Non-proprietary Rev 5 to HI-961586, Thermal-Hydraulic Analysis of Waterford-3 Spent Fuel PoolML20198H391 |
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Waterford ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
07/14/1998 |
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From: |
Rampall I HOLTEC INTERNATIONAL |
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To: |
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Shared Package |
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ML20198H363 |
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References |
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HI-961586-(NP), HI-961586-R05, HI-961586-R5, NUDOCS 9812290331 |
Download: ML20198H391 (9) |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20195C3041999-05-28028 May 1999 Annual Rept on Abb CE ECCS Performance Evaluation Models ML20204H1401999-03-23023 March 1999 Rev 1 to Engineering Rept C-NOME-ER-0120, Design Evaluation of Various Applications at Waterford Unit 3 ML20204H2451999-03-22022 March 1999 Rev 2 to C-NOME-SP-0067, Design Specification for Mechanical Nozzle Seal Assembly (Mnsa) Waterford Unit 3 ML20204H1231999-03-22022 March 1999 Rev 1 to Design Rept C-PENG-DR-006, Addendum to Cenc Rept 1444 Analytical Rept for Waterford Unit 3 Piping ML20198H3911998-07-14014 July 1998 Non-proprietary Rev 5 to HI-961586, Thermal-Hydraulic Analysis of Waterford-3 Spent Fuel Pool ML20248E7781998-06-0101 June 1998 Annual Rept on Abb CE ECCS Performance Evaluation Models ML20198H4681998-05-20020 May 1998 Non-proprietary Rev 1 to HI-981942, Independent Review of Waterford Unit 3 Spent Fuel Pool Cfd Model ML20247A3891998-05-0101 May 1998 SG Eddy Current Examination (8th Refueling Outage) ML20199F5831998-01-29029 January 1998 Errata Change Pages for Rept HI-971628,for Section 8.6.1.2 & Table 8.1.Change Pages Submitted to Assure Consistency Between LAR & Calculations Performed for SFP Structural Analysis ML20198H4641998-01-28028 January 1998 Non-proprietary Rev 1 to HI-91700, Dynarack Validation Manual ML20141G7081997-07-0505 July 1997 to Rept on Vortexing in Condensate Storage Pool ML20140F1491997-04-16016 April 1997 Rev 3 to 10CFR50.59 Safety Evaluation ML20137G2141997-03-27027 March 1997 Non-proprietary Version of Licensing Rept for Reracking of Waterford 3 Sfps ML20094H4141995-11-0303 November 1995 Thermo-Lag Installed to Tested Fire Barrier Evaluation (GL 86-10 Evaluation) ML20094H4001995-05-30030 May 1995 Pyrolysis Gas Chromatography Analysis of 3 Thermo-Lag Fire Barrier Samples ML20078F1001995-01-31031 January 1995 Summary of Waterford 3 Criticality Safety Analysis for Fuel Enrichments Above 4.1 W/O U-235 Taking Credit for Fixed Burnable Poisons ML20078Q2951994-11-0909 November 1994 3 Ses Tsc/Osc Tabletop 4,941109 ML20078Q3111994-11-0707 November 1994 3 Ses EOF Tabletop 4,941107 ML20078Q2851994-10-12012 October 1994 3 Ses Tsc/Osc Tabletop 3,941012 ML20078Q3051994-10-10010 October 1994 3 Ses EOF Tabletop 3,941010 ML20078Q2741994-09-20020 September 1994 3 Ses Tsc/Osc Tabletop 2,940920 ML20078Q3021994-08-15015 August 1994 3 Ses EOF Tabletop 2,940815 ML20078Q2731994-05-25025 May 1994 3 Ses Tsc/Osc Tabletop 1,940525 ML20078Q3001994-05-23023 May 1994 3 Ses EOF Tabletop 1,940523 ML20062M1441993-12-29029 December 1993 Section 6.0 of Development of RCS Pts...& Recommended Surveillance Withdrawal Schedule for Waterford Unit 3 ML20059D3971993-10-31031 October 1993 Rev 0 to Development of RCS Pressure Temp Limits for 20 EFPYs (Fluence = 2.29 X 10(19) n/cm(2)) & Recommended Surveillance Withdrawal Schedule for Waterford Unit 3, Final Rept ML20198H3711991-11-12012 November 1991 Non-proprietary HI-91700, Dynarack Validation Manual ML20086C4241991-09-0505 September 1991 Design Engineering Program Assessment Executive Summary ML20199F5531991-03-31031 March 1991 Chin Shan Analyses Show Advantages of Whole Pool Multi-Rack Approach, from Nuclear Engineering International,Mar 1991 ML20073K8451991-03-31031 March 1991 Entergy Nuclear Performance Rept,Mar 1991 ML20072R2261991-03-20020 March 1991 3 Plant Ref Simulator Certification Package ML20056A7301990-06-30030 June 1990 Basemat Monitoring Program Special Rept 3 ML20245J5071989-07-31031 July 1989 Unit 3 Control Element Assembly Drop Time Tech Spec Change Justification ML20246P2561989-07-31031 July 1989 Compliance W/10CFR50.62 Reduction of Risk from ATWS Events