DECOMMISSIONING OF THE GEORGIA TECH RESEARCH REACTOR. Steve Marske, Robert Eby, Lark Lundberg CH2M HILL
|
|
- Josephine Leonard
- 8 years ago
- Views:
Transcription
1 ABSTRACT DECOMMISSIONING OF THE GEORGIA TECH RESEARCH REACTOR Steve Marske, Robert Eby, Lark Lundberg CH2M HILL Nolan Hertel, Rod Ice Georgia Institute of Technology On July 1, 1997, the Georgia Institute of Technology (Georgia Tech) administration notified the U.S. Nuclear Regulatory Commission (NRC) of their intent to decommission the Georgia Tech Research Reactor (GTRR). The GTRR is a 5-megawatt (MW) heavy-water-cooled nuclear reactor located in downtown Atlanta, Georgia. In the summer of 1999, the NRC issued a license amendment to decommission the GTRR in accordance with NRC s Regulatory Guide In the spring of 1999, Georgia Tech and the State of Georgia contracted the services of CH2M HILL to serve as the Executive Engineer to manage the decommissioning project. Later in the summer of 1999, the IT Corporation was selected as the decommissioning contractor. IT subcontracted the waste management activities to GTS/Duratek, and the contractor mobilized on the Georgia Tech site in November 1999 to begin the dismantlement process. By February 2000, the reactor support systems, such as the primary and secondary cooling water systems, and the bismuth cooling system, were removed and packaged for off-site disposal. The reactor internals were removed in April The bioshield removal occurred in the May to November 2000 time frame. Various levels of effort were spent throughout January 2001 decontaminating concrete structures, including the Spent Fuel Storage Hole. The Final Survey report is anticipated to be submitted to the NRC in March 2001, and the final license termination is expected from the NRC August of Original Approach During the process, Georgia Tech took a unique approach to "as low as reasonably achievable" (ALARA), setting as an unrestricted release goal of 20 percent of the Regulatory Guide 1.86 contamination limits. This unique ALARA approach involves State of Georgia funding set aside to decontaminate the facility below the Regulatory Guide 1.86 limits. Because Georgia Tech is a premier institute of higher education, one of the de-commissioning objectives was to use the project as a learning tool for the institute's students. This paper will cover the project's status, describe the approach to decommission the reactor, and presents photographs and data from the work. DESCRIPTION OF THE REACTOR When in operation, the GTRR was a 5-MW thermal, heavy-water-moderated and-cooled reactor, fueled with plates of aluminum and highly enriched uranium alloy. The reactor core was approximately 2-feet in diameter and 2-feet high. When it was fully loaded, it contained 19 fuel elements, spaced 6 inches apart. Each element contained 16 fuel plates per assembly, each plate was 0.05 inches thick, 23.5 inches long, and 2.85 inches wide. Each element also contained 11.7 grams of 93 percent enriched uranium. The fuel elements were centrally located within a 6-foot diameter aluminum reactor vessel that provided a 2-foot thick D 2 O reflector that completely
2 surrounded the core. The reactor was controlled with four cadmium shim-safety blades and one cadmium regulating rod. The reactor vessel was mounted on a steel support structure and suspended within a thick-walled graphite cup. The graphite provided an additional 2 feet of reflector, both radially and beneath the vessel. The core and reflector system was completely enclosed by a lead and concrete biological shield (Figure 1). The bioshield was housed inside a cylindrical containment building made of steel and concrete. The containment building is approximately 82-feet in diameter and 50-feet tall. Fig. 1. Georgia Tech Research Reactor The reactor components included a heat removal system, a D 2 O storage system, a radiolytic gas recombiner system, and a ventilating system. The heat removal system was composed of a primary heavy-water system and a secondary light-water system. All components in contact with the D 2 O were fabricated of stainless steel or aluminum. Because the GTRR was intended for research application, it was equipped with a variety of experimental facilities that allowed for a wide range of investigations. Experiments that required high-intensity neutron or gamma-ray beams could be accommodated, as well as those that required a uniform thermal neutron flux throughout a large volume. The reactor was designed to produce a thermal flux of greater than neutrons/cm 2 /sec at a power of 5 MW. Irradiation of short duration and irradiation that required rapid sample recovery could also be accomplished. In addition, the reactor face contained a thermal column and a biomedical irradiation facility, although no biomedical experiments were ever performed. The containment building has three levels. The basement contained process and ventilating equipment and space for experimental systems. The main floor provided space for the reactor bioshield and the installation of experiments. The control room was located at the level of the top
3 of the biological shield. During operation, access was restricted via an air lock connected to the adjoining laboratory building, along with an air lock leading to the outside. DECISION TO DECOMMISSION The reactor was licensed in 1964 with an engineered lifetime of 30 years. It operated through November 17, 1995 and generated 40,204 MW-hours (hr) of thermal energy over its lifetime. After 30 years of operations, Georgia Tech applied for a license renewal. As a part of the license renewal, the conversion of the reactor from high-enriched fuel to low-enriched fuel was planned. Because Georgia Tech was to serve as the Olympic Village and the venue for several sporting events during the summer of 1996, the Georgia Tech Administration had the fuel removed and shipped to the Savannah River Site in February In May 1997, the NRC renewed the GTRR operating license. However, shortly thereafter, the Georgia Tech Administration decided not to receive the low-enriched fuel, but to decommission the reactor instead. The administration cited several reasons for this decision: (1) approximately $2 million in renovations would be required to bring the reactor up to present-day standards; (2) under utilization of the reactor for the previous 10 years; (3) major public and political attention during the Olympics, and (4) the cost of continued operation. The decision to decommission was announced on July 1, PATH FORWARD With decommissioning in mind, Georgia Tech's intent was to remove all NRC-licensable materials from the site, terminate the license, and release the site for unrestricted use. The site release guideline for the facility was grandfathered under NRC Regulatory Guide 1.86 with guideline values of 5,000 disintegrations per minute (dpm)/100 cm 2 for total contamination and 1,000 dpm/100 cm 2 for removable contamination, instead of the new Code of Federal Regulations 10 CFR 20 Subpart E "Decommissioning Criteria." Georgia Tech selected the DECON alternative, which is the removal of all fuel assemblies, source material, radioactive fission and corrosion products, and all other radioactive and contaminated materials that have activity levels above the unrestricted release values. The Decommissioning Plan (DP) was approved by NRC on July 22, 1999, as an amendment to the existing license (Amendment 14 to Facility Operating License No. R- 97). One advantage to issuing the DP as an amendment to the license as opposed to a stand-alone document was that minor changes to the DP could then be approved by the licensee (in this case, Georgia Tech) through an established 10 CFR 50.59, "Changes, tests or experiments" safety screening and evaluation process, as opposed to sending all changes back to the NRC for its action. The project has successfully used this 10 CFR process to change the: sequence of the decommissioning tasks means of radioactive material control method of plug storage vault removal method of graphite retaining sleeve removal method of spent fuel storage hole removal reactor bioshield demolition approach.
