000 15238 1.010 1350 1.016 8380 1.000 15409 1.009 1522 1.014 8551 1.000 15581 1.009 1693 1.011 8723 1.000 15752 1.002 1865 1.010 8894 1.000 15923 1.001 2036 1.010 9065 1.000 16095 1.000 2207 1.009 9237 1.000 16266 1.000 2379 1.007 9408 1.001 16438 1.000 2550 1.006 9580 1.000 16609 1.000 2722 1.005 9751 1.001 16781 1.000 2893 1.006 9923 1.002 16952 1.000 3065 1.006 10094 1.003 17124 1.000 3236 1.006 10266 1.005 17295 1.000 3408 1.006 10437 1.004 17467 1.000 3579 1.006 10609 1.004 17638 1.000 3750 1.009 10780 1.004 17809 1.000 3922 1.009 10951 1.004 17981 1.000 4093 1.009 11123 1.003 18152 1.000 4265 1.009 11294 1.004 18324 1.000 4436 1.009 11466 1.004 18495 1.000 4608 1.009 11637 1.004 18667 1.000 4779 1.008 11809 1.005 18838 1.000 4951 1.008 11980 1.006 19010 1.000 5122 1.008 12152 1.009 19181 1.000 5294 1.007 12323 1.010 19353 1.001 5465 1.006 12494 1.010 19524 1.000 5636 1.006 12666 1.010 19695 1.000 5808 1.004 12837 1.010 19867 1.000 5979 1.003 13009 1.010 20038 1.000 6151 1.003 13180 1.009 20210 1.000 6322 1.002 13352 1.009 20381 1.000 6494 1.002 13523 1.007 20553 1.000 6665 1.001 13695 1.007 6837 1.000 13866 1.006 7008 1.000 14038 1.006 Values may be interpolated to the surveillance cycle burnup. The Rj factor value for the last burnup step shall be used for all burnups greater than the last burnup step.

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  • Safe Table 6: Required THERMAL POWER Limits and AFD Reductions RAOC Operating Space Required FQW(z) Margin Improvement (%)

Required THERMAL POWER Limit

(%RTP)

Reference AFD Figure ROS1 (Figure 5)

> 0

< 50 N/A ROS2 (Figure 6) 1.5 95 Use Figure 7

> 1.5 and 7.0 90 Use Figure 8

> 7.0

< 50 N/A

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  • Safe Figure 1: Reactor Core Safety Limits 540 560 580 600 620 640 660 680 0

0.2 0.4 0.6 0.8 1

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

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  • Safe Figure 2: Rod Insertion Limit, 128 Step Tip-to-Tip Bank Positions Given By:

Bank D = (150 / 63) * (P - 100) + 185 Bank C = (150 / 63) * (P - 100) + 185 + 128 Bank B = (150 / 63) * (P - 100) + 185 + 128 + 128 Note: The top of the active fuel height corresponds to 224 steps.

Bank D Bank C Bank B 0

50 100 150 200 0

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

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Bank Positions Given By:

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

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Bank Positions Given By:

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

Operation Forbidden in this Region 0

50 150 200 224 0

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

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  • Safe Figure 5: Flux Difference Operating Envelope associated with ROS1 (Table 2 and Table 3)

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  • Safe Figure 6: Flux Difference Operating Envelope associated with ROS2 (Table 4 and Table 5)

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  • Safe Figure 7: Flux Difference Operating Envelope associated with ROS2 95% THERMAL POWER Required Action (Table 4, Table 5, and Table 6)

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  • Safe Figure 8: Flux Difference Operating Envelope associated with ROS2 90% THERMAL POWER Required Action (Table 4, Table 5, and Table 6)
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