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Category:Meeting Briefing Package/Handouts
MONTHYEARML24137A1882024-05-16016 May 2024 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML24100A7672024-04-11011 April 2024 Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2 ML24089A2612024-04-0909 April 2024 Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041) ML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML23053A1562023-02-23023 February 2023 NRC Presentation Slides for Public Meeting on February 23, 2023 - 10 CFR 50.69 Alternate Processes License Amendment Request Preliminary Partial Denial ML23076A2812023-02-23023 February 2023 Licensee Presentation on Pressure Boundary Process ML23076A2822023-02-23023 February 2023 Licensee Presentation on Defense-in-Depth Process ML23006A2572023-01-10010 January 2023 Digital Modernization Project Installation Support License Amendment Request and Exemption Request Presentation - January 10, 2023 (EPID L-2022-LRM-0099) (Slides) ML22347A1532022-12-13013 December 2022 Public Meeting Presentation, December 15, 2022 Di&C License Amendment Request ML22319A0012022-11-14014 November 2022 Constellation Energy Generation, Llc'S Presentation for November 10, 2022 Public Meeting with NRC ML22312A4402022-11-10010 November 2022 Public Meeting with Constellation About Acceptance Review: Status of NRC Staff'S Acceptance Review of the Limerick Digital Instrumentation and Controls License Amendment Request ML22249A0972022-09-0808 September 2022 Constellation'S Open Presentation for September 8, 2022 Partially Closed Public Meeting ML22250A4372022-09-0808 September 2022 NRC Staff'S Presentation for September 8, 2022 Partially Closed Public Meeting with Constellation - Review Planning and Tentative Review Timeline ML22249A2202022-09-0606 September 2022 Constellation'S Non-Proprietary Presentation for Limerick Generating Station Digital Modernization Project LAR Pre-submittal Meeting September 8, 2022 ML22164A8082022-06-13013 June 2022 Westinghouse, Presentation GLIMM-RPS-PM-L1-000008, Revision 0 ML22153A3602022-06-0909 June 2022 Constellation'S Presentation for June 9, 2022 Public Meeting About Limerick Generating Station Digital Modernization Project ML22187A0652022-06-0808 June 2022 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - NRC Presentation Slides ML22103A2542022-04-19019 April 2022 Draft Request for Additional Information ML22076A1942022-03-23023 March 2022 Constellation Presentation March 23, 2022 NRC Di_C Workshop ML22080A1522022-03-21021 March 2022 Non-Proprietary Presentation for March 31, 2022 Pre-Submittal Meeting with Constellation Energy Generation, LLC Regarding Planned Digital Modernization License Amendment Request for Limerick Generating Station, Units 1 and 2 ML22010A0692022-01-10010 January 2022 Jan 11 2022 LGS Digital Modernization Pre-submittal Meeting Slides ML21335A0772021-12-0707 December 2021 Dec 07 2021 LGS Digital Modernization Pre-submittal Meeting Slides ML21294A3692021-11-15015 November 2021 Summary of October 6, 2021, Public Observation Meeting with Exelon Generation Company, LLC Proposed License Amendment Request to Modify Emergency Diesel Generator and Emregency Core Cooling System Surveillance Requirements ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21278A5452021-10-20020 October 2021 Digital Modernization Project LAR Pre-submittal Meeting Presentation Slides October 20, 2021 ML21174A0852021-06-23023 June 2021 Digital Modernization Project LAR Pre-submittal Meeting ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML21063A1192021-03-0404 March 2021 Digital Modernization Project LAR Pre-submittal Meeting - March 16, 2021 (EPID L-2020-LRM-0041) (Slides) ML21049A3102021-02-19019 February 2021 CFR 50.69 Alternative Categorization LAR ML21034A6032021-02-0303 February 2021 External Presentation Am Connelly_ISG-6 Workshop Presentation ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20168A3192020-06-15015 June 2020 Joint Annual Assessment Meeting for Pa/Md Power Plants - Webinar Presentation ML20162A0192020-06-10010 June 2020 NRC Staff Presentation for June 12, 2020, Public Pre-Application Meeting: ISG-06 Alternate Review Process Lessons Learned from Pre-Application Meetings ML20160A0532020-06-0808 June 2020 Digital Modernization Project LAR - Presubmittal Meeting - NRC Presubmittal Meeting Telecon