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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
MONTHYEARIR 05000335/20230102024-01-26026 January 2024 NRC Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000335/2023010 and 05000389/2023010 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) IR 05000335/20230042024-01-24024 January 2024 Integrated Inspection Report 05000335/2023004 and 05000389/2023004 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, ML23332A1772023-11-28028 November 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals IR 05000335/20230032023-11-0606 November 2023 Integrated Inspection Report 05000335/2023003 and 05000389/2023003 ML23270B8882023-10-23023 October 2023 Regulatory Audit Summary Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components for Nuclear Power Reactors EPID L-2022-LLA-0182 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 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 IR 05000335/20233012023-09-20020 September 2023 NRC Operator License Examination Report 05000335/2023301 and 05000389/2023301 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-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes 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-2023-112, 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 ML23219A0042023-09-0101 September 2023 Transmittal Letter - Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1and 2, Revision 1 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 IR 05000335/20230022023-08-0707 August 2023 Integrated Inspection Report 05000335/2023002 and 05000389/2023002 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23212B2652023-07-27027 July 2023 Operator Licensing Written Examination Approval 05000335/2023301 and 05000389/2023301 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 ML23200A1232023-07-21021 July 2023 Transmittal Letter for the St. Lucie SLRA Review 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) ML23184A0352023-06-30030 June 2023 Notification of St. Lucie Units 1 & 2 Focused Engineering Inspection (FEI) 05000335/2023010 and 05000389/2023010 and Initial Information Request 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) IR 05000335/20234032023-06-29029 June 2023 Security Inspection Report 05000335/2023403 and 05000389/2023403 IR 05000335/20234022023-06-20020 June 2023 Security Baseline Inspection Report 05000335/2023402 and 05000389/2023402 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 IR 05000335/20234012023-05-16016 May 2023 Cyber Security Inspection Report 05000335/2023401 and 05000389/2023401 (Cover Letter) IR 05000335/20230012023-05-0909 May 2023 Integrated Inspection Report 05000335/2023001 and 05000389/2023001 ML23109A1132023-04-30030 April 2023 SLRA Change Schedule Letter 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 ML23097A1642023-04-17017 April 2023 Summary of March 23, 2023, Meeting with Florida Power and Light on St. Lucie and Turkey Point Improved Technical Specifications Conversion License Amendment Requests L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report 2024-01-08
[Table view] Category:Safety Evaluation
MONTHYEARML23219A0032023-09-0101 September 2023 SLRA SER Rev 1 ML23200A1462023-07-21021 July 2023 Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1 and 2 ML22255A1022022-09-21021 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 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 ML21342A2092022-01-14014 January 2022 Issuance of Amendment Nos. 252 and 207 to Allow Risk-Informed Completion Times (RICT) for the 120-Volt Alternating Current (AC) Instrument Bus Requirements 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 ML21022A2192021-02-26026 February 2021 Issuance of Amendment No. 206 to Replace the Current Time-Limited Reactor Coolant System Pressure/Temperature Limit Curves and LTOP Setpoints with Curves and Setpoints That Will Remain Effective for 55 Effective Full Power 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 ML20259A2982020-11-18018 November 2020 Issuance of Amendment No. 205 Regarding Modification of the Reactor Coolant Pump Flywheel Inspection Program ML20237F2572020-10-30030 October 2020 Issuance of Amendment Nos. 251 and 204 