ML17229A848

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Rev 1 to PSL-ENG-SEFJ-98-013, St Lucie Unit 2,Cycle 10 Colr.
ML17229A848
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 08/07/1998
From:
FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17229A847 List:
References
PSL-ENG-SEFJ-98, PSL-ENG-SEFJ-98-013, PSL-ENG-SEFJ-98-13, NUDOCS 9809010224
Download: ML17229A848 (15)
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Text

t PSL-ENG-SEF J-98-013 Rev. 0 Attachment 1, Page) of 14 ST. LUCIE UNIT 2, CYCLE 10 CORE OPERATING LIMITS REPORT Revision 0 s/p/ g repared By S-7-1$

Verified By 98090i0224 980826 PDR ADQCK 0500038'F P PDR St. Lucie Unit 2 Cycle 10 COLR Rev1 Page 1 of 14

PSL-ENG-SEFJ-98-013 Rev. 0 Attachment 1, Page 2 of 14 Table of Contents Descri tion Pacae 1.0 Introduction 2.0 Core Operating Limits 2.1 Moderator Temperature Coefficient 2.2 CEA Position - Misalignment > 15 inches 2.3 Regulating CEA Insertion Limits 2.4 Linear Heat Rate 2.5 TOTAL PLANAR RADIALPEAKING FACTORS 2.6 TOTAL INTEGRATED RADIALPEAKING FACTOR 2.7 DNB Parameters - AXIALSHAPE INDEX 2.8 Refueling Operations - Boron Concentration 3.0 List of Approved Methods 12 List of Figures

~Fi Ure Title ~Pa e 3.1-1a Allowable Time To Realign CEA vs. Initial F, 3.1-2 CEA Insertion Limits vs. THERMAL POWER 3.2 1 Allowable Peak Linear Heat Rate vs. Burnup 3.2 2 AXIALSHAPE INDEX vs. Maximum Allowable Power Level 3.2-3 Allowable Combinations of THERMAL POWER and F,, F~ 10 3.2-4 AXIAI SHAPE INDEX Operating Limits vs. THERMAL POWER 11 St. Lucie Unit 2 Cycle 10 COLR Rev 1 Page 2 of 14

PSL-ENG-SEF J-98-013 Rev. 0 Attachment 1, Page 3 of 14

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) describes the cycle-specific parameter limits for operation of St. Lucie Unit 2 Cycle 10. It contains the limits for the following as provided in Section 2.

Moderator Temperature Coefficient CEA Position - Misalignment > 15 Inches Regulating CEA Insertion Limits Linear Heat Rate TOTAL PLANAR RADIALPEAKING FACTORS - F~

TOTAL INTEGRATED RADIALPEAKING FACTOR - F~

DNB Parameter - AXIALSHAPE INDEX Refueling Operations - Boron Concentration This report also contains the necessary 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 2 Cycle 10 COLR Rev1 Page 3 of 14

t PSL-EN 6-SEF J-98-013 Rev. 0 Attachment 1, Page 4 of 14 2.0 CORE OPERATING LIMITS 2.1 Moderator Tem erature Coefficient (TS 3.1.1.4)

The moderator temperature coefficient (MTC) shall be less negative than -30 pcmi'F at RATED THERMAL POWER.

2.2 CEA Position - Misali nment > 15 Inches (TS 3.1.3.1)

The time constraints for full power operation with one full-length CEA misaligned from any other CEA in its group by more than 15 inches are shown in Figure 3.1-1a.

2.3 Re ulatin CEA Insertion Limits (TS 3.1.3.6)

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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. Less than or equal to 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. Less than or equal to 5 Effective Full Power Days per 30 Effective Full Power Days, and
c. Less than or equal to 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 AXIALSHAPE 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 Monitorin S stem, the AXIALSHAPE INDEX shall be maintained within the limits of Figure 3.2-2.

t During operation, with the linear heat rate being monitored by the Incore Detector Monitorin S stem, 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 2 Cycle 10 COLR Rev 1 Page 4 of 14

PSL-ENG-SEF J-98-013 Rev. 0 Attachment 1, Page 5 of 14 2.5 TOTAL PLANAR RADIAL PEAKING FACTORS - F (TS 3.2.2)

The calculated value of F~ shall be limited to < 1.75.

The power dependent F~ limits are shown on Figure 3.2-3.

2.6 TOTAL INTEGRATED RADIALPEAKING FACTOR - Fi- (TS 3.2.3)

The calculated value of F, shall be limited to < 1.70.

