DOCSLIB.ORG

Reed College Reed Research Reactor License No

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Reed College Reed Research Reactor License No REED COLLEGE REED RESEARCH REACTOR LICENSE NO. R-112 DOCKET NO. 50-288 LICENSE RENEWAL APPLICATION SAFETY ANALYSIS REPORT, TECHNICAL SPECIFICATIONS, ENVIRONMENTAL CONSIDERATIONS, AND OPERATOR REQUALIFICATION PROGRAM REDACTED VERSION* SECURITY-RELATED INFORMATION REMOVED *REDACTED TEXT AND FIGURES BLACKED OUR OR DENOTED BY BRACKETS REED COLLEGE __ Portland, Oregon 97202 REACTOR FACILITY August 29, 2007 US Nuclear Regulatory Commission Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Docket: 50-288 Subject: License Renewal This is Reed College's application for a renewal of the operating license for the Reed Research Reactor, License R-1 12, Docket 50-288. Reed College is a private non-profit educational institution incorporated in the State of Oregon. The applicant information is: Reed Institute (dba Reed College) 3203 SE Woodstock Blvd. Portland, OR 97202 Reed is applying to be licensed as a Class 104 facility for an additional 20 years. As part of the relicensing, Reed is upgrading the licensed power level to 500 kW. The license will be used for primarily educational activities in Portland, Oregon and the surrounding region. Enclosed are the supporting documents, including; 1. Updated Safety Analysis Report (SAR) 2. Technical Specifications 3. Financial Qualifications and Decommissioning per 1OCFR50.33(f)(2) and 1OCFR50.33(k) 4. Environmental Report 5. Radiation Protection Plan 6. Operator Requalification Plan• 7. Fire Plan 8. Administrative Procedures There are no changes to Reed College's Emergency Plan or Physical Security Plan being implemented as part of the relicensing, so they are not included in this submittal. The most recent versions of each plan remains in effect. Reed College is not owned, controlled, or dominated by an. alien, foreign corporation, or foreign government. I declare under penalty of perjury that the foregoing is true and correct. Executed on August 29, 2007. Stephen G. Frantz Ao2o Reactor Director 3203 SE Woodstock Blvd., Portland,OR 97202-8199 503-777-7222 Fax: 503-777-7274 [email protected] /i Safety Analysis .Report August 2007 Reed Research Reactor 3203 SE Woodstock Boulevard Portland, Oregon 97202 (503) 777-7222 License R-1 12 Docket 50-288 0 This Page is Intentionally Blank 0 0 1. The Facility ....................c ........................................................ 2. Site Characteristics ................................................................ 3. Design Of Structures, Systems, and Components ............... 4. Reactor Description ......................................................... 5. Reactor Coolant Systems ...................................................... 6. Engineered Safety Features .................................................. 7. Instrumentation and Control Systems .................................. 8. Electrical Power Systems ............................... 9. Auxiliary Systems .................................................................. 10. Experimental Facilities and Utilization ............................... 11. Radiation Protection and Waste Management ..................... 12. Conduct of Operations .......................................................... 13. Accident Analysis .................................................................. 14. Technical Specifications ................................ 15. Financial Qualifications ....................................................... 16. Other License Conditions ...................................................... 17. Environmental Report ........................................................... 18. Radiation Protection Plan .............................. 19. Requalification Plan .............................................................. 20. Fire Plan ........................................... 21. Administrative Procedures .................................................... Chapter 1 The Facility Reed Research Reactor Safety Analysis Report 0 This Page is Intentionally Blank Chapter 1 The Facility Table of Contents 1 The Facility ....................................................................................................... 