L-2012-083, Cycle 24 Core Operating Limits Report
| ML12068A197 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 02/27/2012 |
| From: | Katzman E Florida Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-2012-083 | |
| Download: ML12068A197 (27) | |
Text
Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 February 27, 2012 FPL L-2012-083 10 CFR 50.36 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: St. Lucie Unit 1 Docket No. 50-335 Cycle 24 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 24.
Technical Specification 6.9.1.11 .d requires that the COLR, including any mid-cycle revisions or supplements, be provided to the NRC upon issuance for each reload cycle. Accordingly, enclosed is a copy of the St. Lucie Unit 1, Cycle 24 Core Operating Limits Report, Revision 0, that was required for core reload for the SL1-24 refueling outage (Attachment 1), and the St. Lucie Unit 1, Cycle 24 Core Operating Limits Report, Revision 1, that was required for unit startup from the SL 1-24 refueling outage (Attachment 2).
Please contact us if there are any questions regarding this submittal.
Very truly yours, Eric S. Katzman Licensing Manager St. Lucie Plant ESK/KWF Attachments an FPL Group company
L-2012-083 Attachment 1 Page 1 of 13 EC-DCP 273422, Rev 0 Attachment 14, Page 1 of 13 ST. LUCIE UNIT 1, CYCLE 24 CORE OPERATING LIMITS REPORT Modes 5 and 6 Operation Only Revision 0 Prepared by: Oci. Z6, 20 11 MA F.e Wand Date Verified by: ae 10at Approved by:
Date
L-2012-083 Attachment 1 Page 2 of 13 EC-DCP 273422, Rev 0 Attachment 14, Page 2 of 13 Table of Contents Description Pine 1.0 Introduction 3 2.0 Core OperatingLimits 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 - AXIAL SHAPE INDEX 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 12 List of Figures Figure Title age 3.1-1a Allowable Time To Realign CEA vs. Initial FT 6 3.1-2 CEA Insertion Limits vs. THERMAL POWER 7 3.2-1 Allowable Peak Linear Heat Rate vs. Burnup 8 3.2-2 AXIAL SHAPE INDEX vs, Maximum Allowable Power Level 9 3.2-3 Allowable Combinations of THERMAL POWER and Fr 10 3.2-4 AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER 11 Rev 0 Page 2 ofl3 St. Lucie St. CYCLE 24 UnIt I1 CYCLE Lucie Unlt COLR 24 COLR Rev 0 Page 2 of 13
L-2012-083 Attachment 1 Page 3 of 13 EC-DCP 273422, Rev 0 Attachment 14, Page 3 of 13
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.
Moderator Temperature Coefficient Full Length CEA Position - Misalignment > 15 Inches Regulating CEA Insertion Limits Linear Heat Rate TOTAL INTEGRATED RADIAL PEAKING FACTOR - FrT DNB Parameter - AXIAL SHAPE INDEX Refueling Operations - Boron Concentration SHUTDOWN MARGIN - Tr, Greater Than 200 OF SHUTDOWN MARGIN - Tavg Less Than or Equal To 200 OF 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.
This COLR only applies to operation in MODES 5 and 6, beginning of Cycle 24.
Parameter values for Modes 1 through 4 will be provided in subsequent revisions to this document.
St. Lucie Unit 1 CYCLE 24 COLR Rev 0 Page 3 of 13
L-2012-083 Attachment I Page 4 of 13 EC-DCP 273422, Rev 0 Attachment 14, Page 4 of 13 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 [Later]
pcm/0 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 3.1-1la.
2.3 Regulating 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 hours 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.
Rev 0 Page 4 of 13 St Lucie SL CYCLE 24 Unit I1 CYCLE Lucia Unit 24 COLR COLR Rev 0 Page 4 of 13
L-2012-083 Attachment 1 Page 5 of 13 EC-DCP 273422, Rev 0 Attachment 14, Page 5 of 13 2.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR - F[T (TS 3.2.3)
The calculated value of Fr at RATED THERMAL POWER shall be limited to <
[Later].
The power dependent FrT 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 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 Ken 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 [Later] pcm.
