L-PI-10-091, Core Operating Limits Report, Cycle 26, Revision 1

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Core Operating Limits Report, Cycle 26, Revision 1
ML102810081
Person / Time
Site: Prairie Island Xcel Energy icon.png
Issue date: 10/07/2010
From: Schimmel M
Northern States Power Co, Xcel Energy
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-PI-10-091
Download: ML102810081 (30)
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@ Xcel Energye U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Unit I Docket 50-282 License No. DPR-42 Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant IPINGP) Unit 1, Cvcle 26, Revision 1 Pursuant to the requirements of Technical Specification 5.6.5.d, the COLR for the PlNGP Unit 1, Cycle 26, Revision 1, is attached. The limits specified in the attached COLR have been established using Nuclear Regulatory Commission (NRC) approved methodologies.

The COLR for the Unit I , Cycle 26, Revision I,has been updated to include the second set of W(z) factors. This resulted in changes to the following sections:

Revised Section 3.2.1, Heat Flux Hot Channel Factor (FQ(Z))

Revised Section 3.2.3, Axial Flux Difference (AFD)

Revised the References section, item 28, to update the 50.59 Evaluation 1072 reference to Revision 1 Revised Table 2 title to add "associated with Figure 5" Revised Table 3 title to add "associated with Figure 5 and Table 2" Added Table 4, W(z) Values associated with Figure 6 Added Table 5, F ~ ~ ( Penalty z) Factor associated with Figure 6 and Table 4 Revised Figure 5 title to add "associated with Table 2" Added Figure 6, Flux Difference Operating Envelope associated with Table 4 Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.

Mark A. Schimmel Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure 1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1 121

Document Control Desk Page 2 cc: Administrator, Region Ill, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC State of Minnesota

ENCLOSURE PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT UNIT 1 - CYCLE 26 REVISION 1 Record of Revision (6 pages)

Unit 1 -Cycle 26, Revision 1 (21 pages)

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

1 1.4 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 2111/91 Incorporated revised FQof2.45 as a result of NRC approval of Westinghouse Topical Report WCAP-10924-P-A, Volume 1, Addendum 4, October 1990.

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.

2 211 1/91 Incorporated revised FQof 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. lncorporated additional discussion related to V(z) and K(z).

PRAIRIE ISLAND NUCLEAR GENERATING PLANT

, t Core Operating Limits Report B

t~ .

.--J Record of Revision Revision Approval Unit Cycle No. 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 GWDIMTU. Figures 3 through 6 re-formatted.

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. lncorporated additional discussion related to V(z) and K(z).

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

2/7/96 Updated to Unit 1 Cycle 18. lncorporated revised FAHlimit of 1.77. lncorporated Table 1 and updated Figure 2 with revised bounding V(z) values.

2/27197 Updated to Unit 2 Cycle 18. Revised FAHlimit to 1.77. Updated Table 1 and Figures 2a through 2e with revised bounding V(z) values.

lncorporated new Figures 2f and 29 with additional bounding V(z) values.

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

0 12117/98 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.

0 5113/99 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 6

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record of Revision Revision Approval Unit 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 29. Added discussion of two tier V(z) curve presented in Table 2 and Figure 29.

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.

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

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 10102102 Revised to support License Amendment 158 changes, including revision of all references to TS, revision of FQsymbols, addition of Table 4, ITC limits, DNB limits and refueling boron concentrations.

2/06/02 Updated to Unit 2 Cycle 21 Page 3 of 6

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record of Revision 1 Revision Approval a Unit Cycle No. Date Remarks I

21 1 10/02/02 Revised to support License Amendment 149 changes, including revision of all references to TS, revision of FQsymbols, addition of 'Table 4, ITC limits, DNB limits and refueling boron concentrations. Also revised to include an additional V(z) curve to give greater FQmargin between 13.0 and 16.0 GWdIMTU.

0 11/25/02 Updated to Unit 1 Cycle 22. Updated Tables I 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.

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 I , 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.

