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Category:Photograph
MONTHYEARML0807010172008-03-10010 March 2008 EPRI Reports (St. Lucie Pressurizer Nozzle DM Weld Examination Project Internal Office Report) 2008-03-10
[Table view] Category:Report
MONTHYEARL-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update 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-2023-028, 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-2023-009, Owner'S Activity Report2023-01-31031 January 2023 Owner'S Activity Report ML22227A0532022-08-15015 August 2022 Biological Opinion for the Continued Operation of St. Lucie Nuclear Power Plant ML22124A0112022-04-30030 April 2022 Scoping Summary Report - Final 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-2022-015, Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld - RAI2022-01-14014 January 2022 Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld - RAI L-2022-011, Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld2022-01-12012 January 2022 Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld ML22010A0942022-01-0404 January 2022 Trp 29 St. Lucie SLRA - Tank Breakout L-2021-178, Report of 10 CFR 50.59 Plant Changes2021-11-0808 November 2021 Report of 10 CFR 50.59 Plant Changes 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 ML19252A4002019-09-0909 September 2019 FPL to NRC, Notification of Smalltooth Sawfish Capture at St. Lucie L-2019-010, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds2019-03-19019 March 2019 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds ML18096B3952018-04-0606 April 2018 Exhibit III Estimate of Construction Costs and Exhibit IV Technical Qualifications of Contractors ML18088B1952018-03-29029 March 2018 Hutchinson Island Plant Units 1 and 2 - Chapter 9, Auxiliary Systems and Chapter 10, Steam and Power Conversion System ML18088B1942018-03-29029 March 2018 Hutchinson Island Plant Units 1 and 2 - Chapter 11, Radioactive Waste Management System, Chapter 12, Radiation Protection, and Chapter 13, Conduct of Operations ML18088A0942018-03-29029 March 2018 Unit II Plants ECCS Performance Results L-2017-173, Environmental Protection Plan Report, Unusual or Important Environmental Event - Turtle Mortality - 09/11/2017 Event2017-09-28028 September 2017 Environmental Protection Plan Report, Unusual or Important Environmental Event - Turtle Mortality - 09/11/2017 Event L-2018-081, Kld Engineering, Pc - 2017 Population Update Analysis2017-09-20020 September 2017 Kld Engineering, Pc - 2017 Population Update Analysis L-2017-117, Submittal of SL2-23 Outage, Owner'S Activity Report, Form OAR-12017-06-20020 June 2017 Submittal of SL2-23 Outage, Owner'S Activity Report, Form OAR-1 L-2018-015, Plan of Study 316(b) Implementation2017-04-28028 April 2017 Plan of Study 316(b) Implementation L-2017-015, PWROG-15105-NP PA-MSC-1288 PWR Rv Internals Cold-Work Assessment, Materials Committee.2016-04-30030 April 2016 PWROG-15105-NP PA-MSC-1288 PWR Rv Internals Cold-Work Assessment, Materials Committee. ML16084A6162016-03-24024 March 2016 Submittal of Biological Opinion for the Continued Operation of St. Lucie Nuclear Power Plant, Units 1 and 2 in St. Lucie County, Florida ML16063A0072016-02-26026 February 2016 Participation in Additional Work Under the Support for Applicant Action Items 1, 2, and 7 from the Final Safety Evaluation on MRP-227, Revision 0 PA-MSC-0983 R2 Cafeteria Task 8 and Acceptance Criteria for Measurement Of.. ML15352A0532016-01-0707 January 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Revaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights L-2015-297, Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, and Submittal of Site FLEX Final Integrated Plan2015-12-10010 December 2015 Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, and Submittal of Site FLEX Final Integrated Plan L-2015-300, ANP-3352NP, Revision 1, Transition License Amendment Request, Technical Report.2015-11-30030 November 2015 