ML24240A123

Non-Proprietary - Enclosure 2 - Report Regarding March 4 -29, 2024, Regulatory Audit for EPRI Technical Report BWRVIP-138, Updated Jet Pump Beam Inspection and Flaw Evaluation Guidelines, Revision 2 (EPID L-2023-NTR-0007) - Non-Proprietary

ML24240A123
Person / Time
Site:	99902016
Issue date:	10/01/2024
From:	Lois James Licensing Processes Branch
To:	Boiling Water Reactor (BWR) Vessel and Internals Project (BWRVIP), Electric Power Research Institute
Shared Package
ML24240A102	List: ML24060A094 ML24240A123
References
EPID L-2023-TOP-0020, EPID L-2023-TOP-0053, EPID L-2023-NTR-0007 BWRVIP-138, Rev. 2
Download: ML24240A123 (1)

Text

OFFICIAL USE ONLYPROPRIETARY INFORMATION OFFICIAL USE ONLY PROPRIETARY INFORMATION 3.0 REGULATORY AUDIT OBJECTIVES AND SCOPE The objective of this audit is to verify, via an independent evaluation, the background information related to the TR that supports the technical basis for the updated initial inspection intervals and reinspection intervals for the jet pump beams in BWR plants. Specifically, the NRC staff has reviewed BWRVIPs supporting documents related to the topics as described in this audit report to determine if additional information will require docketing to develop and support the NRC staffs conclusions for its safety evaluation of the TR.

The NRC staff conducted the audit through an online portal (also known as electronic portal, ePortal, or electronic reading room) established by EPRI.

4.0 INFORMATION AND MATERIAL FOR THE REGULATORY AUDIT The NRC staff audited many relevant documents in the EPRIs ePortal. The NRC staff reviewed and discussed with EPRI the following key information and associated material in the ePortal.

EPRIs response to staffs technical questions on the following sections of the TR Crack Initiation data and analysis in Section 5.

Crack growth calculations in Section 6.

Flaw evaluation in Section 7.

The inspection strategy in Section 8.

Updated crack growth calculations in Appendix G.

Implementation Protocol.

EPRIs response to staffs clarification questions on the following sections of the TR Background of the jet pump beams in Section 1.

Beam Susceptibility in Section 2.

Operational Experience in Section 3.

Nondestructive Examination in Section 4.

Below are References from Section 9 of the TR BWR Vessel and Internals Project, Guidelines for Selection and Use of Materials for Repairs to BWR Internal Components (BWRVIP-84). EPRI Report, October 2000.

TR-1000248.

Technical Basis for the Inspection Frequency of a BWR Group 2 Jet Pump Beam, 0000-0069-0773-01, Rev. 0, GE Hitachi Nuclear Energy.

Technical Basis for the Inspection Frequency of a BWR Group 3 Jet Pump Beam, 0000-0082-8669-01, Rev. 0, GE Hitachi Nuclear Energy.

P. L. Andresen, P. W. Emigh, M. M. Morra, and R. M. Horn: Alloy X750 Stress Corrosion Crack Growth Rate Behavior in High Temperature Water, Proc. 11th Int.

Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, NACE, Stevenson, WA, Aug. 10-14, 2003.

OFFICIAL USE ONLYPROPRIETARY INFORMATION OFFICIAL USE ONLY PROPRIETARY INFORMATION GEH Letter Report DRF 0000-0088-9987, BWRVIP-84 Alloy X-750 Design Criteria Assessment, November 25, 2009.

E-mail from P. Andresen to R. Carter dated April 27, 2020, Equations for X-750 crack growth rate (CGR) curves in BWRVIP-291, Rev 1.

Below are References from Appendix G of the TR BWRVIP-291, Revision 1: BWR Vessel and Internals Project: Microstructure, SCC and J-R Fracture Resistance of Alloy X-750 and XM-19: Final Report 2017. EPRI, Palo Alto, CA: 2017. 3002011583.

BWRVIP-336: BWR Vessel and Internals Project, Irradiation and Post-Irradiation Examination of Alloys X-750 and XM-19. EPRI, Palo Alto, CA: 2020. 3002018307.

BWRVIP-315: BWR Vessel and Internals Project, Reactor Internals Aging Management Evaluation for Extended Operations. EPRI, Palo Alto, CA: 2019. 3002012535.

BWRVIP-03, Revision 20: BWR Vessel and Internals Project, Reactor Pressure Vessel and Internals Examination Guidelines. EPRI, Palo Alto, CA: 2021. 3002010675.

5.0 DISCUSSION The NRC staff forwarded EPRI technical audit questions and clarification audit questions prior to the start of the audit activities. After the entrance meeting, the NRC staff reviewed the documents that EPRI has uploaded into the ePortal.

EPRI responded to the NRC staffs audit questions and uploaded its response to the ePortal.

The NRC staff reviewed EPRIs response in the ePortal. The NRC staff and EPRI held breakout session to discuss the EPRIs response.

In these meetings, the NRC staff obtained valuable information on the technical basis that supports the TR. EPRI also clarified for the NRC staff the analysis discussed in the TR.

The audit activities ended on May 24, 2024. The next step in the technical review phase is for the NRC staff to transmit to the EPRI the official Request for Additional Information (RAI). After that, EPRI may provide its response to NRC staffs RAI as a supplement. If the NRC staff finds the EPRIs RAI response satisfactorily, the NRC staff will start to develop the safety evaluation for the TR.

Appendix A attached to the audit report contains the participants of the audit. Appendix B contains the NRC staffs audit questions.

6.0 CONCLUSION

The audit accomplished the objectives and goals of the audit plan by allowing direct interaction with EPRIs technical experts. The NRC staff were able to obtain from EPRI clarification on multiple audit questions, and test data supporting the TR. The clarifications will allow the NRC staff to assess the technical basis of the TR more efficiently and effectively.

OFFICIAL USE ONLYPROPRIETARY INFORMATION OFFICIAL USE ONLY PROPRIETARY INFORMATION

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OFFICIAL USE ONLYPROPRIETARY INFORMATION OFFICIAL USE ONLY PROPRIETARY INFORMATION incorporated in the TR. Clarify whether TR has incorporated BWRVIPs response to RAI8 dated May 17, 2011.

CGT-2. The ASME Code,Section XI, IWB-2420 requires successive examinations if an indication is detected in a Class 1 component. If an indication is detected in BB-1, BB-2 or BB-3 region of the JPBs, discuss whether the successive examination of JPBs per IWB-2420 is applicable. If negative, provide justification.