PNP 2019-020, Submittal of Annual Report of Changes in Emergency Core Cooling System Models
| ML19099A011 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 04/08/2019 |
| From: | Hardy J Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PNP 2019-020 | |
| Download: ML19099A011 (4) | |
Text
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~Entergy PNP 2019-020 April 8, 2019 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 2697642000 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 Renewed Facility Operating License No. DPR-20
Reference:
- 1. Letter FS1-0043219-1.0, dated March 25, 2019, from E. Hunter Marshall, Framatome, to Mr. Dennis Pearson, Entergy Services, Inc.,
"Palisades, Annual 10 CFR 50.46 Report - 2018"
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, 2018, through December 31,
2018.
PNP 2019-020 Document Control Desk Page 2 This letter contains no new commitments and no revisions to existing commitments.
Respectfully, JAH/bed : Large Break Loss of Coolant Accident Peak Cladding Temperature Summary : Small 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
~PCT (OF)
PCT (Last Acceptable Model Results) New Cycle 21 Analysis PCT (2009 Annual Report) 10 CFR 50.46 Changes CR 2009-337 S-RELAP5 Radiation to Fluid Correlation Under
-27 Predicts the Radiative Heat Transfer CR 2009-2309 S-RELAP5 Kinetics and Heat Conduction
-22 Model PCT (2010 Annual Report)
PCT (2011 Annual Report) 10 CFR 50.46 Changes CR 2011-7155 S-RELAP5 Sieicher-Rouse Correlation
+8 PCT (2012 Annual Report) 10 CFR 50.46 Changes CR 2012-2301 Liquid fallback into surrounding 6 assemblies 0
PCT (2013 Annual Report) 10 CFR 50.46 Changes CR 2013-4230 S-RELAP5 routine associated with the
+6 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
CR 2014-3953 Non-Physical Axial Shapes Generated by 0
Modal Decomposition Procedure PCT (2015 Annual Report)
PCT (2016 Annual Report)
PCT (2017 Annual Report)
PCT (2018 Annual Report)
Total Delta
-35 Total Page 1 of 1 PCT (OF) 1740 1713 1691 1691 1699 1699 1705 1705 1705 1705 1705 1705 1705 1705
ATTACHMENT 2 SMALL BREAK LOSS OF COOLANT ACCIDENT PEAK CLADDING TEMPERATURE
SUMMARY
aPCT (OF)
PCT eF)
PCT (Last Acceptable Model Results) New Cycle 21 Analysis 1734 PCT (2009 Annual Report) 10 CFR 50.46 Changes CR 2009-337 S-RELAP5 Radiation to Fluid Correlation Under
-64 1670 Predicts the Radiative Heat Transfer CR 2009-2309 S-RELAP5 Kinetics Model
+4 1674 PCT (2010 Annual Report) 1674 PCT (2011 Annual Report) 1674 PCT (2012 Annual Report) 10 CFR 50.46 Changes CR 2011-7155 S-RELAP5 Sieicher-Rouse Correlation
-3 1671 PCT (2013 Annual Report) 1671 PCT (2014 Annual Report) 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 PCT (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)
PCT (2018 Annual Report) 1761 Total Delta
+27 Total 1761 Page 1 of 1