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Category:Meeting Briefing Package/Handouts
MONTHYEARML22336A0382022-12-0808 December 2022 Presentation Slides December 8, 2022, pre-submittal Meeting to Discuss Proposed License Amendment Request Regarding TS 3.7.11, Control Room Area Chilled Water System (Cracws) ML22251A2352022-09-14014 September 2022 Presentation Slides for September 14, 2022, Observation Public Meeting ML22067A1992022-03-0303 March 2022 Annual Assessment Meeting Presentation ML21336A1422021-12-0707 December 2021 December 7, 2021, Pre-submittal Presentation Slides Regarding Embedded Flaw Repair Relief Request - Revised ML21327A2112021-11-23023 November 2021 December 7, 2021, Pre-submittal Presentation Regarding Embedded Flaw Repair Relief Request ML21236A2862021-08-30030 August 2021 License Amendment Request for Revision 1 of DPC-NE-1007-P, Conditional Exemption of the End-of-Cycle (EOC) Moderator Temperature Coefficient (Mtc) Measurement Methodology ML21116A2542021-04-15015 April 2021 C2R24 Relief Request Pre-Submittal Slides Call 1 ML21089A1732021-03-30030 March 2021 EOC Slides Final ML21081A1242021-03-22022 March 2021 EOC Slides Final ML19318F2912019-11-18018 November 2019 Duke Energy Presentation for the Pre-submittal Meeting on November 18, 2019, Regarding the RPV Stud Examination Relief Request ML19214A0562019-08-0707 August 2019 Presentation: Duke Energy Presubmittal Meeting - August 7, 2019 ML18157A0322018-06-0606 June 2018 Nw System LAR Presubmittal Meeting ML17278A1342017-10-0404 October 2017 Duke Presentation for Public Meeting 09-20-17 ML16242A2382016-08-30030 August 2016 Catawba/Mcguiproposed Changes to Technical Specification 3.8.1, AC Sources - Operating. ML16112A0112016-04-28028 April 2016 Duke Presentation in Support of April 28, 2016 Pre-Submittal Meeting Catawba Nuclear Station, Units 1 and 2, License Amendment Request Proposed TS Bases Descriptions for Shared Systems ML16117A4632016-04-28028 April 2016 Duke Presentation in Support of April 28, 2016 Pre-Submittal Meeting Catawba Nuclear Station, Units 1 and 2, License Amendment Request Proposed TS Bases Descriptions for Shared Systems (Revised) ML16081A3352016-03-17017 March 2016 Summary of Meeting with Public Concerning Annual Assessment of Catawba Nuclear Station, Units 1 and 2 ML15106A0302015-04-15015 April 2015 Meeting Summary with Public to Discuss the Annual Assessment of Catawba Nuclear Station, Units 1 and 2 ML15099A5872015-04-14014 April 2015 Duke Energy Slides for April 14 Meeting on NFPA-805 for Catawba, McGuire and Robinson ML15085A4242015-03-24024 March 2015 Nuclear Reactor Effluents Webinar ML14126A6792014-05-0606 May 2014 Summary of Public Meeting with Catawba, Units 1 & 2 to Discuss Annual Assessment ML14016A1692014-01-0707 January 2014 Presentation Regarding Use of High Density Polyethylene (Hdpe) Piping as Replacement for Underground Piping January 7, 2014 -Catawba Nuclear Station Hdpe Relief Request ML13312A9882013-11-0808 November 2013 Summary of Public Meeting with Duke Energy Carolinas, LLC, to Provide Opportunities to Discuss the Planned Fukushima-Related Modifications ML13308A0072013-11-0101 November 2013 Open Phase Resolution Update Meeting Duke Energy Entitled Open Phase Detection and Protection. ML13127A0802013-04-18018 April 2013 Fleet Fire Protection Program NFPA 805 National Fire Protection Association NFPA 805 Pre-LAR Application for CNS, MNS, RNP ML12261A2232012-09-17017 September 2012 September 11, 2012 - Summary of Category 1 Public Meeting Held in Atlanta, Ga ML12206A3252012-08-0707 August 2012 G20120513/EDATS: OEDO-2012-0436 - Briefing Book for