DOCSLIB.ORG

Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design Appendices A -c U- A U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation July 1994 AVAILABILITY NOTICE Availability of Reference Materials Cited in NRC Publications Most. documents cited in NRC publications will be available from one of the following sources: 1. The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC 20555-0001 2. The Superintendent of Documents, U.S. Government Printing Office, Mail Stop SSOP, Washington, DC 20402-9328 3. The National Technical Information Service, Springfield, VA 22161 Although the listing that follows represents the majority of documents cited in NRC publica- tions, it is not intended to be exhaustive. Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and internal NRC memoranda; NRC bulletins, circulars, information notices, inspection and investigation notices-, licensee event reports; vendor reports and correspondence; Commission papers; and applicant and licensee docu- ments and correspondence. The following documents in the NUREG series are available for purchase from the GPO Sales Program: formal NRC staff and contractor reports, NRC-sponsored conference proceedings, international agreement reports, grant publications, and NRC booklets and brochures. Also available are regulatory guides, NRC regulations in the Code of Federal Regulations, and Nu- clear Regulatory* Commission Issuances. Documents available from the National Technical Information Service include NUREG-series reports and technical reports prepared by other Federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission. Documents available from public and special technical libraries include all open literature items, such as books, journal articles, and transactions. Federal Register notices, Federal and State legislation, and congressional reports can usually be obtained from these libraries. Documents such as theses, dissertations, foreign reports and translations, and non-NRC con- ference proceedings are available for purchase from the organization sponsoring the publica- tion cited. Single copies of NRC draft reports are available free, to the extent of supply, upon written request to the Office of Administration, Distribution and Mail Services Section, U.S. Nuclear Regulatory Commission, Washington, DC 2D555-0001. Copies of industry codes and standards used in a substantive manner in the NRC regulatory process are maintained at the NRC Library, 7920 Norfolk Avenue, Bethesda, Maryland, for use by the public. Codes and standards are usually copyrighted and may be purchased from the originating organization or, if they are American National Standards, from the American Na- tional Standards Institute, 1430 Broadway, New York, NY 10018. NUTREG-1 503 Vol. 2 Final Safety Evaluation Report Related to the Certification *of the Advanced Boiling Water Reactor Design Appendices Manuscript Completed: July 1994 Date Published: July 1994 Associate Directorate for Advanced Reactors and License Renewal Office,' of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 I xl ABSTRACT This safety evaluation report (SER) documents the ABWR design features that are substantially the same as technical review of the U.S. Advanced Boiling Water those previously considered. The SERs for the other BWR . eacI&POftor(AIIWR) standard design by the U.S. Nuclear designs have been published and are available for public Wegulatory Commission (NRC) staff. The application for inspection at the NRC Public Document Room, the ABWR design was initially submitted by the General 2120 L Street, N.W., Washington, D.C. 20037. Unique Electric Company, now GE Nuclear Energy (GE), in features of the ABWR design include internal recirculation accordance with the procedures of Appendix 0 of Part 50 pumps, fine-motion control rod drives, microprocessor- of Title 10 of the Code of Federal Reoulations (10 CFR based digital logic and control systems, and digital safety Part 50). Later GE requested that its application be systems. considered as an application for design approval and subsequent design certification pursuant to On the basis of its evaluation and independent