June 12, 2020 ML19318F9512019-11-20020 November 2019 Presentation Slides for November 20, 2019, Pre-Application Meeting - Request for Revision to Quality Assurance Program Internal Audit Frequency ML19317C9952019-11-12012 November 2019 In-Service Testing Supplemental Position Indication Relief Request NRC Pre-Application Meeting November 18, 2019 ML19157A0542019-06-0606 June 2019 Joint Annual Assessment Meeting (Webinar) for Pennsylvania Power Plants - NRC Presentation Slides ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19151A6602019-05-31031 May 2019 BWR Fleet Mssv/Srv Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19022A2002019-01-23023 January 2019 Request for Use of ASME Code Case N-879 for Exelon Nuclear Power Plants ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 2024-05-16
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24249A3092024-09-0606 September 2024 September 6, 2024, Public Meeting Related to Digital Instrumentation and Control Amendment Slides ML24137A1882024-05-16016 May 2024 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML24100A7672024-04-11011 April 2024 Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2 ML24089A2612024-04-0909 April 2024 Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041) ML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML23053A1562023-02-23023 February 2023 NRC Presentation Slides for Public Meeting on February 23, 2023 - 10 CFR 50.69 Alternate Processes License Amendment Request Preliminary Partial Denial ML23076A2812023-02-23023 February 2023 Licensee Presentation on Pressure Boundary Process ML23076A2822023-02-23023 February 2023 Licensee Presentation on Defense-in-Depth Process NEI 99-01, Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides2023-02-21021 February 2023 Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides ML23006A2572023-01-10010 January 2023 Digital Modernization Project Installation Support License Amendment Request and Exemption Request Presentation - January 10, 2023 (EPID L-2022-LRM-0099) (Slides) ML22347A1532022-12-13013 December 2022 Public Meeting Presentation, December 15, 2022 Di&C License Amendment Request ML22319A0012022-11-14014 November 2022 Constellation Energy Generation, Llc'S Presentation for November 10, 2022 Public Meeting with NRC ML22250A4372022-09-0808 September 2022 NRC Staff'S Presentation for September 8, 2022 Partially Closed Public Meeting with Constellation - Review Planning and Tentative Review Timeline ML22249A0972022-09-0808 September 2022 Constellation'S Open Presentation for September 8, 2022 Partially Closed Public Meeting ML22249A2202022-09-0606 September 2022 Constellation'S Non-Proprietary Presentation for Limerick Generating Station Digital Modernization Project LAR Pre-submittal Meeting September 8, 2022 ML22195A2172022-07-12012 July 2022 D3 Audit Open Items List (Non-Proprietary) (07-12-22)_redacted ML22164A8082022-06-13013 June 2022 Westinghouse, Presentation GLIMM-RPS-PM-L1-000008, Revision 0 ML22153A3602022-06-0909 June 2022 Constellation'S Presentation for June 9, 2022 Public Meeting About Limerick Generating Station Digital Modernization Project ML22187A0652022-06-0808 June 2022 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - NRC Presentation Slides ML22076A1942022-03-23023 March 2022 Constellation Presentation March 23, 2022 NRC Di_C Workshop ML22080A1522022-03-21021 March 2022 Non-Proprietary Presentation for March 31, 2022 Pre-Submittal Meeting with Constellation Energy Generation, LLC Regarding Planned Digital Modernization License Amendment Request for Limerick Generating Station, Units 1 and 2 ML22010A0692022-01-10010 January 2022 Jan 11 2022 LGS Digital Modernization Pre-submittal Meeting Slides ML21335A0772021-12-0707 December 2021 Dec 07 2021 LGS Digital Modernization Pre-submittal Meeting Slides ML21294A3692021-11-15015 November 2021 Summary of October 6, 2021, Public Observation Meeting with Exelon Generation Company, LLC Proposed License Amendment Request to Modify Emergency Diesel Generator and Emregency Core Cooling System Surveillance Requirements ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21278A5452021-10-20020 October 2021 Digital Modernization Project LAR Pre-submittal Meeting Presentation Slides October 20, 2021 ML21294A3792021-10-0606 October 2021 WCAP-17308 Implementation Licensing Amendment Request