ANP-3352NP, Revision 1, Transition License Amendment Request, Technical Report. ML15314A1602015-10-29029 October 2015 St. Lucie, Units 1 and 2 - License Renewal Commitment, Submittal of Pressurizer Surge Line Welds Inspection Program L-2015-221, Report of 10 CFR 50.59 Plant Changes2015-10-16016 October 2015 Report of 10 CFR 50.59 Plant Changes ML15240A1542015-09-0808 September 2015 Staff Observations of Sump Strainer Head Loss Testing at Alden Laboratory for Generic Safety Issue 191 L-2015-206, ANP-3428NP, Revision 0, St. Lucie Unit 2 Fuel Transition: Response to SNPB-RAI-1, Attachment 4 to L-2015-2062015-07-31031 July 2015 ANP-3428NP, Revision 0, St. Lucie Unit 2 Fuel Transition: Response to SNPB-RAI-1, Attachment 4 to L-2015-206 L-2015-177, Fuel Transition Small Break LOCA Summary Report, ANP-3345NP, Revision 12015-06-30030 June 2015 Fuel Transition Small Break LOCA Summary Report, ANP-3345NP, Revision 1 L-2015-143, Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2015-05-14014 May 2015 Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events L-2015-272, 1301103.401, Revision 0, Flaw Tolerance Evaluation of St. Lucie Surge Line Welds Using ASME Code Section XI, Appendix L, May 20152015-05-0808 May 2015 1301103.401, Revision 0, Flaw Tolerance Evaluation of St. Lucie Surge Line Welds Using ASME Code Section XI, Appendix L, May 2015 L-2016-052, TN-5696-00-02, Revision 0, Technical Note Assessment of Laboratory PWSCC Crack Growth Rate Data Compiled for Alloys 690, 52, and 152 with Regard to Factors of Improvement (Foi) Versus Alloys 600 and 182.2015-03-31031 March 2015 TN-5696-00-02, Revision 0, Technical Note Assessment of Laboratory PWSCC Crack Growth Rate Data Compiled for Alloys 690, 52, and 152 with Regard to Factors of Improvement (Foi) Versus Alloys 600 and 182. L-2015-091, ANP-3396NP, Revision 0, Fuel Transition Supplemental Information to Support the LAR2015-03-31031 March 2015 ANP-3396NP, Revision 0, Fuel Transition Supplemental Information to Support the LAR 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 ML15083A2642015-03-10010 March 2015 St. Lucie, Units 1 and 2 - Submittal of Revision 0 to FPL-072-PR-002, Flooding Hazards Reevaluation Report L-2015-048, St. Lucie, Units 1 and 2 - Submittal of Revision 0 to FPL-072-PR-002, Flooding Hazards Reevaluation Report2015-03-10010 March 2015 St. Lucie, Units 1 and 2 - Submittal of Revision 0 to FPL-072-PR-002, Flooding Hazards Reevaluation Report L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Cover Page to Page 1092015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Cover Page to Page 109 L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-92015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-9 L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Figure 4-10 Through the End2015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Figure 4-10 Through the End ML15083A2652015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-9 ML15083A2662015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Figure 4-10 Through the End L-2014-366, ANP-3352NP, Revision 0, St. Luice, Unit 2, Fuel Transition License Amendment Request, Technical Report2014-12-31031 December 2014 ANP-3352NP, Revision 0, St. Luice, Unit 2, Fuel Transition License Amendment Request, Technical Report ML14338A5552014-12-0404 December 2014 NRC-2013-TN3079-NRC 2014 St. Lucie License Renewal ML14338A5542014-12-0404 December 2014 NRC-2013- TN2986-NRC 2014 St. Lucie L-2014-125, Report of 10 CFR 50.59 Plant Changes2014-05-0606 May 2014 Report of 10 CFR 50.59 Plant Changes ML13360A2022013-12-12012 December 2013 EPA Echo Report Martin County, Fl 2023-09-28
[Table view] Category:Miscellaneous