2.9 SHUTDOWN MARGIN - T._- Less Than or Equal To 200 OF (TS 3.1.1.2)
The SHUTDOWN MARGIN shall be greater than or equal to 2000 pcm.
Rev 0 Page 5 ofl3 St. Lucie St. CYCLE 24 Unit II CYCLE Lucie Unit COLR 24 COLR Rev 0 Page 5 of 13
L-2012-083 Attachment 1 Page 6 of 13 EC-DCP 273422, Rev 0 Attachment 14, Page 6 of 13
[Later]
FIGURE 3.1-1a Allowable Time to Realign CEA vs. Initial FrT St CYCLE- 24---- -
Uni-u-i--- Rev-- ----- ----- Pag 6-- of 13----
St. Lucie Unit 1 CYCLE 24 COLIR Rev 0 Page 6 of 13
EC-DCP 273422, Rev 0 Attachment 14, Page 7 of 13
[Later]
FIGURE 3.1-2 CEA Insertion Limits vs. THERMAL POWER (4 Reactor Coolant Pumps Operating)
- ------------- CD St. Lucie Unit 1 CYCLE 24 COLR Rev 0 Page 7 of 13 CD
L-2012-083 Attachment 1 Page 8 of 13 EC-DCP 273422, Rev 0 Attachment 14, Page 8 of 13
[Later]
FIGURE 3.2-1 Allowable Peak Linear Heat Rate vs. Burnup L-t- - Un- t CYCLE 24 Re 0-P ----- ge8--1 St. Lucie Unit 1 CYCLE 24 COLR Rev 0 Page 8 of 13
L-2012-083 Attachment 1 Page 9 of 13 EC-DCP 273422, Rev 0 Attachment 14, Page 9 of 13
[Later]
FIGURE 3.2-2 AXIAL SHAPE INDEX vs. Maximum Allowable Power Level St. Lucie Unit I CYCLE 24 COLR Rev 0 Page 9 of 13
EC-DCP 273422, Rev 0 Attachment 14, Page 10 of 13
[Later]
FIGURE 3.2-3 Allowable Combinations of THERMAL POWER and Fm ol St --ce--t-- C CE-4---Re 0Pge1 St. Lucie Unit I CYCLE 24 COLR Rev 0 Page 10 of 13
L-2012-083 Attachment 1 Page 11 of 13 EC-DCP 273422, Rev 0 Attachment 14, Page 11 of 13
[Later]
FIGURE 3.2-4 AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER (Four Reactor Coolant Pumps Operating)
St. Lucie Unit 1 CYCLE 24 COLR Rev 0 Pagel 1 of 13
L-2012-083 Attachment 1 Page 12 of 13 EC-DCP 273422, Rev 0 Attachment 14, 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.
- 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 I 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. ANF-84-73(P)(A) Revision 5, Appendix B, & Supplements 1 and 2, "Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events," Advanced Nuclear Fuels Corporation, October 1990
- 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. EMF-84-093(P)(A) Revision 1, "Steam Line Break Methodology for PWRs," Siemens Power Corporation, February 1999 (This document is a Revision to ANF-84-93)
- 7. XN-75-32(P)(A) Supplements 1 through 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company, Inc., October 1983
- 8. XN-NF-82-49(P)(A) Revision I Supplement 1, "Exxon Nuclear Company Evaluation Model Revised EXEM PWR Small Break Model," Siemens Power Corporation, December 1994
- 9. XN-NF-78-44(NP)(A), "A Generic 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. EMF-2087(P)(A) Revision 0, "SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation, June 1999 St.~~~Uni -ui--
CCLE24-----ev--Pge-2-o-1 St. Lucie Unit I CYCLE 24 COLR Rev 0 Page 12 of 13
L-2012-083 Attachment 1 Page 13 of 13 EC-DCP 273422, Rev 0 Attachment 14, Page 13 of 13
- 12. XN-NF-82-06(P)(A) Revision 1, and Supplements 2, 4 and 5, "Qualification of Exxon Nuclear Fuel for Extended Bumup," 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
- 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. ANF-89-151(P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors:
Analysis of Non-LOCA Chapter 15 Events," Advanced Nuclear Fuels Corporation, May 1992
- 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, "ReactorAnalysis System for PWRs Volume I
- 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), Revision 1, "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," May 2004
- 22. EMF-2328(P)(A), Revision 0, "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based," March 2001 St L- i- Unit- CYCLE-- 24 C---ev0-ag St. Lucie Unit 1 CYCLE 24 COLR Rev 0 Page 13 of 13
L-2012-083 Attachment 2 Page I of 13 EC-DCP 273422, Rev I Attachment 14, Page 1 of 13 ST. LUCIE UNIT 1, CYCLE 24 CORE OPERATING LIMITS REPORT Revision 1 Prepared by:E A .