Meeting with Duke Energy on August 7, 2012 ML12188A0712012-07-11011 July 2012 G20120473/ EDATS: OEDO-2012-0404 - Briefing Book - Briefing Package for Meeting with Duke Energy on July 11, 2012 ML12117A2542012-04-26026 April 2012 2011 EOC Slides ML11097A0272011-04-14014 April 2011 Summary of Meeting with Duke Energy Carolinas, LLC, on Upcoming Submittal of License Amendments Regarding Implementation of National Fire Protection Association Standard 805, (TACs ME5767 & ME5768, Catawba 1 & 2 ME5769 & ME5770 Mcguire 1 & ML0927304602009-10-0707 October 2009 09/01/2009 Summary of Conference Call with Duke Regarding Responses to Generic Letter (GL) 2004-02. Meeting Handouts ML0912803032009-05-0808 May 2009 Summary of Public Meeting/Open House to Provide Opportunities to Discuss Annual Assessment of Catawba Nuclear Station with Public ML0833000612008-11-24024 November 2008 Meeting Slides for Category 1 Public Meeting with Duke Energy Carolinas, Regarding a Request for Additional Information on Duke'S Response to GL 200-04 ML0822001632008-08-0101 August 2008 Meeting Slides, Performance Discussion Meeting to Provide the NRC Staff with an Update of Plant Performance at the Catawba Nuclear Station ML0819903672008-07-15015 July 2008 Handouts from Duke Energy & NRC Meeting - NQA-1 Based QA Program Conversion ML0720502202007-05-0303 May 2007 Public Meeting Slides for Catawba ML0525503072005-09-21021 September 2005 Meeting Summary with NRC, Ventilation Systems Amendments ML0529200662005-09-19019 September 2005 9/19/05, Catawba, Units 1 and 2, Enclosure 2, Meeting Summary Handouts, Nuclear Service Water System ML0524300932005-08-18018 August 2005 Att. 6, FAQ Log ML0519501972005-06-27027 June 2005 6/27/05, Catawba, Meeting Summary Handouts, Attachment 2, Polyethylene Piping Use for Safety Related Buried Service Water Pipe ML0510905952005-03-22022 March 2005 Meeting Slides for NRC CY2004 Annual Assessment Meeting - Catawba Nuclear Station ML0502501572004-12-0606 December 2004 Meeting Presentation Slides to 12/06/2004 Summary of Meeting with Duke Energy Corporation to Discuss Appendix R Reconstitution and Transition to NFPA 805 ML0421903532004-07-30030 July 2004 Summary of 07/27/2004 Meeting with Duke Energy Corp. Re. Modification to Quality Assurance Program for Catawba, McGuire, and Oconee Nuclear Station, Attachment 2 - Meeting Handouts ML0412502222004-04-23023 April 2004 Meeting Handouts Next Generation Fuel and MOX ML0411105312004-04-0808 April 2004 Duke Energy Corporation Meeting Handouts, Enclosure 2, Meeting Summary ML0403602192004-01-22022 January 2004 /22/2004 Meeting Handouts by the Licensee - Enclosure 3 ML0403707402004-01-22022 January 2004 Enclosure 2 - Meeting Handouts from 01/22/2004 Meeting Between NRC-Duke Power and Framatome Anp ML0332406362003-11-17017 November 2003 Meeting Between Duke Energy, Framatome Anp and NRC Staff on Use of MOX Lead Test Fuel Assemblies at Catawba Nuclear Station ML0327206212003-09-24024 September 2003 Examiner - Vendor Matrix with Phone Number ML0327206112003-09-22022 September 2003 Exam Process 2022-09-14
[Table view] Category:Slides and Viewgraphs