4 In addition, the process has been used to set the free release standards of tritium and Fe-55 to 200,000 dpm/100 cm 2 fixed and 10,000 dpm/100 cm 2 removable, based on previous NRC allowances for these isotopes at other decommissioning sites. In Georgia, the Georgia State Financing and Investment Commission (GSFIC) acts as the owner on construction jobs working for the using agency (Georgia Tech in this case). While waiting for approval of the DP, the GSFIC hired, through a technical competitive procurement, CH2M HILL, Inc. to serve as the Executive Engineer on the project, acting for the State and for Georgia Tech. With CH2M HILL support, the State and Georgia Tech then prequalified five potential Decontamination and Decommissioning (D&D) contractors. The IT Corporation subsequently won the project as Decommissioning Contractor (DC) on a low-price competitive bid basis. IT was awarded the contract on June 30, One of the first tasks was a joint chartering session held among Georgia Tech, the State of Georgia, the Executive Engineer, and the DC. The purpose of the chartering session was to develop vision and mission statements for the project. The vision of this project was: "A facility (reactor containment building and grounds) left in a condition that meets required safety codes and is suitable for conventional demolition and construction (i.e., unrestricted free release plus ALARA [as low as reasonably achievable])." The mission of the project team is to work together in an enjoyable teaming relationship to bring to fruition the vision while concurrently accomplishing the following: Remain a good neighbor to the surrounding communities Win the confidence of the local people and the State of Georgia Become a model for learning, as befits one of the premier locations in the country for health physics studies Avoid negative impact to ongoing operations in the remainder of the facility During the chartering session, critical success factors for the project were developed and barriers to achieving the goals were identified. Actions were taken to prevent or mitigate those barriers. Following the chartering session, the DC spent the first 60 days developing eight major project specific plans and procedures for executing the decommissioning contract. These included policies and procedures for Health and Safety, Radiation Protection, Decommissioning Work Plan, Quality Assurance, Waste Management and the Initial Survey Plan. These plans contained more than 70 individual procedures. These documents were submitted to the Executive Engineer for subsequent approval by the Georgia Tech Technical Safety Review Committee (TSRC) prior to implementation. The TSRC is a standing committee at Georgia Tech designed to oversee the technical safety of the operations during decommissioning. The TSRC is composed of six senior people: 1. the Associate Dean of Engineering 2. the Chair of the School of Mechanical Engineering 3. a past President of the Health Physics Society
5 4. the Georgia Tech Radiation Safety Officer 5. the Director of the Neely Nuclear Research Center 6. the Manager of Capital Projects for Georgia Tech. The DC mobilized on the site in December An initial confirmatory survey was performed as well as the packaging and transport of some miscellaneous radioactive and mixed waste from within the containment building for disposal. The primary and secondary cooling systems were removed from the containment building along with the reactor beam tube plugs. In the months of March and April, the reactor start up source, the internal safety mechanisms, the reactor cover shields and the reactor vessel were removed and shipped off site. Except for the high-activity waste, the waste was packaged and sent to GTS Duratek s facilities in Oak Ridge, Tennessee, for subsequent segregation and shipment to either Envirocare of Utah or to the Barnwell Waste Disposal Facility. The highactivity waste, including the reactor vessel, was sent directly from Georgia Tech to the Barnwell disposal site. Once the reactor vessel was removed, the graphite was then accessible for removal (Figure 2). Fig. 2. Removal of Graphite Reflector During the months of June through October, a hoe ram was used to dismantle the bioshield (Figure 3). The outer portion of the shield was uncontaminated and the inner 20 inches were treated as contaminated, due to neutron activation.
6 Fig. 3. Demolition of the Bioshield In October, a specialty-lifting subcontractor removed the lead tank that surrounded the reactor vessel as a single unit. The activated portions of the concrete pedestal underneath the lead tank were removed thereafter. In January 2001, further decontamination activities (such as the decontamination of the spent fuel storage hole) will be undertaken as necessary, followed by the final release surveys. The Final Survey Report is anticipated to be submitted to the NRC by the end of March A few surprises have been encountered during the project, many due to incomplete characterization prior to awarding the decommissioning contract. Since Georgia Tech was operating under a Possession Only License, there was concern that destructive coring of the reactor was not permitted within the licensed operations. Therefore, past experience was used to model the neutron activation of the concrete within the biological shield. Activation was reported as extending 3 inches into the concrete or 67 inches from the center of the reactor core. Once the DC had mobilized and initiated the confirmatory survey, core samples were drilled in the biological shield. These samples showed that the concrete was actually activated extending approximately 20 inches into the concrete (~85 inches from the core) and contained significant amounts of iron resulting in more than 150,000 pounds of additional radioactive concrete as waste for disposal. Monitoring the facility for potential tritium contamination presented difficulties. Because the reactor was a heavy-water-moderated and -cooled reactor, significant levels of tritium contamination were expected where heavy-water spills had occurred. Approximately 2,400 gallons, which equates to greater than 97 percent of the heavy water, had been previously recovered and shipped to the Savannah River Site. However, when coolant systems were opened, residual amounts of tritium-contaminated water were present in pipe elbows and low spots. In an open system, the tritium became airborne and gave the semblance of a much greater contamination problem in the facility. Elevated readings of 8 percent of a derived air concentration (DAC)-hr were observed. Increasing airflow through the ventilation system resolved this concern.
