ML13157A258

Annual Report of Changes Pursuant to 10 CFR 50.46 for May 23, 2012 Through April 23, 2013

ML13157A258
Person / Time
Site:	Harris
Issue date:	06/06/2013
From:	Corlett D H Duke Energy Progress
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
HNP-13-050
Download: ML13157A258 (3)

Text

ENERGY June 6, 2013 Serial: HNP-13-050 ATTN: Document Control Desk U.S. Nuclear Regulatory Commiss i on Washington , DC 20555-0001 Shearon Harris Nuclear Power Plant , Unit 1 Docket No. 50-400

Subject:

Annual Report of Changes Pursuant to 1 0 CFR 50.46 Ladies and Gentlemen: David H. Corlett Manager , Regulatory Affa i rs Harris Nuc l ear Pl ant 5413 Shearon Harris Road New Hill NC 27562-9300 919.362.3137 10 CFR 50.46 Pursuant to 10 CFR 50.46(a)(3)(ii), Duke Energy Progress , Inc., formerly known as Carol i na Power & Light Company , 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 May 23 , 2012, through April 23 , 2013. This document contains no regulatory commitments. Please refer any questions regarding this submittal to John Caves at (919) 362-2406.

Sincerely , David H. Corlett DHC/jrc

Enclosure:

Annual Report of Changes Pursuant to 1 0 CFR 50.46 cc: Mr. J. D. Austin , NRC Sr. Resident Inspector , HNP Ms. A T. Billoch Colon , NRC Projec t Manager , HNP Mr. V. M. McCree , NRC Regional Adm i nistrator , Region II U.S. Nuclear Regulatory Commission Page 1 of 2 Enclosure to HNP-13-050 Shearon Harris Nuclear Power Plant, Unit 1 Annual Report of Changes Pursuant to 10 CFR 50.46 Reporting Period May 23, 2012, through April 23, 2013 Small Break Loss of Coolant Accident (SBLOCA) Analysis Evaluation Model:

AREVA EMF-2328(P)(A)

, PWR Small Break LOCA Evaluation Model, S-RELAP5 Based , Revision 0, March 2001

. The previous SBLOCA analysis of record was superseded using AREVA's EMF

-2 328, PWR Small Break LOCA Evaluation Model, S

-RELAP5 Based

. This result ed in a change to the peak clad temperature (PCT) of +33

°F. The base analysis of record PCT is 1627

°F.

The SBLOCA analysis is impacted by one error discovered during this reporting period

. The Sleicher-Rouse correlation for heat transfer is used by the S

-RELAP5 code.

One of the equations was initially not programmed in a form consistent with other heat transfer correlations and expected physical trends, which resulted in an impact of +4

°F. Summary of Changes

(°F) Resultant PCT (°F) SBLOCA PCT effective May 22, 2012 1594 Changes during reporting period Revised analysis of record

+33 1627 Errors during reporting period Sleicher-Rouse correlation

+4 1631 SBLOCA PCT effective April 23, 2013 1631 Sum of absolute values of PCT changes during this reporting period 37 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).

U.S. Nuclear Regulatory Commission Page 2 of 2 Enclosure to HNP-13-050 Large Break Loss of Coolant Accident (LBLOCA) Analysis Evaluation Model:

AREVA ANP-3011(P), Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis , Revision 1, as approved by NRC Safety Evaluation dated May 30, 2012. This evaluation model is a plant specific implementation of AREVA EMF-2103(P)(A), Realistic Large Break LOCA Methodology, Revision 0 , April 2003.

The previous LBLOCA analysis of record was superseded using ANP-3011 , Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis

. The NRC safety evaluation documenting approval of ANP

-3011 require s that an adder of 138

°F be applied to calculated peak cladding temperatures to address concerns related to droplet shattering and fuel relocation.

In addition, the base analysis also includes a +14

°F impact for the Sleicher

-Rouse error, as discussed above related to SBLOCA. The base analysis of record PCT is 2071

°F.

The LBLOCA analysis is impacted by one error discovered during this reporting period. There was an error in the calculation of uncertainty for one parameter of the Cathcart

-Pawel oxide growth correlation used to calculate energy released from oxidation of cladding.

This results in a 0 °F impact on PCT.

Summary of Changes

(°F) Resultant PCT (°F) LBLOCA PCT effective May 22, 2012 2081 Changes during reporting period Revised analysis of record Calculated PCT: 1919

°F Conservative adder to account for uncertainties related to droplet shattering and fuel relocation: +138

°F Sleicher-Rouse correlation: +14 °F -10 2071 Errors during reporting period Cathcart-Pawel correlation 0 2071 LBLOCA PCT effective April 23, 2013 2071 Sum of absolute values of PCT changes during this reporting period 10 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).