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MONTHYEARL-2017-112, Inservice Inspection Plan, Fourth Ten-Year Interval Unit 1 Relief Request No. 17, Revision 02017-06-12012 June 2017 Inservice Inspection Plan, Fourth Ten-Year Interval Unit 1 Relief Request No. 17, Revision 0 Project stage: Request L-2017-113, Inservice Inspection Plan, Fourth Ten-Year Interval Unit 1 Relief Request No. 16, Revision 02017-06-12012 June 2017 Inservice Inspection Plan, Fourth Ten-Year Interval Unit 1 Relief Request No. 16, Revision 0 Project stage: Request ML17263A1202017-10-27027 October 2017 Inservice Inspection Plan Fourth 10-Year Interval Relief Request No. 16 (CAC No. MF9827; EPID L-2017-LLR-0044) Project stage: Other ML17334A9362018-01-0404 January 2018 Relief from the Requirements of the ASME Code Regarding Relief Request No. 17, Revision 0, for the Fourth 10-Year Inservice Inspection Interval (CAC No. MF9826; EPID L-2017-LLR-0043) Project stage: Approval 2017-06-12
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Category:Code Relief or Alternative
MONTHYEARML22255A1022022-09-21021 September 2022 Authorization and Safety Evaluation for Alternative Relief Request No. 10 - Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality or Safety ML22151A0012022-06-0707 June 2022 Authorization and Safety Evaluation for Relief Request 20, Revision 1 ML22038A1872022-02-0909 February 2022 Authorization and Safety Evaluation for Relief Request No. 19 (RR19) - the Use of an Alternative to ASME Code Case N-729-6 for Replacement Reactor Vessel Closure Head Penetration Nozzle 85 ML22020A4052022-01-24024 January 2022 Summary of January 14, 2022, Teleconference with Florida Power & Light Co. Regarding Verbal Authorization of Request for Alternative to the Requirements of ASME Code for Examination of Closure Head CEDM Housing 27 Canopy Seal Weld ML22026A1022022-01-13013 January 2022 RAIs for RR 20 - Alternate Examination of Canopy Seal Weld Control Element Drive Mechanism Number 27 Housing ML22011A0852022-01-0707 January 2022 Relief Request Number 10 Acceptance Review ML21236A1312021-09-30030 September 2021 Authorization of RR 15 Regarding Extension of ASME Requirements Related to Reactor Pressure Vessel Weld Examinations from 10 to 20 Years ML21027A2262021-02-17017 February 2021 Approval of Alternative to ASME Code, Section XI to Use an Alternative Inservice Inspection Schedule for the Reaction Vessel Closure Head Bolting ML20329A4022021-02-0303 February 2021 Approval of Alternative to Use ASME Code Case N-513-4 for Alternative Repair of Intake Cooling Water System L-2020-160, Extension of St. Lucie Unit 2 RPV Welds from 10 to 20 Years2020-10-30030 October 2020 Extension of St. Lucie Unit 2 RPV Welds from 10 to 20 Years ML20099A3482020-06-25025 June 2020 Safety Evaluation for Relief Request for Fifth Ten-Year Inservice Inspection (ISI) Interval - Alternative Risk-Informed Inservice Inspection Program for Class 1 and 2 Piping Welds L-2018-188, Inservice Inspection Plan - Fifth Ten-Year Interval Unit 1 Relief Request 62018-09-28028 September 2018 Inservice Inspection Plan - Fifth Ten-Year Interval Unit 1 Relief Request 6 ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML18018A0332018-01-26026 January 2018 Safety Evaluation of Relief Requests for the Fifth 10-Year Inservice Testing Program (EPID L-2017-LLR-0113; L-2017-LLR-0017, L-2017-LLR-0018, L-2017-LLR-0119, L-2017-LLR-0120, L-2017-LLR-0121, and L-2017-LLR-0122) ML17341A4422018-01-0404 January 2018 Relief from the Requirements of the ASME Code Relief Request No. 3 for the Fifth 10-Year Inservice Inspection Interval (CAC No. MF9288; EPID L-2017-LLR-0003) ML17334A9362018-01-0404 January 2018 Relief from the Requirements of the ASME Code Regarding Relief Request No. 17, Revision 0, for the Fourth 10-Year Inservice Inspection Interval (CAC No. MF9826; EPID L-2017-LLR-0043) ML17263A1202017-10-27027 October 2017 Inservice Inspection Plan Fourth 10-Year Interval Relief Request No. 16 (CAC No. MF9827; EPID L-2017-LLR-0044) L-2017-183, Fifth 