Letter Sequence RAI |
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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
[Table View] |
Text
MEMORANDUM TO:
Gerond A. George, Chief Licensing Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM:
Lois M. James, Senior Project Manager Licensing Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF MEETING TO DISCUSS MRP-227, REVISION 2, PRESSURIZED WATER REACTOR INTERNALS INSPECTION AND EVALUATIONS GUIDELINE, RAI NO.4 FOR THE B&W DESIGN CORE BARREL WELDS (EPID L-2022-TOP-0029)
On April 4, 2024, the U.S. Nuclear Commission (NRC) staff met with Electric Power Research Institute (EPRI) to discuss EPRI's response to MRP-227, Revision 2, PWR Internals Inspection and Evaluations Guideline, Request for Additional information (RAI) No. 4 for the Babcock &
Wilcox (B&W) design core barrel welds. The meeting summary is Enclosure 1, and the list of attendees is Enclosure 2.
If you have any questions or comments, please contact me via e-mail at Lois.James@nrc.gov.
Docket No. 99902021
Enclosures:
- 1. Meeting Summary
- 2. List of Attendees cc: w/enclosure:
See next page CONTACT: Lois M. James, NRR/DORL/LLPB 301-415-3306 April 30, 2024 Signed by James, Lois on 04/30/24
ML24095A185 (Vendor slides are listed in summary)
^via eConcurrence
- via e-mail NRR-106 OFFICE NRR/DORL/LLPB/PM NRR/DORL/LLPB/LA NRR/DNRL/NVIB/BC NRR/DORL/LLPB/BC NAME LJames*
DHarrison ABuford GGeorge DATE 04/05/2024 04/09/2024 4/24/2024 4/24/2024 OFFICE NRR/DORL/LLPB/PM NAME LJames*
DATE 4/30/2024 U.S. Nuclear Regulatory Commission Public Meeting Summary
Title:
Meeting To Discuss Materials Reliability Program (MRP)-227, Revision 2, Pressurized Water Reactor (PWR) Internals Inspection and Evaluations Guideline, Request for Additional Information (RAI) No. 4 for the Babcock & Wilcox (B&W) Design Core Barrel Welds Date of Meeting: April 4, 2024, 10:30 AM - 12:00 PM Location:
Webinar Type of Meeting: This was an Observation Meeting in which attendees had an opportunity to observe the U.S. Nuclear Regulatory Commission (NRC) performing its regulatory function or discussing regulatory issues. Attendees had an opportunity to ask questions of the NRC staff or make comments about the issues discussed following the business portion of the meeting; however, the NRC was not actively soliciting comments towards regulatory decisions at this meeting.
Purpose of the Meeting:
To discuss Electric Power Research Institutes (EPRI's) response to MRP-227, Revision 2, PWR Internals Inspection and Evaluations Guideline, RAI No. 4 for the B&W design core barrel welds General Details:
The NRC staff held a public, observational meeting with EPRI to discuss EPRI's response to MRP-227, Revision 2, RAI No. 4 for the B&W design core barrel welds. The meeting began at 10:30 am and ended at 11:30 am. There were nine NRC staff members, three EPRI staff members, twelve industry members, and no members of the public. The meeting began with introductions of the NRC staff, EPRI staff members and members of industry.
Summary of Meeting:
The NRC staff began its discussion by stating that we received the slides the day prior to the public meeting and the staff did not have sufficient time to process. The NRC staff also stated that no decisions would be made during this meeting.
Industry reviewed the information provided in EPRIs slides (Agencywide Documents Access and Management System (ADAMS) ML24094A326).
The NRC staff expressed concern about the MRP-227, Revision 2, provision that would expand inspections at one site owned by one licensee based on primary inspections done at another site owned by another licensee. Further, the NRC staff explained that Chapter 7 of MRP-227 does not define licensee-to-licensee interactions, just licensee to EPRI.
Industry pointed out that NEI 03-08, Guideline for the Management of Materials Issues, is guidance that the industry has committed to implement and does implement on a routine basis.
NEI 03-08 has provisions for sharing within industry for emerging issues.
The NRC staff stated that, NEI 03-08 notwithstanding, we are reviewing MRP-227, Revision 2.
The EPRI staff members expressed that industry perceives that the NRC staff needs to understand how industry addresses emergent material issues more explicitly than is expressed in MRP-227, Revision 2.
EPRI restated the NRC staffs concern:
utility x performs primary inspection, utility y is obligated to perform expansion inspection This is in MRP-227, Revision 2, and agreed upon by industry There is no regulatory requirement to link the expansion inspection at utility y based on findings at utility x.
EPRI staff further asked if the NRC staffs concern is really about the method of communication.
Specifically, there is a rapid conference call required by NEI 03-08 and then a follow up MRP letter in approximately 6 months.
EPRI staff ended their discussion by stating that the industry understands the NRC staffs concern better and would like to consider how best to address the concern. EPRI staff indicated that the RAI response submitted this week (ADAMS Accession No. ML24095A274) did not include responses to RAIs 3 and 4. The EPRI staff stated that they will request an extension to RAI 3 and 4 responses. The EPRI staff also stated that they may request another public meeting prior to submitting the RAI 3 and 4 responses.
Public Participation Themes:
No member of the public attended the webinar.
Action Items/Next Steps:
The NRC staff will prepare and issue a meeting summary.
Attachments:
Meeting description and agenda - ADAMS Accession No. ML24079A246 Vendor slide presentation - ADAMS Accession No. ML24094A326 U.S. Nuclear Regulatory Commission Public Meeting - Attendees List April 4, 2024
Title:
Meeting to Discuss MRP-227, Revision 2, Pressurized Water Reactor Internals Inspection and Evaluations Guideline, RAI No.4 for the B&W Design Core Barrel Welds Name U.S. Nuclear Regulatory Commission (NRC) Participants Angie Buford NRC James Delosreyes NRC Carolyn Fairbanks NRC Gerond George NRC Lois James NRC James Medoff NRC Demetrius Murray NRC John Tsao NRC On Yee NRC Electric Power Research Institute (EPRI) Participants Name Affiliation Kyle Amberge EPRI Amy Freed EPRI Robert McGill EPRI Industry Participants Name Affiliation Tyler Whaley Ameren Rachel Lee Doss Duke Energy Jasmyn Bone Entergy Sarah Davidsaver Framatome Steve Fyfitch Framatome John Neil Framatome Corey Thomas Southern Nuclear Co.
Timothy Griesbach Structural Integrity Associates, Inc Aaron Bowsher Vistra Josh Morton Vistra Levi Jones Vistra Joshua K. McKinley Westinghouse Electric Company