Regarding Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 Development of Emergency Action Levels for Non-Passive Reactors 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 ML20023B3782020-02-19019 February 2020 Safety Evaluation for Relief Request RR-16, Alternate Repair of 2B Boric Acid Makeup Pump Revision for the Fourth 10-Year Inservice Inspection Interval ML20015A1232020-02-0606 February 2020 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19266A0722020-01-27027 January 2020 Issuance of Amendment Nos. 250 and 202 Regarding Technical Specification Changes to Allow the Performance of Selected Emergency Diesel Generator Surveillance Requirements During Power Operation ML19254B5332019-09-30030 September 2019 Safety Evaluation for Relief Request RR#15, Revision 0, Regarding Limited Piping Examinations ML19148A7442019-07-31031 July 2019 Issuance of Amendment Nos. 161, 249, 200, 287, and 281 to Add Technical Specification Limiting Condition for Operation 3.0.6 ML19203A1662019-07-26026 July 2019 Issuance of Exigent Amendment No. 248 Technical Specification 3/4.8.1 Change to Allow for a One-Time Extension of the Allowed Outage Time for One Emergency Diesel Generator ML19115A2812019-05-31031 May 2019 Safety Evaluation for Relief Request No. 6 for the Fifth 10 Year Inservice Inspection Interval ML19058A4922019-04-23023 April 2019 Issuance of Amendment 198 Regarding Technical Specification Changes to Reduce the Number of Control Element Assemblies ML18274A2242018-11-0202 November 2018 Issuance of Amendment Nos. 246 and 197 Regarding Technical Specifications Site Area Map ML18256A0982018-10-30030 October 2018 Safety Evaluation for Relief Request No.5 for the Fifth 10-Year Inservice Inspection Interval ML18129A1492018-07-0909 July 2018 Issuance of Amendments Regarding Technical Specification Changes Related to the Auxiliary Feedwater System (CAC Nos. MG0237 and MG0238; EPID L-2017-LLA-0296) ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML18046A7122018-03-26026 March 2018 Issuance of Amendments Regarding the Unusual Event Fire Related Emergency Action Level Scheme 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) 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) 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) ML17257A0152017-10-31031 October 2017 Issuance of Amendments Regarding Technical Specification Changes Related to the Reactor Protection System and Limiting Condition for Operation 3.0.5 ML17263A1202017-10-27027 October 2017 Inservice Inspection Plan Fourth 10-Year Interval Relief Request No. 16 (CAC No. MF9827; EPID L-2017-LLR-0044) ML17248A3792017-10-23023 October 2017 Issuance of Amendments to Revise the Renewed Facility Operating Licenses Fire Protection License Conditions (CAC Nos. MF9681 and MF9682; EPID L-2017-LLA-0230) ML17235A5652017-10-0505 October 2017 Issuance of Amendments Regarding Technical Specification Changes Related to Component Cyclic or Transient Limits 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 ML17195A2912017-08-14014 August 2017 Issuance of Amendments Regarding Relocation of Radiation Monitor Requirements from Technical Specifications to Licensee-Controlled Documents ML17132A1672017-07-10010 July 2017 Inservice Inspection Plan Fourth 10 Year Interval Relief Request No. 13 ML17110A2702017-05-10010 May 2017 Inservice Inspection Plan Fourth 10-year Interval Relief Request No. 14 Rev 0 - ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17038A2252017-03-29029 March 2017 Issuance of Amendment No. 188 Regarding Emergency Diesel Generator Day Tank Volume 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) ML16251A1282016-12-0505 December 2016 Issuance of Amendments to Update Appendix B to the Renewed Facility Operating License to Incorporate the 2016 Biological Opinion ML16292A7612016-11-0202 November 2016 Inservice Inspection Plan Fourth 10 Year Interval Relief Request No. 11 ML16166A4242016-10-0505 October 2016 St. Lucie Plant, Unit Nos. 1 and 2 - Issuance of Amendments Regarding the Use of a New Computer Code to Model the Containment Vacuum Analyses ML16183A1382016-09-19019 September 2016 Issuance of Amendments Regarding Technical Specification Change to Eliminate the Moderator Temperature