ML20155E1311988-10-31031 October 1988 Compliance W/10CFR50.62,Reduction of Risk from ATWS Events ML20207L2881988-09-30030 September 1988 Basemat Monitoring Program,Special Rept 2, from Inception to Aug 1988 ML20154D0571988-09-0909 September 1988 Actions Completed by Louisiana Power & Light Co ML20155B7181988-09-0909 September 1988 Rev 1 to Louisiana Power & Light Co Response to US-NRC Bulletin 88-005 ML20151F1771988-06-30030 June 1988 1987 SALP Progress Rept Updated June 1988 ML20195G8941988-06-20020 June 1988 MSIV Guide Rail Failure Final Rept ML20151B7901988-03-31031 March 1988 1987 SALP Progress Rept W3P87-1746, Emergency Preparedness Exercise1987-10-14014 October 1987 Emergency Preparedness Exercise ML20234C1501987-07-31031 July 1987 Basemat Summary Rept ML20214M5571987-05-27027 May 1987 Draft Waterford 3 Nuclear Plant Island Structure Basemat Summary Rept. W/Two Oversize Figures ML20198H4061987-04-30030 April 1987 Non-proprietary HI-87113, Evaluation of Fluid Flow for In- Phase & Out-of-Phase Rack Motions ML20198H4121987-04-0707 April 1987 Non-proprietary HI-87114, Estimated Effects of Vertical Flow Between Racks & Between Fuel Cell Assemblies ML20198H4421987-04-0707 April 1987 Non-proprietary HI-87112, Fluid Flow in Narrow Channels Surrounding Moving Rigid Bodies ML20198H4371987-01-14014 January 1987 Non-proprietary HI-87102, Study of Non-Linear Coupling Effects ML20215N4601986-10-0101 October 1986 Program to Perform Confirmatory Analyses,Nuclear Plant Island Structure Basemat:Results of Analyses ML20215H6891986-09-30030 September 1986 Nonproprietary Encl 1-NP, Responses to Requests for Addl Info on Waterford 3 Cycle 2 Reload 1999-05-28
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217F2891999-10-13013 October 1999 Drill 99-08 Emergency Preparedness Exercise on 991013 ML20217G7211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Waterford 3 Ses. with ML20211Q2141999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Waterord 3 Ses.With ML20210Q6361999-07-31031 July 1999 Corrected Monthly Operating Rept for July 1999 for Waterford 3 ML20210S0581999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Waterford 3.With ML20210D8951999-07-23023 July 1999 Safety Evaluation Accepting First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 - ISI-020 ML20209H3781999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Waterford 3 Ses. with ML20195J8951999-06-17017 June 1999 Safety Evaluation Granting Relief for Listed ISI Parts for Current Interval,Per 10CFR50.55a(g)(5)(iii) ML20207E8631999-06-0303 June 1999 Safety Evaluation Accepting Licensee 990114 Submittal of one-time Request for Relief from ASME B&PV Code IST Requirements for Pressure Safety Valves at Plant,Unit 3 ML20195K3391999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Waterford 3 Ses.With ML20195C3041999-05-28028 May 1999 Annual Rept on Abb CE ECCS Performance Evaluation Models ML20206S7401999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Waterford 3.With ML20205T2621999-04-22022 April 1999 LER 99-S02-00:on 990216,contract Employee Inappropriately Granted Unescorted Access to Plant Protected Area.Caused by Personnel Error.Security Personnel Performed Review of Work & Work Area That Individual Was Involved with ML20205N9671999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Waterford 3 Ses.With ML20205E8531999-03-30030 March 1999 Corrected Pages COLR 3/4 1-4 & COLR 3/4 2-6 to Rev 1, Cycle 10, Colr ML20205A6331999-03-25025 March 1999 SER Accepting Request to Use Mechanical Nozzle Seal Assemblies as an Alternative Repair Method,Per 10CFR50.55a(a)(3)(i) for Reactor Coolant Sys Applications at Plant,Unit 3 ML20204H1401999-03-23023 March 1999 Rev 1 to Engineering Rept C-NOME-ER-0120, Design Evaluation of Various Applications at Waterford Unit 3 ML20204H1231999-03-22022 March 1999 Rev 1 to Design Rept C-PENG-DR-006, Addendum to Cenc Rept 1444 Analytical Rept for Waterford Unit 3 Piping ML20204H2451999-03-22022 March 1999 Rev 2 to C-NOME-SP-0067, Design Specification for Mechanical Nozzle Seal Assembly (Mnsa) Waterford Unit 3 ML20204F0791999-03-17017 March 1999 Rev 1 to Waterford 3 COLR for Cycle 10 ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207F3491999-03-0505 March 1999 LER 99-S01-00:on 990203,contraband Was Discovered in Plant Protected Area.Bottle Was Determined to Have Been There Since Original Plant Construction.Bottle Was Removed & Security