MONTHYEARL-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update 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-2023-028, 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-2023-009, Owner'S Activity Report2023-01-31031 January 2023 Owner'S Activity Report ML22227A0532022-08-15015 August 2022 Biological Opinion for the Continued Operation of St. Lucie Nuclear Power Plant ML22124A0112022-04-30030 April 2022 Scoping Summary Report - Final ML22010A0942022-01-0404 January 2022 Trp 29 St. Lucie SLRA - Tank Breakout L-2021-178, Report of 10 CFR 50.59 Plant Changes2021-11-0808 November 2021 Report of 10 CFR 50.59 Plant Changes ML19252A4002019-09-0909 September 2019 FPL to NRC, Notification of Smalltooth Sawfish Capture at St. Lucie L-2017-173, Environmental Protection Plan Report, Unusual or Important Environmental Event - Turtle Mortality - 09/11/2017 Event2017-09-28028 September 2017 Environmental Protection Plan Report, Unusual or Important Environmental Event - Turtle Mortality - 09/11/2017 Event L-2017-117, Submittal of SL2-23 Outage, Owner'S Activity Report, Form OAR-12017-06-20020 June 2017 Submittal of SL2-23 Outage, Owner'S Activity Report, Form OAR-1 ML15352A0532016-01-0707 January 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Revaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights L-2015-297, Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, and Submittal of Site FLEX Final Integrated Plan2015-12-10010 December 2015 Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, and Submittal of Site FLEX Final Integrated Plan ML15314A1602015-10-29029 October 2015 St. Lucie, Units 1 and 2 - License Renewal Commitment, Submittal of Pressurizer Surge Line Welds Inspection Program L-2015-221, Report of 10 CFR 50.59 Plant Changes2015-10-16016 October 2015 Report of 10 CFR 50.59 Plant Changes ML15240A1542015-09-0808 September 2015 Staff Observations of Sump Strainer Head Loss Testing at Alden Laboratory for Generic Safety Issue 191 L-2015-143, Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2015-05-14014 May 2015 Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML15083A2642015-03-10010 March 2015 St. Lucie, Units 1 and 2 - Submittal of Revision 0 to FPL-072-PR-002, Flooding Hazards Reevaluation Report L-2015-048, St. Lucie, Units 1 and 2 - Submittal of Revision 0 to FPL-072-PR-002, Flooding Hazards Reevaluation Report2015-03-10010 March 2015 St. Lucie, Units 1 and 2 - Submittal of Revision 0 to FPL-072-PR-002, Flooding Hazards Reevaluation Report ML14338A5552014-12-0404 December 2014 NRC-2013-TN3079-NRC 2014 St. Lucie License Renewal ML14338A5542014-12-0404 December 2014 NRC-2013- TN2986-NRC 2014 St. Lucie L-2014-125, Report of 10 CFR 50.59 Plant Changes2014-05-0606 May 2014 Report of 10 CFR 50.59 Plant Changes ML13360A2022013-12-12012 December 2013 EPA Echo Report Martin County, Fl L-2013-193, Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) Acceptance Review Clarification Response2013-06-14014 June 2013 Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) Acceptance Review Clarification Response L-2013-175, Report of 10 CFR 50.59 Plant Changes2013-05-23023 May 2013 Report of 10 CFR 50.59 Plant Changes L-2012-437, Standardization of Senior Reactor Operator Fuel Handling Duties2012-12-27027 December 2012 Standardization of Senior Reactor Operator Fuel Handling Duties L-2012-105, Response to Nuclear Performance and Code Review Branch Request for Additional Information Identified During an Audit of Analyses Supporting the Extended Power Uprate License Amendment Request2012-03-15015 March 2012 Response to Nuclear Performance and Code Review Branch Request for Additional Information Identified During an Audit of Analyses Supporting the Extended Power Uprate License Amendment Request ML1026405722010-09-14014 September 2010 E-mail St. Lucie Capture Summary Update for January Through August 2010 ML1019304172010-05-0606 May 2010 Tritium Database Report ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants L-2010-059, Florida Dept of Environmental Protection - Wastewater Application Form 2CS - Permit to Discharge Process Wastewater from New or Existing Industrial Wastewater Facilities to Surface Water2010-03-18018 March 2010 Florida Dept of Environmental Protection - Wastewater Application Form 2CS - Permit to Discharge Process Wastewater from New or Existing Industrial Wastewater Facilities to Surface Water ML1008304422010-03-18018 March 2010 Florida Dept of Environmental Protection - Wastewater Application Form 2CS - Permit to Discharge Process Wastewater from New or Existing Industrial Wastewater Facilities to Surface Water L-2009-101, Report of 10 CFR 50.59 Plant Changes, for the Period of May 28, 2007 Through November 21, 20082009-04-22022 April 2009 Report of 10 CFR 50.59 Plant Changes, for the Period of May 28, 2007 Through November 21, 2008 L-2008-261, Technical Specification Special Report Inoperable Containment Sump Wide Range Level Channel B2008-12-16016 December 2008 Technical Specification Special Report Inoperable Containment Sump Wide Range Level Channel B ML0807010172008-03-10010 March 2008 EPRI Reports (St. Lucie Pressurizer Nozzle DM Weld Examination Project Internal Office Report) L-2008-030, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2008-02-27027 February 2008 Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors NOC-AE-07002231, Request for Relaxation of Requirements from Revision 1 of Order EA-03-009 Establishing Interim Inspection Requirements for Reactor Pressure Vessel Head Penetrations (Relief Request RR-ENG-2-46)2007-11-0707 November 2007 Request for Relaxation of Requirements from Revision 1 of Order EA-03-009 Establishing Interim Inspection Requirements for Reactor Pressure Vessel Head Penetrations (Relief Request RR-ENG-2-46) L-2007-167, Report of 10 CFR 50.59 Plant Changes During the Period of December 19, 2005 Through May 27, 20072007-10-29029 October 2007 Report of 10 CFR 50.59 Plant Changes During the Period of December 19, 2005 Through May 27, 2007 L-2007-168, Technical Specifications Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42007-10-29029 October 2007 Technical Specifications Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 L-2007-137, Technical Specification Special Report, Inoperable Containment Sump Wide Range Level Channel B2007-08-31031 August 2007 Technical Specification Special Report, Inoperable Containment Sump Wide Range Level Channel B L-2007-029, Semi-Annual Fitness-For-Duty Program Performance Data for the Six-Month Period Ending December 31, 20062007-02-26026 February 2007 Semi-Annual Fitness-For-Duty Program Performance Data for the Six-Month Period Ending December 31, 2006 L-2007-020, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20062007-02-0606 February 2007 Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2006 L-2006-078, Proposed License Amendment, Containment Spray Nozzle Surveillance Change2006-10-19019 October 2006 Proposed License Amendment, Containment Spray Nozzle Surveillance Change L-2006-217, Day Post Outage Steam Generator Report Technical Specification 4.4.5.5.c2006-09-20020 September 2006 Day Post Outage Steam Generator Report Technical Specification 4.4.5.5.c L-2006-152, NRC Order EA-03-009 - Reactor Vessel Head and Vessel Head Penetration Nozzle Inspection Results SL2-162006-08-10010 August 2006 NRC Order EA-03-009 - Reactor Vessel Head and Vessel Head Penetration Nozzle Inspection Results SL2-16 L-2006-180, Sation; St. Lucie, Units 1 and 2 and Turkey Point, Units 3 and 4 - Groundwater Questionnaire2006-07-31031 July 2006 Sation; St. Lucie, Units 1 and 2 and Turkey Point, Units 3 and 4 - Groundwater Questionnaire L-2006-167, Environmental Protection Plan Report Responses to FDEP Comments on FPL Proposal for Information Collection Clean Water Act Section 316(b)2006-07-0606 July 2006 Environmental Protection Plan Report Responses to FDEP Comments on FPL Proposal for Information Collection Clean Water Act Section 316(b) L-2006-139, Report of 10 CFR 50.59 Plant Changes2006-06-16016 June 2006 Report of 10 CFR 50.59 Plant Changes L-2006-063, Technical Specification Special Report, Radwaste Building Exhaust System, Plant Ventilation Stack Particulate Iodine and Noble Gas (Sping) Radiation - Out of Service2006-02-22022 February 2006 Technical Specification Special Report, Radwaste Building Exhaust System, Plant Ventilation Stack Particulate Iodine and Noble Gas (Sping) Radiation - Out of Service L-2006-043, Responses to NRC Requests for Additional Information on WCAP-16208-P, Rev. 0, NDE Inspection Length for CE Steam Generator Tubesheet Region Explosive Expansions.2006-01-23023 January 2006 Responses to NRC Requests for Additional Information on WCAP-16208-P, Rev. 0, NDE Inspection Length for CE Steam Generator Tubesheet Region Explosive Expansions. 2023-09-28
