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Category:Fuel Cycle Reload Report
MONTHYEARRA24-006, Cycle 21 Core Operating Limits Reports2024-03-11011 March 2024 Cycle 21 Core Operating Limits Reports RA23-019, Cycle 20 Core Operating Limits Reports2023-03-21021 March 2023 Cycle 20 Core Operating Limits Reports RA22-041, Unit 2 Cycle 19 Core Operating Limits Report Revision2022-10-0505 October 2022 Unit 2 Cycle 19 Core Operating Limits Report Revision RA22-010, Cycle 20 Core Operating Limits Reports2022-03-21021 March 2022 Cycle 20 Core Operating Limits Reports RA21-043, Cycle 19 Startup Test Report Summary2021-07-15015 July 2021 Cycle 19 Startup Test Report Summary RA21-019, Unit 2 Cycle 19 Core Operating Limits Reports2021-04-0707 April 2021 Unit 2 Cycle 19 Core Operating Limits Reports RA20-044, Unit 2 - Unit 1 Cycle 19 Core Operating Limits Report2020-09-10010 September 2020 Unit 2 - Unit 1 Cycle 19 Core Operating Limits Report RA20-014, Cycle 19 and Cycle 18 Core Operating Limits Reports2020-03-12012 March 2020 Cycle 19 and Cycle 18 Core Operating Limits Reports ML20072K1502020-03-12012 March 2020 Unit 2 - Unit 1 Cycle 19 and Unit 2 Cycle 18 Core Operating Limits Reports RA19-021, Cycle 18 Core Operating Limits Report (COLR)2019-03-21021 March 2019 Cycle 18 Core Operating Limits Report (COLR) RA18-016, Cycle 18 Core Operating Limits Report (COLR)2018-03-22022 March 2018 Cycle 18 Core Operating Limits Report (COLR) RA-17-029, Cycle 17 Core Operating Limits Report (COLR)2017-03-17017 March 2017 Cycle 17 Core Operating Limits Report (COLR) ML16193A5952016-07-0808 July 2016 Cycle 16, Revision 4 Core Operating Limits Report RA16-011, Cycle 17 Core Operating Limits Report (COLR)2016-03-10010 March 2016 Cycle 17 Core Operating Limits Report (COLR) RA15-079, Cycle 16 Core Operating Limits Report (COLR)2015-11-19019 November 2015 Cycle 16 Core Operating Limits Report (COLR) RA15-047, Cycle Core Operating Limits Report (COLR)2015-08-12012 August 2015 Cycle Core Operating Limits Report (COLR) RA15-020, Cycle 16 Core Operating Limits Report (COLR)2015-04-10010 April 2015 Cycle 16 Core Operating Limits Report (COLR) RA15-016, Cycle 16 Core Operating Limits Report (COLR)2015-04-10010 April 2015 Cycle 16 Core Operating Limits Report (COLR) RA14-025, Cycle 16 Startup Test Report Summary2014-04-25025 April 2014 Cycle 16 Startup Test Report Summary RA13-053, Core Operating Limits Report, Cycle 15, Revision 12013-08-28028 August 2013 Core Operating Limits Report, Cycle 15, Revision 1 RA13-010, Core Operating Limits Report, Cycle 15, Revision 02013-03-0606 March 2013 Core Operating Limits Report, Cycle 15, Revision 0 RA13-012, Unit 1 Cycle 15 Core Operating Limits Report (COLR)2013-02-13013 February 2013 Unit 1 Cycle 15 Core Operating Limits Report (COLR) RA12-012, Core Operating Limits Report, Cycle 15, Revision 1. (Non-Proprietary)2012-03-0808 March 2012 Core Operating Limits Report, Cycle 15, Revision 1. (Non-Proprietary) RA12-010, Core Operating Limits Report for LaSalle Unit 1 Cycle 15, Revision 0 (Non-proprietary)2012-03-0606 March 2012 Core Operating Limits Report for LaSalle Unit 1 Cycle 15, Revision 0 (Non-proprietary) RA11-016, Cycle 14 Core Operating Limits Report (COLR)2011-02-25025 February 2011 Cycle 14 Core Operating Limits Report (COLR) RA10-061, Unit 1 Cycle 14, Revision 1 Core Operating Limits Report (COLR)2010-09-23023 September 2010 Unit 1 Cycle 14, Revision 1 Core Operating Limits Report (COLR) RA10-022, Cycle 14 Startup Test Report Summary2010-04-23023 April 2010 Cycle 14 Startup Test Report Summary L-88-016, Submittal of Unit 1 Cycle 14 Core Operating Limits Report (COLR)2010-02-25025 February 2010 Submittal