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Category:Annual Operating Report
MONTHYEARML22104A0782022-04-14014 April 2022
Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G
PNP 2021-022, 2020 Annual Non-Radiological Environmental Operating Report2021-04-27027 April 2021
2020 Annual Non-Radiological Environmental Operating Report
PNP 2021-010, Annual Report of Changes in Emergency Core Cooling System Models2021-03-19019 March 2021
Annual Report of Changes in Emergency Core Cooling System Models
PNP 2019-020, Submittal of Annual Report of Changes in Emergency Core Cooling System Models2019-04-0808 April 2019
Submittal of Annual Report of Changes in Emergency Core Cooling System Models
ML19094B0782019-04-0303 April 2019
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PNP 2018-021, Submittal of 2017 Annual Non-Radiological Environmental Operating Report2018-04-20020 April 2018
Submittal of 2017 Annual Non-Radiological Environmental Operating Report
PNP 2018-022, Annual Report of Changes in Emergency Core Cooling System Models2018-04-0909 April 2018
Annual Report of Changes in Emergency Core Cooling System Models
ML18347B2982018-04-0303 April 2018
1997 Annual Non-Radiological Environment Operating Report
ML18347B2992018-04-0303 April 2018
1996 Annual Non-Radiological Environmental Operating Report
PNP 2017-060, Report of Changes, Tests and Experiments and Summary of Commitment Changes2017-10-12012 October 2017
Report of Changes, Tests and Experiments and Summary of Commitment Changes
PNP 2017-023, Annual Report of Changes in Emergency Core Cooling System Models2017-05-24024 May 2017
Annual Report of Changes in Emergency Core Cooling System Models
PNP 2016-030, Annual Report of Changes in Emergency Core Cooling System Models2016-04-20020 April 2016
Annual Report of Changes in Emergency Core Cooling System Models
PNP 2015-082, Report of Changes, Tests and Experiments and Summary of Commitment Changes2015-10-14014 October 2015
Report of Changes, Tests and Experiments and Summary of Commitment Changes
CNRO-2014-00003, Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G2014-04-25025 April 2014
Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G
PNP 2013-042, Submittal of 2012 Annual Non-Radiological Environmental Operating Report2013-04-23023 April 2013
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PNP 2013-031, Report of Changes in Emergency Core Cooling System Models2013-04-11011 April 2013
Report of Changes in Emergency Core Cooling System Models
CNRO-2012-00003, Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2012-04-30030 April 2012
Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G
PNP 2011-036, Submittal of 2010 Annual Non-Radiological Environmental Operating Report2011-04-26026 April 2011
Submittal of 2010 Annual Non-Radiological Environmental Operating Report
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Submittal of 2009 Annual Non-radiological Environmental Operating Report
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Submittal of Annual Report of Changes in Emergency Core Cooling System Models and 30-Day Report for Large and Small Break LOCA
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2008 Annual Radioactive Effluent Release and Waste Disposal Report (Attached)
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CNRO-2009-00006, Entergy Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(e) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2009-04-13013 April 2009
Entergy Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(e) Notification of Application of Approved Appendix B to 10CFR72 Subpart G
ML0810805412008-04-17017 April 2008
2007 Nonradiological Environmental Operating Report
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Generator Tube Inspection Report
ML0617301082006-06-21021 June 2006
Annual Report of Changes in Emergency Core Cooling System Models
ML0435102052004-12-0808 December 2004
Annual Report of Changes in Emergency Core Cooling System Models
ML18347A5031995-09-11011 September 1995
1994 Annual Report of Facility Changes, Tests and Experiments.
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2022-04-14
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Category:Licensee 30-Day Written Event Report
[Table view] |
Text
Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 Tel269 764 2000 Terry A. Davis Licensing Manager May 20,2009 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
APCT (OF) PCT (OF)
PCT (Previous 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 -4 1 1915 Palisades Appendix K LBLOCA PCT (2006 Annual Report) 1915 PCT (2007 Annual Report) 1915 PCT (2008 Annual Report) 1915 PCT (Last Acceptable Model Results) New Cycle 21 Analysis 1740 10 CFR 50.46 Changes CR 2009-337 S-RELAP5 Radiation to Fluid Correlation Under -27 1713 Predicts the Radiative Heat Transfer PCT (2009 Annual Report) 1713 Page I of 1
ATTACHMENT 2 SMALL BREAK LOSS OF COOLANT ACCIDENT PEAK CLADDING TEMPERATURE
SUMMARY
APCT("F) PCT("F)
PCT (Previous 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 PCT (2007 Annual Report) 1463 10 CFR 50.46 Changes CR 2007-5220 Legacy Fortran Programming Issues with Point -8 1455 Kinetics in RELAP5 Based Computer Codes PCT (2008 Annual Report) 1455 PCT (Last Acceptable Model Results) New Cycle 21 Analysis 1734 10 CFR 50.46 Changes CR 2009-337 S-RELAP5 Radiation to Fluid Correlation Under -64 Predicts the Radiative Heat Transfer PCT (2009 Annual Report) 1670 Page 1 of 1
