L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 04; Appendix B, Additional Codes and Methods

Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 04; Appendix B, Additional Codes and Methods

ML103560179
Person / Time
Site:	Turkey Point
Issue date:	12/14/2010
From:	Florida Power & Light Co
To:	Office of Nuclear Reactor Regulation
References
L-2010-113, L-2010-299, LAR 205
Download: ML103560179 (4)

Text

Turkey Point Units 3 and 4 EPU Licensing Report App. B-1 Additional Codes and MethodsTurkey Point Units 3 and 4L-2010-113Docket Nos. 50-250 and 50-251Attachment 4Turkey Point Units3 and4Extended Power UprateLicensing ReportAttachment4AppendixBAdditional Codes and MethodsThis coversheet plus 3pages Turkey Point Units 3 and 4 EPU Licensing Report App. B-2 Additional Codes and MethodsTurkey Point Units 3 and 4L-2010-113Docket Nos. 50-250 and 50-251Attachment 4APPENDIXBADDITIONAL CODES AND METHODSIn addition to the codes and methods listed in AppendixA of this Licensing Report (LR), numerous analytical codes and methods were used to support the Turkey Point Units 3 and 4 Extended Power Uprate (EPU). These have been reviewed against the codes and methods currently described in the UFSAR. The information presented below represents the set of key codes used that do not currently reside in the UFSAR as well as their associated application. All of these codes/methods have been determined by Florida Power and Light to be appropriate for use in their respective applications.CODEAPPLICATIONABB-NVThis is a DNB correlation for fuel assembly spans below the first mixing grid in the uncontrolled rod cluster control assembly withdrawal from subcritical transient analysis. See LR Section2.8.3.ARCON96This code is used in the Alternative Source Term calculations of the radiological consequences of accidents. See LR Section2.9.2. ANSYS/MechanicalThis code is PC based QA CategoryI general purpose finite element analysis program capable of performing static, model dynamic, response spectrum, time history and harmonic structural analysis. See LR Section2.2.2.2.ASTRUMThis code (Automated Statistical Treatment of Uncertainty Method) is the uncertainty model in developing the peak cladding temperature (PCT) in the best estimate large-break LOCA analysis. See LR Sections2.8.5.6.3.2 and2.6.6.ATHOSThis code consists of a suite of sequentially executed modules that performs steady state analysis of steam generator tube bundle thermal-hydraulics. See LR Section2.2.2.5.CHECKWORKSThis code is a used to predict the loss of material due to flow accelerated corrosion. See LR Section2.1.8.EPITOMEThis code was used in the calculation of LOCA mass and energy releases. Although not described in the UFSAR, it was also used for this purpose in the current licensing basis. See LR Section2.6.3.1.FERRETThis code is used to determine reactor fluence values. See LR Sections2.1.1, 2.1.2 and2.1.3.GENFThis code is used to perform a steady state thermal-hydraulic analysis of the entire steam generator. See LR Section2.2.2.5.GOTHICThis code is used to calculate the containment response following a postulated LOCA or steamline break. See LR Section2.6.1. It was also used to calculate the LOCA long-term post-reflood releases. See LR Section2.6.3.1.

Turkey Point Units 3 and 4 EPU Licensing Report App. B-3 Additional Codes and MethodsTurkey Point Units 3 and 4L-2010-113Docket Nos. 50-250 and 50-251Attachment 4LOFTRANThis code was used at PTN for the first time for the following EPU analyses: to analyze the NSSS response to design basis operational transients. See LR Section2.4.2; to analyze design basis operational transients to determine pressure control component sizing. See LR Section2.4.3. In addition, LOFTRAN was used to support the ATWS analyses in the current licensing basis as described in LR Section2.8.5.7.1. Also see LR Section2.2.6.MICROSHIELDThis code is used in the Alternative Source Term calculations of the radiological consequences of accidents. See LR Section2.9.2.MULTIFLEX 3.0This code was used to calculate the LOCA hydraulic forcing functions. See LR Section2.8.1 and LR Section2.8.5.6.3.5.NSSSPLUSThis code is used to facilitate the determination of NSSS design parameters. See LR Section1.1.NUPIPE-SWPCThe NUPIPE-SWPC was used to perform detailed pipe stress analysis. This program is designed to perform analyses in accordance with the ASME Boiler and Pressure Vessel Code, SectionIII and the ANSIB31.1 Power Piping Code. See LR Section2.2.2.2.PARAGONFuel management code for depletion calculations.

