ML17229A162

Cycle 14 COLR, Rev 0

ML17229A162
Person / Time
Site:	Saint Lucie
Issue date:	12/09/1996
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17229A160	List: ML17229A159 ML17229A161 ML17229A162
References
NUDOCS 9612120456
Download: ML17229A162 (17)

Text

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St. Lucie Unit I Docket No. 50-335 Proposed L'icense Amendment Core 0 eratin LimitsRe ort COLR ENCLOSURE TO L-96-29S ST. LUCIE UNIT 1, CYCLE 14 CORE OPERATING LIMITSREPORT Revision 0 9bi2i20456 96i209 PDR ADOCK 05000335 P PDR

I I ST. LUCIE UNIT 1, CYCLE 14 CORE OPERATING LIMITS REPORT Revision 0

Table of Contents

~Di ti Pacae 1.0 Introduction 2.0 Core Operating Limits 2.1 Moderator Temperature Coefficient 2.2 Full Length CEA Position - Misalignment > 15 inches 2.3 Regulating CEA Insertion Limits 2.4 Linear Heat Rate 2.5 Total Integrated Radial Peaking Factor 2.6 DNB Parameters - AXIAL SHAPE INDEX 2.7 Refueling Operations - Boron Concentration 3.0 List of Approved Methods 12 List of Figures

~iciure 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 AXIAL SHAPE INDEX vs. Maximum Allowable Power Level 3.2-3 Allowable Combinations of THERMAL POWER and F, 10 3.2-4 AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER St. Lucie Unit 1 Cycle 14 COLR Rev 0 Page 2 of13

1.0 INTRODUCTION

This CORE OPERATING LIMITS REPORT (COLR) describes the cycle-specific parameter limits for operation of St. Lucie Unit 1 Cycle 14. It contains the limits for the following as provided in Section 2.

Moderator Temperature Coefficient Full Length CEA Position - Misalignment > 15 Inches Regulating CEA Insertion Limits Linear Heat Rate Total Integrated Radial Peaking Factor -

F,'NB Parameter - AXIAL SHAPE 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 1 Cycle 14 COLR Rev 0 Page 3 of13

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 -28 pcm/'F at RATED THERMAL POWER.

2.2 Full Len th CEA Position - Misali nment > 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 3.1-1a.

2.3 Re ulatin 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 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 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 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 1 Cycle 14 COLR Rev 0 Page 4 of 13

2.5 Total Inte rated Radial Peakin Factor - F (TS 3.2.3)

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

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

2.6 DNB Parameters - AXIAL SHAPE INDEX (TS 3.2.5)

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

2.7 Refuelin 0 erations - 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 K,of 0.95 or less, which includes a 1000 pcm conservative allowance for uncertainties, or

b. A boron concentration of > 1720 ppm, which includes a 50 ppm conservative allowance for uncertainties.

St. Lucie Unit 1 Cycle 14 COLR Rev 0 Page 5 of13

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g Allowable Time to Realign CEA vs. Initial P '

1.72

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1.62

~ 'S 0 5 f0 15 20 25 30 35 40 45 50 55 60 65 Time at Full Power to Realign CEA, Minutes FlGURE 3.1-1a Allowable Time to Realign CEA vs. Initial F,T St. Lucie Unit 1 Cycle 14 COLR Rev 0 Page 6 of 13

a.sn p, a.sn 82, .7a) 0.7n g8,.75) a.ao

> .a.sn PONR QEPEHDEIIT 1HSERTlnH LlH17 l> g LaHQ TNH STFhDV I'hTE g a.ta 1HSERVlOH I lJH1T I j ~

0. 30 SIIORT THIN t

TEhbV N'h1V.

SRIIttOH fJHt

a. 20

a. la GllaHPS 7 6 27 55 82 109 ll7. 0 27 55 82 109 137 0 27 55 82 l09 l37 5 2 109 137 fl 27 55 82 la9 137 CQ 1HSEINlaH (tNCIlgs)

Allowable Peak Linear Heat Rate vs. Surnup 17 16 UNACCEPTABLE OPERATION L

15 CL 14 ACCEPTABLE OPERATION O

13 BOL Cycle Life EOL (Fuel + Clad + Moderator)

FIGURE 3.2-1 Allowable Peak Linear Heat Rate vs. Burnup St. Lucie Unit 1 Cycle 14 COLR Rev 0 Page 8 of13

