ML091400203
| ML091400203 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 05/20/2009 |
| From: | Davis T Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML091400203 (4) | |
Text
Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 Tel269 764 2000 May 20,2009 Terry A. Davis Licensing Manager 10 CFR 50.46 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Annual Report of Changes in Emergency Core Cooling System Models and 30-Day Report for Large and Small Break LOCA Palisades Nuclear Plant Docket 50-255 License No. DPR-20
Dear Sir or Madam:
Entergy Nuclear Operations, Inc. (ENO) is submitting this annual and 30-day report of changes in the emergency core cooling system (ECCS) models for the Palisades Nuclear Plant (PNP). The report is submitted in accordance with 10 CFR 50.46(a)(3)(ii) as a significant change in peak cladding temperature (PCT) of greater than 50' F. New small and large break loss of coolant accident (LOCA) analyses were performed by Areva for Cycle 21, which began on May 2,2009.
Areva's Condition Report (CR) 2009-337 was written to address an issue discovered during the development of a new radiation heat transfer model for their realistic large break LOCA methodology. This issue impacted both the small and large break LOCA analyses for Cycle 21. The PCT impact of this issue is included in the attachments.
Note that the magnitude of the PCT change for small break LOCA is greater than 50' F.
A small break LOCA reanalysis is not considered to be necessary since the identified issue results in a PCT benefit, as summarized in the attachment. There remains over 500' F of margin to the PCT limit of 2200' F; therefore, PNP continues to meet all 10 CFR 50.46 requirements, and EN0 does not plan on performing a reanalysis to incorporate this identified issue. contains the large break LOCA PCT summary. Attachment 2 contains the small break LOCA PCT summary. This report covers the period from June 14, 2008, through May 20,2009.
Document Control Desk Page 2 Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
Sincerely, : Large Break Loss of Coolant Accident Peak Cladding Temp. Summary : Small Break Loss of Coolant Accident Peak Cladding Temp. Summary CC Administrator, Region Ill, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC
ATTACHMENT 1 LARGE BREAK LOSS OF COOLANT ACCIDENT PEAK CLADDING TEMPERATURE
SUMMARY
Page I of 1 PCT (Previous Last Acceptable Model Results) 10 CFR 50.46 Changes CR 9266 Error In Break Loop SG Exit Junction Inertia CR 9429 Error In Fast Flux Input To RODEX2 PCT (2001 Annual Report) 10 CFR 50.46 Changes CR 9156 Error In TOODEE2 Clad Thermal Expansion CR 8674 RFPAC V&V Findings From CDUP PCT (2002 Annual Report)
PCT (2003 Annual Report)
PCT (2004 Annual Report)
PCT (2005 Annual Report) 10 CFR 50.46 Changes CR 2005-4791 Large Break LOCA Containment Heat Sink Modeling Inputs CR 2006-585 Incorrect ICECON Heat Structure Input for Palisades Appendix K LBLOCA PCT (2006 Annual Report)
PCT (2007 Annual Report)
PCT (2008 Annual Report)
PCT (Last Acceptable Model Results) New Cycle 21 Analysis 10 CFR 50.46 Changes CR 2009-337 S-RELAP5 Radiation to Fluid Correlation Under Predicts the Radiative Heat Transfer PCT (2009 Annual Report)
APCT (OF)
+ 1
+4
-1
+28
-5
-4 1
-27 PCT (OF) 1929 1934 1961 1961 1961 1961 1956 191 5 191 5 191 5 191 5 1740 171 3 171 3
ATTACHMENT 2 SMALL BREAK LOSS OF COOLANT ACCIDENT PEAK CLADDING TEMPERATURE
SUMMARY
Page 1 of 1 PCT (Previous Last Acceptable Model Results)
PCT (2003 Annual Report)
PCT (2004 Annual Report)
PCT (2005 Annual Report) 10 CFR 50.46 Changes CR 2006-1 178-FA SBLOCA Core Exit Modeling PCT (2006 Annual Report)
PCT (2007 Annual Report) 10 CFR 50.46 Changes CR 2007-5220 Legacy Fortran Programming Issues with Point Kinetics in RELAP5 Based Computer Codes PCT (2008 Annual Report)
PCT (Last Acceptable Model Results) New Cycle 21 Analysis 10 CFR 50.46 Changes CR 2009-337 S-RELAP5 Radiation to Fluid Correlation Under Predicts the Radiative Heat Transfer PCT (2009 Annual Report)
APCT("F)
-2
-8
-64 PCT("F) 1465 1465 1465 1465 1463 1463 1463 1455 1455 1734 1670