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Category:Letter type:L
MONTHYEARL-2024-085, Refueling Outage SL1-32 Low Pressure Turbine Rotor Inspection Results2024-10-15015 October 2024 Refueling Outage SL1-32 Low Pressure Turbine Rotor Inspection Results L-2024-165, Report of 10 CFR 50.59 Plant Changes, Tests and Experiments Made2024-10-14014 October 2024 Report of 10 CFR 50.59 Plant Changes, Tests and Experiments Made L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-2024-155, Subsequent License Renewal Application, Third Annual Update2024-09-27027 September 2024 Subsequent License Renewal Application, Third Annual Update L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-138, License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles2024-09-11011 September 2024 License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles L-2024-148, Submittal of Offsite Dose Calculation Manual (Odcm), Revision 552024-09-0909 September 2024 Submittal of Offsite Dose Calculation Manual (Odcm), Revision 55 L-2024-140, Cycle 28 Core Operating Limits Report2024-08-14014 August 2024 Cycle 28 Core Operating Limits Report L-2024-133, Snubber Program Plan Submittal2024-08-14014 August 2024 Snubber Program Plan Submittal L-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024 2024 Population Update Analysis L-2024-129, Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval2024-08-0707 August 2024 Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval L-2024-121, Subsequent License Renewal Commitment 30 Revision2024-07-30030 July 2024 Subsequent License Renewal Commitment 30 Revision L-2024-123, Submittal of In-Service Inspection Program Owners Activity Report (OAR-1)2024-07-29029 July 2024 Submittal of In-Service Inspection Program Owners Activity Report (OAR-1) L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-117, Safety Injection Tank Vent Through Wall Leakage2024-07-11011 July 2024 Safety Injection Tank Vent Through Wall Leakage 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-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024 Cycle 27 Core Operating Limits Report L-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024 Cycle 32 Core Operating Limits Report L-2024-064, Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report2024-04-17017 April 2024 Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report L-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024 Annual Radiological Environmental Operating Report for Calendar Year 2023 L-2024-054, 2023 Annual Environmental Operating Report2024-04-0909 April 2024 2023 Annual Environmental Operating Report L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-045, Report of 10 CFR 72.48 Plant Changes2024-03-27027 March 2024 Report of 10 CFR 72.48 Plant Changes L-2024-011, and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2024-023, Unusual or Important Environmental Event - Turtle Mortality2024-03-0606 March 2024 Unusual or Important Environmental Event - Turtle Mortality L-2024-027, Safety Injection Tank Vent Through Wall Leakage2024-02-29029 February 2024 Safety Injection Tank Vent Through Wall Leakage L-2024-015, 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 2023 Annual Radioactive Effluent Release Report L-2024-029, 2023 Annual Operating Report2024-02-28028 February 2024 2023 Annual Operating Report L-2024-026, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-02-27027 February 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 L-2023-175, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report 2024-09-09
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-2024-155, Subsequent License Renewal Application, Third Annual Update2024-09-27027 September 2024 Subsequent License Renewal Application, Third Annual Update L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-138, License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles2024-09-11011 September 2024 License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles ML24150A2192024-05-29029 May 2024 (E-Mail) St. Lucie, Unit 2 - License Amendment Request, Updated Spent Fuel Pool Criticality Analysis - Acceptance Review 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 ML24005A2772024-02-20020 February 2024 Issuance of Amendment Nos. 253 and 208 Regarding Conversion to Improved Standard Technical Specifications 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 ML23275A1252023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 4.0, Design Features, Revision 2 - Volume 15 ML23275A1262023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 5.0, Administrative Controls, Revision 2 - Volume 16 L-2023-126, Enclosure 1: Contents of Improved