of Unit 1 Cycle 14 Core Operating Limits Report (COLR) RA09-002, Cycle 3 Core Operating Limits Report2009-02-0606 February 2009 Cycle 3 Core Operating Limits Report RA08-059, Cycle 12, Revision 3 Core Operating Limits Report (COLR)2008-09-0303 September 2008 Cycle 12, Revision 3 Core Operating Limits Report (COLR) RA08-008, Cycle 13 Core Operating Limits Report (COLR)2008-03-17017 March 2008 Cycle 13 Core Operating Limits Report (COLR) RA07-081, Cycle 12, Revision 4 Core Operating Limits Report (COLR)2007-09-12012 September 2007 Cycle 12, Revision 4 Core Operating Limits Report (COLR) RA07-071, Cycle 12, Revision 3 and Unit 2 Cycle 12, Revision 1, Core Operating Limits Report (COLR)2007-08-0707 August 2007 Cycle 12, Revision 3 and Unit 2 Cycle 12, Revision 1, Core Operating Limits Report (COLR) ML0710902502007-04-13013 April 2007 Cycle 12 Core Operating Limits Report (COLR) ML0509604612005-03-30030 March 2005 Nonproprietary Version of LaSalle Unit 2, Cycle 11 Core Operating Limits Report, Revision 0 ML0407700792004-01-20020 January 2004 to Section 1 of Core Operating Limits Report for LaSalle, Unit 1, Cycle 11. ML0402600112004-01-16016 January 2004 Revised LaSalle County Station, Unit 2 Cycle 10 Core Operating Limits Report (COLR) ML0334304982003-11-26026 November 2003 Cycle 10 Core Operating Limits Report ML0319500772003-07-0303 July 2003 Cycle 10A Core Operating Limits Report (COLR) ML0229405432002-10-15015 October 2002 Cycle 9 Core Operating Limits Report, Amendment 49, Section 4.0, Attachments 4-8, Figure 12 ML0229405322002-10-15015 October 2002 Cycle 9 Core Operating Limits Report, Amendment 49, Sections 1 and 2 ML0219203842002-07-0303 July 2002 Unit 1 Cycle 10 Core Operating Limits Report (Colr), Section 1, Table of Contents - List of Tables ML0219204022002-07-0303 July 2002 Unit 1 Cycle 10 Core Operating Limits Report (Colr), LaSalle Unit 1 Cycle 10, Plant Transient Analysis, Figures - References ML0206004562002-02-0606 February 2002 LaSalle County, Unit 1 - Cycle 10 Reload and Core Operating Limits Report 2024-03-11
[Table view] Category:Letter type:RA
MONTHYEARRA24-008, Post-Outage Inservice Inspection (ISI) Summary Report2024-06-20020 June 2024 Post-Outage Inservice Inspection (ISI) Summary Report RA24-023, Response to NRC LaSalle County Station, Units 1 and 2, Integrated Inspection Report 05000373/2024001 and 05000374/20240012024-06-12012 June 2024 Response to NRC LaSalle County Station, Units 1 and 2, Integrated Inspection Report 05000373/2024001 and 05000374/2024001 RA24-011, 2023 Annual Radiological Environmental Operating Report2024-05-0303 May 2024 2023 Annual Radiological Environmental Operating Report RA24-009, 2023 Annual Radioactive Effluent Release Report2024-04-26026 April 2024 2023 Annual Radioactive Effluent Release Report RA24-010, Annual Dose Report for 20232024-04-24024 April 2024 Annual Dose Report for 2023 RA24-006, Cycle 21 Core Operating Limits Reports2024-03-11011 March 2024 Cycle 21 Core Operating Limits Reports RA23-072, Regulatory Commitment Change Summary Report2023-12-15015 December 2023 Regulatory Commitment Change Summary Report RA23-057, Registration of Use of Cask to Store Spent Fuel2023-08-11011 August 2023 Registration of Use of Cask to Store Spent Fuel RA23-055, Registration of Use of Cask to Store Spent Fuel2023-08-11011 August 2023 Registration of Use of Cask to Store Spent Fuel RA23-052, Registration of Use of Cask to Store Spent Fuel2023-08-0404 August 2023 Registration of Use of Cask to Store Spent Fuel RA23-051, Registration of Use of Cask to Store Spent Fuel2023-07-21021 July 2023 Registration of Use of Cask to Store Spent Fuel RA23-048, Registration of Use of Cask to