ML20134M356

Final Safety Evaluation by the Office of Nuclear Reactor Regulation Topical Report PWROG-18034-P, Revision 0, Updates to the Methodology for Evaluating the Acceptability of Baffle-Former-Barrel Bolting Distributions Under Faulted Load Condi

ML20134M356
Person / Time
Site:	99902037
Issue date:	05/26/2020
From:	Dennis Morey Licensing Processes Branch
To:	Nowinowski W PWR Owners Group
Fields L
Shared Package
ML20134M479	List: ML20134M356
References
EPID L-2018-TOP-0046, PWROG-18034-P Rev. 0, WCAP-15029-P-A Rev. 1
Download: ML20134M356 (3)

Text

OFFICIAL USE ONLY - PROPRIETARY INFORMATION May 26, 2020 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:

FINAL 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) as supplemented by letters dated October 22, 2019 and January 22, 2020 (ADAMS Nos. ML19317D801 and ML20023A274, respectively), the Pressurized Water Reactor (PWR) Owners Group (PWROG, or the applicant), submitted to the U.S. Nuclear Regulatory Commission (NRC) for review and approval Topical Report (TR)

PWROG-18034-P and PWROG-18034-NP Revision 0, Updates to the Methodology in WCAP-15030-NP-A, Rev. 0, Westinghouse Methodology for Evaluating the Acceptability of Baffle-Former-Barrel Bolting Distributions Under Faulted Load Conditions (ADAMS Nos. ML18306A492 and ML18306A491, respectively) henceforth, referred to as the TR.

The NRC staffs review determined that the information provided in the TR and its supplements updates the NRC-approved methodology in WCAP-15030-NP-A and WCAP-15029-P-A for acceptable bolting pattern analyses (ABPAs) for baffle-former and barrel-former bolting in Westinghouse Electric Company (Westinghouse)-designed PWRs. The NRC staff has concluded that the methodology of PWROG-18034-P/NP may be used to supplement the methodology of WCAP-15029-P-A and WCAP-15030-NP-A for developing ABPAs for all Westinghouse-designed reactors are appropriate subject to the given conditions and limitations identified in the safety evaluation (SE).

By letter dated December 19, 2019 (ADAMS Accession No. ML19346F890), the NRC staff provided the draft SE to the PWROG for review and comment. By letter dated March 19, 2020 (ADAMS Accession No. ML20079H608), the PWROG provided comments to the NRC staff.

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 In accordance with the guidance provided on the NRC website, we request that the PWROG publish an approved version of PWROG-18034-P, Revision 0 within three months of receipt of this letter. The approved versions shall incorporate this letter and the enclosed final SE after the title page. For Non-proprietary versions, the PWROG shall strike the proprietary information markings in this letter and make the appropriate redactions and adjustments to document security classifications to the attached SE. Also, it must contain historical review information, including NRC request for additional information (RAI) questions and your responses. The approved version shall include an -A (designating approved) following the TR identification symbol. As an alternative to including the RAI questions and RAI responses behind the title page, if changes to the TR were provided to the NRC staff to support the resolution of RAI responses, and if the NRC staff reviewed and approved those changes as described in the RAI responses, there are two ways that the accepted version can capture the RAI questions:

1. The RAI questions and RAI responses can be included as an appendix to the accepted version.

2. The RAI questions and RAI responses can be captured in the form of a table (inserted after the final SE) which summarizes the changes as shown in the approved version of the TR. The table should reference the specific RAIs and RAI responses which resulted in any changes, as shown in the accepted version of the TR.

If future changes to the NRCs regulatory requirements affect the acceptability of this TR. The PWROG will be expected to revise the TR appropriately or justify their continued applicability for subsequent referencing. Licensees referencing this TR would be expected to justify their continued applicability or evaluate their plant using the revised TR.

If you have any questions, please contact Leslie Fields at 301-415-1186.

Sincerely,

/RA/

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

Enclosure:

Final SE (Proprietary)

OFFICIAL USE ONLY - PROPRIETARY INFORMATION

ML20134M479 (Package)

ML20134M356 (Letter)

ML20134M168 (Final SE) *via e-mail OFFICE NRR/DORL/LLPB/PM NRR/DORL/LLPB/LA NRR/DNLR/NVIB/BC NRR/DORL/LLPB/BC NAME LFields DHarrison* HGonzalez* DMorey*

DATE 05/21/2020 05/21/2020 05/26/2020 05/26/2020