L-2024-070, Cycle 32 Core Operating Limits Report
| ML24120A211 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/29/2024 |
| From: | Rasmus P Florida Power & Light Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| L-2024-070 | |
| Download: ML24120A211 (1) | |
Text
April 29, 2024 L-2024-070 10 CFR 50.36
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-00001
RE: St. Lucie Nuclear Plant, Unit 1 Docket 50-335
Cycle 32 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 Revision 1 of the Core Operating Limits Report (COLR) for operating cycle 32. Revision 1 reflects changes of the conversion from Current Technical Specifications (CTS) to Improved Technical Specifications (ITS).
Should you have any questions regarding this submission, please contact Mr.
Kenneth Mack, Fleet Licensing Manager, at 561-904-3635.
Sincerely,
Paul Rasmus./'£ti1~
General Manager, Regulatory Affairs Florida Power & Light Company
Enclosure:
St. Lucie Unit 1, Cycle 32 Core Operating Limits Report, Revision 1
cc: USN RC Regional Administrator, Region II USNRC Project Manager, St. Lucie Nuclear Plant USNRC Resident Inspector, St. Lucie Nuclear Plant
F lorida Power & Light Company
6501 S. Ocean Drive, Jensen Beach, FL 34957 ST. LUCIE UNIT 1, CYCLE 32
CORE OPERATING LIMITS REPORT
Revision 1
Prepared by:--~-*:--~..._~~:;:,,,,_. _** *.,,,...*--t-*--t:_-z:;,_~_~_,,, _* _ 4/19/2024
E. A. Hernandez Date
Verified by: 4/19/2024
R. Hunter Date
Approved by:---+..,,..,,__ J7_* ------
~ Date
- St. Lucie Unit 1 CYCLE 32 COLR Rev.1 Page 1 of 14 Table of Contents
Description Page
1.0 Introduction 3 2.0 Core Operating Limits 2.1 Moderator Temperature Coefficient (MTC) 4 2.2 Control Element Assembly (CEA) Alignment 4 2.3 Regulating CEA Insertion Limits 4 2.4 Linear Heat Rate (LHR) and Axial Shape Index (ASI) 4 2.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR (F?) 5 2.6 RCS Pressure, Temperature and Flow Departure from Nucleate Boiling (DNB) Limits 5
- 2. 7 Boron Concentration 5 2.8 SHUTDOWN MARGIN (SOM) - Tavg Greater Than 200 °F 6 2.9 SHUTDOWN MARGIN (SOM) - Tavg Less Than or Equal To 200 °F 6 2.10 Reactor Core Safety Limits 6 3.0 List of Approved Methods 13
List of Tables and Figures Title Page
3.2-1 DNB Margin Limits 6 3.1-1 a Allowable Time To Realign CEA vs. Initial F? 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 F? 11 3.2-4 AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER 12
1.0 INTRODUCTION
St. Lucie Unit 1 CYCLE 32 COLR Rev.1 Page 2 of 14 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 (MTC)
Control Element Assembly (CEA) Alignment
Regulating CEA Insertion Limits
Linear Heat Rate (LHR) and Axial Shape Index (ASI)
TOTAL INTEGRATED RADIAL PEAKING FACTOR-F?
RCS Pressure, Temperature and Flow Departure from Nucleate Boiling (DNB) Limits
Boron Concentration
SHUTDOWN MARGIN (SDM)-Tavg Greater Than 200 °F
SHUTDOWN MARGIN (SDM)-Tavg Less Than or Equal To 200 °F
Reactor Core Safety Limits (SLs)
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 5.6.3.
St. Lucie Unit 1 CYCLE 32 COLR Rev.1 Page 3 of 14 2.0 CORE OPERATING LIMITS
2.1 Moderator Temperature Coefficient (TS 3.1.3)
The moderator temperature coefficient (MTC) shall be less negative than -32 pcm/°F at RATED THERMAL POWER.
The maximum positive limit shall be:
- a. + 7 pcm/°F with THERMAL POWER ::;; 70% RTP, and
- b. +2 pcm/°F with THERMAL POWER> 70% RTP.
