3F0910-01, CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss of Coolant Accident Analysis

CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss of Coolant Accident Analysis

ML102530447
Person / Time
Site:	Crystal River
Issue date:	09/08/2010
From:	Cahill S Progress Energy Florida
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
3F0910-01
Download: ML102530447 (4)

Text

RC Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: 10CFR50.46 September 8, 2010 3F0910-01 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Crystal River Unit 3 - 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss Of Coolant Accident Analysis

Reference:

Crystal River Unit 3 to NRC letter, 3F1209-13, dated December 30, 2009, "Crystal River Unit 3 - 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss of Coolant Accident Analyses"

Dear Sir:

Pursuant to 10 CFR 50.46(a)(3)(ii), Florida Power Corporation (FPC), doing business as Progress Energy Florida, Inc., hereby provides notification of a change in peak clad temperature (PCT) of greater than 50 degrees Fahrenheit (OF) in the Crystal River Unit 3 (CR-3) Small Break Loss of Coolant Accident (SBLOCA) analysis.

This notification is due to an estimated adjustment that results in a significant change, by 2250F, to the PCT for the SBLOCA analysis reposted in the above referenced submittal. The new PCT is 1535'F for the upcoming Cycle 17 SBLOCA analysis.

The Large Break Loss of Coolant Accident (LBLOCA) PCT continues to remain at 1994°F. Additional details are provided in the attachment to this letter. The resulting maximum PCT for both analyses remains within the 2200'F limit of 10 CFR 50.46.

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.

Sincerely,"A/;

Step en J. Cahill K,

Director Engineering Nuc ear 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 Crystal River, FL 34428 r

~

Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 September 8, 2010 3F0910-01 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Ref: 10CFR50.46

Subject:

Crystal River Unit 3 - 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss Of Coolant Accident Analysis

Dear Sir:

Crystal River Unit 3 to NRC letter, 3FI209-13, dated December 30, 2009, "Crystal River Unit 3 - 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss of Coolant Accident Analyses" Pursuant to 10 CFR 50.46(a)(3)(ii), Florida Power Corporation (FPC), doing business as Progress Energy Florida, Inc., hereby provides notification of a change in peak clad temperature (PCT) of greater than 50 degrees Fahrenheit (OP) in the Crystal River Unit 3 (CR-3) Small Break Loss of Coolant Accident (SBLOCA) analysis.

This notification is due to an estimated adjustment that results in a significant change, by 225°P, to the PCT for the SBLOCA analysis reposted in the above referenced submittal. The new PCT is 1535°F for the upcoming Cycle 17 SBLOCA analysis. The Large Break Loss of Coolant Accident (LBLOCA) PCT continues to remain at 1994°F. Additional details are provided in the attachment to this letter. The resulting maximum PCT for both analyses remains within the 2200°F limit of 10 CFR 50.46.

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.

Sinc(3;U~)~ k-r ~CaklJ Ste~?:;~ill Director Engineering Nuc ear 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 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

/',

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 3F0910-01 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 Pursuant to 10 CFR 50.46(a)(3)(ii), Florida Power Corporation (FPC), doing business as Progress Energy Florida, Inc., hereby provides notification of a change in peak clad temperature (PCT) of greater than 50 degrees Fahrenheit (OF) in the Crystal River Unit 3 (CR-3) Small Break Loss of Coolant Accident (SBLOCA) analysis.

Reference 1 below describes an error correction that resulted in a significant change to. the PCT for the Cycle 17 SBLOCA analysis. AREVA found that the Axial Power Shape used in the SBLOCA analysis was not the worst power shape that could be attained by the CR-3 reactor core. A bounding End of Cycle axial power shape was generated, resulting in a higher PCT than reported in Reference 2. This was documented in the CR-3 Corrective Action Program under Nuclear Condition Report (NCR) 415689 and in AREVA CR (Condition Report) 2010-4150.

This results in a SBLOCA PCT change to 1535°F and no change for the Large Break Loss of Coolant Accident (LBLOCA) PCT of 1994°F for Cycle 17. Because the PCT of both analyses remains within the 2200'F limit of 10 CFR 50.46, a reanalysis is not required.

REFERENCES

1.