analyses, the 10 CFR § 52.45. NRC staff concludes that, subject to satisfactory resolution of the confirmatory items identified in Section 1.8 of this SER, GE's application for design certification meets the The U.S. ABWR design is similar to the international requirements of Subpart B of 10 CFR Part 52 that are AB3WR design, which was being built at the Kashiwazaki applicable and technically relevant to the U.S. ABWR Kariwa Nuclear Power Generation Station, at the time of standard design. A copy of the report by the Advisory the staff's review, by the Tokyo Electric Power Company, Committee on Reactor Safeguards required by Inc. The ABWR is a single-cycle, forced-circulation, 10 CFR § 52.53 is provided in Chapter 21. A final design boiling water reactor (BWR) with a rated power of approval, issued on the basis of this SER, does not 3926 megawatts thermal (MWt) and a design power of constitute a commitment to issue a permit or license, or in 4005 MWt. Many features of the ALBWR design are any way affect the authority of the Commission, the similar to those of BWR designs that the staff had Atomic Safety and Licensing Board, and other presiding previously approved. To the extent feasible and officers, in any proceeding pursuant to Subpart G of appropriate, the staff relied on earlier reviews for those 10 CFR Part 2. iii iiiNUREG- 1503 b. CONTENTS VOLUME 2: APPENDICES Page *APPENDIX A..................... A -i... LIST OF ABBREVIATIONS............... .. A ...-i APPENDIX B..................... .I . B-i... REFERENCES........................ .. B-I... APPENDIX C..................... .. C-1 ... CHRONOLOGY OF CORRSPONDENCE .... C-i ... APPENDIX D..................... .. D-1 ... FSER CONTRIBUTORS......... ........ D-1 ... APPENDIX E..................... .. E-1 ... STAFF POSITION ON SHELL BUCKLING DUE TO INTERNAL PRESSURE... E-i ... APPENDIX, F.............................................. .. F-1 ... STAFF POSITION ON STEEL EMBEDMENTS.......................... F-i ... kAPPENDIX G.......................................... .. G-1 ... STAFF POSITIONS AND TECHNICAL BASES ON THE USE OF AMERICAN NATIONAL STANDARDS INSTITUTE (ANSI)/AMERICAN INSTITUTE OF STEEL CONSTRUCTION (AISC) N690, -NUCLEAR FACILITIES - STEEL SAFETY-RELATED STUTRS...... G-1 APPENDIX H...................................................... H-1 DYNAMIC LATERAL SOIL PRESSURES ON EARTH RETAINING WALLS AND EMBEDDED WALLS OF NUCLEAR POWER PLANT STRUCTURES.................................... H-i APPENDIX I........................................................I1-1 EVALUATION OF ABWR PUMP AND VALVE INSERVICE TESTING PLAN (SSAR TABLES 3.9-8 AND 3.9-9)....................................................11 APPENDIX J.............................. I .......................... J-i HUMAN FACTORS ENGINEERING PROGRAM REVIEW MODEL AND ACCEPTANCE CRITERIA FOR EVOLUTIONARY REACTORS......................................................J1 APPENDIX K....................................................... K-1 IMPORTANT SAFETY INSIGHTS.................................................... K-1 V ~NUREG-1503 V FIGURES page G-1 Structural stability curves for the axially loaded compression numbers. .. .. .. .. .. .. .. .. .. ....... G-3 W J. I HFE program review model elements .. .. ..... .. .. .. .. .. .. .. .. .... .. .... .. .... .......... J-4 J.2 BIFE program review stages.............................................. ........ J-5 NUREG- 1503 viv Appendix A LIST OF ABBREVIATIONS A- - C AB)WR advanced boiling water reactor CA compressedl air AC alternating current CAMS containment atmosphere monitoring system ACC accumulator CAV cumulative absolute velocity ACI automatic closure and interlock CBERU contrbuilding emergency recirculation unit ACIWA ac-independent water addition CBRU control-building recirculation unit ACRS Advisory Committee on Reactor CBSREA control building safety-related equipment Safeguards area ACS atmospheric control system CCDF complementary cumulative distribution ACU air conditioning units function ADS automatic depressurization system CCI core concrete interaction AHU air handling units CCS condensate cleanup system AISC American Institute of Steel