Date2 Verified by: R . n Date Approved by: Date
L-2012-083 Attachment 2 Page 2 of 13 EC-DCP 273422, Rev I Attachment 14, Page 2 of 13 Table of Contents Description Paae 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 - AXIAL SHAPE INDEX 5 2.7 Refueling Operations - Boron Concentration 5 2.8 SHUTDOWN MARGIN - Tavg Greater Than 200 OF 5 2.9 SHUTDOWN MARGIN - Tvg Less Than or Equal To 200 °F 5
.3.0. List -of-Approved Methods .... ........ .................... ............
. . . . 12 ................... . - -
List of Figures Figure Title Paqe 3.1-1a Allowable Time To Realign CEA vs. Initial FrT 6 3.1-2 CEA Insertion Limits vs. THERMAL POWER 7 3.2-1 Allowable Peak Linear Heat Rate vs. Burnup 8 3.2-2 AXIAL SHAPE INDEX vs. Maximum Allowable Power Level 9 3.2-3 Allowable Combinations of THERMAL POWER and Frr 10 3.2-4 AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER 11 St.- -ui Unit----- CYCL 24 OL
--e---ag St. Lucie Unit 1 CYCLE 24 COLR Rev. 1 Page 2 of 13
L-2012-083 Attachment 2 Page 3 of 13 EC-DCP 273422, Rev I Attachment 14, Page 3 of 13
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.
Moderator Temperature Coefficient Full Length CEA Position - Misalignment > 15 Inches Regulating CEA Insertion Limits Linear Heat Rate TOTAL INTEGRATED RADIAL PEAKING FACTOR - FrT DNB Parameter - AXIAL SHAPE INDEX Refueling Operations - Boron Concentration SHUTDOWN MARGIN - Tavg Greater Than 200 OF 0 ........
. . SHUTDOWN -MARGIN-T-Tý4-Less-Than or-Equal-To-200 F 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.
Rev. I Page 3 ofl3 St.
St. Lucie Unit II CYCLE Lucie Unit 24 COLR CYCLE 24 COLR Rev. I Page 3 of 13
L-2012-083 Attachment 2 Page 4 of 13 EC-DCP 273422, Rev I Attachment 14, Page 4 of 13 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 3.1-1a.
2.3 Regulating 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 Monitorinq 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.
Lu -Uni St.---- - CY L---24----
L- Rev----- Pag 4-of 13---
St. Lucie Unit I CYCLE 24 COLR Rev. 1 Page 4 of 13
L-2012-083 I Attachment 2 Page 5 of 13 EC-DCP 273422, Rev 1 Attachment 14, Page 5 of 13 2.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR - FrT (TS 3.2.3)
The calculated value of FrT at RATED THERMAL POWER shall be limited to < 1.70.
The power dependent FrT 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 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 Kef 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 - TawyLess Than or Equal To 200 OF (TS 3.1.1.2)
The SHUTDOWN MARGIN shall be greater than or equal to 2000 pcm.
St.. ...........
U --i CYCLE 24-C - Re-... P of 13-----..
St. Lucie Unit 1 CYCLE 24 COLIR Rev. 1 Page 5 of 13
L-2012-083 Attachment 2 Page 6 of 13 EC-DCP 273422, Rev 1 Attachment 14, Page 6 of 13 1.72
....=-- - .. .."
~ ........
-i 2)~
i .........
![i~------- ---
t!i~ ~iii
?i)t~ iii iiiii 1.70
---- ..... ------. ,. ... ... .. =. .
