NG-15-0293, Submittal of 10 CFR 50.46 Annual Report of Chanqes in Peak Claddinq Temperature

Submittal of 10 CFR 50.46 Annual Report of Chanqes in Peak Claddinq Temperature

ML15271A162
Person / Time
Site:	Duane Arnold
Issue date:	09/23/2015
From:	Vehec T NextEra Energy Duane Arnold
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NG-15-0293
Download: ML15271A162 (3)

Text

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September 23, 2015 NG-1 5-0293 10 CFR 50.46(a)(3)(ii)

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Duane Arnold Energy Center Docket 50-331 Renewed Op. License No. DPR-49 10 CFR 50.46 Annual Report of Chanqes in Peak Claddinq Temperature for the Duane Arnold Energy Center

Reference:

Letter from T. A. Vehec (NextEra Energy Duane Arnold) to USNRC, "10 CFR 50.46 Annual Report of Changes in Peak Cladding Temperature for the Duane Arnold Energy Center," NG-14-0219, dated September 18, 2014 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 GEl4 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, 2015.

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.

ttrcontains 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, USNRC Senior Resident Inspector, DAEC, USNRC NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA52324

Enclosure 1 to NG-1 5-0293 September 23, 2015.

10 CFR 50.46 ANNUAL REPORT DAEC - 2015 GEI4 Fuel Peak Cladding Temperature( 1 )

Last Acceptable Model Results( 2 ): 151 0°F Previously Reported Errors and Changes:

2001 - 2014(3): +135°F New Errors and Changes: None Analysis of Record Results: 1645°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.

Enclosure 2 to NG-l15-0293 September 23, 2015 10 CFR 50.46 ANNUAL REPORT DAEC - 2015 GNF2 Fuel Peak Cladding Temperature(1)(2 )

Last Acceptable Model Results* : 1730°F Previously Reported Errors and Changes:

2012 - 2014(4): +10°F New Errors and Changes: None Analysis of Record Results: 1740°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-R0, "Duane Arnold Energy Center GNF2 ECCS-LOCA Evaluation," August 2012.

(4) Evaluations of each reported error have concluded that re-analysis was not required.