The power dependent F, limits are shown on Figure 3.2-3.

2.7 DNB Parameters - AXIALSHAPE INDEX (TS 3.2.5)

The AXIALSHAPE INDEX shall be maintained within the limits specified in Figure 3.2-4.

2.8 Refuelin 0 erations - Boron Concentration (TS 3.9.1)

With the reactor vessel head closure bolts less than fully tensioned or with the head removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met:

a. Either a K,g of 0.95 or less, or
b. A boron concentration of greater than or equal to 1720 ppm.

St. Lucie Unit 2 Cycle10 COLR Rev1 Page 5 of 14

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PSI=ENG-SEF J-98-0'I 3 Rev. 0 Attachment 0, Page 8 of 54

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FIGURE 3.2-1 Allowable Peak Linear Heat Rate vs. Bumnp St. Lucie Unit 2 Cycle 10 COLR Rev1 Page 8 of 14

PSL-ENG-SEF J-98-013 Rev. 0 Attachment), Page 9 of 44 Q) 6 UNACCEPTABLE OPERATION REGION L

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FIGURE 3.2-2 AXIALSHAPE INDEX vs. Maximum Allowable Power Level St. Lucie Unlt2 Cycle)0 COLR Rev1 Page 9 of 14

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PSL-ENG-SEF J-98-013 Rev. 0 Attachment 1, Page 11 of 14 1 (-0,08,<.00) (0.15,1.00)

UNACCEPTABLE UNACCEPTABLE 0 OPERATION OPERATION cL 0.9 REGION REGION

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(Not Applicable Below 40% Power)

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

St. Lucie Unit 2 Cycle 10 COLR Rev 0 Page 11 of 14

PSL-ENG-SEF J-98-013 Rev. 0 Attachment 1, Page 12 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.

WCAP-11596-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 8 St. Lucie Nuclear Plants," Florida Power 8 Light Company, January 1995 (NRC SER dated June 9, 1995), 8 Supplement 1, August 1997
3. CENPD-199-P, Rev. 1-P-A, "C-E Setpoint Methodology: CE Local Power Density and DNB LSSS and LCO Setpoint Methodology for Analog Protection Systems,"

January 1986

4. CENPD-266-P-A, "The ROCS and DIT Computer Code for Nuclear Design," April 1983
5. CENPD-275-P, Revision 1-P-A, "C-E Methodology for Core Designs Containing Gadolinia-Urania Burnable Absorbers," May 1988
6. CENPD-188-A, "HERMITE: A Multi-Dimensional Space - Time Kinetics Code for PWR Transients,: July 1976 CENPD-1 53-P, Rev. 1-P-A, "Evaluation of Uncertainty in the Nuclear Power Peaking Measured by the Self-Powered, Fixed Incore Detector System," May 1980
8. CEN-123(F)-P, "Statistical Combination of Uncertainties Methodology Part 1: C-E Calculated Local Power Density and Thermal Margin/Low Pressure LSSS for St.

Lucie Unit 1," December 1979 CEN-123(F)-P, "Statistical Combination of Uncertainties Methodology Part 2:

Combination of System Parameter Uncertainties in Thermal Margin Analyses for St.

Lucie Unit 1,"-January 1980

10. CEN-123(F)-P, "Statistical Combination of Uncertainties Methodology Part 3: C-E Calculated Departure from Nucleate Boiling and Linear Heat Rate Limiting Conditions for Operation for St., Lucie Unit 1," February 1980 CEN-191(B)-P, "CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units 1 and 2," December 1981
12. Letter, J. W. Miller (NRC) to J. R. Williams, Jr. (FPL), Docket No. 50-389, Regarding St. Lucie Unit 2 Cycle 10 COLR Rev1 Page 12 of 14

PSL-ENG-SEF J-98-013 Rev. 0 Attachment 1, Page 13 of 14 Unit 2 Cycle '2 License Approval (Amendment No. 8 to NPF-16 and SER),

November 9, 1984 (Approval of CEN-123(F)-P (three parts) and CEN-191(B)-P)

13. CEN-371(F)-P, "Extended Statistical Combination of Uncertainties," July 1989
14. Letter, J. A. Norris (NRC) to J. H. Goldberg (FPL), Docket No. 50-389, "St. Lucie Unit 2 - Change to Technical Specification Bases Sections '2.1.1 Reactor Core'nd

'3/4.2.5 DNB Parameters'TAC No. M87722)," March 14, 1994 (Approval of CEN-371(F)-P)