2.2 Control Element Assembly (CEA) Alignment (TS 3.1.4)
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 3.1-1 a.
2.3 Regulating CEA Insertion Limits (TS 3.1.6 and 3.1. 7)
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 365 EFPD.
2.4 Linear Heat Rate (TS 3.2.1) and Axial Shape Index (TS 3.2.4)
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 required by TS 3.2.1 shall be maintained within the limits of Figure 3.2-2.
During operation, with the linear heat rate being monitored by the lncore Detector Monitoring System, the Local Power Density alarm setpoints shall be adjusted to
St. Lucie Unit 1 CYCLE 32 COLR Rev.1 Page 4 of 14 less than or equal to the limits shown on Figure 3.2-1.
The AXIAL SHAPE INDEX required by TS 3.2.4 shall be maintained within the limits shown on Figure 3.2-4.
The instrumentation AXIAL SHAPE INDEX (Y1) used for the trip and pretrip signals in the reactor protection system is the AXIAL SHAPE INDEX value (YE) modified by an appropriate multiplier (A) and a constant (B) to determine the true core axial power distribution for that channel (Y1 = A YE + B). Where YE is the power level detected by the lower excore nuclear instrument detectors (L) less the power level detected by the upper excore nuclear instrument detectors (U), divided by the sum of these power levels, [YE = (L-U) / (L +U)].
2.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR - F/ (TS 3.2.2)
The calculated value of F/ shall be limited to ~ 1.65
The power dependent F? limits are shown on Figure 3.2-3.
2.6 RCS Pressure, Temperature and Flow Departure from Nucleate Boiling (DNB)
Limits (TS 3.4.1)
The following DNB-related parameters shall be maintained within the limits shown on Table 3.2-1:
- a. Cold Leg Temperature
- b. Pressurizer Pressure
With the reactor vessel head unbolted or removed, the boron concentration of all filled portions of the Reactor Coolant System, the refueling canal, 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 Keff of 0.95 or less, which includes a 1000 pcm conservative allowance for uncertainties, or
- b. A boron concentration of 2: 1900 ppm, which includes a 50 ppm conservative allowance for uncertainties.
2.8 SHUTDOWN MARGIN-Tavg Greater Than 200 °F (TS 3.1.1)
St. Lucie Unit 1 CYCLE 32 COLR Rev.1 Page 5 of 14 The SHUTDOWN MARGIN shall be greater than or equal to 3600 pcm.
2.9 SHUTDOWN MARGIN-Tavg Less Than or Equal To 200 °F (TS 3.1.1)
The SHUTDOWN MARGIN shall be greater than or equal to 2000 pcm.
2.10 Reactor Core SLs (TS 2.1)
The fuel melt limit is defined as [(2790 - 17.9 x P - 3.2 x B) x 1.8 + 32] °F, where Pis the maximum weight percent of Gadolinia (%) and B is the maximum pin burnup (GWD/MTU).
Table 3.2-1
DNB MARGIN LIMITS
PARAMETER FOUR REACTOR COOLANT PUMPS OPERATING
Cold Leg Temperature
Pressurizer Pressure* ~ 2225 psia
- 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. Lucie Unit 1 CYCLE 32 COLR Rev.1 Page 6 of 14 1.67
(60, 1.65) 1.65
... 1.63
I-LL
'"O (1)
C 0) m1.61
~ I (1) a_ s...
'"O (1)
- 31.59 en co (1)
~
1.57
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 Frr
St. Lucie Unit 1 CYCLE 32 COLR Rev.1 Page 7 of 14 (Group 7@ 103 in., 1.00)
1.00
0::: 0.90 w
3:
0
- a. 0.80
..J cl
<(
- i!: 0.70 ~I 0::: -0.
w §I ;;;
- c 3: (D l- 0.60 o -~I ! ~1 w
I- 0.50 ~I g. ~1
~ ~ hr-._. & :5 I LL 0.40 @, ~ -~. s 0 r--1.£1' o LONG TERM oo "'-. 0 z 5 I STEADY STATE ~ I SHORT TERM.s 0 0.30 LO
.:: (5 I INSERTION LIMIT @;I STEADY STATE LO
(.) t--- I INSERTION LIMIT @)
~ 0.20.&.. - - - - §-L - - - - -0 a.
