Public Meetings About Reactor Coolant System Weld Issues

Category 2 Meeting – Meeting with the Nuclear Energy Institute (NEI) on technical basis for preemptive weld overlays for alloy 82/182 butt welds in pressurized water reactors (MRP-169)

Contact:  Tanya M. Mensah, 301-415-3610

• Meeting Summary
• Slide Presentation – NRC – Technical Report MRP-169 Weld Overlay on Alloy 82/182 DMBW
• Slide Presentation – EPRI – MRP-169 OWOL Inspection

Public Meeting with Nuclear Energy Institute and Industry regarding inlay and only applications on DMBW

Contact: John Tsao, 301-415-2702

• Meeting Summary
• Slide Presentation – NEI – Weld Onlay, Inlay and Underwater Laser Welding
• Slide Presentation – Weld Onlay, Mitigation and Repair
• Slide Presentation – Inlay Mitigation
• Slide Presentation – Westinghouse – RV Nozzle Clad Deposited by Underwater Laser Beam Welding (ULBW)
• Technical Paper – Use of Weld Inlays as a PWSCC Mitigation for Reactor Vessel Safe-End-to-Primary Nozzle Welds
• Technical Paper – Application of Weld Onlay for Butt Weld Mitigation
• Technical Paper – Westinghouse – Underwater Laser Beam Welding

Category 2 Meeting – Meeting with the Nuclear Energy Institute (NEI) on Materials Reliability Program (MRP) Initiative related to PWSCC

Contact: John Tsao, 301-415-2702

• Meeting Summary
• Slide Presentation – EPRI – Materials Reliability Program (MRP) Initiatives Related to PWSCC: MRP-139
• Slide Presentation – EPRI – NRC/Inspection ITG Meeting
• Slide Presentation – EPRI – MRP-169 Discussion

Category 2 Meeting - Meeting Between the Nuclear Regulatory Commission (NRC) Staff, Industry Representatives, and Electric Power Research Institute/Materials Reliability Project Representatives on Alloy 690/52/152 Research and Areas of Possible Collaboration.

Contact: Robert Tregoning, 301-415-6657; Carol Moyer, 301-415-6764

• Meeting Notice
• Meeting Agenda
• Slide Presentation –GE – Experimental Guidelines for Generating High Quality Data on SCC on Alloy 690 in Hot Water
• Slide Presentation – GE – Crack Initiation Studies in Alloy 690 and Weld Metals
• Slide Presentation – GE – Alloy 690 Base Metal Product Forms
• Slide Presentation – Dominion – PWR Alloy 690 Replacement Pressure Boundary Components - Material Production and Component Fabrication/Installation Practices
• Slide Presentation – NRC – Action Items From May 2008 Alloy 690/52/152 PWSCC Research Meeting
• Slide Presentation – ANL – Stress Corrosion Cracking (SCC) CGRs of Alloy 690 and 52/152 Welds in PWR Water
• Slide Presentation – ThyssenKrupp VDM – Alloys 690/52/152 PWSCC Test Materials
• Slide Presentation – GE – Alloy 690 Base Metal Issues and Strategy
• Meeting Summary – Summary of Meeting Between the NRC Staff, Industry Representatives, and EPRI Materials Reliability Project Representatives on Alloy 690/52/152 Research and Areas on Possible Collaboration

Category 2 Meeting - Meeting Between The Nuclear Regulatory Commission (NRC) Staff, Industry Representatives, And Electric Power Research Institute/Materials Reliability Project Representatives On Alloy 690/52/152 Research And Areas Of Possible Collaboration.