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St. Lucie Pressurizer Nozzle DM Weld Examination Project Internal Office Report St. Lucie Pressurizer DM weld examinations The scope of this project for EPRI was to oversee the examination of six dissimilar metal (DM) welds associated with the Combustion Engineering Pressurizer vessel that was recently removed from service from the St. Lucie Nuclear Power Station. The examinations were to include surface and volumetric examinations, specifically visible liquid dye penetrant (PT) examinations of both the outside (OD) surface and inside (ID) surface of each DM weld, and Phased-Array ultrasonic (UT) examination of the volume of each DM weld. The examination area and volume were to be the same as for a normal Inservice Inspection (ISI) examination of these welds.
EPRI contracted Structural Integrity Associates, Inc.(SIA) to perform the NDE, which also required a procedure expansion of the SIA phased-array UT procedure SI-UT-130.
Initial Visit to the Memphis Facility:
I first met with Kevin Butler and David Jennings, at the Studsvik/Race facility on Presidents Island in Memphis on January 25th, in order to look at the Pressurizer heads and to give the facility instructions on how to prepare the 6 associated dissimilar metal welds for examination. The as-found condition of the nozzles was that they were fully intact and in the same condition as they had come from the plant. The lower head piece contained one nozzle, which was the 14 Surge nozzle. This nozzle had a screen/filter associated with it, which was located on the inside surface of the head. The upper head piece contained five nozzles, which were the 3 Spray nozzle, the 4 Relief nozzle, and three 4 Safety nozzles. The Spray nozzle also had a nozzle associated with it on the opposite surface of the head, which had been internal to the Pressurizer during operation.
Each of the 6 nozzles appeared to have end caps welded on them, and the external surface of both head pieces appeared to be coated with some sort of paint or protective coating.
Upper Head Piece showing five nozzles and the internal portion of the Spray nozzle Cut line
St. Lucie Pressurizer Nozzle DM Weld Examination Project Internal Office Report Lower head containing the Surge nozzle Internal portion of Surge nozzle Cut line During the initial visit to the facility, I explained a little bit about the examinations that we were going to be performing on the nozzles and why. I requested that the two internal nozzles be cut off of the head pieces, and that each end cap be completely removed, so that we would have access to the ID of each nozzle. I instructed them to remove any internal thermal sleeves that would interfere with our access to the inside surfaces of the welds, as well. I also requested that all paint, coatings, rust and scale be removed from all surfaces of the pieces, down to the bare metal. At that time, they expressed concern for their ability to remove the end cap from the Surge nozzle, due to the size of the weld. We discussed that it should only involve cutting along the weld at the edge of the cap, and that the cap should come off fairly easily. They also asked me if it would be a problem if the flanges on the Safety nozzles were damaged during the cutting, and I said that it was not a concern as long as the weld area of the nozzle was not affected.