LL1.6 8 . '-. ..!:--i! - -i~ i' i "":- i ' ; . . .. --------- . . .----- L--4 i-- ---... . -*---- --- ;----
1.66 i1 66 13.. i i I i* : . :: : :-:----:--- - +--+ -+- .- - *-- --+--
4)1.64 ...i"~ * . . - -!-:. .. . ................................ .. ? *---- --- ..--. .---*-? - . . .: -i-? --
ili~~ ...... 1 .......
~...... !...
. i i-----4 ......
......! i 1.62 -- -q-} .. . : - -; -; -4...
.J ...
..Ji.[.!.J..! . . . . ... ...... ...... .2. . . . ........... ..... . i.. -----... .2.2.
1.60 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 FmT St. Lucie Unit I CYCLE 24 COLR Rev. 1 Page 6 of 13
EC-DCP 273422, Rev I Attachment 14, Page 7 of 13 (Group 7 @ 103 in., 1.00) 4
- 1. 00 Li.
0 lgo I 0
Cu 0 .90 (Groop 7 Q@55 in. 0.70) w 0 .70 0
I,- .50 ol UJ 4
0 0:
I,- :
0 C,< o LONGTERM
- z 0 0
.o* .3 TADY STT (3
0g 0 .0 - I I I
I 0
"7 6 3 GROUPS II i l I I I I I I I I I 137 110 8 55 28 0 137 110 02 55 2B 0 137. 117 w 55 28 0 6 4 I I I I l I_ I I I I 1 1 137 110 82 55 22 37 11W 82 55 26 0 CEA GROUP POSITION (INCHES WITHDRAWN)
FIGURE 3.1-2 CEA Insertion Limits vs. THERMAL POWER (4 Reactor Coolant Pumps Operating)
St. Lucie Unit I CYCLE 24 COLR Rev. 1 Page 7 of 13 0 (D
L-2012-083 Attachment 2 Page 8 of 13 EC-DCP 273422, Rev 1 Attachment 14, Page 8 of 13 17.0 UNACCEPTABLE OPERATION 16.0 15.0 IL D
ACCEPTABLE OPERATION 14.0 1 13.0 BOL Cycle Life EOL (Fuel + Clad + Moderator)
FIGURE 3.2-1 Allowable Peak Linear Heat Rate vs. Burnup Rev.1 Page 8 ofI3 St. Lucie St Unit II CYCLE Lucie Unit 24 COLR cycLE 24 COLR Rev.1 Page 8 of 13
L-2012-083 Attachment 2 Page 9 of 13 EC-DCP 273422, Rev I Attachment 14, Page 9 of 13 1.10
.-.*...*-..*..-[...i....*_*-.j .......... r L = - - *
- S,"" I ,: I ,, I I ', " :I,, , , , ,
1.00- - - ....L .... .... ..... .
Region of . I Region of
"-Unacceptable.1--'--- Unacceptable .-'--.
Operatin ....i...;..i......L
.*!* i...... ..L..i .....................
Operation............
0.90 0
- a. (-0.08.0.85) 0.8.8 a)
T 0.80-il ii.,. i~ .......
E 0.70-E I I ~Acceptable: j
- I...-..I--.O.:t9n...*...........
- ,*I., ... . ................. * ...' ..
" ":"-'-0, 5.0.i4,5 i
" 0.60-0
.... "'i"! "'r':;'"..... ('"0"5"0.4 "
,, 0.60-i*- - --------
i l 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
---Lui- Unit- CYCLE -e~ 24 - COLR-- ------- ---- ---------Page- --- of-- 13--
St. Lucie Unit I CYCLE 24 COLIR Rev.1 Page 9 of 13
EC-DCP 273422, Rev 1 Attachment 14, Page 10 of 13 1.1 I. i I: l I i I I i I : I: i . i SI I 1I -t-------------
.. -I
. ----* .. .. . ------- - -------- --- i--- ..- -- -------
. . . --- I----* - - - -:. .
- - - --! - - S----I..............Unacceptable
- -i ---- Operation Region ----
- 1.0. -- ... i --i---- -----4---
r--- -i..