Coefficient Surveillance Test at the End of Cycle ML16210A3742016-08-30030 August 2016 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-422, Revision 2 ML16103A3972016-07-28028 July 2016 Issuance of Amendments Regarding Removal of Technical Specification for Cleaning Fuel Oil Storage Tank Sediment and Relocating Procedures to Licensee Controlled Documents ML16167A4732016-07-0505 July 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16139A5882016-05-27027 May 2016 Inservice Inspection Plan Fourth 10-Year Interval Relief Request No. 10, Revision 0 ML16124A3832016-05-25025 May 2016 St. Lucie Plant, Unit No. 1 - Issuance of Amendment Regarding Changes to the Snubber Surveillance Requirements (CAC No. MF6490) ML16063A1212016-04-19019 April 2016 Redacted - Issuance of Amendment Regarding License Amendment Request for the Transitioning to Areva Fuel ML15344A3462016-03-31031 March 2016 Issuance of Amendments Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with Title 10 of the Code of Federal Regulations Section 50.48(c) (CAC Nos. MF1373 & MF1374) 2023-09-01
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 12, 2009 Mr. Mano Nazar Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
ST. LUCIE PLANT, UNIT 1 - RELIEF REQUEST NO.3, REQUEST FOR ALTERNATIVE TO ASME CODE, SECTION XI REPAIR REQUIREMENTS FOR REFUELING WATER TANK BOTTOM (TAC NO. MD9268)
Dear Mr. Nazar:
By letter dated April 9, 2008, as supplemented by letter dated September 29,2008, Florida Power & Light Company (FPL), the licensee, submitted Relief Request No.3, "Alternative to AMSE Code,Section XI Repair Requirements for Refueling Water Tank Bottom." The licensee requested relief from certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code requirements at St. Lucie, Unit 1.
FPL installed a reinforced vinyl ester liner on the bottom of the St. Lucie, Unit 1 Refueling Water Tank (RWT) in 1994. The Nuclear Regulatory Commission (NRC) previously approved the use of this liner as an alternative non-Code repair for the second and third 1O-year inservice inspection intervals. Relief Request NO.3 was submitted to address the use of the installed RWT liner during the fourth 10-year inspection interval. Based on the enclosed safety evaluation, the staff finds the Inservice Inspection Program Request for Alternative acceptable pursuant to Title 10 of the Code of Federal Regulations, Section 50.55a(a)(3)(i).
Further details on the bases for the NRC staff's conclusions are contained in the enclosed safety evaluation. If you have any questions regarding this issue, please feel free to contact Siva Lingam at (301) 415-1564.
Sincerely,
, Chief Plant Licensing ranch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-335
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION INSERVICE INSPECTION PROGRAM RELIEF REQUEST NO.3 ST. LUCIE PLANT, UNIT 1 FLORIDA POWER AND LIGHT COMPANY.
DOCKET NO. 50-335
1.0 INTRODUCTION
By letter dated April 9,2008, as supplemented by letter dated September 29,2008, the Florida Power & Light Company (FPL, the licensee) requested relief from certain American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code requirements at S1. Lucie, Unit 1. FPL installed a reinforced vinyl ester liner on the bottom of the S1. Lucie, Unit 1 Refueling Water Tank (RWT) in 1994. The Nuclear Regulatory Commission (NRC) approved the use of this liner as an alternative non-Code repair for the second and third 1O-year inservice inspection (lSI) intervals via approval of Relief Request (RR) 13, RR-07, and RR-7A. RR-3 was submitted to address the use of the installed RWT liner during the fourth 1O-year inspection interval. Relief was requested from the Repair and/or Replacement requirements of the ASME Boiler and Pressure Vessel Code,Section XI, 2001 Edition through the 2003 Addenda, Articles IWA-4000 and IWC-3000. In particular, FPL proposed to leave the installed fiberglass reinforced vinyl ester liner in place on the S1. Lucie, Unit 1 RWT bottom, and to consider this installation as an alternative design equivalent to an ASME Code repair or replacement of the RWT bottom. In support of this request, FPL proposed to continue to use an augmented inspection program for the bottom liner installation.