The February 4th Week at the Memphis Facility:
Upon arrival to the facility on Monday, February 4th, we received radiation worker training and facility safety training and were then allowed to dress out and enter the Sectional Shop, where the pieces were staged. The as-found condition of the upper head piece, at this time, was that the internal nozzle and end caps had been completely removed and the surfaces had been bead blasted with some sort of carbon steel metallic material, which had removed all paint and coatings but left the surface in a rough rusty looking condition. Even the stainless and inconel surfaces were rusty. Our assumption was that this was caused from carbon steel blast material being embedded into the surfaces. The flanges at the ends of the three Safety nozzles were completely removed along with the end caps. On the lower head piece, the DM weld on the Surge nozzle was actually damaged from the cutting and there were portions of the end plug still in place.
When I inquired about this, they told me that the end cap had actually been a plug and that it had been very difficult to remove. I took one of the facilities cutting technicians out to the nozzle and showed him the portions of the plug that were still in place and asked him to carefully remove the weld around the edge of it, and that it would come out.
He followed these instructions and was able to remove the remaining portion of the plug.
St. Lucie Pressurizer Nozzle DM Weld Examination Project Internal Office Report An assessment of the Surge nozzle, after complete plug removal showed that a great deal of the ID of the weld had been damaged by flame cutting.
Upper Head after initial prep work Safety nozzle after flange removal Surge nozzle after initial prep work (note ID damage caused by flame cutting)
Portions of the end plug still in place Flame cut hole in the DM weld
St. Lucie Pressurizer Nozzle DM Weld Examination Project Internal Office Report We had brought our own side grinder and flapper wheels, so we proceeded to prepare the outside surfaces of the nozzle weld areas to remove the rust and smooth out the rough surfaces. By the end of the first day, we had managed to adequately prepare the outside surfaces of the welds for PT and UT examinations.
Upper head after flapping Surge nozzle after flapping and plug removal On Tuesday, we set up and performed liquid dye penetrant (PT) examinations of the OD surface of each DM welds. There were two small rounded indications noted during the OD PT exams. One was on the Relief nozzle, in the DM weld surface area. And the other was on the C Safety nozzle, also in the DM weld surface.
Relief Nozzle OD PT indication C Safety nozzle OD PT indication
St. Lucie Pressurizer Nozzle DM Weld Examination Project Internal Office Report Tuesday afternoon, we began Phased-Array UT examination on the A Safety nozzle DM weld, using longitudinal ultrasonic sound beams projected from 0° to 80° angles. We immediately noted a large number of planar reflectors in the weld, which were stacked on top of each other and appeared to extend from the ID surface of the weld up to approximately 0.325 from the OD surface of the weld, at the deepest point. These reflectors were numerous and were present 360° around the circumference of the weld.
When scanning across the tops of these indications, the UT sound beams that were projected normal to the surface (straight beams) did not pick up the indications, as you would expect them to if the indications were caused by internal inclusions. Under normal field examination conditions, these types of indications would have to be recorded and evaluated as one continuous linear planer flaw, seen 360° around the weld.
Screen shot of these stacked UT indications, as seen at the 3 oclock position Stacked indications Backwall On Wednesday, we continued UT examination of the remaining nozzles. The two other Safety nozzle DM welds also contained 360° linear planar indications. The B Safety DM weld indication was measured from the ID surface to within 0.396 of the outside surface. The C Safety nozzle DM weld indication was measured from the ID surface up to 0.495 of the outside surface. These indication exhibited the same features as that of the A Safety nozzle DM weld.
St. Lucie Pressurizer Nozzle DM Weld Examination Project Internal Office Report The Spray nozzle DM weld was found to contain one embedded planar indication that did not appear to be connected to the ID surface, and was indicative of a lack of fusion type flaw located along the upper bevel of the weld to base material interface. The Relief and Surge nozzles did not contain any recordable indications.
Wednesday evening, we purchased a die grinder and some abrasive wheels in order to prepare the ID surfaces of these DM welds for PT examination. On Thursday, we were able to use these new tools to prepare a suitable ID surface for examination on each nozzle DM weld. The PT of the inside surfaces the A and C Safety nozzles produced several aligned dotted indications within the weld material, which were very defined and easy to interpret as surface connected flaws. The B Safety nozzle had three very faint indications in one area of the weld inside surface, which were reproducible, but were not as definitive as on the other two Safety nozzles. Surprisingly, the Spray and Surge nozzles also had recordable PT indications on the ID surfaces, in the area of the DM weld. They, too, were aligned. The Surge nozzle indications were somewhat small and faint, similar to that of the B safety nozzle. However, the Spray nozzle indications were very defined and sizeable. We re-examined the Surge and Spray nozzle DM welds after the ID PT examinations, but were still unable to record UT indications associated with the PT indications.
