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Category:Graphics incl Charts and Tables
MONTHYEARML22013A3172022-01-12012 January 2022
Trp 030 - St. Lucie SLRA Breakout Questions_Fuel Oil
ML22013A3162022-01-12012 January 2022
Trp 020 - St. Lucie SLRA Breakout Questions_Occw
ML22013A3342022-01-11011 January 2022
TRP16 - St. Lucie SLRA Breakout Questions_Pwr Internals
ML22012A3912022-01-11011 January 2022
Scoping and Screening 2.3.3.2 & 2.3.3.4 St. Lucie SLRA - Breakout Questions
ML22013A3072022-01-11011 January 2022
Trp 084 St Lucie SLRA - Ssnial Scclombreakoutq
ML22012A2632022-01-10010 January 2022
Trp 3 - St. Lucie Psl SLRA Breakout Question Reactor Head Closure Stud Bolting
ML22010A0972022-01-0707 January 2022
Trp 038 Psl Internal Surfaces Breakout Questions - Allik
ML22010A1002022-01-0707 January 2022
Trp 033 Psl Selective Leaching Breakout Questions - Allik
ML21356A5772021-12-22022 December 2021
Slar Breakout Questions - Fire Protection Scoping and Screening
ML22013A3052021-12-21021 December 2021
Trp 143.4 St Lucie SLRA - Breakout Questions HELB
ML22013A3042021-12-21021 December 2021
Trp 143.3 St Lucie SLRA - Breakout Questions EAF
ML22013A3032021-12-21021 December 2021
Trp 143.2 St Lucie SLRA - Breakout Questions Non-Class 1 Fatigue
ML22013A3022021-12-21021 December 2021
Trp 143.1 St Lucie SLRA - Breakout Questions Class 1 Fatigue
ML22013A3012021-12-21021 December 2021
TRP60 St. Lucie SLRA - Breakout Questions Fatigue Monitoring
ML22013A2972021-12-21021 December 2021
Trp 77 St. Lucie SLRA - Breakout Questions Corrosion Structural
ML22013A2962021-12-21021 December 2021
Trp 74 St. Lucie SLRA - Breakout Questions
ML22013A2952021-12-21021 December 2021
Trp 47 St. Lucie SLRA - Breakout Questions
ML22013A2942021-12-21021 December 2021
Trp 46 St. Lucie SLRA - Breakout Questions Structures Monitoring
ML22013A2922021-12-21021 December 2021
Trp 41 St. Lucie SLRA - Breakout Questions
ML22013A2882021-12-21021 December 2021
Trp 23 & 147.8 St. Lucie SLRA - Breakout Questions Cranes AMP-TLAA
ML22013A2842021-12-21021 December 2021
Trp 18 St. Lucie SLRA - Breakout Questions Bolting Integrity
ML22013A2822021-12-21021 December 2021
SLRA - Breakoutt Questions Corrosion OE
ML21354A8372021-12-20020 December 2021
Trp 11 St. Lucie SLRA Breakout Questions
ML21351A2382021-12-17017 December 2021
Trp 148.1 St. Lucie SLRA - Breakout Questions for TLAA Section 4.7.1 Rev. 1
ML21351A2412021-12-17017 December 2021
Trp 15 St. Lucie SLRA - Internal Coatings Breakout Questions - Allik
ML21351A2392021-12-17017 December 2021
Trp 14 St. Lucie SLRA - Buried Pipe Breakout Questions - Allik.Docx
L-2021-137, GL 2004-02 Debris Transport Calculation Non-Conservatism2021-07-23023 July 2021
GL 2004-02 Debris Transport Calculation Non-Conservatism
L-2018-067, Units 1 and 2 - Submittal of Joint Plant Access Shared Information Table2018-03-19019 March 2018
Units 1 and 2 - Submittal of Joint Plant Access Shared Information Table
L-2016-109, Official Service List Changes and Distribution for Safeguards Information and Official Use Only-Security-Related Information2016-05-11011 May 2016
Official Service List Changes and Distribution for Safeguards Information and Official Use Only-Security-Related Information
ML16056A1392016-03-11011 March 2016
Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports
ML15224B4492015-09-0303 September 2015
Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation
ML15236A0762015-09-0303 September 2015
Enclosure, Revised St Lucie Tables-LQ-W
ML15231A4122015-08-21021 August 2015
FPL St. Lucie Capture Summary 2015
ML15231A4172015-08-21021 August 2015
Power Plant Causal Turtles
L-2015-093, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report2015-03-24024 March 2015
Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report
L-2014-340, RAI Reply - Fourth Ten-Year Interval Unit 2 Relief Request No. 42014-11-0606 November 2014
RAI Reply - Fourth Ten-Year Interval Unit 2 Relief Request No. 4
L-2013-067, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20122013-02-14014 February 2013
Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2012
ML1214500142012-05-23023 May 2012
NFPA 805 LAR Status Matrix - May 2012
ML12073A1512012-03-0606 March 2012
NRR E-mail Capture - St. Lucie Discharge Headwall Project
L-2010-096, Extended Power Uprate Data for NRC Confirmatory EPU Analyses2010-06-0404 June 2010
Extended Power Uprate Data for NRC Confirmatory EPU Analyses
L-2009-078, Extended Power Uprate Data for NRC Confirmatory EPU Analyses2009-04-0202 April 2009
Extended Power Uprate Data for NRC Confirmatory EPU Analyses
L-2008-236, Extended Power Uprate, Data for NRC Confirmatory EPU Analyses2008-10-29029 October 2008