Letter from AREVA to CR-3, AREVA-FAB 10-542, dated August 9, 2010, "10 CFR 50.46 LOCA Report of EM Error Correction (AREVA CR 2010-4150: EOC SBLOCA axial power shape)"

2.

Crystal River Unit 3 to NRC letter, 3F1209-13, dated December 30, 2009, "Crystal River Unit 3 - 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss of Coolant Accident Analyses" U. S. Nuclear Regulatory Commission 3F0910.,01 Attachment Page 1 of2 Summary of Changes to Evaluation Models and Peak Cladding Temperature for Large Break Loss of Coolant Analysis and Small Break Loss of Coolant Analysis Pursuant to 10 CFR 50.46( a)(3 )(ii), Florida Power Corporation (FPC), doing business as Progress Energy Florida, Inc., hereby provides notification of a change in peak clad temperature (PCT) of greater than 50 degrees Fahrenheit caF) in the Crystal River Unit 3 (CR-3) Small Break Loss of Coolant Accident (SBLOCA) analysis.

Reference 1 below describes an error correction that resulted in a significant change to the PCT for the Cycle 17 SBLOCA analysis. AREV A found that the Axial Power Shape used in the SBLOCA analysis was not the worst power shape that could be attained by the CR-3 reactor core. A bounding End of Cycle axial power shape was generated, resulting in a higher PCT than reported in Reference 2. This was documented in the CR-3 Corrective Action Program under Nuclear Condition Report (NCR) 415689 and in AREVA CR (Condition Report) 2010-4150.

This results in a SBLOCA PCT change to 1535°F and no change for the Large Break Loss of Coolant Accident (LBLOCA) PCT of 1994°F for Cycle 17. Because the PCT of both analyses remains within the 2200°F limit of 10 CFR 50.46, a reanalysis is not required.

REFERENCES

1.

Letter from AREVA to CR-3, AREVA-FAB 10-542, dated August 9, 2010, "10 CFR 50.46 LOCA Report of EM Error Correction (AREVA CR 2010-4150: EOC SBLOCA axial power shape)"

2.

Crystal River Unit 3 to NRC letter, 3F1209-13, dated December 30, 2009, "Crystal River Unit 3 - 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss of Coolant Accident Analyses"

U. S. Nuclear Regulatory Commission 3F0910-01 Attachment Page 2 of 2 Cycle 17 Summary The following tables provide the corrected peak clad temperature (PCT) results for Small Break (SB) and Large Break (LB) Loss of Coolant Accidents (LOCAs) for Cycle 17.

CR-3 LB LOCA PCT Change Summary Cycle 17 Full Core of Mark-B-HTP Assemblies Delta PCT PCT Previously Reported PCT N/A 19940F (10 CFR 50.46 Notification dated December 30, 2009)

Cumulative Change 0°F Sum of absolute magnitude of changes 0°F CR-3 SB LOCA PCT Change Summary Cycle 17 Full Core of Mark-B-HTP Assemblies Delta PCT PCT Previously Reported PCT N/A 13 10°F (10 CFR 50.46 Notification dated December 30, 2009)

AREVA CR 2010-4150 and CR-3 NCR 2250F 1535 0F 415689: Analysis changes due to non conservative axial power shape Cumulative Change 2250F Sum of absolute magnitude of changes 2250 F U. S. Nuclear Regulatory Commission 3F091O-01 CyCle 17 Summary Attachment Page 2 of2 The following tables provide the corrected peak clad temperature (PCT) results for Small Break (SB) and Large Break (LB) Loss of Coolant Accidents (LOCAs) for Cycle 17.

CR-3 LB LOCA PCT Change Summary Cycle 17 Full Core ofMark~B-HTP Assemblies Delta PCT PCT Previously Reported PCT N/A 1994°F (10 CFR 50.46 Notification dated December 30, 2009)

Cumulative Change OaF Sum of absolute magnitude of changes OaF CR-3 SB LOCA PCT Change Summary Cycle 17 Full Core of Mark-B-HTP Assemblies Delta PCT PCT Previously Reported PCT N/A 1310°F (10 CFR 50.46 Notification dated December 30, 2009)

AREVA CR 2010-4150 and CR-3 NCR 225°F 1535°F 415689: Analysis changes due to non conservative axial power shape Cumulative Change 225°F Sum of absolute magnitude of changes 225°F