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(g)(4), requires, in part, that "throughout the service life of a boiling or pressurized water-cooled nuclear power facility, components (including supports) which are classified as ASME Code Class 1, Class 2 and Class 3 must meet the requirements ... set forth in Section XI of editions of the ASIV1E Boiler and Pressure Vessel Code ... to the extent practical within the limitations of design, geometry, and materials of construction of the components." However, 10 CFR 50.55a(a)(3)(i) allows alternatives to the requirements of Section XI of the ASME Code, when an applicant can demonstrate that the alternative program will provide an acceptable level of quality and safety in lieu of complying with the requirements in Section XI.
The licensee submitted the subject relief request, pursuant to 10 CFR 50.55a(a)(3)(i), which proposed an alternative to the implementation of the ASME Boiler and Pressure Vessel Code, Enclosure
-2 Section XI, 2001 Edition through the 2003 Addenda, Articles IWA-4000 and IWC-3000. In particular, FPL proposed to leave the installed fiberglass-reinforced vinyl ester liner in place on the St. Lucie, Unit 1 RWT bottom, and to consider this installation as an alternative design equivalent to an ASME Code repair or replacement of the RWT bottom. In support of this request, FPL proposed to continue to use an augmented inspection program for the bottom liner installation during the fourth 1O-year inspection interval, which begins on February 11,2008, and ends on February 10, 2018.
3.0 BACKGROUND
In July 1993, a small leak approximately 3/16 inch in diameter was discovered in an area on the RWT bottom near the east side of the tank. The failure mechanism was galvanic corrosion (resulting from a galvanic couple between the exterior surface of the RWT aluminum alloy floor and the surrounding copper ground grid), which was manifested as pitting type attack. The root cause of the failure was determined to be the absence of a seal between the tank bottom plates and the concrete ring wall, which permitted the periodic ingress of water into the sand/oil cushion layer beneath the tank. This water likely contained dissolved salts that had been formerly deposited on the tank walls and in the surrounding earth. As this water permeated the sand layer beneath the tank, it rendered the soil more conductive, thus increasing the susceptibility of the exterior of the tank floor plates to corrosive galvanic attack. The root cause evaluation included a recommendation for installation of a joint sealing compound between the tank bottom plates and the concrete ring wall to prevent further ingress of water. This installation was performed via a controlled Work Order. Additionally, the area around the RWT was regraded to prevent standing water from rising to a level above the top of the ring wall foundation. Elimination of water from the sand layer beneath the tank will arrest further galvanic corrosion by eliminating the conductive electrolyte in contact with the tank floor and the ground grid. Further corrosion due to the presence of salts in the sand layer will be minimal if further water ingress is prevented.
RR-13, dated July 30, 1993, was submitted to the I\IRC requesting NRC approval for a non-Code repair involving the use of an epoxy coating to adhere an aluminum plate to the tank bottom over the hole. The non-Code repair was implemented using a 1/8-inch thick, 3-inch diameter piece of aluminum plate and Duromar SARUW epoxy. Additional testing confirmed that there was no further leakage from the identified location. In the RR, FPL committed to providing an ASME Code acceptable repair during the unit's fall 1994 refueling outage (SL1-13).
Engineering documents were prepared to support the implementation of a permanent ASME Code repair during the SL1-13 refueling outage. This repair, as designed, involved removal of the section of the bottom plate that contained the identified leak, and welding of a new 1/4-inch aluminum plate section to the existing bottom plate to cover the opening left by the removal of the temporarily repaired plate. When the bottom plate section was removed from the RWT bottom during the fall 1994 outage, visual inspection revealed corrosion on the exterior surface, scattered pitting, and patches of a loosely adherent white corrosion product (likely aluminum oxide). During the installation of the new plate section, difficulties were experienced in completing the ASME Code repair. The thinning of the base material, coupled with conditions associated with welding inside the contaminated environment, led to localized defects. This resulted in an inability to qualify the welds; for this reason, the ASME Code repair could not be implemented.
