MONTHYEARML22097A2042022-04-0707 April 2022
MRP 227 Rev 2 Completeness and Withholding Determinations
Project stage: Other
ML22097A2052022-04-0707 April 2022
NRC Form 897, Topical Report Withholding Determination
Project stage: Other
PMNS20220445, Meeting for Electric Power Research Institute (EPRI) to Present Anticipated ASME Code Case N-729 Visual Exam Updates to the U.S. Nuclear Regulatory Commission (NRC)2022-04-27027 April 2022
Meeting for Electric Power Research Institute (EPRI) to Present Anticipated ASME Code Case N-729 Visual Exam Updates to the U.S. Nuclear Regulatory Commission (NRC)
Project stage: Meeting
ML22129A0082022-05-0909 May 2022
Proposed Revision to N-729-9 to Revise Ve Acceptance Criteria - Slides (NRC Mtg 2022-05-11)
Project stage: Other
ML22129A0072022-05-0909 May 2022
Proposed N-729-10 with Revised Visual Examination (Ve) Acceptance Criteria (NRC Mtg 2022-05-11) (Redline Vs N-729-9)
Project stage: Other
ML22146A0662022-06-0606 June 2022
Summary of Meeting for Electronic Power Research Institute to Present Anticipated ASME Code Case N 729 Visual Exam Updates to the U.S. Nuclear Regulatory Commission
Project stage: Meeting
ML23010A2762023-03-16016 March 2023
February 1, 2023, Meeting Summary: Public Meeting Between NRC and EPRI to Discuss Proposed Changes to Bare Metal Visual Requirements of ASME Code Case N-729
Project stage: Meeting
ML23264A0132023-10-11011 October 2023
Request for Boiling Water Reactor Vessel Internals Program Technical Report BWRVIP-03, Reactor Pressure Vessel and Internals Examination Guidelines, Revision 20
Project stage: Other
ML23341A1772024-02-22022 February 2024
NRC 897 for BWRVIP-03, Reactor Pressure Vessel and Internals Examination Guidelines, Revision 20
Project stage: Other
ML23341A1752024-02-22022 February 2024
E-mail - U. S. Nuclear Regulatory Commission Withholding Determination Form 897 for BWRVIP-03, Reactor Pressure Vessel and Internals Examination Guidelines, Revision 20
Project stage: Other
ML24058A1052024-02-29029 February 2024
Request for Boiling Water Reactor Vessel Internals Program Technical Report BWRVIP-84, Guidelines for Selection and Use of Materials for Repairs to BWR Internal Components, Revision 3
Project stage: Other
ML24085A7452024-04-15015 April 2024
Request for Transmittal of Boiling Water Reactor Vessel Internals Program Report BWRVIP-57, Revision 1, BWR Vessel and Internals Project—Instrument Penetration Repair Design Criteria, Dated November 16, 2021
Project stage: Other
ML24137A2652024-05-16016 May 2024
Us PWR Fleetwide Performance Monitoring for Optimization of Select NDE Examination Requirements
Project stage: Other
ML24197A2362024-07-15015 July 2024
Public Meeting on July 16, 2024 - Presentation 3 - Proposed ASME Section XI Code Cases - Changes to Inspection and Flaw Evaluation of Cast Austenitic Stainless Steel (CASS) PWR Piping Components
Project stage: Meeting
ML24197A2352024-07-15015 July 2024
Public Meeting on July 16, 2024 - Presentation 2 - Summary of MRP-479, Technical Basis for Changes to Inspection and Flaw Evaluation of Cast Austenitic Stainless Steel (CASS) PWR Piping Components
Project stage: Meeting
ML24197A2332024-07-15015 July 2024
Public Meeting on July 16, 2024 - Presentation 1 - Electric Power Research Institute (EPRI) Project Overview - Probabilistic Fracture Mechanics (Pfm) Evaluation of Pressurized Water Reactor (PWR) Cast Austenitic Stainless Steel (CASS) Pipin
Project stage: Meeting
PMNS20240790, Update and Discussion on EPRIs Work on Probabilistic Fracture Mechanics (Pfm) and Nondestructive Examination (NDE) of Cast Austenitic Stainless Steel (CASS)2024-07-15015 July 2024
Update and Discussion on EPRIs Work on Probabilistic Fracture Mechanics (Pfm) and Nondestructive Examination (NDE) of Cast Austenitic Stainless Steel (CASS)
Project stage: Request
ML24197A2372024-07-15015 July 2024
Public Meeting on July 16, 2024 – Presentation 4 - Research Update on Cast Austenitic Stainless Steel (CASS) Piping Nondestructive Examination (NDE)
Project stage: Meeting
ML24197A2412024-07-24024 July 2024
Summary of Meeting to Update and Discuss Electric Power Research Institutes Activities on Probabilistic Fracture Mechanics and Nondestructive Examination of Cast Austenitic Stainless Steel
Project stage: Meeting
ML25006A1082025-01-0606 January 2025
EPRI Presentation for January 8, 2025, Public Meeting - Optimizing SG and Pzr Examinations - Fleet-wide Performance Monitoring Proposal
Project stage: Request
PMNS20241497, Meeting Between NRC and EPRI to Discuss a Fleet-Wide Approach for Performance Monitoring of Select Steam Generator and Pressurizer Components2025-01-0606 January 2025
Meeting Between NRC and EPRI to Discuss a Fleet-Wide Approach for Performance Monitoring of Select Steam Generator and Pressurizer Components
Project stage: Meeting
ML25028A2642025-01-28028 January 2025
Summary of Meeting Between the U.S. Nuclear Regulatory Commission and Electric Power Research Institute to Discuss a Fleet-Wide Approach for Performance Monitoring of Select Steam Generator and Pressurizer Components
Project stage: Meeting
2024-02-22
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