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Category:Fuel Cycle Reload Report
MONTHYEARL-2023-062, Cycle 33 Core Operating Limits Report2023-04-27027 April 2023 Cycle 33 Core Operating Limits Report L-2022-052, Core Operating Limits Report2022-04-0101 April 2022 Core Operating Limits Report L-2021-195, Submittal of Core Operating Limits Report2021-10-22022 October 2021 Submittal of Core Operating Limits Report L-2020-149, Submittal of Core Operating Limits Report2020-10-13013 October 2020 Submittal of Core Operating Limits Report L-2020-052, Core Operating Limits Report2020-04-10010 April 2020 Core Operating Limits Report L-2019-068, Core Operating Limits Report2019-03-29029 March 2019 Core Operating Limits Report L-2018-195, Core Operating Limits Report2018-10-19019 October 2018 Core Operating Limits Report L-2017-036, Core Operating Limits Report, Cycle 292017-04-14014 April 2017 Core Operating Limits Report, Cycle 29 L-2016-178, Submittal of Cycle 29 Refueling Outage Steam Generator Tube Inspection Report2016-10-18018 October 2016 Submittal of Cycle 29 Refueling Outage Steam Generator Tube Inspection Report L-2016-176, Submittal of Core Operating Limits Report Cycle 28 and Cycle 292016-09-13013 September 2016 Submittal of Core Operating Limits Report Cycle 28 and Cycle 29 L-2016-081, Core Operating Limits Report2016-04-14014 April 2016 Core Operating Limits Report L-2015-271, Core Operating Limits Report, Cycle 282015-11-16016 November 2015 Core Operating Limits Report, Cycle 28 L-2014-069, Core Operating Limits Report2014-03-26026 March 2014 Core Operating Limits Report L-2013-034, Core Operating Limits Report for Unit 4 Cycle 272013-01-28028 January 2013 Core Operating Limits Report for Unit 4 Cycle 27 L-2012-356, Revised Core Operating Limits Report2012-10-0303 October 2012 Revised Core Operating Limits Report L-2012-258, Core Operating Limits Report2012-06-22022 June 2012 Core Operating Limits Report L-2012-204, CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - 2011 Annual Report2012-04-30030 April 2012 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - 2011 Annual Report L-2012-180, Revised Core Operating Limits Report2012-04-21021 April 2012 Revised Core Operating Limits Report L-2011-118, Core Operating Limits Report2011-04-11011 April 2011 Core Operating Limits Report L-2011-067, 2010 Annual Fitness for Duty Performance Report2011-02-24024 February 2011 2010 Annual Fitness for Duty Performance Report L-2011-006, License Amendment Request No. 209; Relocation of Cycle Specific Parameters to the Core Operating Limits Report (COLR)2011-02-21021 February 2011 License Amendment Request No. 209; Relocation of Cycle Specific Parameters to the Core Operating Limits Report (COLR) L-2011-019, Cycle 25 Sartup Report2011-02-0404 February 2011 Cycle 25 Sartup Report L-2010-230, Core Operating Limits Report2010-10-11011 October 2010 Core Operating Limits Report L-2009-240, Core Operating Limits Report for Turkey Point Unit 42009-11-13013 November 2009 Core Operating Limits Report for Turkey Point Unit 4 L-2009-076, Submittal of Core Operating Limits Report2009-04-0707 April 2009 Submittal of Core Operating Limits Report L-2008-087, Core Operating Limits Report, Cycle 242008-04-24024 April 2008 Core Operating Limits Report, Cycle 24 L-2007-150, Submittal of Core Operating Limits Report2007-09-27027 September 2007 Submittal of Core Operating Limits Report L-2005-088, Core Operating Limits Report2005-05-20020 May 2005 Core Operating Limits Report L-2004-219, Core Operating Limits Report2004-10-12012 October 2004 Core Operating Limits Report L-2003-254, Core Operating Limits Report for Cycle 212003-10-20020 October 2003 Core Operating Limits Report for Cycle 21 L-2003-040, Core Operating Limits Report2003-03-13013 March 2003 Core Operating Limits Report L-2002-063, Core Operating Limits Report for Turkey Point, Unit 42002-04-0404 April 2002 Core Operating Limits Report for Turkey Point, Unit 4 2023-04-27
[Table view] Category:Letter type:L
MONTHYEARL-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-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) 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-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-172, 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-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023 Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation. L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-072, Preparation and Scheduling of Operator Licensing Examinations2023-05-22022 May 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-061, 2022 Annual Radiological Environmental Operating Report2023-05-12012 May 2023 2022 Annual Radiological Environmental Operating Report L-2023-062, Cycle 33 Core Operating Limits Report2023-04-27027 April 2023 Cycle 33 Core Operating Limits Report L-2023-060, Radiological Emergency Plan, Revision 752023-04-26026 April 