BSEP 13-0100, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors

Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors

ML13261A293
Person / Time
Site:	Brunswick
Issue date:	09/05/2013
From:	Pope A Duke Energy Progress
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 13-0100
Download: ML13261A293 (4)

Text

Brunswick Nuclear Plant

@DUKE ENERGY, P.O. Box 10429 Southport, NC 28461 SEP 0 5 2013 Serial: BSEP 13-0100 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 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors

Reference:

Letter from Annette H. Pope (CP&L) to the Nuclear Regulatory Commission, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors,dated September 10, 2012, ADAMS Accession Number ML12298A357 Ladies and Gentlemen:

In accordance with 10 CFR 50.46, Acceptance criteriafor emergency core cooling systems for light-waternuclearpower reactors,paragraph (a)(3)(ii), Duke Energy Progress, Inc., formerly known as Carolina Power & Light Company (CP&L), is submitting the annual report of the emergency core cooling system (ECCS) evaluation model changes and errors for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2. The enclosed report covers the period from August 10, 2012, through August 5, 2013.

Both BSEP units employ a mixed core design containing co-resident AREVA ATRIUM-10 and ATRIUM 1OXM fuel.

This document contains no regulatory commitments.

Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager - Regulatory Affairs, at (910) 457-2487.

Sincerely, Annbtte H. Pope Manager - Organizational Effectiveness Brunswick Steam Electric Plant KULa

U.S. Nuclear Regulatory Commission Page 2 of 2 WRM/wrm

Enclosure:

10 CFR 50.46 Report for Brunswick Units 1 and 2 cc (with enclosure):

U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Victor M. McCree, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission ATTN: Mr. Christopher Gratton (Mail Stop OWFN 8G9A) 11555 Rockville Pike Rockville, MD 20852-2738 U. S. Nuclear Regulatory Commission ATTN: Ms. Michelle P. Catts, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510

Enclosure BSEP 13-0100 Page 1 of 2 10 CFR 50.46 Report for Brunswick Units I and 2 Plant: Brunswick Steam Electric Plant, Units 1 and 2 Report Revision Date: August 5, 2013 Current Operating Cycles: Unit 1 - Cycle 19 Unit 2 - Cycle 21 Evaluation Model: EMF-2361(P)(A), Revision 0 EXEM BWR-2000 ECCS Evaluation Model, May 2001.

Fuel: ATRIUM-10 (A10)

Net Absolute PCT Effect PCT Effect A. Cumulative 10 CFR 50.46 Changes and Error +10 F 1IF Corrections - Previously Reported B. 10 CFR 50.46 Changes and Error Corrections - This Reporting Period N o ne ......

C. Absolute Sum of 10 CFR 50.46 Changes and Error +1°F 1°F Corrections (based on licensing basis PCT of 1904 0 F)

D. Evaluated Effective Licensing Basis PCT including Changes and Error Corrections Licensing Cumulative Basis Incremental Estimated Estimated PCT Fuel Type PCT Change in PCT PCT < 2200°F A10 1904 0 F +10 F 1905 0 F Yes

Enclosure BSEP 13-0100 Page 2 of 2 Plant: Brunswick Steam Electric Plant (BSEP), Units 1 and 2 Report Revision Date: August 5, 2013 Current Operating Cycles: Unit 1 -Cycle 19 Unit 2 - Cycle 21 Evaluation Model: EMF-2361(P)(A), Revision 0 EXEM BWR-2000 ECCS Evaluation Model, May 2001.

Fuel: ATRIUM 1OXM (A10XM)

Net Absolute PCT Effect PCT Effect A. Cumulative 10 CFR 50.46 Changes and Error 0°F 0°F Corrections - Previously Reported B. 10 CFR 50.46 Changes and Error Corrections - This Reporting Period None ......

C. Absolute Sum of 10 CFR 50.46 Changes and Error 0°F 0°F Corrections (based on licensing basis PCT of 1871 OF)

D. Evaluated Effective Licensing Basis PCT including Changes and Error Corrections Licensing Cumulative Basis Incremental Estimated Estimated PCT Fuel Type PCT Change in PCT PCT < 2200°F A1OXM 1871°F 0°F 1871°F Yes