15. CENPD-161-P-A, "TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core," April 1986
16. CENPD-162-P-A, "Critical Heat Flux Correlation for C-E Fuel Assemblies with Standard Spacer Grids Part 1, Uniform Axial Power Distribution," April 1975
17. CENPD-207-P-A, "Critical Heat Flux Correlation for C-E Fuel Assemblies with Standard Spacer Grids Part 2, Non-uniform Axial Power Distribution," December 1984
18. CENPD-206-P-A, "TORC Code, Verification and Simplified Modeling Methods,"

June 1981

19. CENPD-225-P-A, "Fuel and Poison Rod Bowing," June 1983
20. CENPD-139-P-A, "C-E Fuel Evaluation Model Topical Report," July 1974
21. CEN-161(B)-P-A, "Improvements to Fuel Evaluation Model," August 1989
22. CEN-161(B)-P, Supplement 1-P-A, "Improvements to Fuel Evaluation Model,"

January 1992

23. CENPD-132, Supplement 3-P-A, "Calculative Methods for the C-E Large Break LOCA Evaluation Model for the Analysis of C-E and W Designed NSSS," June 1985
24. CENPD-133, Supplement 5-A, "CEFLASH-4A, A FORTRAN77 Digital Computer Program for Reactor Blowdown Analysis," June 1985
25. CENPD-134, Supplement 2-A, "COMPERC-II, a Program for Emergency Refill-Reflood of the Core," June 1985
26. CENPD-135-P, Supplement 5, "STRIKIN-II,A Cylindrical Geometry Fuel Rod Heat Transfer Program," April 1977 St. Lucie Unit 2 Cycle10 COLR Rev1 Page 13 of 14

t PSL-ENG-SEF J-98-013 Rev. 0 Attachment 1, Page 14 of 14

27. Letter, R. L. Baer (NRC) to A. E. Scherer (CE), "Evaluation of Topical Report CENPD-135, Supplement ¹5," September 6, 1978 2d. CENPD-137, Supplement 1-P, "Calculative Methods for the C-E Small Break LOCA Evaluation Model," January 1977
29. CENPD-133, Supplement 3-P, "CEFLASH-4AS, A Computer Program for the Reactor Blowdown Analysis of the Small Break Loss of Coolant Accident," January 1977
30. Letter, K. Kniel (NRC) to A, E. Scherer (CE), "Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, Supplement 1-P," September 27, 1977 3'I. CENPD-138, Supplement 2-P, "PARCH, A FORTRAN-IV Digital Program to Evaluate Pool Boiling, Axial Rod and Coolant Heatup," January 1977
32. Letter, C. Aniel (NRC) to A. E. Scherer (CE), "Evaluation of Topical Report CENPD-138, Supplement 2-P," April 10, 1978 33 Letter, W. H. Bohlke (FPL) to Document Control Desk (NRC), "St. Lucie Unit 2, Docket No. 50-389, Proposed License Amendment, MTC Chan e from -27 cm to

~30 cm," L-91-325, December 17, 1991

34. Letter, J. A. Norris (NRC) to J H. Goldberg (FPL), "St, Lucie Unit 2 - Issuance of

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Amendment Re: Moderator Temperature Coefficient (TAC No. M82517)," July 15, 1992 .

35. Letter, J. W. Williams, Jr. (FPL) to D. G. Eisenhut (NRC), "St. Lucie Unit No. 2, 8 2 tN.88-888,8 8 dN 2 d 8~pl 28 8 d,"8-84-t48, June 4, 1984
36. Letter, J. R. Miller (NRC) to J. W. Williams, Jr. (FPL), Docket No. 50-389, Regarding Unit 2 Cycle 2 License Approval (Amendment No. 8 to NPF-16 and SER),

November 9, 1984 (Approval of Methodology contained in L-84-148)

37. Letter, A. E. Scherer Enclosure 1-P to LD-82-001, "CESEC-Digital Simulation of a Combustion Engineering Nuclear Steam Supply System," December 1981
38. Safety Evaluation Report, "CESEC Digital Simulation of a Combustion Engineering Steam Supply System (TAC No.: 01142)," October 27, 1983
39. CENPD-282-P-A, Volumes 1, 2, and 3, and Supplement 1, "Technical Manual for the CENTS Code," February1991, February1991, October 1991, and June 1993, respectively St. Lucie Unit 2 Cycle10 COLR Rev1 Page 14 of 14
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