Technical Specifications (ITS) Submittal2023-10-0202 October 2023 Enclosure 1: Contents of Improved Technical Specifications (ITS) Submittal ML23275A1242023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.9, Refueling Operations, Revision 2 - Volume 14 ML23275A1232023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.8, Electrical Systems, Revision 2 - Volume 13 ML23275A1222023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.7, Plant Systems, Revision 2 - Volume 12 ML23275A1212023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.6, Containment Systems, Revision 2 - Volume 11 ML23275A1192023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.4, Reactor Coolant System, Revision 2 - Volume 9 ML23275A1202023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.5, Emergency Core Cooling Systems, Revision 2 - Volume 10 ML23275A1182023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.3, Instrumentation, Revision 2 - Volume 8 ML23275A1122023-10-0202 October 2023 Improved Technical Specifications Conversion License Amendment Request Self-Identified Administrative Changes - Volume 2 ML23275A1152023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.0, LCO and SR Applicability, Revision 2 - Volume 5 ML23275A1162023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.1, Reactivity Control Systems, Revision 2 - Volume 6 ML23275A1172023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.2, Power Distribution Limits, Revision 2 - Volume 7 ML23275A1142023-10-0202 October 2023 Improved Technical Specifications Conversion, Chapter 2.0, Safety Limits, Revision 1 - Volume 4 ML23275A1112023-10-0202 October 2023 Improved Technical Specifications (ITS) Revision 2 Submittal Volumes 1 Through 16 ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 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-2022-160, 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 L-2022-154, Subsequent License Renewal Application Revision 1, Supplement 42022-09-22022 September 2022 Subsequent License Renewal Application Revision 1, Supplement 4 L-2022-046, Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal2022-04-13013 April 2022 Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal L-2022-043, Subsequent License Renewal Application Revision 1 - Supplement 12022-04-0707 April 2022 Subsequent License Renewal Application Revision 1 - Supplement 1 ML22010A0962022-01-0505 January 2022 Trp 010 St Lucie SLRA - Boricacidcorrbreakoutq - Makar ML21285A1072021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1 ML21285A1082021-10-12012 October 2021 Enclosure 1: St. Lucie Nuclear Plant, Units 1 and 2, Subsequent Licensee Renewal Application, Revision 1 ML21285A1112021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report L-2021-192, Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report2021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report L-2021-142, Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 20212021-08-0303 August 2021 Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 ML21215A3152021-08-0303 August 2021 Application for Subsequent Renewed Facility Operating Licenses ML21215A3162021-08-0303 August 2021 Enclosure 1: Subsequent License Renewal Application Enclosures Summary ML21215A3192021-08-0303 August 2021 Appendix E - Applicant'S Environmental Report for St. Lucie L-2021-192, Westinghouse, Report LTR-REA-21-1-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 20212021-05-26026 May 2021 Westinghouse, Report LTR-REA-21-1-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 L-2020-164, License Amendment to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements2020-12-21021 December 2020 License Amendment to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements L-2020-020, License Amendment Request for RCS Pressure/ Temperature Limits and LTOP Applicable for 55 Effective Full Power Years2020-02-18018 February 2020 License Amendment Request for RCS Pressure/ Temperature Limits and LTOP Applicable for 55 Effective Full Power Years L-2019-091, License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements2019-10-0909 October 2019 License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements L-2019-147, Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-19019 July 2019 Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG L-2018-161, License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation2018-12-20020 December 2018 License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation L-2018-182, License Amendment Request Iodine Removal System Elimination2018-11-0909 November 2018 License Amendment Request Iodine Removal System Elimination L-2018-201, Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2018-11-0909 November 2018 Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2018-147, Submittal of License Amendment Request to Remove the Site Area Map from Technical Specifications2018-08-0202 August 2018 Submittal of License Amendment Request to Remove the Site Area Map from Technical Specifications L-2018-121, License Amendment Request to Reduce the Number of Control Element Assemblies2018-06-29029 June 2018 License Amendment Request to Reduce the Number of Control Element Assemblies 2024-09-27