MONTHYEARML23087A2972023-04-17017 April 2023 Annual Assessment Meeting Presentation ML22336A0382022-12-0808 December 2022 Presentation Slides December 8, 2022, pre-submittal Meeting to Discuss Proposed License Amendment Request Regarding TS 3.7.11, Control Room Area Chilled Water System (Cracws) ML22251A2352022-09-14014 September 2022 Presentation Slides for September 14, 2022, Observation Public Meeting ML22109A2122022-04-20020 April 2022 Duke Energy Pre-Submittal Public April 20, 2022, Meeting Presentation ML22067A1992022-03-0303 March 2022 Annual Assessment Meeting Presentation ML21336A1422021-12-0707 December 2021 December 7, 2021, Pre-submittal Presentation Slides Regarding Embedded Flaw Repair Relief Request - Revised ML21322A3262021-11-29029 November 2021 Duke Energy November 29, 2021 Pre-Submittal Public Meeting Slides for EOF Relocation Licensing Amendment Request ML21327A2112021-11-23023 November 2021 December 7, 2021, Pre-submittal Presentation Regarding Embedded Flaw Repair Relief Request ML21236A2862021-08-30030 August 2021 License Amendment Request for Revision 1 of DPC-NE-1007-P, Conditional Exemption of the End-of-Cycle (EOC) Moderator Temperature Coefficient (Mtc) Measurement Methodology ML21116A0662021-04-22022 April 2021 C2R24 Relief Request Pre-Submittal Slides Call 2 ML21116A2542021-04-15015 April 2021 C2R24 Relief Request Pre-Submittal Slides Call 1 ML21089A1732021-03-30030 March 2021 EOC Slides Final ML21081A1242021-03-22022 March 2021 EOC Slides Final ML20134J0052020-05-13013 May 2020 EOC Slides (2) ML20125A2312020-05-0404 May 2020 EOC Slides ML19318F2912019-11-18018 November 2019 Duke Energy Presentation for the Pre-submittal Meeting on November 18, 2019, Regarding the RPV Stud Examination Relief Request ML19214A0562019-08-0707 August 2019 Presentation: Duke Energy Presubmittal Meeting - August 7, 2019 ML17278A1342017-10-0404 October 2017 Duke Presentation for Public Meeting 09-20-17 ML16112A0112016-04-28028 April 2016 Duke Presentation in Support of April 28, 2016 Pre-Submittal Meeting Catawba Nuclear Station, Units 1 and 2, License Amendment Request Proposed TS Bases Descriptions for Shared Systems ML16117A4632016-04-28028 April 2016 Duke Presentation in Support of April 28, 2016 Pre-Submittal Meeting Catawba Nuclear Station, Units 1 and 2, License Amendment Request Proposed TS Bases Descriptions for Shared Systems (Revised) ML16081A3352016-03-17017 March 2016 Summary of Meeting with Public Concerning Annual Assessment of Catawba Nuclear Station, Units 1 and 2 ML15106A0302015-04-15015 April 2015 Meeting Summary with Public to Discuss the Annual Assessment of Catawba Nuclear Station, Units 1 and 2 ML15099A5872015-04-14014 April 2015 Duke Energy Slides for April 14 Meeting on NFPA-805 for Catawba, McGuire and Robinson ML15085A4242015-03-24024 March 2015 Nuclear Reactor Effluents Webinar ML14126A6792014-05-0606 May 2014 Summary of Public Meeting with Catawba, Units 1 & 2 to Discuss Annual Assessment ML14016A1692014-01-0707 January 2014 Presentation Regarding Use of High Density Polyethylene (Hdpe) Piping as Replacement for Underground Piping January 7, 2014 -Catawba Nuclear Station Hdpe Relief Request ML13312A9882013-11-0808 November 2013 Summary of Public Meeting with Duke Energy Carolinas, LLC, to Provide Opportunities to Discuss the Planned Fukushima-Related Modifications ML13308A0072013-11-0101 November 2013 Open Phase Resolution Update Meeting Duke Energy Entitled Open Phase Detection and Protection. ML13127A0802013-04-18018 April 2013 Fleet Fire Protection Program NFPA 805 National Fire Protection Association NFPA 805 Pre-LAR Application for CNS, MNS, RNP ML12261A2232012-09-17017 September 2012 September 11, 2012 - Summary of Category 1 Public Meeting Held in Atlanta, Ga ML12117A2542012-04-26026 April 2012 2011 EOC Slides ML1112308322011-05-0303 May 2011 End of Cycle Public Meeting Summary ML11097A0272011-04-14014 April 2011 Summary of Meeting with Duke Energy Carolinas, LLC, on Upcoming Submittal of License Amendments Regarding Implementation of National Fire Protection Association Standard 805, (TACs ME5767 & ME5768, Catawba 1 & 2 ME5769 & ME5770 