BSEP 12-0100, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors

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

ML12298A357
Person / Time
Site:	Brunswick
Issue date:	09/10/2012
From:	Pope A Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 12-0100
Download: ML12298A357 (5)

Text

Duke Energ~y 10 CFR 50.46(a)(3)(ii)

SEP 10 2012 Serial: BSEP 12-0100 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Docket Nos. 50-325, 50-324 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors

Reference:

1. Letter from Phyllis N. Mentel (CP&L) to the Nuclear Regulatory Commission, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors, dated September 13, 2011, ADAMS Accession Number ML11263A099 In accordance with 10 CFR 50.46, Acceptance criteriafor emergency core cooling systems for light-waternuclearpower reactors, paragraph (a)(3)(ii), 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.

BSEP Unit 1 employs a mixed core design containing co-resident AREVA ATRIUM-10 and ATRIUM 1OXM fuel; BSEP Unit 2 employs a mixed core design containing co-resident AREVA ATRIUM-10 and ATRIUM 1OXM fuel, and Global Nuclear Fuel (GNF) fuel. Because the GNF fuel is now a non-limiting fuel type, model changes and errors are not being reported for the GNF fuel.

The enclosed report covers the period from August 26, 2011, through August 9, 2012. The reported estimated licensing basis peak cladding temperature (PCT) remains within the acceptance criteria set forth in 10 CFR 50.46 (i.e., < 22000 F).

This document contains no regulatory commitments.

U.S. Nuclear Regulatory Commission Page 2 of 3 Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager - Regulatory Affairs, at (910) 457-2487.

Sincerely, Annette H. Pope Manager - Organizational Effectiveness Brunswick Steam Electric Plant WRM/wrm

Enclosure:

10 CFR 50.46 Report for Brunswick Units 1 and 2

U.S. Nuclear Regulatory Commission Page 3 of 3 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: Ms. Michelle P. Catts, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)

ATTN: Mrs. Farideh E. Saba (Mail Stop OWFN 8G9A) 11555 Rockville Pike Rockville, MD 20852-2738 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510

Enclosure to BSEP 12-0100 Page 1 of 2 10 CFR 50.46 Report for Brunswick Units 1 and 2 Plant: Brunswick Steam Electric Plant, Units 1 and 2 Report Revision Date: August 9, 2012 Current Operating Cycles: Unit 1 - Cycle 19, Unit 2 - Cycle 20 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 Thermal Conductivity Degradation 0°F 0°F C. Absolute Sum of 10 CFR 50.46 Changes and Error +10 F 1IF Corrections (based on licensing basis PCT of 19040 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°F +1 OF 1905°F Yes

Enclosure to BSEP 12-0100 , Page 2 of 2 Plant: Brunswick Steam Electric Plant (BSEP), Units 1 and 2 Report Revision Date: August 9, 2012 Current Operating Cycles: Unit 1 - Cycle 19, Unit 2 - Cycle 20 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 Thermal Conductivity Degradation 0°F 0°F C. Absolute Sum of 10 CFR 50.46 Changes and Error 0°F 0°F Corrections (based on licensing basis PCT of 1871OF)

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 A10XM 1871°F 0°F 1871°F Yes