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{{#Wiki_filter:Entergy Nuclear Operations, Inc.__ Palisades Nuclear Plant~- I- flt~l~lf27780 Blue Star Memorial Highway%-=RE n tf,;oyCovert, Ml 49043 June 14, 2007 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 Changes in Emergency Core Cooling System Models  
{{#Wiki_filter:Entergy Nuclear Operations, Inc.
__                                               Palisades Nuclear Plant
              ~- I- flt~l~lf27780                                   Blue Star Memorial Highway
            %-=RE n tf,;oyCovert,                                   Ml 49043 June 14, 2007                                                                 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 Changes in Emergency Core Cooling System Models


==Dear Sir or Madam:==
==Dear Sir or Madam:==
Entergy Nuclear Operations, Inc., 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 50.46(a)(3)(ii).
 
Enclosure 1 contains the large break loss of coolant accident peak cladding temperature summary. Enclosure 2 contains the small break loss of coolant accident peak cladding temperature summary. This report covers the period from June 21, 2006, through June 20, 2007.Summary of Commitments This letter contains no new commitments and no revision to existing commitments.
Entergy Nuclear Operations, Inc., 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 50.46(a)(3)(ii). contains the large break loss of coolant accident peak cladding temperature summary. Enclosure 2 contains the small break loss of coolant accident peak cladding temperature summary. This report covers the period from June 21, 2006, through June 20, 2007.
Christopher J. Schv Site Vice President Palisades Nuclear Plant Enclosures (2)CC Administrator, Region 111, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC ENCLOSURE 1 LARGE BREAK LOSS OF COOLANT ACCIDENT PEAK CLADDING TEMPERATURE  
Summary of Commitments This letter contains no new commitments and no revision to existing commitments.
Christopher J. Schv Site Vice President Palisades Nuclear Plant Enclosures (2)
CC Administrator, Region 111, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC
 
ENCLOSURE 1 LARGE BREAK LOSS OF COOLANT ACCIDENT PEAK CLADDING TEMPERATURE  


==SUMMARY==
==SUMMARY==
APCT (OF)PCT (-F)PCT Las Accptale MdelResuts)1929 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 CODUP +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_____
APCT (OF)     PCT (-F)
CR 2006-585 Incorrect ICECON Heat Structure Input for -41 1915 Palisades Appendix K LBLOCA_______
PCT     Las MdelResuts)1929   Accptale CR 9266 Error In Break Loop SG Exit Junction Inertia               +1   ____
PCT (2006 Annual Report) 1915 PCT (2007 Annual Report) _______ 1915 Page 1 of 1 ENCLOSURE 2 SMALL BREAK LOSS OF COOLANT ACCIDENT PEAK CLADDING TEMPERATURE  
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 CODUP                           +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 PCT (2007 Annual Report)                                   _______                 1915 Page 1 of 1
 
ENCLOSURE 2 SMALL BREAK LOSS OF COOLANT ACCIDENT PEAK CLADDING TEMPERATURE  


==SUMMARY==
==SUMMARY==
APCT (OF)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 2006-1 178-FA SBLOCA Core Exit Modeling -2 1463 PCT (2006 Annual Report) 1463 PCT (2007 Annual Report) 1463 Page 1 of 1}}
 
APCT (OF)   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 2006-1 178-FA SBLOCA Core Exit Modeling                 -2   1463 PCT (2006 Annual Report)                                           1463 PCT (2007 Annual Report)                                           1463 Page 1 of 1}}

Latest revision as of 05:03, 23 November 2019

Annual Report of Changes in Emergency Core Cooling System Models
ML071770347
Person / Time
Site: Palisades Entergy icon.png
Issue date: 06/14/2007
From: Schwarz C
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML071770347 (3)
v • d • e


Text

Entergy Nuclear Operations, Inc.

__ Palisades Nuclear Plant

~- I- flt~l~lf27780 Blue Star Memorial Highway

%-=RE n tf,;oyCovert, Ml 49043 June 14, 2007 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 Changes in Emergency Core Cooling System Models

Dear Sir or Madam:

Entergy Nuclear Operations, Inc., 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 50.46(a)(3)(ii). contains the large break loss of coolant accident peak cladding temperature summary. Enclosure 2 contains the small break loss of coolant accident peak cladding temperature summary. This report covers the period from June 21, 2006, through June 20, 2007.

Summary of Commitments This letter contains no new commitments and no revision to existing commitments.

Christopher J. Schv Site Vice President Palisades Nuclear Plant Enclosures (2)

CC Administrator, Region 111, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC

ENCLOSURE 1 LARGE BREAK LOSS OF COOLANT ACCIDENT PEAK CLADDING TEMPERATURE

SUMMARY

APCT (OF) PCT (-F)

PCT Las MdelResuts)1929 Accptale 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 CODUP +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 PCT (2007 Annual Report) _______ 1915 Page 1 of 1

ENCLOSURE 2 SMALL BREAK LOSS OF COOLANT ACCIDENT PEAK CLADDING TEMPERATURE

SUMMARY

APCT (OF) 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 2006-1 178-FA SBLOCA Core Exit Modeling -2 1463 PCT (2006 Annual Report) 1463 PCT (2007 Annual Report) 1463 Page 1 of 1

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