HITACHI. GE Hitachi Nuclear Energy. Subject:
|
|
|
- Stewart Wilkerson
- 5 years ago
- Views:
Transcription
1 HITACHI GE Hitachi Nuclear Energy Richard E. Kingston Vice President, ESBWR Licensing Regulatory Affairs P.O. Box 780 M/C A-55 Wilmington, NC USA MFN November 4, 2008 T F rick.kingston@ge.com Docket No U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC Subject: Update to the Integrated Plan and Schedule - Responses to NRC Requests for Additional Information (RAts) and Licensing Topical Reports In Reference 1, GE Hitachi Nuclear Energy (GEH) provided an updated submittal schedule for responding to open RAIs supporting completion of ESBWR Design Certification. The purpose of this letter is to provide dates for remaining outstanding RAI responses and Licensing Topical Report (LTR) submittals in order that the NRC may publish a schedule for review of the ESBWR Design Certification and rulemaking. Enclosure 1 provides the dates for outstanding RAIs and LTRs. In addition, GEH understands that the NRC will essentially conclude developing RAIs for Revision 5 of the Design Control Document (submitted by GEH June 1, 2008) by mid-november We recognize that the NRC may subsequently identify supplemental RAIs and may request additional information for resolving open items. For these RAIs that the NRC has not yet issued, GEH will respond within the 90-day period established for RAI responses by our letter of July 7, 2008 (Ref. 2). On this basis, GEH expects to submit all outstanding RAI responses by mid-february 2009 and proceed toward completion of and submittal to the NRC Revision 6 of the Design Control Document (DCD) by the end of June This schedule is based on GEH and the NRC resolving all outstanding open items for the DCD by May 1, GEH intends that Revision 6 would be the basis for the NRC Final Safety Evaluation Report for review by the Advisory Committee on Reactor Safeguards.
2 Page 2 of 2 If you have any questions or require additional information, please contact me. Sincerely, Richard E. Kingston Vice President, ESBWR Licensing Reference: 1. MFN , Supplement 1, Letter from Richard E. Kingston to U.S. Nuclear Regulatory Commission, Update to the Integrated Plan and Schedule - Licensing Topical Reports (LTRs) and Responses to NRC Requests for Additional Information (RAIs), September 17, Enclosure: 2. MFN , Letter from Richard E. Kingston to U.S. Nuclear Regulatory Commission, Update to the Integrated Plan and Schedule - Licensing Topical Reports (LTRs) and Responses to NRC Requests for Additional Information (RAIs), July 7, DCD RAI and LTR Revision Schedule, November 4, cc: RE Brown (GEH/Wilmington) PL Campbell (GEH/Washington) AE Cubbage (NRC) JF Higgins (GEH/Wilmington) G Honma (GEH/Wilmington) DA Piepmeyer (GEH/Wilmington) RN Wachowiak (GEH/Wilmington)
3 Enclosure 1 DCD RAI and LTR Revision Schedule November 4, 2008
4 Outstanding DCD RAIs i NumberI Ciurrent NRC Forecast 'Commitment Date Deliveryý Date S04 12/8/ S02 11/19/ S03 11/13/ /14/ /8/ S02 12/31/ S01 10/20/ /29/ /22/ /22/ S02 9/8/ /17/ S01 9/8/ /17/ SO1 9/8/ /17/ SO1 9/8/ /17/ SO1 9/8/ /17/ SO1 9/8/ /17/ SO1 9/8/ /17/ SOI 9/8/ /17/ S05 12/31/2008 2/20/ S04 12/22/ S05 5/31/ /24/ S06 11/5/ S03 10/20/ /29/ S03 10/20/ /29/ S03 10/20/ /12/ S03 10/20/ /12/ S02 12/8/ S04 11/5/ /17/ S02 11/3/ /22/ /3/ S03 11/3/ /5/ S02 11/3/ S02 12/1/ S03 1/20/ S02 12/1/ SO1 12/29/ SO1 11/14/ SO1 11/5/2008 2/20/ SO1 1/20/ /24/ /24/ /24/ /25/ /29/ /29/ /13/ /20/ /3/2008 Page 1
5 Outstanding DCD RAIs /3/ /17/ /5/ /3/ /22/ /3/ /22/ /3/ /22/ /8/ /22/ /8/ /22/ /8/ /22/ /8/ /22/ /8/ /22/ /8/ /17/ /22/ /17/ /22/ /17/ /17/ /17/ /17/ /17/ /17/ /17/ /17/ /17/ /17/ /17/ /17/ /17/ /17/ /17/ /17/ /8/ /17/ /17/ /17/ /8/ /22/ /17/ /17/ /8/ /22/ /8/ /8/ /8/ /8/ /6/ /8/ /8/ /22/ /8/ /22/ /17/ /17/ /8/ /17/ SO1 12/18/2008 Page 2
6 Outstanding DCD RAIs /19/ /8/ /17/ /17/ S02 11/5/ S01 11/5/ /8/ /1/ /1/ SO5 11/25/ S03 11/17/ S02 12/29/ S /29/ S /29/ S /29/ S02 12/29/ S /29/ S /29/ S /29/ /29/ /29/ A-D 12/29/ SO1 12/31/ SO1 12/31/ /25/ S03 11/25/ S02 11/17/ S02 11/25/ S02 11/20/ S01 12/22/ S01 11/6/ /22/ SO0 11/3/ S01 12/22/ /6/ /6/ /6/ /5/ /22/ /17/ /17/ /20/ /20/ /20/ /20/ /20/ /20/ /20/ /20/ /20/ /25/ /22/ /22/2008 Page 3
