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MONTHYEARML12258A0802012-09-14014 September 2012 NRC Conference Call St. Lucie Unit 2 Steam Generator Inspection September 13, 2012 Project stage: Request ML13059A5522013-03-0101 March 2013 3/14/13 - Forthcoming Meeting with Florida Power and Light Company Regarding Steam Generator Performance at St. Lucie Nuclear Plant, Units 1 and 2 Project stage: Request ML13094A1812013-03-14014 March 2013 Meeting Handout - Operational Assessment for Cycle 20 Project stage: Meeting ML13094A1932013-03-14014 March 2013 Meeting Handout - Independent Operational Assessment Project stage: Meeting ML13094A1912013-03-14014 March 2013 Meeting Handout - Results of Fall 2012 Inspection Project stage: Meeting ML13084A0302013-04-0404 April 2013 9/13/2012 - Summary of Conference Call with Florida Power & Light Co. Re. the Findings of the Fall 2012 Steam Generator Tube Inspections at Saint Lucie Plant, Unit No. 2 Project stage: Other ML13095A3472013-04-11011 April 2013 3/14/2013 - Summary of Meeting with Florida Power & Light Co., to Discuss Insights About the Performance of the Steam Generators at St. Lucie Plant, Unit No. 2 After Three Operating Cycles Project stage: Meeting 2013-03-14
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Category:Meeting Briefing Package/Handouts
MONTHYEARML24305A2002024-11-0404 November 2024 Pre-Submittal Meeting - St. Lucie, Unit 1 - Criticality Analysis for Transition to 24-Month Fuel Cycle (L-2023-LRM-0122) ML24099A2142024-04-10010 April 2024 Presentation Material for April 10th Presubmittal Meeting on Proposed 24 Month Cycle Submittal ML24073A3372024-03-13013 March 2024 NextEra - NRC Slides for the Public Meeting on March 19, 2024 Regarding Emergency Plan Licensing Amendment ML23124A3412023-05-0404 May 2023 FPL 2022 Public Meeting Slides ML21320A2612021-11-17017 November 2021 Supporting Information for Turkey Point and St. Lucie Improved Technical Specifications November 17, 2021, Public Meeting - List of Topics ML21302A0792021-11-0303 November 2021 November 3, 2021, St. Lucie Plant, Units 1 and 2, Subsequent License Renewal Application Public Environmental Scoping Meeting Slides ML21225A0012021-08-18018 August 2021 Preapplication Meeting Presentation Improved Technical Specifications Conversion ML21153A0522021-06-0202 June 2021 Psl SLRA Preapplication Meeting 06-03-21 ML21139A3002021-05-20020 May 2021 5-20-21 St. Lucie Plant, Units 1 & 2, Subsequent License Renewal Environmental Pre-Application Meeting Florida Power and Light Slides ML21111A0122021-04-21021 April 2021 Subsequent License Renewal Application - Pre-Application Meeting ML21109A0052021-04-19019 April 2021 2020 - Stl - Tpn Combined EOC Presentation ML21106A1692021-04-16016 April 2021 SLRA - NRC Presubmittal Meeting Slides ML20135F6652020-05-14014 May 2020 Stl - Tpn Combined EOC Presentation ML20080M1532020-02-21021 February 2020 PFHA-2020-3B-1-Hanna-Briefing_on_STL Flooding-rev0 ML18122A1502018-04-30030 April 2018 Pre-Submittal Meeting for St. Lucie Nuclear Plant, Unit 2 - Spent Fuel Pool Criticality Analyses - April 30, 2018 ML17072A3762017-03-21021 March 2017 Regulatory Conference on 3/21/2017 Licensee Presentation ML16097A1302016-04-0404 April 2016 March 29, 2016 Summary of Public Meeting - 2015 Annual Assessment Regarding Saint Lucie ML15086A2232015-03-27027 March 2015 Summary of Meeting Concerning the Annual Assessment of St. Lucie Nuclear Plant, Units 1 and 2 ML14174A4022014-06-24024 June 2014 6/24/2014, Pre-Submittal Meeting Slide for St. Lucie and Turkey Point Re. License Amendment Request Adoption of TSTF-505 Risk-Informed Completion Time ML14156A2132014-06-0404 June 2014 Public Meeting Summary - St. Lucie Nuclear Plant Docket Nos. 50-335 and 50-389 ML14147A4152014-05-29029 May 2014 Slide for 5/29/14 Meeting Re. 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[Table view] Category:Slides and Viewgraphs