Pre-Submittal Meeting Presentation, October 6, 2021 ML21175A1732021-06-29029 June 2021 Digital Modernization Project LAR Pre-submittal Meeting ML21174A0852021-06-23023 June 2021 Digital Modernization Project LAR Pre-submittal Meeting ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21162A3322021-06-11011 June 2021 BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs ML21063A1192021-03-0404 March 2021 Digital Modernization Project LAR Pre-submittal Meeting - March 16, 2021 (EPID L-2020-LRM-0041) (Slides) ML21049A3102021-02-19019 February 2021 CFR 50.69 Alternative Categorization LAR ML21034A6032021-02-0303 February 2021 External Presentation Am Connelly_ISG-6 Workshop Presentation ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20163A6542020-06-18018 June 2020 2020 NRC Annual Assessment Webinar Presentation - Pennsylvania and Maryland Facilities (Beaver Valley, Calvert Cliffs, Limerick, Peach Bottom, Susquehanna) ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20168A3192020-06-15015 June 2020 Joint Annual Assessment Meeting for Pa/Md Power Plants - Webinar Presentation ML20162A0192020-06-10010 June 2020 NRC Staff Presentation for June 12, 2020, Public Pre-Application Meeting: ISG-06 Alternate Review Process Lessons Learned from Pre-Application Meetings ML20160A0532020-06-0808 June 2020 Digital Modernization Project LAR - Presubmittal Meeting - NRC Presubmittal Meeting Telecon June 12, 2020 ML19304A8752019-11-0505 November 2019 Presentation Slides for Limerick/Nrc Pre-Submittal Meeting (Technical Specification 4.05 License Amendment Request) - November 5, 2019 ML19157A0542019-06-0606 June 2019 Joint Annual Assessment Meeting (Webinar) for Pennsylvania Power Plants - NRC Presentation Slides 2024-09-06
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BWR Operating Experience Chuck Wirtz EPRI, BWRVIP Integration Task Manager EPRI/NRC Technical Exchange Meetings May 22-24, 2018
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Outline Significant BWR Operating Experience (OE) since last years Technical Exchange meetings
- Limerick Unit 2 Instrumentation Nozzle Leak
- Hatch Unit 1 Top Guide Grid Beam to Top Guide Rim Attachment Cracking
- Brunswick Unit 1 Feedwater Nozzle Assembly Dissimilar Metal Weld Planar Indications Utility and BWRVIP Actions 2
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Limerick Unit 2 Instrumentation Nozzle Leak 3
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Limerick Unit 2 BWR 4, 251 Diameter Vessel RPV Manufacturer: CB&I Instrument Nozzles: 10 Total
LGS 2 N16D Nozzle - 2 Nominal Dia.
- Inconel (SB-166) material bored from a solid piece of bar stock
- Alloy 182, J-groove weld on the ID of the RPV
- Corrosion Resistant Cladding installed over weld surface 4
© 2018 Electric Power Research Institute, Inc. All rights reserved.
N16D Instrument Nozzle Leak
- Leakage Identified during RPV System Leakage test at end of refuel outage
- ~1 pint/min
- Leak originating from ~1 oclock position within the RPV shell bore
- Similar to QDC Fall 2012 leak - repaired with AREVA half nozzle method
- N16 is below water line and requires plug from vessel ID for repair Leak Area @
1 O'clock 5
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Nozzle Location & Configuration Nozzle Location 6
© 2018 Electric Power Research Institute, Inc. All rights reserved.
UT Performed From RPV OD
- The N16D nozzle forging was examined 360° around the nozzle from an area adjacent to RPV shell exterior reinforcement pad. The purpose was to detect potential cracking within the forging wall thickness.
- There was no evidence of through-wall cracks detected. (Demonstrated Technique PDI-02 was used)
- An additional informational examination utilizing multiple Vee-paths beyond the qualification of the procedure was utilized to try to get a reflection from the end of the nozzle forging. A calibration block of similar thickness and material was used for reference and was able to detect the outside corner trap at a 9 distance.
- Exam in the field was not able to detect the end of the forging using this unqualified technique.
- A straight beam UT exam was performed from the weld reinforcement pad adjacent to nozzle forging to identify any evidence of significant wall thickness loss due to wastage and measurement of the nozzle exterior weld reinforcement pad at four locations.
