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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARL-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-2024-090, Revised Steam Generator Tube Inspection Reports2024-06-0404 June 2024 Revised Steam Generator Tube Inspection Reports L-2022-048, Submittal of Refueling Outage SL2-26 Steam Generator Tube Inspection Report2022-03-21021 March 2022 Submittal of Refueling Outage SL2-26 Steam Generator Tube Inspection Report L-2021-220, Submittal of In-Service Inspection Program ISI Fourth Interval - Third Period SL2-26 Owner'S Activity Report (OAR-1)2021-12-27027 December 2021 Submittal of In-Service Inspection Program ISI Fourth Interval - Third Period SL2-26 Owner'S Activity Report (OAR-1) L-2021-209, Refueling Outage SL1-30 Steam Generator Tube Inspection Report2021-11-0101 November 2021 Refueling Outage SL1-30 Steam Generator Tube Inspection Report L-2021-112, In-Service Inspection Program, ISI Fifth Interval - First Period SL1-30, Owner'S Activity Report (OAR-1)2021-08-13013 August 2021 In-Service Inspection Program, ISI Fifth Interval - First Period SL1-30, Owner'S Activity Report (OAR-1) L-2020-030, In-Service Inspection Program ISI Fifth Interval - First Period SL1-29 Owner'S Activity Report (OAR-1)2020-02-18018 February 2020 In-Service Inspection Program ISI Fifth Interval - First Period SL1-29 Owner'S Activity Report (OAR-1) L-2020-025, Unit 2 ISI 4th Interval Relief Request 17, Proposed Alternative to Use ASME Code Case N-513-42020-02-0707 February 2020 Unit 2 ISI 4th Interval Relief Request 17, Proposed Alternative to Use ASME Code Case N-513-4 L-2018-239, In-Service Inspection Program ISI Fourth Interval - Second Period - SL2-24 Refueling Outage Owner'S Activity Report (OAR-1)2018-12-28028 December 2018 In-Service Inspection Program ISI Fourth Interval - Second Period - SL2-24 Refueling Outage Owner'S Activity Report (OAR-1) L-2018-135, In-Service Inspection Program, ISI Fourth Interval- Third Period; Fifth Interval- First Period; SL1-28 Owner'S Activity Report (OAR-1)2018-07-0909 July 2018 In-Service Inspection Program, ISI Fourth Interval- Third Period; Fifth Interval- First Period; SL1-28 Owner'S Activity Report (OAR-1) L-2018-110, Submittal of Fifth Ten-Year Inservice Inspection Interval ISI Program Plan, Revision 02018-05-0202 May 2018 Submittal of Fifth Ten-Year Inservice Inspection Interval ISI Program Plan, Revision 0 L-2018-069, Fifth 10-Year Interval - Inservice Testing (1ST) Program Plan2018-03-30030 March 2018 Fifth 10-Year Interval - Inservice Testing (1ST) Program Plan L-2018-042, Snubber Program Plan Submittal for Fifth 10-Year Inservice Testing Interval2018-02-0909 February 2018 Snubber Program Plan Submittal for Fifth 10-Year Inservice Testing Interval L-2017-152, Refueling Outage SL2-23, Steam Generator Tube Inspection Report2017-09-13013 September 2017 Refueling Outage SL2-23, Steam Generator Tube Inspection Report L-2017-070, Refueling Outage SL1-27 Steam Generator Tube Inspection Report2017-04-27027 April 2017 Refueling Outage SL1-27 Steam Generator Tube Inspection Report L-2017-019, Submittal of In-Service Inspection Program, ISI Fourth Interval- Third Period- SL1-27, Owner'S Activity Report (OAR-1)2017-02-0606 February 2017 Submittal of In-Service Inspection Program, ISI Fourth Interval- Third Period- SL1-27, Owner'S Activity Report (OAR-1) L-2017-017, Inservice Inspection Plan, Fourth Ten-Year Unit 1 Relief Request No. 14, Revision 02017-02-0202 February 2017 Inservice Inspection Plan, Fourth Ten-Year Unit 1 Relief Request No. 14, Revision 0 L-2016-088, Report of 10 CFR 50.59 Plant Changes - Docket No. 50-3892016-04-19019 April 2016 Report of 10 CFR 50.59 Plant Changes - Docket No. 50-389 L-2016-089, Refueling Outage SL2-22, Steam Generator Tube Inspection Report2016-04-15015 April 2016 Refueling Outage SL2-22, Steam Generator Tube Inspection Report ML16076A4312016-03-0707 March 2016 St. Lucie, Unit 2, In-Service Inspection Plans Fourth Ten-Year Interval Relief Request 11 L-2016-015, In-Service Inspection Program, ISI Fourth Interval - First Period - SL2-22 Refueling Outage, Owner'S Activity Report (OAR-1)2016-01-21021 January 2016 In-Service Inspection Program, ISI Fourth Interval - First Period - SL2-22 Refueling