|
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Category:Fuel Cycle Reload Report
MONTHYEARL-2024-140, Cycle 28 Core Operating Limits Report2024-08-14014 August 2024 Cycle 28 Core Operating Limits Report L-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024 Cycle 32 Core Operating Limits Report L-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024 Cycle 27 Core Operating Limits Report L-2023-039, Cycle 27 Core Operating Limits Report2023-03-0707 March 2023 Cycle 27 Core Operating Limits Report L-2022-125, Cycle 31 Core Operating Limits Report2022-09-0606 September 2022 Cycle 31 Core Operating Limits Report L-2021-187, Cycle 26 Core Operating Limits Report2021-09-10010 September 2021 Cycle 26 Core Operating Limits Report L-2021-077, Cycle 30 Core Operating Limits Report2021-04-26026 April 2021 Cycle 30 Core Operating Limits Report L-2020-034, Cycle 25 Core Operating Limits Report2020-02-28028 February 2020 Cycle 25 Core Operating Limits Report L-2019-196, Cycle 29 Core Operating Limits Report2019-10-30030 October 2019 Cycle 29 Core Operating Limits Report L-2018-167, Cycle 24 Core Operating Limits Report2018-09-12012 September 2018 Cycle 24 Core Operating Limits Report L-2018-083, Cycle 28 Core Operating Limits Report2018-04-0202 April 2018 Cycle 28 Core Operating Limits Report L-2017-072, Submittal of Cycle 23 Startup Report2017-04-27027 April 2017 Submittal of Cycle 23 Startup Report L-2016-190, Submittal of Core Operating Limits Report for Cycle 272016-10-14014 October 2016 Submittal of Core Operating Limits Report for Cycle 27 L-2016-048, Submittal of Cycle 22 Core Operating Limits Report2016-02-29029 February 2016 Submittal of Cycle 22 Core Operating Limits Report L-2015-265, Cycle 22 Core Operating Limits Report2015-10-0808 October 2015 Cycle 22 Core Operating Limits Report L-2015-114, Cycle 26 Core Operating Limits Report2015-04-14014 April 2015 Cycle 26 Core Operating Limits Report L-2014-091, Cycle 21 Core Operating Limits Report2014-03-28028 March 2014 Cycle 21 Core Operating Limits Report L-2013-307, Cycle 25 Core Operating Limits Report2013-10-17017 October 2013 Cycle 25 Core Operating Limits Report L-2012-382, Extended Power Uprate Cycle 24 Startup Report2012-10-19019 October 2012 Extended Power Uprate Cycle 24 Startup Report L-2012-298, Cycle 24 Core Operating Limits Report2012-07-25025 July 2012 Cycle 24 Core Operating Limits Report L-2012-083, Cycle 24 Core Operating Limits Report2012-02-27027 February 2012 Cycle 24 Core Operating Limits Report L-2011-066, Cycle 19 Core Operating Limits Report2011-03-0303 March 2011 Cycle 19 Core Operating Limits Report L-2011-021, License Amendment Request for Extended Power Uprate, Attachment 8; Core Operating Limits Report (COLR) Markups2011-02-25025 February 2011 License Amendment Request for Extended Power Uprate, Attachment 8; Core Operating Limits Report (COLR) Markups L-2010-095, Cycle 23 Core Operating Limits Report2010-05-0505 May 2010 Cycle 23 Core Operating Limits Report L-2009-116, Cycle 18 Core Operating Limits Report2009-05-11011 May 2009 Cycle 18 Core Operating Limits Report L-2009-061, Submittal of Annual Report Acceptance Criteria for Emergency Core Cooling System Analyses for Light Water Nuclear Power Reactors2009-03-11011 March 2009 Submittal of Annual Report Acceptance Criteria for Emergency Core Cooling System Analyses for Light Water Nuclear Power Reactors L-2008-254, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors, 10 CFR 50.46 Change Report2008-12-0404 December 2008 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors, 10 CFR 50.46 Change Report L-2008-244, Cycle 22 Core Operating Limits Report2008-11-0505 November 2008 Cycle 22 Core Operating Limits Report L-2008-052, Cycle 17 Reactor Startup Physics Testing Report2008-03-26026 March 2008 Cycle 17 Reactor Startup Physics Testing Report L-2007-183, Cycle 17 Core Operating Limits Report, Rev. 02007-11-19019 November 2007 Cycle 17 Core Operating Limits Report, Rev. 0 L-2007-121, Cycle 21 Startup Physics Testing Report2007-08-0909 August 2007 Cycle 21 Startup Physics Testing Report L-2007-066, Transmittal of Cycle 21 Core Operating Limits Report2007-04-27027 April 2007 Transmittal of Cycle 21 Core Operating Limits Report L-2006-128, Cycle 16 Core Operating Limits Report2006-05-25025 May 2006 Cycle 16 Core Operating Limits Report L-2005-232, Cycle 20 Core Operating Limits Report2005-11-0909 November 2005 Cycle 20 Core Operating Limits Report L-2004-138, Cycle 19 Core Operating Limits Report - Revision 12004-06-29029 June 2004 Cycle 19 Core Operating Limits Report - Revision 1 L-2004-076, Cycle 19 Core Operating Limits Report, Revision 02004-03-29029 March 2004 Cycle 19 Core Operating Limits Report, Revision 0 L-2003-110, Cycle 14 Core Operating Limits Report2003-05-0101 May 2003 Cycle 14 Core Operating Limits Report L-2002-209, Cycle 18 Core Operating Limits Report - Revision 02002-10-18018 October 2002 Cycle 18 Core Operating Limits Report - Revision 0 2024-08-14
