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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARL-2024-133, Snubber Program Plan Submittal2024-08-14014 August 2024 Snubber Program Plan Submittal 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-2024-090, 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) 2024-08-14
[Table view] Category:Letter type:L
MONTHYEARL-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-138, License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles2024-09-11011 September 2024 License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles L-2024-148, Submittal of Offsite Dose Calculation Manual (Odcm), Revision 552024-09-0909 September 2024 Submittal of Offsite Dose Calculation Manual (Odcm), Revision 55 L-2024-140, Cycle 28 Core Operating Limits Report2024-08-14014 August 2024 Cycle 28 Core Operating Limits Report L-2024-133, Snubber Program Plan Submittal2024-08-14014 August 2024 Snubber Program Plan Submittal L-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024 2024 Population Update Analysis L-2024-129, Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval2024-08-0707 August 2024 Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval L-2024-121, Subsequent License Renewal Commitment 30 Revision2024-07-30030 July 2024 Subsequent License Renewal Commitment 30 Revision L-2024-123, Submittal of In-Service Inspection Program Owners Activity Report (OAR-1)2024-07-29029 July 2024 Submittal of In-Service Inspection Program Owners Activity Report (OAR-1) L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-110, Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake2024-07-10010 July 2024 Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake L-2024-109, Schedule for Subsequent License Renewal Environmental Review2024-07-0303 July 2024 Schedule for Subsequent License Renewal Environmental Review L-2024-104, Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 102024-06-26026 June 2024 Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 L-2024-097, Technical Specification Special Report2024-06-20020 June 2024 Technical Specification Special Report L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-090, Revised Steam Generator Tube Inspection Reports2024-06-0404 June 2024 Revised Steam Generator Tube Inspection Reports L-2024-075, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-05-13013 May 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation L-2024-053, License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis2024-04-30030 April 2024 License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis L-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024 Cycle 32 Core Operating Limits Report L-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024 Cycle 27 Core Operating Limits Report L-2024-064, Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report2024-04-17017 April 2024 Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report L-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024 Annual Radiological Environmental Operating Report for Calendar Year 2023 L-2024-054, 2023 Annual Environmental Operating Report2024-04-0909 April 2024 2023 Annual Environmental Operating Report L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-045, Report of 10 CFR 72.48 Plant Changes2024-03-27027 March 2024 Report of 10 CFR 72.48 Plant Changes L-2024-011, and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2024-023, Unusual or Important Environmental Event - Turtle Mortality2024-03-0606 March 2024 Unusual or Important Environmental Event - Turtle Mortality L-2024-015, 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 2023 Annual Radioactive Effluent Release Report L-2024-029, 2023 Annual Operating Report2024-02-28028 February 2024 2023 Annual Operating Report L-2024-026, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-02-27027 February 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 L-2023-175, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes 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 2024-09-09
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June 30, 2014 0
FPL.
L-2014-208 10 CFR 50.4 10 CFR 50.55a U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re: St. Lucie Unit 2 Docket No. 50-389 Inservice Inspection Plan Third Ten-Year Interval Unit 2 Relief Request No. 17 In accordance with 10 CFR 50.55a(g)(5)(iii), inservice inspection impracticality, Florida Power
& Light (FPL) requests relief from the examination requirements of the ASME Code,Section XI, 1998 Edition with Addenda through 2000, as clarified by Code Case N-460, for the subject ASME Code Category B-A welds. The basis for the relief request is provided in the Attachment.
Please contact Ken Frehafer at (772) 467-7748 if there are any questions about this submittal.
Sincerely, Eric S. Katzman Licensing Manager St. Lucie Plant Attachment ESK/KWF C4 -7 Florida Power & Light Company (U(44L 6501 S. Ocean Drive, Jensen Beach, FL 34957
L-2014-208 Attachment 1 of 20 St. Lucie Unit 2 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 17, REVISION 0 Relief Request In Accordance with 10 CFR50.55a(g)(5)(iii)
-- Inservice Inspection Impracticality--
- 1. ASME Code Component(s) Affected Class 1 pressure retaining welds in the reactor pressure vessel (RPV).
