PNP 2018-022, Annual Report of Changes in Emergency Core Cooling System Models

Annual Report of Changes in Emergency Core Cooling System Models

ML18100A008
Person / Time
Site:	Palisades
Issue date:	04/09/2018
From:	Hardy J Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PNP 2018-022
Download: ML18100A008 (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 2018-022 April 9, 2018 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 Palisades Nuclear Plant Docket 50-255 License No. DPR-20

Reference:

1. Letter dated March 20, 2018, from Hunter Marshall, Framatome, to Mr.

Thomas Allen, Entergy Nuclear Operations, Inc, "Palisades, Annual 10 CFR 50.46 Report - 2017"

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. This report covers the period from January 1, 2017, through December 31 ,

2017.

PNP 2018-022 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 : Small Break Loss of Coolant Accident Peak Claddi~g 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 (OF)

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 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) 10 CFR 50.46 Changes CR 2011-7155 S-RELAP5 Sieicher-Rouse Correlation +8 1699 PCT (2012 Annual Report) 1699 10 CFR 50.46 Changes CR 2012-2301 Liquid fallback into surrounding 6 assemblies 0 1699 PCT (2013 Annual Report) 10 CFR 50.46 Changes CR 2013-4230 S-RELAP5 routine associated with the +6 1705 RODEX3a fuel rod model in the code.

PCT (2014 Annual Report) 10 CFR 50.46 Changes CR 2012-8371 S-RELAP5 vapor absorptivity correlation 0 1705 CR 2014-3953 Non-Physical Axial Shapes Generated by 0 1705 Modal Decomposition Procedure PCT (2014 Annual Report) 1705 PCT{2015 Annual Report) 1705 PCT (2016 Annual Rep_ort) 1705 PCT (2017 Annual Report) 1705 Page 1 of 1

ATTACHMENT 2 SMALL BREAK LOSS OF COOLANT ACCIDENT PEAK CLADDING TEMPERATURE

SUMMARY

APCT (OF) PCT (OF)

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 1670 Predicts the Radiative Heat Transfer PCT (2009 Annual Report) 1670 10 CFR 50.46 Changes CR 2009-2309 S-RELAP5 Kinetics Model +4 1674 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 2014 Annual Re~ort 10 CFR 50.46 Changes CR 2012-8371 - S-RELAP5 Vapor Absorptivity Correlation +73 1744 PCT (2015 Annual Report) 1744 PCT (2016 Annual Report) 1744 2017 Annual Report 10 CFR 50.46 Changes CR 2017-3565 M5 LOCA Swelling and Rupture Model (SRM) 0 1744 Update (FAB17-00369)

CR 2017-5630 Error in S-RELAP5 Oxidation Calculations +17 1761 (FS1-0035262-1.0)

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