Extended Power Uprate, Data for NRC Confirmatory EPU Analyses
L-2008-178, Fourth Ten-Year Interval In-Service-Test Program Submittal RAI Reply to Relief Request PR-042008-08-0505 August 2008
Fourth Ten-Year Interval In-Service-Test Program Submittal RAI Reply to Relief Request PR-04
ML0810502642008-03-19019 March 2008
NDE Report, on PSL-1 Pressurizer Nozzles, Attachment 2
ML0808506472008-03-19019 March 2008
NDE Report on PSL-1 Pressurizer Nozzles
L-2008-018, Transmittal of Pressurized Butt Weld Alloy Report, and Mitigation Status and Swol Inspection Results2008-02-21021 February 2008
Transmittal of Pressurized Butt Weld Alloy Report, and Mitigation Status and Swol Inspection Results
L-2008-002, Corporate Merger of Decommissioning Trustee2008-01-0303 January 2008
Corporate Merger of Decommissioning Trustee
ML0728203072007-10-11011 October 2007
Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists
ML0526603212005-09-21021 September 2005
Tech Spec Pages for Amendment No. 196, Extension of the Reactor Coolant System Pressure/Temperature Curve Limits
L-2004-293, Third 10-Year Inservice Inspection Interval Relief Request No. 2 Supplemental Information2004-12-28028 December 2004
Third 10-Year Inservice Inspection Interval Relief Request No. 2 Supplemental Information
2022-01-07
[Table view]
Category:Letter type:L
MONTHYEARL-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024
Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)
L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024
Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years
L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024
Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump
L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023
Quality Assurance Topical Report (FPL-1) Revision 30 Update
L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023
Unusual or Important Environmental Event - Turtle Mortality
L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023
License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5
L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023
Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654,
L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023
Response to 50.69 2nd Round of Rals
L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023
Subsequent License Renewal Application - Second Annual Update
L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023
Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023
Corrections to the 2022 Annual Radiological Environmental Operating Report
L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023
Correction to the 2022 Annual Radioactive Effluent Release Report
L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023
Correction to the 2020 Annual Radiological Environmental Operating Report
L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023
Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023
Report of 10 CFR 50.59 Plant Changes
L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023
Corrections to the 2021 Annual Radioactive Effluent Release Report
L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023
Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023
Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update
L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023
and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2
L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023
Preparation and Scheduling of Operator Licensing Examinations
L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023
Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump
L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023
Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches
L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023
Subsequent License Renewal Application Revision 1 - Supplement 6
L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023
In-Service Inspection Program Owner'S Activity Report (OAR-1)
L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023
Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)
L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023
Subsequent License Renewal Application Revision 1, Supplement 5
L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023
Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update
L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023
NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal
L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023
Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response
L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023
2022 Annual Environmental Operating Report
L-2023-041, Annual Radiological Environmental Operating Report for Calendar Year 20222023-04-0404 April 2023