-3 As an alternative to the ASME Code repair, a fiberglass reinforced vinyl ester liner (Protecto-Line 800 system, manufactured by Dudick, Inc.) was applied to the inside surface of the RWT bottom. The liner system is a 1/8-inch (approximate) thick coating consisting of a prime coat, a troweled base coat with a layer of fiberglass roving, and a top coat. Prior to application, the aluminum surfaces to receive the liner were abrasive blasted to obtain the specified surface profile and anchor pattern. The surface was inspected to ensure proper preparation for the application of the coating. The liner was applied over the entire tank bottom, and extended approximately 24-inches up the tank wall. The liner was visually inspected to verify proper installation. The installation of this liner system was performed during the fall 1994 SL1-13 refueling outage. The liner installation was a non-Code repair. For this reason, FPL submitted RR-13A dated November 16, 1994, to the NRC for approval of the use of this liner.
The NRC granted relief to install and use the Protecto-Line 800 system in a letter and safety evaluation dated November 25, 1994. The RWT was placed in service immediately following the installation and inspection of the liner material; the liner system has satisfactorily performed its required functions since its installation.
Laboratory test results of the physical properties provided the necessary confirmation of the ability of the Dudick system to perform its intended functions as a liner for the RWT. Samples of the liner material (primer, coatings, filler, hardener, and fiberglass roving) were subjected to chemical analysis to confirm the composition of the liner materials, and to determine whether the amounts of impurities in the materials are within the limits specified in plant procedures for materials used in the primary system. The results of this testing were documented and indicated that the Dudick Protecto-Line 800 liner is composed of materials specified by Dudick, Inc., and that the levels of impurities in the material are within the specified limits.
4.0 TECHNICAL EVALUATION
4.1 Component Affected The RWT is an above ground storage tank which provides a source of primary grade borated water for refueling, reactor coolant makeup, and reactivity control during plant operations, and accident conditions. The RWT is a Quality Group B, ASME Code Class 2 structure, and was designed and erected in accordance with American National Standards Institute (ANSI)
B96.1-1967.
4.2 ASME Code Requirements for which Relief was Requested Relief was requested from the Repair and/or Replacement requirements of the ASME Boiler and Pressure Vessel Code,Section XI, 2001 Edition through the 2003 Addenda, Articles IWA-4000 and IWC-3000.
Subparagraph IWC-3132 of the 2001 Edition through the 2003 Addenda of ASME Code Section XI states that relevant flaws that are detected in ASME Code Class 2 structures or components as a result of an inservice visual examination shall be unacceptable for continued service unless it is demonstrated that the flaws are acceptable by "Supplemental Examination,"
"Corrective Measures or Repair Replacement," or "Evaluation."
-4 Article IWA-4000 of the 2001 Edition through the 2003 Addenda of ASME Code Section XI provides the general and specific requirements for performing welded repairs of ASME Code Class 2 components that do not meet the acceptance standards for continued service contained in Subparagraph IWC-3132 to the 2001 Edition through the 2003 Addenda of ASME Code Section XI.
4.3 Duration of Relief Request This RR for S1. Lucie, Unit 1 is applicable to its fourth 1O-year lSI interval, which began on February 11, 2008, and ends on February 10, 2018.
4.4 Proposed Alternative Program Relief was requested from the Repair and/or Replacement requirements of the ASME Code,Section XI, 2001 Edition through the 2003 Addenda, Articles IWA-4000 and IWC-3000. In particular, FPL proposed to leave the installed fiberglass-reinforced vinyl ester liner (installed in 1994) in place on the S1. Lucie, Unit 1 RWT bottom, and to consider this installation as an alternative design equivalent to an ASME Code repair or replacement of the RWT bottom. In support of this request, FPL proposed to continue to use an augmented inspection program for the bottom liner installation.