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

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

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 6

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record of Revision Revision Approval Unit Cycle No. Date Remarks 1 22 2 7116/04 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 7111/05 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.

0 5/10/06 Updated to Unit 1 Cycle 24.

1 8/7/06 Updated Table 3 to reflect the correct Fqw(z) penalty factors.

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

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

2 9/4/07 Revised to support LA-1791169. 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 2111/08 Updated Table 1 to reflect correct Shutdown Margin Requirements and added Figures 6A through 6H.

Page 5 of 6

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Core Operating Limits Report Record of Revision Revision Approval Unit Cycle No. Date Remarks 2 24 3 2111/08 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 MWdIMTU 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 513110 Updated for Unit 2 Cycle 26 2 26 1 5117110 Updated to include part W(z) factors 1 26 1 912110 Updated for second set of W(z) factors Page 6 of 6

Core Operating Limits Report Unit 1, cycle 26

~evisfon1 I PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE: OPERATING IJMITS REPORT UNIT 1 - CYCLE 26 REVISION 1 Reviewed By: Date:-

I /

Supervisor7PWR Analyses Approved :

Steve Skoyen Director, Site Engineering

.ate: %z -,

Note: This report is not part of the Technical Specifications This report is referenced in the Technical Specifications Page 1 of 21 1

Core Operating Limits Report Unit 1, Cycle 26 Revision 1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT UNIT 1 CYCLE 26 REVISION 1 This report provides the values of the limits for Unit 1 Cycle 26 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:

Reactor Core SLs Shutdown Margin (SDM)

Isothermal Temperature Coefficient (ITC)

Shutdown Bank Insertion Limits Control Bank Insertion Limits Physics Tests Exceptions - MODE 2 Heat Flux Hot Channel Factor (FQ(z))

Nuclear Enthdpy Rise Hot Channel Factor (F;)

Axial Flux Difference (AFD)

Reactor Trip System (RTS) Instrumentation Overtemperature AT and Overpower AT Parameter Values for Table 3.3.1-3 RCS Pressure, Temperature, and Flow - Departure from Nucleate Boiling (DNB) Limits Boron Concentration

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

Reference Technical Specification section 2.1.1.

2. 3.1.1 Shutdown Margin Requirements Minimum Shutdown Margin requirements are shown in Table 1.

Reference Technical Specification section 3.1.1.

Page 2 of 21

Core Operating Limits Report Unit 1 , Cycle 26 Revision 1

3. 3.1.3 Isothermal Temperature Coefficient (ITC)

ITC Upper limit:

a. < 5 p c d ° F for power levels < 70% RTP; and
b. less than a line which slopes linearly from
i. 0 p c d F at a power level = 70% RTP to ii. -1.5 pcrnPF at a power level = 100% RTP ITC Lower limit:
a. -43.15 p c d ° F Reference Technical Specification section 3.1.3.
4. 3.1.5 Shutdown Bank Insertion Limits The shutdown rods shall be fully withdrawn.

Reference Technical Specification section 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 ~ a n A, k 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 section 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 section 3.1.8.

Page 3 of 21

Core Operating Limits Report Unit 1 , Cycle 26 Revision 1

7. 3.2.1 Heat Flux Hot Channel Factor ( F a 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 F ~ Q ( ZPenalty

) Factors associated with Figure 5 and Table 2 are provided in Table 3.

The F ~ Q ( ZPenalty

) 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, F ~ Q ( Zmust) be confirmed to meet Technical Specification requirements by one of the follow methods:

I. 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 F ~ ~ ( meets z ) 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. When a part power surveillance is performed, the W(Z) values should be multiplied by the factor UP, when P > 0.5. When P is 5 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 Fa(Z) limit at part power conditions.

Reference 10 provides the basis for multiple sets of W(Z) curves.

Page 4 of 21

Core Operating Limits Report Unit 1, Cycle 26 Revision 1 Applicability: MODE 1 .