7 Outstanding DCD RAIs /22/ /22/ /22/ /22/ /22/ /22/ /22/ /22/ /22/ /22/ /22/ /22/ /22/ /22/ /22/ /22/ /22/ /31/ /31/ /13/ /8/ S02 12/8/ S01 10/27/2008 1/30/ /1/ /1/ /5/ /5/ /5/ S04 12/8/ S03 11/17/ S02 11/17/ S01 1/14/ /8/ /17/ /17/ /15/ S03 11/17/ S01 11/17/ /29/2008 1/26/ /29/ /15/ S01 11/21/ S01 12/15/ /5/ /5/ /5/ S02 1/14/ S02 1/14/2009 Page 4
8 LTR RAIs RAI Number CurrentNRC 'Forecast... Number Do nncommitment Date Delivery Date LTR NEDE-33312P 10/28/ /15/ LTR NEDE-33312P 10/28/ /15/ LTR NEDE-33312P 10/28/ /15/ LTR NEDE-33312P 10/28/ /15/ LTR NEDE-33312P 10/28/ /15/ LTR NEDE-33312P 10/28/ /15/ LTR NEDE-33313P 10/28/ /15/ LTR NEDE-33313P 10/28/ /15/ LTR NEDE-33313P 10/28/ /15/ LTR NEDE-33313P. 10/28/ LTR NEDE-33313P 10/28/ LTR NEDE-33313P 10/28/ /15/ LTR NEDE-33313P 10/28/ /15/ LTR NEDE-33313P 10/28/ /15/ LTR NEDC-33408P 10/28/ /15/ LTR NEDC-33408P 10/28/ LTR NEDC-33408P 10/28/ LTR NEDC-33408P 10/28/ /15/ LTR NEDC-33408P 10/28/ LTR NEDC-33408P 10/28/ LTR NEDC-33408P 10/28/ LTR NEDC-33408P 10/28/ LTR NEDC-33408P 10/28/ LTR NEDC-33408P 10/28/ LTR NEDC-33408P 10/28/ LTR NEDC-33408P 10/28/ LTR NEDC-33408P 10/28/ LTR NEDE-33259P 10/28/ /19/ LTR NEDE-33259P 10/28/ /19/ LTR NEDE-33259P 10/28/ /19/ LTR NEDE-33259P 10/28/ /19/ LTR NEDE-33259P 10/28/ /19/ LTR NEDE-33259P 10/28/ /19/ LTR NEDE-33259P 10/28/ /19/ S01 LTR NEDE-33244P 12/8/ LTR NEDE-33240P 12/8/ LTR NEDO /17/ LTR NEDO /17/ LTR NEDO /17/ LTR NEDO /3/ S01 Rev 1 LTR NEDE-33295P 8/4/ /17/ LTR NEDE-33226P 12/17/ LTR NEDE-33226P 12/17/ LTR NEDE-33245P 12/17/ LTR NEDE-33226P 12/17/ LTR NEDO /18/ LTR NEDE-33197P 2/2/ LTR NEDE-33197P 2/2/2009 Page 1
9 LTR RAIs LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33373P 11/10/ LTR NEDC-33374P 11/24/ LTR NEDC-33374P 11/24/ LTR NEDC-33374P 11/24/ LTR NEDC-33374P 11/24/ LTR NEDC-33374P 11/24/ LTR NEDC-33374P 11/24/ LTR NEDC-33374P 11/24/ LTR NEDC-33374P 11/24/ LTR NEDC-33374P 11/24/ LTR NEDC-33374P 11/24/ LTR NEDC-33374P 11/24/ LTR NEDC-33374P 11/24/ LTR NEDC-33374P 11/24/ LTR NEDC-33374P 11/24/ LTR NEDC-33374P 11/24/ LTR NEDC-33374P 11/24/ LTR NEDC-33374P 11/24/ LTR NEDC-33374P 11/24/ LTR NEDC-33374P 11/24/ LTR NEDE-33226P 12/22/ LTR NEDE-33226P 12/22/ SO1 LTR NEDO /8/ SO1 LTR NEDO /15/ LTR NEDO /15/2008 Page 2
10 LTR RAIs LTR NEDO /15/ LTR NEDO /15/ LTR NEDO /15/ LTR NEDO /15/ LTR NEDO /15/ LTR NEDO /15/ LTR NEDO /15/ LTR NEDO /15/ LTR NEDO /15/ LTR NEDO /15/ SO1 LTR NEDO /31/ S01 LTR NEDO /31/ S01 LTR NEDO /31/ S01 LTR NEDO /31/ S01 LTR NEDO /31/ S01 LTR NEDO /31/ S01 LTR NEDO /31/ S01 LTR NEDO /24/ S02 LTR NEDO /24/ LTR NEDO /17/ LTR NEDO /17/ LTR NEDO /17/ LTR NEDO /17/2008 Page 3
11 LTR Revisions Topical Report LTR Rev Date Note/Comment NEDE-33390P, "ESBWR Interim Compensatory 12/5/2008 RAI Incorporation Measures Assessment Report" NEDE P, "ESBWR Safeguards Assessment 12/5/2008 RAI Incorporation Report" NEDC-33373P, "Dynamic, Load-Drop, and Thermal- RAI Incorporation/Changing design of Hydraulic Analysis for ESBWR Fuel Racks" 12/3/2008 fuel racks NEDC-33374P, "Safety Analysis Report for Fuel Storage 12/3/2008 RAI Incorporation Racks Criticality Analysis for ESBWR Plants" NEDE-33313P, "Steam Dryer - Structural Evaluation" TBD RAI Response in Progress NEDE-33312P, "Steam Dryer - Acoustic Load Definition" TBD RAI Response in Progress NEDE-33259P "ESBWR Reactor Internals flow Induced RAI Incorporation/Update in Reactor Vibration Program" 1/16/2009 Internals Design NEDO-33304, "GEH ABWR/ESBWR Setpoint 12/3/2008 RAI Incorporation Methodology" RAl Incorporation/Update Channel NEDO-33337, "ESBWR Initial Core Transient Analysis" 3/31/2009 Presr Drop e Pressure Drop NEDO-33338, "ESBWR Feedwater Temperature 3/31/2009 RAI Incorporation/Update Channel Operating Domain Transient and Accident Analysis" Pressure Drop Forecast will be provided after RAls 7.1 NEDE-33295P, "Cyber Security Program Plan" 2/28/ eand 7.-9 are acted by NRC 87 and are accepted by NRC NEDE-33242P, "GE14E for ESBWR Fuel Rod Thermal- 3/31/2009 RAI Incorporation Mechanical Design" NEDE-33239P "GE14 for ESBWR Nuclear Design 3/31/2009 RAI Incorporation Report" (Note: Revision to capture ) NEDC-33413P "GE14E CPR test data report" [Note: this 12/12/2008 Waiting for NRC review to be report is associated with response to RAI ] completed Page 1