10-Year Inservice Testing (IST) Program Interval Relief Requests PR-01 Through PR-06, and PR-09,2017-10-0606 October 2017 Fifth 10-Year Inservice Testing (IST) Program Interval Relief Requests PR-01 Through PR-06, and PR-09, ML17219A1742017-08-31031 August 2017 Relief from the Requirements of the ASME Code Regarding Relief Request 12 for the Fourth 10-Year Inservice Inspection Interval L-2017-121, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-07-24024 July 2017 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML17132A1672017-07-10010 July 2017 Inservice Inspection Plan Fourth 10 Year Interval Relief Request No. 13 L-2017-113, Inservice Inspection Plan, Fourth Ten-Year Interval Unit 1 Relief Request No. 16, Revision 02017-06-12012 June 2017 Inservice Inspection Plan, Fourth Ten-Year Interval Unit 1 Relief Request No. 16, Revision 0 L-2017-112, Inservice Inspection Plan, Fourth Ten-Year Interval Unit 1 Relief Request No. 17, Revision 02017-06-12012 June 2017 Inservice Inspection Plan, Fourth Ten-Year Interval Unit 1 Relief Request No. 17, Revision 0 ML17110A2702017-05-10010 May 2017 Inservice Inspection Plan Fourth 10-year Interval Relief Request No. 14 Rev 0 - ML16330A1182016-12-15015 December 2016 NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201) ML16292A7612016-11-0202 November 2016 Inservice Inspection Plan Fourth 10 Year Interval Relief Request No. 11 ML15196A6232015-08-10010 August 2015 Relief Request No. 7 for Use of an Alternative to the Requirements of the ASME Code ML14013A3042014-01-30030 January 2014 Relief Request No. 7 Regarding Alternative Repair for Intake Cooling Piping ML13316A5552013-12-11011 December 2013 Relief Request Number 5 for Examination of Cold Leg Dissimilar Metal Welds ML13308C4262013-11-25025 November 2013 Relief from the Requirements of the American Society of Mechanical Engineers Code Regarding Extension of Pressure Retaining Boundary During System Leakage Test ML12313A4152012-11-0909 November 2012 Relief from the Requirements of the ASME Code ML11143A0772011-07-0101 July 2011 Relief from the Requirements of the ASME Code, Relief Request No. 9 ML11136A1382011-06-23023 June 2011 Fourth 10-Year Interval Inservice Inspection Program Plan Relief Request No. 4 and Third 10-Year Interval Inservice Inspection Program Plan Relief Request No. 11 ML1003212812010-02-0505 February 2010 Third 10-Year Internal Inservice Inspection Program Plan Request for Relief 31, Revision 1 and Request for Relief 32, Revision 1 (Tac No. ME0662) L-2010-001, Inservice Inspection Plan, Fourth Ten-Year Interval Relief Request No. 62010-01-15015 January 2010 Inservice Inspection Plan, Fourth Ten-Year Interval Relief Request No. 6 ML0904103622009-02-12012 February 2009 Relief Request No. 3, Request for Alternative to ASME Code, Section XI Repair Requirements for Refueling Water Tank Bottom, TAC MD9268 ML0828404942008-11-26026 November 2008 SE for the Continued Use of Risk-Informed Inservice Inspection Program ML0824700892008-09-25025 September 2008 Safety Evaluation of Relief Request for St. Lucie Fourth 10-year Pump and Valve Inservice Testing Program ML0805000752008-03-0404 March 2008 Safety Evaluation of Relief Request No. 29, to Use Alternative Plant Conditions on Class 1 Piping and Valves TAC No. MD5145) L-2007-195, Inservice Inspection Plan Fourth Ten-Year Interval Unit 1 Relief Request 12007-12-0707 December 2007 Inservice Inspection Plan Fourth Ten-Year Interval Unit 1 Relief Request 1 L-2007-144, Submittal of Fourth Ten-Year Interval In-Service-Test Program2007-09-11011 September 2007 Submittal of Fourth Ten-Year Interval In-Service-Test Program ML0612900562006-05-26026 May 2006 Relief Request No. 5, Rev. 1 Regarding Repair of Small Bore Piping Nozzles ML0602704862006-02-10010 February 2006 Safety Evaluation for Relief Request No. 28 Steam Generator Manway Studs ML0531401962005-11-22022 November 2005 Relief Request, Reactor Coolant Piping Hot Leg Alloy-600 Small Bore Nozzles ML0507303852005-03-14014 March 2005 Ltr, Correction