HNP-11-046, Emergency Core Cooling System Evaluation Changes Annual Report

Emergency Core Cooling System Evaluation Changes Annual Report

ML11152A147
Person / Time
Site:	Harris
Issue date:	05/23/2011
From:	Corlett D Progress Energy Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
HNP-11-046
Download: ML11152A147 (3)

Text

Progress Energy SERIAL: HNP- 11-046 10 CFR 50.46(a)(3)(ii)

MAY 2 3 2011 U. S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 EMERGENCY CORE COOLING SYSTEM EVALUATION CHANGES ANNUAL REPORT Ladies and Gentlemen:

In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," paragraph (a)(3)(ii), Carolina Power & Light Company, doing business as Progress Energy Carolinas, Inc. (PEC), is submitting the Harris Nuclear Plant (HNP) annual report regarding changes to and errors discovered in an acceptable Loss of Coolant Accident (LOCA) evaluation model for the Emergency Core Cooling System (ECCS).

The ECCS performance following a Large Break Loss of Coolant Accident (LBLOCA) is calculated for HNP by AREVA NP using the SEM/PWR-98 ECCS Evaluation Model for PWR LBLOCA Applications. The ECCS performance following a Small Break Loss of Coolant Accident (SBLOCA) is calculated for HNP by AREVA NP using the EXEM PWR Small Break Model.

The previous HNP 10 CFR 50.46 annual report to the NRC, dated June 24, 2010 (Serial: HNP-10-054), documented a SBLOCA peak clad temperature (PCT) of 1594°F and a LBLOCA PCT of 2081 F. Since that report, there have been no errors or changes in the LOCA models or results. provides HNP's PCT information for the SBLOCA and LBLOCA evaluations since the June 2010 report.

The Enclosure indicates no cumulative change in PCT associated with HNP's LBLOCA model and no cumulative change in PCT relative to HNP's SBLOCA model.

This document contains no regulatory commitments.

Progress Energy Carolinas, Inc.

Hariis Nuclear Plant P.0. Box 165 New Hill, NC27562

SERIAL: HNP-1 1-046 Page 2 Please refer any questions regarding this submittal to me at (919) 362-3137.

Sincerely, David H. Corlett Supervisor - Licensing/Regulatory Programs Harris Nuclear Plant DHC/kab

Enclosures:

Loss-of-Coolant Accident Margin Summary Sheet - Annual Report cc: Mr. J. D. Austin, NRC Senior Resident Inspector, HNP Mr. V.M. McCree, NRC Regional Administrator, Region II Mrs. B. L. Mozafari, NRC Project Manager, HNP

Enclosure to Serial HNP-1 1-046 HARRIS NUCLEAR PLANT (HNP) UNIT 1 LOSS-OF-COOLANT ACCIDENT MARGIN

SUMMARY

SHEET - ANNUAL REPORT SBLOCA Peak Clad Temperature Summary Evaluation Model: XN-NF-82-49(P)(A), Revision I Supplement 1, Exxon Nuclear Company Evaluation Model Revised EXEM PWR Small Break Model, Siemens Power Corporation, December 1994 SBLOCA Peak Clad Temperature Value reported 06/24/2010 1594 OF No errors found A PCT = 0 OF Total PCT change from current assessments E APCT = 0 'F New SBLOCA PCT Value 1594 OF LBLOCA Peak Clad Temperature Summary ECCS Evaluation Model: EMF-2087(P)(A), SEM/PWR-98: ECCS Evaluation Modelfor PWR LBLOCA Applications, Siemens Power Corporation, June 1999 LBLOCA Peak Clad Temperature Value reported 06/24/2010 2081 OF No errors found A PCT -0 0 F Total PCT change from current assessments Y APCT = 0 'F New LBLOCA PCT Value 2081 OF