Store Spent Fuel2023-07-14014 July 2023 Registration of Use of Cask to Store Spent Fuel RA23-045, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2023-06-30030 June 2023 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation RA23-047, Registration of Use of Cask to Store Spent Fuel2023-06-30030 June 2023 Registration of Use of Cask to Store Spent Fuel RA23-018, Post-Outage Inservice Inspection (ISI) Summary Report2023-06-27027 June 2023 Post-Outage Inservice Inspection (ISI) Summary Report RA23-046, Registration of Use of Cask to Store Spent Fuel2023-06-23023 June 2023 Registration of Use of Cask to Store Spent Fuel RA23-042, Registration of Use of Cask to Store Spent Fuel2023-06-16016 June 2023 Registration of Use of Cask to Store Spent Fuel RA23-029, 2022 Annual Radiological Environmental Operating Report2023-05-12012 May 2023 2022 Annual Radiological Environmental Operating Report RA23-028, Submittal of 2022 Annual Radioactive Effluent Release Report2023-04-28028 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report RA23-027, Annual Dose Report for 20222023-04-21021 April 2023 Annual Dose Report for 2022 RA23-025, Post Accident Monitoring Report2023-04-0707 April 2023 Post Accident Monitoring Report RA23-013, Submittal of Triennial Chlorine Survey Report2023-03-30030 March 2023 Submittal of Triennial Chlorine Survey Report RA23-019, Cycle 20 Core Operating Limits Reports2023-03-21021 March 2023 Cycle 20 Core Operating Limits Reports RA22-066, 150 Day Submittal Cover Letter2022-12-0202 December 2022 150 Day Submittal Cover Letter RA22-060, Regulatory Commitment Change Summary Report2022-11-30030 November 2022 Regulatory Commitment Change Summary Report RA22-051, Submittal of the Snubber Program Plan for the Fourth 10-Year Interval2022-11-16016 November 2022 Submittal of the Snubber Program Plan for the Fourth 10-Year Interval RA22-041, Unit 2 Cycle 19 Core Operating Limits Report Revision2022-10-0505 October 2022 Unit 2 Cycle 19 Core Operating Limits Report Revision RA22-029, Cycle 20 Startup Test Report Summary2022-06-10010 June 2022 Cycle 20 Startup Test Report Summary RA22-021, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report2022-06-0808 June 2022 Post-Outage 90-Day Inservice Inspection (ISI) Summary Report RA22-020, Annual Radiological Environmental Operating Report2022-05-13013 May 2022 Annual Radiological Environmental Operating Report RA22-018, Annual Dose Report for 20212022-04-22022 April 2022 Annual Dose Report for 2021 RA22-010, Cycle 20 Core Operating Limits Reports2022-03-21021 March 2022 Cycle 20 Core Operating Limits Reports RA21-059, Regulatory Commitment Change Summary Report2021-11-30030 November 2021 Regulatory Commitment Change Summary Report RA21-050, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2021-11-0909 November 2021 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation RA21-051, County Station Physical Security Plan (Revision 18)2021-09-29029 September 2021 County Station Physical Security Plan (Revision 18) RA21-052, Registration of Use of Cask Store Spent Fuel2021-09-17017 September 2021 Registration of Use of Cask Store Spent Fuel RA21-046, Registration of Use of Cask to Store Spent Fuel2021-08-0505 August 2021 Registration of Use of Cask to Store Spent Fuel RA21-043, Cycle 19 Startup Test Report Summary2021-07-15015 July 2021 Cycle 19 Startup Test Report Summary RA21-031, 2020 Annual Radiological Environmental Operating Report2021-05-13013 May 2021 2020 Annual Radiological Environmental Operating Report RA21-029, Unit 2 - 2020 Annual Radioactive Effluent Release Report2021-04-29029 April 2021 Unit 2 - 2020 Annual Radioactive Effluent Release Report RA21-026, Annual