12 LTR Revisions NEDO "Diversity and Defense in Depth" 2/27/2009 NEDO-33226P "Software Management Plan" 3/31/2009 NEDO-33245P "Software Quality Assurance Program 3/31/2009 Management" NEDC-33240P, "GE14E Fuel Assembly Mechanical 2/9/2009 RAI Incorporation Design Report LTR" NEDC "GE14E for ESBWR Initial Core Nuclear 3/31/2009 Core dp issue Design Report: Page 2
Phase 2 Executive Summary: Pre-Project Review of AECL s Advanced CANDU Reactor ACR
August 31, 2009 Phase 2 Executive Summary: Pre-Project Review of AECL s Advanced CANDU Reactor ACR-1000-1 Executive Summary A vendor pre-project design review of a new nuclear power plant provides an opportunity
June Phase 3 Executive Summary Pre-Project Design Review of Candu Energy Inc. Enhanced CANDU 6 Design
June 2013 Phase 3 Executive Summary Pre-Project Design Review of Candu Energy Inc. Enhanced CANDU 6 Design Executive Summary A vendor pre-project design review of a new nuclear power plant provides an
EPRI Update. Marc H. Tannenbaum Technical Leader, EPRI. RAPID Clearwater Beach, Florida May16, 2016
EPRI Update Marc H. Tannenbaum Technical Leader, EPRI RAPID Clearwater Beach, Florida May16, 2016 Recently Completed EPRI Products (www.epri.com) Digital Equivalency Evaluation: Screening Checklist and
LICENSING THE PALLAS-REACTOR USING THE CONCEPTUAL SAFETY DOCUMENT
LICENSING THE PALLAS-REACTOR USING THE CONCEPTUAL SAFETY DOCUMENT M. VISSER, N.D. VAN DER LINDEN Licensing and compliance department, PALLAS Comeniusstraat 8, 1018 MS Alkmaar, The Netherlands 1. Abstract
Mitsubishi s computerized HSI and digital I&C system for PWR plants
Mitsubishi s computerized HSI and digital I&C system for PWR plants ITO Koji 1, HANADA Satoshi 2, and MASHIO Kenji 3 1. Mitsubishi Heavy Industries, Ltd., Kobe 655-8585, Japan (koji_ito@mhi.co.jp) 2. Mitsubishi
NEPIO s Role in Incorporating 3S into the Nuclear Power Programme
NEPIO s Role in Incorporating 3S into the Nuclear Power Programme Jean-Maurice Crete SGCP/CTR International Atomic Energy Agency Introduction Role and Objectives of the NEPIO Examples of 3S Coordination
The Nuclear Regulatory Commission s Oversight of Safety Culture
The Nuclear Regulatory Commission s Oversight of Safety Culture Diane J. Sieracki Senior Safety Culture Program Manager Office of Enforcement IAEA TM October 6-8, 2014 1 2 Outline History of safety culture
Integration of MGDS Design into the Licensing Process' This paper presents an overview of how the Mined Geologic Disposal System (MGDS) design
ntegration of MGDS Design into the Licensing Process' ntroduction This paper presents an overview of how the Mined Geologic Disposal System (MGDS) design for a potential repository is integrated into the
System Analyses for The Elimination of Selected Response Time Testing Requirements
NEDO-32291-A Supplement 1 DRF A42-00126 Class I October 1999 BWR Owners' Group Licensing Topical Report System Analyses for The Elimination of Selected Response Time Testing Requirements D. W. Reigel W.
Perspectives on CFD V&V in Nuclear Regulatory Applications
Perspectives on CFD V&V in Nuclear Regulatory Applications Christopher Boyd Senior Technical Advisor for Computational Fluid Dynamics US Nuclear Regulatory Commission 1 Foreword Not a discussion of the
UTILIZING RESEARCH REACTOR SIMULATORS FOR REACTOR OPERATOR TRAINING AND LICENSING ABSTRACT
UTILIZING RESEARCH REACTOR SIMULATORS FOR REACTOR OPERATOR TRAINING AND LICENSING C. TAKASUGI, R. SCHOW, T. JEVREMOVIC* Utah Nuclear Engineering Program, University of Utah 50 S. Central Campus Dr., Salt
INTERNATIONAL ATOMIC ENERGY AGENCY TECHNICAL MEETING ON FUEL DESIGN AND LICENSING OF MIXED CORES FOR WATER COOLED REACTORS
I3-TM-41825 INTERNATIONAL ATOMIC ENERGY AGENCY TECHNICAL MEETING ON FUEL DESIGN AND LICENSING OF MIXED CORES FOR WATER COOLED REACTORS 12 14 December 2011 IAEA Headquarters Vienna International Centre,
USE OF WHITE NOISE IN TRACE/PARCS ANALYSIS OF ATWS WITH INSTABILITY
USE OF WHITE NOISE IN TRACE/PARCS ANALYSIS OF ATWS WITH INSTABILITY T. Zaki and P. Yarsky Nuclear Regulatory Commission Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission, MS CSB-3A07M,
UNITED STATES NUCLEAR
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 8,2001 MEMORANDUM TO: FROM: File Sikhindra K. Mitra Engineering Section Licensing Renewal and Standardization Branch Division
IEEE STD AND NEI 96-07, APPENDIX D STRANGE BEDFELLOWS?