2023 Radiological Emergency Plan, Revision 75 L-2023-054, Submittal of Periodic Reports2023-04-12012 April 2023 Submittal of Periodic Reports L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, 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 Applications2023-03-27027 March 2023 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-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-040, Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application2023-03-0303 March 2023 Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application L-2023-037, Annual Radioactive Effluent Release Report2023-03-0101 March 2023 Annual Radioactive Effluent Release Report L-2023-017, Radiological Emergency Plan Revision 73 and Revision 7 42023-02-17017 February 2023 Radiological Emergency Plan Revision 73 and Revision 7 4 L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis L-2023-004, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results2023-01-17017 January 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-181, Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 52022-12-0101 December 2022 Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 5 L-2022-182, Emergency Response Data System (Eros) Changes2022-11-17017 November 2022 Emergency Response Data System (Eros) Changes L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2022-168, and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2022-171, 10 CFR 50.59(d)(2) Summary Report2022-10-20020 October 2022 10 CFR 50.59(d)(2) Summary Report L-2022-167, Submittal of Periodic Reports2022-10-13013 October 2022 Submittal of Periodic Reports L-2022-166, Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement2022-10-0505 October 2022 Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement L-2022-149, U4R33 Steam Generator Tube Inspection Report2022-10-0404 October 2022 U4R33 Steam Generator Tube Inspection Report L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-148, Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication2022-09-16016 September 2022 Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication L-2022-151, Evacuation Time Estimate Study2022-09-15015 September 2022 Evacuation Time Estimate Study L-2022-142, Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-08-19019 August 2022 Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 L-2022-136, Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report2022-08-12012 August 2022 Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report L-2022-109, Inservice Inspection Program - Owner'S Activity Report (OAR-1)2022-06-27027 June 2022 Inservice Inspection Program - Owner'S Activity Report (OAR-1) L-2022-076, Subsequent License Renewal Application - Appendix E Environmental Report Supplement 22022-06-0909 June 2022 Subsequent License Renewal Application - Appendix E Environmental Report Supplement 2 2024-01-25
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Text
0IPL.
POWERING TODAY.
FEB 4 2011 0
EMPOWERING TOMORROW.
L-2011-019 10 CFR 50.36 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re: Turkey Point Unit 3 Docket No. 50-250 Turkey Point Unit 3 Cycle 25 Startup Report Technical Specification (TS) 6.9.1.1, Startup Report,' states that a summary report of plant startup and power escalation testing shall be submitted following installation of fuel that has a different design. Turkey Point Unit 3 implemented new 15x15 UPGRADE fuel assemblies in support of the future implementation of power uprate at Turkey Point Unit 3. Cycle 25 is the first cycle in which Unit 3 is operating with the new 15X15 UPGRADE fuel assemblies and the old 15X1 5 Debris Resistant Fuel Assemblies (DRFA) in the same core.
The new 15xl 5 UPGRADE fuel assemblies have different thermal-hydraulic characteristics than the old 15x15 DRFAs. The differences between the two fuel designs include the addition of intermediate flow mixing grids, a change in the structural grid design and a change in the elevation of the active fuel stack which is 2.103 inches lower for the UPGRADE fuel.
In accordance with TS 6.9.1.1 the attached startup report is provided.
Should there be any questions, please contact Robert Tomonto, Licensing Manager, at 305-246-7327.
Very truly yours, Michael Kiley Vice President Turkey Point Nuclear Plant Attachment cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant L'Lo an FPL Group company
Attachment to L-2011-019 Page 1 of 5 TURKEY POINT UNIT 3 CYCLE 25 STARTUP REPORT
1.0 DESCRIPTION
AND PURPOSE Turkey Point Unit 3 implemented new 15x1 5 UPGRADE fuel assemblies in support of the future implementation of power uprate at Turkey Point Unit 3. On November 9, 2010, Turkey Point Unit 3 completed the Cycle 25 refueling outage and the unit was placed on line. Cycle 25 is the first cycle in which Unit 3 is operating with the new 15X1 5 UPGRADE fuel assemblies and the old 15X1 5 Debris Resistant Fuel Assemblies (DRFA) in the same core.
