ML17229A514
| ML17229A514 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 11/03/1997 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17229A513 | List: |
| References | |
| PCM-97055, PCM-97055-R, PCM-97055-R00, NUDOCS 9711100092 | |
| Download: ML17229A514 (16) | |
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PCM No. 97055 Rev 0 4, Page 1 of 13 ST. LUCIE UNIT 1, CYCLE 15 CORE OPERATING LIMITSREPORT Revision 0' t ~ogo9P 97'03 pDR ADOCK 0 pDR p
PCM No. 97055 Rev 0 4, Page 2 of 13 Table of Contents D
ri tin 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 TOTALINTEGRATED RADIALPEAKING FACTOR 2.6 DNB Parameters
- AXIALSHAPE INDEX 2.7 Refueling Operations - Boron Concentration 3.0 List of Approved Methods Pgigg 12
. Fi(~Us List of Figures 3.1-1a Allowable Time To Realign CEA vs. Initial F,T 3.1 2 3.2 1
3.2-2 3.2-3 3.2-4 CEA Insertion Limits vs. THERMALPOWER Allowable Peak Linear Heat Rate vs. Burnup AXIALSHAPE INDEXvs. Maximum Allowable Power Level Allowable Combinations of THERMALPOWER and F, AXIALSHAPE INDEXOperating Limits vs. THERMALPOWER 10 St. Lucie Unit 1 Cycle 15 COLR Rev 0 Page 2 of 13
PCM No. 97055 Rev 0 4, Page 3 of 13
1.0 INTRODUCTION
This CORE OPERATING LIMITSREPORT (COLR) describes the cycle-specific parameter limits for operation of St. Lucie Unit 1 Cycle 15.
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
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Linear Heat Rate TOTALINTEGRATED 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 Unit1 Cycle 15 COLR Rev 0 Page 3 of 13
PCM No. 97055 Rev 0 4, Page 4 of 13 2.0 CORE OPERATING LlMITS 2.1 Moderator T m eratur o fficien (TS 3.1.1.4)
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The moderator temperature coefficient (MTC) shall be less negative than -28 pcm$'F at RATED THERMALPOWER.
2.2 Full Len th EA Position-Misali nm nt >1 n h s(TS3,1.3.1)
The time constraints forfullpower operation with the misalignment of one full length GEA by 15 or more inches from any other CEA in its group are shown in Figure 3.1-1a.
'.3 Re ulatin EA 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 ~dt LTX 3.2.tt The linear heat rate shall not exceed the limits shown on Figure 3.2-1.
The AXIALSHAPE INDEXpower dependent control limits are shown on Figure 3.2-2.
During operation, with the linear heat rate being monitored by the Excore Detector
~Mi ',td AXIALXIIAPMIMOXX 3 II 3 I t I
3 ttdt td of Figure 3.2-2.
During operation, with the linear heat rate being monitored by the lncore Detector Monitorin 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 Unit1 Cycle 15 COLR Rev 0 Page4 of13
PCM No. 97055 Rev 0 4, Page 5 of 13 2.5 T TAL INTE RAT D RADIALP AKIN FA T R-F (TS3.2.3)
The calculated value of F,T shall be limited to < 1.70.
The power dependent F,T limits are shown on Figure 3.2-3.
2.6 DNB Parameters
- AXIAL HAPE INDE (TS 3.2.5)
The AXIAl SHAPE iNDEXshall be maintained within the limits specified in Figure 3.2-4.
2.7 Refuelin 0 erations - Boron oncentration (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 conser vative allowance for uncertainties.
St. Lucie Unit 1 Cycle 15 COLR Rev 0 Page 5 of 13
PCM No. 97055 Rev 0 4, Page 6 of 13 Allowable Time to Realign CEA vs. initial P,'.7 (15 1.70):
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1.66 Q.