[Table view] |
Text
September 27, 2024 L-2024-155 10 CFR 54.17
U.S. Nuclear Regulatoi-y Commission Attn: Document Control Desk 11545 Rockville Pike One \\Vh.ite Flint North Rockville, 1YID 20852-2746
St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 Facility Operating Licenses DPR-67 and NPF-16
SUBSEQUENT LICENSE RENEWAL APPLICATION -THIRD ANNUAL UPDATE
References:
- 1. Florida Power & Light Company (FPL) letter L-2021-192, Subsequent License Renewal Application -
Revision 1, October 12, 2021 (ADAMS Package Accession No. ML21285A106)
- 2. FPL Letter L-2022-163 dated September 28, 2022, Subsequent License Renewal Application -First Annual Update (ADAMS Accession No. ML22271A399)
- 3. FPL letter L-2023-131 dated September 28, 2023, Subsequent License Renewal Application -Second Annual Update (ADAMS Accession No. ML23271A117)
- 4. FPL letter L-2024-121 dated July 30, 2024, St. Lucie Unit 1 Subsequent License Renewal Commitment
- 30 Revision (ADAMS Accession No. ML24212A194)
FPL, the owner and licensee for St. Lucie Nuclear Plant (PSL) Units 1 and 2, has submitted a revised subsequent license renewal application (SLRA) for the Facility Operating Licenses for PSL Units 1 and 2 (Reference 1), first annual update (Reference 2), and second annual update (Reference 3). The License Renewal Rule, 10 CFR 54.21(b), requires that each year following submittal of an LRA, and at least 3 months before scheduled completion of the NRC review, an update to the LRA must be submitted that identifies any change to the current licensing basis (CLB) of the facility that materially affects the content of the LRA including the Updated Final Safety Analysis Repo1t Supplement.
In accordance with the License Renewal Rule, FPL has performed the third annual review of PSL Units 1 and 2 CLB changes since SLRA submittal to determine whether any sections of the SLRA were materially affected by these changes. As a result of this annual review, FPL identified changes to materially affecting SLRA content due to Reference 4. A description of these changes and the corresponding affected SLRA content revisions are provided in Attachments 1 and 2 to this letter, respectively.
For ease of reference, the index of attached information is provided on page 3 of this letter. Attachment 2 includes associated revisions to the SLRA (Enclosure 3 Attachment 1 of Reference 1) denoted by strikethrough ( deletion) and/ or bold red underline (insertion) text. Previous SLRA revisions are denoted by bo ld black text. SLRA table revisions are included as excerpts from each affected table.
Florida Pow e r & Light Company
15430 Endeavor Drive,Jupiter, FL 33478 St. Lucie Nuclear Plant Units 1 and 2 L-2024-155 Dockets 50-335 and 50-389 Page 2 of3
Should you have any questions regarding this submittal, please contact Ms. Maribel Valdez, Fleet Licensing Manager, at 561-904-5164.
I declare under penalty of perjuty that the foregoing is Uue and correct.
Executed on the 27th day of September 2024.
Sincerely,
Director, Regulatory Affairs
Attachments (2)
cc: Regional Administrator, USNRC, Region II Senior Resident Inspector, USNRC, St. Lucie Plant Chief, USNRC, Division of New and Renewed Licenses Senior Project Manager, USNRC, Division of New and Renewed Licenses Chief, Bureau of Radiation Control, Florida Department of Health St. Lucie Nuclear Plant Units 1 and 2 L-2024-155 Dockets 50-335 and 50-389 Page 3 of3
Attachment No. Subject 1 Current Licensing Basis (CLB) Change Affecting the SLRA 2 Affected SLRA Content Revisions St. Lucie Nuclear Plant Units 1 and 2 L-2024-155 Dockets 50-335 and 50-389 Attachment 1 Page. 1 of 1
CURRENT LICENSING BASIS (CLB) CHANGE AFFECTING THE SLRA
PSL 1 and 2 CLB Change Screening / Aging SLRA Sections Affected Management Review/
Program (AMR /AMP)
Documents Affected
Change to the regulatory commit-NEESLOOOOS-REPT-057 Appendix A 1, Section 19.2.2.27 ment for installing a cathodic pro-Appendix A 1, Table 19-3 tection system for St. Lucie Unit
- 1. The change affects SLRA Unit Appendix B, Section B.2.3.27 1 Updated Final Safety Analysis Report Supplement, Appendix A 1, and Aging Management Pro-grams, Appendix B.