This startup report is generated on the basis that the new 15x1 5 UPGRADE fuel assemblies have different thermal-hydraulic characteristics than the old 15x1 5 DRFAs. The differences between the two fuel designs include the addition of intermediate flow mixing grids, a change in the structural grid design and a change in the elevation of the active fuel stack which is 2.103 inches lower for the UPGRADE fuel.
Technical Specification (TS) 6.9.1.1, Startup Report, states that "a summary report of plant startup and power escalation testing shall be submitted following: ... (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the unit. The report shall address each of the tests identified in the FSAR and shall in general include a description of the measured values of the operating conditions of characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report. Subsequent Startup Reports shall address startup tests that are necessary to demonstrate the acceptability of changes and/or modifications."
2.0 CORE DESIGN
SUMMARY
The Unit 3 Cycle 25 core is designed to operate for 14,000 MWD/MTU. Forty-eight fresh fuel assemblies of the UPGRADE design were loaded into the Cycle 25 core. Forty have a nominal enrichment of 3.600 w/o and eight have a nominal enrichment of 4.000 w/o. In addition, the top and bottom 8 inches have a natural uranium annular blanket vs. the 6 inch natural uranium annular blanket for the previous DRFA fuel.
The following is a summary of the mechanical fuel design features of the UPGRADE assemblies:
- The fuel envelope, fuel assembly height, outside diameter of the fuel rods (0.422 in), and the pellet stack length (144 in) will be unchanged. However, pellet stack elevation will be shifted down by 2.103 inches.
Attachment to L-2011-019 Page 2 of 5
" The fuel rod length will increase from 152.600 to 152.880 inches.
- The same Removable Top Nozzle (RTN) design currently in operation at Turkey Point Units 3 and 4 will be used. TM
" ZIRLO TM OFA structural mid grids with unbalanced vane pattern will be changed to ZIRLO I-Spring mid grids with balanced vane pattern.
" Intermediate Flow Mixer (IFM) grids with a balanced vane pattern referred to as the Enhanced IFM (IFM) will be included in the 15x15 UPGRADE design.
" Tube-in-Tube ZIRLOTM guide thimbles.
- High-force Alloy 718 bottom grid as currently used in the DRFA fuel design.
- Alloy 718 top grid as currently used in the DRFA fuel design.
" ZIRLOTM instrument tube as currently used in the DRFA fuel design.
" ZIRLO TM fuel rod cladding as currently used in the DRFA fuel design.
" Debris mitigation features will replace the long end cap DRFA design by:
- Debris filter bottom nozzle (DFBN)
- Zirconium Dioxide (ZrO 2) coated cladding on lower portion of the fuel rod will be added.
Based on the design changes between the DRFA fuel design and the UPGRADE fuel design, and the potential changes in the operational characteristics of the UPGRADE fuel in the Cycle 25 core, the following tests will be reported in the Unit 3 Cycle 25 Startup Test Report.
- 1. Rod Drop Test, due to a change in the guide thimbles.
- 2. RCS Flow Verification, due to a change in the hydraulic characteristic from grid and bottom nozzle differences.
- 3. Low Power Physics Testing, due to nuclear characteristic changes associated with overall assembly design.
- 4. Power Ascension Testing, due to nuclear characteristic changes associated with overall assembly design.
ROD DROP TEST The rod drop time verification was performed to satisfy the requirements of TS 3.1.3.4 which requires that after reactor vessel head removal, maintenance or modification to the Control Rod Drive System (only specific rods) and at least once per 18 months, the rod drop time for all full length rods shall be determined to be less than or equal to 2.4 seconds. For Cycle 25, the placement of the UPGRADE fuel assemblies under rod cluster control assembly (RCCA) locations was limited to positions G5, E7, E9, G11, J1 1, L9, L7 and J5. The rod drop times for these RCCA's were compared to rod drop times for the other RCCA locations containing DRFA fuel assemblies in Cycle 25. The comparison was also performed for Cycles 22 to 24 where all RCCA locations contained DRFA fuel assemblies. The results indicate negligible differences in rod drop times of the UPGRADE fuel assemblies vs. DRFA fuel assemblies and the Rod Drop Test TS requirement is met for Cycle 25 for all RCCAs.
