Letter Sequence Other |
|---|
|
|
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
[Table View] |
Text
From:
Lois James To:
martin.bonifanti@constellation.com; Palm, Nathan Cc:
Lois James; Gerond George; Angie Buford; John Wise; David Rudland; Varoujan Kalikian
Subject:
U. S. Nuclear Regulatory Commission Withholding Determination Form 897 for BWRVIP-03, Reactor Pressure Vessel and Internals Examination Guidelines, Revision 20 (EPID L-2022-PPM-0000)
Date:
Thursday, February 22, 2024 10:26:24 PM Attachments:
BWRVIP NRC 897 02-22.pdf Martin Bonifanti, Constellation, BWRVIP Chairman Nathan Palm, EPRI, BWRVIP Program Manager 1300 West W.T. Harris Blvd Charlotte, NC 28262-8550
Mr. Bonifanti and Mr. Palm,
Attached is the U.S. Nuclear Regulatory Commission (NRC) staff withholding determination for the Electric Power Research Institutes (EPRIs) BWRVIP-03, Reactor Pressure Vessel and Internals Examination Guidelines, Revision 20
If you have any questions, please feel free to contact me via email lois.james@nrc.gov.
Sincerely,
Lois M. James, Senior Project Manager Licensing Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission
Docket No. 99902016
ADAMS Accession Nos.: ML23341A171 (pkg); ML23341A175 (email); ML23341A177 (Form 897)