Outage, Owner'S Activity Report (OAR-1) L-2015-204, In-Service Inspection Program, ISI Fourth Interval - Third Period - SL1-26, Owner'S Activity Report (OAR-1)2015-07-22022 July 2015 In-Service Inspection Program, ISI Fourth Interval - Third Period - SL1-26, Owner'S Activity Report (OAR-1) L-2015-126, License Renewal One-Time Inspection of Class 1 Small Bore Piping Revised Commitments and Revised Inspection Plan2015-05-11011 May 2015 License Renewal One-Time Inspection of Class 1 Small Bore Piping Revised Commitments and Revised Inspection Plan L-2015-063, In-Service Inspection Plans Fourth Ten-Year Interval Unit 2 Relief Request 2 RAI Reply2015-03-0505 March 2015 In-Service Inspection Plans Fourth Ten-Year Interval Unit 2 Relief Request 2 RAI Reply L-2014-360, Inservice Inspection Plan Fourth Ten-Year Interval Relief Request No. 9, Revision 02014-12-0303 December 2014 Inservice Inspection Plan Fourth Ten-Year Interval Relief Request No. 9, Revision 0 L-2014-339, Inservice Inspection Plan - RAI Reply - Third Ten-Year Interval Unit 2 Relief Request No. 142014-11-0303 November 2014 Inservice Inspection Plan - RAI Reply - Third Ten-Year Interval Unit 2 Relief Request No. 14 L-2014-331, TS Correction for Fourth Ten-Year Inservice Inspection Interval License Amendment Request Changes to Snubber Surveillance Requirements2014-10-23023 October 2014 TS Correction for Fourth Ten-Year Inservice Inspection Interval License Amendment Request Changes to Snubber Surveillance Requirements L-2014-277, Inservice Inspection Plan, RAI Reply - Third Ten-Year Interval Unit 2 Relief Request No. 172014-08-28028 August 2014 Inservice Inspection Plan, RAI Reply - Third Ten-Year Interval Unit 2 Relief Request No. 17 L-2014-224, In-Service Inspection Program ISI Fourth Interval - First Period - SL2-21 Refueling Outage Owner'S Activity Report (OAR-l)2014-07-17017 July 2014 In-Service Inspection Program ISI Fourth Interval - First Period - SL2-21 Refueling Outage Owner'S Activity Report (OAR-l) L-2014-208, Third Ten-Year Interval Unit 2 Relief Request No. 172014-06-30030 June 2014 Third Ten-Year Interval Unit 2 Relief Request No. 17 L-2014-206, Third Ten-Year Interval Unit 2 Relief Request No. 142014-06-30030 June 2014 Third Ten-Year Interval Unit 2 Relief Request No. 14 L-2014-113, Refueling Outage SL 1-25, Steam Generator Tube Inspection Special Report2014-04-29029 April 2014 Refueling Outage SL 1-25, Steam Generator Tube Inspection Special Report L-2014-039, Submittal of In-Service Inspection Program ISI Fourth Interval - Second Period - SLI-25 Owner'S Activity Report (OAR-I)2014-02-0606 February 2014 Submittal of In-Service Inspection Program ISI Fourth Interval - Second Period - SLI-25 Owner'S Activity Report (OAR-I) L-2014-027, Fourth Ten-Year Inservice Inspection Interval License Amendment Request, Changes to Snubber Surveillance Requirements2014-01-30030 January 2014 Fourth Ten-Year Inservice Inspection Interval License Amendment Request, Changes to Snubber Surveillance Requirements L-2013-240, Fourth Ten-Year Interval, Relief Request No. 7, Rev. 02013-08-0505 August 2013 Fourth Ten-Year Interval, Relief Request No. 7, Rev. 0 L-2013-063, In-Service Inspection Program ISI Third Interval - Third Period - Second Outage (SL2-20) Owner'S Activity Report (OAR-1)2013-02-20020 February 2013 In-Service Inspection Program ISI Third Interval - Third Period - Second Outage (SL2-20) Owner'S Activity Report (OAR-1) L-2013-066, Third Ten-Year Interval Unit 2 Relief Request No. 9, Revision 02013-02-13013 February 2013 Third Ten-Year Interval Unit 2 Relief Request No. 9, Revision 0 L-2013-044, Inservice Inspection Plan, Fourth Ten-Year Interval Unit 1 Relief Request No. 5, Revision 02013-02-0404 February 2013 Inservice Inspection Plan, Fourth Ten-Year Interval Unit 1 Relief Request No. 5, Revision 0 L-2012-301, In-Service Inspection Program, ISI Fourth Interval - Second Period - SLI-24 Owner'S Activity Report (OAR-1)2012-07-20020 July 2012 In-Service Inspection Program, ISI Fourth Interval - Second Period - SLI-24 Owner'S Activity Report (OAR-1) L-2010-207, Fourth Ten-Year Interval Relief Request PR-92010-09-14014 September 2010 Fourth Ten-Year Interval Relief Request PR-9 L-2010-202, In-Service Inspection Program, ISI Fourth Interval - First Period - Second Outage (SL1-23), Owner'S Activity Report, (OAR-1)2010-09-0101 September 2010 In-Service Inspection Program, ISI Fourth Interval - First Period - Second Outage (SL1-23), Owner'S Activity Report, (OAR-1) L-2009-183, Submittal of In-Service Inspection Program, ISI Third Interval - Second Period - Second Outage (SL2-18) Owner'S Activity Report (OAR- 1)2009-08-14014 August 2009 Submittal of In-Service Inspection Program, ISI Third Interval - Second Period - Second Outage (SL2-18) Owner'S Activity Report (OAR- 1) L-2009-168, Response to Request for Additional Information, Third Interval Relief Request 312009-07-20020 July 2009 Response to Request for Additional Information, Third Interval Relief Request 31 L-2009-091, Steam Generator Tube Inspection Report2009-04-13013 April 2009 Steam Generator Tube Inspection Report L-2009-036, In-Service Inspection Program Fourth Interval - First Period Owner'S Activity Report (OAR-1) Submittal2009-02-0909 February 2009 In-Service Inspection Program Fourth Interval - First Period Owner'S Activity Report (OAR-1) Submittal L-2008-253, Inservice Inspection Plans, Unit 1 Fourth Inspection Interval RR 4, and Unit 2 Third Inspection Interval RR 112008-12-0303 December 2008 Inservice Inspection Plans, Unit 1 Fourth Inspection Interval RR 4, and Unit 2 Third Inspection Interval RR 11 L-2008-158, Submittal of In-Service Inspection Program Third Interval - Third Period Owner'S Activity Report for SL1-20 and SL1-21 Outages2008-07-21021 July 2008 Submittal of In-Service Inspection Program Third Interval - Third Period Owner'S Activity Report for SL1-20 and SL1-21 Outages L-2008-098, In-Service Inspection Plans, Submittal for the Use of Structural Weld Overlays as an Alternative Repair Technique, Fourth Ten-Year Interval Unit 1 Relief Request 22008-04-29029 April 2008 In-Service Inspection Plans, Submittal for the Use of Structural Weld Overlays as an Alternative Repair Technique, Fourth Ten-Year Interval Unit 1 Relief Request 2 L-2008-067, In-Service Inspection Program, Third Interval - Second Period - First Outage (SL2-17) Owner'S Activity Report (OAR-1)2008-03-26026 March 2008 In-Service Inspection Program, Third Interval - Second Period - First Outage (SL2-17) Owner'S Activity Report (OAR-1) L-2008-043, Fourth Ten-Year Inservice Inspection Interval ISI Program Plan - Revision 02008-03-13013 March 2008 Fourth Ten-Year Inservice Inspection Interval ISI Program Plan - Revision 0 2024-07-29
[Table view] Category:Letter type:L
MONTHYEARL-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-2024-110, 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-2024-114, 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-2024-109, 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-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024 Cycle 27 Core Operating Limits Report L-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024 Cycle 32 Core Operating Limits Report L-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024 Annual Radiological Environmental Operating Report for Calendar Year 2023 L-2024-064, 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-2024-054, 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-2024-029, 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-2023-155, 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 L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report 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-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) 2024-08-07
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Florida Power & Light Company, 6501 S.Ocean Drive, Jensen Beach, FL 34957 November 9, 2005 FPL L-2005-234 10 CFR 50.55a 10 CFR 50.36 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re: St. Lucie Unit 1 Docket No. 50-335 Revised Steam Generator Tube Inservice Inspection Special Report for Refueling Outage SLI-19 & RAI Response Attached is complete replacement of the Steam Generator Tube Inservice Inspection Special Report required by sections 4.4.5.5.b and 6.9.2 of the St. Lucie Unit 1 Technical Specifications for the spring 2004 refueling outage (SLI-19) submitted by FPL letter L-2005-077 dated April 8, 2005. A portion of the report was inadvertently omitted in the original submittal.