4.5 Licensee's Basis for the Relief Request Inspections of the RWT liner have been performed in accordance with the approved augmented inspection program. Based on the results of these inspections, FPL requested NRC approval for continued use of the installed fiberglass-reinforced vinyl ester liner during the fourth 10-year lSI interval (beginning 2/11/08) as an approved alternative design equivalent to an ASME Code repair or replacement of the RWT bottom. In support of this request, FPL proposed to continue the augmented inspection program in accordance with the previously approved schedule. This will require that the RWT be drained and a hands-on inspection of the liner performed every sixth refueling outage (approximately once every 9 years). The next hands-on inspection would occur at SL1-26. During refueling outages for which a hands-on inspection is not performed, a remote visual inspection is required. (Note that the remote visual inspections may be performed with the unit on-line, within a period approximately 3 weeks before or following the designated refueling outage.) The water level in the RWT is monitored by four Rosemount level transmitters. S1. Lucie, Unit 1 Technical Specification 4.5.4 requires that the RWT be demonstrated to be operable at least once every 7 days (while in Modes 1 - 4) by verifying the water level in the tank. Although the Technical Specification action statement would not be entered until the tank volume becomes less than the minimum value (401,800 gallons of borated water), any continuous reduction in tank inventory would be noticed by Operations.
This is the means by which the original RWT leak was discovered in 1993. A review of the condition report database has shown no evidence of such inventory loss. Thus, there is no evidence of leakage from the S1. Lucie, Unit 1 RWT.
The use of the RWT liner with the continuation of the augmented inspection schedule is considered acceptable for the following reasons:
-5 Special process controls were used during installation (under the direct supervision of the Nuclear Coatings Specialist).
The material of the liner, as verified through laboratory testing.
The historical performance of the liner.
The results of the inspections performed to date.
The nature of the water stored in the tank.
Also, should any RWT liner inspections indicate unacceptable results, or if there are any documented occurrences of leakage through the RWT bottom, the inspection schedule (and types of inspections required) shall be revised as follows: a full hands-on inspection shall be performed during the first refueling outage following the unacceptable inspection results or documented leakage, and during every third refueling outage thereafter (through the end of the fourth 1O-year lSI interval).
4.6 Staff Evaluation of the Requested Alternative Program The RWT is an above ground aluminum tank sitting on a sand bed and supported by a concrete ring foundation. The RWT is a Quality Group B, ASME Class 2 structure constructed in accordance with ANSI B96.1-1967. A copper ground grid is below the tank and the licensee has reported that there has been a galvanic coupling between the tank bottom and the ground grid.
The RWT was drained in 2005 (six operating cycles after the original hands-on inspection) and inspected by the Nuclear Coatings Specialist and an Engineering representative. The liner met the acceptance criteria for all of the properties listed below, and showed no degradation that could affect its ability to perform its required functions. FPL performed nondestructive tests of the coating liner to test the liner for acceptability of the following conditions and properties:
hardness, delamination, adhesion, peeling, flaking, undercutting, blistering, cracking, discoloration, holidays (i.e., voids), and pinholes.
The NRC previously approved the installation of the fiberglass reinforced vinyl ester as an acceptable alternate repair method by safety evaluation dated November 25, 1994. The current liner inspection program, approved in the I\IRC safety evaluation of June 22, 2001, for the third 10-year lSI interval consists of the following inspections of the RWT:
Beginning with the fall 2008 refueling outage (SL1-22), and during every refueling outage for which a full, hands-on inspection is not scheduled a remote visual inspection of the RWT liner will be performed. Inspections will be performed or observed by the Nuclear Coatings Specialist (or designee) and an Engineering representative.
Draining of the borated water inventory of the tank and performing a full hands-on examination of the RWT during every sixth refueling outage (the next hands-on
-6 inspection would occur at SL1-26). Inspections will be performed or observed by the Nuclear Coatings Specialist (or designee) and an Engineering representative.
Should any RWT liner inspections indicate unacceptable results, or if there are any documented occurrences 01' leakage through the RWT bottom, the inspection schedule (and types of inspections required) shall be revised as shown in Section 4.5 above.
