L-2017-145, CFR 50.46 30-Day Special Report of Changes in Peak Cladding Temperature

CFR 50.46 30-Day Special Report of Changes in Peak Cladding Temperature

ML17242A024
Person / Time
Site:	Duane Arnold
Issue date:	08/28/2017
From:	Larry Nicholson Florida Power & Light Co, NextEra Energy Duane Arnold
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2017-145
Download: ML17242A024 (3)

Text

AUG 2 8 2017 L-2017-145 10 CFR 50.46(a)(3)(ii)

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 NextEra Energy Duane Arnold, LLC Duane Arnold Energy Center Docket No. 50-331

Subject:

10 CFR 50.46 30-Day Special Report of Changes in Peak Cladding Temperature for the Duane Arnold Energy Center

References:

(1) Letter from L. Nicholson (Florida Power & Light Company) to USNRC, "10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications," L-2017-014, April 17, 2017.

(2) Letter from L. Nicholson (Florida Power & Light Company) to USNRC, "10 CFR 50.46 30-Day Special Report of Changes in Peak Cladding Temperature for the Duane Arnold Energy Center," L-2017-118, June 28, 2017.

In accordance with 10 CFR 50.46(a)(3)(ii), Florida Power & Light acting as agent for NextEra Energy Duane Arnold, LLC (NextEra), hereby provides this 30-day special report regarding changes in the calculated peak cladding temperature (PCT) of the GNF2 fuel design currently utilized at the Duane Arnold Energy Center (DAEC).

Our fuel vendor, Global Nuclear Fuels (GNF), has notified NextEra of an evaluation model change in the DAEC Loss-of-Coolant Accident (LOCA) analysis. This new change, when combined (sum of the absolute magnitudes) with all the applicable* PCT changes previously reported for the GNF2 fuel design, results in a cumulative PCT change for DAEC of greater than the 50 °F reporting threshold under 10 CFR 50.46(a)(3)(i). The change in the evaluation model would result in no change to the pellet cladding temperature (PCT), meaning that this change would not have any impact on analysis margin, which is more than 450 °F below the regulatory limit of 2200 °F. Accordingly, a schedule for re-analysis for GNF2 fuel design is not required.

PCT effect is reported as O °F.

Florida Power & Light Company 700 Universe Boulevard, Juno Beach, FL 33408

• L-2017-145 Page 2 of2 Enclosed is a summary rack-up of changes or errors for GNF2 fuel for the 30-day report to NRC.

This submittal contains no new commitments or revisions to existing commitments.

S;;:ly,$L Lar~ Nicholson Director, Nuclear Licensing and Regulatory Compliance Enclosure (1) cc: Administrator, Region Ill, USNRC Project Manager, Duane Arnold Energy Center, USNRC Resident l_nspector, Duane Arnold Energy Center, USNRC

L-2017-145

• ~ Enclosure 1

'* ,

• Page 1 of 1 Enclosure 1 Summary Rack-Up Sheet GNF2 Fuel LOCA Margin Summary Sheet - 30 Day Report Plant Name: Duane Arnold Energy Center Utility name: NextEra Energy Evaluation Model: GE Hitachi Report, "Duane Arnold Energy Center GNF2 ECCS-LOCA Evaluation," GNF Report 0000-0133-6901-RO, ORF 0000-0133-6885-RO, August 2012 Last Acceptable Evaluation Model Analyzed PCT: 1730 °F Net PCT Absolute PCT Effect Effect Prior 10 CPR 50.46 Changes or 10 op A L1PCT 50 °P Error Corrections - up to Year N-1 Prior 10 CPR 50.46 Changes or B L1PCT -20 °P 20 °P Errors Corrections - Year N c Current 10 CPR 50.46 Changes

1. Impact of new inputs for fuel rod 0 op 0 op L1PCT plenum temperature modeling Absolute Sum of 10 CPR 50.46 L1PCT -10 °P 70 °P Changes The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates ofPCT 1720 °P < 2200 °P impact for changes and errors identified since this analysis