Attachment 1 provides a revised report and Attachment 2 provides a response to the NRC request for additional information (RAI) dated July 12, 2005. A revised response date was discussed with the NRC project manager.
Should there be any questions, please contact us.
Williamn I' Vice President St. Lucie Plant WJ/GRM Attachment
.1 §C:cil an FPL Group company
I St. Lucie Unit 1 Docket No. 50-335 L-2005-234 Attachment 1 Page 1 Replacement St. Lucie Unit I Spring 2004 Refueling Outage SLI1-19 Steam Generator Tube Inservice Inspection Special Report
St. Lucie Unit 1 Docket No. 50-335 L-2005-234 Attachment 1 Page 2 This report addresses Plant Technical Specification Section 4.4.5.5 b. The attached information provides the summarized results for the inservice examination of steam generator tubing, which is to be submitted to the Commission within 12 months of the examination completion date.
- 1. Inservice eddy current examination and tube plugging of the St. Lucie Unit 1 steam generators was completed between April 4, 2004 and April 10, 2004. The examination scope as noted below is represented under "Total Tubes Inspected" on the attached FORM NIS-BB, Owners' Data Report for Eddy Current Examination Results.
Examination Scope Bobbin Coil Probe
- Approximately 57% of the inservice tubes in S/G 1A and approximately 54% of the inservice tubes in S/G 1B were examined from tube end to tube end. Row 3 examinations (because of the tight bend radii) included the hot leg and cold leg straight sections with complementary u-bend examinations performed using the Plus Point Probe.
Plus Point Rotating Probe
- Approximately 50% of the hot leg Expansion Transitions from 3 inches above to 2 inches below the secondary face of the tubesheet.
- 50% of the row 3 U-bends as a minimum were examined. (Row 3 has the tightest bend radius due to the crossover design)
- Special interest (diagnostic) locations as required by the bobbin coil results.
- 2. The location and percent of wall thickness penetration is also summarized on the attached FORM NIS-BB under "Location of Indications. To date, no corrosion type indications have been reported at St. Lucie Unit 1.
- 3. Three (3) tubes were preventively plugged in S/G 1A due to mechanical wear that was less than the Technical Specification plugging limit of 40% wall thickness penetration.
This is summarized in the upper portion of the attached FORM NIS-BB.
- 4. A total of 21 mechanical wear indications (17 in S/G 1A and 4 in S/G 1B) detected at u-bend support structures that measured less than 20% wall thickness penetration will remain in service for cycle 19.
- 5. The source documents (tubes preventively plugged, 20% to 39%, and 1% to 19%)
used for preparation of FORM NIS-BB are attached for reference.
