ML16256A128

Waterford Steam Electric Station, Unit 3, Revision 309 to Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant, Section 1.6

ML16256A128
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Site:	Waterford
Issue date:	08/25/2016
From:	Entergy Operations
To:	Office of Nuclear Reactor Regulation
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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

Coatings in CE Nuclear Power

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)