Construction CDF core damage frequency ALARA as low as is reasonably achievable CDM Certified Design Material ALWVR advanced light water reactor CDRL core damage radiation level AM accident management CE ABB-Combustion Engineering ANL Argonne National Laboratory CED common engineering documents ANS American Nuclear Society CET containment event trees ANSI American National Standards Institute CF&CAE condensate feedwater, and condensate air AQO(s) anticipated operational occurrences extraction APR automatic power regulator CFR Code of Federal Re~yulations APRM average power range monitor CFS condensate and feedwater system ARI alternate rod insertion CH chugging O"ASamplified response spectra CIV containment isolation valve *ASB Auxiliary Systems Branch cm centimeters ASCE American Society of Civil Engineers CMAA Crane Manufacturers Association of ASD allowable stress design America ASD adjustable speed drive CMP configuration management plan ASF automatic suppression function CMU control
Load more

Recommended publications
  • Consolidated Safety Analysis Report for IF-300 Shipping Cask
    REVISION CONTROL SHEET TITLE: Consolidated Safety DOCUMENT NO.: NEDO-10084 Analysis Report for IF-300 Shipping Cask AFFECTED | DOC. REMARKS PAGE(S) I REV. I __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .I.I by General Electric Company. 1-i 3 Last revision prepared Incorporates all C of C 9001, Revision 29 references 1-1 & 1-2 2-i & 2-ii From 2/8/84 through 5/10/85. A vertical line on the right hand margin indicates a 2-1 - 2-15 Revision. "N" denotes new information while "E" 3-i & 3-ii Denotes an editorial change. 3-1 - 3-16 4-i - 4-ii 4-1 - 4-21 5-i - 5-vi 5-1 - 5-311 6-i - 6-iv U 6-1 - 6-82 7-i - 7-ii 7-1 - 7-22 8-i & 8-ii 8-1 - 8-22 n 9-i & 9-ii 9-1 - 9-6 10-i & 10-ii 10-1 - 10-15 A-i & A-ii V1-i - V1-iv V1-1 - V1-52 V1-A-i/ii V1-A-1 - V1 -A- 3 Vl-B-i/ii V1-B-1 & V1-B-2 Vi-C-i/ii V1-C-1 - 1 of 4 V1-C-8 PAGE J. I 9906220178 990608 PDR ADOCK 07109001 iii-1 B PDR REVISION CONTROL SHEET TITLE: Consolidated Safety DOCUMENT NO.: NEDO-10084 Analysis Report for IF-300 Shipping Cask AFFECTED DOC. REMARKS PAGE(S) REV. Vl-D-i - 3 Vl-D-vi Vl-D-1 - Vl-D-132 Vl-E-i & Vl-E-ii V1-E-l - V1-E-34 U V2-i - V2-iv V2-1 - V2-64 V3-i - V3-iv V3-1 - V3-32 VI-i & VI-ii VI-1 - VI-6 i - viii First revision prepared by VECTRA Technologies, Inc.
    [Show full text]
  • Fundamentals of Boiling Water Reactor (Bwr)
    FUNDAMENTALS OF BOILING In this light a general description of BWR is presented, with emphasis on the reactor physics aspects (first lecture), and a survey of methods applied in fuel WATER REACTOR (BWR) and core design and operation is presented in order to indicate the main features of the calculation^ tools (second lecture). The third and fourth lectures are devoted to a review of BWR design bases, S. BOZZOLA reactivity requirements, reactivity and power control, fuel loading patternc. Moreover, operating 'innts are reviewed, as the actual limits during power AMN Ansaldo Impianti, operation and constraints for reactor physics analyses (design and operation). Genoa, The basic elements of core management are also presented. The constraints on control rod movements during the achieving of criticality Italy and low power operation are illustrated in the fifth lecture. The banked position withdrawal sequence mode of operation is indeed an example of safety and design/operation combined approach. Some considerations on plant transient analyses are also presented in the fifth lecture, in order to show the impact Abstract between core and fuel performance and plant/system performance. The last (sixth) lecture is devoted to the open vessel testing during the These lectures on fundamentals of BWR reactor physics are a synthesis startup of a commercial BWR. A control .od calibration is also illustrated. of known and established concepts. These lecture are intended to be a comprehensive (even though descriptive in nature) presentation, which would give the basis for a fair understanding of power operation, fuel cycle and safety aspects of the boiling water reactor. The fundamentals of BWR reactor physics are oriented to design and operation.