7 During the removal of the thermal column and graphite reflectors, some of the graphite reflector blocks read more than 300 millirem (mr)/hr on contact, with many having contact readings of between 20 and 80 mr/hr. Closer investigation revealed not only that C-14, as expected, was present, but Cobalt (Co-60) also was present at up to 300,000 pci/g concentrations. The higher dose rates were associated with steel heli-coils that had been attached to the end of the graphite stringers to use to remove the stringers during the reactor operations so samples could be introduced for irradiation activities. Discussions with other research reactor D&D personnel who had worked on the Argonne CP series of reactors revealed another common problem that resulted from metal shavings from the saw blades that were used to cut the graphite to fit around the reactor vessel. These metal shavings impregnated in the graphite while sizing the blocks and became activated during the reactor operations producing the Co-60 source. As stated, other graphite blocks were reading from 20 to 80 mr/hr. These blocks contained quantities of europium Eu-152, Eu-154 and Eu-155. In reviewing the graphite specification during reactor construction, it was noted that the specified reactor graphite grade AGOT was thermally purified to drive off impurities; however, removal of rare earth elements, such as europium, requires a halogenated chemical purification at elevated temperatures. Envirocare s waste acceptance criteria for Co-60 is 30,000 pci/g and for Europium is 20,000 pci/g. Therefore, the vast majority of the graphite (45,000+ pounds) could not be shipped to Envirocare of Utah, and instead required disposal at Barnwell at three times the cost. ALARA WORKER EXPOSURE DURING D&D Through the end of November, the cumulative dose to workers was a 10.2 person-rem. At the start of each work activity, an ALARA plan is developed and an ALARA dose allocated. An increase in exposure was observed beginning in mid-march, which correlated with the removal of the reactor vessel and activation products in the surrounding material. Most of the increase in dose corresponds to the removal of the activated graphite. Specific ALARA Georgia Tech Approach The Georgia Tech approach includes a unique aspect for decontaminating hot spots below the Regulatory Guide 1.86 limits toward achieving the institute s ALARA goal of 20 percent of the regulatory guide values. As the contractor is decontaminating the facility, if hot spots are identified, the DC may propose a change order to the Executive Engineer to further reduce the contamination even though the release limits as defined in Regulatory Guide 1.86 are met. The Executive Engineer and Georgia Tech have developed a procedure to assess the value of reduced dose compared to the cost of the decontamination effort to achieve the reduced dose. The requests may or may not be approved based on the overall dose reduction versus cost effectiveness assessment. As a result of this approach, Georgia Tech hopes to develop a cost versus dose reduction assessment, which may prove helpful to other parties interested in achieving specific ALARA goals in their decommissioning activities. To date some candidate areas have been identified for this unique ALARA approach, and these are being evaluated for possible further decontamination.
8 EDUCATIONAL OBJECTIVE Four video cameras were installed inside the containment building to record the decommissioning process. Tapes are being summarized to produce a documentary that can be used for other decommissioning projects, as well as for students at Georgia Tech. Output from the cameras are displayed in a war room where students, regulators, and other interested parties can come and observe the activities in real time. The war room also contains copies of the approved policies and procedures, active Radiological Work Permits (RWPs), work packages, and data from the decommissioning project, allowing students to observe project delivery techniques as a learning experience. The educational objectives are being achieved and it is clear that the project will continue to provide valuable lessons for the students. COST The DP contained a cost estimate the State of Georgia Legislature fully funded at $7.4 million. This included $500,000 for specific ALARA activities. With change orders, the estimated project cost at completion is currently $6.9 million, which is within the State s allocated budget and is expected to remain so through license termination. SUMMARY Although it took much longer to remove the bioshield than expected, the project is progressing smoothly and is meeting all the mission objectives, at this writing. As can be seen in Figure 4, the reactor vessel, concrete bioshield and lead tank have been removed. The facility should be completely decontaminated and the final survey report sent to the NRC in March Following the NRC final confirmatory survey, free release of the site and termination of the license is expected in August An assessment of cost versus dose reduction is planned for specific ALARA activities. A documentary of the D&D activities for research reactors will be published after the license is terminated.
9 Fig. 4. Bioshield and Lead Tank Removed
INTRODUCTION. Three Mile Island Unit 2
INTRODUCTION here was an accident at Three Mile Island Unit 2 on March 28,1979. It caused extensive damage to the plant's nuclear fuel core. Most of the plant's major systems were relatively undamaged.