Mcguire 1 & ML1034807072010-12-14014 December 2010 Public Meeting Summary - Duke Quality Assurance Program Discussion Meeting ML1011604522010-04-26026 April 2010 Summary of Public Meeting with Catawba Nuclear Station to Discuss Nrc'S Reactor Oversight Process and the Nrc'S Annual Assessment of Plant Safety Performance for the Period of January 1, 2009 - December 31, 2009 ML0912803032009-05-0808 May 2009 Summary of Public Meeting/Open House to Provide Opportunities to Discuss Annual Assessment of Catawba Nuclear Station with Public ML0833000612008-11-24024 November 2008 Meeting Slides for Category 1 Public Meeting with Duke Energy Carolinas, Regarding a Request for Additional Information on Duke'S Response to GL 200-04 ML0822001632008-08-0101 August 2008 Meeting Slides, Performance Discussion Meeting to Provide the NRC Staff with an Update of Plant Performance at the Catawba Nuclear Station ML0819903672008-07-15015 July 2008 Handouts from Duke Energy & NRC Meeting - NQA-1 Based QA Program Conversion ML0720502202007-05-0303 May 2007 Public Meeting Slides for Catawba ML0618002722006-06-28028 June 2006 AIT Meeting Summary Handouts ML0615106012006-05-23023 May 2006 EPRI HRA Users Group Review of Draft NUREG-1842 ML0611703402006-04-26026 April 2006 Annual Assessment Meeting Cy 2005 Slide Show ML0535502672005-12-0707 December 2005 Service Water Project Update Presentation on 12/07/2005 ML0510905952005-03-22022 March 2005 Meeting Slides for NRC CY2004 Annual Assessment Meeting - Catawba Nuclear Station ML0502501572004-12-0606 December 2004 Meeting Presentation Slides to 12/06/2004 Summary of Meeting with Duke Energy Corporation to Discuss Appendix R Reconstitution and Transition to NFPA 805 ML0412502222004-04-23023 April 2004 Meeting Handouts Next Generation Fuel and MOX ML0407011552004-02-24024 February 2004 Plant Performance Update Meeting ML0332406362003-11-17017 November 2003 Meeting Between Duke Energy, Framatome Anp and NRC Staff on Use of MOX Lead Test Fuel Assemblies at Catawba Nuclear Station ML0403506912003-08-27027 August 2003 DRS Open Items Status 2023-04-17
[Table view] |
Text
NRC Informational Call Potential Relief Request:
Reactor Vessel Head Nozzle #74 Examination Catawba Nuclear Station Unit 2 April 15, 2021 1
Agenda Introductions and Opening Remarks Objectives and Scope Inspection History of the Catawba Unit 2 RVCH Current Inspection Requirements Nozzle #74 Description RVCH Examinations this RFO Leak Path Assessment Obstruction Nozzle #74 Funnel Removal Attempts Proposed Alternative Technical Basis for Relief Request Timeline for Submittal 2
Objectives and Scope Objectives:
Present Dukes potential need for relief for deferral of completion of the leak path assessment of CRDM Nozzle
- 74 at Catawba Unit 2 for one nominal 18-month cycle, in the event undue hardship is encountered with obstruction removal efforts Scope:
Proposed alternative only applies to a fraction of the leak path assessment portion of the Item B4.20 examination per Note (6) of Table 1 of ASME Code Case N-729-6 for a single head penetration 3
Inspection History Catawba Unit 2 RVCH Reactor Vessel Closure Head (RVCH) is original and fabricated by CE with Alloy 600 nozzle material supplied by Huntington attached to the inside of the head with Alloy 82/182 J-groove welds Previous volumetric examinations and leak path assessments of all penetrations performed using UT in 2007 and 2013 with no detected PWSCC indications Volumetric examinations and leak path assessments completed on all other penetrations during the current outage with no PWSCC detected. Leak path assessment of nozzle #74 is unresolved.