Attachment to L-2011-019 Page 3 of 5 REACTOR COOLANT SYSTEM (RCS) FLOW VERIFICATION The RCS flow verification was performed to satisfy the TS 4.2.5.4 which requires that after each fuel loading and at least once per 18 months, the RCS flow rate be determined by precision heat balance after exceeding 90% power. In addition, TS 3.2.5 requires that the measured RCS flow be greater than or equal to 264,000 gpm. On 1/26/11, this test was conducted. The measured RCS flow was approximately 287,317 gpm, which is similar to the measured RCS flow in recent cycles, and meets the TS requirement.
LOW POWER PHYSICS TESTING
SUMMARY
Low Power Physics Testing was performed in accordance with the following general sequence:
- 1. Initial Criticality: Criticality was achieved by withdrawing all shutdown and control banks and diluting to critical.
- 2. Zero Power Test Range Determination: This was determined after the point of adding heat had been demonstrated.
- 3. On-line Verification of the Reactivity Computer: This was determined by examining the output of the reactivity computer during rod withdrawal and the determination of the point of adding heat.
- 4. Boron Endpoint Measurement: This was determined with all the Control and Shutdown banks withdrawn using the reactivity computer.
- 5. Rod Worth Measurement: Individual control bank and shutdown bank worths were measured using the rod swap technique. The highest worth bank was measured using the boron dilution technique.
- 6. Isothermal Temperature Coefficient Measurement (ITC): This was determined using the reactivity computer during a reactor coolant temperature change. The Moderator Temperature Coefficient (MTC) was calculated from the ITC Data.
All acceptance criteria were met as can be seen in the table below. The Low Power Physics Data fidelity with predictions for Cycle 25 is similar to recent Unit 3 cycles.
Attachment to L-2011-019 Page 4 of 5 LOW POWER PHYSICS RESULTS: UNIT 3 CYCLE 25 ITEM MEASURED PREDICTED DIFFERENCE CRITERIA (M-P)
BORON END POINT:
HZP ALL RODS OUT (ppm) 1605 1628 -23 + 50 ALL RODS OUT ITC (pcm/°F) -2.214 -2.947 0.733 +/-2 ALL RODS OUT MTC (pcm/fF) -0.506 -1.239 CONTROL BANK ROD WORTHS: (pcm)
A 1147 1176 -29(-2.5%)
B 275 274 +1 (+0.4%)
C 1403 1411 -8(-0.6%) 100 pcm or D 681 707 -26 (-3.7%) 15%
SA 1085 1090 -5 (-0.5%)
SB 1197 1222 -25(-2.0%)
TOTAL 5788 5880 -92 (-1.6%) + 7%
POWER ASCENSION TESTING
SUMMARY
Thermal-hydraulic parameters, nuclear parameters and related instrumentation were monitored throughout the power ascension. Data was compared to previous cycle power ascension data and engineering predictions, as required, at each test plateau to identify calibration or system problems. Power changes were governed by operating procedures and fuel preconditioning guidelines.
Flux mapping was performed at approximately 30%, 50% and 100% rated thermal power (RTP) using the Movable Incore Detector System. The resultant peaking factors and power distribution were compared to Technical Specification limits to verify that the core was operating within its design limits. All analysis limits were met. The flux map results are shown in the table below. Also shown in the table is a comparison of FAH to design predictions. The results show that the measured to predicted fidelity for Cycle 25 is very good and is similar to recent Unit 3 cycles. In addition, incore tilt and radial power distribution fidelity is also good and similar to recent Unit 3 cycles.
Attachment to L-2011-019 Page 5 of 5 POWER ASCENSION FLUX MAP RESULTS: UNIT 3 CYCLE 25 ITEM MAP 1 MAP 2 MAP 3 DATE OF MAP 11/09/10 11/10/10 11/29/10 POWER LEVEL (%) 28.9 48.2 99.9 CONTROL BANK D 157 168 228 POSITION (steps)
Predicted FAH 1.518 1.497 1.470 (from map)
FAH 1.525 1.504 1.476 FAH Difference 0.5 0.5 0.4 (M-P in %)
INCORE TILT 0.9921 0.9951 1.0052 MAXIMUM MEASURED TO -2.9 +3.0 -2.9 PREDICTED ASSEMBLY POWER DIFFERENCE (%)
RMS MEASURED TO PREDICTED 1.14 0.99 0.72 ASSEMBLY POWER DIFFERENCE (%) I
4.0 CONCLUSION
S As demonstrated in this report, the transition from DRFA fuel with 6" natural uranium annular blankets to UPGRADE fuel with 8" natural uranium annular blankets in the Turkey Point Unit 3 Cycle 25 core has resulted in no increased deviation from predicted core design behavior with all operating and surveillance criteria met.