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Results
Other: ML22145A444, ML22145A445, ML23027A098, ML23095A050, ML23151A701, ML23263A023, ML24064A081, ML24064A083, ML24094A326, ML24096B714, ML24304B020
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MONTHYEARML22129A1392022-05-0909 May 2022 Request for Exemption of NRC Review Fees for MRP-227, Revision 2 (Ref. EPRI Docket Number 99902021) Project stage: Request ML22129A1402022-05-0909 May 2022 Report Transmittal: Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227, Revision 2). EPRI, Palo Alto, CA: 2021. 3002020105. Ref.: EPRI Docket No. 99902021 Project stage: Request ML22145A4442022-06-17017 June 2022 MRP-227, Revision 2, PWR Internals Inspection and Evaluations Guideline - E-mail for Completeness Review Project stage: Other ML22145A4452022-06-17017 June 2022 MRP-227, Revision 2, PWR Internals Inspection and Evaluations Guideline - NRC 898, Completeness Project stage: Other PMNS20221108, NRC Staff Meeting with EPRI to Discuss the Process for Reviewing Technical Report MRP-227, Revision 2, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines2022-10-27027 October 2022 NRC Staff Meeting with EPRI to Discuss the Process for Reviewing Technical Report MRP-227, Revision 2, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines Project stage: Meeting ML22311A0802022-11-0707 November 2022 Public Meeting Regarding Staff Review of EPRI Non-Proprietary Rpt MRP-227 R2 - 22-11-07 Project stage: Approval ML22311A0892022-11-23023 November 2022 Meeting Between NRC Staff and EPRI to Discuss the Process for Reviewing Technical Report MRP-227, Rev 2, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines Project stage: Meeting ML22335A4912022-12-0101 December 2022 E-Mail - Final Request for Additional Information – Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227, Revision 2) Project stage: RAI ML22335A5132022-12-0101 December 2022 Nonproprietary - MRP-227 Revision 2 RAIs Enclosure - Final - Nonproprietary - Redacted Project stage: RAI ML23027A0982023-02-0707 February 2023 Report Regarding October 31 Through November 4, 2022, Regulatory Audit for EPRI Technical Report MRP-227, Revision 2, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines Project stage: Other ML23095A0492023-04-0404 April 2023 Responses to NRC Request for Additional Information for Electric Power Research Institute Topical Report MRP-227, Revision 2, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluations Guideline (300202010 Project stage: Response to RAI ML23095A0502023-04-0404 April 2023 Responses to NRC Request or Additional Information for Electric Power Research Institute Topical Report MRP-227, Revision 2, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluations Guideline (3002020105 Project stage: Other PMNS20230643, Meeting Between NRC and EPRI to Discuss Staffs Remaining Questions and Proposed Limitations and Conditions on MRP-227, Revision 2, Pressurized Water Reactor Internals Inspection and Evaluations Guideline2023-05-19019 May 2023 Meeting Between NRC and EPRI to Discuss Staffs Remaining Questions and Proposed Limitations and Conditions on MRP-227, Revision 2, Pressurized Water Reactor Internals Inspection and Evaluations Guideline Project stage: Meeting ML23146A0142023-05-31031 May 2023 Discussion Topics for the May 31, 2023, Public Meeting on MRP-227, Rev. 2, Pressurized Water Reactor Internals Inspection and Evaluations Guideline, Review Project stage: Meeting ML23151A7022023-05-31031 May 2023 NRC Supplemental Information for the May 31, 2023 Public Meeting on MRP-227, Revision 2 - Topic 6 Project stage: Meeting ML23151A7012023-05-31031 May 2023 Recent PWR Reactor Vessel Internals Operating Experience Project stage: Other ML23263A0232023-10-11011 October 2023 Request for Materials Reliability Program: MRP 2023-005, MRP 227 NEI 03-08 Needed Interim Guidance for Wec/Ce Core Barrel Inspections Project stage: Other PMNS20231081, Meeting Between NRC and EPRI to Discuss Potential Limitations and Conditions in the Safety Evaluation for MRP-227, Revision 2, Pressurized Water Reactor Internals Inspection and Evaluations Guideline2023-10-25025 October 2023 Meeting Between NRC and EPRI to Discuss Potential Limitations and Conditions in the Safety Evaluation for MRP-227, Revision 2, Pressurized Water Reactor Internals Inspection and Evaluations Guideline Project stage: Approval ML23318A4022023-11-14014 November 2023 MRP-227 Rev 2 - Draft Conditions and Alais for Safety Evaluation Project stage: Draft Approval ML23352A2422023-12-18018 