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Category:Graphics incl Charts and Tables
MONTHYEARL-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 ML22013A3172022-01-12012 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 ML22013A3072022-01-11011 January 2022 Trp 084 St Lucie SLRA - Ssnial Scclombreakoutq ML22012A3912022-01-11011 January 2022 Scoping and Screening 2.3.3.2 & 2.3.3.4 St. Lucie SLRA - Breakout Questions 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 ML22013A3032021-12-21021 December 2021 Trp 143.2 St Lucie SLRA - Breakout Questions Non-Class 1 Fatigue ML22013A3042021-12-21021 December 2021 Trp 143.3 St Lucie SLRA - Breakout Questions EAF 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 ML22013A3052021-12-21021 December 2021 Trp 143.4 St Lucie SLRA - Breakout Questions HELB 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 ML0808506472008-03-19019 March 2008 NDE Report on PSL-1 Pressurizer Nozzles ML0810502642008-03-19019 March 2008 NDE Report, on PSL-1 Pressurizer Nozzles, Attachment 2 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 2024-03-13
[Table view] Category:Letter type:L
MONTHYEARL-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024 Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes L-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-2024-133, Snubber Program Plan Submittal2024-08-14014 August 2024 Snubber Program Plan Submittal L-2024-140, Cycle 28 Core Operating Limits Report2024-08-14014 August 2024 Cycle 28 Core Operating Limits Report 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-2024-114, 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-2024-015, 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-2023-169, Correction to the 2022 Annual Radioactive Effluent Release Report2023-11-28028 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 L-2023-158, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update 2024-09-09
[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%