ML061730108

Annual Report of Changes in Emergency Core Cooling System Models

ML061730108
Person / Time
Site:	Palisades
Issue date:	06/21/2006
From:	Harden P Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML061730108 (3)

Text

Palisades Nuclear Plant Operated by Nuclear Management Company, LLC June 21,2006 10 CFR 50.46 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Palisades Nuclear Plant Docket 50-255 License No. DPR-20 Annual Report of Channes in Emernencv Core Coolina Svstem Models Nuclear Management Company, LLC (NMC), is submitting the annual report of changes in the emergency core cooling system (ECCS) models for the Palisades Nuclear Plant.

The report is submitted in accordance with 10 CFR 50a46(a)(3)(ii).

There was a significant temperature change (greater than 50 degrees) subsequent to November 14, 2005, for the large break loss of coolant accident (LBLOCA). A 30-day report was submitted on March 14, 2006, as required. Enclosure 1 contains the LBLOCA peak cladding temperature summary. There was a slight peak cladding temperature change (-2 degrees) for the small break loss of coolant accident (SBLOCA) subsequent to November 14,2005. Enclosure 2 contains the SBLOCA peak cladding temperature summary. This report covers the period from November 15, 2005, through June 21, 2006.

Summarv of Commitments This letter contains no new commitments and no revisions to existinn commitments.

Paul A. Harden

. ----..,.- *CC_

Site Vice President, Palisades ~ u c l e aPlant r Nuclear Management Company, LLC Enclosures (2)

CC Administrator, Region Ill, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC 27780 Blue Star Memorial Highway Covert, Michigan 49043-9530 Telephone: 269.764.2000

ENCLOSURE 1 LARGE BREAK LOSS OF COOLANT ACCIDENT PEAK CLADDING TEMPERATURE

SUMMARY

APCT("F) PCT("F)

PCT (Last Acceptable Model Results) 1929 10 CFR 50.46 Changes CR 9266 Error In Break Loop SG Exit Junction Inertia +1 CR 9429 Error In Fast Flux Input To RODEX2 +4 PCT (2001 Annual Report) 1934 10 CFR 50.46 Changes CR 9156 Error In TOODEE2 Clad Thermal Expansion -1 CR 8674 RFPAC V&V Findings From CDUP +28 PCT (2002 Annual Report) 1961 PCT (2003 Annual Report) 1961 PCT (2004 Annual Report) 1961 PCT (2005 Annual Report) 1961 10 CFR 50.46 Changes CR 2005-4791 Large Break LOCA Containment Heat Sink -5 1956 Modeling Inputs CR 2006-585 Incorrect ICECON Heat Structure Input for -41 1915 Palisades Appendix K LBLOCA PCT (2006 Annual Report) 1915 Page 1 of 1

ENCLOSURE 2 SMALL BREAK LOSS OF COOLANT ACCIDENT PEAK CLADDING TEMPERATURE

SUMMARY

APCT ( O F ) PCT (OF)

PCT (Last Acceptable Model Results) 1465 PCT (2003 Annual Report) 1465 PCT (2004 Annual Report) 1465 PCT (2005 Annual Report) 1465 10 CFR 50.46 Changes CR 2006-1178-FA SBLOCA Core Exit Modeling -2 1463 PCT (2006 Annual Report) 1463 Page 1 of 1