Dose Report for 20202021-04-22022 April 2021 Annual Dose Report for 2020 RA21-016, Netco Rack Insert 10-year Surveillance Report2021-04-15015 April 2021 Netco Rack Insert 10-year Surveillance Report RA21-017, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report2021-04-0909 April 2021 Post-Outage 90-Day Inservice Inspection (ISI) Summary Report RA21-019, Unit 2 Cycle 19 Core Operating Limits Reports2021-04-0707 April 2021 Unit 2 Cycle 19 Core Operating Limits Reports RA20-058, Licensee Post Exam Submittal Letter2020-12-0202 December 2020 Licensee Post Exam Submittal Letter RA20-044, Unit 2 - Unit 1 Cycle 19 Core Operating Limits Report2020-09-10010 September 2020 Unit 2 - Unit 1 Cycle 19 Core Operating Limits Report RA20-026, 2019 Annual Radiological Environmental Operating Report2020-05-13013 May 2020 2019 Annual Radiological Environmental Operating Report RA20-023, Annual Dose Report for 20192020-04-28028 April 2020 Annual Dose Report for 2019 RA20-016, Corrected Drawing for One-Line Electrical Power Supply for Containment Vent System Final Integrated Plan2020-03-24024 March 2020 Corrected Drawing for One-Line Electrical Power Supply for Containment Vent System Final Integrated Plan RA20-015, Triennial Chlorine Survey Report2020-03-20020 March 2020 Triennial Chlorine Survey Report 2024-06-20
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LaSalle County Station Exelon Generation , 2601 North 21 ** Road Marseilles. IL 61341 815-415-2000 Telephone www.exeloncorp com RA21-043 July 15, 2021 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 LaSalle County Station, Unit 2 Renewed Facility Operating License No. NPF-18 NRC Docket No. 50-374
Subject:
LaSalle 2 Cycle 19 Startup Test Report Summary Enclosed for your information is the LaSalle County Station (LSCS) Unit 2 Cycle 19 Startup Test Report. This report is submitted in accordance with Technical Requirements Manual Section 5.0.b.
LaSalle County Station Unit 2 Cycle 19 began operation on April 17, 2021, following a refueling and maintenance outage. The Unit 2 Cycle 19 core loading consisted of 276 fresh Global Nuclear Fuel GNF-3 fuel bundles, 276 once-burned Global Nuclear Fuel GNF-2 fuel bundles, and 212 twice-burned Global Nuclear Fuel GNF-2 fuel bundles. Also installed in the Unit 2 Cycle 19 reactor were 8 new GE/Reuter-Stokes NA-300 Local Power Range Monitors (LPRMs), and 12 new General Electric Ultra HD Control Rod blades and 2 new General Electric Ultra MD Control Rod blades.
Attached are the evaluation results from the following tests:
- Reactor Core Verification
- Control Rod Friction and Settle Testing
- Control Rod Drive Timing
- Shutdown Margin Test (In-sequence critical)
- Reactivity Anomaly Calculation (Critical and Full Power)
- Scram Insertion Times
- Core Power Distribution Symmetry Analysis
- Reactor Recirculation System Performance
July 15, 2021 U.S. Nuclear Regulatory Commission Page 2 All test data was reviewed in accordance with the applicable test procedures, and exceptions to any results were evaluated to verify compliance with Technical Specification limits and to ensure the acceptability of subsequent test results.
There are no regulatory commitments in this letter. Should you have any questions concerning this report, please contact Mr. Daniel Mearhoff, Regulatory Assurance Manager, at (815) 415-2800.
Respectfully, i~,v(__.,
Jo shko Site resident LaSalle County Station Attachment cc: Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - LaSalle County Station
ATTACHMENT Page 1 of 8 Reactor Core Verification Purpose The purpose of this test is to visually verify that the core is loaded as intended for Unit 2 Cycle 19 operation.
