PNP 2016-030, Annual Report of Changes in Emergency Core Cooling System Models

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Annual Report of Changes in Emergency Core Cooling System Models
ML16127A052
Person / Time
Site: Palisades Entergy icon.png
Issue date: 04/20/2016
From: Hardy J
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
PNP 2016-030
Download: ML16127A052 (4)


Text

,.

~Entergy Entergy Nuclear Operations, Inc.

Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 2697642000 Jeffery A. Hardy Regulatory Assurance Manager PNP 2016-030 April 20, 2016 10 CFR50.46 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Annual Report of Changes in Emergency Core Cooling System Models Palisades Nuclear Plant Docket 50-255 License No. DPR-20

Reference:

1. Letter dated April 5, 2016, from L.W.Newman, AREVA, to Mr. Thomas Allen, Entergy Nuclear Operations, Inc, "Annual 10CFR50.46 Reporting for Palisades"

Dear Sir or Madam:

Entergy Nuclear Operations, Inc. (ENO) is submitting the annual 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). contains the large break loss of coolant accident (LOCA) peak clad temperature (PCT) summary. Attachment 2 contains the small break LOCA PCT summary. There have been no changes to either the small or large break LOCA PCT summary since the previous annual report. This report covers the period from January 1, 2015, through December 31, 2015.

PNP 2016-030 Document Control Desk Page 2 This letter contains no new commitments and no revisions to existing commitments.

Sincerely, JAH/bed : Large Break Loss of Coolant Accident Peak Cladding Temperature Summary : Sma" Break Loss of Coolant Accident Peak Cladding Temperature Summary CC Administrator, Region III, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC

ATTACHMENT 1 LARGE BREAK LOSS OF COOLANT ACCIDENT PEAK CLADDING TEMPERATURE

SUMMARY

APCT (OF) PCT(DF)

PCT (Last Acce~table 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 10 CFR 50.46 Changes CR 2009-2309 S-RELAP5 Kinetics and Heat Conduction -22 1691 Model PCT (2010 Annual Report) 1691 PCT(2011 Annual Report) 1691 10 CFR 50.46 Changes CR 2011-7155 S-RELAP5 Sieicher-Rouse Correlation +8 PCT(2012AnnuaIReport) 1699 PCT (2013 Annual Report) 1699 10 CFR 50.46 Changes CR 2013-4230 S-RELAP5 routine associated with the +6 1705 RODEX3a fuel rod model in the code. Letter, Len Newman (AREVA NP) to Gary Jarka (Entergy Operations, Inc.), "Interim 10CFR50.46 Reporting for Palisades," FAB13-426, dated September 16, 2013.

PCT (2014 Annual Report) 1705 PCT (2015 Annual Report) 1705 Sum Total of PCT Adjustments -35 Page 1 of 1

ATTACHMENT 2 SMALL BREAK LOSS OF COOLANT ACCIDENT PEAK CLADDING TEMPERATURE

SUMMARY

APCT (oF) PCT (OF)

PCT (Last Acceptable Model Resulta) New Cycle 21 Analysis 1734 10 CFR 50.46 Changea CR 2009-337 S-RELAP5 Radiation to Fluid Correlation Under -64 Predicts the Radiative Heat Transfer PCT (2009 Annual Report) 1670 10 CFR 50.46 Changes CR 2009-2309 S-RELAP5 Kinetics Model +4 PCT (2010 Annual Report) 1674 PCT(2011 Annual Report) 1674 10 CFR 50.46 Changes CR 2011-7155 S-RELAP5 Sieicher-Rouse Correlation -3 1671 PCT (2012 Annual Report) 1671 PCT (2013 Annual Report) 1671 10 CFR 50.46 Changes CR-2012-8371 - S-RELAP5 Vapor Absorptivity Correlation +73 1744 PCT {2014 Annual Report) 1744 PCT (2015 Annual Report) 1744 Sum Total of PCT Adjustments +10 Page 1 of 1

~Entergy Entergy Nuclear Operations, Inc.

Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 2697642000 Jeffery A. Hardy Regulatory Assurance Manager PNP 2016-030 April 20, 2016 10 CFR50.46 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Annual Report of Changes in Emergency Core Cooling System Models Palisades Nuclear Plant Docket 50-255 License No. DPR-20

Reference:

1. Letter dated April 5, 2016, from L.W.Newman, AREVA, to Mr. Thomas Allen, Entergy Nuclear Operations, Inc, "Annual 10CFR50.46 Reporting for Palisades"

Dear Sir or Madam:

Entergy Nuclear Operations, Inc. (ENO) is submitting the annual 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). contains the large break loss of coolant accident (LOCA) peak clad temperature (PCT) summary. Attachment 2 contains the small break LOCA PCT summary. There have been no changes to either the small or large break LOCA PCT summary since the previous annual report. This report covers the period from January 1, 2015, through December 31, 2015.

PNP 2016-030 Document Control Desk Page 2 This letter contains no new commitments and no revisions to existing commitments.

Sincerely, JAH/bed : Large Break Loss of Coolant Accident Peak Cladding Temperature Summary : Sma" Break Loss of Coolant Accident Peak Cladding Temperature Summary CC Administrator, Region III, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC

ATTACHMENT 1 LARGE BREAK LOSS OF COOLANT ACCIDENT PEAK CLADDING TEMPERATURE

SUMMARY

APCT (OF) PCT(DF)

PCT (Last Acce~table 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 10 CFR 50.46 Changes CR 2009-2309 S-RELAP5 Kinetics and Heat Conduction -22 1691 Model PCT (2010 Annual Report) 1691 PCT(2011 Annual Report) 1691 10 CFR 50.46 Changes CR 2011-7155 S-RELAP5 Sieicher-Rouse Correlation +8 PCT(2012AnnuaIReport) 1699 PCT (2013 Annual Report) 1699 10 CFR 50.46 Changes CR 2013-4230 S-RELAP5 routine associated with the +6 1705 RODEX3a fuel rod model in the code. Letter, Len Newman (AREVA NP) to Gary Jarka (Entergy Operations, Inc.), "Interim 10CFR50.46 Reporting for Palisades," FAB13-426, dated September 16, 2013.

PCT (2014 Annual Report) 1705 PCT (2015 Annual Report) 1705 Sum Total of PCT Adjustments -35 Page 1 of 1

ATTACHMENT 2 SMALL BREAK LOSS OF COOLANT ACCIDENT PEAK CLADDING TEMPERATURE

SUMMARY

APCT (oF) PCT (OF)

PCT (Last Acceptable Model Resulta) New Cycle 21 Analysis 1734 10 CFR 50.46 Changea CR 2009-337 S-RELAP5 Radiation to Fluid Correlation Under -64 Predicts the Radiative Heat Transfer PCT (2009 Annual Report) 1670 10 CFR 50.46 Changes CR 2009-2309 S-RELAP5 Kinetics Model +4 PCT (2010 Annual Report) 1674 PCT(2011 Annual Report) 1674 10 CFR 50.46 Changes CR 2011-7155 S-RELAP5 Sieicher-Rouse Correlation -3 1671 PCT (2012 Annual Report) 1671 PCT (2013 Annual Report) 1671 10 CFR 50.46 Changes CR-2012-8371 - S-RELAP5 Vapor Absorptivity Correlation +73 1744 PCT {2014 Annual Report) 1744 PCT (2015 Annual Report) 1744 Sum Total of PCT Adjustments +10 Page 1 of 1