2. Applicable Code Edition and Addenda
The Code of record for St. Lucie Unit 2 (PSL-2) is the 1998 Edition with Addenda through 2000 of the ASME Boiler and Pressure Vessel Code, Section Xl, "Rules for Inservice Inspection of Nuclear Power Plant Components" as modified by 10CFR50.55a.
The 1998 Edition with Addenda through 2000 was utilized for ASME Section XI, Appendix VIII.
3. Applicable Code Requirement
Exam Item No. Examination Requirements Cat.
B1.10 Essentially 100% volumetric examination of all B-A B1.11 longitudinal and circumferential shell welds (does not B1.12 include shell to flange weld).
B1.20 Essentially 100% volumetric examination of accessible B1.22 length of circumferential and meridional head welds.
As defined by 10CFR50.55a(g)(6)(ii)(A)(2) and ASME Code Case N-460, essentially 100% means more than 90% of the examination volume of each weld where reduction in coverage is due to interference by another component or part geometry.
- 4. Impracticality of Compliance Due to the configuration of the Reactor Vessel, it is impractical to meet the examination coverage requirements of the ASME Code,Section XI, 1998 Edition with Addenda through 2000, as clarified by Code Case N-460. Relief is requested in accordance with 10 CFR 50.55a(g)(5)(iii). These areas were found during the 3rd 10-year inservice inspection interval.
When examined, the welds listed within this request did not receive the required code volume coverage due to their configuration and/or the presence of permanent attachments. These scanning limitations prohibit essentially 100% ultrasonic examination coverage of the required examination volume.
L-2014-208 Attachment 2 of 20 St. Lucie Unit 2 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 17, REVISION 0 Described below, coupled with figures, are details of the examination limitations by weld description. Figure 1 provides an illustration of the contact UT head used for scanning from the vessel shell. Figures 2 through 15 provide the dimensions and locations of obstructions and views of each of the affected welds showing the interference caused by the permanent attachments on the Trans World System (TWS) robot and the affect of the obstructions on scanning.
RPV Intermediate Shell-to-Lower Shell Circumferential Weld (101-171)
Examination Category B-A, Item B1.11 The examination of the Figure IWB-2500-2 A-B-C-D volume is limited due to the six surveillance capsule holders. Access to approximately 17% of the examination volume is restricted. The remaining examination volume was examined with techniques which have been qualified by demonstration in accordance with Supplements 4 & 6 of the 1998 Edition with Addenda through 2000 of the ASME Code Section Xl, Appendix VIII, using the Performance Demonstration Initiative Protocol. This weld was examined from both sides of the weld, scanning both parallel and perpendicular. These ultrasonic examinations did not reveal any recordable or reportable flaws in accordance with the ASME Code Section Xl, 1998 Edition with Addenda through 2000.
Figure 2 is a view of the TWS robot in the vessel shell region showing scan limitations caused by the six surveillance capsule holders. The weld is covered by the six surveillance capsule holders. Figure 3 provides dimensional information for the six surveillance capsule holders and their affect on scanning.
Figure 4 is a roll out view showing the reactor vessel inside surface scan areas (cross hatched) and the locations of limited areas due to the presence of the six surveillance capsule holders.
RPV Circumferential Bottom Head-to-Lower Shell Weld (201-141)
Examination Category B-A, Item B1.21 The examination of the Figure IWB-2500-3 A-B-C-D volume is limited due to the proximity of the Core Barrel Stabilizers and Core Lugs. Access to approximately 29% of the examination volume is restricted. The remaining examination volume was examined with techniques which have been qualified by demonstration in accordance with Supplements 4 & 6 of the 1998 Edition with Addenda through 2000 of the ASME Code Section Xl, Appendix VIII, using the Performance Demonstration Initiative Protocol. This weld was examined from both sides of the weld, scanning both parallel and perpendicular to the weld. These ultrasonic examinations did not reveal any recordable or reportable flaws in accordance with the ASME Code Section XI, 1998 Edition with Addenda through 2000.