IEEE STD. 1012 AND NEI 96-07, APPENDIX D STRANGE BEDFELLOWS? David Hooten Altran US Corp 543 Pylon Drive, Raleigh, NC 27606 david.hooten@altran.com ABSTRACT The final draft of a revision to IEEE Std. 1012-2012,
Research in automation, risk analysis, control rooms and organisational factors;
Research in automation, risk analysis, control rooms and organisational factors; applications to plant life management Shanghai, China, 17 October 2007 Björn Wahlström, J.J. Hämäläinen, J.-E. Holmberg,
RELAP5, TRACE, RELAP/SCDAPSIM, MARS-KS training course. Barcelona June 25 29, 2018
RELAP5, TRACE, RELAP/SCDAPSIM, MARS-KS training course Barcelona June 25 29, 2018 The training organized last year was a success with 14 participants from 6 different countries: South Korea, People s Republic
Agency Information Collection Activities: Submission for Review; Information
This document is scheduled to be published in the Federal Register on 11/04/2015 and available online at http://federalregister.gov/a/2015-28096, and on FDsys.gov 9110-9F DEPARTMENT OF HOMELAND SECURITY
The Regulation of Nuclear Power
Chapter 6 The Regulation of Nuclear Power One of aisles in the document vault at St. Lucie 2 Photo credit: Florida Power & Light Contents Page Federal Regulation............................................143
FAST TRACK WORKSHOP OBJECTIVES
1 FAST TRACKING FAST TRACK WORKSHOP OBJECTIVES TO UNDERSTAND: 1. WHY ARE CRITICAL PATH ( FAST TRACK ) DESIGN SUBMITTAL PACKAGES ALLOWED 2. WHEN IS FAST TRACK ALLOWED 3. WHEN IS THE CONTRACTOR ALLOWED TO
LEVEL TECHNOLOGIES TO POWER THE FUTURE
LEVEL TECHNOLOGIES TO POWER THE FUTURE Increase generation efficiency and keep your plant safe INCREASE GENERATION EFFICIENCY AND GET THE MOST OUT OF YOUR PROCESS When you need to reduce variation in level
New Reactors Programme. GDA close-out for the AP1000. GDA Issues GI-AP1000-CI-05 Smart Device Justification
New Reactors Programme GDA close-out for the AP1000 GDA Issues GI-AP1000-CI-05 Smart Device Justification Assessment Report: ONR-NR-AR-16-032 Revision 0 March 2017 Template Ref: ONR-DOC-TEMP-004 Revision
IN USE: CABLE AGING MANAGEMENT
IN USE: CABLE AGING MANAGEMENT ISSUE STATEMENT Concerns exist that cable aging-related failures may impact nuclear plant safety and reliability. As a result, plant owners and regulators are requiring the
Decommissioning conduct Working Group
Decommissioning conduct Working Group Patrice FRANÇOIS Third Annual Meeting of the IAEA FaSa Project 29 November 3 December 2010 IAEA Headquaters, Vienna, Decommissioning conduct Working group participants:
Yolande Akl, Director, Canadian Nuclear Safety Commission Ottawa, Canada. Abstract
OVERVIEW OF SOME CHALLENGES IN PSA REVIEWS FOR EXISTING AND NEW NUCLEAR POWER PLANTS IN CANADA 1 Guna Renganathan and Raducu Gheorghe Canadian Nuclear Safety Commission Ottawa, Canada Yolande Akl, Director,
generation greater than 75 MVA (gross aggregate nameplate rating) Generation in the ERCOT Interconnection with the following characteristics:
A. Introduction 1. Title: Verification of Models and Data for Turbine/Governor and Load Control or Active Power/Frequency Control Functions 2. Number: MOD-027-1 3. Purpose: To verify that the turbine/governor
Before the FEDERAL COMMUNICATIONS COMMISSION Washington, DC ) ) ) ) ) ) ) ) ) ) ) PETITION FOR ETC DESIGNATION OF HUGHES NETWORK SYSTEMS, LLC
Before the FEDERAL COMMUNICATIONS COMMISSION Washington, DC 20554 In the Matter of Telecommunications Carriers Eligible to Receive Universal Service Support Petition of Hughes Network Systems, LLC for
Before the Federal Communications Commission Washington, DC ) ) ) ) ) ) ) ) REPLY COMMENTS OF THE TELECOMMUNICATIONS INDUSTRY ASSOCIATION
Before the Federal Communications Commission Washington, DC 20554 In the Matter of the Petition of The State of Maryland Request for Waiver to permit operation of Airto-Ground radio equipment on 700 MHz
Before the FEDERAL COMMUNICATIONS COMMISSION Washington, DC ) ) ) ) ) ) COMMENTS OF THE NATIONAL ASSOCIATION OF BROADCASTERS
Before the FEDERAL COMMUNICATIONS COMMISSION Washington, DC 20554 In the In the Matter of Revision of Part 15 of the Commission s Rules to Permit Unlicensed National Information Infrastructure (U-NII Devices
DATA ANALYSIS FOR VALVE LEAK DETECTION OF NUCLEAR POWER PLANT SAFETY CRITICAL COMPONENTS
DATA ANALYSIS FOR VALVE LEAK DETECTION OF NUCLEAR POWER PLANT SAFETY CRITICAL COMPONENTS Jung-Taek Kim, Hyeonmin Kim, Wan Man Park Korea Atomic Energy Research Institute 145 Daedeok-daero, Yuseong-gu,
SECTION PROJECT MANAGEMENT AND COORDINATION
SECTION 013100 - PROJECT MANAGEMENT AND COORDINATION PART 1 - GENERAL 1.1 RELATED DOCUMENTS A. Drawings and general provisions of the Contract, including General and Supplementary Conditions and other
Focus on Mission Success: Process Safety for the Atychiphobist
Focus on Mission Success: Process Safety for the Atychiphobist Mary Kay O Connor Process Safety International Symposium Bill Nelson and Karl Van Scyoc October 28-29, 2008 First: A Little Pop Psychology