to SE St. Lucie, Unit 2, Ltr, Correction to SE Methodology and SG Tube Plugging Limit Change for Amendment No. 138 ML0502103922005-01-21021 January 2005 RR #6 & 7, Vessel Head Penetration Weld Repair & Flaw Evaluation (TAC Nos. MC3860, 3861) ML0501002222005-01-19019 January 2005 Ltr, Relief Request No. 8 for Radiographic Inspection of Intake Cooling Water System Piping ML0500700852005-01-10010 January 2005 Relief, Correction to SE for Relaxation Request No. 3 ML0416105142004-06-0808 June 2004 Relief, 1995 Edition Through the 1996 Addenda & Select ASME Code, Section XI, Appendix Viii, Supplement 10 Provisions, Regarding Third 10-Year Inservice Inspection Interval ML0410408512004-04-13013 April 2004 Relief, Inservice Inspection of Reactor Vessel Bottom Area & Piping in Covering Trenches 2022-09-21
[Table view] Category:Letter type:L
MONTHYEARL-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-004, 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-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, 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-2023-114, 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-2023-099, 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-2023-102, 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-2023-097, 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) L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report L-2023-041, Annual Radiological Environmental Operating Report for Calendar Year 20222023-04-0404 April 2023 Annual Radiological Environmental Operating Report for Calendar Year 2022 L-2023-051, Report of 10 CFR 50.59 Plant Changes2023-04-0404 April 2023 Report of 10 CFR 50.59 Plant Changes L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-042, Periodic Update of Population Data within 10 and 50 Miles of the Plant2023-03-27027 March 2023 Periodic Update of Population Data within 10 and 50 Miles of the Plant L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4 L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-039, Cycle 27 Core Operating Limits Report2023-03-0707 March 2023 Cycle 27 Core Operating Limits Report L-2023-032, 2022 Annual Radioactive Effluent Release Report2023-02-28028 February 2023 2022 Annual Radioactive Effluent Release Report L-2023-038, 2022 Annual Operating Report2023-02-28028 February 2023 2022 Annual Operating Report L-2023-016, Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan2023-02-15015 February 2023 Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan L-2023-019, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20222023-02-15015 February 2023 Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2022 L-2023-009, Owner'S Activity Report2023-01-31031 January 2023 Owner'S Activity Report L-2022-188, Unusual or Important Environmental Event - Turtle Mortality2022-12-19019 December 2022 Unusual or Important Environmental Event - Turtle Mortality L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022 Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 2024-01-08
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JUN 1 2 2017 L-2017-112 10 CFR 50.4 10 CFR 50.55a U.S. Nuclear Regulatory Co1nmission Attn: Document Control Desk Washington, DC 20555 Re: St. Lucie Unit 1 Docket No. 50-335 Inservice Inspection Plan Fourth Ten-Year Interval Unit 1 Relief Request No. 17, Revision 0 Pursuant to 10 CFR 50.55a(z)(1), as an alternative to the requirements specified in ASME Section XI, Appendix I, Article I-2110(b), Florida Power & Light (FPL) proposes to use procedures, personnel, and equip1nent qualified to the requirements of ASME Section XI, Appendix VIII, Su.pplements 4 and 6 of the 2001 Edition with No Addenda, as administered by the Electric Power Research Institute's (EPRI)
PDI program to conduct the reactor vessel upper Shell-to-Flange weld exa1nination. The details and justification for this request are provided in the attach1nent to this letter.
Please contact K.en Frehafer at (772) 467-77 48 if there are any questions about this submittal.