More informationNRC s Program for Remediating Polluted Sites J.T. Greeves, D.A. Orlando, J.T. Buckley, G.N. Gnugnoli, R.L. Johnson US Nuclear Regulatory Commission
NRC s Program for Remediating Polluted Sites J.T. Greeves, D.A. Orlando, J.T. Buckley, G.N. Gnugnoli, R.L. Johnson US Nuclear Regulatory Commission Background The U.S. Nuclear Regulatory Commission (NRC)
More informationAPPENDIX CC NUCLEAR WASTE STORAGE
APPENDIX CC NUCLEAR WASTE STORAGE APPENDIX CC NUCLEAR WASTE STORAGE MICHIEL P.H. BRONGERS 1 SUMMARY Nuclear wastes are generated from spent nuclear fuel, dismantled weapons, and products such as radio
More informationWM2011 Conference, February 27 - March 3, 2011, Phoenix, AZ
Risk Identification, Analysis, and Mitigation Plan for Environmental Remediation Activities at Brookhaven National Laboratory - 11109 Steve Feinberg*, Thomas E. Jernigan**, Thomas Johnson, Jr***, Melanie
More informationDEVELOPMENT OF PROCESS TEMPLATES AS A PROJECT MANAGEMENT TOOL FOR THE PLUTONIUM FINISHING PLANT
DEVELOPMENT OF PROCESS TEMPLATES AS A PROJECT MANAGEMENT TOOL FOR THE PLUTONIUM FINISHING PLANT ABSTRACT William G. Jasen, Project Enhancement Corporation Thomas W. Halverson, Fluor Hanford, Inc. Steven
More informationHazard Classification of the Remote Handled Low Level Waste Disposal Facility
1 Hazard Classification of the Remote Handled Low Level Waste Disposal Facility Abstract Boyd D. Christensen Battelle Energy Alliance, Idaho National Laboratory P.O. Box 1625 Idaho Falls, Idaho 83415 208
More informationTechnical Challenges for Conversion of U.S. High-Performance Research Reactors (USHPRR)
Technical Challenges for Conversion of U.S. High-Performance Research Reactors (USHPRR) John G. Stevens, Ph.D. Argonne National Laboratory Technical Lead of Reactor Conversion GTRI USHPRR Conversion Program
More informationChemical Decontamination and Fluid Handling Services
Chemical Decontamination and Fluid Handling Services Westinghouse is a global industry expert in decontamination and fluid handling processes, with proven abilities in decontamination and remediation work.
More informationSECTION TWO PACKAGING, TRANSPORTATION AND STORAGE OF RADIOACTIVE MATERIALS
SECTION TWO PACKAGING, TRANSPORTATION AND STORAGE OF RADIOACTIVE MATERIALS LEARNING OBJECTIVES By the end of this section, participants will be able to: Identify three types of packaging for radioactive
More informationNUCLEARINSTALLATIONSAFETYTRAININGSUPPORTGROUP DISCLAIMER
NUCLEARINSTALLATIONSAFETYTRAININGSUPPORTGROUP DISCLAIMER Theinformationcontainedinthisdocumentcannotbechangedormodifiedinanywayand shouldserveonlythepurposeofpromotingexchangeofexperience,knowledgedissemination
More informationDECOMMISSIONING THE BROOKHAVEN NATIONAL LABORATORY BUILDING 830 GAMMA IRRADIATION FACILITY
BNL 68088 DECOMMISSIONING THE BROOKHAVEN NATIONAL LABORATORY BUILDING 830 GAMMA IRRADIATION FACILITY Biays Bowerman and Patrick T. Sullivan Brookhaven National Laboratory PO Box 5000, Bldg. 830 Upton,
More informationImporting and Exporting Radioactive Materials and Waste for Treatment, Processing and Recycling
Importing and Exporting Radioactive Materials and Waste for Treatment, Processing and Recycling J.T. Greeves, J. Lieberman Talisman International, LLC 1000 Potomac Street, NW, Suite 300 Washington, DC
More informationSpent Fuel Project Office Interim Staff Guidance - 17 Interim Storage of Greater Than Class C Waste
Spent Fuel Project Office Interim Staff Guidance - 17 Interim Storage of Greater Than Class C Waste Issue: Guidance is necessary on the interim storage of greater than Class C (GTCC) waste due to the revision
More informationV K Raina. Reactor Group, BARC
Critical facility for AHWR and PHWRs V K Raina Reactor Group, BARC India has large reserves of Thorium Critical facility Utilisation of Thorium for power production is a thrust area of the Indian Nuclear
More informationTHE DECOMMISSIONING OF COMMERCIAL MAGNOX GAS XA9848063 COOLED REACTOR POWER STATIONS IN THE UNITED KINGDOM
THE DECOMMISSIONING OF COMMERCIAL MAGNOX GAS XA9848063 COOLED REACTOR POWER STATIONS IN THE UNITED KINGDOM G. HOLT Magnox Electric pic, Berkeley Centre, Berkeley, Gloucestershire, United Kingdom Abstract
More informationBoiling Water Reactor Systems
Boiling Water (BWR) s This chapter will discuss the purposes of some of the major systems and components associated with a boiling water reactor (BWR) in the generation of electrical power. USNRC Technical
More informationSeptember 15, 2003. Docket No. 99990001 General License (10 CFR 31.5)
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 475 ALLENDALE ROAD KING OF PRUSSIA, PENNSYLVANIA 19406-1415 September 15, 2003 Docket No. 99990001 General License (10 CFR 31.5) Annette D. Knox Superintendent
More informationInternational Action Plan On The Decommissioning of Nuclear Facilities
International Action Plan On The Decommissioning of Nuclear Facilities A. Introduction Decommissioning is defined by the International Atomic Energy Agency (the Agency) as the administrative and technical
More informationDecommissioning of the nuclear facilities
Risø-R-1250(EN) Decommissioning of the nuclear facilities at Risø National Laboratory Descriptions and cost assessment Edited by Kurt Lauridsen Risø National Laboratory February 2001 Abstract The report
More informationMEMORANDUM OF UNDERSTANDING BETWEEN THE ENVIRONMENTAL PROTECTION AGENCY AND THE NUCLEAR REGULATORY COMMISSION
MEMORANDUM OF UNDERSTANDING BETWEEN THE ENVIRONMENTAL PROTECTION AGENCY AND THE NUCLEAR REGULATORY COMMISSION CONSULTATION AND FINALITY ON DECOMMISSIONING AND DECONTAMINATION OF CONTAMINATED SITES I. Introduction
More informationDose Standards and Methods for Protection. Radiation and Contamination