o 1.64 (60 1.67)
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5 10 I5 20 25 30 35 40 45 50 55 60 65 Time at Full Power to Realign CEA, Minutes FIGURE 3.1-1 a Allowable Time to Realign CEA vs. initial F, o
St. Lucie Unit 1 Cycle 15 COLR Rev 0 Page 6 of 13
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i PCM No. 97055 Rev 0 4, Page S of 13 Allowable Peak Linear Heat Rate vs. Burnup L7
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UNACCEPTABLE OPERATION ACCEPTABLE OPERATION 13 BOL Cycle Life EOL (Fuel + Clad + Moderator)
FIGURE 3.2-1 Allowable Peak Linear Heat Rate vs. Burnup St. L'ucie Unit 1 Cycle 15 COLR Rev 0 Page8 of)3
l PCM No. 97055 Rev 0 Attachment t4, Page 9 of 43 Region of
.Unacceptable Operation Region of Unacceptable Operation o 09 o 0.8 E
0.7 XC o 0.6 0
O 0.5 04
(-0.5,0.45)
(-0.08,0.85)
Region of Acceptable Operation (0.08,0.85)
(0.5,0.45)
-0.6
-0.4
-0.2 0
0.2 Peripheral AXIALSHAPE INDEX 0.4 0.6 (Not Applicable Below 40% Power)
FIGURE 3.2-2 AXIALSHAPE INDEXvs. Maximum Allowable Power Level St. Lucie Unit 1 Cycle 15 COLR Rev 0 Page 9 of 13
Allowable Combinations of Thermal Power And F,"
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Acceptable Operation Region Unacceptable Operation Region
( 1.'N,0.9) 0.6 1.?
j.?1 1.72 1.73 1.74 1.75 3.76 1.77 1.78 i.?9 Measured F,"'
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PCM No. 97055 Rev 0
'- "'ttachment 14, Page 11 of 13 1
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Region of Unacceptable Operation
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Region of Acceptable Operation (0.15,1.0)
Region of Unacceptable Operation (0.5,0.65)
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0.2 Peripheral AXIALSHAPE INDEX (Y1) 0.4 0.6 (Not Applicable Below 40% Power)
FIGURE 3.2-4 AXIALSHAPE INDEX Operating Limits vs. THERMALPOWER (Four Reactor Coolant Pumps Operating)
St. Lucie Unit 1 Cycle 15 COLR Rev 0 Page 11 of 13
i PCM No. 97055 Rev 0 4, Page 12 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 I ight Company, January 1995 3.
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 19?5, Supplement 1 dated September 1976, Supplement 2 dated December 1980, Supplement 3 dated September 1981, Supplement 4 dated December 1986, Supplement 5 dated February 198?.
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 7.
XN-75-32(A), Supplements 1, 2, 3, and 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company, dated October 1983 8.
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 9.
XN-NF-78-44(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company, dated October 1983
'IO.
XN-NF-621(A), Rev. 1, "Exxon Nuclear DNB Correlation of PWR Fuel Design,"
Exxon Nuclear Company, dated September 1983 St. Lucie Unit1 Cycle15 COLR Rev 0 Page12 of 13
PCM No. 97055 Rev 0 4, Page 13 of 13 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,'xxon 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-Mechanical Response Evaluation Model," 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 St. Lucie Unit 1 Cycle 15 COLR Rev 0 Page13 of 13
The APRM system is divided into four APRM channels and four 2-out-of-4 voter channels.
Each APRM channel provides inputs to each of the four voter channels.
The four voter channels are divided into two groups of two each, with each group of two providing inputs to one RPS trip system.
The system is designed to allow one APRM channel, but no voter channels, to be bypassed.
Note (I) to Table 3.3.1-1 states that the Minimum Operable Channels in Table 3.3.1-1 for the APRM Functional Units (except the 2-out-of-4 voter Functional Unit) are the total number of APRM channels required and are not on a trip system basis.
Therefore, when only one required APRM is inoperable, Action a is the only Action required to be entered.
This Action requires the APRM to be restored to operable status or placed in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
As stated in Action a, footnote *,
placing either trip system in trip is not applicable since the APRM channels are not on a trip system basis.
When two or more required APRMs are inoperable, Action b is entered.
Action b.1 requires verification of trip capability in the affected functional unit within one hour (i.e., one APRM operable and one APRM in the tripped condition). Action b.2, as stated in footnote **,is not applicable since the APRM channels are not on a trip system basis. Action b.3 requires that the remaining required inoperable APRM be restored to operable status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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