PNP 2020-010, Annual Report of Changes in Emergency Core Cooling System Models
| ML20080H320 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 03/19/2020 |
| From: | Hardy J Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PNP 2020-010 | |
| Download: ML20080H320 (4) | |
Text
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-===-Entergy PNP 2020-010 March 19, 2020 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, Ml 49043 269764 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 Renewed Facility Operating License No. DPR-20
Reference:
- 1. Letter FS1-0048733 1.0, dated March 2, 2020, from E. Hunter Marshall, Framatome, to Mr. Dennis Pearson, Entergy Services, Inc.,
"Palisades, Annual 1 O CFR 50.46 Report - 2019"
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, 2019, through December 31, 2019.
PNP 2020-010 Document Control Desk Page2 This letter contains no new commitments and no revisions to existing commitments.
Respectfully, 9,4,~1/
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 111, 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 PCT (2009 Annual Report)
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 CR 2009-2360 RODEX TCD (FAB09-306) 0 PCT (2010 Annual Report)
CR 2010-3095 RLBLOCA & S-RELAP5 - FIJ Multiplier &
0 UnderpredictinQ Liquid Entrained to SG Tubes (FAB10-387)
PCT (2011 Annual Report)
CR 2011-1688 RLBLOCA Upper Plenum Modeling 0
(FAB11-219)
CR 2011-7155 S-RELAP5 Sleicher-Rouse Correlation
+8 PCT (2012 Annual Report)
CR 2012-2301 Liquid fallback into surroundinQ 6 assemblies 0
CR 2012-8277 Cathcart-Pawel Uncertainty Implementation 0
in RLBLOCA Aoolications (FAB13-00134-001)
PCT (2013 Annual Report)
CR 2013-4230 S-RELAP5 routine associated with the
+6 RODEX3a fuel rod model in the code.
PCT (2014 Annual Report)
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)
PCT (2019 Annual Report)
CR 2019-1130 Cathcart-Pawel Correlation Implementation 0
(FS1-0046435-1.0)
Total Delta
-35 Total Page 1 of 1 PCT (°F) 1740 1713 1691 1691 1691 1699 1699 1705 1705 1705 1705 1705 1705 1705 1705 1705
ATTACHMENT 2 SMALL BREAK LOSS OF COOLANT ACCIDENT PEAK CLADDING TEMPERATURE
SUMMARY
APCT (0 f)
PCT (Last Acceptable Model Results) New Cycle 21 Analysis PCT (2009 Annual Report)
CR 2009-337 S-RELAP5 Radiation to Fluid Correlation Under
-64 Predicts the Radiative Heat Transfer CR 2009-2309 S-RELAP5 Kinetics Model
+4 PCT (201 0 Annual Report)
PCT (2011 Annual Report)
PCT (2012 Annual Report)
CR 2011-7155 S-RELAP5 Sleicher-Rouse Correlation
-3 PCT (2013 Annual Report)
PCT (2014 Annual Report)
CR 2012-8371 - S-RELAP5 Vapor Absorptivity Correlation
+73 PCT (2015 Annual Report)
PCT (2016 Annual Report)
PCT (2017 Annual Report)
CR 2017-3565 MS LOCA Swelling and Rupture Model (SRM) 0 Update (FAB17-00369)
CR 2017-5630 Error in S-RELAP5 Oxidation Calculations
+17 (FS1-0035262-1.0)
PCT (2018 Annual Report)
PCT (2019 Annual Report)
Total Delta
+27 Total Page 1 of 1 PCT (0 f) 1734 1670 1674 1674 1674 1671 1671 1744 1744 1744 1744 1761 1761 1761 1761