December 2023 E-Mail - Final Request for Additional Information - MRP-227, Revision 2, Pressurized Water Reactor Internals Inspection and Evaluations Guideline Project stage: RAI ML23352A2432023-12-18018 December 2023 Final Request for Additional Information - MRP-227, Revision 2, Pressurized Water Reactor Internals Inspection and Evaluations Guideline Project stage: RAI ML24064A0832024-02-29029 February 2024 EPRI Informed NRC That the RAI Response Will Be Delayed a Few Weeks Project stage: Other ML24064A0812024-03-0404 March 2024 EPRI Informed NRC That Report PWROG-16003-P Should Be Requested from the PWROG Project stage: Other PMNS20240395, Meeting to Discuss MRP-227, Revision 2, PWR Internals Inspection and Evaluations Guideline, RAI No.4 for the B&W Design Core Barrel Welds2024-03-19019 March 2024 Meeting to Discuss MRP-227, Revision 2, PWR Internals Inspection and Evaluations Guideline, RAI No.4 for the B&W Design Core Barrel Welds Project stage: RAI ML24094A3262024-04-0303 April 2024 MRP-227, Revision 2, Subsequent RAI 4 - B&W-Designed PWR Internals Aging Management Project stage: Other ML24095A2752024-04-0404 April 2024 EPRI - Responses to NRC Request for Additional Information for Topical Report MRP-227, Revision 2, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluations Guideline (3002020105) Project stage: Response to RAI ML24095A2762024-04-0404 April 2024 EPRI - Responses to NRC Request for Additional Information for Topical Report MRP-227, Revision 2, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluations Guideline (3002020105) Project stage: Response to RAI ML24095A1852024-04-30030 April 2024 4/4/2024, Summary of Meeting to Discuss MRP-227, Revision 2, PWR Internals Inspection and Evaluations Guideline, RAI No. 4 for the B&W Design Core Barrel Welds Project stage: RAI ML24096B7142024-04-30030 April 2024 Change in Estimated Review Schedule for MRP-227, Revision 2, Pressurized Water Reactor Internals Inspection and Evaluations Guideline Project stage: Other ML24150A0922024-05-28028 May 2024 Responses to NRC Request for Additional Information for EPRI Topical Report MRP-227, Rev. 2, Materials Reliability Program PWR Internals Inspections & Evaluations Guideline Project stage: Response to RAI ML24150A0932024-05-28028 May 2024 Attachment - Industry Responses to NRC Request for Additional Information Re B&W Design PWRs Project stage: Response to RAI ML24233A0702024-09-30030 September 2024 E-mail - Transmittal of Draft Safety Evaluation for MRP-227, Revision 2, Pressurized Water Reactor Internals Inspection and Evaluations Guideline Project stage: Draft Approval ML24304B0312024-09-30030 September 2024 Public Version of Draft Safety Evaluation for MRP-227, Revision 2, Pressurized Water Reactor Internals Inspection and Evaluations Guideline Project stage: Draft Approval ML24274A1352024-09-30030 September 2024 EPRI Comment on MRP-227, Revision 2, Draft SE, Dated September 30, 2024, Correcting an Incorrect Acronym Project stage: Draft Other ML24304B0202024-10-28028 October 2024 EPRI Response to Proprietary Review of MRP-227, Revision 2, Pressurized Water Reactor Internals Inspection and Evaluations Guideline, Safety Evaluation and Comments Project stage: Other ML24304B0302024-11-0101 November 2024 E-mail - Transmittal of Public Version of Draft Safety Evaluation for MRP-227, Revision 2, Pressurized Water Reactor Internals Inspection and Evaluations Guideline to Advisory Committee on Reactor Safeguards Project stage: Draft Approval 2023-04-04
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November 23, 2022 MEMORANDUM TO:
Ngola A. Otto, Acting Chief Licensing Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM:
Lois M. James, Senior Project Manager
/RA/
Licensing Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
MEETING BETWEEN NUCLEAR REGULATORY COMMISSION STAFF AND ELECTRIC POWER RESEARCH INSTITUTE TO DISCUSS THE PROCESS FOR REVIEWING TECHNICAL REPORT MRP-227, REVISION 2, MATERIALS RELIABILITY PROGRAM: PRESSURIZED WATER REACTOR INTERNALS INSPECTION AND EVALUATION GUIDELINES (EPID L-2022-TOP-0029)
On November 7, 2022, the U.S. Nuclear Regulatory Commission (NRC) staff met with representatives from the Electric Power Research Institute (EPRI) to discuss the process for reviewing Technical Report MRP-227, Revision 2, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines. The meeting summary is enclosed as Enclosure 1 and the list of attendees is enclosed as Enclosure 2.
If you have any questions or comments, please contact me via email at Lois.James@nrc.gov.
