RA-15-0022, Annual Report of Changes Pursuant to 10 CFR 50.46

Annual Report of Changes Pursuant to 10 CFR 50.46

ML15134A029
Person / Time
Site:	Harris
Issue date:	05/14/2015
From:	Repko R Duke Energy Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-15-0022
Download: ML15134A029 (4)

Text

Regis T. Repko

(~ DUKE 526 South Church Street Charlotte, NC 28202 ENERGY. Mailing Address:

Mail Code EC07H /P.O. Box 1006 Charlotte, NC 28201 - 1006 704-382-4126 704-382-4541 fax May 14,2015 RA-15-0022 10 CFR 50.46 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 License No. NPF-63

Subject:

Annual Report of Changes Pursuant to 10 CFR 50.46 Pursuant to 10 CFR 50.46(a)(3)(ii), Duke Energy hereby submits the enclosed annual report of changes to and errors discovered in the loss of coolant accident analyses for the Shearon Harris Nuclear Power Plant, Unit 1, for the period April 9, 2014, through April 9, 2015.

This document contains no regulatory commitments. Please refer any questions regarding this submittal to Art Zaremba at (980) 373-2062.

Sincerely, Regis T. Repko Senior Vice President Governance, Projects, and Engineering

Enclosure:

1) Annual Report of Changes Pursuant to 10 CFR 50.46

U.S. Nuclear Regulatory Commission May 14, 2015 Page2 xc:

V. M. McCree, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, Georgia 30303-1257 Martha Barillas, NRC Project Manager, HNP U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 J.D. Austin NRC Senior Resident Inspector, HNP

RA-15-0022 Page 1 of 2 ENCLOSURE 1 Shearon Harris Nuclear Power Plant, Unit 1 Annual Report of Changes Pursuant to 10 CFR 50.46 Reporting Period April9, 2014 through April 9, 2015 Small Break Loss of Coolant Accident (SBLOCA) Analysis The SBLOCA analysis is not impacted during this reporting period.

SBLOCA Peak Cladding Temperature (Pen Summary of Changes ~PCT Resultant (oF) PCT (°F)

Previously reported SBLOCA PCT effective April 9, 2014 1681 Changes during reporting period None 1681 SBLOCA PCT effective April9, 2015 1681 The resultant predicted fuel element PCT, accounting for changes and errors in the evaluation model, is within the 2200°F acceptance criteria in 10 CFR 50.46(b)(1 ).

RA-15-0022 Page 2 of 2 Large Break Loss of Coolant Accident (LBLOCA) Analysis The LBLOCA analysis is not impacted during this reporting period.

LBLOCA PCT Summary of Changes ~PCT Resultant (oF) PCT (°F)

Previously reported LBLOCA PCT effective April 9, 2014 2073 Changes during reporting period None 2073 LBLOCA PCT effective April 9, 2015 2073 The resultant predicted fuel element PCT, accounting for changes and errors in the evaluation model, is within the 2200°F acceptance criteria in 10 CFR 50.46(b)(1).