3F1112-03, 10 CFR 50.46 Loss-of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report

10 CFR 50.46 Loss-of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report

ML12326A677
Person / Time
Site:	Crystal River
Issue date:	11/15/2012
From:	Wunderly B Duke Energy Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
3F1112-03
Download: ML12326A677 (4)

Text

Duke EEnergy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: 10CFR50.46 November 15, 2012 3Fl112-03 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Crystal River Unit 3 - 10 CFR 50.46 Loss-of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report

Reference:

Crystal River Unit 3 to NRC letter, 3F1211-14, dated December 14, 2011, "Crystal River Unit 3 - 10 CFR 50.46 Loss-of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report"

Dear Sir:

Florida Power Corporation is providing the attached information pursuant to 10 CFR 50.46(a)(3)(ii). The previous annual report for Crystal River Unit 3 (CR-3) was submitted in the above referenced letter. There has been one change in peak cladding temperature (PCT) of greater than 50 degrees Fahrenheit (OF) in the CR-3 Large Break Loss of Coolant Accident (LBLOCA) analysis since the previous annual report was submitted. Tables stating the PCT for large break and small break loss-of-coolant accidents (LBLOCA and SBLOCA, respectively) are included in the attachment.

This correspondence contains no new regulatory commitments.

If you have any questions regarding this submittal, please contact Mr. Dan Westcott, Superintendent, Licensing and Regulatory Programs at (352) 563-4796.

Siqz~rey, Blair P. Wunderly Director-Engineering-Nuclear Crystal River Nuclear Plant BPW/sam

Attachment:

Summary of Changes to Evaluation Models and Peak Cladding Temperature for Large Break Loss of Coolant Analysis and Small Break Loss of Coolant Analysis xc: NRR Project Manager Regional Administrator, Region II Senior Resident Inspector Crystal River Nuclear Plant 15760 W. Power Line Street Crystal River, FL 34428

FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 Attachment Summary of Changes to Evaluation Models and Peak Cladding Temperature for Large Break Loss of Coolant Analysis and Small Break Loss of Coolant Analysis

U. S. Nuclear Regulatory Commission Attachment 3F1112-03 Page 1 of 2 Summary of Changes to Evaluation Models and Peak Cladding Temperature for Large Break Loss of Coolant Analysis and Small Break Loss of Coolant Analysis Florida Power Corporation (FPC) is providing the following information pursuant to 10 CFR 50.46(a)(3)(ii). One change in peak cladding temperature (PCT) of greater than 50 degrees Fahrenheit (0 F) has occurred in the Large Break (LB) Loss of Coolant Accident (LOCA) analysis since FPC provided the previous annual report by letter dated December 14, 2011 (Reference 1).

The change was identified in a letter from AREVA to Crystal River Unit 3 (CR-3) (Reference 2) and was provided to the NRC by letter dated March 19, 2012 (Reference 3). No other changes in PCT have been identified since the previous CR-3 annual report was submitted by letter dated December 14, 2011 (Reference 1). Current PCT results for Small Break (SB) and Large Break LB LOCAs are provided in the following tables.

REFERENCES

1. CR-3 to NRC letter, 3F1211-14, dated December 14, 2011, "Crystal River Unit 3 - 10 CFR 50.46 Loss-of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report." (Accession No. ML11354A095)

2. Letter from AREVA to CR-3, AREVA-FAB12-110, dated February 21, 2012, "10CFR 50.46 LOCA Report of Two EM Error Corrections (AREVA CR 2012-165: ECCS Bypass Mathematical Error and AREVA CR 2012-757: Upper Plenum Column Weldment EM Change)."

3. CR-3 to NRC letter, 3F0312-04, dated March 19, 2012, "Crystal River Unit 3 - 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Analysis." (Accession No. ML12081A278) 2012 Annual Report F CR-3 LB LOCA PCT Change Summary Full Core of Mark-B-HTP Assemblies Delta PCT PCT Reported PCT for 2011 Annual Report n/a 1994 0 F (Reference 1)

Cumulative Change from previous 0°F Report (Reference 3)

Sum of absolute magnitude of chanies 160°F since previous Annual Report

U. S. Nuclear Regulatory Commission Attachment 3Fl 112-03 Page 2 of 2 2012 Annual Report CR-3 SB LOCA PCT Change Summary Full Core of Mark-B-HTP Assemblies Delta PCT PCT Reported PCT for 2011 Annual Report n/a 1535 0 F (Reference 1)

Cumulative Change 0°F Sum of absolute magnitude of changes 0°F