ML24233A070

E-mail - Transmittal of Draft Safety Evaluation for MRP-227, Revision 2, Pressurized Water Reactor Internals Inspection and Evaluations Guideline

ML24233A070
Person / Time
Site:	Electric Power Research Institute
Issue date:	09/30/2024
From:	Lois James Licensing Processes Branch
To:	Mcgill R, Meeden A Arizona Public Service Co, Electric Power Research Institute
Shared Package
ML24233A065	List: ML24233A070
References
EPID L-2022-TOP-0029, MRP-227, Rev. 2
Download: ML24233A070 (1)

Text

1 Lois James From:

Lois James Sent:

Monday, September 30, 2024 8:22 AM To:

rmcgill@epri.com; alfred.meeden@aps.com Cc:

RidsNrrOd Resource; RidsNrrDorl Resource; RidsNrrDorlLlpb Resource; RidsNrrDnrl Resource; RidsNrrDnrlNvib Resource; RidsNrrLADHarrison Resource; RidsACRS_MailCTR Resource; Lois James; Gerond George; James Medoff; Carol Moyer; John Tsao; Dan Widrevitz; kamberge@epri.com; msaucier@epri.com

Subject:

Transmittal of Draft Safety Evaluation for MRP-227, Revision 2, Pressurized Water Reactor Internals Inspection and Evaluations Guideline (EPID L-2022-TOP-0029)

A. Rex Meeden, Chairman, PMMP EC, Arizona Public Service (APS)

Robert O. McGill, MRP Program Manager, Electric Power Research Institute Palo Alto Office 3420 Hillview Avenue Palo Alto, CA 94304-1338 Rex Meeden and Robert McGill:

By letter dated May 9, 2022, the Electric Power Research Institute (EPRI) submitted technical report Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227, Revision 2) to the U.S. Nuclear Regulatory Commission (NRC) staff for review and approval (Agencywide Documents Access and Management System Accession No. ML21301A194). The staff reviewed and accepted the technical report on June 17, 2022 (ADAMS Accession No. ML22145A401).

A copy of the draft SE has been placed in the box.com folder. Robert McGill, Kyle Amberge, and Morgan Saucier have been given access to the folder. The draft SE is being provided for a proprietary information review. If EPRI provides comments on other areas, the NRC staff will exercise its discretion on whether to address those comments.

Pursuant to Section 2.390 of Title 10 of the Code of Federal Regulations (10 CFR), we do not believe the draft SE contains proprietary information. If you believe that any information in the draft SE is proprietary, please identify such information line-by-line and define the basis pursuant to the criteria of 10 CFR 2.390. Use double brackets and yellow highlight to identify any (( proprietary information )).

To support the November 2024,Advisory Committee for Reactor Safeguards meeting, your response is due back to the NRC no later than 30 days from the date of this email.

Your response must be via a letter from an authorized individual. In addition, please provide an electronic redline/strikeout Word version of the SE either via email or the box.com folder. It helps expedite the NRC staff response to comments if EPRI provides, in the formal transmittal and in a separate Word file, a table with the following columns: Comment No., Page No., and Line No.,

Comment Type (if comments other than proprietary information are provided (i.e., clarity, accuracy)),

Suggested Revision, and a blank column NRC Disposition. However, EPRI may provide its comments in any format it chooses. The final SE will be issued after making any necessary changes.

ML24233A065 (pkg); ML24233A070 (email); ML24233A076 (proprietary draft SE - nonpublic) ^via eConcurrence *via email NRR-106 OFFICE DORL/LLPB/PM DORL/LLPB/LA DNRL/NVIB/BC OGC (NLO)

NAME LJames^

DHarrison^

ABuford*

DRoth*

DATE 08/21/2024 08/30/2024 07/10/2024 09/27/2024 OFFICE DORL/LLPB/BC DORL/LLPB/PM NAME GGeorge LJames DATE 09/29/2024 09/30/2024