- There was no evidence of wall loss or localized wastage noted.
- Demonstrated phased -array UT performed from the vessel reinforcing weld pad.
- Results in following slide 7
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Demonstrated UT results
- No flaws identified in low-alloy RPV material
- Circ Flaws not detected in weld butter
- Ultrasonic responses observed along penetration tube-to-J-groove weld interface
- Located from TDC to
~45-degree CW when looking towards RPV
- Somewhat similar pattern seen near bottom, but not as severe
- Suspect indications may be a cluster of stacked volumetric fabrication flaws located along fusion line or an SCC flaw 8
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Likely Cause
- Source of wetted environment at suspect area noted in IVVI (see following slide)
- Crevice conditions are not mitigated by HWC/NMC 9
9
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Wetted Environment Path Suspected area of initiation Area where the IN-82 overlay is missing from the nozzle inner radius 10 10
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Performed Half Nozzle Repair 11
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Analysis Flaw Analysis postulating a bounding flaw performed to demonstrate the acceptability of not removing the potential flaw in the j-groove weld Corrosion Evaluation for RPV base metal within the nozzle bore that will be exposed to the BWR environment Fatigue Crack Growth Evaluation for postulated flaw Lost Parts analysis for the potential of remaining nozzle becoming a loose part Relief Request approved for:
- Performing repair without removing the existing flaw
- Not fully characterizing and sizing the flaw 12
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Hatch Unit 1 Top Guide Grid Beam to Top Guide Rim Attachment Cracking 13
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Hatch Unit 1 Top Guide
- BWR/4 Mark I design
- Top Guide Constructed of 304 SS.
- No top guide wedges are installed on Hatch-1.
(U2 uses wedges)
- Current fluence at H3 (lower top guide rim location) approx. 6x1020 n/cm2 max.
SNC Proprietary Information 14
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Hatch Top Guide Support Configuration HNP1 has 8 top guide cross-connecting beam attachments to the top guide rim (4 on each quadrant), cross connecting beams. Single beam attachments exist as well.
The hardware attaching these beams consists of pins inserted in the upper and lower top guide plates, which are connected to the beam via upper and lower collars welded to the beam.
The pins are similar to location 4 from BWRVIP-26-A, and the welds to the beam are similar to location 5, however, Hatchs rim connector at these location is not a solid collar extending from top to bottom like shown in BWRVIP-26-A, but two separate collars.
15
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Hatch 1R28 Inspection While positioning the camera for inspection of the Shroud ID, indications of cracking on one of the lower collars of a top guide grid to top guide rim cross-beam connection were noted from within one of the top guide cells.
BWRVIP-26-A considers weld connection failure and states that the pins remain captured assuming fillet welds fail. However, failure at collar location not addressed by BWRVIP-26-A.
Contacted OEM to start evaluation process.
16
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Hatch 1R28 Inspection Additional exams were performed (best effort VT-1) at all accessible beam connection locations, including both cross-beam connection points and single beam connection points. The results of all the exams found:
- 5 of the 8 azimuths with cross-beam connections were found to have cracking in the lower collars
- 7 of 8 azimuths with cross-beam connections and 1 of 16 azimuths with single connections had cracking in the bottom support plate of the top guide rim assembly
- No cracking was found on any of the upper collars or anywhere in the top support plate of the top guide rim assembly 17
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Analysis Apparent cause is IGSCC driven by high installation stresses (e.g., jacking of beams and rim assembly to facilitate fit-up at beam connections).
Conservative analysis assuming complete failure of flawed collars performed by OEM and flaws found to be acceptable for one cycle.
Under current analysis, Hatch must re-inspect the accessible locations every outage.
Consideration will be given to performance of a more detailed analysis to show additional margin and reduce the re-inspection requirements.