Figure 5 is a view of the TWS robot in the vessel shell region showing scan limitations caused by the Core Barrel Stabilizers and Core Lugs. Figure 6
L-2014-208 Attachment 3 of 20 St. Lucie Unit 2 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 17, REVISION 0 provides dimensional information for the core barrel stabilizers and core lugs and their locations in the reactor vessel. Figure 7 is a roll out view showing the reactor vessel inside surface scan areas (cross hatched) for the bottom head-to-lower shell weld and the locations of limited areas due to the presence of the core barrel stabilizers and core lugs.
RPV Upper Shell Longitudinal Seam Weld at 15 Degrees (101-122A)
Examination Category B-A, Item B1.12 The examination of the Figure IWB-2500-2 A-B-C-D volume is limited due to the outlet nozzle at zero degrees integral extension. Access to approximately 37%
of the examination volume is restricted. The remaining examination volume was examined with techniques which have been qualified by demonstration in accordance with Supplements 4 & 6 of the 1998 Edition with Addenda through 2000 of the ASME Code Section XI, Appendix VIII, using the Performance Demonstration Initiative Protocol. This weld was examined from both sides of the weld, scanning both parallel and perpendicular to the weld. These ultrasonic examinations did not reveal any recordable or reportable flaws in accordance with the ASME Code Section Xl, 1998 Edition with Addenda through 2000.
Figures 8 and 9 are views of the TWS robot in the vessel shell region showing the scan limitation caused by the outlet nozzle at zero degrees integral extension. Figure 10 provides dimensional information and the affect the outlet nozzle at zero integral extension had on scanning. Figure 11 is a roll out view showing the reactor vessel inside surface scan areas (cross hatched) for the upper shell longitudinal seam weld at 15 degrees.
RPV Lower Head Peel Segment Welds (101-154-A through F)
Examination Category B-A, Item B13.22 The examination of the Figure IWB-2500-3 E-F-G-H volume is limited due to the proximity of the flow baffle. Access to approximately 47% of welds 101-154-A, 101-154-C, 101-154-E and 57% of welds 101-154-B, 101-154-D, 101-154-F examination volume is restricted due to limited access behind the flow baffle.
The remaining examination volume was examined with techniques which have been qualified by demonstration in accordance with Supplements 4 & 6 of the 1998 Edition with Addenda through 2000 of the ASME Code Section XI, Appendix VIII, using the Performance Demonstration Initiative Protocol. This weld was examined from both sides of the weld, scanning both parallel and perpendicular to the weld. These ultrasonic examinations did not reveal any recordable or reportable flaws in accordance with the ASME Code Section Xl, 1998 Edition with Addenda through 2000.
Figures 12 and 13 are views of the TWS robot in the vessel shell region showing scan limitations due to limited access behind the flow baffle and core lugs.
Figure 14 provides dimensional information for the core lugs and core baffle and
L-2014-208 Attachment 4 of 20 St. Lucie Unit 2 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 17, REVISION 0 their affect on scanning. Figure 15 is a roll out view showing the reactor vessel inside surface scan areas (cross hatched) for the peel segment welds and the locations of the core lugs.
- 5. Burden Caused by Compliance It is not possible to obtain ultrasonic interrogation of greater than 90% of the required examination volume due to interference caused by configuration and/or permanent attachments. Examinations were performed to the maximum extent possible. For the welds listed in this relief request, it is not possible to remove the permanently attached obstructions to increase ASME Code coverage without significant work, increased radiation exposure, and/or damage to the plant.
- 6. Proposed Alternative and Basis for Use Proposed Alternative
- 1) Periodic system pressure tests in accordance with ASME Section XI Category B-P, Table IWB-2500-1.
- 2) Conduct ultrasonic examinations to the maximum extent possible.
Basis FPL performed inservice examinations of selected welds in accordance with the requirements of 10CFR50.55a, plant technical specifications, and the 1998 Edition with Addenda through 2000, of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl. When a component has conditions which limit the examination volume, Florida Power and Light is required to submit the information to the enforcement and regulatory authorities having jurisdiction at the plant site. This Relief Request has been written to address areas where those types of conditions exist and the required amount of coverage was reduced below the minimum acceptable.
FPL performed mechanized ultrasonic examinations of the reactor vessel during the 2012 (SL2-20) refueling outage.