1 1.1 Introduction ......................... o.............................................................................. 1 1.2 Summary & Conclusions on Principal Safety Considerations ........................ 2 1.2.1 Safety C onsiderations .............................................................................. 2 1.2.2 Consequences of Normal Operations ....................................................... 3 1.2.3 Consequences of Potential Accidents ...................................................... 4 1.3 General Description of the Facility ................................................................... 4 1.3.1 G eographical Location .............................................................................. 4 1.3.2 Principal Characteristics of the Site ........................................................... 4 1.3.3 Principal Design Criteria, Operating Characteristics, & Safety System s .............................................................................................. ... 5 1.3.4 Engineered Safety Features ..................................................................... 5 1.3.5 Instrumentation and Control (I&C) and Electrical Systems ....................... 5 1.3.5.1 Reactor Control System ............................................................... 6 1.3.5.2 Radiation Safety Monitoring Systems ........................................... 8 1.3.5.3 Electrical Power ................................ .... 8 1.3.5.4 Reactor Protection System .......................................................... 8 1.3.6 Reactor Coolant and Other Auxiliary Systems ........................................ 8 1.3.6.1 Reactor Coolant System .............................................................. 8 1.3.6.2 Secondary Cooling System .......................................................... 9 1.3.6.3 M akeup ........................................................................................ 9 1.3.7 Radioactive Waste Management and Radiation Protection ....................... 9 1.3.7.1 G aseous W aste ........................................................................... 9 1.3.7.2 L iquid W aste ............................................................................... 9 1.3.7.3 Solid Waste ............................................................. 9 1.3.8 Experimental Facilities and Capabilities ....................................... ... 10 1.3.8.1 Central Thimble .................................... 10 1.3.8.2 Rotary Specimen Rack ........ ............... 10 1.3.8.3 Pneum atic Specim en Tube ........................................................... 10 1.4 Shared Facilities and Equipment ................................. 10 1.5 Comparison with Similar Facilities ....... .......... ;................................. 11 1.6 Summary of Operations ................................................................................... 12 1.7 Compliance with Nuclear Waste Policy Act of 1982 ..................... e..................... 13 1.8 Facility Modifications and History ...................................................................... 13 1.9 R eferences ............................................................................................................. 13 This Page is Intentionally. Blank 0 0 1 THE FACILITY 1.1 Introduction This safety analysis report supports an application to the U.S. Nuclear Regulatory Commission (NRC) by Reed College for the utilization of a TRIGA®-fueled research reactor. The reactor is owned and operated by Reed College for the purpose of performing neutron irradiation services for a wide variety of scientific applications. The reactor is known as the Reed Research Reactor (RRR). The license number is R-112, Docket 50-288. The Reed Research Reactor (RRR) is owned and operated by Reed College, a private undergraduate educational institution located in Portland, Oregon. The reactor was obtained in 1968 through a grant from the United States Atomic Energy Commission and is currently operated under Nuclear Regulatory Commission License R- 112 and the regulations of Chapter 1, Title 10, Code of Federal Regulations. The facility supports education and training, research, and public service activities. The reactor is in a building constructed for that purpose and which is situated adjacent to the Psychology Building near the southeast comer of the Reed College campus in southeast Portland. The