5 Reference Technical Specification section 3.2.1.

I j

1

8. 3.2.2 Nuclear Enthalpv Rise Hot Channel Factor (~~a The Nuclear Enthalpy Rise Hot Channel Factor shall be within the following limits:

FAHI 1.77 x [l + 0.3(1- P)] for all 422V+ type fuel assemblies, and FAHI 1.712 x [1 + 0.3(1- P)] for all OFA type fuel assemblies where: P is the fraction of RATED THERMAL POWER at which the core is operating.

Applicability: MODE 1.

Reference Teefinical Specification section 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 Figures5 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.

Applicability: MODE 1 with RATED THERMAL POWER > 50% RTP.

Reference Technical Specification section 3.2.3.

Page 5 of 21

i Core Operating Limits Report 3 Unit 1, Cycle 26 i

Revision 1 P

> 10. 3.3.1 Reactor Trip System (RTS) Instrumentation 9

rl P

I t

Overtemperature AT and Overpower AT Parameter Values for Table 3.3.1-1; i

B 4 Overtemperature AT Setpoint I

S Overtemperature AT setpoint parameter values:

s Indicated AT at RATED THERMAL POWER, %

Average temperature, O F 560.0 O F Pressurizer Pressure, psig 2235 psig 1.17 0.014 1°F 0.00 100 /psi 30 seconds 4 seconds A function of the indicated difference between top and bottom detectors of the power range nuclear ion chambers. Selected gains are based on measured instrument response during plant startup tests, where q, and qb are the percent power in the top and bottom halves of the core respectively, and q, + qb is total core power in percent of RATED THERMAL POWER, such that (a) For qt - q b within -13, +8 % f(A1) = 0 (b) For each percent that the magnitude of qt - qb exceeds +8%

the AT 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 AT trip setpoint shall be automatically reduced by an equivalent of 3.846 % of RATED THERMAL POWER.

Overpower AT Setpoint Overpower AT setpoint parameter values:

AT0 = Indicated AT at RATED THERMAL POWER, %

T = Average temperature, OF T' = 560.0 "F K4 5 1.11 K5 = 0.0275IoF for increasing T; 0 for decreasing T Kg = 0-0021°Ffor T > T' ; 0 for T 5 T' x3 = 10 seconds Page 6 of 21

Core Operating Limits Report Unit 1, Cycle 26 Revision 1

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

Pressurizer pressure limit = 2190 psia RCS average temperature limit = 564OF RCS total flow rate limit = 178,000 gpm Reference Technical Specification section 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) KeK 1 0.95 b) 2000ppm c) The Shutdown Margin specified in Table 1 D Reference Technical Specification section 3.9.1.

1

Core Operating Limits Report Unit 1, Cycle 26 Revision 1 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.a Deleted.

6.b Deleted.

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-NF77-57, Supplement 1 (A), "Exxon Nuclear Power Distribution Control for Pressurized Water Reactors Phase 11,"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 zIRLoTM 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 Plant F ~ Q ( Z ) Penalty With Increasing

[F'Q(z)/K(z)] Trend," Revision 0, January 2001.

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

Page 8 of 21

Core Operating Limits Report Unit 1, Cycle 26 Revision 1

14. WCAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT 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 TV Code for Thermal Transients in a UOz Fuel Rod," December 1989.

P i 19. WCAP-7907-P-A, "LOFTRAN Code Description," April 1984.

20. WCAP-7979-P-A, "TWINKLE - A Multidimensional Neutron Kinetics Computer Code," January 1975.

1 f?

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

September 1986.

I1 (J k

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

i 3

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

2 5

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.

28.50.59 Evaluation 1072, Revision 1, "Unit 1 Cycle 26 Core Reload."

Page 9 of 21

Core Operating Limits Report Unit 1, Cycle 26 Revision 1 Table 1 Minimum Required Shutdown Margin, %Ap A Mode 4 0-1 pump 2 Pumps I 3 pumps I 0 MU I 12000 N 1 22000 MWd/MTU I 2.0 2.0 2.5 1 Operational Mode Definitions, as per TS Table 1.1- 1.