-4 .. ***..----------.------------ -i----- ----------
._J FT .7 [1 +0.47x x(1 P). ..
~ ~ ~ ~ ............ ~ ~ ~--- ----..............
...------- .-J--. ..
W --------- -- -----i--.-- _. .
0.9 -- ----- --I---- -------- j -- -- ! ----.--- . . --.-
0 ----..------.--- ---- ...... ............---..---.-- _ ...
--- Operation Region _---I.-.-Acceptable
J ... ...
S0.8 ---.- -... ...
LU :;;;!]iiT :*:i';;*-[--T-----p---- ----I ......... ] £2: :i-----t o-------- :-i]
- ] ---i _.------
... -_ , _, __,I,,.. , .. , . . .. . .. . . .. . ... I, ,. ., .. ,
.. --- .,I I, .I, . I. .,I_._.
_. _ . , .. ,. .. . ]. .
S0.7 .... _,___.. _.,....,..,.... ,.. I
.,,.,.. I..,__. I, I_____,_.._,._,.
II L,- -- i , I 0.6 1.7 1.71 1.72 1.73 1.74 1.75 1.76 1.77 1.78 1.79 1.8 1.81 1.82 1.83 1.84 1.85 1.86 Measured FrT FIGURE 3.2-3 Allowable Combinations of THERMAL POWER and Fr t
(D St. Lucie Unit I CYCLE 24 COLR Rev. I Page 10 of 13 0
00 W
L-2012-083 Attachment 2 Page 11I of 13 EC-DCP 273422, Rev 1 Attachment 14, Page 11 of 13 1.10 1.00 S-0 B.o6 ,I.0) : I : (0 .1.0) I -
"Unacceptable [ l ') i F ,,- " " '"Unacceptable "
Operation ! I/' ! I i ! I\ Operation 0.90 ...i.:...*i*.*/1
- ..*..i..i..i... ..i*.*..*...*... ..i i..*..i
... .. ... i...-
0.80 0.
.. . ofeRegion
. . . . ofo 0.70 --- e a-f i--- Acceptableb O p era o ..- -- - - 5 . . .
't', . --. ~ .. --- ,---~--
.I. - -----
0.60
- +::
I --Ac o p r toblT- --- I--- fi--- i LL 0 .50.
0.40
-I 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)
CYL-2----e.I ae11ol St.- Lu- -Unit St. Lucie Unit I CYCLE 24 COILR Rev. 1 Page 11 of 13
L-2012-083 Attachment 2 Page 12 of 13 EC-DCP 273422, Rev I Attachment 14, 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.
- 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. ANF-84-73(P)(A) Revision 5, Appendix B, & Supplements 1 and 2, "Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events," Advanced Nuclear Fuels Corporation, October 1990 5-
- -XNWNF-82ý21 (P)(A)-Revision "Application-of-Exxon -Nuclear- Company- PW R ----------------.....
Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company, Inc., September 1983
- 6. EMF-84-093(P)(A) Revision 1, "Steam Line Break Methodology for PWRs," Siemens Power Corporation, February 1999 (This document is a Revision to ANF-84-93)
- 7. XN-75-32(P)(A) Supplements 1 through 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company, Inc., October 1983
- 8. XN-NF-82-49(P)(A) Revision 1 Supplement 1, "Exxon Nuclear Company Evaluation Model Revised EXEM PWR Small Break Model," Siemens Power Corporation, December 1994
- 9. XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transientfor 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. EMF-2087(P)(A) Revision 0, uSEMIPWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation, June 1999 Un- CY L 24 C-L --------Re. --
St.~~~~ -- ae12o St. Lucie Unit I CYCLE 24 COLR Rev. 1 Page 12 of 13
L-2012-083 Attachment 2 Page 13 of 13 EC-DCP 273422, Rev 1 Attachment 14, Page 13 of 13
- 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
- 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. ANF-89-151(P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors:
Analysis of Non-LOCA Chapter 15 Events," Advanced Nuclear Fuels Corporation, May 1992
- 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, "ReactorAnalysis System for PWRs Volume 1
.g Vole B m*hh-kiig Rdsulta,"-Sie Pow*er. .
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), Revision 1, "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," May 2004