ML16256A128
| ML16256A128 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 08/25/2016 |
| From: | Entergy Operations |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML16256A115 | List:
|
| References | |
| W3F1-2016-0053 | |
| Download: ML16256A128 (6) | |
Text
WSES-FSAR-UNIT-31.6-11.6MATERIAL INCORPORATED BY REFERENCEThe following topical reports are incorporated by reference.ReportFSARNumberAuthor and Title Date to NRCSectionCENPD-26Combustion Engineering, Inc.August 19713.6, 6.2(with Suppl."Description of Combustion 1 through 5)Engineering Loss of CoolantCalculational Procedures"CENPD-42Combustion Engineering, Inc.August 19723.6"Dynamic Analysis of Reactor Vessel Internals Under Loss of Coolant Accident Conditions with Application to C-E 800 Mwe Class Reactors"CENPD-67Combustion Engineering, Inc.September 197310.3(with Suppl."Iodine Decontamination 1 and 2 andFactors During PWR Steam Addenda 1Generation and Steam Venting" and 2)CENPD-87"Safety Related Research Development1.5for CE PWRs, Program Summaries"CENPD-98Combustion Engineering, Inc.July 19734.4, 15.0"Coast Code Description"CENPD-105Combustion Engineering, Inc.June 19734.3"Fast Neutron Attenuation by the ANISN-SHADRAC Analytical Method"CENPD-107Combustion Engineering, Inc.August 197415.0(with Suppl."CESEC" 1 through 4)CENPD-118Combustion Engineering, Inc.September 19744.3"Densification of CombustionEngineering Fuel"CENPD-132Combustion Engineering, Inc.September 19746.2, 15.6(with Suppl."Calculative Methods for the6.3 1 and 2)C-E Large Break LOCA Evaluation Model" WSES-FSAR-UNIT-3 1.6-2 Revision 11-A (02/02)
Report FSARNumberAuthor and Title Date to NRC Section CENPD-133 Combustion Engineering, Inc.
September 1974 6.2, 15.6 (with"CEFLASH-4A Fortran IV6.3Suppl. 2)Digital Computer Program for Reactor Blowdown Analysis" CENPD-134 Combustion Engineering, Inc.
September 1974 6.2, 15.6 (with"COMPERC-II A Program for6.3 Suppl. 1)Emergency Refill-Reflood of the Core" CENPD-135Combustion Engineering, Inc.September 19744.2, 6.3, (with"STRIKIN-II A Cylindrical 15.6 Suppl.Geometry Fuel Rod Heat2 and 4)Transfer Program" CENPD-136 Combustion Engineering, Inc.
September 1974 4.2, 15.6"High Temperature Properties
of Zircaloy and UO 2 , for use in LOCA Evaluation Model" CENPD-137 Combustion Engineering, Inc.
September 1974 6.3, 15.6 (with"Calculative Methods for theSuppl. 1)C-E Small Break LOCA Evaluation Model"(DRN 01-758)
CENPD-138"PARCH, A FORTAN IV Digital Program February 1975 15.6 to Evaluate Pool Boiling, Axial Rod and Coolant Heatup" (with Supplement 1)(DRN 01-758)
CENPD-139Combustion Engineering, Inc.September 19744.1, 4.2, (with"C-E Fuel Evaluation Model" 4.3, 6.3 Suppl. 1)CENPD-145Combustion Engineering, Inc.April 1975 4.3, 7.7"A Method of Analyzing
In-Core Detector Data in Power Reactors" CENPD-148 Combustion Engineering, Inc.November 19744.6"Review of Reactor Shutdown
System (PPS Design) for Common Mode Failure Susceptibility" CENPD-153 Combustion Engineering, Inc.August 19744.3"Evaluation Uncertainty in
the Nuclear Form Factor WSES-FSAR-UNIT-3ReportFSARNumberAuthor and Title Date to NRCSection1.6-3CENPD-153Measured by Self Powered(cont)Fixed In-Core DetectorSystems"CENPD-155Combustion Engineering, Inc.October 19745.3"C-E Procedure for Design, Fabrication, Installation and Inspection of Surveillance Specimen Brackets Attached toReactor Vessel Beltline Region"CENPD-161Combustion Engineering, Inc,June 19754.1, 4.2,"TORC - A Computer Code for4.4, 15.0 Determining the Thermal Marginof a Reactor Core"CENPD-162Combustion Engineering, Inc.May 19754.4(with"CHF Correlation for C-E FuelSuppl. 1)Assemblies with StandardSpacer Grids - Part 1; Uniform Axial Power Distribution"CENPD-168Combustion Engineering, Inc.September 19763.6, 6.2Rev. 1"Design Basis Pipe Breaksfor the Combustion Engineering Two Loop Reactor Coolant System"CENPD-169Combustion Engineering, Inc.August 19754.3, 7.2"Assessment of the Accuracy7.7 of PWR Operating Limits as Determined by Core Operating Limit SupervisorySystem"CENPD-170Combustion Engineering, Inc.August 19757.2"Assessment of the Accuracy of the PWR Safety System Actuation as Performed by the Core Protection Calculators"CENPD-178PCombustion Engineering, Inc.October 19763.9, 4.2and 178"Structural Analysis of the16 x 16 Fuel Assembly for Combined Seismic and Loss-of-Coolant-Accident Loadings" WSES-FSAR-UNIT-3ReportFSARNumberAuthor and Title Date to NRCSection1.6-4CENPD-179Combustion Engineering, Inc.April 19764.2"C-E Thermo-Structural Fuel
