L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix B Additional Codes and Methods
ML110730301 | |
Person / Time | |
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Site: | Saint Lucie ![]() |
Issue date: | 02/25/2011 |
From: | Florida Power & Light Co |
To: | Office of Nuclear Reactor Regulation |
References | |
L-2011-021 | |
Download: ML110730301 (3) | |
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Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
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L-2015-091, ANP-3396NP, Revision 0, Fuel Transition Supplemental Information to Support the LAR2015-03-31031 March 2015 ANP-3396NP, Revision 0, Fuel Transition Supplemental Information to Support the LAR L-2015-093, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report2015-03-24024 March 2015 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Cover Page to Page 1092015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Cover Page to Page 109 L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-92015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-9 L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Figure 4-10 Through the End2015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Figure 4-10 Through the End ML15083A2652015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-9 ML15083A2662015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Figure 4-10 Through the End L-2014-366, ANP-3352NP, Revision 0, St. Luice, Unit 2, Fuel Transition License Amendment Request, Technical Report2014-12-31031 December 2014 ANP-3352NP, Revision 0, St. Luice, Unit 2, Fuel Transition License Amendment Request, Technical Report ML14149A1952013-02-0404 February 2013 Pacific Northwest National Laboratory Technical Letter Report for Evaluation of Alternative to 10 CFR 50.55a(G)(6)ll)(F)(4) for Limitations to Volumetric Examination of Dissimilar Metal Welds ML12340A3522012-11-30030 November 2012 St. Lucie, Unit 1, 12Q4116-RPT-001, Rev. 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Force Recommendation 2.3: Seismic L-2012-427, Q4116-R-002, Rev. 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Force Recommendation 2.3: Seismic2012-11-30030 November 2012 Q4116-R-002, Rev. 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Force Recommendation 2.3: Seismic ML12097A2682012-04-17017 April 2012 Biological Assessment for Formal Section 7 Consultation at the St. Lucie Plant, Units 1 and 2 L-2012-072, ANP-2903Q2(NP), Rev 0, St. Lucie, Unit 1 - EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding, Attachment 32012-02-29029 February 2012 ANP-2903Q2(NP), Rev 0, St. Lucie, Unit 1 - EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding, Attachment 3 ML12061A2492012-02-29029 February 2012 ANP-3067, Rev. 1, St. Lucie, Unit 1 EPU - Information to Support NRC Review of RCS Depressurization with Pressurizer Overfill L-2012-072, ANP-3067, Rev. 1, St. Lucie, Unit 1 EPU - Information to Support NRC Review of RCS Depressurization with Pressurizer Overfill2012-02-29029 February 2012 ANP-3067, Rev. 1, St. Lucie, Unit 1 EPU - Information to Support NRC Review of RCS Depressurization with Pressurizer Overfill L-2011-471, ANP-3057(NP), Revision 0, St. Lucie Unit 1 EPU - Responses to NRC Questions SRXB-58, SRXB-59, and SRXB-60.2011-10-31031 October 2011 ANP-3057(NP), Revision 0, St. Lucie Unit 1 EPU - Responses to NRC Questions SRXB-58, SRXB-59, and SRXB-60. L-2011-389, Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2011-09-22022 September 2011 Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request L-2011-311, ANP-3019NP, Revision 0, St. Lucie Unit 1 EPU - Information to Support NRC Review of Steam Generator Tube Rupture, Attachment 22011-08-31031 August 2011 ANP-3019NP, Revision 0, St. Lucie Unit 1 EPU - Information to Support NRC Review of Steam Generator Tube Rupture, Attachment 2 L-2011-342, ANP-3028(NP), Revision 0, St. Lucie Plant, Unit 1 EPU RAIs - Nuclear Performance & Code (Snpb)2011-08-31031 August 2011 ANP-3028(NP), Revision 0, St. Lucie Plant, Unit 1 EPU RAIs - Nuclear Performance & Code (Snpb) L-2011-228, 103-87735, Heated Water Plan of Study2011-06-30030 June 2011 103-87735, Heated Water Plan of Study L-2011-206, ANP-2903(NP), Revision 1, St. Lucie Nuclear Plant, Unit 1 - EPU Cycle Realistic Large Break LOCA Summary Report with ZR-4 Fuel Cladding, Attachment 72011-05-31031 May 2011 ANP-2903(NP), Revision 1, St. Lucie Nuclear Plant, Unit 1 - EPU Cycle Realistic Large Break LOCA Summary Report with ZR-4 Fuel Cladding, Attachment 7 ML11153A0492011-05-31031 May 2011 ANP-3000(NP), Rev. 0, St. Lucie Nuclear, Unit 1 - EPU-Information to Support License Amendment Request, Attachment 6 L-2011-206, ANP-3000(NP), Rev. 0, St. Lucie Nuclear, Unit 1 - EPU-Information to Support License Amendment Request, Attachment 62011-05-31031 May 2011 ANP-3000(NP), Rev. 0, St. Lucie Nuclear, Unit 1 - EPU-Information to Support License Amendment Request, Attachment 6 L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix D, List of Key Acronyms2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix D, List of Key Acronyms L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix B Additional Codes and Methods2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix B Additional Codes and Methods ML1107302992011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Licensing Report L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix a Safety Evaluation Report Compliance2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix a Safety Evaluation Report Compliance L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix F, Camereron Ultrasonics Engineering Reports, Cover2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix F, Camereron Ultrasonics Engineering Reports, Cover L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix E, Supplement to Licensing Report Section 2.4.1 Reactor Protection, Engineered Safety Feature Actuation, and Control Systems2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix E, Supplement to Licensing Report Section 2.4.1 Reactor Protection, Engineered Safety Feature Actuation, and Control Systems L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix G, Holtec Report No. HI-2104753, St. Lucie Unit 2 Criticality Analysis for EPU and Non-EPU2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix G, Holtec Report No. HI-2104753, St. Lucie Unit 2 Criticality Analysis for EPU and Non-EPU L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5, Appendix C, Grid Stability Analysis and System Impact Study for St. Lucie Plant with Proposed EPU2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5, Appendix C, Grid Stability Analysis and System Impact Study for St. Lucie Plant with Proposed EPU 2022-04-13 |
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St. Lucie Unit 2 EPU Licensing Report App. B-1Additional Codes and MethodsSt. Lucie Unit 2L-2011-021Docket No. 50-389Attachment 5St. Lucie Unit 2Extended Power UprateLicensing ReportAttachment 5Appendix BAdditional Codes and MethodsThis cover sheet plus 2 pages St. Lucie Unit 2 EPU Licensing Report App. B-2Additional Codes and MethodsSt. Lucie Unit 2L-2011-021Docket No. 50-389Attachment 5APPENDIX BADDITIONAL CODES AND METHODSIn addition to the codes and methods listed in Appendix A 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 MethodsCODEAPPLICATIONANETHThe ANETH computer code is a one-dimensional code which was used for water level instability analysis. BULKTEMThis code was used to calculate the decay heat produced in the spent fuel pool by the recently off-loaded fuel. CHECWORKS-SFAThis code was used to determine Flow Accelerated Corrosion (FAC) predictions.CENTSThis code was used to perform Nuclear Steam Supply System (NSSS) modeling.CAFTAThe Computer Assisted Fault Tree Analysis (CAFTA) code was used in the modeling, development and maintenance of fault tree models.FLUENTGeneral Purpose Computational Fluid Dynamics (CFD) Program. HRA HRA Calculator is a software tool which was used to facilitate a standardized approach to human reliability analysis (HRA).LONGORThis code was used to quantify the decay heat produced by previously off-loaded fuel. LASERThis code was used to estimate flux depression in fuel. MAAPThe Modular Accident Analyses Program (MAAP) simulates plant response to severe accidents given a set of initiating events and operator actions. This code was used to support development of the St. Lucie Probabilistic Risk Analysis (PRA).MCNP5This code was used to perform criticality analysis. NSSSPlusThis code was used to generate Performance Capability Working Group (PCWG) design sheets.ORIGEN 2.1This code was used to support the determination of core inventory nuclides for dose calculations.ORIGEN2This code was used to support the determination of core inventory nuclides for decay heat calculations. PITRUST-PCPITRUST-PC is a computer program which was used to calculate local stress intensity at the junction of two cylindrical vessels.
St. Lucie Unit 2 EPU Licensing Report App. B-3Additional Codes and MethodsSt. Lucie Unit 2L-2011-021Docket No. 50-389Attachment 5PILUG-PCPILUG-PC is a computer program which was used in support of the analysis of local stresses at the connection of rectangular lugs to piping.PITRIFEPITRIFE is a computer program which was used to perform analysis of local stresses at the connection of round trunnions to piping.PERFGVThis program was used to provide performance and thermal-hydraulic parameters of U-tube type steam generators for BOL and EOL conditions at various power levels.PLAQUE TUBULAIREThis program was used to determine stresses taking into account the stress concentration factors associated with the tubesheet hole pattern.PLSCADDThis program was used to perform sag-tension analysis of overhead power lines.PSS/EThis computer program was used to perform power flow analysis of the post transient condition for outage events.RCCM-ASMEThis code was used to calculate the linearized stress intensity range and fatigue usage factor in accordance with ASME Section III, Subsection NB. SYSNUKEThis code was used to determine the stress field including temperature variation and stress distribution.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 valve closure and feedwater pump trip events.TableB-1Additional Codes and MethodsCODEAPPLICATION