St. Lucie Unit 1 Docket No. 50-335 L-2005-234 Attachment 1 Page 3 FORM NIS-BB OWNERS' DATA REPORT FOR EDDY CURRENT EXAMINATION RESULTS As required by the provisions of the ASME CODE RULES EDDY CURRENT EXAMINATION RESULTS PLANT: St. Lucie Unit I Outage: SL1-19 EXAMINATION DATE: April 4.2004 through April 10, 2004 TTLTUBES TOTAL STEAM TOTAL TOTAL TOTAL TUBES PLUGGED PLUGGED GENERATOR TUBES TUBES >4W PIT& VO PREVENTIVELY THIS TUBES INSPECTED 201/-39% PLUGGED (PTP) OUTAGE INS/G 769802A (Bobbin) 4834 3 0 3 3 14 769801B (Bobbin) 4640 0 0 0 0 0 769802A (RPC) I,) 4288 (2) 0 0 0 0 See Bobbin 769801B (RPC) (1) 4291 (2) 0 0 0 0 See Bobbin LOCATION OF INDICATIONS (1%- 100%. PIT & VOL)
U Bend Lattice Grids STEAM CBH p (TSP's) Top of Topof Total GENERATOR To 01 to 07 Tubesheet Tubesheet Indications CBC 3)to to
- 1Support #1 Support PTo H/L CC / LH /L 1%-19% 20%-39% V0%.PITor 769802A (Bobbin) 3 0 0 0 0 17 3 (z)0 7698018 (Bobbin) 0 0 0 0 0 4 0 769802A (RPC) (1) 0 0 n rn/a n/a n/a n/a 0 769801B (RPC) t . n/a n/a n/a n/a n/a n/a 0 Remarks:
(1) RPC = Rotating Pancake Coil Technique.
(2) Includes tubes In the low row U-bend & dent programs.
(3) CBH =Connector Bar Hot Leg: CBC = Connector Bar Cold Leg (4) Tubes with indications measuring greater than or equal to 20% through wall were preventively plugged (PTP).
St. Lucie Unit 1 Docket No. 50-335 L-2005-234 Attachment 1 Page 4 The following listings are source documents used for the preparation of "Form NIS-BB".
S/G A Tubes with Bobbin 20-39% TWD Indications QUERY: QueryMl ROW LINE VOLTS DEC CHN IND %TW LOCATION EXT EXT CAL 1 LEG PROBE
.===== -= === -= -= == ... =~=====
... === === ====
68 77 0.36 109 P 3 TWD 22 F06 -1.40 TEH TEC 38 COLD 61OUL 100 79 0.80 122 P 3 TWD 32 F06 +0.91 TEH TEC 38 COLD 61OUL 103 78 0.32 109 P 3 TWD 21 CBC +1.80 TEH TEC 38 COLD 61OUL Total Tubes : 3 Total Records: 3 S G A Tubes Preventatively Plugged QUERY: QueryMl ROW LINE VOLTS DEC CHM IND %TW LOCATION EXT EXT CAL t LEG PROBE 68= ==== ====e= === === === ====8==L===1====== = =
68 77 PTP TEH TEC 38 COLD 61OUL 100 79 PTP TEH TEC 38 COLD 61OUL 103 78 PTP TEH TEC 38 COLD 610UL Total Tubes : 3 Total Records: 3 S/G B Tubes with Bobbin 20-100% TWD Indications No damage was reported in S/G B that exceeded 20% wall thickness penetration.
St. Lucie Unit 1 Docket No. 50-335 L-2005-234 Attachment 1 Page 5 S/G A:
Tubes with Bobbin 1-19% TWD Indications QUERY: QueryMl ROW LINE VOLTS DEG CHN IND %TW LOCATION EXT EXT CAL t LEG PROBE
=
77 92 0.20 127 P 3 TWD 14 F09 -2.28 TEH TEC 20 COLD 610UL 79 92 0.15 130 P 3 TWO 11 F09 -1.99 TEH TEC 20 COLD 0.13 114 P 3 TWD 11 F06 +1.30 TEH TEC 38 COLD 610UL 84 99 93 0.14 124 P 3 TWO 11 F04 -0.61 TEH TEC 20 COLD 610UL 88 610UL 78 0.25 112 P 3 TOD 16 CBC +1.91 TEH TEC 20 COLD 91 92 77 0.13 127 P 3 TWD 11 CBC +0.37 TEH TEC 38 COLD 61OUL 95 92 0.19 107 P 3 TWD 13 F09 -1.93 TEH TEC 20 COLD 610UL 97 92 0.13 123 P 3 TWD 11 F09 -2.02 TEH TEC 38 COLD 610UL 144 0.11 155 P 3 TWD 10 OIC -1.53 TEH TEC 62 COLD 610UL 97 0.24 124 P 3 TWO 17 02C -1.56 TEH TEC 62 COLD 610UL 78 0.27 155 P 3 TWD 18 CBC +1.74 TEH TEC 38 COLD 610UL 99 0.14 111 P 3 TWO 11 F06 -1.07 TEU TEC 22 COLD 610UL 102 111 0.12 115 P 3 TWD 9 F09 -1.92 TEH TEC 20 COLD 610UL 103 92 0.25 109 P 3 TWD 17 F06 -0.99 TEH TEC 38 COLD 610UL 114 75 0.12 137 P 3 ThO 9 F10 +2.24 TEH TEC 20 COLD 610UL 115 78 115 82 0.19 130 P 3 rWD 15 F05 +0.89 TEH TEC 61 COLD 610UL 128 51 0.14 74 P 3 TWD 11 F10 +0.54 TEH TEC 41 COLD 61OUL Total Tubes : 16 Total Indications: 17 S/G B:
Tubes with Bobbin 1-19% TWD Indications QUERY: QueryMl ROW LINE VOLTS DEG CHN IND %TW LOCATION EXT EXT CAL