  • For Mode 1 and Mode 2 with I(kff 2 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 10 of 21

Core Operating Limits Report Unit 1, Cycle 26 Revision 1 Table 1, Continued Minimum Required Shutdown Margin, %Ap 0-1 Pump 2 Pumps 3 Pumps 0 MWd/MTu*** 5.129 5.5 8.5 f-% I 12000 MWdMTU 5.129 5.129 7.0

  • , L 22000 MWdIMTU 5.129 5.129 5.129 Operational Mode Definitions, as per TS Table 1.1- 1.
    • Charging pump(s) in service only pertains to steady state operations. It does not include

- transitory operations. For example, operations such as starting a second charging pump in order to secure the operating pump would fall under the one pump in service column.

      • These values are also applicable for the Unit 1 Cycle 25 end of cycle.

Page 11 of 21

Core Operating Limits Report Unit 1, Cycle 26 Revision 1 Table 2 W(z) Values associated with Figure 5 (Top 10% and Bottom 8% excluded)*

Page 12 of 21

Core Operating Limits Report Unit 1, Cycle 26 Revision 1 Table 2 (cont.) W(z) Values associated with Figure 5 (Top 10% and Bottom 8% excluded)"

  • Linear extrapolation based on a line between 18,000 MWD/MTU and 20,000 MWDIMTU is adequate for addressing burnups beyond 20,000 MWD/MTU.

Table 3 F ~ ~ ( Penalty z) Factor associated with Figure 5 and Table 2 Cycle Burnup (MWDMTU) F ~ ~ ( Penalty z) Factor 14632 1.0200 14779 1.0203 14925 1.0202 15071 1.0200 F ~ ~= ( 1.020 z ) for all bumups except those listed above. Linear interpolation is adequate for intermediate cycle burnups.

Page 13 of 21

Core Operating Limits Report Unit 1 , Cycle 26 Revision 1 Table 4 W(z) Values associated with Figure 6 (Top 10%and Bottom 8% excluded)"

Page 14 of 21

Core Operating Limits Report Unit 1, Cycle 26 Revision 1 Table 4 (cont.) W(z) Values associated with Figure 6 (Top 10%and Bottom 8% excluded)*

Linear extrapolationbased on a line between 18,000 MWD/MTU and 20,000 MWDIMTU is adequate for addressing ,

burnups beyond 20,000 MWD/MTU.

Table 5 FWQ(z)Penalty Factor associated with Figure 6 and Table 4 Cycle Burnup (MWDMTU) FWo(z)Penalty Factor 15364 1.0200 15510 1.0215 15656 1.0232 15803 1.0212 15947 1.0200 F ~ ~ (=z1.020

) for all burnups except those listed above. Linear interpolation is adequate for intermediate cycle burnups.

Page 15 of 21

Core Operating Limits Report Unit 1, Cycle 26 Revision 1 Figure 1 Reactor Core Safety Limits Page 16 of 21

Core Operating Limits Report Unit 1, Cycle 26 Revision 1 Figure 2 Rod Insertion Limit, 128 Step Tip-to-Tip 0 20 40 60 80 100 Power Level, % of Rated Thermal Power Bank Positions Given By:

Bank D = (150 / 63) * (P - 100) + 185 Bank B = (150 163) * (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 17 of 21

Core Operating Limits Report Unit 1, Cycle 26 Revision 1 Figure 3 Rod Insertion Limit, 128 Step Tip-to-Tip, One Bottomed Rod (Technical Specification 3.1.4, Condition B)

Bank Positions Given By:

Bank D = (150 1 63) * (P - 90) + 224 Bank C = (150 163) * (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 18 of 21

Core Operating Limits Report Unit 1, Cycle 26 Revision 1 Figure 4 Rod Insertion Limit, 128 Step Tip-to-Tip, One Inoperable Rod (Technical Specification 3.1.4, Condition A)

Power Level, % of Rated Thermal Power Bank Positions Given By:

Bank D = (150 1 63) * (P - 70) + 224 BankC=(150/63)*(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.

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Core Operating Limits Report Unit 1 , Cycle 26 Revision 1 Page 20 of 2 1

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