4 Briefing. Responsible investor
Issue Responsible investor 4 Briefing Wednesday 8 th February 2012 In 2010, we accepted all 26 recommendations made by the Bly Report our internal investigation into the Deepwater Horizon incident. BP
MBB400TX12A Silicon N-channel IGBT
MBB4TX12A Silicon N-channel IGBT IGBT-SP-1714-R1 (P1/8) 1. FEATURES * High speed, low loss IGBT module. * Low driving power: Low input capacitance advanced IGBT. * Low thermal impedance due to direct liquid
November 25, Via Electronic Filing
Association of Public-Safety Communications Officials (APCO) CTIA The Wireless Association National Emergency Number Association (NENA) National Public Safety Telecommunications Council (NPSTC) Rural Cellular
STANDARD MICROCIRCUIT DRAWING MICROCIRCUIT, LINEAR, 16-CHANNEL JFET ANALOG MULTIPLEXER, MONOLITHIC SILICON
REVISIONS LTR DESCRIPTION DATE (YR-MO-DA) APPROVED A Drawing updated to reflect current requirements. Editorial changes throughout. drw 00-12-13 Raymond Monnin Corrected paragraph 1.2.1. Editorial changes
Stakeholder involvement in Canadian Initiatives for Deep Geological Repositories for the Long Term Management of Radioactive Wastes
Stakeholder involvement in Canadian Initiatives for Deep Geological Repositories for the Long Term Management of Radioactive Wastes ICGR December 6-9, 2016 Paris, France Haidy Tadros Director General DNCFR
New Plant Cable Issues. SC-2 Knoxville Tennessee April 8, 2009
New Plant Cable Issues SC-2 Knoxville Tennessee April 8, 2009 STEVE SANDBERG General Manager Nuclear Utility Group NEW NUCLEAR PLANTS Agenda Introduction Cable Designs Issues EQ Requirements Standards
Overview of U.S. DOE Nuclear Energy Instrumentation and Control R&D
Overview of U.S. DOE Nuclear Energy Instrumentation and Control R&D Suibel Schuppner Office of Nuclear Energy U.S. Department of Energy IAEA Technical Working Group on Nuclear Power Plant Instrumentation
Certificate of Compliance
Certificate of Compliance Certificate: 1243943 (LR 116214) Master Contract: 200116 Project: 70077085 Date Issued: 2016-05-09 International Hydraulics, Inc. 7638 St Clair Ave Mentor, Ohio 44060 USA Ned
Office for Nuclear Regulation
Summary of Lessons Learnt during Generic Design Assessment (2007 2013) ONR-GDA-SR-13-001 Revision 0 September 2013 1 INTRODUCTION 1 The purpose of this document is to provide a summary of the key lessons
Optimize Your Process Using Normal Operation Data
Optimize Your Process Using Normal Operation Data Michel Ruel, PE Top Control, Inc. 49, rue du Bel-Air, bur.103, Lévis, QC G6V 6K9, Canada Phone +1.418.834.2242, michel.ruel@topcontrol.com Henri (Hank)
SMR Conference Manchester 2014 Regulator s view UK and International. Bob Jennings Systems Lead for ONR s Generic Design Assessment (GDA)
SMR Conference Manchester 2014 Regulator s view UK and International Bob Jennings Systems Lead for ONR s Generic Design Assessment (GDA) Contents Approach to New Nuclear Build Regulation in Great Britain:
Intimate Communications Hub Interface Specification Report to Secretary of State
Intimate Communications Hub Interface Specification Report to Secretary of State DCC V1.0 28/02/14 Page 1 of 14 Executive Summary 1. DCC is required in accordance with the terms of its Licence to produce,
Lincoln County Tax Appraisal Office Project No. RFB
Red Bike Architecture, PLLC James M. Ratliff, Architect, NCARB P.O. Box 574, Rutherford College, NC 28671-0574 Phone: 828-413-2276 Email: ratliffarch@outlook.com Addendum #1 July 3, 2018 Project: Interior
REGULATORY GUIDE (Draft was issued as DG-1029)
U.S. NUCLEAR REGULATORY COMMISSION January 2000 REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.180 (Draft was issued as DG-1029) GUIDELINES FOR EVALUATING ELECTROMAGNETIC AND
STANDARD MICROCIRCUIT DRAWING MICROCIRCUIT, LINEAR, WIDEBAND, DIFFERENTIAL OPERATIONAL AMPLIFIER, MONOLITHIC SILICON
REVISIONS LTR DESCRIPTION DATE (YR-MO-DA) APPROVED A Change table II to have a higher V IO delta limit for life test than for burn-in. rrp Update drawing to current MIL-PRF-38535 requirements. Removed
NHS England CCG Authorisation
NHS England CCG Authorisation Post Authorisation December 2013 Review Conditions Report CCG name: Vale of York CCG Wave: 3 Regional Operations Director Jon Develing Date report generated: 22/01/2014 Vale
Public and Aboriginal Engagement Public Information and Disclosure REGDOC-3.2.1
Public and Aboriginal Engagement Public Information and Disclosure REGDOC-3.2.1 May 2018 Public Information and Disclosure Regulatory document REGDOC-3.2.1 Canadian Nuclear Safety Commission (CNSC) 2018
Stakeholder Involvement in Decision Making
IAEA Conference on Advancing Global Implementation of Decommissioning and Environmental Remediation Madrid, Spain May 24, 2016 Stakeholder Involvement in Decision Making Opening Remarks Jason K Cameron,
DEPARTMENT OF TRANSPORTATION BEFORE THE PIPELINE AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION
DEPARTMENT OF TRANSPORTATION BEFORE THE PIPELINE AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION ) Pipeline Safety: Information Collection Activities ) Docket No. PHMSA 2013 0061 ) COMMENTS OF THE AMERICAN