St. Luci e Nuclear Plant Units 1 and 2 L-2024-155 Dockets 50-335 and 50 -38 9 Attachme nt 2 Page 1 of 5 Affected SLRA Content Revisions
SLRAAppendixA1, Section 19.2.2.27, pageA1-31, is revised as follows:
19.2.2.27 Buried and Underground Piping and Tanks
The PSL Buried and Underground Piping and Tanks AMP is a new AMP. This a condition moni -
toring AMP that manages the aging effects associated with the external surfaces of buried and underground piping.
There are no buried or underground tanks at PSL.
This AMP manages the external surface condition of buried and underground piping for loss of material and cracking for the external surfaces of buried piping fabricated of steel (cast iron, carbon steel, ductile iron) and stainless steel through preventive measures (e.g., coat -
ings, backfill, and compaction), mitigative measures (e.g., electrical isolation between piping and supports of dissimilar metals, etc.), and periodic inspection activities (e.g., direct visual inspection of external surfaces, protective coatings, wrappings and quality of backfill} during opportunistic or directed excavations. The number of inspections is based on the effective -
ness of the preventive and mitigative actions.
Inspections are conducted by qualified individuals. Where the coatings, backfill or the condi-tion of exposed piping does not meet acceptance criteria, such that the depth or extent of degradation of the base metal could have resulted in a loss of pressure boundary function when the loss of material rate is extrapolated to the end of the SPEO, an increase in the sam-ple size is conducted. Direct visual inspections are performed on the external surfaces, pro-tective coatings, wrappings, quality of backfill and wall thickness measurements using NOE techniques. Additional inspections are performed on steel piping in lieu of fire main testing.
The table below provides additional information related to inspections. Preventive Action Category F has been selected for monitoring steel piping during the initial monitoring period since the proposed cathodic protection system will not be operational during that time pe-riod. Upon entering the SPEO, Preventive Action Category Chas been selected for buried steel piping after the cathodic protection system has been in service for approximately § years for Unit 1 and 10 years for Unit 2 and annual effectiveness reviews are performed.
However, if these conditions were to change, the Preventive Action Category would require reevaluation and could potentially change.
The number of inspections for each 10-year inspection period, beginning--+/-G §_ years before the start of SPEO for Unit 1 and 10 years before the SPEO for Unit 2, are based on the in -
spection quantities noted in NUREG-2191, Table XI.M41-2, adjusted for a 2-Unit plant site.
St. Lucie Nuclear Plant Units 1 and 2 L-2024-155 Dockets 50-335 and 50-389 Attachment 2 P age 2 of 5 Affected SLRA Content Revisions
SLRA Appendix Al, Table 19-3 (Item 30), page Al-98 is revised as follows:
Table 19-3 List of Unit 1 SLR Commitments and Implementation Schedule
No. Aging Management NUREG-2191 Commitment Implementation Schedule Program or Activity (Section) Section
30 Buried and Underground Piping XI.M41 Implement the new PSL Buried and Underground Piping and Tanks AMP. Program inspections begin~ § and Tanks (19.2.2.27 ) a) Install cathodic protection systems and perform effectiveness reviews in years before the SPEO. lnspec-accordance with Table XI.M41-2 in NUREG-2191,Section XI.M41. tions that are to be completed b) If after five years of operation the cathodic protection system does prior to the SPEO are completed not meet the effectiveness acceptance criteria defined by NUREG-2191, 6 months prior to the SPEO or no Tables XI.M41-2 and -3 (-850 mV relative to a CSE, instant off, for at later than the last refueling out-least 80% of the time, and in operation for at least 85% of the time), age prior to the SPEO.