Sincerely,
~~(0~
Michael J Snyder Licensing Manager St. Lucie Plant Attachment MJS/I<WF cc: USNRC Regional Ad1ninistrator, Region II USNRC Senior Resident Inspector, St. Lucie Units 1 and 2 Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957
L-2017-112 Attachment Page 1 of 5 St. Lucie Unit 1 Fourth Inservice Inspection Interval Relief Request Number 17 Revision 0 Proposed Alternative In Accordance with 10 CFR 50.55a(z)(1)
--Alternative Provides Acceptable Level of Quality and Safety--
Alternative Ultrasonic Examination of the Reactor Pressure Vessel Flange-to-Upper Shell Weld using ASME Section XI, Appendix VIII Demonstrated Techniques
- 1. ASME Code Component(s) Affected Class 1 Reactor Pressure Vessel (RPV) upper Shell-to-Flange weld (Weld Number 7-203) subject to Ultrasonic (UT) examination.
2. Applicable Code Edition and Addenda
St. Lucie Unit 1 is currently in the 4th 10-year Inservice Inspection (ISI) interval. The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) of record for the current 10-year ISI interval isSection XI, is 2001 Edition with Addenda through 2003. The code of record for ASME Section XI, Appendix VIII is the 2001 Edition with No Addenda.
3. Applicable Code Requirement
ASME Code Class 1, Table IWB-2500-1, Pressure Retaining in Reactor Vessel, Examination Category B-A, Item Number B1.30, Shell-to-Flange Weld. ASME Section XI, Paragraph IWA-2232 states, Ultrasonic examinations shall be conducted in accordance with Appendix I. Appendix I, Article I-2110(b), requires Ultrasonic examination of reactor vessel-to-flange welds, closure head-to-flange welds, and integral attachment welds shall be conducted in accordance with Article 4 of Section V, except that alternative beam angles may be used. These examinations shall be further supplemented by Table I-2000-1.
Exam Cat. Item No. Examination Description Essentially 100% volumetric examination of the reactor B-A B1.30 vessel-to-flange weld in accordance with Appendix I, Article I-2000
L-2017-112 Attachment Page 2 of 5 St. Lucie Unit 1 Fourth Inservice Inspection Interval Relief Request Number 17 Revision 0
4. Reason for Request
FPL is performing volumetric examinations of all Reactor Pressure Vessel (RPV) welds during the upcoming 10-year Inservice Inspection (ISI). FPL is required to perform the 10-year RPV ISI pursuant to 10CFR50.55a. The Code requires that Ultrasonic (UT) examination of RPV welds, excluding the reactor vessel upper shell-to-flange weld, shall be with techniques that have been demonstrated in accordance with ASME Section XI, Appendix VIII.
Examination from the inside surface provides the best access for examination of the reactor vessel upper shell-to-flange weld. The outside surface of the RPV is inaccessible due to its placement inside the biological-shield wall and the installed insulation.
Although the reactor vessel upper Shell-to-Flange weld is specifically excluded from the requirement to utilize ASME Section XI, Appendix VIII qualified UT techniques by the referenced Code, FPL believes that performing the UT examination with Appendix VIII/PDI qualified personnel and procedures from the inside surface will provide an acceptable level of quality and safety.
- 5. Proposed Alternative and Basis for Use Proposed Alternative:
As an alternative to the requirements specified in ASME Section XI, Appendix I, Article I-2110(b), FPL proposes to use procedures, personnel, and equipment qualified to the requirements of ASME Section XI, Appendix VIII, Supplements 4 and 6 of the 2001 Edition with No Addenda, as administered by the Electric Power Research Institutes (EPRI) PDI program to conduct the reactor vessel upper Shell-to-Flange weld examination. The examinations from the inside surface will be implemented to achieve the maximum coverage possible utilizing procedures and personnel qualified by the PDI program. The proposed alternative represents the best techniques, procedures, and qualifications available to perform UT examinations of RPV welds. The PDI program addresses qualification requirements for each of the supplements that are defined in ASME Section XI, Appendix VIII. The applicable vendor procedure has been qualified in accordance with PDIs implementation of Supplements 4 and 6 of ASME Section XI, Appendix VIII.
