3F1211-14, Summary of Changes to Evaluation Models and Peak Cladding Temperature for Large Break Loss of Coolant Analysis and Small Break Loss of Coolant Analysis

Summary of Changes to Evaluation Models and Peak Cladding Temperature for Large Break Loss of Coolant Analysis and Small Break Loss of Coolant Analysis

ML11354A095
Person / Time
Site:	Crystal River
Issue date:	12/14/2011
From:	Swartz J Progress Energy Florida
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
3F1211-14
Download: ML11354A095 (3)

Text

Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: 10CFR50.46 December 14, 2011 3F1211-14 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, 3F 1210-04, dated December 3, 2010, "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, Jeffrey Swartz Director - Site Operions Crystal River Nuclear Plant JS/par

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 (yr)ý Progress Energy Florida, Inc.

Crystal River Nuclear Plant 15760 W. Power Line Street Crystal River, FL 34428

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 3F1211-14 Page 1 of I 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 by letter dated December 3, 2010. Current PCT results for Small Break (SB) and Large Break (LB)

Loss of Coolant Accidents (LOCAs) are provided in the following tables.

2011 Annual Report CR-3 LB LOCA PCT Change Summary Full Core of Mark-B-HTP Assemblies Delta PCT PCT Previously Reported PCT N/A 1994 0 F (10 CFR 50.46 Notification dated December 3, 2010)

Cumulative Change 0 Sum of absolute magnitude of changes 0 2011 Annual Report CR-3 SB LOCA PCT Change Summary Full Core of Mark-B-HTP Assemblies Delta PCT PCT Previously Reported PCT N/A 1535 0 F (10 CFR 50.46 Notification dated December 3, 2010)

Cumulative Change 0 Sum of absolute magnitude of changes 0