a campus has approximately 1,300 students while the city of Portland has approximately 560,000 people, as described in Chapter 2, Site Characteristics. This report is based on the Safety Analysis Report, Reed Reactor Facility for the initial operation of the reactor at 250 kW thermal power, and subsequent analyses supporting steady-state operations to a maximum of 500 kW. The RRR is a non-pulsing reactor. This report addresses safety issues associated with operation of the reactor at steady-state power levels up to 500 kW. This report reflects the as-built condition of the facility, and includes experience with the operation and performance of the reactor, radiation surveys, and personnel exposure histories related to operations to a maximum of 250 kW steady- state power. The consequence of routine generation of radioactive effluent and other waste products from steady-state operation to a maximum of 500 kW is addressed in Chapter 11, Radiation
Load more

Recommended publications
  • EMD Uranium (Nuclear Minerals) Committee 2017 EMD Uranium (Nuclear Minerals and REE) Committee Mid-Year Report
    EMD Uranium (Nuclear Minerals) Committee 2017 EMD Uranium (Nuclear Minerals and REE) Committee Mid-Year Report November 26, 2017 Table of Contents Page UCOM Committee Personnel .………………………….... 3 UCOM Committee Activities ……………………………. 4 UCOM Publications and Nuclear Outreach ……………… 5 Objectives of UCOM Reports ……………………………. 7 Executive Summary ……………………………………... 8 Introduction ………………………………………………. 9 Sources of Uranium 13 Energy Subsidies ………………………………………….. 14 Uranium Prices ………………….. ………………………. 17 Industry Response to Uranium Price Fluctuations ……………. 19 The Impact of Japan ………………………………………. 19 Uranium Production in the U.S.- 4th Quarter, 2017 . ……… 20 U.S. Uranium Mill in Production (by State) …………………. 20 U.S. Uranium In-Situ Recovery Plants in Production (by State) 20 Uranium Exploration. ………………………………………. 23 Uranium Mining ……………………………………………. 23 Uranium Milling ……………………………………………. 24 Uranium Conversion ………………………………………. 24 Uranium Enrichment ……………………………………….. 25 Uranium Reconversion and Nuclear Fuel Fabrication . ……. 25 Interim Storage and Final Disposal ………………………… 26 U.S. Nuclear Power Plants Under Construction …………… 30 Design Certifications …………………………………………….. 31 Small Modular Reactors (SMRs) …………………………... 32 Nuclear Waste Storage ……………………………………… 33 International Uranium Exploration & Development ………. 34 International Uranium Production …………………………. 35 International Nuclear Power Activity ……………………… 36 Overall Perspective ………………………………………… 38 Coal vs. Nuclear Power & National Gas ……………………. 38 Renewable Energy vs. Nuclear Power ………………………. 38
    [Show full text]
  • NRC Collection of Abbreviations
    I Nuclear Regulatory Commission c ElLc LI El LIL El, EEELIILE El ClV. El El, El1 ....... I -4 PI 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, P. 0. Box 37082, Washington, DC 20402-9328 3. The National Technical Information Service, Springfield, VA 22161-0002 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 Government Printing Office: formal NRC staff and contractor reports, NRC-sponsored conference pro- ceedings, international agreement reports, grantee reports, and NRC booklets and bro- chures. Also available are regulatory guides, NRC regulations in the Code of Federal Regula- tions, and Nuclear 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.
    [Show full text]
  • Innovative Nuclear Research Highlights
    U.S. Department of Energy Innovative Nuclear Research Highlights The Oregon State University TRIGA reactor is a water cooled, pool type research reactor which uses uranium/zirconium hydride fuel elements in a circular grid array. The reactor is licensed by the U.S. Regulatory Commission to operate at a maximum stead state power of 1.1 MW and can also be pulsed up to a peak power of about 2,500 MW. ii INNOVATIVE NUCLEAR RESEARCH Overview Innovative Nuclear Research (INR) houses the competitively funded programs ad- ministered by the U.S. Department of Energy, Office of Nuclear Energy (DOE-NE). INR provides a consolidated vision and peer review process to DOE-NE research and de- velopment programs and dedicates support to training the next generation of nuclear scientists through multiple student opportunities. Through the Consolidated Innovative DOE-NE conducts Several programs fall under