ML13261A293: Difference between revisions

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{{Adams
#REDIRECT [[BSEP 13-0100, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors]]
| number = ML13261A293
| issue date = 09/05/2013
| title = Brunswick, Units 1 and 2 - Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors
| author name = Pope A H
| author affiliation = Duke Energy Progress, Inc
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000324, 05000325
| license number = DPR-062, DPR-071
| contact person =
| case reference number = BSEP 13-0100
| document type = Annual Report, Letter
| page count = 4
}}
 
=Text=
{{#Wiki_filter:@DUKE ENERGY, Brunswick Nuclear Plant 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:==
 
==Reference:==
 
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 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 criteria for emergency core cooling systems for light-water nuclear power 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: Report Revision Date: Current Operating Cycles: Evaluation Model: Fuel: Brunswick Steam Electric Plant, Units 1 and 2 August 5, 2013 Unit 1 -Cycle 19 Unit 2 -Cycle 21 EMF-2361(P)(A), Revision 0 EXEM BWR-2000 ECCS Evaluation Model, May 2001.ATRIUM-10 (A10)Net Absolute PCT Effect PCT Effect A. Cumulative 10 CFR 50.46 Changes and Error +1 0 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&deg;F 1&deg;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&deg;F A10 1904 0 F +1 0 F 1905 0 F Yes Enclosure BSEP 13-0100 Page 2 of 2 Plant: Report Revision Date: Current Operating Cycles: Evaluation Model: Fuel: Brunswick Steam Electric Plant (BSEP), Units 1 and 2 August 5, 2013 Unit 1 -Cycle 19 Unit 2 -Cycle 21 EMF-2361(P)(A), Revision 0 EXEM BWR-2000 ECCS Evaluation Model, May 2001.ATRIUM 1OXM (A10XM)Net Absolute PCT Effect PCT Effect A. Cumulative 10 CFR 50.46 Changes and Error 0&deg;F 0&deg;F Corrections
-Previously Reported B. 10 CFR 50.46 Changes and Error Corrections
-This Reporting Period N one ......C. Absolute Sum of 10 CFR 50.46 Changes and Error 0&deg;F 0&deg;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&deg;F A1OXM 1871&deg;F 0&deg;F 1871&deg;F Yes}}

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