RNP-RA/11-0100, Annual Report of Changes to or Errors Discovered in an Acceptable Loss-of-Coolant Accident Evaluation Model Application for the Emergency Core Cooling System

Annual Report of Changes to or Errors Discovered in an Acceptable Loss-of-Coolant Accident Evaluation Model Application for the Emergency Core Cooling System

ML11340A075
Person / Time
Site:	Robinson
Issue date:	11/23/2011
From:	Hightower R Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RNP-RA/11-0100
Download: ML11340A075 (4)

Text

10 CFR 50.46(a)(3)(ii)

~j~Progress Energy Serial: RNP-RA/11-0100 NOv 23 111 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/ RENEWED LICENSE NO. DPR-23 ANNUAL REPORT OF CHANGES TO OR ERRORS DISCOVERED IN AN ACCEPTABLE LOSS-OF-COOLANT ACCIDENT EVALUATION MODEL APPLICATION FOR THE EMERGENCY CORE COOLING SYSTEM Ladies and Gentlemen:

In accordance with the provisions of the Code of Federal Regulations, Title 10, Part 50.46 (10 CFR 50.46), Carolina Power & Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., hereby submits the attached report of non-significant changes to and errors discovered in an acceptable Loss-of-Coolant Accident (LOCA) evaluation model (EM) for the Emergency Core Cooling System at the H. B. Robinson Steam Electric Plant (HBRSEP), Unit No.

2. The applicable LOCA EMs are referenced in the HBRSEP, Unit No. 2, Core Operating Limits Report. This submittal satisfies the 10 CFR 50.46(a)(3)(ii) requirement for annual reporting of LOCA EM changes for HBRSEP, Unit No. 2.

The last annual report was submitted to the Nuclear Regulatory Commission by letter dated November 29, 2010, covering changes through November 8, 2010. This annual report provides the changes covering the period of November 9, 2010 through November 14, 2011. The non-significant changes and error corrections are provided in Attachment I. The effects of these non-significant changes and error corrections on HBRSEP, Unit No. 2, peak cladding temperature (PCT) estimates are also sunmarized in Attachment I.

The latest PCT estimates for the Large Break (LB) LOCA and Small Break (SB) LOCA are included in Attachment II.

This document contains no new Regulatory Commitments. If you have any questions, please contact me at (843) 857-1329.

Sincerely, Richard Hightoir*

Supervisor - Licensing/Regulatory Programs Progress Energy Carolinas, Inc.

Robinson Nuclear Plant 3581 West Entrance Road Hartsville, SC 29550

United States Nuclear Regulatory Commission Serial: RNP-RA/11-0100 Page 2 of 2 RJR/rjr Attachments:

I. Report of Changes/Errors in Loss-of-Coolant Accident Evaluation Models for the Emergency Core Cooling System II. Peak Cladding Temperature Estimates c: V. M. McCree, NRC, Region II B. Mozafari, NRC Project Manager, NRR NRC Resident Inspector, HBRSEP

United States Nuclear Regulatory Commission Attachment I to Serial: RNP-RA/1 1-0100 Page 1 of I H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 REPORT OF CHANGES/ERRORS IN LOSS-OF-COOLANT ACCIDENT EVALUATION MODELS FOR THE EMERGENCY CORE COOLING SYSTEM This report provides an estimate of the effect on peak cladding temperature (PCT) of changes and error corrections in the Loss-of-Coolant Accident (LOCA) evaluation models (EMs) and EM applications for the Emergency Core Cooling System (ECCS) at the H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, covering the period of November 9, 2010 through November 14, 2011.

Large Break Loss-of-Coolant Accident (LBLOCA) Evaluation Model CHANGED CONDITION PCT IMPACT (-F)

One error was found in the Robinson LBLOCA analysis. The analysis model produces a non-physical event, the influx of liquid into the hot 0 channel and surrounding 6 assemblies from the Lipper plenum.

Cumulative Impact 0 Small Break Loss-of-Coolant Accident (SBLOCA) Evaluation Model CHANGED CONDITION PCT IMPACT ('F)

No changes or errors 0 Cumulative Impact 0

United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/11-0100 Page 1 of 1 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 PEAK CLADDING TEMPERATURE ESTIMATES The current peak cladding temperature (PCT) estimates associated with Loss-of-Coolant Accident (LOCA) Emergency Core Cooling System (ECCS) evaluation models are listed below. These estimates include the cumulative effects of significant and non-significant error corrections and evaluation model changes through November 14, 2010.

Event PCT (OF)

Large Break LOCA, ECCS Injection Mode 1820 Small Break LOCA, ECCS Injection Mode 1615