Annual Radiological Environmental Operating Report for Calendar Year 2022
L-2023-051, Report of 10 CFR 50.59 Plant Changes2023-04-0404 April 2023
Report of 10 CFR 50.59 Plant Changes
L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023
Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update
L-2023-042, Periodic Update of Population Data within 10 and 50 Miles of the Plant2023-03-27027 March 2023
Periodic Update of Population Data within 10 and 50 Miles of the Plant
L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023
Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4
L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023
and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications
L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023
Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1
L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023
and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)
L-2023-039, Cycle 27 Core Operating Limits Report2023-03-0707 March 2023
Cycle 27 Core Operating Limits Report
L-2023-032, 2022 Annual Radioactive Effluent Release Report2023-02-28028 February 2023
2022 Annual Radioactive Effluent Release Report
L-2023-038, 2022 Annual Operating Report2023-02-28028 February 2023
2022 Annual Operating Report
L-2023-016, Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan2023-02-15015 February 2023
Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan
L-2023-019, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20222023-02-15015 February 2023
Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2022
L-2023-009, Owner'S Activity Report2023-01-31031 January 2023
Owner'S Activity Report
L-2022-188, Unusual or Important Environmental Event - Turtle Mortality2022-12-19019 December 2022
Unusual or Important Environmental Event - Turtle Mortality
L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022
Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2
L-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022
Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022
CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums
L-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022
Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response
L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022
Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2
2024-01-08
[Table view] |
Text
July 23, 2021 L-2021-137 GL 2004-02 10 CFR 50.54(f)
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington DC 20555-0001 RE: St. Lucie Nuclear Plant, Units 1 and 2 Docket Nos. 50-335 and 50-389 Renewed Facility Operating Licenses DPR-67 and NPF-16 GL 2004-02 Debris Transport Calculation Non-Conservatism
References:
- 1. Florida Power & Light Company letter L-2017-210, Updated Final Response to NRC Generic Letter 2004-02, December 20, 2017 (ADAMS Accession No. ML17362A108)
- 2. Florida Power & Light Company letter L-2020-165, Supplement to Updated Final Response to NRC Generic Letter 2004-02, December 4, 2020 (ADAMS Accession No. ML20339A501)
In Reference 1, as supplemented by Reference 2, Florida Power & Light Company (FPL) provided an updated final response to Generic Letter (GL) 2004- 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, (ADAMS Accession No. ML042360586), for St. Lucie Units 1 and 2 (St. Lucie).
Recently, FPL learned of a non-conservatism in the St. Lucie debris transport evaluation that supported the submittal in Reference 1. Specifically, the non-conservatism occurred when determining the debris transport fractions for postulated reactor nozzle breaks, which incorrectly applied the pool fill-up transport fractions for selected debris types, resulting in non-conservative transported debris quantities. The issue has been entered into the St. Lucie corrective action program (CAP), and the calculations containing the non-conservatism have been revised. The revision increased the overall transport fractions for the fine debris from 97% to 100% for the reactor nozzle breaks. Table 3.e.6-14 and Table 3.e.6-17 of the enclosure to this letter provide the corrected debris transport fraction values for the reactor nozzle breaks for St. Lucie. These tables supersede Table 3.e.6-14 and Table 3.e.6-17 of Reference 1. The non-conservatism did not impact the limiting breaks scenarios evaluated in Reference 1, as shown in existing Table 3.e.6-19 through Table 3.e.6-21 of Reference 1. As a result, the conclusions specified in Reference 1 are not affected.
Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957
St. Lucie Nuclear Plant, Units 1 and 2 L-2021-137 Docket Nos. 50-335 and 50-389 Page 2 of 2 This letter contains no new regulatory commitments.