FPL commits to performing two additional buried steel piping inspec-Install cathodic protection sys-tions beyond the number required by Preventive Action Category F re-terns at least ~ §_years before suiting in a total of 13 inspections being completed 6 months prior to the SPEO.
the SPEO. The cathodic protection criterion listed above will continue Program and SLR enhancements to be used after five years through the end of the SPEO. are implemented 6 months prior c) Perform periodic pressure testing and blow-out testing (purging) with to the SPEO, i.e.:
air or nitrogen of the annular volume between the underground stain-PSLl: 09/01/2035 less steel fuel oil piping and its respective guard piping to verify no leakage of guard pipe and no leakage from the fuel oil piping. This testing will be performed for at least 25 percent of the stainless steel fuel oil piping housed within guard piping at an interval not to exceed 5 years with the first occurrence prior to the SPEO. The annular vol-ume between the fuel oil piping and guard piping will be pressurized to 110 percent of the design pressure of any component within the boundary (not to exceed the maximum allowable test pressure of any non-isolated components) with test pressure being held for a continu-ous eight hour interval.
St. L u cie Nucl ea r P lant U ni ts 1 and 2 L-2024-15 5 D oc kets 50 -33 5 and 50- 389 A t tac h ment 2 Page 3 of 5 Affected SLRA Content Revisions
SLRA Section B.2.3.27, page B-215 is revised as follows :
B.2.3.27 Buried and Underground Piping and Tanks
Program Description The PSL Buried and Underground Piping and Tanks AMP is a new condition monitoring AMP that manages the aging effects associated with the external surfaces of buried and under -
ground piping such as loss of material and cracking. It addresses piping composed of steel (carbon steel, cast iron, and ductile iron) and SS materials that are within the scope of Subse-quent License Renewal. There are no buried or underground tanks at PSL.
There are no polymeric, cementitious, or additional metallic materials other than the steel metals stated above for the in-scope systems, therefore, the aging management of these ma-terials is not applicable. The interior surfaces of the coated, cement lined cast iron fire water system piping is managed by the PSL Internal Coatings/Linings for In-Scope Piping, Piping Com -
ponents, Heat Exchangers, and Tanks {Section B.2.3.28 ) AMP.
The objective of this program is accomplished through the use of preventive, mitigative, in-spection, and in some cases, performance monitoring activities. The PSL Buried and Under-ground Piping and Tanks AMP includes (a) preventive measures to mitigate degradation (e.g.,
external coatings/wrappings), (b) visual inspections of external surfaces of buried components for evidence of coating/wrapping damage, and (c) visual inspections of external surfaces of buried components for evidence of degradation, if the coating or wrapping is damaged or the pipe is uncoated or unwrapped, to manage the effects of aging. The periodicity of these in-spections will be based on plant OE and opportunities for inspection such as scheduled maintenance work. These inspections will occur once prior to the SPEO and at least every 10 years during the SPEO. If an opportunity for inspection of nonleaking piping occurs prior to the scheduled inspection, the opportunistic inspection can be credited fo r satisfying the scheduled inspection if the GALL-SLR AMP XI.M41 criteria are met.
The PSL Buried and Underground Piping and Tanks AMP manages applicable aging effects such as loss of material, cracking, and blistering. Depending on the material, preventive and mitiga-tive techniques may include using external coatings, cathodic protection, and quality backfill.
Depending on the material and environment, inspection activities may include electrochemi-cal verification of the effectiveness of cathodic protection, nondestructive evaluation of pipe wall thicknesses, pressure testing and blow-out testing, and visual inspections of the pipe from the exterior.
PSL currently does not have an active cathodic protection system fo r buried and underground piping.
Backfill specifications, average pH of soil samples, the use of guard pipe and coatings was previous justification for not having a need for an active cathodic protection system for buried steel piping. In accordance with the recommendations of NUREG-2191 AMP XI.M41, a cathodic protection system will be installed at least 6 years before the SPEO for Unit 1 and at least 10 years before the prior to SPEO for Unit 2.