18
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Brunswick Unit 1 Feedwater Nozzle Assembly Dissimilar Metal Weld Planar Indications 19
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Discovery Planar indications were found during weld examinations for:
- BWRVIP-75-A Category D weld examinations
- ASME Risk-Informed ISI Program for Exam Category R-A, Item Numbers R1.14-2 and R1.20-4 The NDE method was automated/encoded phased array UT (PAUT)
ID-connected circumferential planar indications were found at 3 feedwater nozzle dissimilar metal weld locations
- Nozzle N4A, Weld 1B21N4A-2-SW1-2, Exam required by BWRVIP-75-A only
- Nozzle N4D, Weld 1B21N4D-5-SW1-2, Exam required by BWRVIP-75-A & RI-ISI Item No. R1.14-2 (Crevice corrosion mechanism)
- Nozzle N4D, Weld 1B21N4D-5-SW2-3, Exam required by BWRVIP-75-A & RI-ISI Item No. R1.20-4 (No degradation mechanism)
The planar indications were found in the weld exam volume, but at distances that could be beyond the primary HAZ 20
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Feedwater Nozzle Safe-End Assembly Configuration and Indication Locations 21
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Location Details 22
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Exam Details Welds all BWRVIP-75-A Category D welds that are considered susceptible to IGSCC with no stress improvement and require a 6-year exam frequency No indications were found during the last weld exams in 2012 The NDE method used in 2012 was manual phased array UT The automated phased array UT performed in 2018 used larger transducers and all the welds required some additional weld prep/contouring in order to ensure good contact All Cat D, Inconel DM welds inspected during the outage, including all Feedwater nozzles (8 DM welds), so no scope expansion in accordance with BWRVIP-75-A needed.
7 additional welds examined to meet Section XI Risk-Informed scope expansion requirements No indications found in the scope expansion welds 23
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Indication Details The indications have similarities:
- All at the edge of the base metal / HAZ exam boundary
- All on the Inconel 600 side of the DM weld
- Both N4A and N4D have 3 indications with roughly equal axial spacing
- All flaw locations were in NSSS manufacturer provided subassemblies (shop weldments)
- All present as ID connected surface planar flaws EPRI performed and independent review of the UT data
- EPRI noted that the indications exhibit some UT characteristics that are not typical of classic IGSCC and possibly suggest some type of fabrication/repair activities in the areas of the indications
- Lacking any definitive evidence of repairs, EPRIs review of the data concurred with Brunswick calling the indications inservice ID connected surface planar flaws 24
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Analysis and Repairs Apparent Cause is IGSCC The Alloy 600 safe-end to carbon steel welds in both the N4A and N4D nozzle assemblies were repaired by weld overlay in accordance with an approved relief request The single surface planar indication in the Alloy 600 safe-end transition piece to carbon steel weld of the N4D nozzle assembly was evaluated in accordance with ASME Section XI, IWB-3600, and found acceptable for operation beyond the successive examination requirements of ASME Section XI.
25
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Utility and BWRVIP Actions 26
© 2018 Electric Power Research Institute, Inc. All rights reserved.
Utility and BWRVIP Actions In all three cases, the affected utilities contacted the BWRVIP within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of discovery and briefed the BWRVIP on the emergent OE.
The BWRVIP Research Integration Chairman contacted NRR to let them know that the BWRVIP had been informed of the OE and would be looking into whether there are any generic implications requiring follow-up actions by the BWRVIP.
Once the plants worked through the discovery phase, calls were held between the utility and the BWRVIP to discuss and screen the OE in accordance with the NEI 03-08 emergent issues protocol.
27
© 2018 Electric Power Research Institute, Inc. All rights reserved.
BWRVIP Follow-up Actions For the Limerick leaking instrument nozzle OE, the BWRVIP has initiated a project to:
- As a short term action, develop a strategy document (i.e., playbook) to aid utilities in dealing with any future similar OE
- As long term actions, consider revisions to BWRVIP-49-A, the BWRVIP Inspection and Evaluation Guidelines for instrument penetrations, and BWRVIP-57-A, the BWRVIP Repair Design Criteria for instrument penetrations For the Hatch top guide grid beam attachment OE, the BWRVIP has initiated a project to:
- Survey the BWRVIP members to establish inspection experience and availability of design input
- Conduct a fabrication study for the top guide assemblies to better understand conditions that could lead to the subject degradation and the configurations that may be affected
- Based on the results of the first two items, conduct modeling and evaluation to determine whether additional inspections are necessary Follow-up actions, if any are necessary, for the Brunswick dissimilar metal weld OE are still under consideration 28
© 2018 Electric Power Research Institute, Inc. All rights reserved.
TogetherShaping the Future of Electricity 29
© 2018 Electric Power Research Institute, Inc. All rights reserved.