10 CFR 50.55a(g)(4) recognizes that throughout the service life of a nuclear power facility, components which are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements set forth in the ASME Code to the extent practical within the limitations of design, geometry and materials of construction of the components.
The mechanized techniques employed for examination from the RPV inside have been demonstrated in accordance with Supplements 4 & 6 of the 1998 Edition with Addenda through 2000 of the ASME Code Section XI, Appendix VIII, using the Performance Demonstration Initiative Protocol. The Ultrasonic (UT) techniques for each weld were reviewed to determine if additional coverage could be achieved. Access for examination of the affected welds from the outside of the reactor vessel is not possible. Access and
L-2014-208 Attachment 5 of 20 St. Lucie Unit 2 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 17, REVISION 0 permanently installed attachments inside the reactor vessel limit additional scanning of the welds included in this request for relief.
In addition to the required ultrasonic examinations, the interior of the reactor vessel, including welded attachments, received visual examination in accordance with Table IWB-2500-1, Examination Categories B-N-i, B-N-2, and B-N-3. Additionally, Examination Category B-D nozzle inner radius examinations were performed in accordance with ASME Code Case N-648-1, as amended by 10CFR50.55a. With the exception of acceptable visual indications identified at the top of the material surveillance capsule holders at the 83 and 97 degree azimuths, the visual examinations revealed no indications.
The subject welds were also examined in the second interval during the 10-year reactor vessel examination. The second interval examinations did not reveal any reportable flaws.
The extent of examination volume achieved ultrasonically, the alternate scans performed, and the system pressure tests provide assurance of an acceptable level of quality and safety.
- 7. Duration of Proposed Alternative This relief request is applicable to the St. Lucie unit 2 Third Inservice Inspection Interval which began August 8, 2003 and ended August 7, 2013.
- 8. References 10CFR50.55a ASME Section XI, "Rules For Inservice Inspection of Nuclear Power Plant Components,"
1998 Edition with Addenda through 2000 ASME Section Xl, Division 1, Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 Welds,Section XI, Division 1"
L-2014-208 Attachment 6 of 20 St. Lucie Unit 2 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 17, REVISION 0 CONTACT 51OCK END CONTACT HEAD D RECTIONAL ARROW V
2x3 L,7 HEAD CO\FIGUFRATION FOR SHELL SCANNING (AS VyEWED FROM BACK OF ROBOHAND COUPLING)
Illustration of the typical UT head configuration used for vessel shell weld scanning. Overall head dimensions are approximately 12" x 8".
Figure 1
L-2014-208 Attachment 7 of 20 St. Lucie Unit 2 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 17, REVISION 0 RPV Intermediate Shell-to-Lower Shell Circumferential Weld (101-171)
View of TWS robot in vessel shell region showing scan limitation caused by the surveillance capsule holders. The weld is covered by the surveillance capsule holders. These limitations occur at two circumferential locations on this weld at 1800 apart. Single sided scan parameters are used near obstructions to improve examination coverage. Coverage obtained on this weld is 83%.
Figure 2
L-2014-208 Attachment 8 of 20 St. Lucie Unit 2 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 17, REVISION 0 270Y AND 90"
-263, 27'T AND AND IDELTA-40 izsTP(STP w sr)
UIMENS*UNS* SHOUWNIN DLEGIREES TOTAL SCAN AREA OF YELD101-171 IS LIMITED DUE TO 6 SURVEILLANCE HOLDERS TOTAL WELD LENGTH= 546.01 INCHES SHO- SURVEILLANCE HOLDER OBSTRUCTED RPV Intermediate Shell-to-Lower Shell Circumferential Weld (101-171)
Figure 3
L-2014-208 Attachment 9 of 20 St. Lucie Unit 2 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 17, REVISION 0 I. ZRr -~v r 1 I
T
~ I:
I RPV Intermediate Shell-to-Lower Shell Circumferential Weld (101-171)
Figure 4
L-2014-208 Attachment 10 of 20 St. Lucie Unit 2 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 17, REVISION 0 RPV Circumferential Bottom Head-to-Lower Shell Weld (201-141) and Peel Segment Welds (101-154-A through F) Behind Flow Baffle View of TWS robot in lower vessel shell region showing scan limitations caused by the Core Barrel Stabilizers, Core Lugs and the Flow Baffle. The weld examinations are obstructed by these features.
