L-2010-259, St. Lucie, Unit 1 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix B, Additional Codes and Methods

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St. Lucie, Unit 1 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix B, Additional Codes and Methods
ML103560431
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 12/15/2010
From:
Florida Power & Light Co
To:
Office of Nuclear Reactor Regulation
References
L-2010-259
Download: ML103560431 (3)


Text

St. Lucie Unit 1 EPU Licensing Report App. B-1 Additional Codes and MethodsSt. Lucie Unit 1L-2010-259Docket No. 50-335Attachment 5St. Lucie Unit1Extended Power UprateLicensing ReportAttachment5AppendixBAdditional Codes and MethodsThis coversheet plus 2 pages St. Lucie Unit 1 EPU Licensing Report App. B-2 Additional Codes and MethodsSt. Lucie Unit 1L-2010-259Docket No. 50-335Attachment 5APPENDIXBADDITIONAL CODES AND METHODSIn addition to the codes and methods listed in AppendixA of this LR, numerous analytical codes and methods were used to support the 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 & Light to be appropriate for use in their respective applications.TableB-1Additional Codes and MethodsCODEAPPLICATIONAUTORLBLOCAThe AUTORLBLOCA code is used for generation of ranged parameter values, transient input, transient runs and general output documentation.CAFTAThe Computer Assisted Fault Tree Analysis (CAFTA) code is used in the modeling, development and maintenance of fault tree models.CENTSThis code was used to perform Nuclear Steam Supply System (NSSS) modeling.CHECWORKS SFAThis code was used to determine Flow Accelerated Corrosion (FAC).

FLOOD3 Mod2This code was used to calculate Mass and Energy (M&E) releases from postulated Reactor Coolant System (RCS) pipe ruptures.GOTHICThis code was used for various applications including determining Shield Building annulus pressure, Emergency Core Cooling ventilation reviews and Refueling Water Tank temperatures.HRAHRA Calculator is a software tool designed to facilitate a standardized approach to human reliability analysis (HRA).MAAPThe Modular Accident Analyses Program (MAAP) simulates plant response to severe accidents given a set of initiating events and operator actions. This code is used to support development of the St.

Lucie Probabilistic Risk Analysis (PRA).MCNP5MCNP5 was the principal method used for the criticality analysis of the fuel pool storage racks.NSSSPlusThis code was used to generate Performance Capability Working Group (PCWG) design sheets.ORIGEN2.1This code was used to support the determination of core inventory nuclides.ORIGEN2.2.1This code is used to calculate EPU core inventory.PIPESTRESSThis code was used to perform pipe stress analysis.

St. Lucie Unit 1 EPU Licensing Report App. B-3 Additional Codes and MethodsSt. Lucie Unit 1L-2010-259Docket No. 50-335Attachment 5PITRUST-PCThis code was used to obtain local pipe stresses in accordance with Welding Research Council (WRC) No.107 at trunnions and branch pipe exits.RADTRAD-NAIThis code was used to perform Alternate Source Term (AST) dose consequence analysis.RELAP5This code was used to determine forcing functions for the Power Operated Relief Valve (PORV) opening event.RODEX2-2AThis code was used to determine the burnup-dependent initial fuel rod conditions.STEHAM-PCThis code was used to determine forcing functions for a main steam isolation valve (MSIV) closure event and a turbine stop valve (TSV) closure fluid transient event.WATHAM-PCThis code was used to determine forcing functions for the feedwater regulating valve, isolation closure and feedwater pump trip events.TableB-1 (Continued)Additional Codes and MethodsCODEAPPLICATION