Dose Standards and Methods for Protection Against Radiation and Contamination This section will discuss the NRC dose standards and the methods used to protect individuals from the harmful effects of radiation
More informationPROPOSALS FOR UNIVERSITY REACTORS OF A NEW GENERATION
PROPOSALS FOR UNIVERSITY REACTORS OF A NEW GENERATION Introduction R.P. Kuatbekov, O.A. Kravtsova, K.A. Nikel, N.V. Romanova, S.A. Sokolov, I.T. Tretiyakov, V.I. Trushkin (NIKIET, Moscow, Russia) Worldwide,
More informationDecommissioning situation of Nuclear Power Plant in Japan
Decommissioning situation of Nuclear Power Plant in Japan April, 2015 The Japan Atomic Power Co. The Kansai Electric Power Co., Inc. General Description 1 Operational years of commercial NPP in Japan 40
More informationRadioactive waste managment in Estonia past, present and future
Radioactive waste managment in Estonia past, present and future Ivo Tatrik ivo.tatrik@alara.ee Content 1. Status of ALARA 2. Decomission of Paldiski Former Navy Submarine Training Centre 3. Decomission
More informationThree Mile Island Unit 2 Overview and Management Issues
Three Mile Island Unit 2 Overview and Management Issues OECD-Nuclear Energy Agency 12 th Meeting of the WPDD November 2011 Paris France Andrew P. Szilagyi U.S. Department of Energy Office of 1 Subjects
More informationApplication Note. ipix A Gamma imager to support various applications
Application Note ipix A Gamma imager to support various applications Introduction ipix is a unique gamma imager that quickly locates low level radioactive sources from a distance and estimates the dose
More informationSummary of the D&D Engineering Operations
Summary of the D&D Engineering Operations Keith Rule Princeton Plasma Physics Laboratory Project Attributes! Schedule: October 1999 through September 2002! Original Estimated Project Cost: $40.3M! Project
More informationOperating Performance: Accident Management: Severe Accident Management Programs for Nuclear Reactors REGDOC-2.3.2
Operating Performance: Accident Management: Severe Accident Management Programs for Nuclear Reactors REGDOC-2.3.2 September 2013 Accident Management: Severe Accident Regulatory Document REGDOC-2.3.2 Canadian
More informationOffice for Nuclear Regulation
ONR GUIDE CONTAINMENT: CHEMICAL PLANTS Document Type: Nuclear Safety Technical Assessment Guide Unique Document ID and Revision No: NS-TAST-GD-021 Revision 2 Date Issued: March 2013 Review Date: March
More informationINSPECTION OF STATE OF SPENT FUEL ELEMENTS STORED IN RA REACTOR SPENT FUEL STORAGE POOL
CH01$0025 INSPECTION OF STATE OF SPENT FUEL ELEMENTS STORED IN RA REACTOR SPENT FUEL STORAGE POOL V. G. ADEN, S. YU. BULKIN, A. V. SOKOLOV Research and Development Institute of Power Engineering, P. Box
More informationAdditional Facility Details for Release of Waste Area 3 (Seattle, Washington)
1. Description of facility to be released. The facility to be released is a separate structure, identified and referred to as Waste Area 3 and also as Waste Station #3, in documents and survey forms, located
More informationPart 1 General and Administrative Information. Part 3 Applicant s Environmental Report Combined License Stage
Part 16 South Carolina Electric and Gas V. C. Summer Nuclear Station, Units 2 & 3 COL Application COLA Table of Contents Navigation Page Part 1 General and Administrative Information Part 2 Final Safety
More informationMATERIALS LICENSE. Delaware City, Delaware 19706 5. Docket No. 030-38418 Reference No.
NRC FORM 374 U.S. NUCLEAR REGULATORY COMMISSION PAGE 1 OF 5 PAGES Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of
More informationCurrent as of 11/10/08 1 of 1
BEST PRACTICES STANDARDS FOR SCHOOLS UNDER CONSTRUCTION OR BEING PLANNED FOR CONSTRUCTION I. Site Layout A. School buildings shall be provided with a securable perimeter. A securable perimeter means that
More informationMATERIALS LICENSE. 1. Honeywell International, Inc. 3. License Number: SUB-526, Amendment 6-1
NRC FORM 374 U.S. NUCLEAR REGULATORY COMMISSION Page 1 of 5 Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federal
More informationPIONEER ROBOT TESTING PROGRAM AND STATUS
PIONEER ROBOT TESTING PROGRAM AND STATUS Joseph N. Herndon and Dennis C. Haley Robotics and Process Systems Division Oak Ridge National Laboratory P.O. Box 2008 Oak Ridge, Tennessee 37831-6305 (865) 574-7065
More informationNORTH CAROLINA EASTERN MUNICIPAL POWER AGENCY SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1. Renewed License No. NPF-63
CAROLINA POWER & LIGHT COMPANY NORTH CAROLINA EASTERN MUNICIPAL POWER AGENCY DOCKET NO. 50-400 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 RENEWED FACILITY OPERATING LICENSE 1. The Nuclear Regulatory Commission
More informationDEMONSTRATION ACCELERATOR DRIVEN COMPLEX FOR EFFECTIVE INCINERATION OF 99 Tc AND 129 I
DEMONSTRATION ACCELERATOR DRIVEN COMPLEX FOR EFFECTIVE INCINERATION OF 99 Tc AND 129 I A.S. Gerasimov, G.V. Kiselev, L.A. Myrtsymova State Scientific Centre of the Russian Federation Institute of Theoretical
More information11. Radioactive Waste Management AP1000 Design Control Document
11.4 Solid Waste Management The solid waste management system (WSS) is designed to collect and accumulate spent ion exchange resins and deep bed filtration media, spent filter cartridges, dry active wastes,
More informationSystem/activ. ity of interest Comment Priority. Referenc. Id Category Text. Waste management Establish waste classification 5 Romuald Duperrier Waste
1 Waste management Establish waste classification 5 Romuald Duperrier Waste IAEA GSG- 1 or SSI FS 1996-2? page 34 2 Evaluate environmental impact (including workers) of the decommissioning 5 Romuald Duperrier
More informationTHIS PAGE MUST BE KEPT WITH DOE 1540.3A, BASE TECHNOLOGY FOR RADIOACTIVE MATERIAl TRANSPORTATION PACKAGING SYSTEMS.