    [Show full text]
  • Tracg Analysis of Boiling Water Reactor Control Rod Drop Accident to Optimize Analysis Methodology
    TRACG ANALYSIS OF BOILING WATER REACTOR CONTROL ROD DROP ACCIDENT TO OPTIMIZE ANALYSIS METHODOLOGY D. Miranda*, C. McElroy, D. G. Vreeland, J. Yang, J. Banfield, and J. Vedovi GE Hitachi Nuclear Energy 3901 Castle Hayne Road, Wilmington, NC 28402, USA [email protected]; [email protected]; [email protected]; [email protected]; [email protected]; [email protected] ABSTRACT During transient events, it is important to confirm that the plant maintains compliance to regulatory standards that provide safety criteria to prevent the release of fission products. The design basis Reactivity Insertion Accident (RIA) considered for Boiling Water Reactors (BWRs) is the Control Rod Drop Accident (CRDA). During this postulated scenario, a control blade becomes decoupled from the control rod drive mechanism as the drive is withdrawn and remains lodged in place. At a later time, the blade falls out to the position of the drive causing a reactivity insertion into the core. This leads to a power excursion and terminates due to the Doppler Effect or upon completion of the SCRAM. Many BWR plants adopt a Banked Position Withdrawal Sequence (BPWS) methodology that was developed to minimize the control rod worth and mitigate the consequences of the CRDA event. The BPWS methodology places restrictions on control rod movement to ensure that no CRDA could exceed the applicable event limits by reducing the incremental control rod reactivity worth to acceptable values. In this paper, the best estimate model code TRACG, the GE Hitachi (GEH) Nuclear Energy proprietary version of the Transient Reactor Analysis Code, TRAC, is used to model CRDA event to ensure that the plant is compliant with the new more restrictive regulatory standards.
    [Show full text]
  • Occupational Exposure at Nuclear Power Plants in Tarragona Spain in April 2000
    INFORMATION SYSTEM ON OCCUPATIONAL EXPOSURE Ninth Annual Report OCCUPATIONAL EXPOSURES AT NUCLEAR POWER PLANTS 1999 ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT Pursuant to Article 1 of the Convention signed in Paris on 14th December 1960, and which came into force on 30th September 1961, the Organisation for Economic Co-operation and Development (OECD) shall promote policies designed: - to achieve the highest sustainable economic growth and employment and a rising standard of living in Member countries, while maintaining financial stability, and thus to contribute to the development of the world economy; - to contribute to sound economic expansion in Member as well as non-member countries in the process of economic development; and - to contribute to the expansion of world trade on a multilateral, non-discriminatory basis in accordance with international obligations. The original Member countries of the OECD are Austria, Belgium, Canada, Denmark, France, Germany, Greece, Iceland, Ireland, Italy, Luxembourg, the Netherlands, Norway, Portugal, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States. The following countries became Members subsequently through accession at the dates indicated hereafter: Japan (28th April 1964), Finland (28th January 1969), Australia (7th June 1971), New Zealand (29th May 1973), Mexico (18th May 1994), the Czech Republic (21st December 1995), Hungary (7th May 1996), Poland (22nd November 1996) and the Republic of Korea (12th December 1996). The Commission of the European Communities takes part in the work of the OECD (Article 13 of the OECD Convention). NUCLEAR ENERGY AGENCY The OECD Nuclear Energy Agency (NEA) was established on 1st February 1958 under the name of the OEEC European Nuclear Energy Agency.
    [Show full text]
  • BWRX-300 (GE Hitachi and Hitachi GE Nuclear Energy) USA DATE (2019/9/30)
