ML19346F890

Cover Letter by the Office of Nuclear Reactor Regulation Topical Report for PWROG-18034-P, Revision 0, Updates to the Methodology in WCAP-15029-P-A, Rev 1, Westinghouse Methodology for Evaluating the Acceptability of Baffle-Former-Barrel Bo

ML19346F890
Person / Time
Site:	99902037
Issue date:	12/19/2019
From:	Leslie Fields, Dennis Morey Licensing Processes Branch
To:	Nowinowski W PWR Owners Group
Fields L
Shared Package
ML19346F920	List: ML19346F890
References
EPID L-2018-TOP-0046
Download: ML19346F890 (3)

Text

OFFICIAL USE ONLY - PROPRIETARY INFORMATION W. Nowinowski 1 December 19, 2019 Mr. W. Anthony Nowinowski, Executive Director PWR Owners Group, Program Management Office Westinghouse Electric Company 1000 Westinghouse Drive, Suite 380 Cranberry Township, PA 16066

SUBJECT:

DRAFT SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION TOPICAL REPORT PWROG-18034-P, REVISION 0, UPDATES TO THE METHODOLOGY IN WCAP-15029-P-A, REV. 1, WESTINGHOUSE METHODOLOGY FOR EVALUATING THE ACCEPTABILITY OF BAFFLE-FORMER-BARREL BOLTING DISTRIBUTIONS UNDER FAULTED LOAD CONDITIONS (EPID L-2018-TOP-0046)

Dear Mr. Nowinowski:

By letter dated October 31, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18306A490) and supplemented by letter dated October 16, 2019 (ADAMS Accession No. ML19317D793), the Pressurized Water Reactor (PWR) Owners Group (PWROG) transmitted Topical Report (TR), PWROG-18034-NP, Revision 0) and PWROG-18034-P, Revision 0 (ADAMS Accession Nos. ML18306A491 and ML18306A492) to the U.S.

Nuclear Regulatory Commission (NRC) for review and approval.

The TR updates the NRC-approved methodology in WCAP-15030-NP-A (ADAMS Accession No. ML15222A882) and WCAP-15029-P-A (ADAMS Accession No. ML18306A790) for acceptable bolting pattern analyses (ABPAs) for baffle-former and barrel-former bolting in Westinghouse-designed PWRs. The TR and its supplement cover major topics including the summary of changes to the NRC-approved methodology in WCAP-15029-P-A which includes a review of the limitations in the NRC safety evaluation in WCAP-15029-P-A and how these limitations are addressed in the new methodology are addressed in the safety evaluation (SE).

Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 2.390, we believe that the enclosed draft SE may contain proprietary information. If you believe that any information in the enclosure is proprietary, please identify such information line-by-line denoted by bold brackets

((( ))), and define the basis pursuant to the criteria of 10 CFR 2.390. Twenty working days are provided for you to comment on the proprietary aspects and provide any factual errors or clarity concerns contained in the SE. The final SE will be issued after making any necessary changes and a non-proprietary version will be made publicly available. The NRC staff's disposition of your comments on the draft SE will be discussed in the final SE.

To facilitate the NRC staff's review of your comments, please provide a marked-up copy of the revised draft SE showing proposed changes and provide a summary table of the proposed changes.

NOTICE: The enclosure transmitted herewith contains Proprietary Information.

When separated from the enclosure, this transmittal document is decontrolled.

OFFICIAL USE ONLY - PROPRIETARY INFORMATION

OFFICIAL USE ONLY - PROPRIETARY INFORMATION W. Nowinowski If you have any questions, please contact Leslie Fields at 301-415-1186.

Sincerely,

/RA/

Dennis C. Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Docket No. 99902037

Enclosure:

Draft SE (Proprietary)

OFFICIAL USE ONLY - PROPRIETARY INFORMATION

ML19346F920 (Package)

ML19346F890 (Letter)

ML19345H407 (Draft SE) *via e-mail OFFICE DORL/LLPB/PM DORL/LLPB/LA DNLR/NVIB/BC DORL/LLPB/BC NAME LFields* DHarrison* HGonzalez* DMorey*

DATE 12/13/2019 12/19/2019 12/16/2019 12/19/2019