RA-20-0359, Supplement to Response for Request for Additional Information for Proposed Alternative for RPV Nozzle-to-Vessel Weld and Inner Radii Examination Requirement

Supplement to Response for Request for Additional Information for Proposed Alternative for RPV Nozzle-to-Vessel Weld and Inner Radii Examination Requirement

ML20322A257
Person / Time
Site:	Brunswick
Issue date:	11/17/2020
From:	Krakuszeski J Duke Energy Progress
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-20-0359
Download: ML20322A257 (2)

Text

John A. Krakuszeski Vice President Brunswick Nuclear Plant 8470 River Rd SE Southport, NC 28461 o: 910.832.3698 Serial: RA-20-0359 10 CFR 50.55(a)

November 17, 2020 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 RENEWED FACILITY OPERATING LICENSE NOS. DPR-71 AND DPR-62 DOCKET NOS. 50-325 AND 50-324

SUBJECT:

Supplement to Response for Request for Additional Information for Proposed Alternative for RPV Nozzle-to-Vessel Weld and Inner Radii Examination Requirements

REFERENCES:

1. Duke Energy Letter RA-19-0447, Proposed Alternative for RPV Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(z)(1),

dated June 23, 2020 (ADAMS Accession Number ML20181A004).

2. Duke Energy Letter RA-20-0247, Supplement to Proposed Alternative for RPV Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(z)(1), dated July 30, 2020 (ADAMS Accession Number ML20212L731).

3. Email from Andy Hon to Art Zaremba, Request for Additional Information - Brunswick Request for Alternate Examination of Reactor Vessel Nozzles (EPID: L-2020-LLR-0091) dated October 1, 2020 (ADAMS Accession Number ML20275A297).

4. Duke Energy Letter RA-20-0324, Response to Request for Additional Information for Proposed Alternative for RPV Nozzle-to-Vessel Weld and Inner Radii Examination Requirements, dated October 27, 2020 (ADMAS Accession Number ML20301A475).

Ladies and Gentlemen:

By letter dated June 23, 2020 (Reference 1), as supplemented by letter dated July 30, 2020 (Reference 2), Duke Energy Progress, LLC. (Duke Energy) submitted Relief Request RA 0447 in accordance with 10 CFR 50.55a(z)(1) to the requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for the Brunswick Steam Electric Plant, Units 1 and 2.

By email dated October 1, 2020, (Reference 3), the NRC requested additional information required to complete its review. Duke Energy provided responses to the requests for additional information by letter dated October 27, 2020 (Reference 4).

U.S. Nuclear Regulatory Commission Page 2 Serial: RA-20-0359 Duke Energy submits this corresondence to clarify that the neutron fluence results as provided in Attachment 1 to letter dated October 27, 2020 (Reference 4) are based on the same model, computer code, and methodology used in WCAP-17660, Revision O without any changes.

This document contains no new Regulatory Commitments.

Should you have any questions concerning this letter, or require additional information, please contact Art Zaremba, Director - Nuclear Fleet Licensing, at 980-373-2062.

Sincerely, John A. Krakuszeski Site Vice President Brunswick Steam Electric Plant cc : L. Dudes, Regional Administrator USNRC Region II Mr. Andrew Hon, Project Manager Mr. Gale Smith, NRC Senior Resident Inspector Chair - North Carolina Utilities Commission Mr. W. Lee Cox, Ill Section Chief, Radiation Protection Section, NC DHHS