RA-15-0036, Brunswick Steam Electric Plant, Units 1 and 2 - Annual Report of Changes Pursuant to 10 CFR 50.46: Difference between revisions

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{{Adams
#REDIRECT [[RA-15-0036, Annual Report of Changes Pursuant to 10 CFR 50.46]]
| number = ML15243A180
| issue date = 08/31/2015
| title = Brunswick Steam Electric Plant, Units 1 and 2 - Annual Report of Changes Pursuant to 10 CFR 50.46
| author name = Nolan M C
| 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 = RA-15-0036
| document type = Annual Operating Report, Letter type:RA
| page count = 5
}}
 
=Text=
{{#Wiki_filter:ENERGY GI August 31, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Brunswick Steam Electric Plant, Unit Nos. 1 and 2 M. Chr is topher Nolan 526 Sourh Church Srre e r Clwr/orre, NC 28202 Marling Adtlre ss: Mail Code EC2ZF /P.O. Box 1006 Clwr/orre , NC 28201-1006 704-382-7426 RA-15-0036 10 CFR 50.46 Docket Nos. 50-325 and 50-324 I Renewed License Nos. DPR-71 and DPR-62
 
==Subject:==
Annual Report of Changes Pursuant to 10 CFR 50.46 Pursuant to 10 CFR 50.46(a)(3)(ii), Duke Energy Progress, Inc. hereby submits the enclosed annual report of changes to and errors discovered in the loss of coolant accident analyses for the Brunswick Steam Electric Plant, Unit Nos. 1 and 2, for the period August 6, 2014, through August 5, 2015. Unit 1 employs a mixed core design containing co-resident AREVA ATRIUM-10 and ATRIUM 10XM fuel. Unit 2 employs a core containing AREVA ATRIUM 10XM fuel with eight ATRIUM 11 lead test assemblies (LTAs). This document contains no regulatory commitments.
Please refer any questions regarding this submittal to Art Zaremba at {980) 373-2062.
Sincerely, M. Christopher Nolan Director Nuclear Regulatory Affairs
 
==Enclosure:==
: 1) Annual Report of Changes Pursuant to 10 CFR 50.46 U.S. Nuclear Regulatory Commission August 31, 2015 Page2 xc: V. M. McCree, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, Georgia 30303-1257 Andrew Hon, NRC Project Manager (Electronic Copy Only) U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 Michelle P. Catts NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 Chair -North Carolina Utilities Commission P. 0. Pox 29510 Raleigh, NC 27626-0510 RA-15-0036 Enclosure 1 Page 1 of 3 Plant: Report Revision Date: Current Operating Cycles: Evaluation Model: ENCLOSURE 1 1 0 CFR 50.46 Report for Brunswick Units 1 and 2 Brunswick Steam Electric Plant, Unit 1 August 5, 2015 Unit 1 -Cycle 20 EMF-2361(P)(A), Revision 0 Fuel: EXEM BWR-2000 ECCS Evaluation Model, May 2001 ATRIUM-10 (A10) Net Absolute PCT Effect PCT Effect A. Cumulative 1 0 CFR 50.46 Changes and Error +1°F 1°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 +1°F 1°F Corrections (based on licensing basis PCT of 1904°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 s 2200°F A10 1904°F +1°F 1905°F Yes RA-15-0036 Enclosure 1 Page 2 of 3 Plant: Report Revision Date: Current Operating Cycles: Evaluation Model: 1 0 CFR 50.46 Report for Brunswick Units 1 and 2 Brunswick Steam Electric Plant, Units 1 and 2 August 5, 2015 Unit 1 -Cycle 20 Unit 2 -Cycle 22 EMF-2361 (P)(A), Revision 0 Fuel: EXEM BWR-2000 ECCS Evaluation Model, May 2001 ATRIUM 10XM (A10XM) Net Absolute PCT Effect PCT Effect A. Cumulative 1 0 CFR 50.46 Changes and Error ooF ooF Corrections
-Previously Reported B. 1 0 CFR 50.46 Changes and Error Corrections-This Reporting Period 1. AREVA Report ANP-2943(P), "Brunswick
----Units 1 and 2 LOCA-ECCS Analysis MAPLHGR Limit for ATRIUMŽ 10XM Fuel," Revision 2, October 2014, establishing a new licensing basis PCT of 1882°F 2. Implementation of ACE correlation in RELAX +2°F 2°F error (
 
==Reference:==
 
AREVA Report FS1-0020025, Revision 1.0) 3. Evaluation of the effect of exposure-ooF ooF dependent thermal conductivity degradation (
 
==Reference:==
 
AREVA Report FS1-0020025, Revision 1.0) c. Absolute Sum of 10 CFR 50.46 Changes and Error +2°F 2°F Corrections (based on licensing basis PCT of 1882°F) 0. Evaluated Effective Licensing Basis PCT including Changes and Error Corrections Licensing Cumulative Basis Incremental Estimated Estimated PCT Fuel Type PCT Change in PCT PCT S 2200°F A10XM 1882°F +2°F 1884°F Yes RA-15-0036 Enclosure 1 Page 3 of 3 Plant: Report Revision Date: Current Operating Cycles: Evaluation Model: 1 0 CFR 50.46 Report for Brunswick Units 1 and 2 Brunswick Steam Electric Plant, Unit 2 August 5, 2015 Unit 2 -Cycle 22 EMF-2361 (P)(A), Revision 0 Fuel: EXEM BWR-2000 ECCS Evaluation Model, May 2001 ATRIUM 11 Lead Use Assemblies Net Absolute PCT Effect PCT Effect A. Cumulative 10 CFR 50.46 Changes and Error ooF ooF Corrections
-Previously Reported B. 10 CFR 50.46 Changes and Error Corrections-This Reporting Period 1 ANP-3369(P), " Brunswick Unit 2 Cycle 22 Reload Safety Analysis", Revision 0, January --2015 establishing the licensing basis PCT of 1762°F. c. Absolute Sum of 1 0 CFR 50.46 Changes and Error ooF 0°F Corrections (based on licensing basis PCT of 1762°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 ATRIUM 11 1762°F ooF 1762°F Yes}}

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