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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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October 11, 2023 Nathan Palm, BWRVIP Program Manager Electric Power Research Institute 1300 West W.T. Harris Blvd Charlotte, NC 28262-8550
SUBJECT:
REQUEST FOR BOILING WATER REACTOR VESSEL INTERNALS PROGRAM TECHNICAL REPORT BWRVIP-03, REACTOR PRESSURE VESSEL AND INTERNALS EXAMINATION GUIDELINES, REVISION 20 (EPID L-2022-PPM-0000)
Dear Mr. Palm:
Recently, the U.S. Nuclear Regulatory Commission (NRC) has noted that several nuclear reactor licensees have referenced Revision 20 to Boiling Water Reactor Vessel Internals Program (BWRVIP) Technical Report BWRVIP-03, Reactor Pressure Vessel and Internals Examination Guidelines, in submittals for NRC review and approval. The version currently available to the NRC staff is Revision 19, submitted by the Electric Power Research Institute (EPRI) on February 8, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17054C675).
The purpose of this letter is to request that the EPRI provide BWRVIP-03, Revision 20, to the NRC staff for information purposes only.
This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, under Control Number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number.
In accordance with 10 CFR 2.390 of the NRC rules and practices, a copy of this letter and its enclosures will be available electronically for public inspection in the NRC public document room or from the publicly available records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site.
If you have any questions, please do not hesitate to contact me by email at lois.james@nrc.gov.
Sincerely,
/RA/
Lois M. James, Senior Project Manager Licensing Projects Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Docket No. 99902016
ML23264A013
- via eConcurrence NRR-106 OFFICE NRR/DORL/LPLBPM*
NRR/DORL/LPLB/LA*
NRR/DORL/LPLB/BC*
NRR/DORL/LPLB/PM*
NAME LJames DHarrison GGeorge LJames DATE 09/22/2023 09/28/2023 10/11/2023 10/11/2023