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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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Text
From:
James, Lois To:
"Amberge, Kyle"; "McGill, Robert" Cc:
Chang, Richard; Medoff, James; Sanders, Serita
Subject:
MRP 227 Rev 2 Completeness and Withholding Determinations Date:
Thursday, April 7, 2022 2:47:24 PM Attachments:
NRC 897 for MPR-227 Revision 2 - Second DORL Proprietary Denial with all dgitial signature.pdf
- Kyle,
Attached please find the completed form for the U.S. Nuclear Regulatory Commission staff withholding determination for MRP-227, Revision 2, Materials Reliability Program:
Pressurized Water Reactor Internals Inspection and Evaluation Guidelines.
Note that the NRC staff did not approve the request to withhold the proprietary version from public disclosure. Our basis for that determination is provided in the attached NRC Form897, Topical Report Withholding Determination. As discussed in the form, the Electric Power Research Institute has 30 days to respond before the NRC will make the document public.
If you have any questions, please feel free to contact me at lois.james@nrc.gov.
Lois M. James, Senior Project Manager Licensing Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket No.: 99902021 EPID: L-2022-PPM-0000
ADAMS Accession Nos:
Package: ML22097A203 E-mail: ML22097A204 NRC Form 897: ML22097A205