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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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Public Meeting Regarding Staff Review of EPRI Non-Proprietary Report No. 3002020105, Materials Reliability Program: Pressurized Water Reactor Inspection and Evaluation Guidelines (MRP-227, Revision 2)
Clarifications on Scope of Staff Review Presenter: James Medoff Public Meeting of Nov. 7, 2022
Staff Review for TR MRP-227, Rev. 2 (the Subject TR)
- NRC accepted MRP-227, Rev. 2 for review in Summer of 2022
- NRC PM for MRP-227, Rev. 2 review initiated the review as a Standard Review with inclusion of a PM option to hold an audit of changes made in MRP-227, Rev. 2 from the prior version in MRP-227, Rev. 1-A Standard Review was chosen because:
Number and the complexity of changes in MRP-227, Rev. 2 versus MRP-227, Rev. 1-A Methodology in MRP-227, Rev. 2 assesses aging over a 80-year service period versus MRP-227, Rev. 1-A only assessed aging over a 60-year service period Potential logistics issues (See next slides for examples)
Regulatory Audit is being conducted for efficiency and effectiveness:
Address clarifications and confirmations Ensure RAI process is used only for necessary topics to support NRC review/conclusions in SE
TR MRP-227, Rev. 2 Logistics Issues
- Logistics Issue #1: Bases for some component-specific screening or inspection and evaluation have been revised in MRP-227, Rev. 2 versus MRP-227, Rev. 1-A Main objective of MRP-227, Rev. 2 - focus on changes to MRP-227 criteria that are needed to accommodate implementation of the guidelines during 60 - 80 year subsequent license renewal (SLR) periods NRC staff conclusions in MRP-227, Rev. 1-A (i.e.,related to 60-year service period) are may not be applicable for 80-year service period for these for some component-specific screening or inspection and evaluation
TR MRP-227, Rev. 2 Logistics Issues (Continued)
- Logistics Issue #2 - Revisions to Applicant/Licensee Action Item Resolution:
- MRP-227-A included Applicant/Licensee Action Items (A/LAI)
- MRP-227, Rev. 1-A addressed these Applicant/Licensee Action Items from MRP-227-A Justification to resolve these A/LAIs in MRP-227, Rev. 1-A were based on an aging over a 40 - 60 year license renewal period MRP-227, Rev. 2, appears to resolve some topics in these A/LAIs in a manner different from MRP-227, Rev. 1-A.
NRC staff seeks to understand if:
Resolution of A/LAIs remain valid for MRP-227, Rev. 2 or Updates made in MRP-227, Rev. 2, including bases, support A/LAIs remaining resolved for 80-year service period A/LAI #6 on inaccessible B&W core barrel components is an example.
TR MRP-227, Rev. 2 Logistics Issues (Continued)
WCAP-17096, Rev. 3 (a pending review) applies to MRP-227, Rev. 1-A (the status of Primary and Expansion category components)
Version of WCAP-17096 applicable to MRP-227, Rev. 2 (status of Primary and Expansion category components) has NOT been developed yet
- Logistics Issue #4 - MRP-227, Rev. 2, discusses use of MRP-211 and BWRVIP-100, Revision 1-A lower bound fracture toughness value methods Chapter 6 does not address the Part 21 and open item on lower bound fracture toughness values identified in EPRI Letter MRP 2021-019