The proposed inspection schedule outlined above is only applicable through the end of the fourth 10-year lSI interval. A separate submittal must be made to the NRC regarding a proposed inspection schedule for the period beginning with the fifth 1O-year lSI interval (which begins on February 11,2018), if the licensee intends to continue utilizing the installed non-Code repair.
The proposed inspection schedule must be based on the results of inspections performed up to the time of submittal, along with the documented performance of the RWT liner.
Previous remote visual and full hands-on inspections and hands-on testing of the liner have indicated that the alternative vinyl ester coating repair is performing as expected. Previous independent test laboratory results of the liner material confirmed that the correct lining material was used. In addition, the proposed inspection schedule calls for FPL to continue its inspections of the caulking material between the RWT bottom and the concrete foundation ring wall on an annual basis. The inspection of the caulking material between the RWT bottom and the concrete ring wall will improve the chances that the sand bed will remain dry and that galvanic corrosion effects will not be significant.
4.0 CONCLUSION
Based on the discussion above, the staff concludes that the fiberglass reinforced vinyl ester liner in the RWT is performing as expected and is structurally acceptable for continued service and will provide an acceptable level of quality and safety. The staff's conclusion is predicated on the licensee's continued implementation of the liner inspection program specified in the April 9, 2008, and September 29, 2008 submittals. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the staff authorizes the proposed RR-3 for the use of this liner as an alternative non-Code repair of the RWT. This RR is authorized for the St. Lucie, Unit 1 fourth 1O-year lSI interval that began on February 11, 2008 and ends on February 10, 2018.
All other ASME Code,Section XI requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.
Principle Contributor: Edward Andruszkiewicz Date: February 12, 2009
February 12, 2009 Mr. Mano Nazar Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
ST. LUCIE PLANT, UNIT 1 - RELIEF REQUEST NO.3, REQUEST FOR ALTERNATIVE TO ASME CODE, SECTION XI REPAIR REQUIREMENTS FOR REFUELING WATER TANK BOTTOM (TAC NO. MD9268)
Dear Mr. Nazar:
By letter dated April 9, 2008, as supplemented by letter dated September 29,2008, Florida Power & Light Company (FPL), the licensee, submitted Relief Request No.3, "Alternative to AMSE Code,Section XI Repair Requirements for Refueling Water Tank Bottom." The licensee requested relief from certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code requirements at St. Lucie, Unit 1.
FPL installed a reinforced vinyl ester liner on the bottom of the St. Lucie, Unit 1 Refueling Water Tank (RWT) in 1994. The Nuclear Regulatory Commission (NRC) previously approved the use of this liner as an alternative non-Code repair for the second and third 1O-year in-service inspection intervals. Relief Request No.3 was submitted to address the use of the installed RWT liner during the fourth 1O-year inspection interval. Based on the enclosed safety evaluation, the staff finds the Inservice Inspection Program Request for Alternative acceptable pursuant to Title 10 of the Code of Federal Regulations, Section 50.55a(a)(3)(i).
Further details on the bases for the NRC staff's conclusions are contained in the enclosed safety evaluation. If you have any questions regarding this issue, please feel free to contact Siva Lingam at (301) 415-1564.
Sincerely, IRA!
Thomas H. Boyce, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-335
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC RidsOgcRp RidsN rrDciCvib LPL2-2 r/f RidsAcrsAcnwMailCenter RidsNRRPMSLingam RidsNrrLABClayton (Hard Copy) RidsN rrDorlLpl2-2 ~IPaige, NRR EAndruszkiewicz RidsRgn2MailCenter JAdams, EDO ADAMS Accession No ML090410362 OFFICE LPL2-2/PM LPL2-2/PM LPL2-2/LA DCI/CVIB LPL2-2/BC NAME JPaige SLingam BClayton MMitchel1 TBoyce DATE Memo dated 2/11/09 2/11/09 2/11/09 2/12/09 1/30/09 OFFICIAL RECORD COpy