L-2013-307, Cycle 25 Core Operating Limits Report

Cycle 25 Core Operating Limits Report

ML13301A228
Person / Time
Site:	Saint Lucie
Issue date:	10/17/2013
From:	Katzman E Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2013-307
Download: ML13301A228 (15)

Text

0FPL.

October 17, 2013 L-2013-307 10 CFR 50.36 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: St. Lucie Unit I Docket No. 50-335 Cycle 25 Core Operating Limits Report Pursuant to St. Lucie Unit 1 Technical Specification (TS) 6.9.1.11 .d, Florida Power & Light Company (FPL) is submitting the Core Operating Limits Report (COLR) for operating cycle 25.

Please contact us if there are any questions regarding this submittal.

Very truly yours, Eric S. Katzman Licensing Manager St. Lucie Plant ESK/KWF Attachment Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957

L-2013-307 Attachment Page 1 of 14 EC-DCP 279290, Rev. 0 Attachment 14, Page 1 of 14 ST. LUCIE UNIT 1, CYCLE 25 CORE OPERATING LIMITS REPORT Revision 0 Prepared by: E. A,10*ma dez Date

.Verified by: 9 f = -

B. Jun Date Approved by:

Date

L-2013-307 Attachment Page 2 of 14 EC-DCP 279290, Rev. 0 Attachment 14, Page 2 of 14 Table of Contents Description Page 1.0 Introduction 3 2.0 Core Operating Limits 2.1 Moderator Temperature Coefficient 4 2.2 Full Length CEA Position - Misalignment > 15 inches 4 2.3 Regulating CEA Insertion Limits 4 2.4 Linear Heat Rate 4 2.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR 5 2.6 DNB Parameters 5 2.7 Refueling Operations - Boron Concentration 5 2.8 SHUTDOWN MARGIN - Tavg Greater Than 200 OF 5 2.9 SHUTDOWN MARGIN - Tavg Less Than or Equal To 200 OF 5 3.0 List of Approved Methods 13 List of Figures Figue Title Page 3.1-1a Allowable Time To Realign CEA vs. Initial FrT 7 3.1-2 CEA Insertion Limits vs. THERMAL POWER 8 3.2-1 Allowable Peak Linear Heat Rate vs. Burnup 9 3.2-2 AXIAL SHAPE INDEX vs. Maximum Allowable Power Level 10 3.2-3 Allowable Combinations of THERMAL POWER and FrT 11 3.2-4 AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER 12 List of Tables Table Title Paqe 3.2-1 DNB Margin Limits 6

-t.Lu. .i Unit C 25 C-LR ---....

Rev--0...Page.......2... of.....14..

St. Lucie Unit I CYCLE 26 COLR Rev. 0 Page 2 of 14

L-2013-307 Attachment Page 3 of 14 EC-DCP 279290, Rev. 0 Attachment 14, Page 3 of 14

1.0 INTRODUCTION

This CORE OPERATING LIMITS REPORT (COLR) describes the cycle-specific parameter limits for the operation of St. Lucie Unit 1. It contains the limits for the following, as provided in Section 2.0:

Moderator Temperature Coefficient Full Length CEA Position - Misalignment > 15 Inches Regulating CEA Insertion Limits Linear Heat Rate TOTAL INTEGRATED RADIAL PEAKING FACTOR - FrT DNB Parameters Refueling Operations - Boron Concentration SHUTDOWN MARGIN - T8vg Greater Than 200 OF SHUTDOWN MARGIN - T8 vg Less Than or Equal To 200 OF This report also contains the necessary tables and figures which give the limits for the above listed parameters.

Terms appearing in capitalized type are DEFINED TERMS as defined in Section 1.0 of the Technical Specifications.

This report is prepared in accordance with the requirements of Technical Specification 6.9.1.11.

St. Lucie Unit I CYCLE 25 COLR Rev. 0 Page 3 of 14

L-2013-307 Attachment Page 4 of 14 EC-DCP 279290, Rev. 0 Attachment 14, Page 4 of 14 2.0 CORE OPERATING LIMITS 2.1 Moderator Temperature Coefficient (TS 3.1 .1.4)

The moderator temperature coefficient (MTC) shall be less negative than -32 pcm/°F at RATED THERMAL POWER.

2.2 Full Length CEA Position - Misalignment > 15 Inches (TS 3.1.3.1)

The time constraints for full power operation with the misalignment of one full length CEA by 15 or more inches from any other CEA in its group are shown in Figure 3.1 -

la.

2.3 Re-gulatingq CEA Insertion Limits (TS 3.1.3.6)

The regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits shown on Figure 3.1-2, with CEA insertion between the Long Term Steady State Insertion Limits and the Power Dependent Insertion Limits restricted to:

a. < 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> interval,

b. < 5 Effective Full Power Days per 30 Effective Full Power Day interval, and

c. < 14 Effective Full Power Days per calendar year.

2.4 Linear Heat Rate (TS 3.2.1)

The linear heat rate shall not exceed the limits shown on Figure 3.2-1.