LL (9 e ::i 0.10 S2-o.._ ____.._ ____.._ _________.._ ____.._ _________.._ ____.._ ________ _
7 5 3 GROUPS 137 110 82 55 28 137 110 82 55 28 137 110 82 55 28
6 4
137 110 82 55 28 137 110 82 55 28
CEA GROUP POSITION (INCHES WITHDRAWN)
FIGURE 3.1-2 CEA Insertion Limits vs. THERMAL POWER (4 Reactor Coolant Pumps Operating)
St. Lucie Unit 1 CYCLE 32 COLR Rev.1 Page 8 of 14 17.0 ~-----------------,
16.0 - UNACCEPTABLE OPERATION
Allowable Peak Linear Heat Rate, kw/ft
15.0 -@-,,,,,------------------41>
ACCEPTABLE OPERATION 14.0
13.0 ------------------
BOL Cycle Life EOL
FIGURE 3.2-1 Allowable Peak Linear Heat Rate vs. Burnup
St. Lucie Unit 1 CYCLE 32 COLR Rev.1 Page 9 of 14 1.10
I
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Region of [ [ ! I : I [ I Region of I
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- I : I I : : : I : :,*, 1*
1 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 32 COLR Rev.1 Page 10 of 14 1.1
{1.65, 1.0) 1.0
~ Unac :eptable Operati pn ""-- --....
0.9
0.8 ~-
Allowable Fraction O ~ ~
of RATED THERMAL. 7 ~~
POWER (P) o. 6 ~
0.5 ~ -
(2.05, 0.50) 0.4 Accept able Op* !ration
0.3
0.2 1.65 1.70 1.75 1.80 1.85 1.90 1.95 2.00 2.05 Measured F/
FrT= 1.65x [1+0.48 X (1-P)]
FIGURE 3.2-3 Allowable Combinations of THERMAL POWER and F?
(The expression specified in the Figure may be used for Fl at all power levels)
St. Lucie Unit 1 CYCLE 32 COLR Rev.1 Page 11 of 14 1.10
I I
-~--:- :,--:--:- : 1- :--:--:--1--:--:--:-t--: -: --: --1--: --: - ~-
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o I I I I I I I I I I I I I I
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C 0.60 0 I I I I I I I I
~ ro +- +I I... --r-- --:--,--:--:--:--r--:--:--:,- ~--~--~--r--~--~
u.. I I I I I I I I I : : : I : : r 0.50 --~-- --~--i--~--~--~--i--~ ~--~--1--~--~--~--1 ~--~--~--r--~-- --,--
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--~-- --~--~--~--~--~--~--~--~--! ~--~--~--~--~--~- f f t-i I I I I I I I I I I
I I I 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 1 CYCLE 32 COLR Rev.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.
- 1. 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 &
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. XN-NF-79-56(P)(A) Revision 1 and Revision 1 Supplement 1, "Gadolinia Fuel Properties for LWR Fuel Safety Evaluation", October 1981.
- 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), "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. 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 Burn ups of 62 GWd/MTU," Advanced Nuclear
St. Lucie Unit 1 CYCLE 32 COLR Rev.1 Page 13 of 14 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. Deleted.
- 16. Deleted.
- 17. EMF-92-116(P)(A), Revision 0, and Supplement 1 (P)(A), Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Design," February 1999 and February 2015.
- 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-231 O(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," Revision 1, as supplemented by ANP-3000(P), "St. Lucie Unit 1 EPU -
Information to Support License Amendment Request, " Revision 0.
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.
- 24. BAW-10240(P)(A) Revision 0, "Incorporation of MS Properties in Framatome ANP Approved Methods," Framatome ANP, Inc., May 2004.
- 25. EMF-231 O(P)(A)- Revision 1, Supplement 2 - Revision 0, "SRP Chapter 15 Non LOCA Methodology for Pressurized Water Reactors," Framatome Inc., March 2023.
St. Lucie Unit 1 CYCLE 32 COLR Rev.1 Page 14 of 14