[Table view] Category:Letter type:L
MONTHYEARL-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-138, License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles2024-09-11011 September 2024 License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles L-2024-148, Submittal of Offsite Dose Calculation Manual (Odcm), Revision 552024-09-0909 September 2024 Submittal of Offsite Dose Calculation Manual (Odcm), Revision 55 L-2024-140, Cycle 28 Core Operating Limits Report2024-08-14014 August 2024 Cycle 28 Core Operating Limits Report L-2024-133, Snubber Program Plan Submittal2024-08-14014 August 2024 Snubber Program Plan Submittal L-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024 2024 Population Update Analysis L-2024-129, Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval2024-08-0707 August 2024 Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval L-2024-121, Subsequent License Renewal Commitment 30 Revision2024-07-30030 July 2024 Subsequent License Renewal Commitment 30 Revision L-2024-123, Submittal of In-Service Inspection Program Owners Activity Report (OAR-1)2024-07-29029 July 2024 Submittal of In-Service Inspection Program Owners Activity Report (OAR-1) L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-117, Safety Injection Tank Vent Through Wall Leakage2024-07-11011 July 2024 Safety Injection Tank Vent Through Wall Leakage L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-110, Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake2024-07-10010 July 2024 Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake L-2024-109, Schedule for Subsequent License Renewal Environmental Review2024-07-0303 July 2024 Schedule for Subsequent License Renewal Environmental Review L-2024-104, Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 102024-06-26026 June 2024 Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 L-2024-097, Technical Specification Special Report2024-06-20020 June 2024 Technical Specification Special Report L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-090, Revised Steam Generator Tube Inspection Reports2024-06-0404 June 2024 Revised Steam Generator Tube Inspection Reports L-2024-075, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-05-13013 May 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation L-2024-053, License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis2024-04-30030 April 2024 License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis L-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024 Cycle 32 Core Operating Limits Report L-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024 Cycle 27 Core Operating Limits Report L-2024-064, Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report2024-04-17017 April 2024 Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report L-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024 Annual Radiological Environmental Operating Report for Calendar Year 2023 L-2024-054, 2023 Annual Environmental Operating Report2024-04-0909 April 2024 2023 Annual Environmental Operating Report L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-045, Report of 10 CFR 72.48 Plant Changes2024-03-27027 March 2024 Report of 10 CFR 72.48 Plant Changes L-2024-011, and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2024-023, Unusual or Important Environmental Event - Turtle Mortality2024-03-0606 March 2024 Unusual or Important Environmental Event - Turtle Mortality L-2024-015, 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 2023 Annual Radioactive Effluent Release Report L-2024-027, Safety Injection Tank Vent Through Wall Leakage2024-02-29029 February 2024 Safety Injection Tank Vent Through Wall Leakage L-2024-029, 2023 Annual Operating Report2024-02-28028 February 2024 2023 Annual Operating Report L-2024-026, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-02-27027 February 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 L-2023-175, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes 2024-09-09
[Table view] |
Text
OCT 1 It 2016 L-2016-190 10 CFR50.36 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: St. Lucie Unit 1 Docket No. 50-335 Cycle 27 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 27.
Please contact us ifthere are any questions regarding this submittal.