SLRA Section B.2.3.27, page B-216 is revised as follows:
selected for buried steel piping after the cathodic protection system has been in service for St. Lucie Nuclear Pl ant Units 1 and 2 L-2024-155 Dockets 50-335 and 50-389 Attachment 2 Page 4 of 5 Affected SLRA Content Revisions
approximately 10 years and annual effectiveness reviews are performed. However, if these conditions were to change, the Preventive Action Category would require reevaluation and could potentially change.
The number of inspections for each 10-year inspection period, beginning 6 years before the SPEO for Unit 1 and 10 years before the SPEO for Unit 2, are based on the inspection quanti-ties noted in NUREG-2191, Table XI.M41-2, adjusted for a 2-Unit plant site.
Material No. of Inspections Notes Steel (buried) 11
- prior to the SPEO (Cate-Includes 2 additional inspections to gory F} meet the requirements of NUREG-2191 4 in each 10-year period in Section XI.M41, paragraph 4.e.i the SPEO (Category C} regarding the aging effects associated with fire mains.
Steel (underground) 3
Stainless steel (un-Pressure testing per note Perform periodic pressure testing and derground) blow-out testing (purging) with air or nitrogen of the annular volume be-tween the underground stainless steel fuel oil piping and its respective guard piping to verify no leakage of guard pipe and no leakage from the fuel oil piping. This testing will be performed for at least 25 percent of the stainless steel fuel oil piping housed within guard piping at an interval not to ex-ceed 5 years with the first occurrence prior to the SPEO. The annular volume between the fuel oil piping and guard piping will be pressurized to 110 per-cent of the design pressure of any component within the boundary (not to exceed the maximum allowable test pressure of any non-isolated compo-nents) with test pressure being held for a continuous eight hour interval.
Stainless steel (bur-2 ied)
St. Lucie Nuclear Plant Units 1 and 2 L-2023-131 Dockets 50-335 and 50-389 Attachment 2 Page 5 of 5 Affected SLRA Content Revisions
SLRA Section B.2.3.27, page B-216 (cont'd) is revised as follows:
- If after five years of operation the cathodic protection system does not meet the effectiveness ac-ceptance criteria defined by NUREG-2191, Tables XI.M41-2 and -3 (-850 mV relative to a CSE, instant off, for at least 80 percent of the time, and in operation for at least 85 percent of the time), FPL com-mits to performing two additional buried steel piping inspections beyond the number required by Pre-ventive Action Category F resulting in a total of thirteen (13) inspections being completed six months prior to the SPEO. The cathodic protection criterion listed above will continue to be used after five years through the end of the SPEO.
This AMP does not provide aging management of selective leaching. The PSL Selective Leaching of Materials (Section B.2.3.21 ) AMP is applied in addition to this program for appli-cable materials and environments.
The PSL Buried and Underground Piping and Tanks AMP requires the creation of new gov-erning and inspection procedures consistent with NUREG-2191,Section XI.M41, as well as a new sampling plan and work orders to support the new inspections. A new cathodic protec-tion system will also be installed, and an effectiveness review per Table XI.M41-2 of NUREG-2191,Section XI.M41 will be performed throughout each of the 10-year inspection periods.
Initial inspections begin 6 years before the SPEO for Unit 1 and 10 years before the SPEO for Unit 2 and are completed no later than six months prior to entering the SPEO or no later than the last RFO prior to the SPEO.
NUREG-2191 Consistency
The PSL Buried and Underground Piping and Tanks AMP will be consistent with exception to the 10 elements of NUREG-2191,Section XI.M41, "Buried and Underground Piping and Tanks."
Exceptions to NUREG-2191
An exception to the NUREG-2191 recommendation of coating buried stainless steel as a preventive action will be taken with respect to the Unit 1 stainless steel AFW pump recirculation piping and condensate system (AFW pump suction) piping buried beneath the Unit 1 turbine building. This exception is justified due to the low number of chlorides within the soil, the low likelihood of stagnant moisture due to the concrete floor slab shielding, good soil/backfill drainage, and no history of negative OE for buried stainless steel piping at St.
Lucie.