- LEG PROBE 81 102 0.14 125 P 3 TWD 12 F04 -1.80 TER TEC 21 COLD 610UL 97 144 0.08 158 P 3 TWD 8 05H +1.46 TEH TEC 52 COLD 610UL 110 91 0.10 77 P 3 TWO 9 F06 -1.38 TEH TEC 36 COLD 610UL 114 51 0.08 156 P 3 TWO 6 F05 -1.42 TEH TEC 36 COLD 61OUL Total Tubes : 4 Total RIndications: 4
St. Lucie Unit 1 Docket No. 50-335 L-2005-234 Attachment 2 Page 1 REQUEST FOR ADDITIONAL INFORMATION SLI-19 STEAM GENERATOR TUBE INSERVICE INSPECTION SPECIAL REPORT ST. LUCIE NUCLEAR PLANT, UNIT I DOCKET NUMBER 50-335 NRC Request 1:
St. Lucie Unit 1 Technical Specification (TS) 4.4.5.5.b requires the licensee to provide the location and percent of wall thickness penetration for each indication of an imperfection.
This technical specification also requires identification of tubes plugged. Please provide the location of the three tubes that were plugged in steam generator A (i.e., row, column, and axial location of the flaw). In addition provide the location and percent of wall thickness penetration for each indication of an imperfection in both steam generators.
FPL Response 1:
The required information is provided in the enclosed listings, which include indications 1-19%
through-wall for both steam generators, and indications 20% or greater through-wall for steam generator 1A (S/G 1B does not contain any indications 20% or greater). A listing for tubes preventatively plugged in steam generator 1A is also provided.
NRC Request 2:
Your report identifies the population of tubes that are experiencing wear at U-bend support structure locations. There are different types of wear mechanisms, which behave differently and may present challenges to tube integrity. To help the NRC staff in understanding the identified indications of wear, please discuss the extent to which these wear indications are considered "typical fan bar wear," "atypical U-bend wear," or "localized U-bend wear." Typical fan bar wear refers to wear caused by the thermal hydraulic conditions and tube-to-support clearances, which can vary because of manufacturing tolerances. Atypical U-bend wear refers to pit-like indications found at flat-bar supports and theorized to be the result of asperities on the flat bars introduced during fabrication. Localized U-bend wear refers to wear
'localized" to specific columns of tubes and possibly the adjacent column as a result of arch-bar distortion instead of a more random manufacturing tolerance issue (which causes typical fan bar wear).
Please discuss how the nature of the wear detected during this outage compares to the wear indications detected in 1999 (i.e., what was the cause of wear indications in 1999).
FPL Response 2:
Most indications are localized U-bend wear occurring at flat-bar supports in line 77-79 and line 92-93 in steam generator 1A, which account for 13 of 14 tubes plugged to date. One additional tube (S/G 1A, R27 L100) was plugged in 1999 for an atypical pit-like wear indication at a flat-bar support in the U-bend that is likely due to a manufacturing anomaly.
In the most recent inspection at SL1-19, 16 new wear indications were reported. Five of
St. Lucie Unit 1 Docket No. 50-335 L-2005-234 Attachment 2 Page 2 these were localized wear in the U-bend as discussed above, three of which were plugged (see listing "S/G A Tubes Preventatively Plugged"). Eleven of these are typical wear occurring randomly at flat-bar supports in the U-bend and straight tube regions. Wear indications remaining inservice at the present time include localized U-bend wear and typical (i.e., random) wear indications.