A web-based nuclear simulator using RELAP5 and LabVIEW
Nuclear Engineering and Design 237 (2007) 1185 1194 A web-based nuclear simulator using RELAP5 and LabVIEW K.D. Kim a,, Rizwan-uddin b a Korea Atomic Energy Research Institute (KAERI), Dukjin 150, Yusung,
Robert W. Cummings - NERC Director of System Analysis and Reliability Initiatives William Herbsleb - Chairman of Frequency Response Standard Drafting
Generator Governor and Information Settings Webinar Robert W. Cummings - NERC Director of System Analysis and Reliability Initiatives William Herbsleb - Chairman of Frequency Response Standard Drafting
Developing a Strong Nuclear Safety Culture. Larry Weber Chief Nuclear Officer, Senior Vice President American Electric Power Cook Nuclear Plant
Developing a Strong Nuclear Safety Culture Larry Weber Chief Nuclear Officer, Senior Vice President American Electric Power Cook Nuclear Plant Agenda 2 1. Actions of the U.S. Nuclear Industry to Support
IAEA Training in level 1 PSA and PSA applications. PSA Project. IAEA Guidelines for PSA
IAEA Training in level 1 PSA and PSA applications PSA Project IAEA Guidelines for PSA Introduction The following slides present the IAEA documents that deal with procedures, guidance and good practices
Re: Ruby Pipeline Project; Docket No. CP ; Response to Comments from Mr. Randy Largent, Landman for Newmont Mining Corporation
March 1, 2010 Federal Energy Regulatory Commission 888 First Street, N.E. Washington, D.C. 20426 Attention: Ms. Kimberly D. Bose, Secretary Commissioners: Re: Ruby Pipeline Project; Docket No. CP09-54-000;
J.C. Courtney Nuclear Science Center Louisiana State University Baton Rouge, LA
J.C. Courtney Nuclear Science Center Louisiana State University Baton Rouge, LA 70803-5830 W.H. Perry and RD. Phipps Operations Division Argonne National Laboratory - West P.O. Box 2528 Idaho Falls, ID
INFCIRC/57. 72/Rev.6. under. Safetyy. read in. Convention. involve. National Reports. on Nuclear 2015.
Atoms for Peace and Development Information Circular INFCIRC/57 72/Rev.6 Date: 19 January 2018 General Distribution Original: English Guidelines regarding Convention National Reports under the on Nuclear
Regulatory review process. Pickering Nuclear Generating Station Licence Renewal. nuclearsafety.gc.ca. Kevin Lee, CNSC Senior Regulatory Policy Officer
Regulatory review process Pickering Nuclear Generating Station Licence Renewal Kevin Lee, CNSC Senior Regulatory Policy Officer Heather Overton, CNSC Senior Regulatory Program Officer nuclearsafety.gc.ca
The Advancement of Simulator Models
The Advancement of Simulator Models How the Evolution of Simulator Technology has Impacted its Application Michael M. Petersen Xcel Energy The Age of Simulation Simulation is the imitation of the operation
M. Adorni EMUG March 17-18, 2015 Brussels 1
M. Adorni EMUG March 17-18, 2015 Brussels 1 OVERVIEW OF BEL V AND USE MELCOR CODE 7th Meeting of the European MELCOR User Group Avenue Ariane, 7, Brussels March 17-18, 2015 M. Adorni, B. De Boeck (Bel
ONR-NR-PAR Rev 2
.3 Title of document PROJECT ASSESSMENT REPORT Unique Document ID and Revision No: Project: Site: Title: Licence Instrument No: Nuclear Site Licence No: ONR-NR-PAR-16-006 Rev 2 Commencement of First Nuclear
MBM900FS17F Silicon N-channel IGBT 1700V F version
Silicon N-channel IGBT 1700V F version Spec.No.IGBT-SP-15013 R0 P1 C1 FEATURES High current rate package Low stray inductance & low Rth(j-c) Half-bridge (2in1) Built in temperature sensor Scalable large
The CNSC s Approach to Communications
36th Canadian Nuclear Society (CNS) Annual Conference and 40th CNS/Canadian Nuclear Association Student Conference June 21, 2016 Toronto, ON The CNSC s Approach to Communications Jason K. Cameron Vice-President,
Addendum StartPage : 0
1 n n 1 Control Number : 40377 Item Number : 102 Addendum StartPage : 0 ^ ^ En te^.^ Entergy Operations, Inc. River Bend Station 5485 U S Highway 61 N St Franccav+lle, LA 70775 let 225-381-4374!, r Eric
REVISIONS LTR DESCRIPTION DATE (YR-MO-DA) APPROVED. A Drawing updated to reflect current requirements. gt R. Monnin
REVISIONS LTR DESCRIPTION DATE (YR-MO-DA) APPROVED A Drawing updated to reflect current requirements. gt 03-04-04 R. Monnin Drawing updated to reflect current MIL-PRF-38535 requirements. - ro 12-03-15
Before the FEDERAL COMMUNICATIONS COMMISSION Washington, DC ) ) ) ) ) ) COMMENTS OF THE TELECOMMUNICATIONS INDUSTRY ASSOCIATION
Before the FEDERAL COMMUNICATIONS COMMISSION Washington, DC 20554 In the Matter of Emission Mask Requirements for Digital Technologies on 800 MHz NPSPAC Channels; Analog FM Capability on Mutual Aid and
March 5, Ladies and Gentlemen:
March 5, 2012 United States 1500 Pennsylvania Avenue, N.W. Washington, D.C. 20220 Attn: Financial Research Fund Assessment Comments Docket number TREAS-DO-2012-0001 Re: Assessment of Fees on Large Bank
GDA Issue GI-AP1000-SI-05: Compliance of AP1000 Main Structural Components with ASME III Design Rules.