MONTHYEARML24305A2002024-11-0404 November 2024 Pre-Submittal Meeting - St. Lucie, Unit 1 - Criticality Analysis for Transition to 24-Month Fuel Cycle (L-2023-LRM-0122) ML24103A1042024-04-25025 April 2024 St. Lucie/Turkey Point 2023 Annual Assessment Meeting Slides ML24099A2142024-04-10010 April 2024 Presentation Material for April 10th Presubmittal Meeting on Proposed 24 Month Cycle Submittal ML24073A3372024-03-13013 March 2024 NextEra - NRC Slides for the Public Meeting on March 19, 2024 Regarding Emergency Plan Licensing Amendment ML23310A1552023-11-0909 November 2023 Presentation Material (Slides) - Presubmittal Meeting - St. Lucie, Unit 2 - Criticality Analysis for Transition to 24-Month Fuel Cycle ML23124A3412023-05-0404 May 2023 FPL 2022 Public Meeting Slides ML22311A5332022-11-10010 November 2022 Presentation Material for Presubmittal Meeting (11/10/22) St. Lucie Nuclear Plant, Units 1 and 2 to Adopt 50.69 Risk-Informed Categorization and Treatment of Structures, Systems and Components ML22301A1662022-09-29029 September 2022 Presentation 4 - Recent Biennial PI&R Team Inspection Insights ML22110A2172022-05-0303 May 2022 Annual Assessment Meeting ML21302A0792021-11-0303 November 2021 November 3, 2021, St. Lucie Plant, Units 1 and 2, Subsequent License Renewal Application Public Environmental Scoping Meeting Slides ML21225A0012021-08-18018 August 2021 Preapplication Meeting Presentation Improved Technical Specifications Conversion ML21153A0522021-06-0202 June 2021 Psl SLRA Preapplication Meeting 06-03-21 ML21139A3002021-05-20020 May 2021 5-20-21 St. Lucie Plant, Units 1 & 2, Subsequent License Renewal Environmental Pre-Application Meeting Florida Power and Light Slides ML21139A3072021-05-20020 May 2021 5-20-21 St. Lucie Plant, Units 1 & 2 - Subsequent License Renewal Environmental Pre-Application Meeting NRC Slides ML21111A0122021-04-21021 April 2021 Subsequent License Renewal Application - Pre-Application Meeting ML21109A0052021-04-19019 April 2021 2020 - Stl - Tpn Combined EOC Presentation ML21106A1692021-04-16016 April 2021 SLRA - NRC Presubmittal Meeting Slides ML21076A6152021-03-22022 March 2021 NRC Pre-Submittal Meeting, St. Lucie and Turkey Point Nuclear Plants - Improved Technical Specification Conversion - March 22, 2021 (EPID L-2021-LRM-0032) (Presentation) ML20135F6652020-05-14014 May 2020 Stl - Tpn Combined EOC Presentation ML20080M1532020-02-21021 February 2020 PFHA-2020-3B-1-Hanna-Briefing_on_STL Flooding-rev0 ML18144A1452018-05-24024 May 2018 Public Meeting Summary - St. Lucie Nuclear Plant Docket Nos. 50-335 and 50-389 ML17310B2322017-11-0707 November 2017 Presentation Slides - NextEra Energy/Fpl - GSI-191 Issue Resolution, Pre-submittal Meeting, September 20, 2017 ML17072A3762017-03-21021 March 2017 Regulatory Conference on 3/21/2017 Licensee Presentation ML16097A1302016-04-0404 April 2016 March 29, 2016 Summary of Public Meeting - 2015 Annual Assessment Regarding Saint Lucie ML15086A2232015-03-27027 March 2015 Summary of Meeting Concerning the Annual Assessment of St. Lucie Nuclear Plant, Units 1 and 2 ML14174A4022014-06-24024 June 2014 6/24/2014, Pre-Submittal Meeting Slide for St. Lucie and Turkey Point Re. License Amendment Request Adoption of TSTF-505 Risk-Informed Completion Time ML14156A2132014-06-0404 June 2014 Public Meeting Summary - St. Lucie Nuclear Plant Docket Nos. 50-335 and 50-389 ML14147A4152014-05-29029 May 2014 Slide for 5/29/14 Meeting Re. Fuel Transition Project ML13107B4002013-04-17017 April 2013 Summary of Public Meeting, Florida Power & Light, St. Lucie Nuclear Plant ML13094A1912013-03-14014 March 2013 Meeting Handout - Results of Fall 2012 Inspection ML13094A1932013-03-14014 March 2013 Meeting Handout - Independent Operational Assessment ML13094A1812013-03-14014 March 2013 Meeting Handout - Operational Assessment for Cycle 20 ML12326A8162012-11-21021 November 2012 11/9/2012 - Summary of Meeting with the Florida Power and Light Company Regarding the St. Lucie Nuclear Plant ML1111014612011-04-13013 April 2011 Annual Assessment Meeting Slides ML1108206992011-03-22022 March 2011 3/22/11 Revised Pre-application Meeting Slides Regarding NFPA 805 License Amendment Request ML1107703492011-03-22022 March 2011 3/22/11 PRE-Application Meeting Slides Regarding NFPA 805 License Amendment Request ML1102604062011-01-11011 January 2011 FPL Meeting Summary Presentation Handouts IR 05000335/20100072010-11-17017 November 2010 Summary of Public Regulatory Performance Meeting with Florida Power and Light Company to Discuss Corrective Actions Associated with the Yellow Finding That Was Documented in the NRC Inspection Report IR 05000335-10-007 ML1023502322010-08-18018 August 2010 Extended Power Uprate (EPU) NRC Public Meeting ML1013202002010-05-0404 May 2010 Annual Assessment Meeting Presentation ML1011107312010-04-20020 April 2010 Handout for Meeting with Florida Power & Light to Discuss the Status of Fpl'S Employee Concerns Program (ECP) Improvement Initiatives. FPL Presentation on Nuclear Safety Culture ML1006011702010-02-26026 February 2010 Meeting Summary - Category 1 Public Meeting - Regulatory Conference with St. Lucie Nuclear Plant Regarding Issues with the Component Cooling Water - Docket Nos. 50-335 and 50-389 ML0930902742009-11-0505 November 2009 Summary of Public Meeting with Florida Power and Light Company to Discuss Processes for Addressing Employee Concerns. Slides (Enclosure 2) ML0924402562009-08-25025 August 2009 Slides from August 25, 2009 Meeting with Florida Power & Light ML0912702272009-05-0404 May 2009 Hostile Action Based EP Drills - Elements of a Successful Demonstration ML0813304162008-05-12012 May 2008 Enclosure - St. Lucie Annual Assessment Meeting, Reactor Oversight Program - Cy 2007 ML0734106732007-12-0707 December 2007 Florida Department of Environmental Protection Nuclear Presentation Slides, Nuclear Power in Florida. ML0729806642007-10-24024 October 2007 Meeting Presentation on Update on Generic Safety Issue 191 Plant Audits ML0721104042007-07-25025 July 2007 Slides from Exercises 1 Thru 6 from the Generic Risk-Informed Inspection Notebook ML0701100272007-01-10010 January 2007 Notice of Meeting Handouts with FPL Adoption of AST at St. Lucie 2024-04-25
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Text
St. Lucie (PSL) Unit 2 Operational Assessment For Cycle 20 Intertek APTECH Sunnyvale, CA Russ Cipolla March 14, 2013 1
Operational Assessments (OA)
Degradation Mechanisms Evaluated Wear at tube contact with anti-vibration bars (AVB)
Wear at V-Shaped Support Pads (V-SSP)
Wear at Tube Support Plates (TSP)
Tube Integrity Methods EPRI Integrity Assessment Guidelines (IAGL) implemented Flaw Handbook implemented Full bundle probabilistic analysis for AVB wear Deterministic methods used for the other wear mechanisms 2
Operational Assessment Model For AVB Wear Methodology Full bundle probabilistic operational assessment using Monte Carlo simulation method.
