NG-12-0384, CFR 50.46 Annual Report of Changes in Peak Cladding Temperature

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CFR 50.46 Annual Report of Changes in Peak Cladding Temperature
ML12272A357
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 09/28/2012
From: Richard Anderson
NextEra Energy Duane Arnold
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NG-12-0384
Download: ML12272A357 (3)


Text

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~ DUANE ARNOLD September 28,2012 NG-12-0384 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 Changes in Peak Cladding Temperature for the Duane Arnold Energy Center

Reference:

Letter from P. Wells (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-11-0350, dated September 30, 2011.

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 fuel currently utilized at the Duane Arnold Energy Center (DAEC). This report covers the period from the last annual report (Reference) through August 31, 2012.

Our fuel vendor has notified NextEra Energy Duane Arnold that no changes or errors in the current Loss-of-Coolant Accident (LOCA) analysis methodology have occurred subsequent to those reported in the referenced letter. Enclosure 1 to this letter is a historical summary of previously reported errors for the GE14 fuel.

NextEra Energy Duane Arnold will be introducing a new fuel type, GNF2, manufactured by Global Nuclear Fuels (GNF), as part of the core reload for Cycle 24, planned .for fall 2012. As part of the evaluation associated with the introduction of this new fuel type, GNF performed a new LOCA analysis of the DAEC utilizing the GNF2 fuel design. All previously identified errors in the evaluation model for GE14 were addressed as part of the new GNF2 analysis. Consequently, there are no known errors in the evaluation model associated with this new analysis of the GNF2 fuel. However, the GNF2 analysis does utilize a change in evaluation model from that previously used. The new analysis is based upon the GNF fuel thermal-mechanical model - PRIME, which is NRC approved for this application.

Enclosure 2 to this letter contains the new baseline PCT for the GNF2 fuel.

This letter contains no new commitments or changes to any previous commitments.

Vice President, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC Enclosures NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA 52324

Enclosure 1 to NG-12-0384 September 28, 2012 10 CFR 50.46 ANNUAL REPORT DAEC - 2012 GE14 Fuel Peak Cladding Temperature(1)

Last Acceptable Model Results(2): 1510°F Previously Reported Errors and Changes:

2001 - 2011(3): +115°F New Errors and Changes: 0°F Analysis of Record Results: 1625°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 III - 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-12-0384 September 28, 2012 10 CFR 50.46 ANNUAL REPORT DAEC - 2012 GNF2 Fuel Peak Cladding Temperature(1)(2)

Last Acceptable Model Results(3): 1730°F Previously Reported Errors and Changes: None - New Fuel Introduction New Errors and Changes: 0°F Analysis of Record Results: 1730°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 III - 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.