New Reactors Programme GDA close-out for the AP1000 reactor GDA Issue GI-AP1000-SI-05: Compliance of AP1000 Main Structural Components with ASME III Design Rules. Assessment Report: ONR-NR-AR-16-012 Revision
ENGINEERING SERVICES CONSULTANCY
ENGINEERING SERVICES CONSULTANCY Managing complexity, unlocking value Petrofac Engineering & Production Services 02 03 Discover the difference Consultancy services Petrofac is an international service
STANDARD MICROCIRCUIT DRAWING MICROCIRCUIT, DIGITAL-LINEAR, FAST, SERIAL, 16-BIT, A/D CONVERTER, MULTICHIP SILICON
REVISIONS LTR DESCRIPTION DTE (YR-MO-D) PPROVED Update boilerplate to reflect current requirements. -rrp 01-11-16 R. MONNIN REV REV REV STTUS REV OF S 1 2 3 4 5 6 7 8 9 10 11 PMIC N/ STNDRD MICROCIRCUIT
Applications & Benefits of Engineering Simulators
2018 Power Plant Simulation Conference (PowerPlantSim 18) Applications & Benefits of Engineering Simulators 17 January 2018 Michael Chatlani Vincent Gagnon Topics Introduction Engineering Simulators Applications
Before INDUSTRY CANADA Ottawa, Canada
Before INDUSTRY CANADA Ottawa, Canada ) In the Matter of ) ) Proposed Revisions to the Frequency Plan ) Notice No. SMSE-004-08 For Public Safety in the 700 MHz Band ) Canada Gazette, Part I ) January 19,
February 28, Dr. Richard Benson, President, Ms. Lisa Choate, Chair of the Institutional Audit Committee:
Office of Internal Audit 800 W. Campbell Rd. SPN 32, Richardson, TX 75080 Phone 972-883-4876 Fax 972-883-6846 February 28, 2017 Dr. Richard Benson, President, Ms. Lisa Choate, Chair of the Institutional
United Nations Development Programme
Tax on Price Quotation Payment Terms (max. advanced payment is 20% of total price) must be inclusive of VAT and other applicable indirect taxes must be exclusive of VAT and other applicable indirect taxes
SECTION SHOP DRAWINGS, PRODUCT DATA, AND SAMPLES
SECTION 01 33 23 - SHOP DRAWINGS, PRODUCT DATA, AND PART 1 - GENERAL 1.1 SUMMARY A. Products include, but are not limited to, the following construction submittals: 1. Shop Drawings. 2. Product Data. 3.
GDA Step 2 Assessment of the Probabilistic Safety Analysis and Severe Accident Analysis of Hitachi GE s UK Advanced Boiling Water Reactor (UK ABWR)
GDA Step 2 Assessment of the Probabilistic Safety Analysis and Severe Accident Analysis of Hitachi GE s UK Advanced Boiling Water Reactor (UK ABWR) Civil Nuclear Reactor Build Generic Design Assessment
A. Section includes administrative provisions for coordinating construction operations on Project including, but not limited to, the following:
SECTION 01 31 00 PROJECT MANAGEMENT AND COORDINATION PART 1 GENERAL 1.1 RELATED DOCUMENTS A. Drawings and general provisions of the Contract, including General and Supplementary Conditions and other Division
STANDARD MICROCIRCUIT DRAWING MICROCIRCUIT, LINEAR, PRECISION 1.2 V VOLTAGE REFERENCE, MONOLITHIC SILICON
REVISIONS LTR DESCRIPTION DATE (YR-MO-DA) APPROVED A Replaced reference to MIL-STD-973 with reference to MIL-PRF-38535. Drawing updated to reflect current requirements. - gt 04-03-31 Raymond Monnin Update
SAFIR2014: CORSICA Coverage and rationality of the software I&C safety assurance
SAFIR2014: CORSICA Coverage and rationality of the software I&C safety assurance Mid-Term Seminar 21.-22.3.2013 Jussi Lahtinen, Jukka Ranta, Lauri Lötjönen VTT Risto Nevalainen, Timo Varkoi, FiSMA 2 Introduction
The Safety Case and the Risk-Informed Performance-Based Approach for Management of US Commercial Low-Level Waste (Paper #190)
The Safety Case and the Risk-Informed Performance-Based Approach for Management of US Commercial Low-Level Waste (Paper #190) Rateb (Boby) Abu-Eid, David Esh, and Christopher Grossman Division of Decommissioning,
Engineering Drawing System
LPR 7320.1 Effective Date: February 2, 2010 Expiration Date: February 2, 2015 Langley Research Center Engineering Drawing System National Aeronautics and Space Administration Responsible Office: Systems
Chief Nuclear Inspector s Inspection of NNB GenCo Ltd. s Supply Chain Management Arrangements for the Hinkley Point C Project
Chief Nuclear Inspector s Inspection of NNB GenCo Ltd. s Supply Chain Management Arrangements for the Hinkley Point C Project 15 March 2018 Chief Nuclear Inspector s Inspection of NNB GenCo Ltd. s Supply
Public Information and Disclosure RD/GD-99.3
Public Information and Disclosure RD/GD-99.3 March, 2012 Public Information and Disclosure Regulatory Document RD/GD-99.3 Minister of Public Works and Government Services Canada 2012 Catalogue number CC172-82/2012E-PDF