1.1 Region of Region of Unacceptable Unacceptable Operation Operation L

~o 0.9

(-0.08,0.85) (0.08,0.85) o 0.8 Region of E Acceptable Operation o

0.5

(-o.s,o.as) (0.5,0.45) 0.4

-0.6 -0.4 -0.2 0 0.2 0.4 0.6 Peripheral AXlALSHAPE INDEX (Not Applicable Below 40% Power)

FIGURE 3.2-2 AXIAL SHAPE INDEX vs. Maximum Allowable Power Level St. Lucie Unit 1 Cycle 14 COLR Rev 0 Page 9 of 13

Allowable Combinations of Thermal Power And F.'1.7, Unacceptable Operation Region 1.0)

S O

ILI

~09 CI (1.78,0.9)

O id

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fC

+ Ill < O.S Ol ~

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0~ Acceptable Operation Region O.

I 65 U 0 0.7 6$

0 CL Tl 0.6 1.7 1.71 1.72 1.73 1.74 1.75 1.76 1.77 1.78 1.79 Measured F,'

1.1

(-0.08,<.o) (0.15,1.0)

Region of Region of Unacceptable Unacceptable 0c Operation Operation 0.9 LLI 0.8 I-Cl Region of Acceptable

(-0.5,0.65) Operation (0,5,0.65) 0.5 0.4

-0.6 -0.4 -0.2 0 0.2 0.4 0.6 Peripheral AXIALSHAPE INDEX (Y1)

(Not Applicable Below 4D% Power)

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

St. Lucie Unit 1 Cycle 14 COLR Rev 0 Page 11 of 13

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)

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 XN-75-27(A), Rev. 0 and Supplement 1 through 5, "Exxon Nuclear Neutronics Design Methods for Pressurized Water Reactors," Exxon Nuclear Company, Rev. 0 dated June 1975, Supplement 1 dated September 1976, Supplement 2 dated December 1980, Supplement 3 dated September 1981, Supplement 4 dated December 1986, Supplement 5 dated February 1987.

ANF-84-73(P), Rev. 3, "Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events," Advanced Nuclear Fuel Corporation, dated May 1988 XN-NF-82-21(A), Rev. 1, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company, dated September 1983 ANF-84-93(A), Rev. 0 and Supplement 1, "Steamline Break Methodology for PWR's," Advanced Nuclear Fuels Corporation, Rev. 0 dated March 1989, Supplement 1 dated March 1989 XN-75-32(A), Supplements 1, 2, 3, and 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company, dated October 1983 XN-NF-82-49(A), Rev. 1 and Supplement 1, "Exxon Nuclear Company Evaluation Model EXEM PWR Small Break Model," Advanced Nuclear Fuels Corporation, Rev. 1 dated April 1989, Supplement 1 dated December 1994 XN-NF-78-44(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company, dated October 1983

10. XN-NF-621(A), Rev. 1, "Exxon Nuclear DNB Correlation of PWR Fuel Design,"

Exxon Nuclear Company, dated September 1983 St. Lucie Unit 1 Cycle 14 COLR Rev 0 Page 12 of 13

+I

11. EXEM PWR Large Break LOCA Evaluation Model as defined by:

a. XN-NF-82-20(A), Rev. 1 and Supplements 1 through 4, "Exxon Nuclear Company Evaluation Model EXEM/PWR ECCS Model Updates," Exxon Nuclear Company, all dated January 1990

b. XN-NF-82-07(A), Rev. 1, "Exxon Nuclear Company ECCS Cladding Swelling and Rupture Model," Exxon Nuclear Company, dated November 1982

c. XN-NF-81-58(A), Rev. 2 and Supplements 1 through 4, "RODEX2 Fuel Rod Thermal-lVlechanical Response Evaluation IVlodel," Exxon Nuclear Company, Rev. 2 and Supplement 1 and 2 dated March 1984, Supplements 3 and 4 dated June 1990

d. XN-NF-85-16(A), Volume 1 through Supplement 3; Volume 2, Rev. 1 and Supplement 1, "PWR 17x17 Fuel Cooling Tests Program," Exxon Nuclear Company, all dated February 1990

e. XN-NF-85-105(A), Rev. 0 and Supplement 1, "Scaling of FCTF Based Reflood Heat Transfer Correlation for Other Bundle Designs," Exxon Nuclear Company, all dated January 1990 0

St. Lucie Unit 1 Cycle 14 COLR Rev 0 Page 13 of 13