Multi-cycle approach which tracks the degradation mechanism over previous inspection intervals at end-of-cycle (EOC) to define the beginning-of-cycle (BOC) 20 wear population (both detected and undetected)
Same basic repair-on-sizing model used for previous cycles (EOC 17 and 18) 3
Operational Assessment Model For AVB Wear Methodology (Contd)
Model and input statistical distributions include:
Tubing strengths (normal distribution)
Probability of detection (log-logistic function)
Wear rate (lognormal distribution)
Degradation lengths (lognormal distribution)
Wear shape (normal distribution)
Initiation function for new wear (Weibull distribution)
Measurement uncertainty (normal distribution) 4
Prior Operational Assessment Benchmark How do the prior OA predictions compare with Cycle 19 Condition Monitoring Results?
Number of detected AVB indications in S/G 2A is 7485.
The number of projected AVB wear indications from EOC 18 OA was 7440 to 8750 for the two analysis cases evaluated.
Distribution of detected indications was well estimated for the larger depths 5
Prior Operational Assessment Benchmark Condition Monitoring Benchmark for EOC 18 OA Results 1.0 0.9 0.8 Cumulative Distribution, CDF 0.7 0.6 0.5 0.4 0.3 0.2 SG 2A EOC 19 0.1 EOC 18 OA Results for Cycle 19 (Case 1)
EOC 18 OA Results for Cycle 19 (Case 2) 0.0 0 5 10 15 20 25 30 35 40 45 NDE Depth, d/t (%TW) 6
Operational Assessment Benchmarks Previous Model Benchmark Cycle 19 Detected TW EOC 18 OA Depth PSL-2 Mechanism S/G Prediction at EOC 19 45.8% TW (Case 1) 2A 41.5% TW 49.6% TW (Case 2)
Anti-Vibration Bar Wear(1) 2B NA 40.8% TW Wear at Tube Support 2A & 2B 32.7% TW 20.6% TW Plates(2)
NOTES:
- 1) Probabilistic OA model prediction for worst case indication depth. Depth is maximum structural depth and includes systematic sizing error from the profile analysis.
- 2) Deterministic OA predicted depth includes uncertainty values at the 95-50 level. Depth is maximum peak depth.
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Operational Assessment Model Wear Rates from Cycle 19 Wear rates from Cycle 18 were used for Cycle 19. Wear rates showed correlated behavior with BOC 18 depths.
This was conservatively modeled in previous OA.
Wear rates for Cycle 19 show a weak correlation with BOC depths and wear rates were considered as independent for the next cycle.
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Operational Assessment Model Wear Rates for Cycle 20 Wear rates from Cycle 19 determined from paired bobbin Nondestructive Examination (NDE) depths and used for Cycle 20 Wear rates computed by two different methods as described in EPRI IAGL
- conservative evaluation (only positive growth)
- realistic evaluation (removes sizing error)
The wear rates were increased by a factor of 1.24 (developed by AREVA) to account for power-uprate conditions in Cycle 20 9
Operational Assessment Model PSL-2 AVB Wear Rates for First Three Cycles 1.0 0.9 0.8 Cumulative Distribution (CDF) 0.7 0.6 0.5 0.4 0.3 0.2 S/G 2A (2009) S/G 2B (2009) 0.1 S/G 2A (2011) S/G 2B (2011)
S/G 2A (2012) S/G 2B (2012) 0.0 0 2 4 6 8 10 12 14 16 18 20 22 24 Wear Rate, WR (%TW per EFPY) 10
Operational Assessment Model PSL-2 AVB Wear Rates for Operational Assessment with EPU - S/G 2A 1.0 0.9 0.8 Cumulative Distribution (CDF) 0.7 0.6 0.5 0.4 0.3 0.2 Conservative Evaluation (WR-1) 0.1 Realistic Evaluation (WR-2) 0.0 0 2 4 6 8 10 12 14 16 18 20 22 24 Wear Rate, WR (%TW per EFPY) 11
Input Distributions Other Model Inputs for Cycle 20 No significant changes from previous OA model assessments Tubing properties based on actual mechanical strength data at 650F from Certified Material Test Report (CMTR) data for PSL-2 tubing Indication length and shape characteristics based on profiled data from current and past inspections Probability of detection function developed from EPRI Examination Technique Specification Sheet (ETSS) 96004.1 database for the bobbin coil 12
Probability of Detection Model PSL-2 Bobbin Coil Detection Performance Estimates 1.0 0.9 0.8 0.7 Probability of Detection, POD 0.6 0.5 0.4 0.3 0.2 POD from EOC 17 OA 0.1 ETSS 96004.1 (Logisitc Fit)
ETSS 96004.1 (Log Logistic Fit) 0.0 0 5 10 15 20 25 30 35 40 Depth, d/t (%TW) 13
Benchmarking EOC 19 Results BENCHMARK RESULTS FROM MULTI-CYCLE ANALYSIS FOR WEAR AT ANTI-VIBRATION BARS PSL-2 AT EOC 19 S/G 2A EOC 19 Benchmark Actual Predicted Number of Indications 7485 7384/7497 NDE Maximum Depth 40 -
BE Maximum Depth(1) 43.8 47.8/45.7 Max Structural Depth 41.5 44.3/42.3 Number of Tubes Plugged(2,3) 40 54/32 Notes:
- 1) Actual best estimate (BE) maximum depth includes systematic sizing uncertainty.