NRC Request 3:
In several Babcock and Wilcox replacement steam generators currently in service, tube-to-tube contact or tubes in close proximity have been observed. For St. Lucie Unit 1, please discuss how many tubes are currently considered to be in close proximity and whether any tube wear has been observed at the locations of close proximity. In addition, please discuss whether the number of tubes in close proximity has increased, decreased, or remained the same since the steam generators were installed. If the number of tubes in close proximity is increasing with time, please discuss the cause (the staff understands that the tube proximity issue is a result of manufacture and that it was expected that the condition may correct itself with time).
FPL Response 3:
The approximate number of tubes in close proximity reported during the three inservice inspections conducted to date (SL1-16, SL1-17 and SL1-19) are shown below. The number remains relatively constant over time and none of the tubes contained any wear degradation based on bobbin and rotating probe inspections completed.
Steam Generator Tubes In Close Proximity- St. Lucie Unit 1 SL1-16 SLI-17 SL1-19 S/G 1A 54 54 56 S/G 1B 45 52 48 NRC Request 4:
There is limited steam generator design information in the St. Lucie Updated Final Safety Analysis Report. In order for the staff to better understand the design of your steam generators and the location of the indications described in your reports, please provide the following design information for St. Lucie Unit 1: (a) the manufacturer's model number for the replacement steam generators, (b) tube manufacturer, (c) outer diameter and nominal wall thickness of tubes, (d) number of tubes in each steam generator, (e) tube pitch and pattern ( e.g., 0.95 inches triangular), (f) tubesheet thickness (with and without clad), (g) a sketch depicting the tube support structure naming (h)anti-vibration bar (fan bar) design, (i) tube support material (e.g., 410 Stainless Steel), 0) a sketch of a tubesheet map which depicts the rows and columns of the tubes in the steam generators, (k) smallest U-bend radius in the steam generator and the radii of the row 1 tubes, (I)stress relief after bending of tubes (e.g., stress relief of the entire tube length for the tubes in rows 1 through 27).
St. Lucie Unit 1 Docket No. 50-335 L-2005-234 Attachment 2 Page 3 FPL Response 4:
Babcock & Wilcox International does not use model numbers, but instead uses a descriptive title and serial number in the manufacture of their steam generators as shown in the table below. Additional figures are enclosed as identified in the table.
St. Lucie Unit I Steam Generator Design Information (a) the manufacturer's model number St. Lucie Nuclear Power Plant Unit 1 Replacement Steam Generator SIG A S/N 769802A, S/G B S/N 769801 B (b)tube manufacturer Sumitomo Special Metals (c) tube outer diameter & nominal wall 0.75 inches x 0.045 inches thickness (d) number of tubes in each steam 8523 generator (e) tube pitch and pattern ( e.g., 0.95 1.0 inch triangular inches triangular)
(f) tubesheet thickness (with/without clad) 21.875 inches /21.50 inches (g) a sketch depicting the tube support See Figure 1 structure naming (h) anti-vibration bar (fan bar) design, See Figure 2 (i) tube support material (e.g., 410 410 Stainless Steel Stainless Steel)
- 0) a sketch of a tubesheet map which See Figure 3 depicts the rows and columns of the tubes in the steam generators (k) smallest U-bend radius in the steam Row 3 has the smallest radius of 3.905 generator and the radii of the row 1 tubes inches, Row 1 radius measures 4.272 inches (I) stress relief after bending of tubes (e.g., The u-bend regions of tubes in Row 1-20 are stress relief of the entire tube length for stress relieved after bending the tubes in rows 1 through 27)
NRC Request 5:
Steam generator inspections may not be required each refueling outage to meet TS requirements. To ensure NRC staff records are accurate, please confirm that no tube inspections were performed during the fall 2002 refueling outage (SL1-1 8).
FPL Response 5:
No tube inspections were performed during the fall 2002 refueling outage (SL1 -18).
St. Lucie Unit 1 Docket No. 50-335 L-2005-234 Attachment 2 Page 4 FIGURE 1 PSL-1 Replacement Steam Generator Support Identification
St. Lucie Unit I Docket No. 50-335 L-2005-234 Attachment 2 Page 5 FIGURE 2 PSL-1 Replacement Steam Generator U-Bend Structure Identification
St. Lucie Unit 1 Docket No. 50-335 L-2005-234 Attachment 2 Page 6 Lines ROWS S
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