Typical Safety nozzle aligned ID PT indications Spray nozzle aligned ID PT indications
St. Lucie Pressurizer Nozzle DM Weld Examination Project Internal Office Report Faint ID PT indications on the Surge nozzle Summary of NDE findings:
All six nozzle DM welds on the former St. Lucie Combustion Engineering Pressurizer vessel were successfully examined from both the OD and ID with liquid dye penetrant, and were volumetrically examined by the Phased-Array UT method, using Structural Integrity Associates PDI qualified procedure SI-UT-130. The only limitations to these examinations were on the Surge nozzle, where initial attempts to remove the end plug by flame cutting had resulted in extensive damage to the ID surface and in one area had resulted in a hole through the middle of the DM weld.
The OD surface PT examinations of these six nozzle welds resulted in two recordable indications. One small rounded indication was recorded in the Relief nozzle DM weld crown surface. One small rounded indication was recorded in the C Safety nozzle DM weld crown surface. Both of these indications were indicative of porosity-type indications, which may have been uncovered during the bead blasting and flapping processes. Further surface preparations were not performed in the areas of these indications to see if they could be removed.
The phased-array UT examinations of the nozzles resulted in multiple stacked planar indications being recorded in all three of the Safety nozzle DM welds, which under normal field NDE conditions would likely be reported as 360° linear planar flaws. The approximate through-wall depths of these indications at the deepest points were 80% on the A Safety nozzle, 75% on the B Safety nozzle, and 69% on the C Safety nozzle.
Additionally, one non-surface connected indication, indicative of lack of fusion was
St. Lucie Pressurizer Nozzle DM Weld Examination Project Internal Office Report recorded on the Spray nozzle. No recordable indications were noted on the Relief or Surge nozzles, during the UT examinations.
The ID surface PT examinations of the nozzles resulted in multiple, well defined, aligned surface indications being recorded in the weld root area of the A and C Safety nozzles and the Spray nozzle. The B Safety nozzle and Surge nozzle each showed a few faint indications in the weld root area, which were not as well defined, but were recordable. The Relief nozzle did not reveal any ID surface indications. As with the OD surface indications that were noted, all of these ID connected indications could have been uncovered during the surface preparation activities. Further surface preparations were not attempted in the areas of any of these ID indications to see if they could be removed.
Conclusions The two rounded indications recorded during the OD PT examinations are not unusual, during normal ISI surface examinations. Additional grinding would normally be prescribed to attempt to remove these indications. Surface Eddy Current examination could also be utilized to determine if these indications become linear underneath the surface.
The UT indications recorded on the three Safety nozzles contained multiple planar reflectors, which appear to be vertically stacked and extend from the ID surface to a significant through-wall depth. These indications are indicative of corrosion cracking, but could also be attributed to multiple stacked inclusions in the weld material, left over from construction. Performing automated UT on these three nozzle welds would allow for better flaw mapping and analysis. However, under normal field NDE conditions, these three welds would certainly be reported as containing 360° linear planar flaws of significant through-wall depth, which would require immediate repair.
The aligned ID PT indications noted on several of these nozzles could also be indicative of corrosion cracking. During many recent PT examinations of Reactor Upper Head penetration welds, PWSCC flaws were initially recorded as small aligned snake bite indications in the surface of the weld, which upon further surface grinding revealed linear cracking. However, it is also possible that the initial surface preparation of these welds uncovered inclusions in the weld material, which may have been removed upon further surface preparation. Surface Eddy Current examination could also be used to determine whether or not these indications are linked.