- 2) Predicted tubes plugged are based on a plugging limit of 37% TW.
Preventative plug campaign included more tubes than just those > 37% TW.
- 3) Actual number of tubes plugged in S/G 2A with indications > 37% TW is 40.
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Operational Assessment Results RESULTS FROM MULTI-CYCLE ANALYSIS FOR WEAR AT ANTI-VIBRATION BARS PSL-2 AT EOC 19 EOC 20 Probability of Burst EOC 20 Accident Leakage, Wear Rate Determination at 3x NOPD Q95% (gpm)
Conservative Evaluation 2.48% 0 Realistic Evaluation 0.62% 0 Note: Wear rates based on IAGL procedures.
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Other Degradation Mechanisms Wear at V-Shaped Support Pads Located adjacent to AVBs on certain periphery tubes V-SSPs in contact tubes at the extrados and flank regions Observed wear degradation area is small and predominately axial Only 5 indications observed over three cycles - plug on detection Very limited wear rate information. Used largest indication to determine wear rate Probability of Detection (POD) used to assign BOC wear depth for undetected indications Deterministic OA shows acceptable Cycle 20 operation for this mechanism including power-uprate conditions 16
Other Degradation Mechanisms Wear at Tube Support Plates Broached tube support plate design Observed wear degradation area is small and predominately axial 147 indications observed over three cycles - plug on sizing (no tubes required plugging)
Limited wear rate information - used bounding data from other plants Deterministic OA shows acceptable Cycle 20 operation for this mechanism including power-uprate conditions 17
Historical TSP Wear Rates PSL-2 TSP Wear Rates 1.0 0.9 0.8 Cumulative Distribution, CDF 0.7 0.6 0.5 0.4 0.3 2009 Data 0.2 2011 Data (NDD = 5%TW) 2011 Data (Only Paired Points) 2012 Data (Only Paired Points) 0.1 TSP Wear (Industry Data) 0.0 0 2 4 6 8 10 12 14 16 18 20 Wear Rate, WR (%TW per EFPY) 18
Operational Assessment - TSP wear Deterministic Operational Assessment PSL-2 Tube Support Plate Wear - Detected Indications at EOC 19 100 90 Deterministic Method Repair-on-Sizing Method 80 70 3xNOPD Limit Arithmetic Approach Used Worst Case True Depth, (%TW)
- BOC 20 depth + upper 95-50 sizing error 60
- Growth rate at 95-50 upper value 50
- EOC 20 structural limit - 65% TW EOC 21 40 EOC 20 30 EOC 19 20 10 Tube Inspection Unit Outage 0
0 2 4 6 8 10 Operation Time (EFPY) 19
Operational Assessment Summary Tube Integrity Results for Cycle 20, with Power Uprate Scheduled Cycle 20 for PSL-2 is 11,402 EFPH (1.302 EFPY)
Limiting mechanism is AVB wear; S/G A is the limiting generator Probability of burst at the Structural Integrity Performance Criteria (SIPC) margin requirement of 3x Normal Operating Pressure Differential (NOPD) is 2.5% for the conservative method of evaluation for AVB wear rates, which meets the performance standards of < 5%
Deterministic OA for tube support and V-shaped support pad wear show acceptable margins Accident-induced leakage at EOC 20 is negligible for all mechanisms.
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