the INR umbrella: Nuclear Research Funding Opportunity Announcement, NE conducts Nuclear Energy University Program crosscutting nuclear energy research (NEUP) - University research integrated and development (R&D) and associated with overall DOE-NE program priorities infrastructure support activities to develop innovative technologies Integrated University Program (IUP) - that offer the promise of dramatically Student educational support to improved performance for its mission train the next generation nuclear needs, while maximizing the impact of energy workforce DOE resources. Nuclear Energy Enabling Technologies Through the Integrated University Crosscutting
    [Show full text]
  • REED COLLEGE RESEARCH REACTOR DECOMMISSIONING COST ESTIMATE February 2018
    REED COLLEGE RESEARCH REACTOR DECOMMISSIONING COST ESTIMATE February 2018 Stephen L. Bump, CHP, CIH, PMP William E. Kennedy, Jr, MSNE Tracy A. Ikenberry, CHP Prepared For: Reed College 32-3 SE Woodstock Blvd. Portland, OR 97212 1835 Terminal Drive Suite 200 Richland, WA 99354 DMA-TR-083 EXECUTIVE SUMMARY At the request of Reed College, NV5/Dade Moeller performed this Decommissioning Study to provide cost estimates and to evaluate alternatives for the eventual decommissioning the Reed Research Reactor (RRR) facility located in Portland, Oregon. This study uses information from a variety of sources, including the previous study performed by Reed College in 2010, several U.S. Nuclear Regulatory Commission (NRC) guidance documents and reports, and the decommissioning plans, cost estimates, and experience from other university research reactors. Wherever possible, current RRR-specific information and current decommissioning cost factors were used, particularly those related to low-level radioactive waste handling and disposal. This study presents alternative decommissioning strategies: one called DECON, where the facility is qualified for unrestricted release within a couple of years after permanent cessation of reactor operations; and one called SAFSTOR, where the facility is placed in a secure mode for several decades after permanent cessation of reactor operations to allow time for additional radioactive decay before final decommissioning. Due to the uncertainties associated with SAFSTOR, the DECON strategy is likely to be preferred for RRR decommissioning. In order to provide a frame of reference, three additional reactor decommissioning cost estimates are shown in Table E-1. The University of Illinois shows actual costs for their decommissioning project.
    [Show full text]
  • TRTR IGORR 2005 Schedule of Speakers.Pdf
    Tuesday, September 13 Welcoming Session: 8:30-8:40 Tawfik Raby, Co-Chair, TRTR Seymour Weiss, Co-Chair, TRTR 8:40-8:50 Alain Ballagny, Chairman, IGORR 8:50-9:05 Welcome Dr. Patrick Gallagher Director, NIST Center for Neutron Research 9:05-9:20 Keynote Address: Colin West, First IGORR Chairman 9:20-9:40 Keynote Address: William Magwood, Former Director, DOE-NE 9:40-10:00 Keynote Address: Prof. Dr. Winfried Petry, Scientific Director, FRM-II Performance of the New High Flux Neutron Source -FRM-II 10:00-10:20 Keynote Address: Dr. Daniel Iracane, CEA, Project Leader, Jules Horowitz Reactor The Jules Horowitz Reactor, a New Material Testing Reactor in Europe Technical Session 1: Ballroom Chairman: Robert Williams 10:40-11:00 Enhancing Research Reactor Safety – The IAEA’s Approach Ken E. Brockman (presented by L. Walter Deitrich) 11:00-11:20 Progress on the Construction of Australia’s Replacement Research Reactor (OPAL) Ross Miller 11:20-12:20 Operating Reactors and Upgrades Ballroom 11:20-11:40 First Experience with the Operation of the FRM-II Heiko Gerstenberg 11:40-12:00 Advanced Test Reactor Capabilities and Future Operating Plans Frances M. Marshall 12:00-12:20 Status of the High Flux Isotope Reactor and the Reactor Scientific Upgrades Program Douglas L. Selby 13:30-14:00 Keynote Address: Ballroom The Honorable William A. Jeffrey Director, National Institute of Standards and Technology Technical Session 2: Fuel Cycle Developments Ballroom Chairman: Alain Ballagny 14:00-14:20 Research Reactor Low Enriched Uranium: Supply, Demand, Capabilities and Quality Morris Hassler 14:20-14:40 Update on the Effort to Develop and Qualify New Low Enrichment Fuels Mitchell K.
    [Show full text]
  • "Handbook of Acronyms & Initialisms."