o DOE 1540.3A THIS PAGE MUST BE KEPT WITH DOE 1540.3A, BASE TECHNOLOGY FOR RADIOACTIVE MATERIAl TRANSPORTATION PACKAGING SYSTEMS. DOE 1540.3A,BASE TECHNOLOGY FOR RADIOACTIVE MATERIAL TRANSPORTATION PACKAGING
More informationBECHTEL JACOBS COMPANY ORR WASTE CERTIFICATION PROGRAM DOCUMENT CONTROL SYSTEM
BECHTEL JACOBS COMPANY ORR WASTE CERTIFICATION PROGRAM DOCUMENT CONTROL SYSTEM If you print the following document, this page must be attached to the front of the document and you must fill in the information
More informationUNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION. OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Carl J. Paperiello, Director
DD-98-11 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Carl J. Paperiello, Director In the Matter of ) ) ADVANCED MEDICAL SYSTEMS, INC. ) Docket
More information10 Nuclear Power Reactors Figure 10.1
10 Nuclear Power Reactors Figure 10.1 89 10.1 What is a Nuclear Power Station? The purpose of a power station is to generate electricity safely reliably and economically. Figure 10.1 is the schematic of
More informationA MTR FUEL ELEMENT FLOW DISTRIBUTION MEASUREMENT PRELIMINARY RESULTS
A MTR FUEL ELEMENT FLOW DISTRIBUTION MEASUREMENT PRELIMINARY RESULTS W. M. Torres, P. E. Umbehaun, D. A. Andrade and J. A. B. Souza Centro de Engenharia Nuclear Instituto de Pesquisas Energéticas e Nucleares
More informationV. ENVIRONMENTAL IMPACT ANALYSIS E. Hazardous Materials
E. HAZARDOUS MATERIALS An Environmental Site Assessment Phase I Update was performed on the subject properties by California Environmental Inc. in March 2000 1. This report is included in Appendix E of
More informationRetrieval of Damaged Components form Experimental Fast Reactor Joyo Reactor Vessel
Retrieval of Damaged Components form Experimental Fast Reactor Joyo Reactor Vessel June. 8 th, 2010 Yukimoto MAEDA Japan Atomic Energy Agency (JAEA) Experimental fast reactor Joyo Joyo (Oarai R&D Center)
More informationApril 30, 2013 E M. Environmental Management. www.em.doe.gov. safety performance cleanup closure
April 30, 2013 1 Facility Stabilization and Deactivation C.1.3 - (Period 3) After facilities are turned over by USEC and accepted by DOE: Perform minimal stabilization and deactivation activities for facilities
More informationTreatment Centers for Radioactive Waste
Treatment Centers for Radioactive Waste TREATMENT CENTERS FOR RADIOACTIVE WASTE Introduction Nuclear facilities such as nuclear power plants, reprocessing plants, nuclear fuel cycle production units, laboratories
More informationAugust 21, 2012. Dear Mr. Marcinowski:
August 21, 2012 Mr. Frank Marcinowski Deputy Assistant Secretary for Technical and Regulatory Support Office of Environmental Management U.S. Department of Energy 1000 Independence Avenue, S.W. Washington,
More informationHow to Become a Radiation Safety Officer
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REGULATORY RESEARCH April 1982 Division 8 DRAFT REGULATORY GUIDE AN1D VALUE/IMPACT STATEMENT Task OP 722-4 * Contact: J. M. Bell (301) 443-5970 QUALIFICATIONS
More informationThe following assumptions are to be considered when reviewing this model procedure:
Transportation Emergency Preparedness Program (TEPP) Model Procedure for Properly Handling and Packaging Potentially Radiologically Contaminated Patients This Transportation Emergency Preparedness Program
More informationMATERIALS LICENSE. In accordance with the letter dated January 15, 2009,
NRC FORM 374 U.S. NUCLEAR REGULATORY COMMISSION PAGE 1 OF 5 PAGES Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of
More informationATTACHMENT 1-9 CHWSF CONTAINER MANAGEMENT
1.0 INTRODUCTION ATTACHMENT 1-9 CHWSF CONTAINER MANAGEMENT 1.1 This Attachment provides information about the management of containers in U.S. Army Dugway Proving Ground s (DPG s) Container Storage Building
More informationRadiation Protection s Benefits in the Production of Iodine-131
Radiation Protection s Benefits in the Production of Iodine-131 Daniel M. Cestau *, Ariel N. Novello, Cecilia Bravo, Pablo Cristini, Marcelo Bronca, Eduardo Carranza, Ricardo Bavaro, Julián Cestau and
More informationLong Term Operation R&D to Investigate the Technical Basis for Life Extension and License Renewal Decisions
Long Term Operation R&D to Investigate the Technical Basis for Life Extension and License Renewal Decisions John Gaertner Technical Executive Electric Power Research Institute Charlotte, North Carolina,
More informationGUIDE FOR THE PREPARATION OF RADIOACTIVE MATERIAL APPLICATIONS FOR WELL LOGGING OPERATIONS IN KENTUCKY
GUIDE FOR THE PREPARATION OF RADIOACTIVE MATERIAL APPLICATIONS FOR WELL LOGGING OPERATIONS IN KENTUCKY Radiation Control Cabinet for Human Resources 275 East Main Street Frankfort, Kentucky 40621 JANUARY
More informationLessons learned from the radiological accident in Mayapuri, New Delhi, India
Lessons learned from the radiological accident in Mayapuri, New Delhi, India Rajoo Kumar Atomic Energy Regulatory Board Government of India Mumbai, India www.aerb.gov.in 1 Contents About Mayapuri, New
More informationDecommissioning of German Nuclear Research Facilities under the Governance of the Federal Ministry of Education and Research - 8059
Decommissioning of German Nuclear Research Facilities under the Governance of the Federal Ministry of Education and Research - 8059 M. Weigl Forschungszentrum Karlsruhe GmbH Projektträgerforschungszentrum
More informationREGULATORY GUIDE 5.29 (Draft was issued as DG 5028, dated May 2012) SPECIAL NUCLEAR MATERIAL CONTROL AND ACCOUNTING SYSTEMS FOR NUCLEAR POWER PLANTS
