ML20198H391

Non-proprietary Rev 5 to HI-961586, Thermal-Hydraulic Analysis of Waterford-3 Spent Fuel Pool

ML20198H391
Person / Time
Site:	Waterford
Issue date:	07/14/1998
From:	Rampall I HOLTEC INTERNATIONAL
To:
Shared Package
ML20198H363	List: ML20198H357 ML20198H371 ML20198H391 ML20198H406 ML20198H412 ML20198H437 ML20198H442 ML20198H464 ML20198H468
References
HI-961586-(NP), HI-961586-R05, HI-961586-R5, NUDOCS 9812290331
Download: ML20198H391 (9)

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Holtec Center,555 Lincoln Drive West, Mariton, NJ 08053 Telephone (609) 797-0900 HOLTEC Fax (609) 797-0909 IN T E R N ATIO N A L J

J THERMAL-HYDRAULIC ANALYSIS l

OF WATERFORD-3 SPENT FUEL POOL by Indresh Rampall, Ph.D.

Holtec Project 60994 l

Holtec Report HI-961586 Report Category: I Client: Entergy Operations, Inc.

Client Contract Order: NWC00176

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_l Holtec Center,555 Lincoln Drive West, Marlton, NJ 08053 HOLTEC Telephone (609) 797-0900 Fax (609) 797-0909 INTERNATlONAL REVIEW AND CERTIFICATION LOG DOCUMENT NAME:

THERMAL-HYDRAULIC ANALYSIS OF WATERFORD-3 SPENT FUEL POOL IIOLTEC DOCUMENT I.D. NUMBER:

HI-%1586 HOLTEC PROJECT NUMBER:

60994 CUSTOMER / CLIENT:

ENTERGY OPERATIONS,INC.

REVISION BLOCK REVISION AUTHOR &

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This document ' conforms to the requirements of the design specification and the applicable sections of the governing Codes.

Note: Signatures and printed names are required in the review block.

A revision of this document will be ordered by the Project Manager and carried out if any of its contents is materially affected during evolution of this project. 'Ite determination as to the need for revision will be made by the Project Manager with input from others, as deemed necessary by him.

Must be Project Manager or his designee.

Distribution:

C:

Client M:

Designated Manufacturer F:

Florida Office THE REVISION CONTROL OF THIS DOCUMENT IS BY A "

SUMMARY

OF REVISIONS LOG" PLACED BEFORE THE TEXT OF THE REPORT.

Form: RCL.02

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SUMMARY

OF REVISIONS LOG

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i HOLTEC REPORT HI-961586 l

REVISION I:

(i)

EDITORIAL CHANGES PER COMMENTS FROM ENTERGY INCORPORATED.

(ii)

APPENDIX I ADDED TO REPORT.

REVISION 2:

Per comments from Entergy, Appendix J listing inputs used in the Waterford-3 CFD analysis are provided.

REVISION 3:

Appendix K Documenting Waterford.3 FSAR/DBD Update Computations Added MVISION 4: -

Appendix K revised as indicated by revision bars.

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.._ y TABLE OF CONTENTS i

1.0 SCOPE OF WORK............................................ 1 2.0 METHODOLOGY AND ACCEPTANCE CRITERIA.................... 2 2.1 Long-Term Decay Heat Calculation............................ 2 2.2 SFP Transient Hermal Response Determination................... 2 2.3 Sparger Truncation and Maximum local Temperature Evaluation Study..

5 3.0 ASSUMPTIONS AND INPUTS................................... 9 3.1 Background Decay Heat Calculation........................... 9 3.2 Spent Fuel Pool Cooling loop Hydraulic Analysis................. 9 3.3 Bulk Pool Tmnsient Hermal Analysis.........................

10 3.4 Local Water Temperature Analysis...........................

11 4.0 RESULTS AND CONCLUSIONS...................... :.......... 17 4.1 Hydraulic Performance of SFP Cooling Loop and Primary Exchanger Effectiveness

..........................................17 4.2 Bulk Pool Transient Evaluation.............................. 17 4.3 Resits of Local Thermal-Hydraulic Study on FLUENT Program....... 18 5.0 REFE RENCES.............................................. 25 5.1 List of Waterford-3 Input / Output Files.......................