    Status Report – BWRX-300 (GE Hitachi and Hitachi GE Nuclear Energy) USA DATE (2019/9/30) The BWR-300 is the 10th generation Boiling Water Reactor (BWR) crated by GE Hitachi Nuclear Energy (GEH). It is a SMR evolution of the ESBWR which is licensed by the US NRC and utilizes many of the components for the operational ABWR. The first BWRX-300s are expected to start construction in in 2024 and 2025 and enter commercial operation in 2027 and 2028. INTRODUCTION Indicate which booklet(s): [ ] Large WCR [√] SMR [ ] FR GE Hitachi Nuclear Energy’s (GEH’s) BWRX-300 is a designed-to-cost, 300 MWe water- cooled, natural circulation Small Modular Reactor (SMR) utilizing simple, natural phenomena driven safety systems. It is the tenth generation of the Boiling Water Reactor (BWR) and represents the simplest, yet most innovative BWR design since GE, GEH’s predecessor in the nuclear business, began developing nuclear reactors in 1955. The BWRX-300 is an evolution of the U.S. NRC-licensed, 1,520 MWe ESBWR. It is designed to provide clean, flexible energy generation that is cost competitive with natural gas fired plants. Target applications include base load electricity generation, load following electrical generation within a range of 50 to 100% power and district heating. GEH, a world-leading provider of advanced reactor technology and nuclear services, is a global alliance created by the General Electric Company (GE) and Hitachi, Ltd. to serve the global nuclear industry. Development Milestones 2014 ESBWR DCD Issued 2017 BWRX-300 Evolution from ESBWR
    [Show full text]
  • Limerick Generating Station, Units 1 & 2, Revision 19 to Updated Final
    LGS UFSAR CHAPTER 1 - INTRODUCTION AND GENERAL DESCRIPTION OF PLANT TABLE OF CONTENTS 1.1 INTRODUCTION 1.2 GENERAL PLANT DESCRIPTION 1.2.1 Site Characteristics 1.2.1.1 Location 1.2.1.2 Site Environs and Access 1.2.1.3 Geology 1.2.1.4 Seismology 1.2.1.5 Hydrology 1.2.1.6 Meteorology 1.2.2 Principal Design Criteria 1.2.2.1 General Design Criteria 1.2.2.2 System Design Criteria 1.2.2.2.1 Nuclear System Criteria 1.2.2.2.2 Safety-Related Systems Criteria 1.2.2.2.3 Process Control Systems Criteria 1.2.2.2.4 Power Conversion Systems Criteria 1.2.2.2.5 Electrical Power Systems Criteria 1.2.2.2.6 Auxiliary Systems Criteria 1.2.2.2.7 Radioactive Waste Management Systems Criteria 1.2.2.2.8 Shielding and Access Control Criteria 1.2.2.2.9 Fuel Handling and Storage Facilities 1.2.3 General Arrangement of Structures and Equipment 1.2.4 System Description 1.2.4.1 Nuclear System 1.2.4.1.1 Reactor Core and Control Rods 1.2.4.1.2 Reactor Vessel and Internals 1.2.4.1.3 Reactor Recirculation System 1.2.4.1.4 Residual Heat Removal System 1.2.4.1.5 Reactor Water Cleanup System 1.2.4.1.6 Nuclear Leak Detection System 1.2.4.2 Safety-Related Systems 1.2.4.2.1 Reactor Protection System 1.2.4.2.2 Neutron Monitoring System 1.2.4.2.3 Control Rod Drive System 1.2.4.2.4 Control Rod Velocity Limiter 1.2.4.2.5 Control Rod Drive Housing Supports 1.2.4.2.6 Nuclear System Pressure Relief System 1.2.4.2.7 Reactor Core Isolation Cooling System 1.2.4.2.8 Primary Containment CHAPTER 01 1-i REV.
    [Show full text]
  • Innovation Pathway Study: U.S. Commercial Nuclear Power
    Nuclear Industry Innovation Pathway Study Prepared for the Office of Energy Policy and Systems Analysis Task Order No. DE-BP0004706 Innovation Pathway Study: U.S. Commercial Nuclear Power Prepared by Energetics Incorporated1 Christopher W. Gillespie, Robert A. Johnson, Marty Martinez, Emmanuel Taylor April 29, 2016 This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference therein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views of the authors do not necessarily reflect those of the United States Government or any agency thereof. 1Energetics Incorporated, 901 D St SW, Washington, DC 20024; email: [email protected], [email protected], [email protected], [email protected] i Nuclear Industry Innovation Pathway Study EPSA Task Order No. DE-BP0004706 Executive Summary The nuclear energy sector has one of the most idiosyncratic histories of research, development, demonstration, and deployment among widely-used energy technologies in the U.S. The unique attributes of nuclear energy and fissile materials, the historical context in which nuclear technologies were introduced, and institutional attributes of the post-war U.S.
