HNP-12-065, CFR 50.46 Annual Report of Changes to LOCA Analyses

CFR 50.46 Annual Report of Changes to LOCA Analyses

ML12151A253
Person / Time
Site:	Harris
Issue date:	05/30/2012
From:	Corlett D Progress Energy Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
HNP-12-065
Download: ML12151A253 (3)

Text

~

Progress ne y May 30, 2012 Serial: HNP-12-065 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400 I Renewed Facility Operating License No. NPF-63 David H. Corlett Supervisor, Licensing/Regulatory Programs Harris Nuclear Plant Progress Energy Carolinas, Inc.

10 CFR 50.46

Subject:

10 CFR 50.46 Annual Report of Changes to LOCA Analyses Ladies and Gentlemen:

In accordance with 10 CFR 50.46(a)(3)(ii), Carolina Power & Light Company, doing business as Progress Energy Carolinas, Inc., hereby submits the annual report of changes to and errors discovered in the Loss of Coolant Accident (LOCA) analyses for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP) for the period May 23,2011, through May 22,2012.

The previous HNP 10 CFR 50.46 annual report to the NRC, dated May 23,2011 (Serial: HNP-11-046), documented a Small Break LOCA Peak Cladding Temperature (PCT) of 1594°F and a Large Break LOCA PCT of2081 OF. For this reporting period, there have been no errors or changes in the LOCA analyses and the results stand as previously reported. The 10 CFR 50.46 annual report is enclosed.

This document contains no regulatory commitments. Please refer any questions regarding this submittal to me at (919) 362-3137.

Sincerely,

Enclosure:

10 CFR 50.46 Annual Report of Changes to LOCA Analyses cc:

Mr. 1. D. Austin, NRC Sr. Resident Inspector, HNP Ms. A. T. Billoch Colon, NRC Project Manager, HNP Mr. V. M. McCree, NRC Regional Administrator, Region II P.O. Box 165 New Hill, NC 27562 T> 919.362.3137

HNP-12-065 Enclosure Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400 / Renewed Facility Operating License No. NPF-63 10 CFR 50.46 Annual Report of Changes to LOCA Analyses

U.S. Nuclear Regulatory Commission Page 1 of 1 HNP-12-065 Enclosure Shearon Harris Nuclear Power Plant, Unit 1 10 CFR 50.46 Annual Report of Changes to LOCA Analyses Reporting Period May 23, 2011, through May 22, 2012 Small Break Loss of Coolant Accident (SBLOCA) Analysis Peak Cladding Temperature Evaluation Model: XN-NF-82-49(P)(A), Revision 1 Supplement 1, Exxon Nuclear Company Evaluation Model Revised EXEM PWR Small Break Model, Siemens Power Corporation, December 1994.

SBLOCA Peak Cladding Temperature (PCT) reported May 23, 2011 1594 °F Changes during reporting period None Errors during reporting period None Total PCT change during reporting period PCT = 0 °F End of Reporting Period SBLOCA PCT 1594 °F Large Break Loss of Coolant Accident (LBLOCA) Analysis Peak Cladding Temperature Evaluation Model: EMF-2087(P)(A), SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications, Siemens Power Corporation, June 1999.

LBLOCA Peak Cladding Temperature reported May 23, 2011 2081 °F Changes during reporting period None Errors during reporting period None Total PCT change during reporting period PCT = 0 °F End of Reporting Period LBLOCA PCT 2081 °F