Very truly yours, MJS/KWF Attachment cc: NRC Region II Administrator NRC Site Resident Inspector Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957
L-2016- I-90 Attachment 1 Page 1Of14 ST. LUCIE UNIT 1, CYCLE 27 CORE OPERATING LIMITS REPORT Revision 0 Prepared""' ~ . A- H andez Date
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L-2016-190 Attachment 1 Page 2of14 Table of Contents Description Page 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 5 2.7 Refueling Operations - Boron Concentration 5 2.8 SHUTDOWN MARGIN - Tavg Greater Than 200 °F 5 2.9 SHUTDOWN MARGIN - Tavg Less Than or Equal To 200 °F 5 3.0 List of Approved Methods 13 List of Figures Page 3.1-1a Allowable Time To Realign CEA vs. Initial F,T 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 I
3.2-3 Allowable Combinations of THERMAL POWER and F,T 11 3.2-4 AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER 12 List of Tables Table Title Page 3.2-1 DNB Margin Limits 6 St. Lucie Unit 1 CYCLE 27 COLR Rev.O Page 2of14
L-2016-190 Attachment 1 Page 3of14
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 2.0:
Moderator Temperature Coefficient Full Length CEA Position - Misalignment > 15 Inches Regulating CEA Insertion Limits Linear Heat Rate TOTAL INTEGRATED RADIAL PEAKING FACTOR - F,T DNB Parameters Refueling Operations - Boron Concentration SHUTDOWN MARGIN - Tavg Greater Than 200 °F SHUTDOWN MARGIN - Tavg Less Than or Equal To 200 °F 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 6.9.1.11.
St. Lucie Unit 1 CYCLE 27 COLR Rev.a Page 3of14
L-2016-19-0 Attachment 1 Page 4of14 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 pcmt°F at RATED THERMAL POWER.
2.2
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 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 lncore 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.
St. Lucie Unit 1 CYCLE 27 COLR Rev.O Page 4of14
L-2016-190 Attachment 1 Page 5of14 2.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR - F,T (TS 3.2.3)
The calculated value of F,T shall be limited to.:::_ 1.65 The power dependent F,T limits are shown on Figure 3.2-3.
2.6 DNB Parameters (TS 3.2.5)
The following DNB-related parameters shall be maintained within the limits shown on Table 3.2-1:
- a. Cold Leg Temperature
- b. Pressurizer Pressure
- c. AXIAL SHAPE INDEX
- 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 K,,11 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 - T2Y9. Greater Than 200 °F (TS 3.1.1.1)
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 3.1.1.2)
The SHUTDOWN MARGIN shall be greater than or equal to 2000 pcm.
St. Lucie Unit 1 CYCLE 27 COLR Rev.O Page 5of14
L-2016-190 Attachment 1 Page 6of14 Table 3.2-1 DNB MARGIN LIMITS PARAMETER FOUR REACTOR COOLANT PUMPS OPERATING Cold Leg Temperature ~ 551°F Pressurizer Pressure* ~2225 psia AXIAL SHAPE INDEX COLR Figure 3.2-4
- 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 27 COLR Rev.O Page 6of14
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FIGURE 3.1-2 CEA Insertion Limits vs. THERMAL POWER (4 Reactor Coolant Pumps Operating)
St. Lucie Unit 1 CYCLE 27 COLR Rev.O Page 8of14
L-2016-190 Attachment 1 Page 9of14 17.0 ~--------------~
16.0 UNACCEPTABLE OPERATION Allowable Peak Linear Heat Rate, kw/ft 15.0 .....-----------------<!>
ACCEPTABLE OPERATION 14.0 13.0 .L..__ _ _ _ _ _ _ _ _ _ _ _ _ ___J BOL Cycle Life EOL FIGURE 3.2-1 Allowable Peak Linear Heat Rate vs. Burnup St. Lucie Unit 1 CYCLE 27 COLR Rev.O Page 9of14
L-2016-190 Attachment 1 Page 10of14 1.10 1.00 I Region of Region of Unacceptable I Unacceptable - ~
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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 27 COLR Rev.O Page 10of14
L-2016-190 Attachment 1 Page 11of14
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St. Lucie Unit 1 CYCLE 27 COLR Rev.O Page 11 of14
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FIGURE 3.2-4 AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER (Four Reactor Coolant Pumps Operating)
St. Lucie Unit 1 CYCLE 27 COLR Rev.O Page 12of14
L-2016-190 Attachment 1 Page 13of14 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. I 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. Deleted.
- 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 Nucl_~ar 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 St. Lucie Unit 1 CYCLE 27 COLR Rev.O Page 13of14
\
L-2016-190 Attachment 1 Page 14of14 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, Supplement 1(P)(A), Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Design," 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.
- 22. EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based,"
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 M5 Properties in Framatome ANP Approved Methods."
St. Lucie Unit 1 CYCLE 27 COLR Rev.O Page 14of14