3F1209-11, 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

ML093560078
Person / Time
Site:	Crystal River
Issue date:	12/16/2009
From:	Cahill S Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
3F1209-11
Download: ML093560078 (3)

Text

CProgress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: 10CFR50.46 December 16, 2009 3F1209-11 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, dated December 11, 2008, "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 (FPC), doing business as Progress Energy Florida, Inc., is providing the attached information pursuant to 10 CFR 50.46(a)(3)(ii). There have been no changes to the peak cladding temperature (PCT) for Crystal River Unit 3 since the last report was submitted in the above referenced letter. Tables stating the PCT for large break and small break loss-of-coolant accidents (LBLOCA and SBLOCA, respectively) are included in the attachment.

No new regulatory commitments are made in this letter.

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

Sincerely, Stephen J. Cahill Manager Engineering Crystal River Nuclear Plant SJC/pdk

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 Progress Energy Florida, Inc.

Crystal River Nuclear Plant 15760 W. Power Line Street 0ý Crystal River, FL 34428 Orr-

Progress Energy Florida, Inc.

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 3F1209-11 Page 1 of 1 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), doing business as Progress Energy Florida, Inc., is providing the following information pursuant to 10 CFR 50.46(a)(3)(ii). No changes to the Evaluation Model or Peak Cladding Temperature (PCT) have occurred since FPC provided the last report in December 2008. Current PCT results for Small Break (SB) and Large Break (LB) Loss of Coolant Accidents (LOCAs) are provided in the following tables.

2009 Annual Report CR-3 LB LOCA PCT Change Summary Cycle 16 Full Core of Mark-B-HTP Assemblies Delta PCT PCT Previously Reported PCT N/A 1994 0F (2008 Change Report dated December 11,2008)

Changes or Errors since last report None 1994 0 F Cumulative Change 0 Sum of absolute magnitude of changes 0 2009 Annual Report CR-3 SB LOCA PCT Change Summary Cycle 16 Full Core of Mark-B-HTP Assemblies Delta PCT PCT Previously Reported PCT N/A 1248 0 F (2008 Change Report dated December 11, 2008)

Changes or Errors since last report None 1248 0 F Cumulative Change 0 Sum of absolute magnitude of changes 1 0