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Category:Letter type:L
MONTHYEARL-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024 2024 Population Update Analysis L-2024-129, Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval2024-08-0707 August 2024 Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval L-2024-121, Subsequent License Renewal Commitment 30 Revision2024-07-30030 July 2024 Subsequent License Renewal Commitment 30 Revision L-2024-123, Submittal of In-Service Inspection Program Owners Activity Report (OAR-1)2024-07-29029 July 2024 Submittal of In-Service Inspection Program Owners Activity Report (OAR-1) L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-114, 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-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024 Annual Radiological Environmental Operating Report for Calendar Year 2023 L-2024-064, Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report2024-04-17017 April 2024 Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report L-2024-054, 2023 Annual Environmental Operating Report2024-04-0909 April 2024 2023 Annual Environmental Operating Report L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-045, Report of 10 CFR 72.48 Plant Changes2024-03-27027 March 2024 Report of 10 CFR 72.48 Plant Changes L-2024-010, 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-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) 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 2024-08-07
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0 September 3, 2014 FPL. L-2014-265 10 CFR 54 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555-0001 St. Lucie Unit I Docket No. 50-335 License Renewal One-Time Inspection of Class 1 Small Bore Piping Inspection Plan Submittal
References:
- 1. Safety Evaluation Report Related to the License Renewal of St. Lucie Nuclear Plant, Units I and 2, NUREG-1779, September 2003.2. Letter from Joseph Jensen (FPL) to U.S. Nuclear Regulatory Commission (L-2014-059), "License Renewal One-Time Inspection of Class I Small Bore Piping Revised Commitments," March 19, 2014, ADAMS Accession No. 14087A007.
- 3. Generic Aging Lessons Learned (GALL) Report, NUREG-1801, Rev. 2, December 2010.Florida Power and Light Company (FPL) has License Renewal (LR) commitments for St. Lucie Units I and 2 to perform a one-time inspection of Class I Small Bore Piping prior to the end of the initial operating license term. For St. Lucie Unit 1 specifically, this inspection was originally addressed by Commitment 7 listed in Appendix D, Table I of Reference
- 1. The Unit 1 small bore piping inspection requirements were revised in Reference 2, such that this one-time inspection will follow the guidance provided in the Reference 3, Section AMP XI.M35, "One-Time Inspection of ASME Code Class I Small-Bore Piping." St. Lucie Unit 1 Updated Final Safety Analysis Report (UFSAR), Section 18.1.5, Small Bore Class I Piping Inspection, states that a report describing the details of the one-time inspection plan will be submitted prior to the implementation of the inspection.
To comply with UFSAR Section 18.1.5 requirements, the one-time Class I Small Bore Piping Program Inspection Plan is provided herein in the Attachment.
Should you have any questions, please contact Mr. Eric Katzman, Licensing Manager, at 772-467-7734.( y yours, Site Vice President St. Lucie Plant C--JJ/lrb _ ,O c(Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957 L-2014-265 10 CFR 54 Page 2 of 2
Attachment:
St. Lucie Unit I One-Time ASME Code Class I Small-Bore Piping Inspection Plan (4 pages)cc: USNRC Regional Administrator, Region II USNRC Senior Resident Inspector, St. Lucie Plant L-2014-265 Attachment Page 1 of 4 St. Lucie Unit 1 ASME Code Class 1 Small-Bore Piping One Time Inspection Plan, Revision 0 L-2014-265 Attachment Page 2 of 4 Plan Description This plan augments the requirements in American Society of Mechanical Engineers (ASME) Code,Section XI, 1998 edition with Addenda through 2000, and is applicable to small-bore ASME Code Class 1 piping and systems less than 4 inches nominal pipe size (less than NPS 4) and greater than or equal to NPS 1. The plan includes pipes, fittings, branch connections, and all full and partial penetration (socket) welds. This plan was developed using the Generic Aging Lessons Learned (GALL) Report, NUREG-1801, Rev. 2 XI.M35; One-Time Inspection of ASME Code Class 1 Small-Bore Piping as guidance.A one-time inspection to detect cracking resulting from thermal and mechanical loading, vibration, or intergranular stress corrosion of full penetration welds will be performed by volumetric examination.
A one-time inspection to detect cracking in socket welds will be performed by either volumetric or destructive examination.
The number of welds to be examined will be on a sample basis as described in Section 4 of this plan. The sample of welds to be examined will be selected using the risk-informed approach as approved by the NRC for St. Lucie Nuclear Plant, Units No. 1 and 2 -Fourth 10-Year Interval Inservice Inspection Program Plan Relief Request No. 1 (TAC NO.MD7739)These inspections will provide additional assurance that either aging of small-bore ASME Code Class 1 piping is not occurring or the aging is insignificant, such that a plant-specific Aging Management Program (AMP) is not warranted.
