RA-19-0380, Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request

Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request

ML19290H551
Person / Time
Site:	Brunswick
Issue date:	10/17/2019
From:	Krakuszeski J Duke Energy Progress
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-19-0380
Download: ML19290H551 (7)

Text

John A. Krakuszeski Vice President Brunswick Nuclear Plant 8470 River Rd SE Southport, NC 28461 o: 910.832.3698 October 17, 2019 Serial: RA-19-0380 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

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 Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request

Reference:

1. Letter from William R. Gideon (Duke Energy) to the U.S. Nuclear Regulatory Commission Document Control Desk, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, dated October 11, 2018, ADAMS Accession Number ML18284A395.

2. NRC E-mail Capture, Request for Additional Information - Brunswick ATRIUM 11 LAR, dated October 9, 2019, ADAMS Accession Number ML19283C829.

3. Letter from Gary Peters (Framatome Inc.) to the U.S. Nuclear Regulatory Commission Document Control Desk, Informational Transmittal of ANP-2637P, Revision 8, "Boiling Water Reactor Licensing Compendium", dated June 5, 2019, ADAMS Accession Number ML19158A093.

Ladies and Gentlemen:

By letter dated October 11, 2018 (i.e., Reference 1), Duke Energy Progress, LLC (Duke Energy), submitted a license amendment request (LAR) for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2. The proposed license amendment revises Technical Specification 5.6.5.b to allow application of Advanced Framatome Methodologies for determining core operating limits in support of loading Framatome fuel type ATRIUM 11.

On October 9, 2019, by electronic mail (i.e., Reference 2), the NRC provided a request for additional information (RAI) regarding the LAR. The subject of this RAI relates to the incorporation of additional conditions on the Best Estimate Enhanced Option-III (BEO-III) and BEO-III with Confirmation Density Algorithm (BEO-III w/CDA) stability methodologies (i.e., ANP-3703P and DPC-NE-1009-P, respectively). Enclosures 1 and 2 contain a markup of Unit 1 and Unit 2 Operating Licenses, respectively, incorporating a proposed License Condition to address the additional conditions from Reference 2.

U.S. Nuclear Regulatory Commission Page 3 of 3 cc (with all Enclosures):

U. S. Nuclear Regulatory Commission, Region II ATTN: Ms. Laura Dudes, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission ATTN: Mr. Gale Smith, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon 11555 Rockville Pike Rockville, MD 20852-2738 Chair - North Carolina Utilities Commission (Electronic Copy Only) 4325 Mail Service Center Raleigh, NC 27699-4300 swatson@ncuc.net Mr. W. Lee Cox, III, Section Chief (Electronic Copy Only)

Radiation Protection Section North Carolina Department of Health and Human Services 1645 Mail Service Center Raleigh, NC 27699-1645 lee.cox@dhhs.nc.gov

RA-19-0380 Enclosure 1 Operating License, Appendix B Mark-Up - Unit 1

Amendment Number Additional Conditions Implementation Date XXX When determining the core operating limits, the Upon implementation of Licensee shall apply the conditions outlined in the Amendment No. XXX.

NRC's Request for Additional Information dated October 9, 2019, when applying ANP-3703P, BEO-III Analysis Methodology for Brunswick Using RAMONA5-FA, and DPC-NE-1009-P, Brunswick Nuclear Plant Implementation of Best-estimate Enhanced Option-III (i.e., Technical Specification 5.6.5.b.19 and 5.6.5.b.22, respectively).

This is a new Unit 1 Page App. B-6 Brunswick Unit 1 App. B-6 Amendment No. 313

RA-19-0380 Enclosure 2 Operating License, Appendix B Mark-Up - Unit 2

Amendment Number Additional Conditions Implementation Date XXX When determining the core operating limits, the Upon implementation of Licensee shall apply the conditions outlined in the Amendment No. XXX.

NRC's Request for Additional Information dated October 9, 2019, when applying ANP-3703P, BEO-III Analysis Methodology for Brunswick Using RAMONA5-FA, and DPC-NE-1009-P, Brunswick Nuclear Plant Implementation of Best-estimate Enhanced Option-III (i.e., Technical Specification 5.6.5.b.19 and 5.6.5.b.22, respectively).

This is a new Unit 2 Page App. B-6 Brunswick Unit 2 App. B-6 Amendment No. 313