Bare metal visual examinations performed of the head in 2018 (C2R22), 2019 (C2R23), and 2021 (C2R24) with no detections of head penetration leakage To date there have been no reports of PWSCC affecting U.S.
heads fabricated by CE or fabricated with Alloy 600 nozzle material supplied by Huntington and operating at reactor cold leg temperature (Tcold) 4
Current Inspection Requirements The Catawba Unit 2 head operates at reactor cold leg temperature (Tcold = 557°F), and PWSCC has not been detected Hence, per 10 CFR 50.55a(g)(6)(ii)(D) and ASME Code Case N-729-6, Item B4.20 volumetric or surface examinations of all penetrations are required prior to RIY = 2.25 or 8 years, whichever is sooner Per Note (6) of Table 1 of ASME Code Case N-729-6, the volumetric or surface examination of each penetration must include a volumetric and/or surface leak path assessment examination 5
Nozzle #74 Description The nozzle at penetration
- 74 is one of five core exit thermocouple (CET) locations on the outer periphery of the RVCH The CET nozzles have a threaded guide funnel attached with two anti-rotation dowel pins installed which are plug welded in place 6
RVCH Examinations this RFO Nozzle #74 UT examination of the Alloy 600 nozzle tube was successfully completed with no indications of PWSCC detected A change in back-wall reflectivity between the penetration OD and RVCH in penetration number 74 was discovered during the volumetric leak path assessment (UTLP).
There is an area of reduction in amplitude of the backwall region contained within the interference fit region located above the high-hill side of the J-groove weld profile.
EPRI review indicated the UTLP pattern does not exhibit variations similar to that of industry OE.
A bare metal visual in accordance with Item No. B4.10 of ASME Code Case N-729-6 was performed with no relevant visual indications.
Supplemental OD j-groove weld ECT was performed on approximately 89% (320° of 360° circumferentially) of the wetted surface of the weld, and no planar flaws or surface breaking indications were detected within the examined region.
Until the remaining 11% (40° of 360° circumferentially) of the j-groove weld can be examined by surface methods, the examination is incomplete and the leak path assessment is unresolved.
7
Leak Path Assessment Obstruction Nozzle #74 Interference from the funnel welded to the end of the penetration nozzle (which functions as a thermocouple column) prevented completion of the ECT surface examination over 11% of the weld area NDE of the j-groove weld surface requires funnel removal to obtain full coverage 8
Nozzle #74 Funnel Removal Attempts Catawba contracted an outside vendor with relevant experience to work with Duke Energy maintenance personnel on removal of the plug-welded funnel A manual grinding evolution was performed to remove the plug welds on the dowel pins Attempts to remove the dowel pin and free the funnel were made using available tooling and additional tooling purchased emergently Dowel pins were not able to be extracted from funnel through multiple attempts, thus funnel removal was prevented Approximately 4.8 REM dose has been accrued to date on the funnel removal activities 9
Proposed Alternative One-time alternative will be requested in accordance with 10 CFR 50.55a(z)(2) - Hardship without a commensurate increase in quality and safety At the next refueling outage in Fall 2022 (C2R25):
The obstruction will be removed and the remaining portion of the weld surface will be examined Bare metal visual will be performed The routine online leakage detection capability provides additional assurance and defense in depth until the time of the next refueling outage and beyond 10
Technical Basis for Relief Request The two main safety concerns addressed by the B4.20 volumetric or surface examination are:
- 1) Nozzle ejection The nozzle ejection is a concern if circumferential cracking occurs above the weld within the nozzle tube material UT inspection revealed no cracking in the tube material, thus nozzle ejection is not a concern
- 2) Boric acid corrosion of the low-alloy steel head Concern is wastage of low-alloy steel material due to nozzle leakage Visual examinations are highly effective in detecting any leakage caused by PWSCC before any discernible material loss is produced via boric acid corrosion of carbon or low-alloy steel pressure boundary components Bare metal visual performed during current outage validated no visual indication of nozzle leakage, so discernible material loss due to boric acid corrosion over the next operating cycle is not a concern 11
Technical Basis for Relief Request During the current outage, 89% of the wetted surface of the weld was examined and no planar flaws or surface breaking indications were detected The susceptibility of the examined area of the weld is representative of the unexamined portion To date there have been no reports of PWSCC on RVCHs of equivalent fabrication material and operating temperature 12
Timeline for Submittal C2R24 outage is ongoing, with plans being made for funnel removal and completion of leak path assessment for nozzle
- 74 In the event emergent funnel removal is not feasible, or it is determined it cannot be performed without undue risk to plant personnel or critical plant equipment, Duke Energy may request verbal approval for relief per 10 CFR 50.55a(z)(2) 13