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US-APWR 3rd Pre-Application ReView Meeting
US-APWR 3rd Pre-Application ReView Meeting November 28 & 29, 2006 Mitsubishi Heavy Industries, Ltd. LM ITSBUBISHIaHEAV•=Y--IIN DUS-TRIES, LTD.- UAP-HF-06 023 APS4 Introduction Masayuki Kambara E-ngineering Manger IkPWR Promoting Department IEMITSU BIS HUIHEAVZYJ•INI)USTR IES, LTD. UAP-HF-06023-1 Meeting Objectives (fAPS4 To propose revised plan for pre-application review meeting and submittal of Topical Reports to reflect comments of NRC staff ,To provide the contents of Topical Reports and to obtain feedback from the NRC / November 28 " AM: Digital I & C System, HFE Process and HSI System Design " PM: Quality Assurance Program Description for Design Certification of the US-APWR / November 29 Advanced AccumLJlator TISUBISHIH.EAVYINDUSTERIES, LTD. UAP-HF-06023-2 QA PS Revised Plan of Pre-Application Review Meeting and Topical Reports Submittal MI1LSUBISHI-HEAVYINDUSTRIES, LTD. UAP-H F-0O6023-3 Revised Plan of Pre-Application Review Meeting and Topical Reports Submittal 78 9 ~~11 12 10 Pre-Applicatio n Review Meeting N. .Advanced i Safety Vi Design Philosophy Design :Features ACC Topical Report pre-rot submittal meeting I &C Topical ,Reports Pannrwteot I1 MIES, 2 5 4 3 6 7 8 9 1 DC i NV I N No.4 o2No.3 Design] 1 (S1 o1 No. - Advanced A curiuantdaor EFWS, CN No.11I No.12 No.13 Application Other Safety ECCS with Submittal o Advanced Accumplator Topical 9 No.8 No 7 i !• Features PatD sg Safety Design ring mco Base s Safety Analysis Submittals of I&C I and HFE Topical " 'nil (FeMar.) I (eJa. LHSI Electrical Submittal of Topical Report LTD. : Meeting Subjects 111IM-000a UAP-HF-06023-4 Revised Pre-Application Review Meeting Plan Meeting Subject - Mitsubishi Nuclear Activities - US-APWR Overview - Revised Pre-Application Review Meeting Plan Topical Report Submittals Plan Safety Design Philosophy US-APWR Design Features Computer Codes and Methodology Used - for Safety Analysis Topical Report Pre-submittal Meeting Advanced Accumulator - Meeting Objectives - Introduce MHI nuclear activities and US-APWR - Propose the review meeting Date July 2006 and topical report schedule - Provide a more extensive technical discussion to demonstrate the design is similar to US current PWR September 2006 plant -Identify the form and contents of the topical report - Provide a more extensive November 2006 technical discussion Topical Report Pre-submittal Meeting - Digital Platform - Safety System Design Process and Description - Identify the form and coIdentif thef orm November contents of the topical reports 2006 contents of the topical report 20061- - Defense-in Depth and Diversity - HFE Process and HSI System Design Topical Report Pre-submittal Meeting - Quality Assurance Program Description for Design. Certification of the US-APWR &A 1--TIS-UStStil--tiEAlCY71ND-U-STRIES, LTD. TD.UAP-H ~EMI~jJBSHIHEA~YINISTRES, F-06023-5 Revised Pre-Application Review Meeting Plan - Core and Fuel Design Overview Date Meeting Objectives Meeting Subject -Clarify necessary actions before the DC application Topical Report Pre-submittal Meeting January - Fuel System Design Criteria and 2007 Methodology - Thermal Design Methodology -Identify the form and contents of the topical reports Topical Report Pre-submittal Meeting - Large Break LOCA Analysis Methodology - Non-LOCA Analysis Methodology -Identify the form and contents of the topical reports -Explain codes used in analysis for January 2007 Large Break LOCA and Non- LOCA - Severe Accident Analysis Methodology Overview -Explain codes used in analysis for Severe Accident - Probabilistic Risk Assessment -Explain codes, database and key February Methodology - Radiation Dose Analysis Methodology assumption of the PRA -Explain codes and key assumption of the Radiation dose 2007 analysis methodology iN,-_-NFVUW1SH1=HE A-W-YaINW1ASXRIES, LTD. MITSUBISHIHEAVY~INDUSTRIES, LTD. V UAP-HF-06023-R UAP-H -06023-6 I •l m I m Revised