The AXIAL SHAPE INDEX power dependent control limits are shown on Figure 3.2-2.

During operation, with the linear heat rate being monitored by the Excore Detector Monitoring System, the AXIAL SHAPE INDEX shall be maintained within the limits of Figure 3.2-2.

During operation, with the linear heat rate being monitored by the Incore Detector Monitoring System, the Local Power Density alarm setpoints shall be adjusted to less than or equal to the limits shown on Figure 3.2-1.

St. Lucie Unit 1 CYCLE 25 COLR Rev. 0 Page 4 of 14

L-2013-307 Attachment Page 5 of 14 EC-DCP 279290, Rev. 0 Attachment 14, Page 5 of 14 2.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR - F*T (TS 3.2.3)

The calculated value of FrT shall be limited to < 1.65 The power dependent FrT limits are shown on Figure 3.2-3.

2.6 DNB Parameters (TS 3.2.5)

The following DNB-related parameters shall be maintained within the limits shown on Table 3.2-1:

a. Cold Leg Temperature

b. Pressurizer Pressure

c. AXIAL SHAPE INDEX 2.7 Refueling Operations - Boron Concentration (TS 3.9.1)

With the reactor vessel head unbolted or removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling cavity shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met:

a. Either a Ke, of 0.95 or less, which includes a 1000 pcm conservative allowance for uncertainties, or

b. A boron concentration of > 1900 ppm, which includes a 50 ppm conservative allowance for uncertainties.

2.8 SHUTDOWN MARGIN - T,_. Greater Than 200 OF (TS 3.1.1.1)

The SHUTDOWN MARGIN shall be greater than or equal to 3600 pcm.

2.9 SHUTDOWN MARGIN - Tpvn Less Than or Equal To 200 OF (TS 3.1.1.2)

The SHUTDOWN MARGIN shall be greater than or equal to 2000 pcm.

St. Lucie Unit 1 CYCLE 25 COLR Rev. 0 Page 5 of 14

L-2013-307 Attachment Page 6 of 14 EC-DCP 279290, Rev. 0 Attachment 14, Page 6 of 14 Table 3.2-1 DNB MARGIN LIMITS PARAMETER FOUR REACTOR COOLANT PUMPS OPERATING Cold Leg Temperature

• 551 OF Pressurizer Pressure*

• 2225 psia AXIAL SHAPE INDEX COLR Figure 3.2-4

• Limit not applicable during either a THERMAL POWER ramp increase in excess of 5% per minute of RATED THERMAL POWER or a THERMAL POWER step increase of greater than 10% of RATED THERMAL POWER.

St. Lu cie Unit 1 CYCLE 25 COLIR Rev. 0 Page 6 of 14

L-2013-307 Attachment Page 7 of 14 EC-DCP 279290, Rev. 0 Attachment 14, Page 7 of 14 1.67 H

(60 1.6.

1.65 1.63 -- 1 U-

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.U1.61 (IL 1.59 1 57 iJ 1.55 0 10 20 30 40 50 60 70 Time at Full Power to Realign CEA, Minutes FIGURE 3.1-1a Allowable Time to Realign CEA vs. Initial Fr,

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-- - CY L 25---C- Rev. 0 7 of 14-------------------------

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St. Lucie Unit 1 CYCLE 25 COLR Rev. 0 Page 7 of 14

L-2013-307 Attachment Page 8 of 14 EC-DCP 279290, Rev. 0 Attachment 14, Page 8 of 14 (Group 7@103 in., 1.00) w 0.00 0

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7 5 3 GROUPS I I I I I I I I I I I I I I I I 1 1 137 Il1 62 55 26 0 137 110 62 55 26 0 137 Ila 82 55 26 0 6 4 I I I I I I I I I I I I 137 ISa 62 55 26 5 137 110 62 55 26 a CEA GROUP POSI'RON (INCHES WITHDRAWN)

FIGURE 3.1-2 CEA Insertion Limits vs. THERMAL POWER (4 Reactor Coolant Pumps Operating)

St. Lucie Unit 1 CYCLE 25 COLR Rev. 0 Page 8 of 14

L-2013-307 Attachment Page 9 of 14 EC-DCP 279290, Rev. 0 Attachment 14, Page 9 of 14 17.0 16.0 UNACCEPTABLE OPERATION 0;

a)

I TM a) 15.0 14.7 (D

01) 1..

