BSEP 14-0101, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors

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

ML14261A092
Person / Time
Site:	Brunswick
Issue date:	09/04/2014
From:	Pope A Duke Energy Progress
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 14-0101
Download: ML14261A092 (4)

Text

Brunswick Nuclear Plant P.O. Box 10429 ENERGY. Southport, NC 28461 SEP 6 4 2014 10 CFR 50.46(a)(3)(ii)

Serial: BSEP 14-0101 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 (Duke Energy Progress, Inc.) to the USNRC, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors,dated September 5, 2013, ADAMS Accession Number ML13261A293 Ladies and Gentlemen:

In accordance with 10 CFR 50.46, Acceptance criteriafor emergency core cooling systems for light-waternuclear power reactors, paragraph (a)(3)(ii), Duke Energy Progress, Inc., 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 6, 2013, through August 5, 2014.

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

No regulatory commitments are contained in this letter. Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager - Regulatory Affairs, at (910) 457-2487.

Sincerely, Anne te H. Pope Director - Organizational Effectiveness Brunswick Steam Electric Plant

U.S. Nuclear Regulatory Commission Page 2 of 2 MAT/mat

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. Andrew Hon (Mail Stop OWFN 8G9A) (Electronic Copy Only) 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

BSEP 14-0101 Enclosure 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, 2014 Current Operating Cycles: Unit 1 - Cycle 20 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 None C. Absolute Sum of 10 CFR 50.46 Changes and Error +10 F 1IF 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°F +1 0 F 1905°F Yes

BSEP 14-0101 Enclosure Page 2 of 2 10 CFR 50.46 Report for Brunswick Units 1 and 2 Plant: Brunswick Steam Electric Plant (BSEP), Units 1 and 2 Report Revision Date: August 5, 2014 Current Operating Cycles: Unit 1 - Cycle 20 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

1. LOCA re-analysis establishing a new licensing basis PCT of 1878°F (

Reference:

AREVA Report ANP-2943(P), Revision 1)

2. Implementation of ACE correlation in RELAX error +20 F 20F

(

Reference:

AREVA Report FS1-0015388, Revision 1)

C, Absolute Sum of 10 CFR 50.46 Changes and Error +2 0 F 20F Corrections (based on licensing basis PCT of 1878°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 A1OXM 1878 0 F +20 F 1880°F Yes