    [Show full text]
  • Nuclear Engineering Handbook Boiling Water Reactors
    This article was downloaded by: 10.3.98.104 On: 28 Sep 2021 Access details: subscription number Publisher: CRC Press Informa Ltd Registered in England and Wales Registered Number: 1072954 Registered office: 5 Howick Place, London SW1P 1WG, UK Nuclear Engineering Handbook Kenneth D. Kok Boiling Water Reactors Publication details https://www.routledgehandbooks.com/doi/10.1201/9781315373829-5 Kevin Theriault Published online on: 21 Oct 2016 How to cite :- Kevin Theriault. 21 Oct 2016, Boiling Water Reactors from: Nuclear Engineering Handbook CRC Press Accessed on: 28 Sep 2021 https://www.routledgehandbooks.com/doi/10.1201/9781315373829-5 PLEASE SCROLL DOWN FOR DOCUMENT Full terms and conditions of use: https://www.routledgehandbooks.com/legal-notices/terms This Document PDF may be used for research, teaching and private study purposes. Any substantial or systematic reproductions, re-distribution, re-selling, loan or sub-licensing, systematic supply or distribution in any form to anyone is expressly forbidden. The publisher does not give any warranty express or implied or make any representation that the contents will be complete or accurate or up to date. The publisher shall not be liable for an loss, actions, claims, proceedings, demand or costs or damages whatsoever or howsoever caused arising directly or indirectly in connection with or arising out of the use of this material. 3 Boiling Water Reactors Kevin Theriault CONTENTS 3.1 Introduction ..........................................................................................................................87
    [Show full text]
  • REVIEW of FUEL FAILURES in WATER COOLED REACTORS the Following States Are Members of the International Atomic Energy Agency
    IAEA Nuclear Energy Series IAEA Nuclear No. NF-T-2.1 No. Reactors Water-Cooled in Failures Fuel of Review IAEA Nuclear Energy Series No. NF-T-2.1 Basic Review of Principles Fuel Failures in Water Cooled Reactors Objectives Guides Technical Reports INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA ISBN 978–92–0–102610–1 ISSN 1995–7807 10-08811_P1445_cover.indd 1 2010-06-24 14:41:44 IAEA NUCLEAR ENERGY SERIES PUBLICATIONS STRUCTURE OF THE IAEA NUCLEAR ENERGY SERIES Under the terms of Articles III.A and VIII.C of its Statute, the IAEA is authorized to foster the exchange of scientific and technical information on the peaceful uses of atomic energy. The publications in the IAEA Nuclear Energy Series provide information in the areas of nuclear power, nuclear fuel cycle, radioactive waste management and decommissioning, and on general issues that are relevant to all of the above mentioned areas. The structure of the IAEA Nuclear Energy Series comprises three levels: 1 — Basic Principles and Objectives; 2 — Guides; and 3 — Technical Reports. The Nuclear Energy Basic Principles publication describes the rationale and vision for the peaceful uses of nuclear energy. Nuclear Energy Series Objectives publications explain the expectations to be met in various areas at different stages of implementation. Nuclear Energy Series Guides provide high level guidance on how to achieve the objectives related to the various topics and areas involving the peaceful uses of nuclear energy. Nuclear Energy Series Technical Reports provide additional, more detailed, information on activities related to the various areas dealt with in the IAEA Nuclear Energy Series.
    [Show full text]
  • NUREG-1617, Supplement 1
    NUREG-1617 Supplement 1 NU Standard Review Plan for Transportation Packages for MOX Spent Nuclear Fuel U.S. Nuclear Regulatory Commission Office of Nuclear Material Safety and Safeguards Washington, DC 20555-0001 NUREG-1617 Supplement 1 Standard Review Plan for Transportation Packages for MOX Spent Nuclear Fuel Manuscript Completed: September 2005 Date Published: September 2005 Prepared by R.S. Hafner, G.C. Mok, J. Hovingh, C. K. Syn, E.W. Russell, S.C. Keaton, J.L. Boles, D.K. Vogt, P. Prassinos Lawrence Livermore National Laboratory 7000 East Avenue Livermore, CA 94550-9234 J.A. Smith, NRC Project Manager Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 NRC Job Code A0291 [THIS PAGE BLANK] ii ABSTRACT The NRC contracted with LLNL to compile this supplement to NUREG-1617 to incorporate additional information specific to mixed uranium-plutonium oxide (MOX) fuel. This supplement provides details on package review guidance resulting from significant differences between spent nuclear fuel from irradiated LEU fuel and that from irradiated MOX fuel. The information presented is not to be construed as having the force and effect of NRC regulations (except where regulations are cited), or as indicating that applications supported by safety analyses and prepared in accordance with Regulatory Guide 7.9 will necessarily be approved, or as relieving anyone from the requirements of any pertinent regulations. The principal purpose of this supplement is to ensure the quality and uniformity of staff reviews of packagings intended for transport of MOX fuel assemblies irradiated in thermal reactors only.
