ML16116A222

Annual Report of Changes in Emergency Core Cooling System Models

ML16116A222
Person / Time
Site:	Palisades
Issue date:	04/20/2016
From:	Hardy J A Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PNP 2016-030
Download: ML16116A222 (4)

Text

PNP 2016-030 April 20, 2016 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Entergy Nuclear Operations, Inc. Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, Ml 49043 269 764 2000 Jeffery A. Hardy Regulatory Assurance Manager 10 CFR 50.46

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 1 OCFR50.46 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).

Attachme"nt 1 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 Page2 This letter contains no new commitments and no revisions to existing commitments.

Sincerely, JAH/bed Attachment 1: Large Break Loss of Coolant Accident Peak Cladding Temperature Summary Attachment 2: Small Break Loss of Coolant Accident Peak Cladding Temperature 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 (°F) PCT (Last Acceptable Model Results) New Cycle 21 Analysis 10 CFR 50.46 Changes CR 2009-337 S-RELAP5 Radiation to Fluid Correlation Under -27 Predicts the Radiative Heat Transfer PCT (2009 Annual Report) 1 O CFR 50.46 Changes CR 2009-2309 S-RELAP5 Kinetics and Heat Conduction

-22 Model PCT (201 O Annual Report) PCT (2011 Annual Report) 1 O CFR 50.46 Changes CR 2011-7155 S-RELAP5 Sleicher-Rouse Correlation

+8 PCT (2012 Annual Report) PCT (2013 Annual Report) 1 O CFR 50.46 Changes CR 2013-4230 S-RELAP5 routine associated with the +6 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) PCT (2015 Annual Report) Sum Total of PCT Adjustments

-35 Page 1 of 1 PCT (°F) 1740 1713 1713 1691 1691 1691 1699 1699 1705 1705 1705 ATTACHMENT 2 SMALL BREAK LOSS OF COOLANT ACCIDENT PEAK CLADDING TEMPERATURE

SUMMARY

.l\PCT (°F) PCT (Last Acceptable Model Results) New Cycle 21 Analysis 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) 10 CFR 50.46 Changes CR 2009-2309 S-RELAP5 Kinetics Model +4 PCT (201 O Annual Report) PCT (2011 Annual Report) 10 CFR 50.46 Changes CR 2011-7155 S-RELAP5 Sleicher-Rouse Correlation

-3 PCT (2012 Annual Report) PCT (2013 Annual Report) 1 O CFR 50.46 Changes CR-2012-8371

-S-RELAP5 Vapor Absorptivity Correlation

+73 PCT (2014 Annual Report) PCT (2015 Annual Report) Sum Total of PCT Adjustments

+10 Page 1 of 1 PCT (°F) 1734 1670 1674 1674 1671 1671 1671 1744 1744 1744

• PNP 2016-030 April 20, 2016 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Entergy Nuclear Operations, Inc. Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, Ml 49043 269 764 2000 Jeffery A. Hardy Regulatory Assurance Manager 10 CFR 50.46

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 1 OCFR50.46 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).

Attachme"nt 1 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 Page2 This letter contains no new commitments and no revisions to existing commitments.

Sincerely, JAH/bed Attachment 1: Large Break Loss of Coolant Accident Peak Cladding Temperature Summary Attachment 2: Small Break Loss of Coolant Accident Peak Cladding Temperature 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 (°F) PCT (Last Acceptable Model Results) New Cycle 21 Analysis 10 CFR 50.46 Changes CR 2009-337 S-RELAP5 Radiation to Fluid Correlation Under -27 Predicts the Radiative Heat Transfer PCT (2009 Annual Report) 1 O CFR 50.46 Changes CR 2009-2309 S-RELAP5 Kinetics and Heat Conduction

-22 Model PCT (201 O Annual Report) PCT (2011 Annual Report) 1 O CFR 50.46 Changes CR 2011-7155 S-RELAP5 Sleicher-Rouse Correlation

+8 PCT (2012 Annual Report) PCT (2013 Annual Report) 1 O CFR 50.46 Changes CR 2013-4230 S-RELAP5 routine associated with the +6 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) PCT (2015 Annual Report) Sum Total of PCT Adjustments

-35 Page 1 of 1 PCT (°F) 1740 1713 1713 1691 1691 1691 1699 1699 1705 1705 1705 ATTACHMENT 2 SMALL BREAK LOSS OF COOLANT ACCIDENT PEAK CLADDING TEMPERATURE

SUMMARY

.l\PCT (°F) PCT (Last Acceptable Model Results) New Cycle 21 Analysis 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) 10 CFR 50.46 Changes CR 2009-2309 S-RELAP5 Kinetics Model +4 PCT (201 O Annual Report) PCT (2011 Annual Report) 10 CFR 50.46 Changes CR 2011-7155 S-RELAP5 Sleicher-Rouse Correlation

-3 PCT (2012 Annual Report) PCT (2013 Annual Report) 1 O CFR 50.46 Changes CR-2012-8371

-S-RELAP5 Vapor Absorptivity Correlation

+73 PCT (2014 Annual Report) PCT (2015 Annual Report) Sum Total of PCT Adjustments

+10 Page 1 of 1 PCT (°F) 1734 1670 1674 1674 1671 1671 1671 1744 1744 1744