U.S. NUCLEAR REGULATORY COMMISSION June 2013 Revision 2 REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 5.29 (Draft was issued as DG 5028, dated May 2012) SPECIAL NUCLEAR MATERIAL
More informationHow To Decommission A Nuclear Plant
International Atomic Energy Agency Decommissioning of Nuclear Facilities Management of Decommissioning Projects Lawrence E. Boing Manila, Philippines, October 2006 1 Lesson Objectives Understand the management
More informationNRC REGULATORY ISSUE SUMMARY 2007-28 SECURITY REQUIREMENTS FOR PORTABLE GAUGES
ADDRESSEES UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF FEDERAL AND STATE MATERIALS AND ENVIRONMENTAL MANAGEMENT PROGRAMS WASHINGTON, D.C. 20555 December 7, 2007 NRC REGULATORY ISSUE SUMMARY 2007-28
More informationWM2013 Conference, February 24 28, 2013, Phoenix, Arizona, USA. Classified Component Disposal at the Nevada National Security Site (NNSS) 13454
WM2013 Conference, February 24 28, 2013, Phoenix, Arizona, USA DOE/NV/25946--1648 Classified Component Disposal at the Nevada National Security Site (NNSS) 13454 Jeanne Poling*, Pat Arnold,* Max Saad,**
More informationINFORMATION NOTICE: 09-01-01 USE OF XRF DEVICES CONTAINING RADIOACTIVE MATERIAL North Dakota Department of Health Radiation Control Program (2/06)
INFORMATION NOTICE: 09-01-01 USE OF XRF DEVICES CONTAINING RADIOACTIVE MATERIAL North Dakota Department of Health Radiation Control Program (2/06) Radioactive material is regulated by the North Dakota
More information318 DECREE. of the State Office for Nuclear Safety of 13 June 2202,
318 DECREE of the State Office for Nuclear Safety of 13 June 2202, On details for emergency preparedness assurance at nuclear installations and workplaces with ionizing radiation sources and on requirements
More informationNorth Carolina State University Emergency Facilities Closure Checklist- Part I
North Carolina State University Emergency Facilities Closure Checklist- Part I Unplanned or spontaneous events often disrupt daily operations on campus. In the event that an incident may interrupt your
More informationPOLICY ISSUE NOTATION VOTE
POLICY ISSUE NOTATION VOTE November 25, 2013 SECY-13-0125 FOR: FROM: SUBJECT: The Commissioners Mark A. Satorius Executive Director for Operations REPORT TO CONGRESS ON THE HEALTH, SAFETY, AND ENVIRONMENTAL
More informationSection 4 RADIATION SAFETY RULES AND REGULATIONS
Page RR- 1 Section 4 RADIATION SAFETY RULES AND REGULATIONS UW Environmental Health and Safety Page RR-3 A. Historical Perspective Standards and regulations for radiation protection have been evolving
More informationRC-17. Alejandro V. Nader National Regulatory Authority Montevideo - Uruguay
RC-17 Radiation Protection in Waste Management and Disposal Implementing the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management Alejandro V. Nader
More informationItemized RAI Responses
Itemized RAI Responses Question 1-1: Justify the use of a tapped bar or equivalent with a helicoil insert. This justification should specifically address any reduction in packaging performance from the
More informationFORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM
-_-~---- _.l~- _^--._.---..^- FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM ELIMINATION REPORT FOk FORMER QUALITY HARDWARE AND MACHINE COMPANY; 5823/5849 NORTH RAVENSWOOD AVENUE; CHICAGO, ILLINOIS JULY
More informationTest Section for Experimental Simulation of Loss of Coolant Accident in an Instrumented Fuel Assembly Irradiated in the IEA-R1 Reactor
2013 International Nuclear Atlantic Conference - INAC 2013 Recife, PE, Brazil, November 24-29, 2013 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-05-2 Test Section for Experimental
More informationUX-30 PERFORMANCE TESTING SUMMARY REPORT Revision 0
UX-30 PERFORMANCE TESTING SUMMARY REPORT Revision 0 Prepared By: Patrick L. Paquin, EnergySolutions Date Reviewed By: Mirza I. Baig, EnergySolutions Date Approved By: Thomas F. Dougherty, Columbiana Hi
More informationOverview of the Multi-nuclide Removal Equipment (ALPS) at Fukushima Daiichi Nuclear Power Station. March 29, 2013 Tokyo Electric Power Company
Overview of the Multi-nuclide Removal Equipment (ALPS) at Fukushima Daiichi Nuclear Power Station March 29, 2013 Tokyo Electric Power Company Purpose of Installing the Multi-nuclide Removal Equipment Installation
More informationO R I S IF. April 12, 2002
O R I S IF OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION April 12, 2002 Mr. Thomas G. McLaughlin U.S. Nuclear Regulatory Commission Division of Waste Management 11555 Rockville Pike Mail Stop: T-7F27 Rockville,
More informationMATERIALS LICENSE. 1. American Centrifuge Operating, LLC 3. License Number: SNM-2011, Amendment 4
NRC FORM 374 U.S. NUCLEAR REGULATORY COMMISSION Page 1 of 8 Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federal
More informationAudit Report. Implementation of the Recovery Act at the Savannah River Site
U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Audit Report Implementation of the Recovery Act at the Savannah River Site OAS-RA-L-11-12 September 2011 Department
More informationGEET Fuel Processor Plans
GEET Fuel Processor Plans This is a greatly simplified Proof of Concept version of the GEET Fuel Processor that just about anyone can build from parts from a local Hardware store in a weekend for very
More informationNUCLEAR POWER PLANT SYSTEMS and OPERATION
Revision 4 July 2005 NUCLEAR POWER PLANT SYSTEMS and OPERATION Reference Text Professor and Dean School of Energy Systems and Nuclear Science University of Ontario Institute of Technology Oshawa, Ontario