    [Show full text]
  • False Promises
    False Promises Debunking Nuclear Industry Propaganda NUCLEAR INFORMATION AND RESOURCE SERVICE 6930 Carroll Avenue, Suite 340 • Takoma Park, MD 20912 • 301-270-6477 www.nirs.org • [email protected] False Promises By the Staff of Nuclear Information and Resource Service Michael Mariotte, Executive Director Diane D’Arrigo, Radioactive Waste Project Director Mary Olson, Southeast Regional Coordinator Aja Binette, Nuclear Power Economics Campaigner Donald Keesing, Administrative Coordinator With contributions from Cindy Folkers, Paul Gunter and Kevin Kamps Revised from False Promises by Jessie Carr and Dulce Fernandes May 2008 TABLE OF CONTENTS 1 FOREWORD 23 By Michael Mariotte 3 FOREWORD TO FIRST EDITION By Robert Alvarez 30 5 EXECUTIVE SUMMARY 34 6 INTRODUCTION 9 BRIEF HISTORY OF NUCLEAR POWER’S 38 FALSE PROMISES 11 CHAPTER 1 41 Nuclear power is counterproductive for combating climate change 14 CHAPTER 2 42 Nuclear power can be dangerously unreliable under severe weather or destabilized climate conditions 16 CHAPTER 3 47 There are many proven, sustainable alternatives to nuclear power and coal 51 21 CHAPTER 4 Nuclear power pollutes 52 23 CHAPTER 5 Reactors remain dangerous; catastrophic accidents can and likely will occur 30 CHAPTER 6 Nuclear power is expensive 34 CHAPTER 7 Radioactive waste remains a problem without a solution 38 CHAPTER 8 Nuclear weapons proliferation concerns are increasing worldwide 41 CHAPTER 9 Nuclear power does not lead to greater energy security or US energy independence 42 CHAPTER 10 Even routine operations of nuclear reactors result in radiation releases and health impacts 47 PROPAGANDA MACHINE: MISLEADING POLLS AND PSEUDO EXPERTS 51 CONCLUSION 52 NOTES FOREWORD By Michael Mariotte Executive Director, Nuclear Information and Resource Service wrote my first article on the potential resurgence States (currently 104) and probably quadruple or more of nuclear power in 1989, for the Multinational the number across the world (currently about 440), all IMonitor.
    [Show full text]
  • References – Nuclear Power Plants Company Profile and References for Architect-Engineering Services - Nuclear Projects
    EMPRESARIOS AGRUPADOS References – Nuclear Power Plants Company Profile and References for Architect-Engineering Services - Nuclear Projects COMPANY PROFILE Empresarios Agrupados (EA) is a leading architect-engineering organisation in Spain with significant international experience, providing a complete range of consulting, project management, engineering and design, procurement, construction management, plant testing, safety assessment, quality assurance, as well as plant operation and maintenance support services to the electric utility industry. Founded in 1971, EA has a permanent multidisciplinary staff of approximately 1000, 65% of whom are university graduates, involved in engineering projects and services in the electric utility sector. Serving the electric utility industry is one of EA's primary objectives as an architect-engineering company. In the field of power generation, EA's work includes the design, construction and operation support of nuclear, fossil-fired and hydroelectric power plants and radioactive waste management facilities, as well as the safety assessment, modernisation, backfitting, repowering and life extension of operating plants and facilities. Services provided by EA in the field of power generation are: Feasibility studies Site selection and project development studies Preparation of Bid Invitation Specifications (BIS) and evaluation of bids Project management Engineering and design Procurement management Construction management Plant testing and startup Plant operation and maintenance Quality assurance/quality control EA has completed the engineering and construction of power plant projects totalling more than 39,000 MWe of power generating capacity worldwide. Nuclear – 2 (11.1) Page 1 Company Profile and References for Architect-Engineering Services - Nuclear Projects EA has provided engineering and consultancy services, and completed projects in Spain and some 35 other countries.
    [Show full text]