L-2017-112 Attachment Page 3 of 5 St. Lucie Unit 1 Fourth Inservice Inspection Interval Relief Request Number 17 Revision 0 Basis for Use:
The listed weld is the only circumferential shell weld in the reactor vessel that is not examined with ASME Section XI, Appendix VIII techniques, as mandated by 10CFR50.55a. 10CFR50.55a mandates the use of ASME Section XI, Appendix VIII, Supplements 4 and 6 for the conduct of all other reactor vessel weld examinations.
ASME Section XI, Appendix I, Article I-2110(b) identifies that ASME Section V, Article 4 techniques be utilized for the examination of the reactor upper Shell-to-Flange weld.
The calibration techniques, recording criteria, and flaw sizing methods are based upon the use of a distance-amplitude-correction (DAC) curve derived from the ultrasonic responses to machined reflectors in a basic calibration block. Reflectors detected in the field require investigation only if they exceed 20% of the amplitude response of the DAC curve obtained from the machined reflectors in the basic calibration block. Indications detected in the designated examination volume with amplitudes below this threshold are therefore, not required to be recorded. The amplitude based recording threshold is generic and does not take factors into consideration such as flaw orientation, which can influence the amplitude of the UT response. Use of the ASME Section XI, Appendix VIII, qualified techniques enhance the quality of the examination. The detection criterion is more conservative because the qualified procedure requires examiners to measure and evaluate all indications determined to be flaws, regardless of their amplitude response, in accordance with the applicable criteria.
EPRI Report NP-6273, Accuracy of Ultrasonic Flaw Sizing Techniques for Reactor Vessels, dated March 1989, contains a comparative analysis of sizing accuracy for several different techniques. The results show that the UT flaw sizing techniques based upon tip diffraction are the most accurate. ASME Section XI, Appendix VIII qualified detection and sizing methodologies use analysis tools based upon echo dynamics and tip diffraction. This methodology is considered more sensitive and accurate than amplitude only based comparisons.
For the RPV upper shell-to-flange weld examinations using ASME Section XI, Appendix VIII, qualified techniques, FPL anticipates obtaining essentially 100% code volume coverage. However, if limitations are encountered that preclude obtaining essentially 100% examination coverage of the required volume, individual relief requests will be submitted.
Procedures, equipment, and personnel qualified via the PDI Appendix VIII, Supplement 4 and 6 programs have been demonstrated to have a high probability of detection and are generally considered superior to the techniques employed during previous ASME Section V, Article 4, reactor vessel weld examinations. Accordingly, approval of this alternative examination and evaluation process is requested pursuant to 10CFR50.55a
L-2017-112 Attachment Page 4 of 5 St. Lucie Unit 1 Fourth Inservice Inspection Interval Relief Request Number 17 Revision 0 (z)(1).
- 6. Duration of Proposed Alternative FPL will implement the proposed alternative Ultrasonic examination of the RPV upper Shell-to-Flange weld using PDI Demonstrated Techniques during the St. Lucie Unit 1 fourth inservice inspection interval.
- 7. Precedents Similar Relief Requests have been granted to the following plants:
NRC Safety Evaluation dated November 29, 2013, Turkey Point Units 3 and 4 - Safety Evaluation for Relief Request Nos. 10, Associated with (TAC Nos. MF0086 and MF0087), (ML13260A493).
NRC Safety Evaluation dated March 23, 2012, St. Lucie Unit No. 2, Relief from the Requirements of the ASME Code, Relief Request No. 12 (TAC No. ME6745).
NRC Safety Evaluation dated August 1, 2007, St. Lucie Nuclear Plant Unit 1, Safety Evaluation for Relief Request No. 27 Regarding Examination Methodology of Reactor Pressure Vessel Flange-to-Upper Weld (TAC No. MD2955).
- 8. Attachment to Relief Request 17 Upper Shell-to-Flange Weld Illustration
L-2017-112 Attachment Page 5 of 5 St. Lucie Unit 1 Fourth lnservice Inspection Interval Relief Request Number 17 Revision 0 Upper Shell-to-Flange Weld Illustration t~----------------- ~ZG\5.00 t~----- 1 'iL?5 ------r.------- !iH6, 50 BA.':'E MEf.;!,L tt~--- 0Hi 5.GO IV LEDGE DEPTH = 8.2.5
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