Should you have any questions regarding this submittal, please contact Mr. Wyatt Gades, St. Lucie Licensing Manager, at (772) 467-7435.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on 1~tr 23J .20'-i Sincerely, Daniel DeBoer Site Vice President St. Lucie Nuclear Plant DD/jam/res Enclosure cc: USNRC Regional Administrator, Region II USNRC Project Manager, St. Lucie Nuclear Plant, Units 1 and 2 USNRC Senior Resident Inspector, St. Lucie Nuclear Plant, Units 1 and 2 Ms. Cindy Becker, Florida Department of Health
St. Lucie Nuclear Plant, Units 1 and 2 L-2021-137 Docket Nos. 50-335 and 50-389 Enclosure Page 1 of 2 Table 3.e.6-14 (Revised), PSL1 Overall Transport Fractions for a Reactor Cavity Break Debris Type Debris Size 1 Train 2 Train Fines - -
Small Transport as Erosion Fines - -
Pieces Transport as Small Pieces - -
Generic Fiberglass Large Transport as Erosion Fines - -
Pieces Transport as Large Pieces - -
Intact Blankets - -
Fines 100% 100%
Small Transport as Erosion Fines 9% 9%
Pieces Transport as Small Pieces 29% 47%
Nukon Large Transport as Erosion Fines 8% 8%
Pieces Transport as Large Pieces 4% 7%
Intact Blankets 0% 0%
Fines 100% 100%
Small Transport as Erosion Fines 9% 9%
Pieces Transport as Small Pieces 29% 47%
Thermal-Wrap Large Transport as Erosion Fines 8% 8%
Pieces Transport as Large Pieces 4% 7%
Intact Blankets 0% 0%
Fines 100% 100%
Small Transport as Erosion Fines 9% 9%
Pieces Transport as Small Pieces 83% 83%
Temp-Mat Large Transport as Erosion Fines 8% 8%
Pieces Transport as Large Pieces 73% 73%
Intact Blankets 0% 0%
Fines 5% 13%
Mirror RMI Large Pieces 6% 11%
Fines 5% 13%
Transco RMI Large Pieces 6% 11%
Transco RMI (inside Fines 3% 7%
cavity) Large Pieces 0% 0%
Fines 100% 100%
Non-banded Cal-Sil Small Transport as Erosion Fines 17% 17%
Pieces Transport as Small Pieces 6% 14%
Fines 100% 100%
Banded Cal-Sil Small Transport as Erosion Fines 17% 17%
Pieces Transport as Small Pieces 6% 14%
Qualified Coatings Particulate 100% 100%
Unqualified Coatings Particulate 100% 100%
Latent Debris Particulate/Fiber 100% 100%
St. Lucie Nuclear Plant, Units 1 and 2 L-2021-137 Docket Nos. 50-335 and 50-389 Enclosure Page 2 of 2 Table 3.e.6-17 (Revised), PSL2 Overall Transport Fractions for a Reactor Cavity Break Debris Type Debris Size 1 Train 2 Train Fines - -
Small Transport as Erosion Fines - -
Pieces Transport as Small Pieces - -
LDFG Large Transport as Erosion Fines - -
Pieces Transport as Large Pieces - -
Intact Blankets - -
Fines 100% 100%
Small Transport as Erosion Fines 10% 9%
Pieces Transport as Small Pieces 10% 18%
Nukon Large Transport as Erosion Fines 8% 8%
Pieces Transport as Large Pieces 2% 5%
Intact Blankets 0% 0%
Fines 100% 100%
Small Transport as Erosion Fines 10% 10%
Pieces Transport as Small Pieces 5% 8%
Nukon (inside cavity)
Large Transport as Erosion Fines 10% 10%
Pieces Transport as Large Pieces 0% 0%
Intact Blankets 0% 0%
Fines 1% 9%
Mirror RMI Large Pieces 2% 5%
Mirror RMI (inside Fines 1% 4%
cavity) Large Pieces 0% 0%
Fines - -
Transco RMI Large Pieces - -
Fines 100% 100%
Cal-Sil Small Transport as Erosion Fines 17% 17%
Pieces Transport as Small Pieces 1% 7%
Qualified Coatings Particulate 100% 100%
Unqualified Coatings Particulate 100% 100%
Latent Debris Particulate/Fiber 100% 100%