Should evidence of cracking be revealed by the one-time inspection, a periodic inspection plan will be developed and implemented using a plant-specific AMP.A search of the St. Lucie Corrective Action Program and the ASME Section XI, Repair and Replacement Reports over the operating history of St. Lucie Unit 1 was performed to detennine if any ASME Code Class 1 Small-Bore Piping greater than or equal to NPS 1 and less than NPS 4 had experienced cracking.
No instance of cracking of ASME Code Class 1 Small-Bore Piping greater than or equal to NPS 1 and less than NPS 4 was identified.
Evaluation and Technical Basis 1. Scope of Plan: This plan is a one-time inspection of a sample of ASME Code Class 1 piping less than NPS 4 and greater or equal to NPS 1. This plan includes measures to verify that degradation is not occurring, thereby confirming that there is no need to manage age-related degradation.
The one-time inspection plan for ASME Code Class 1 small-bore piping includes locations that are susceptible to cracking.
The sample of welds will be selected using the risk-informed approach as approved by the NRC for St. Lucie Nuclear Plant, Unit No. 1 -Fourth 10-Year Interval Inservice Inspection Program Plan Relief Request No. 1 (TAC NOS. MD7739).All ASME Class 1 pipe segments less than 4-inch NPS and greater than equal to 1-inch NPS have the same Low Safety Significance Risk Ranking and, as such, all welds were given the same level of consideration.
- 2. Preventive Actions: This plan is a condition monitoring activity independent of methods to mitigate or prevent degradation.
- 3. Parameters Monitored/Inspected:
This inspection is intended to detect potential cracking in ASME Code Class 1 small-bore piping.
L-2014-265 Attachment Page 3 of 4 4. Description of Aging Effects: This one-time inspection is designed to provide assurance that aging of ASME Code Class 1 small-bore piping is not occurring, or that the effects of aging are not significant.
The one-time inspection to detect cracking in socket welds will be either a volumetric or destructive examination.
The inspection to detect cracking resulting from thermal and mechanical loading, vibration, or intergranular stress corrosion of full penetration welds will be a volumetric examination.
Volumetric examination will be performed using demonstrated techniques from the ASME Code that are capable of detecting the aging effects in the examination volume of interest.
The inspection will be performed at a sufficient number of locations to ensure an adequate sample. This number, or sample size, is based on susceptibility, accessibility, dose considerations, operating experience, and limiting locations of the total population of ASME Code Class 1 small-bore piping inspections.
The inspection sample size will be at least 3%, up to a maximum of 10 welds, of each weld type, for each operating unit using a methodology to select the most susceptible and risk-significant welds from the risk-informed approach as described above. For socket welds, destructive examination may be performed in lieu of volumetric examinations.
Because more information can be obtained from a destructive examination than from nondestructive examination, credit will be taken for each weld destructively examined equivalent to having volumetrically examined two welds.St. Lucie Unit 1 Weld Type Approx. 3% Sample Size Number (Max 10 Welds Each Type)" Volumetric OR Destructive Socket 493 15 N/A 5 (NPS-2 and smaller)Full Penetration 92 3 3 N/A (Greater than NPS-2 and less than NPS-4)5. Monitoring and Trending:
This is a one-time inspection to determine whether cracking in ASMEE Code Class 1 small-bore piping resulting from stress corrosion, cyclical (including thermal, mechanical, and vibration fatigue) loading, or thermal stratification and thenrial turbulence (MRP 146 and MRP 146S) is an issue. Evaluation of the inspection results may indicate the need for additional or periodic examinations (i.e., a plant-specific AMP for Class 1 small-bore piping using volumetric inspection methods consistent with ASME Code,Section XI, Subsection IWB).6. Acceptance Criteria:
If flaws or indications exceed the acceptance criteria of ASME Code,Section XI, Paragraph IWB-3400, they are evaluated in accordance with ASME Code, Section L-2014-265 Attachment Page 4 of 4 XL, Paragraph IWB-3 131; additional inspections are performed in accordance with ASME Code,Section XI, Paragraph IWB-2430.
Evaluation of flaws identified during a volumetric examination of socket welds will be in accordance with IWB-3600.7. Corrective Actions: The site corrective action program, quality assurance procedures, site review and approval process, and administrative controls are implemented in accordance with the requirements of 10 CFR Part 50, Appendix B. Should evidence of cracking be revealed by the one-time inspection, a periodic inspection will be developed and implemented, using a plant-specific AMP.8. Confirmation Process: The requirements of 10 CFR Part 50, Appendix B are used to address the confirmation process.9. Administrative Controls:
The requirements of 10 CFR Part 50, Appendix B are used to address the administrative controls.10. Operating Experience:
This one-time inspection plan uses volumetric inspection techniques with demonstrated capability and a proven industry record and/or destructive examinations to detect cracking in piping weld and base material.
Currently, an industry proven volumetric technique for detection, sizing and performing analytical evaluation of flaws in socket welds has not been established; therefore, a destructive examination will be performed.