Personnel Performed Search of Area.With ML20204B5141999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Waterford 3.With ML20203H8591999-02-17017 February 1999 Safety Evaluation Accepting Licensee Second Ten Year ISI Program & Associated Relief Requests for Plant,Unit 3 ML20199H6261999-01-21021 January 1999 Safety Evaluation Accepting Classification of Instrument Air Tubing & Components for Safety Related Valve Top Works.Staff Recommends That EOI Revise Licensing Basis to Permit Incorporation of Change ML20199C9101998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Waterford 3.With ML20196F4911998-12-0101 December 1998 SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2 ML20206N4131998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Waterford 3.With ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program ML20195E5161998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Waterford 3.With ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual ML20154K0801998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Waterford 3 Ses. with ML20151W8331998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Waterford,Unit 3. with ML20237B6831998-08-17017 August 1998 LER 98-S01-00:on 980723,discovered That Waterford 3 Physical Security Plan,Safeguards Document Was Not Under Positive Control of Authorized Person at All Times.Caused by Human Error/Inappropriate Action.Counseled Employee Involved ML20237C5661998-08-17017 August 1998 Safety Evaluation Accepting Licensee Request for Exemption from Section Iii.O of Appendix R to 10CFR50 ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20237B5261998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Waterford 3 ML20236S9031998-07-22022 July 1998 SER Accepting Rev 19 to Quality Assurance Program for Waterford Steam Electric Station,Unit 3 ML20198H3911998-07-14014 July 1998 Non-proprietary Rev 5 to HI-961586, Thermal-Hydraulic Analysis of Waterford-3 Spent Fuel Pool ML20236N4181998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Waterford,Unit 3 ML20248E7781998-06-0101 June 1998 Annual Rept on Abb CE ECCS Performance Evaluation Models ML20249A4711998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Waterford 3 Ses ML20196A4051998-05-31031 May 1998 Rept of Facility Changes,Tests & Experiments,Per 10CFR50.59 for 970601-980531. with ML20198H4681998-05-20020 May 1998 Non-proprietary Rev 1 to HI-981942, Independent Review of Waterford Unit 3 Spent Fuel Pool Cfd Model ML20247A3891998-05-0101 May 1998 SG Eddy Current Examination (8th Refueling Outage) ML20247F6761998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Waterford,Unit 3.W/ ML20217M8951998-04-30030 April 1998 QA Program Manual ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) ML20216B1751998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Waterford 3 Ses ML20217M1411998-03-0303 March 1998 Rev 2 of Waterford 3 Cycle 9 Colr 1999-09-30
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Holtec Center,555 Lincoln Drive West, Mariton, NJ 08053 HOLTEC IN T E R N ATIO N A L Telephone (609) 797-0900 Fax (609) 797-0909 '
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THERMAL-HYDRAULIC ANALYSIS ,
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WATERFORD-3 SPENT FUEL POOL :
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, by Indresh Rampall, Ph.D. I Holtec Project 60994 l Holtec Report HI-961586 Report Category: I Client: Entergy Operations, Inc.
Client Contract Order: NWC00176
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, Holtec Center,555 Lincoln Drive West, Marlton, NJ 08053 HOLTEC INTERNATlONAL Telephone (609) 797-0900 Fax (609) 797-0909 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 & REVIEWER & QA APPROVEDt DIST.*
NUMBER
- DATE DATE & DATE & DATE ORIGINAL s ubCu p W4*
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7l12] Y O 26 1 YN n/ C SKP 1- > 4 95 '.W 7-u %8 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) 1 l
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
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ENCLOSURE 4 l
(Non-Proprietary Version of Attachment 1 to W3F1-98-0016, dated 1/29/98) l l
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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
1 i
ENCLOSURE 5 (Non-Proprietary Version of Attachment 3 to W3F1-98-0016, dated 1/29/98) l l
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