Contact: Samantha Crane, 301-415-6380

• Meeting Notice
• Meeting Agenda
• Slide Presentation – EPRI – Resistance of Alloys 690,152 and 52 to PWSCC "White Paper" on Research Findings since Publication in 2004 of MRP-111.
• Slide Presentation – NRC – Research Objectives.
• Slide Presentation - PNNL - Comments on Stress Corrosion Cracking Crack-Growth-Rate Testing Issues .
• Slide Presentation - Andresen – Final Results from Alloy 182 Round Robin.
• Slide Presentation - Andresen - Limitations and Value of Crack Initiation Studies.
• Slide Presentation - Andresen - PWSCC Growth Rates of Alloy 690 and its Weld Metals.
• Slide Presentation - ANL - SCC CGR Data for Round-Robin Alloy 182 Weld Alloy in PWR Environment.
• Slide Presentation - ANL SCC CGRs of Alloy 690 and 152 Weld in PWR Water.
• Slide Presentation - DEI - Application of PWSCC Crack Initiation Laboratory Test Data Screening Process for Laboratory PWSCC Crack Growth Data
• Slide Presentation - NRC - A690/52/152 Knowledge Gap Rankings and Research Initiatives.
• Slide Presentation - PNNL - Grain Boundary Damage in Alloy 690 After One Dimensional Cold Rolling Preliminary Observations .
• Slide Presentation – RRAC, and Advanced Nuclear Technology – Alloy 52 Weldability Test Program, and New Plant Welding Best Practices
• Slide Presentation - Andresen - "Cold Work" From Weld Shrinkage.
• Slide Presentation - ANL - Cracking of Nickel Alloys and Welds Scope of Future Work
• Slide Presentation – ANL - Cracking of Nickel Alloys and Welds CGRs of Alloys 600 and 690 in PWR Water
• Meeting Summary

Category 2 Meeting - Meeting between the Nuclear Regulatory Commission Staff, Argonne National Laboratory Staff and Industry Representatives on Program Plans for Environmentally Assisted Cracking of Light Water Reactor Structural Materials.

Contact: Samantha Crane, 301-415-6380

• Meeting Notice
• Meeting Agenda
• Slide Presentation – EAC Program Overview
• Slide Presentation – Task 1: Overview -- Prior Efforts
• Slide Presentation – Task 1: IASCC Susceptibility of Austenitic SSs & Alloy 690
• Slide Presentation – Task 1: Crack Growth & Fracture Toughness of Irradiated SSs
• Slide Presentation – EPRI Research on Crack Growth and Fracture Toughness of Irradiated Stainless Steels
• Slide Presentation – Task 1: Scope of Future Work
• Slide Presentation – Task 2: Overview - Prior Efforts
• Slide Presentation – Preliminary Results of IASCC Study on BOR-60 Materials
• Slide Presentation - Task 2: Microstructural Examination of Austenitic SSs & Alloy 690 irradiated to 25 dpa
• Slide Presentation – EPRI MRP Research on Irradiation Effects on PWR Internals Materials
• Slide Presentation – Task 2: Scope of Future Work
• Slide Presentation – Task 3: Overview - Prior Efforts
• Slide Presentation – Task 3: Metallographic Studies
• Slide Presentation – Task 3: CGRs of Ni-alloy Welds in Primary Water
• Slide Presentation – Task 3: CGRs of Alloys 600 and 690 in PWR Water
• Slide Presentation – EPRI/MRP R&D Programs for PWR RCS Materials
• Slide Presentation – Task 3 - Scope of Future Work
• Meeting Summary

Category 2 Meeting - Meeting between the Nuclear Regulatory Commission Staff, EPRI/MRP, utility representatives and vendors updating research results on the mitigation of primary water stress corrosion cracking of nickel-base alloys.

Contact: Samantha Crane, 301-415-6380

• Meeting Notice
• Meeting Agenda
• Slide Presentation – Overview of Industry Activities on Mitigation of PWSCC in NI-Based RCS Components
• Slide Presentation – Optimization of Dissolved Hydrogen in Primary Water to Mitigate PWSCC in NI-Based RCS Components
• Slide Presentation – Effect of Primary Water Zinc Injection on PWSCC in Nickel-Based RCS Components
• Slide Presentation – PWROG Farley Zinc Program
• Slide Presentation – Surface Remediation for Mitigation of PWSCC in Nickel-Based Materials
• Slide Presentation – Weld Inlay Qualification Program
• Slide Presentation – Surface Stress Improvement Technologies Qualification
• Meeting Summary

Category 2 Meeting - Meeting with Nuclear Energy Institute (NEI) regarding implications of Wolf Creek dissimilar metal weld inspections.

• Meeting Notice
• Meeting Slides (NRC)
• Meeting Slides (Industry)

Category 2 Meeting - Meeting with Nuclear Energy Institute (NEI) regarding implications of dissimilar metal weld inspection results at Wolf Creek.