Pre-Application Review Meeting Plan Meeting Subject Meeting Objectives (fAPS4 Date - Safety Related Features (ECCS, EFWS, Containment Vessel) -Provide a more specific discussion on safety related features - Including safety Design Bases concerning Safety Analysis - Discuss the NRC comments after March 2007 the NRC staff has read the - Advanced Accumulator Topical advanced accumulator topical Report report - Small Break LOCA Analysis -Explain codes used in analysis for Methodology Topical Report Presubmittal Meeting Small Break LOCA -Identify the form and contents of the topical report - CV Response Analysis Methodology - March 2007 2007 Explain- codes and key assumption of the Containment Response Analysis methodology II ýA Tý&U-BISHI=HEAIU=Y:-:ýINWU-SI-RPES, MITSUBISHIZHEAVY-UNDUSTRIES, LTD. LTD. UAP-HF-06023-7 F-06023-7 UAP-H Revised Pre-Application Review Meeting Plan - Electrical and I & C System Date Meeting Objectives Meeting Subject -Provide plant-wide architecture and system level design and Design Criteria function of safety related I & C - Overall I & C and Safety System April - Digital Platform Topical Report - Safety I&C System Design Process the Digital Platform and Safety I & C System topical reports and Description Topical Report Provide HSI concept and system level design of other important I & C and safety - Human System Interface - Other Important I & C Systems - Safety Grade 1E Electrical Power Defense-in-Depth and Diversity (D3) May 2007 electrical system System - 2007 -Discuss the NRC comments after the NRC staff has read - Discuss the NRC comments after the NRC staff has read the HFE and D3 topical reports Topical Report -HFE Process and HSI System Design Topical Report Jr Severe accident mitigation design - Explain schematic system features and evaluation methodology T:SUSISHI=-HEAIU-Y=!MD-U-S-T-RIES, LTD. MUT'SJJBISHIZHEAV-Y--INDUSTRIES, LTD. description and their effectiveness evaluation method June 2007 2007 UAP-HF-06023-8 UAP-H F-06023-8 Revised Pre-Application Review Meeting Plan Meeting Objectives Meeting Subject - Fuel System Design Criteria and - Discuss the NRC comments Methodology Topical Report after the NRC staff has read Thermal Design Methodology Topical the topical reports A PS4 Date July 2007 Report - - Other Safety Features - Provide a .more specific (Safety shutdown system, SBO mitigation system etc.) discussion on other safety features and plant design Plant Design Concepts concepts August 2007 (Plant Layout, Separation Criteria, Steel & Concrete Structure) - Safety Analysis Methodologies - Topical Report - Final Overall Review Meeting - LTD. %ý--Ml-='US-U-BISHI-HEA-IU-Y719WU-ST-lk!ES, ~MU1LSUBISHI HEAVY-INDUSTRIES, LTD. Discuss the NRC comments after the NRC staff has read the topical report September 2007 Summarize the NRC November 2007 comments and discussion UAP-HF-06023-9 UAP-H F-06023-9 Revised Topical Reports Submittal Plan Topical Report (APE Date Quality Assurance Program Description for Design Certification of the US-APWR January 2007 Advanced Accumulator January 2007 Digital Platform February 2007 Safety I&C System Design Process and Description February 2007 Defense-in-Depth and Diversity March 2007 HFE Process and HSI System Design March 2007 Fuel System Design Criteria and Methodology May 2007 Thermal Design Methodology May 2007 Safety Analysis Methodology (LBLOCA, SBLOCA) July 2007 Safety Analysis Methodology (Non-LOCA) July 2007 -US-TRIES, LTD. II%aJ411-TS UB1SHL=HEAVM-1ND I~MILSUBSHLHAVYUDU5TIESLTD.UAP-HF-06023-10 Next Steps ýSubmittal of Topical Reports in January 2007 /Quality Assurance Program Description for Design Certification of the US-APWR /Advanced Accumulator >Meetings in January 2007 /Core and Fuel Design Overview -'Topical Report Pre-submittal Meeting * Fuel System Design Criteria and Methodology * Thermal Design Methodology * Large Break LOCA Analysis Methodology * Non-LOCA Analysis Methodology MITSUBISHIHEAVY-INDUSTRIES, LTD. UAP-HF-06023-11