Criteria The as loaded core must conform to the cycle core design used by the Core Management Organization (GNF & Nuclear Fuels) in the reload licensing analysis. Any discrepancies discovered in the loading will be promptly corrected and the affected areas re-verified to ensure proper core loading prior to unit startup.
Conformance to the cycle core design will be documented by a permanent core serial number map signed by the audit participants.
Results and Discussion Core verification was performed concurrently with core load and shuffle the guidance in NF-AA-330-1001, "Core Verification Guideline." The Unit 2 Cycle 19 core verification consisted of a core height, assembly orientation, assembly location, and assembly seating check. Bundle serial numbers and orientations were recorded during the video recorded scans for comparison to the appropriate core loading map and Cycle Management documentation. The core was verified as being properly loaded and consistent with the LaSalle 2 Cycle 19 Core Loading Plan, Revision 8. This was documented in work order (WO)# 4902283-01.
ATTACHMENT Page 2 of 8 Control Rod Friction and Settle Testing Purpose The purpose of this test is to demonstrate that excessive friction does not exist between the Control Rod Blade and the fuel assemblies during operation of the Control Rod Drive (CRD) following core alterations.
Criteria Appropriate acceptance criteria are provided in LOS-RD-SR?, "Channel Interference Monitoring" and include limits on rod settle time. The control rod settle test acceptance criterion is less than or equal to 7 seconds.
Results and Discussion CRD Friction Testing commenced after the completion of the core load verification and single rod subcritical check. All 185 control rods settled in less than 4.4 seconds, which is documented in WO# 4902211-01.
ATTACHMENT Page 3 of 8 Control Rod Drive Timing Purpose The purpose of this test is to check and set the insert and withdrawal speeds of the Control Rod Drives (CRDs).
Criteria LOS-RD-SR5, "Control Rod Drive Timing," preferred beginning of cycle acceptance criteria for the withdraw times (full-in to full-out) is between 45 and 60 seconds and insert times (full-out to full-in) is between 40 and 55 seconds.
Results and Discussion Control rod timing per LOS-RD-SR5 was performed satisfactorily for all 185 CRDMs and is documented in WO# 4902820-01. None of the rod withdrawal speeds were faster or slower than the LOS-RD-SR5 preferred criteria.
ATTACHMENT Page 4 of 8 Shutdown Margin Test Purpose The purpose of this test is to demonstrate, from a normal in-sequence critical, that the core loading has been limited such that the reactor will remain subcritical throughout the operating cycle with the strongest worth Control Rod in the full-out position and all other rods fully inserted.
Criteria In accordance with LTS-1100-1, "Shutdown Margin Determination" and Technical Specifications, if a shutdown margin (SOM) of 0.38% Llk/k + R cannot be demonstrated with the strongest worth Control Rod fully withdrawn, the core loading must be altered to meet this margin. R is the reactivity difference between the core's beginning of cycle SDM and the minimum SDM for the cycle. The R value for Cycle 19 is 0.00% Llk/k per the LaSalle Unit 2 Cycle 19 Cycle Management Report, Revision 7, so a SDM of 0 .38% Llk/k must be demonstrated.
Results and Discussion The beginning of cycle SOM was successfully determined from the initial critical data. The initial Cycle 19 critical occurred on April 17, 2021, on Control Rod 14-19 at position 16, using an A2 sequence. The moderator temperature was 153 °F and the reactor period was 303 seconds. Using LTS-1100-1 and the LaSalle Unit 2 Cycle 19 Cycle Management Report, Revision 7, the SOM was determined to be
- 1. 732% Llk/k. This was documented rn L TS-1100-1 , Attachment A and WO# 4902281-
- 01. The SDM was greater than the minimum 0.38% Llk/k that is required to satisfy the Technical Specifications.
ATTACHMENT Page 5 of 8 Reactivity Anomaly Determination Purpose The purpose of this test is to compare the actual and predicted critical rod configurations to detect any unexpected reactivity trends.
Criteria In accordance with NF-LA-715 "Critical Predictions with 3D Monicore," NF-AB-760 "Reactivity Anomaly Determination," and Technical Specifications, the reactivity equivalence of the difference between the actual critical Control Rod configuration and the predicted critical Control Rod configuration and the difference between the actual and predicted reactivity of the Control Rod configuration at full power steady state conditions shall not exceed 1% Lik/k. If the difference exceeds 1% Lik/k, the cause of the anomaly must be determined, explained, and corrected for continued operation of the unit.