Single sided scan parameters are applied as applicable near the obstructions to increase coverage.
Coverage on the circumferential weld is 71% and coverage on the peel segment welds is 53% for welds A, C, and E and 43% for welds B, D, and F.
Figure 5
L-2014-208 Attachment 11 of 20 St. Lucie Unit 2 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 17, REVISION 0 0.
CORE BARREL STABIUZER TYP 6X-CORE WELD 201-141 BAFFLE
'CORE LUG TYp 9x RPV Circumferential Bottom Head-to-Lower Shell Weld (201-141)
Figure 6
L-2014-208 Attachment 12 of 20 St. Lucie Unit 2 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 17, REVISION 0
[2.I-41]
,-o-, ,101-1,4-F 101-154-A 101o154-,
RPV Circumferential Bottom Head-to-Lower Shell Weld (201-141)
Figure 7
L-2014-208 Attachment 13 of 20 St. Lucie Unit 2 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 17, REVISION 0 RPV Upper Shell Longitudinal Seam Weld at 15 Degrees (101-122-A)
View of TWS robot in upper vessel nozzle belt region showing scan limitation caused by the outlet nozzle reinforcement. The weld intersects the outlet nozzle and limits UT head movement adjacent to the outlet nozzle on both the upper and lower portions of the weld. Single side scan parameters are used on this weld in the axial beam directions to improve coverage. Coverage obtained on this weld is 63%.
Figure 8
L-2014-208 Attachment 14 of 20 St. Lucie Unit 2 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 17, REVISION 0 RPV Upper Shell Longitudinal Seam Weld at 15 Degrees (101-122-A)
View of TWS robot in upper vessel nozzle belt region showing scan limitation caused by the outlet nozzle reinforcement on the upper portion of the weld. The weld intersects the outlet nozzle and limits UT head movement adjacent to the outlet nozzle. Single side scan parameters are used on this weld in the axial beam directions to improve coverage. Coverage obtained on this weld is 63%.
Figure 9
L-2014-208 Attachment 15 of 20 St. Lucie Unit 2 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 17, REVISION 0 F--- -- __--_--__
RPV Upper Shell Longitudinal Seam Weld at 15 Degrees (101-122-A)
Figure 10
L-2014-208 Attachment 16 of 20 St. Lucie Unit 2 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 17, REVISION 0 I .c.
101-121 1 - i-- i I-- rAp I,I, ,I, rAý II, I, , rrAtýý Ii U 101-122" VBFW v-i tl
-4 RPV Upper Shell Longitudinal Seam Weld at 15 Degrees (101-122-A)
Figure 11
L-2014-208 Attachment 17 of 20 St. Lucie Unit 2 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 17, REVISION 0 RPV Lower Head Peel Segment Welds (101-154-A through F) Below Flow Baffle View of TWS robot in lower head below flow baffle showing scan limitation caused by the baffle. The peel segment welds are covered by the baffle. Single side scan parameters are used on these welds below the baffle for the axial beam directions. Coverage on the peel segment welds is 53% for welds A, C, and E and 43% for welds B, D, and F.
Figure 12
L-2014-208 Attachment 18 of 20 St. Lucie Unit 2 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 17, REVISION 0 RPV Lower Head Peel Segment Welds (101-154-A through F)
View of TWS robot in lower head below flow baffle showing scan limitation caused by the baffle. The peel segment welds are covered by the baffle. Single side scan parameters are used on these welds below the baffle for the axial beam directions. Coverage on the peel segment welds is 53% for welds A, C, and E and 43% for welds B, D, and F.
Figure 13
L-2014-208 Attachment 19 of 20 St. Lucie Unit 2 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 17, REVISION 0 FLOW RPV Lower Head Peel Segment Welds (101-154-A through F)
Figure 14
L-2014-208 Attachment 20 of 20 St. Lucie Unit 2 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 17, REVISION 0 1W 27 1
° U ' U U ..... .. - U "
777777:'* ' ;777Y 201-141 ,
RPV Lower Head Peel Segment Welds (101-154-A through F)
Figure 15