• Meeting Notice
• Meeting Agenda
• Meeting Summary
• Meeting Slides (NRC)
• Meeting Slides (Industry)

Category 2 Meeting - Meeting between the Nuclear Regulatory Commission Staff, Nuclear Energy Institute and other industry representatives on inspection program for primary system piping butt welds (MRP-139).

• Meeting Notice
• Meeting Slides
• Meeting Summary

Category 2 Meeting - Review of NRC and EPRI/MRP coordination of nickel-base alloy programs in the areas of stress analysis and non-destructive examination of reactor components.

Contact: William Cullen, 301-415-7510

• Meeting Notice
• Meeting Slides (NRC Overview of Ni-base Alloys Research on Stress Analysis and NDE Agenda)
• Meeting Slides (MRP Overview of Ni-base Alloys Research (details of the Gap Analysis))
• Meeting Slides (NRC Presentation on Ni-base Stress Analysis Research)
• Meeting Slides (MRP (DEI) Presentation on Ni-base Stress Analysis Research)
• Meeting Slides (NRC (PNNL) Presentation on Ni-base Alloy NDE Research)
• Meeting Slides (MRP Presentation on Ni-base Alloy NDE Research)
• Meeting Summary

Category 2 Meeting - Meeting between the Nuclear Regulatory Commission Staff, Nuclear Energy Institute and other industry to discuss responses to NRC comments on MRP-139 guidance document.

• Meeting Slides
• Meeting Summary

Category 2 Meeting - Meeting between the Nuclear Regulatory Commission Staff, EPRI/MRP, and Southern Nuclear Operating Company and Westinghouse on Mitigation of Primary Water Stress Corrosion Cracking.

• Meeting Notice
• Meeting Slides (EPRI/MRP)
• Meeting Slides (SNOC/Westinghouse)
• Meeting Summary

Category 2 Meeting - Meeting between the Nuclear Regulatory Commission Staff, Nuclear Energy Institute, and other industry to discuss butt weld inspection and evaluation guidelines.

• Meeting Slides
• Meeting Summary

Category 2 Meeting - Meeting between the Nuclear Regulatory Commission Staff and the Nuclear Energy Institute on the alloy 600 management and Materials Reliability Program MRP-139.

• Meeting Slides
• Meeting Summary

Pre-emptive weld overlays (PWOLS) for alloy 82/182 Butt welds in PWR's topical report Kickoff meeting.

• Meeting Slides
• Meeting Summary

Category 2 Meeting - Meeting between the Nuclear Regulatory Commission Staff and the Nuclear Energy Institue on the status of the Alloy 600 butt weld safety assessment.

Contact: Joe Birmingham, 301-415-2829

• Meeting Notice

Category 2 Meeting – Meeting between Nuclear Regulatory Commission (NRC) staff, and representatives of the Nuclear Energy Institute, the Electrical Power Research Institute (EPRI) Materials Reliability Program (MRP) and industry on butt weld safety assessment.

• Meeting Slides
• Meeting Summary

Category 2 Meeting - NRC and Nuclear Energy Institute (NEI) - Discuss materials issues related to South Texas Project vessel residue, butt weld safety assessment, RPV safety assessment, BAC program, and North Anna head study.

Contact: Joe Birmingham, 301-415-2829

• MRP Alloy 600 Butt Weld Assessment

Public meeting with V.C. Summer to discuss hot leg weld crack root cause analysis, corrective actions, and readiness for restart.

• Meeting Slides (SCE&G)
• Meeting Slides (NRC)

(Meeting Rescheduled 1/18/01)

• Meeting Notice

Public meeting with V. C. Summer to discuss the laboratory analysis results for the flawed weld.

• Meeting Notice
• Meeting Summary

Meeting with South Carolina Electric & Gas on the V. C. Summer Nuclear Station reactor coolant system hot leg weld crack

• Meeting Notice
• Meeting Summary
• Meeting Slides

Public meeting between the NRC and South Carolina Electric & Gas Company to discuss planned activities concerning evaluating and repairing the crack in RCS hot leg weld.

• Meeting Notice
• Meeting Summary
• Meeting Slides