    NUREG-0544 A HANDBOOK OF ACRONYMS AND INITIALISMS p* "muq % 5 ..... Office of Administration U. S. Nuclear Regulatory Commission '9 05 140 f73 NUREG4544 A HANDBOOK OF ACRONYMS AND INITIALISMS Manuscript Completed: March 1979 Date Published: March 1979 Division of Technical Information and Document Control Office of Administration U. S. Nuclear Regulatory Commission Washington, D.C. 20555 PREFACE This " Handbook of Acronyms and Initialisms" is a dictionary of acro- nyms, initialisms and similar condensed forms observed in use in the nuclear industry. It was compiled to serve as a source for learning the meaning of undefined acronyms found in the literature. The use of these acronyms in NRC documents is neither recommended or condemned, and, similarly, the accuracy and completeness of this document is not assured. If you use these or similar condensed forms in your writing we strongly recommend the practice of writing out the condensed form first and following it with the acronym or initialism in parentheses; for example, U.S. Nuclear Regulatory Commission (NRC). After the ini- tial writing out of the full name, the acronym may be used by itself. For the purposes of this document the following definitions apply: Acronym - a pronounceable term formed from the initial letters of a compound expression, e.g. NASA (National Aeronautics andSpaceAdministration)orRem({oentgen[quivalent man). Initialism - a term, not pronounceable, formed from the initial letters of a compound expression, e.g. CIA (Central Intelligence Agency) or ac (alternating current). Comments, criticisms or suggestions regarding this publication are en- couraged. In so far as possible, we would like this document to be a valuable part of your reference material.
    [Show full text]
  • Environmental Assessment and Finding of No Significant Impact For
    19362 Federal Register / Vol. 77, No. 62 / Friday, March 30, 2012 / Notices appropriate automated, electronic, relating to international cooperation or Tuesday, April 24, 2012 mechanical, or other technological national security, and, when deemed 6 p.m.–7 p.m. Closed—Briefing of panel collection techniques or other forms of appropriate by the Foundation, such 7 p.m.–8:30 p.m. Open—Poster Session information technology should be contracts or other arrangements or Wednesday, April 25, 2012 addressed to: Office of Information and modifications thereof, may be entered Regulatory Affairs of OMB, Attention: into without legal consideration, 7:45 a.m.–3:45 p.m. Open—Review of the MRSEC Desk Officer for National Science without performance or other bonds and 3:45 p.m.–5:30 p.m. Closed—Executive Foundation, 725 17th Street NW., Room without regard to section 5 of title 41, Session 10235, Washington, DC 20503, and to U.S.C. 6 p.m.–7:30 p.m. Open—Dinner Suzanne H. Plimpton, Reports Clearance Use of the Information: Request for Thursday, April 26, 2012 Officer, National Science Foundation, Proposals (RFP) is used to competitively 4201 Wilson Boulevard, Suite 295, solicit proposals in response to NSF 8 a.m.–9 a.m. Closed—Executive session Arlington, Virginia 22230 or send email need for services. Impact will be on 9 a.m.–10:45 a.m. Open—Review of the MRSEC to [email protected]. Comments regarding those individuals or organizations who 10:45 a.m.–4:45 p.m. Closed—Executive these information collections are best elect to submit proposals in response to Session, Draft and Review Report assured of having their full effect if the RFP.
    [Show full text]
  • Nuclear Reactors Built, Being Built, Or Planned 1994
    DOE/OSTI--8200-R58 (DE95012001) August 1995 Distribution Categories UC-500, UC-522, UC-523, UC-530, and SO820 ISSN: 0364-6866 CODEN: NRBPDB Nuclear Reactors Built, Being Built, or Planned 1994 Prepared for: U.S. DEPARTMENT OF ENERGY Director, Office of Nuclear Energy, Science and Technology Washington, D.C. 20585 Prepared by: Office of Scientific and Technical Information DISCLAIMER 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, make 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 herein to any specific commercial product, process, or service fay 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 and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document. Preface Nuclear Reactors Built, Being Built, or Planned contains of nuclear radiation for testing the life or performance of reactor unclassified information about facilities built, being built, or components as its major function (Part I, Section 3A; Part IV, planned in the United States for domestic use or export as of Section 2A).