Instrumentation and Control
Instrumentation and Control Program Description Program Overview Instrumentation and control (I&C) systems affect all areas of plant operation and can profoundly impact plant reliability, efficiency, and
Before the Federal Communications Commission Washington, DC ) ) ) ) COMMENTS OF CTIA THE WIRELESS ASSOCIATION
Before the Federal Communications Commission Washington, DC 20554 In the Matter of Expanding Access to Mobile Wireless Services Onboard Aircraft WT Docket No. 13-301 To: The Commission COMMENTS OF CTIA
Monticello Nuclear Generatin Plant Reload Safety Evaluation Met ods NSPNAD-86 08, Rev. 1
5 Monticello Nuclear Generatin Plant Reload Safety Evaluation Met ods NSPNAD-86 08, Rev. 1 August 1988 Nuclear Analysis Department Northern States Power Company AD~~05000P263 i RELOAD SAFETY EVALUATION
Nuclear Infrastructure Support
Nuclear Infrastructure Support presentation to US Energy Association Panel Rebecca Smith-Kevern, Director for Light Water Reactor Technology November 9, 2010 DM#202983 1 Activities in Infrastructure Development
BAE Systems Combat Vehicles Supplier Quality Assurance AS9102 Requirement
1 BAE Systems Combat Vehicles Supplier Quality Assurance AS9102 Requirement February 27, 2019 2 Scope The intent of this document is to provide an understanding, and clarification as to what BAE Systems
CNSC Research Program Presentation to COG Nuclear Safety Peer Group
Canadian Nuclear Safety Commission Commission canadienne de sûreté nucléaire CNSC Research Program Presentation to COG Nuclear Safety Peer Group Daniel Tello Senior Research Program Officer February 17,
BC Hydro 2015 Rate Design Module 2 Presentation - October 26, 2016 Non-Integrated Area Rates PRIMER PRESENTATION & INPUT REQUEST Feedback Form
BC Hydro 2015 Rate Design Module 2 Presentation - October 26, 2016 Non-Integrated Area Rates PRIMER PRESENTATION & INPUT REQUEST Feedback Form We would appreciate it if you could please complete and return
JOSEPH A. KEOUGH JR.* JEROME V. SWEENEY III* SEAN P. KEOUGH* STACI L. KOLB JEROME V. SWEENEY II OF COUNSEL
KEOUGH & SWEENEY, LTD. ATTORNEYS AND COUNSELORS AT LAW MENDON AVENUE PAWTUCKET, RHODE ISLAND 0 TELEPHONE (0) -00 FACSIMILE (0) -0 www.keoughsweeney.com RAYNHAM OFFICE: 0 NEW STATE HIGHWAY RAYNHAM, MA 0
August 6, Ms. Kimberly D. Bose, Secretary Federal Energy Regulatory Commission 888 First Street, NE Washington, DC 20426
August 6, 2010 Ms. Kimberly D. Bose, Secretary Federal Energy Regulatory Commission 888 First Street, NE Washington, DC 20426 ANR Pipeline Company 717 Texas Street, Suite 2400 Houston, TX 77002-2761 John
ILLINOIS BELL TELEPHONE COMPANY ILL. C. C. NO. 16
ILLINOIS BELL TELEPHONE COMPANY ILL. C. C. NO. 16 By T. L. Cox, Vice Pres. - Fin. 1st Revised Title Page 225 West Randolph Street Canceling Original Title Page Issued: June 30, 1988 Effective: August 15,
GIANOLA, BARNUM & WIGAL, L.C. Attorneys At Law
GIANOLA, BARNUM & WIGAL, L.C. Attorneys At Law 1714 Mileground 304-291 -6300 JAMES A. GIANOLA CHRISTOPHER A. BARNUM GARY S. WIGAL BRENT L. VAN DEYSEN* MICHELLE L. BECHTEL DAVID M. JECKLIN LARRY W. MAY
ADOPTION NOTICE CONCLUDING MATERIAL. Navy - AS Air Force - 99 (Project )
SAE- ADOPTION NOTICE SAE-, Fitting, Tee, Standard and Reducer, Bulkhead on Run, Internal Port on Side, Flared", was adopted on 03 February 1984 for use by the Department of Defense (DoD). Proposed changes
UK Shared Business Services Ltd
SBS 001-18 UK Shared Business Services Ltd Minutes of the 76 th UK SBS Board Meeting held at Polaris House, Swindon on Wednesday 6 th December 2017 commencing at 10.00am. Attending: Board Members: UK SBS
Ask the Regulator and Industry Experts Thursday, September 14 3:30 p.m. 4:30 p.m.
Ask the Regulator and Industry Experts Thursday, September 14 3:30 p.m. 4:30 p.m. During this session, panelists answer your questions related to the fixed income regulatory landscape. Panelists also address
SECTION CONTRACTOR SUBMITTALS. A. All submittals by the CONTRACTOR shall be submitted to the ENGINEER.
SECTION 01300 - PART 1 - GENERAL 1.1 GENERAL A. All submittals by the CONTRACTOR shall be submitted to the ENGINEER. B. Unless otherwise noted, within 14 days after the date of commencement as stated in
How to Learn from the Experience in Japan
Chapter 16 From Fukushima to the World How to Learn from the Experience in Japan Tatsujiro Suzuki Abstract This is the text for the after-dinner speech given by Prof. Tatsujiro Suzuki, then Vice Chair