NG-16-0203, Duane Arnold Energy Center - 10 CFR 50.46 Annual Report of Changes in Peak Cladding Temperature for the Duane Arnold Energy Center: Difference between revisions

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{{Adams
#REDIRECT [[NG-16-0203, Energy Center - 10 CFR 50.46 Annual Report of Changes in Peak Cladding Temperature for the Duane Arnold Energy Center]]
| number = ML16287A725
| issue date = 10/12/2016
| title = Duane Arnold Energy Center - 10 CFR 50.46 Annual Report of Changes in Peak Cladding Temperature for the Duane Arnold Energy Center
| author name = Vehec T A
| author affiliation = NextEra Energy Duane Arnold, LLC
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000331
| license number = DPR-049
| contact person =
| case reference number = NG-16-0203
| document type = Annual Operating Report, Letter type:NG
| page count = 3
}}
 
=Text=
{{#Wiki_filter:October 12, 2016 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Duane Arnold Energy Center Docket 50-331 Renewed Op. License No. DPR-49 NEXTeraM
:*"" -DUANE ARNOLD-_NG-16-0203 10 CFR 50.46(a)(3)(ii) 10 CFR 50.46 Annual Report of Changes in Peak Cladding Temperature for the Duane Arnold Energy Center  
 
==Reference:==
 
Letter from T. A Vehec (NextEra Energy Duane Arnold) to USN RC, "10 CFR 50.46 Annual Report of Changes in Peak Cladding Temperature for the Duane Arnold-Energy Center," NG-15-0293, dated September 2015 In accordance with 10 CFR 50.46(a)(3)(ii), NextEra Energy Duane Arnold,-LLC (hereafter NextEra Energy Duane Arnold) hereby provides the annual report regarding the changes in the calculated peak cladding temperature (PCT) of the GE14 and GNF2 fuel currently utilized at the Duane Arnold Energy Center (DAEC). This report covers the period from the last annual report (Reference
: 1) through August 31, 2016, Our fuel vendor has notified NextEra Energy Duane Arnold that no changes or errors in the current Loss-of-Coolant Accident analysis methodology have occurred subsequent to the referenced report. Enclosed is a historical summary of previously reported errors. This le ter contains no new commitments or changes to any previous commitments.
T. A Vehec Vice President, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC Enclosures CC: Administrator, Region Ill, USNRC Project Manager, DAEC, USN RC Senior Resident Inspector, DAEC, USNRC NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA 52324 10 CFR 50.46 ANNUAL REPORT DAEC -2016 GE14 Fuel Enclosure 1 to NG-16-0203 October 12, 2016 Peak Cladding Temperature<
1 l Last Acceptable Model Results(2 l: 1510&deg;F Previously Reported Errors and Changes: 2001 -2015<3): +135&deg;F New Errors and Changes: None Analysis of Record Results: 1645&deg;F . (1) Licensing Basis PCT (LBPCT), as defined in NEDE-23785-1-P-A, "The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident:
Volume Ill -SAFER/GESTR Application Methodology," February 1985. . (2) General Electric Report, "Safety Analysis Report for Duane Arnold Energy Center Extended Power Uprate," NEDC-32980P, Revision 1, April 2001. (3) Evaluations of each reported error have concluded that re-analysis was not required.
10 CFR 50.46 ANNUAL REPORT DAEC-2016-GNF2 Fuel Enclosure 2 to NG-16-0203 October 12, 2016 Peak Cladding Temperature<
1><2> Last Acceptable Model Results<3>: 1730&deg;F Previously Reported Errors and Changes: 2012 -2015<4>: +10&deg;F New Errors and Changes: None Analysis of Record Results: 1740&deg;F (1) Licensing Basis PCT (LBPCT), as defined in NEDE-23785-1-P-A, "The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident:
Volume Ill -SAFER/GESTR Application Methodology," February 1985. (2) Licensing Topical Report, Global Nuclear Fuel, "The PRIME Model for Analysis of Fuel Rod Thermal-Mechanical Performance", Technical Bases -NEDC-33256P-A, Qualification
-NEDC-33257P-A, and Application Methodology
-NEDC-33258P-A, September 2010. (3) General Electric-Hitachi (GEH) Engineering Report# 0000-0133-6901-RO, "Duane Arnold Energy Center GNF2 ECCS-LOCA Evaluation," August 2012. * (4) Evaluations of each reported error have concluded that re-analysis was not required.}}

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