    [Show full text]
  • Reed Response to Request for Additional Information with a Revised Safety Analysis Report and Technical Specifications
    REED RESEARCH REACOR LICENSE NO. R-112 DOCKET NO. 50-288 REED RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION WITH A REVISED SAFETY ANALYSIS REPORT AND TECHNICAL SPECIFICATIONS JULY 2010 REDACTED VERSION* SECURITY-RELATED INFORMATION REMOVED *REDACTED TEXT AND FIGURES BLACKED OUR OR DENOTED BY BRACKETS REED COLLEGE REACTOR FACILITY 3203 Southeast Woodstock Boulevard July 30, 2010 Portland, Oregon ATTN: Document Control Desk 97202-8199 U S. Nuclear Regulatory Commission Washington, DC 20555-0001 telephonw 5031777-7222 Docket: 50-288 fax License No: R-112 503/777-7274 Subject: RAI TACNO. ME1583 email [email protected] Attached are some of the answers to the subject RAI dated March 8, 2010. web As noted under the individual RAIs, some of the information needed for hrrp://reactor.reed.edu response is to be completed as part of the analysis being performed by Oregon State and General Atomics and will be submitted by November 2010. The response and attachments do not contain any sensitive informa- tion. Please contact us if you have any questions. Thank you. I declare under penalty of perjury that the foregoing is true and correct. Executed on 7-34- '- pDirector, Reed Research Reactor. Attachments: 1. RRRRAIs 1-58 2. RRR SOP 34, Control Rods 3. RRR SOP 34B Control Rod Calibration January 2010 4. RRR SAR Chapaters that have changed since the 2007 submital Aco'-Q) pvac 1. NUREG-1537, Part 1, Section 1.4, Shared Facilitiesand Equipment, states the applicant should consider whether the loss of any shared facilities or equipment could lead to a loss of function that would lead to an uncontrolled release of radioactive material,or if released,are analyzed and found to be acceptable.
    [Show full text]
  • Reactor-Grade Plutonium and Nuclear Weapons: Exploding the Myths REACTOR- GRADE PLUTONIUM and NUCLEAR WEAPONS
    Reactor-Grade Plutonium and Nuclear Weapons: Exploding the Myths Exploding Weapons: Nuclear and Plutonium Reactor-Grade REACTOR- GRADE PLUTONIUM AND NUCLEAR WEAPONS: “Bene ting from his decades-long research and EXPLODING analysis of publicly available, non-classi ed information, Jones seeks to debunk a long-standing myth that reactor-grade plutonium cannot be used THE MYTHS for nuclear weapons”. – Olli Heinonen, former Deputy Director-General for Safeguards at the International Atomic Energy Agency Gregory S. Jones Gregory S. Jones NPECNonproliferation Policy Education Center Foreword by Olli Heinonen Reactor-Grade Plutonium and Nuclear Weapons Reactor-Grade Plutonium and Nuclear Weapons: Exploding the Myths By Gregory S. Jones Copyright © 2018 by Gregory S. Jones Published by Nonproliferation Policy Education Center Arlington, VA 22209 www.npolicy.org 2018 Printed in the United States of America All rights reserved. Except for brief quotations in a review, this book, or parts thereof, must not be reproduced in any form without permission in writing from the author. ISBN 978-0-9862895-9-0 Cover design by Amanda Sokolski. Front cover image is of Cerenkov radiation surrounding the underwater core of the Reed Research Reactor, Reed College, Oregon, USA. The image was generated by the United States Nuclear Regulatory Commission. The image “Explosion Brushes,” by TWENSTUDIO is also used in the cover and is licensed under CC ND. Contents Foreword ii Preface viii Introduction 1 Chapter 1: Why Countries Might Choose Reactor- Grade Plutonium
    [Show full text]