ML19226A259

Draft Safety Evaluation for Pressurized Water Reactor Owners Group Topical Report PWROG-17090-NP, Revision 0 Generic Rotterdam Forging and Weld Initial Upper-Shelf Energy Determination Pressurized Water Reactor Owners Group Westinghouse Ele

ML19226A259
Person / Time
Site:	99902037
Issue date:	09/11/2019
From:	Dennis Morey NRC/NRR/DLP/PLPB
To:	Nowinowski W Westinghouse
Drake J, NRR/DLP, 415-8378
Shared Package
ML19226A255 -Pkg.	List: ML19226A259 ML19226A263
References
EPID L-2018-TOP-0017, PWROG-17090-NP, Rev. 0
Download: ML19226A259 (3)

Text

September 11, 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 FOR PRESSURIZED WATER REACTOR OWNERS GROUP TOPICAL REPORT PWROG-17090-NP, REVISION 0, GENERIC ROTTERDAM FORGING AND WELD INITIAL UPPER-SHELF ENERGY DETERMINATION (EPID: L-2018-TOP-0017)

Dear Mr. Nowinowski:

By letter dated April 6, 2018 (Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML18114A173), the Pressurized Water Reactor (PWR)

Owners Group (PWROG) submitted Topical Report (TR) PWROG-17090-NP, Revision (Rev.) 0, Generic Rotterdam Forging and Weld Initial Upper-Shelf Energy Determination for U.S.

Nuclear Regulatory Commission (NRC) review and approval. Additional information related to PWROG-17090-NP, Rev. 0 was submitted by letter dated June 12, 2019 (ADAMS Accession No. ML19170A06), in response to a request for additional information from the NRC staff.

The NRC staff has reviewed the PWROG-17090-NP, Rev. 0 report and has determined that the report is acceptable for providing conservative estimates of generic unirradiated Charpy Upper-Shelf Energy (USE) for SA508, Class 2 forgings in Rotterdam reactor vessels (RVs); and conservative estimates of generic unirradiated Charpy USE, copper (Cu) content, and nickel (Ni) content for Rotterdam Submerged Arc Welds and Shielded Metal Arc Welds based on the material classes specified in the TR. When measured values of unirradiated Charpy USE, Cu content, and/or Ni content are available for the specific RV materials under consideration, the measured values should be used.

The NRC staffs review has concluded that when measured values of unirradiated Charpy USE, Cu content, and/or Ni content are not available for the plant-specific Rotterdam RV materials under consideration, the generic values for the Rotterdam RV material classes identified in the TR may be used in PWR plant licensing applications for addressing regulatory requirements in Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix G; 10 CFR 50.61 or 50.61a; and/or Time-Limited Aging Analyses requirements in 10 CFR 54.21(c)(1).

Twenty working days are provided for you to comment on any factual errors or clarity concerns contained in the safety evaluation (SE). The final SE will be issued and will be made publicly available after making any necessary changes. The NRC staff's disposition of your comments on the draft SE will be discussed in the final SE.

W. Anthony Nowinowski 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.

If you have any questions, please contact Jason Drake at 301-415-8378.

Sincerely,

/RA/

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

Enclosure:

Draft SE

ML19226A255 Pkg.

ML19226A259 Letter ML19226A263 Draft Enclosure *concurrence via email NRR-106 OFFICE NRR/DLP/PLPB/PM NRR/DLP/PLPB/LA* NRR/DMLR/MVIB/BC NRR/DLP/PLPB/BC NAME JDrake DHarrison DAlley DMorey DATE 8/14/2019 9/3/2019 9/6/2019 9/11/2019