2 ACCEPTABLE OPERATION 14.0 0

<0 131A BOL Cycle Ufe EOL FIGURE 3.2-1 Allowable Peak Linear Heat Rate vs. Burnup St. Lucie Unit 1 CYCLE 25 COLR Rev. 0 Page 9 of 14

L-2013-307 Attachment Page 10 of 14 EC-DCP 279290, Rev. 0 Attachment 14, Page 10 of 14 1.10 1.00 Region of Region of Unacceptable - Unacceptable Operation Operation 0.90 o 0.80

(-..O.f85 - (.0,0.8) 0.70 R aiin f Ac ep a le E

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/1*117 1\ 111 0.40

-0.6 -0.4 -0.2 0.0 0.2 0.4 0.6 Peripheral AXIAL SHAPE INDEX (Not Applicable Below 40% Power)

Note: AXIAL SHAPE INDEX limits for Linear Heat Rate when using Excore Detector Monitoring System)

FIGURE 3.2-2 AXIAL SHAPE INDEX vs. Maximum Allowable Power Level St. Lucie Unit 1 CYCLE 25 COLR Rev. 0 Page 10 of 14

L-2013-307 Attachment Page 11 of 14 EC-DCP 279290, Rev. 0 Attachment 14, Page 11 of 14 1.1 o 1.0 Of I-- 0.9 w

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0.8 C

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L_ 0.7 0.6 1.65 1.67 1.69 1.71 1.73 1.75 1.77 1.79 Measured FrT FIGURE 3.2-3 Allowable Combinations of THERMAL POWER and FrT Rev. 0 Page 11 of 14 St. Lucie St. CYCLE 25 Unit II CYCLE Lucie Unit 26 COLR COLR Rev. 0 Page I11 of 14

L-2013-307 Attachment Page 12 of 14 EC-DCP 279290, Rev. 0 Attachment 14, Page 12 of 14 1.10

(,0'l~) (0151.4 1.00 a Region of of Jnacc eca )le Unacceptable S pe ra:io-- -Operation uJ 0.90 0

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LL 0.50 0.40 0.6 -0.4 -0.2 0.0 0.2 0.4 0.6 Peripheral AXIAL SHAPE INDEX (Y1)

(Not Applicable Below 40% Power)

(AXIAL SHAPE INDEX limits for DNB)

FIGURE 3.2-4 AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER (Four Reactor Coolant Pumps Operating)

St. Lucie Unit I CYCLE 25 COLR Rev. 0 Page 12 of 14

L-2013-307 Attachment Page 13 of 14 EC-DCP 279290, Rev. 0 Attachment 14, Page 13 of 14 3.0 LIST OF APPROVED METHODS The analytical methods used to determine the core operating limits are those previously approved by the NRC, and are listed below.

1. WCAP-1 1596-P-A, "Qualification of the PHOENIX-P/ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988 (Westinghouse Proprietary)

2. NF-TR-95-01, "Nuclear Physics Methodology for Reload Design of Turkey Point &

St. Lucie Nuclear Plants," Florida Power & Light Company, January 1995

3. XN-75-27(A) and Supplements 1 through 5, [also issued as XN-NF-75-27(A)],

"Exxon Nuclear Neutronic(s) Design Methods for Pressurized Water Reactors,"

Exxon Nuclear Company, Inc. / Advanced Nuclear Fuels Corporation, Report and Supplement 1 dated April 1977, Supplement 2 dated December 1980, Supplement 3 dated September 1981 (P), Supplement 4 dated December 1986 (P), and Supplement 5 dated February 1987 (P)

4. Deleted

5. XN-NF-82-21(P)(A) Revision 1, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company, Inc., September 1983

6. Deleted

7. XN-75-32(P)(A) Supplements 1 through 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company, Inc., October 1983

8. Deleted

9. XN-NF-78-44(NP)(A), "AGeneric Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company, Inc., October 1983

10. XN-NF-621(P)(A) Revision 1, "Exxon Nuclear DNB Correlation for PWR Fuel Designs," Exxon Nuclear Company, Inc., September 1983

11. Deleted

12. XN-NF-82-06(P)(A) Revision 1, and Supplements 2, 4 and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup," Exxon Nuclear Company, Inc., October 1986

13. ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, December 1991 St. Lucie Unit 1 CYCLE 25 COLIR Rev. 0 Page 13 of 14

L-2013-307 Attachment Page 14 of 14 EC-DCP 279290, Rev. 0 Attachment "14, Page 14 of 14

14. XN-NF-85-92(P)(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company, Inc.,

November 1986

15. Deleted

16. Deleted

17. EMF-92-116(P)(A), Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Design," Siemens Power Corporation, February 1999

18. EMF-92-153(P)(A) Revision 1, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Power Corporation, January 2005

19. EMF-96-029(P)(A) Volumes 1 and 2, "Reactor Analysis System for PWRs Volume 1

- Methodology Description, Volume 2 - Benchmarking Results," Siemens Power Corporation, January 1997

20. EMF-1961(P)(A), Revision 0, "Statistical Setpoint/Transient Methodology for Combustion Engineering Type Reactors," Siemens Power Corporation, July 2000

21. EMF-2310(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," Revision 1, as supplemented by ANP-3000(P), "St. Lucie Unit I EPU -

Information to Support License Amendment Request, " Revision 0.

22. EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based,"

Revision 0, as supplemented by ANP-3000(P), "St. Lucie Unit 1 EPU - Information to Support License Amendment Request, " Revision 0.

23. EMF-2103(P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," Revision 0, as supplemented by ANP-2903(P), "St. Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding, " Revision 1.

St. Lucie Unit I CYCLE 25 COLIR Rev. 0 Page 14 of 14