Results and Discussion Two reactivity anomaly calculations were successfully performed during the Unit 2 Cycle 19 Startup Test Program. One reactivity anomaly calculation is from the in-sequence critical and the other is from steady state, equilibrium conditions at approximately 100% full power.
The initial Cycle 19 critical occurred on April 17, 2021, on Control Rod 14-19 at position 16, using an A2 sequence. The moderator temperature was 153 °F and the reactor period was 303 seconds. The expected kett supplied by Nuclear Fuels was 1.0025. The actual kett was 1.00482. The resulting anomaly was 0.232% Lik/k. The anomaly determined is within the 1% Lik/k required for BOC conditions as stated in NF-LA-715. This was documented in NF-LA-715, Attachment 3 and WO# 4902273-01.
The reactivity anomaly calculation for full power steady state operation was performed.
The data used was from 99.8% power at a cycle exposure of 316.3 MWD/sT at equilibrium conditions. The expected kett supplied by Nuclear Fuels was 1.0080. The actual kett was 1.0077. The resulting anomaly was 0.03% Lik/k. This value is within the 1% Lik/k criteria of Technical Specifications. This was documented in NF-AB-760, , and WO# 4902282-01.
ATTACHMENT Page 6 of 8 Scram Insertion Times Purpose The purpose of this test is to demonstrate that the Control Rod scram insertion times are within the operating limits set forth by the Technical Specifications.
Criteria In accordance with LOS-RD-SR12, "Scram Insertion Times," and Technical Specifications, the maximum scram insertion time of each Control Rod from the fully withdrawn position (48) to notch position 05, based on de-energization of the scram pilot valve solenoids as time zero , shall not exceed 7.0 seconds. Also, no more than 12 OPERABLE Control Rods shall be "slow" in accordance with the below table. In addition, no more than 2 Operable Control Rods that are "slow" shall occupy adjacent locations.
When the scram insertion time of an operable Control Rod from the fully withdrawn position (48), based on de-energization of the scram pilot valve solenoids as time zero, exceeds any of the following, that Control Rod is considered "slow":
Notch Position Scram Time to Notch Indicated (seconds) 45 0.52 39 0.80 25 1.77 05 3.20 Results and Discussion Scram testing was performed per WO# 4902192-01 . Results of testing are given below.
Notch Position Core Average Scram Times of all CRDs (sec) 45 0.302 39 0.585 25 1.261 05 2.278 Once SCRAM Timing was complete, there were no slow rods. These results also meet the "Option B" Scram Speeds referenced in the Unit 2 Cycle 19 Core Operating Limits Report (TRM Appendix J).
ATTACHMENT Page 7 of 8 Core Power Distribution Symmetry Analysis Purpose The purpose of this test is to verify the core power symmetry.
Criteria In accordance with NF-AB-707, "3D Monicore - Operation and Maintenance," the TIP uncertainty value must be less than 6%.
Results and Discussion Core power symmetry calculations were obtained based upon data obtained from a full core TIP set (OD1) at approximately 100% power. The TIP uncertainty value was 2.80%. This was documented in WO# 5108272-01.
ATTACHMENT Page 8 of 8 Recirculation System Performance Purpose The purpose of this test is to collect sufficient baseline data at the beginning of cycle to establish the following relationships:
- core thermal power vs. total core flow
- recirculation total drive flow vs. total core flow
- core plate flow vs. total core flow
- recirculation flow control valve position vs. loop drive flow
- jet pump readings vs. loop drive flow Criteria In accordance with LTP-1600-13 "Recirculation System Performance" and Technical Specifications, the performance curves used in conjunction with reactor recirculation system flow and differential pressure data will establish baseline data to determine if possible jet pump or recirculation pump degradation exists.
The established baseline performance curves will also be used to verify jet pump operability to determine if jet pump anomalies exist.
Results and Discussion Reactor Recirculation data was collected during the L2C19 startup. Data was obtained from computer points for all the points of interest to evaluate the RR System performance . The RR performance curves were updated for L2C19; jet pump performance was improved in the jet pumps that had foreign material removed in comparison to L2C18 . This is documented in WO# 4904311-01 .