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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
April 15, 2024 Nathan Palm BWRVIP Program Manager Electric Power Research Institute 1300 West W.T. Harris Blvd Charlotte, NC 28262-8550
SUBJECT:
REQUEST FOR TRANSMITTAL OF BOILING WATER REACTOR VESSEL INTERNALS PROGRAM REPORT BWRVIP-57, REVISION 1, BWR VESSEL AND INTERNALS PROJECTINSTRUMENT PENETRATION REPAIR DESIGN CRITERIA, DATED NOVEMBER 16, 2021 (EPID L-2022-PPM-0000)
Dear Nathan Palm,
This letter serves as a request for transmittal of the Boiling Water Reactor Vessel Internals Program Report (BWRVIP)-57, Revision 1, BWR [Boiling Water Reactor] Vessel and Internals ProjectInstrument Penetration Repair Design Criteria, dated November 16, 2021. This is for informational purposes only.
By letter dated January 19, 2024 (Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML24019A009), the Tennessee Valley Authority (TVA) submitted subsequent license renewal application for Browns Ferry Nuclear Plant (BFN),
Units 1, 2, and 3. For the BWR penetration aging management program, TVA referenced BWRVIP-57, Revision 1, instead of the approved BWRVIP-57-A as guidelines for repair design criteria for instrumentation penetrations as recommended in NUREG-2191, Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report Final Report, published July 2017 (ADAMS Accession Nos. ML17187A031 and ML17187A204).
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 2.390 of Title 10 of the Code of Federal Regulations of the NRC rules and practices, a copy of this letter and its publicly available 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
ML24085A745
^ via eConcurrence
- via E-mail NRR-106 OFFICE NRR/DORL/LPLB/PM NRR/DORL/LPLB/LA NRR/DNRL/NPHP NRR/DORL/LPLB/BC NAME LJames DHarrison MMitchell GGeorge DATE 03/28/2024 03/29/2024 04/15/2024 04/15/2024 OFFICE NRR/DORL/LPLB/PM NAME LJames DATE 04/15/2024