CONTACT: Lois M. James, NRR/DORL 301-415-3306 Docket Nos. 99902021
Enclosures:
- 1. Meeting Summary
- 2. List of Attendees
U.S. Nuclear Regulatory Commission Public Meeting Summary
Title:
U.S. Nuclear Regulatory Commission (NRC) Staff Meeting with Electric Power Research Institute (EPRI) Representatives to Discuss the Process for Reviewing Technical Report MRP-227, Revision 2, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines Date of Meeting: November 7, 2022, 2:00 pm - 3:00 pm Location: Webinar Type of Meeting: This was an Observation Meeting. The attendees had an opportunity to observe the NRC performing its regulatory function or discussing regulatory issues. The attendees had an opportunity to ask questions of the NRC staff and to make comments about the issues discussed following the business portion of the meeting; however, the NRC is not actively soliciting comments towards regulatory decisions at this meeting.
Purpose of the Meeting:
To Discuss the Process for Reviewing Technical Report MRP-227, Revision 2, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines.
General Details:
The NRC staff held an observational meeting with the EPRI representatives to discuss the process for reviewing Technical Report MRP-227, Revision 2, Materials Reliability Program:
Pressurized Water Reactor Internals Inspection and Evaluation Guidelines. The meeting began at 2:00 pm and ended 2:35 pm. There were nine NRC staff members, three EPRI, sixteen members of industry, and no members of the public or individuals who did not identify their affiliation. The meeting began with introductions of the NRC staff, EPRI representatives, and industry staff.
Summary of the Meeting:
The NRC staff began the meeting by describing the history of its review of Revision 2 of Technical Report MRP-227, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines. The NRC staff accepted MRP-227, Revision 2, for review in the summer of 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22145A401). The NRC staff opted for a Standard Review in accordance with the Office of Nuclear Reactor Regulation Office Instruction LIC-500, Topical Report Process (ADAMS Accession No. ML20247G279) which includes the following steps:
acceptance review, regulatory audit, request for additional information (RAI),
a draft safety evaluation (SE),
final SE, and version -A TR with staff verification.
The Standard Review was chosen because:
Number and the complexity of changes in MRP-227, Revision 2, versus MRP-227, Revision 1-A Methodology in MRP-227, Revision 2, assesses aging over an 80-year service period versus MRP-227, Revision 1-A, only assessed aging over a 60-year service period Potential logistics issues Bases for some component-specific screening or inspection and evaluation have been revised in MRP-227, Revision 2, versus MRP-227, Revision 1-A Revisions to Applicant/Licensee Action Item Resolution Referencing of WCAP-17096-NP-A, Revision 2 MRP-227, Revision 2, discusses use of MRP-211 and BWRVIP-100, Revision 1-A, lower bound fracture toughness value methods MRP-227, Revision 2, references Crack Growth Model in EPRI Report No. 3002003103 EPRI representatives pointed out an error on presentation Slide 5. The reference to EPRI letter MRP 2021-019 was incorrect. The correct reference is EPRI BWRVIP 2021-030, Electric Power Research Institute - 2021-030, Potential Non-Conservatism in EPRI Report, BWRVIP-100, Rev. 1-A, 3002008388 and Impacted BWRVIP Reports (ADAMS Accession No. ML21084A164).
Public Participation Themes:
No member of the public spoke during the meeting.
Attachments:
Meeting description and agenda - ADAMS Accession No. ML22300A059 NRC slide presentation-ADAMS Accession No. ML22311A080
U.S. Nuclear Regulatory Commission Public Meeting Attendees
Title:
U.S. Nuclear Regulatory Commission (NRC) Staff Meeting with Electric Power Research Institute (EPRI) Representatives to Discuss the Process for Reviewing Technical Report MRP-227, Revision 2, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines NRC Participants Name Affiliation David Dijamco NRC Allen Hiser NRC Lois James NRC James Medoff NRC Carol Moyer NRC David Rudland NRC John Tsao NRC Christopher Tyree NRC Dan Widrevitz NRC EPRI Participants Name Affiliation Kyle Amberge EPRI James Cirilli EPRI Randy Stark EPRI Industry Participants Name Affiliation Dale E Turinetti American Electric Power Ramon Cruz Constellation Nuclear Kemper Young Constellation Nuclear Sarah DavidSaver Framatome Inc. (Framatome)
Ryan Hosler Framatome Stacy Yoder Framatome Shane Webb NextEra Energy Kris Garg Public Service Enterprise Group Corey Thomas Southern Nuclear Company Tyler Bro Westinghouse Electric Company (WEC)
Geoffrey Campbell WEC Ernest Deemer WEC Joshua K. McKinley WEC James P Molkenthin WEC Tim L. OConnor WEC Tyler Whaley WEC
ML22311A089
- via email NRR-106 OFFICE DORL/LLPB/PM DORL/LLPB/LA DNRL/NVIB/TR NAME LJames*
DHarrison JMedoff DATE 11/07/2022 11/10/2022 11/16/2022 OFFICE DNRL/NVIB/BC DORL/LLPB/BC DORL/LLPB/PM NAME DWidrevitz (A)
NOtto (A)
LJames DATE 11/16/2022 11/16/2022 11/23/2022