PAVANThis code is used in the Alternative Source Term calculations of the radiological consequences of accidents. See LR Section2.9.2.PERC2This code was used to model the activity, transport and calculate the offsite doses for the Spent Fuel Pool accident at EPU conditions.pc-CRACKThis is a fracture mechanics software program used to conduct the crack growth analysis in the Leak-Before-Break evaluation for the Accumulator, pressurizer surge and residual heat removal lines. See Attachment12, Structural Integrity Associates Leak-Before-Break evaluation for the Accumulator, Pressurizer Surge and Residual Heat Removal Lines Turkey Point Units3 and4 dated April2010.PC-PREPSThis is a PC based computer program which performs a complete structural analysis, performing an AISC Code check, weld qualification and baseplate/anchor bolt qualifications. See LR Section2.2.2.2.RADTRAD-NAIThis code is used in the Alternative Source Term calculations of the radiological consequences of accidents. See LR Section2.9.2.RETRANThis code is used in the EPU analyses of: excessive increase in steam flow (LR Section2.8.5.1.1); steam line break (LR Section2.6.3.2 and Section2.8.5.1.2); loss of external electric load (LR Section2.8.5.2.1);

loss of all AC (LR Section2.8.5.2.2); loss of normal feedwater flow (LR Section2.8.5.2.3); loss of reactor flow (LR Section2.8.5.3.1); locked rotor incident (LR Section2.8.5.3.2); and uncontrolled rod withdrawal at power (LR Section2.8.5.4.2).CODEAPPLICATION Turkey Point Units 3 and 4 EPU Licensing Report App. B-4 Additional Codes and MethodsTurkey Point Units 3 and 4L-2010-113Docket Nos. 50-250 and 50-251Attachment 4SBLOCTAThis code is used to analyze the thermal-hydraulic responses to the small break LOCA for their for their effect on the hot rod heat-up to demonstrate that the peak cladding temperature, cladding oxidation and hydrogen generation are below their limiting values as defined by 10CFR50.46. See LR Section2.8.5.6.3.3.SCALE/KENOSpent fuel pool criticality calculations.

STEHAM-PCThis was used to determine forcing functions for the main steam isolation valve (MSIV) closure and a turbine stop valve (TSV) closure events. It determines forcing functions in steam filled piping systems due to valve opening and closing conditions. See LR Section2.2.2.2.THRIVEThis code is used to determine the distribution of pressure and flow within the reactor vessel, internals and the reactor core. See LR Section2.2.3.VIPREThis is a sub-channel analysis code used in the thermal-hydraulic DNB analyses. It is used in the following EPU analyses: to support operation with Upgrade fuel (LR Section2.8.3); excessive heat removal due to feedwater malfunction transient (LR Section2.8.5.1.1); loss of forced reactor flow (LR Section2.8.5.3.1); reactor coolant pump locked rotor/shaft break (LR Section2.8.5.3.2); uncontrolled rod cluster control assembly withdrawal from subcritical or low power during startup (LR Section2.8.5.4.1); and control rod misoperation (LR Section2.8.5.4.3).WATHAM-PCThis was used to determine forcing functions for the feedwater regulatory valve and isolation valve closure and feedwater pump trip events. It determines forcing functions in water filled piping systems due to pump start/stop/trip, check valve closure and valve opening and closing events. See LR Section2.2.2.2.WEGAPThis code is used to analyze fuel transient loadings. See LR Section2.8.1.WLOPThis is a DNB correlation used in the core and reactor coolant system design analyses. See LR Section2.8.3.CODEAPPLICATION