26 List of Figures Figure 2.1 Spent Fuel Cooling Model Figure 4.1 Bulk Pool Transient Temperature Plots for Normal Discharge Scenarios Figure 4.2 Bulk Pool Transient Teng-&ure Plots for Full Core Discharge Scenarios Figure 4.3 Pool Decay Heat Loads for Normal Discharge Scenarios Figure 4.4 Pool Decay Heat Loads for Full Core Discharge Scenarios Figure 4.5 Rate of Water Evaporation from Pool Surface During Normal Discharge Scenarios Figure 4.6 Rate of Water Evaporation from Pool Surface During Full Core Discharge Scenarios Figure 4.7 Post loss of Forced Cooling Pool Depth vs. Time Plot [ Case (i) Normal Discharge Scenario]

Figure 4.8 Post Loss of Forced Cooling Pool Depth vs. Time Plot [ Case (ii) Normal Discharge]

Figure 4.9 Post Loss of Forced Cooling Pool Depth vs. Time Plot [ Case (iii) Full Core Discharge Scenario]

Holtec Intemational Proprietary Information Holtec Report HI-961586 i

TABLE OF CONTENTS Figure 4.10 Post Loss of Forced Cooling Pool Depth vs. Time Plot [ Case (iv) Full Core Discharge Scenario]

Figure 4.11 Waterford-3 CFD Analysis - Computational Grid Figure 4.12 Waterford-3 SFP Temperatue Contours Plot Figure 4.13 Waterford-3 CFD Analysis - Velocity Vectors Plot Figure 4.14 Dropped Assembly Scenario - Computational Grid Figure 4.15 Dropped Assembly Scenario - Temperature Contours Plot Figure 4.16 Dropped Assembly Scenario - Velocity Vectors Plot List of Accendices Appendix A:

Hydraulic Analysis of Spent Fuel Pool Cooling Loop (39 pages)

Appendix B:

Evaluation of Spent Fuel Pool Primary Heat Exchanger Effectiveness on STER (19 pages)

Appendix C:

Calculation of CE 16x16 Fuel Assembly Flow Resistance Parameters (10 pages)

Appendix D:

Background Decay Heat Calculation Summary (6 pages)

Appendix E:

Waterford-3 Pool Thermal Inertia Calculation Summary (3 pages)

Appendix F:

Pool Bulk Transient Evaluation Input / Output Files for ONEPOOL Program (15pages)

Appendix G:

TBOIL Program Input Files and Output Results Summary (23 pages)

Appendix H:

Peak Fuel Cladding Temperature Calculation (3 pages)

Appendix I:

Resolution of Waterford Comments (5 pages)

Appendix J:

Listing of Waterford-3 CFD Model Inputs (14 pages) hppendix K:

Waterford 3 FSAR/DBD Update (6 pages)

Holtec International Proprietary Information Holtec Report HI-961586 ii

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l.0 SCOPE OF WORK I

Waterford Unit 3 is a p-urized water reactor (PWR) electric generating station. Spent t

l nuclear fuel (SNF) assemblies discharged from the reactor are stored in an on-site spent fuel j

pool (SFP). Through the replacement of the existing storage racks with new high-density storage modules, the total storage capacity of the Waterford-3 spent fuel pool will be increased to a total of 2,104 cells.

Increasing the installed storage capacity requires consideration of the consequences of both normal and off-normal scenarios. It must be shown that sufficient cooling capacity exists l

during normal refueling operations, even if a single SFP pump failure is experienced. It must be shown that the local temperature of the stored SNF does not exceed boiling levels in any fuel cell location. All design criteria as set forth in the Waterford Unit 3 design basis i

i document [1] shall be complied with.

The purpose of this report is to document evaluations performed to characterize the bulk and a

local spent fuel pool thermal-hydraulic response and to demonstrate compliance with applicable design criteria with an adequate margin of safety. Specifically, the following analyses are performed:

l REMAINDER OF DOCUMENT IS PROPRIETARY AND IS EXCLUDED FROM THIS NON-PROPRIETARY VERSION

ENCLOSURE 4 (Non-Proprietary Version of Attachment 1 to W3F1-98-0016, dated 1/29/98) l

I 3-D SINGLE RACK ANALYSIS OF FUEL RACKS O

HOLTEC POSITION PAPER WS-115 Revision 0: DemmM 2,1996 Revision 1: January 20,1998 A free-esnding spent fuel rack typically features four or more support perkenk and an array of vertical storage cells into which spent fuel assemble are stored in the upright position.

All racks share the following four characteristics:

i REMAINDER OF DOCUMENT IS PROPRIETARY AND IS EXCLUDED FROM THIS NON-PROPRIETARY VERSION

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ENCLOSURE 5 (Non-Proprietary Version of Attachment 3 to W3F1-98-0016, dated 1/29/98) 1

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