Evaluation Method"CENPD-183Combustion Engineering, Inc.August 197515.0"C-E Methods for Loss of15.3 Flow Analysis"CENPD-187Combustion Engineering, Inc.October 19754.2(with"Method of Analyzing CreepSuppl. 1)Collapse of Oval Cladding"CENPD-190Combustion Engineering, Inc.January 197615.4"C-E Method for Control Element Assembly Ejection Analysis"CENPD-198PCombustion Engineering, Inc.December 19754.2and 198"Zircaloy Growth-In-ReactorDimensional Changes in Zircaloy-4 Fuel Assemblies"CENPD-206Combustion Engineering, Inc.December 19764.4"Comparison of TORC Code Predictions with Experimental
Data"CENPD-207Combustion Engineering, Inc.June 19764.4"Critical Heat Flux Corre-lation for C-E Fuel Assemblies with Standard Spacer Grids, Part 2, Non-Uniform Axial PowerDistributions"CENPD-213Combustion Engineering, Inc.February 19766.3, 15.6"Application of FLECHT Reflood Heat Transfer Coefficients to Combustion Engineering 16 x 16 Fuel Bundles"CENPD-225PCombustion Engineering, Inc.October 19764.2, 4.4and 225"Fuel and Poison Rod Bowing"CENPD-252"Method for the Analysis of BlowdownJuly 19793.9E WSES-FSAR-UNIT-3 1.6-5 Revision 304 (06/10)
Report Number Author and Title Date to NRC FSAR Section WCAP 7709-L Electric Hydrogen Recombiners for PWR Containments
April 1972 6.2.5 (DRN 03-2054, R14)
CEN-367-A Combustion Engineering, Inc.
Leak-Before-Break of Primary
Coolant Loop Piping in Combustion
Engineering Designed Nuclear
Steam Supply System
February 1991 3.6 (DRN 03-2054, R14)
(EC-13881, R304)
WCAP-11596-P-A Westinghouse Electric Company, Qualification of the PHOENIX -
P/ANC Nuclear Design System for
Pressurized Water Reactor Cores
June 1988 4.2, 4.3A, 15.1 WCAP-10965-P-A Westinghouse Electric Company, ANC: A Westinghouse Advanced Nodal
Computer Code
September 1986 4.2, 4.3A, 15.1 WCAP-10965-P-A Addendum 1 Westinghouse Electric Company, ANC: A Westinghouse Advanced Nodal
Computer Code:
Enhancements to ANC Rod Power
Recovery
April 1989 4.2, 4.3A, 15.1 WCAP-16045-P-A Westinghouse Electric Company, Qualification of the Two-
Dimensional Transport Code
- PARAGON,
August 2004 4.3A WCAP-16072-P-A Westinghouse Electric Company, Implementation of Zirconium
Diboride Burnable Absorber
Fuel Assembly Designs
August 2004 4.2, 4.3A CENPD-404-P-A Combustion Engineering, Inc., Implementation of ZIRLO Material
Cladding in CE Nuclear Power
Fuel Assembly Designs,
November 2001 4.2, 4.3A, 15.0 WCAP-16500-P-A Westinghouse Electric Company, CE 16 x 16 Next Generation Fuel
Core Reference Report,
August 2007 4.2, 4.3A WCAP-12610-P-A and CENPD-404-
P-A Addendum 1-
A Westinghouse Electric Company, Optimized ZIRLO TM , July 2006 4.2, 4.3A, 15.0 EC-13881, R304)
WSES-FSAR-UNIT-3 1.6-6 Revision 305 (11/11)
(EC-13881, R304)
Report Number Author and Title
Date to NRC FSAR Section WCAP-16523-P-
A Westinghouse Electric Company,
"Westinghouse Correlations
WSSV and WSSV-T for Predicting
Critical Heat Flux in Rod Bundles
with Side-Supported Mixing
Vanes,"
August 2007 4.4, 15.0, 15.1, 15.2, 15.3, 15.4 CENPD-387-P-A Combustion Engineering, Inc., "ABB Critical Heat Flux Correlations for PWR Fuel,"
May 2000 4.3A, 15.0 WCAP-15996-P-
A, Rev. 1 Westinghouse Electric Company, "Technical Manual for the CENTS
Code,"
March 2005 15.0, 15.1, 15.2, 15.3, 15.4 CEN-356(V)-P-A, Revision 01-P-A Combustion Engineering, Inc.,
"Modified Statistical Combination
of Uncertainties, May 1988 4.2, 4.3A (EC-13881, R304)
(EC-19087, R305)
WCAP-17817-P Technical Justification for Eliminating Pressurizer Surge Line Rupture as the
Structural Design Basis for Waterford Steam
Electric Station, Unit 3 Using Leak-Before-
Break Methdology February 2010 3.6.3 (EC-19087, R305)