More informationEnvironmental Synopsis D-1 Portsmouth DUF 6 Conversion Final EIS APPENDIX D: ENVIRONMENTAL SYNOPSIS FOR THE DEPLETED UF 6 CONVERSION PROJECT
Environmental Synopsis D-1 Portsmouth DUF 6 Conversion Final EIS APPENDIX D: ENVIRONMENTAL SYNOPSIS FOR THE DEPLETED UF 6 CONVERSION PROJECT Environmental Synopsis D-2 Portsmouth DUF 6 Conversion Final
More informationGovernment Degree on the Safety of Nuclear Power Plants 717/2013
Translation from Finnish. Legally binding only in Finnish and Swedish. Ministry of Employment and the Economy, Finland Government Degree on the Safety of Nuclear Power Plants 717/2013 Chapter 1 Scope and
More informationContingency Plan. Facility Name
Contingency Plan Facility Name This plan is reviewed annually and amended whenever changes occur that will significantly affect the ability of this facility to respond to an emergency situation. This includes
More informationIntroductions: Dr. Stephen P. Schultz
Introductions: Dr. Stephen P. Schultz Vienna, Austria 1 3 September 2015 Work Experience Current Member Advisory Committee on Reactor Safeguards, U.S. Nuclear Regulatory Commission, 12/2011 Chair, Fukushima
More informationHow To Use An Akua Magnetic Lime Scale Preventing Device
AKUA MAGNETIC LIMESCALE PREVENTING DEVICES INTRODUCTION AND OPERATING MANUAL This manual contains information about Akua Magnetic Lime Scale Preventing devices, their assembly and usage rules. In order
More informationATTACHMENT 12 CONTAINERS
ATTACHMENT 12 CONTAINERS Attachment 12 - Page 1 Table of Contents Table of Contents List of Tables List of Acronyms 12.1 Applicability 12.2 Description of 12.3 Reserved 12.4 Reserved 12.5 Description of
More informationGAO. NUCLEAR REGULATION Regulatory and Cultural Changes Challenge NRC. Testimony
GAO For Release on Delivery Expected at 9a.m.EDT Thursday, March 9, 2000 United States General Accounting Office Testimony Before the Subcommittee on Clean Air, Wetlands, Private Property, and Nuclear
More informationSUPPLEMENTAL TECHNICAL SPECIFICATIONS BI-DIRECTIONAL STATIC LOAD TESTING OF DRILLED SHAFTS
July 14, 2015 1.0 GENERAL BI-DIRECTIONAL STATIC LOAD TESTING OF DRILLED SHAFTS This work shall consist of furnishing all materials, equipment, labor, and incidentals necessary for conducting bi-directional
More informationSAVANNAH RIVER SITE S MACROENCAPSULATION PROCESSING OF LESS THAN 3700 BQ/GM1 TRU ISOTOPIC MIXED WASTE FOR DISPOSAL AT THE NEVADA TEST SITE
SAVANNAH RIVER SITE S MACROENCAPSULATION PROCESSING OF LESS THAN 3700 BQ/GM1 TRU ISOTOPIC MIXED WASTE FOR DISPOSAL AT THE NEVADA TEST SITE ABSTRACT Glenn W. Siry, Luke T. Reid Washington Savannah River
More informationNuclear Energy: Nuclear Energy
Introduction Nuclear : Nuclear As we discussed in the last activity, energy is released when isotopes decay. This energy can either be in the form of electromagnetic radiation or the kinetic energy of
More informationStructure and Properties of Atoms
PS-2.1 Compare the subatomic particles (protons, neutrons, electrons) of an atom with regard to mass, location, and charge, and explain how these particles affect the properties of an atom (including identity,
More informationIncoming Letter. 01/10/1994 Final No Comments 8/18/00. 01/01/1994 Final No Comments 10/25/1995. 10/15/1994 Final No Comments 08/18/2000
STATE REGULATION STATUS State: North Carolina Tracking Ticket Number: 16-26 Date: [ 6 amendment(s) reviewed identified by a * at the beginning of the equivalent NRC requirement.] RATS ID NRC Chronology
More informationPublished in the Official State Gazette (BOE) number 166 of July 10th 2009 [1]
Nuclear Safety Council Instruction number IS-22, of July 1st 2009, on safety requirements for the management of ageing and long-term operation of nuclear power plants Published in the Official State Gazette
More informationNatural and Man-Made Radiation Sources
Natural and Man-Made Radiation Sources All living creatures, from the beginning of time, have been, and are still being, exposed to radiation. This chapter will discuss the sources of this radiation, which
More informationDECOMMISSIONING COST ANALYSIS. for the MONTICELLO NUCLEAR GENERATING PLANT
Document X01-1617-004, Rev. 0 DECOMMISSIONING COST ANALYSIS for the MONTICELLO NUCLEAR GENERATING PLANT prepared for Xcel Energy Services, Inc. prepared by Bridgewater, Connecticut September 2011 Decommissioning
More informationSolar Energy Production
Solar Energy Production We re now ready to address the very important question: What makes the Sun shine? Why is this such an important topic in astronomy? As humans, we see in the visible part of the
More informationDecommissioning and dismantlement of the Stade nuclear power plant from nuclear power plant to green fields. Stade
Decommissioning and dismantlement of the Stade nuclear power plant from nuclear power plant to green fields Stade Contents 3 The Stade nuclear power station a short history 4 What does decommissioning
More informationANTEP 2015 Needs from China (NNSA)
ANTEP 2015 Needs from China (NNSA) 1 Content of training/education that Decommissioning plan and technologies 2 Background of above need 1. Design life of Qinshan NPP is 30 years, and it has been put into
More informationUniversity of Texas Nuclear Security Program: Academic Curriculum and Nuclear Engineering Teaching Laboratory
University of Texas Nuclear Security Program: Academic Curriculum and Nuclear Engineering Teaching Laboratory Specific Program Information Academic Curriculum and Nuclear Engineering Teaching Laboratory
More informationOil Spill Clean-up by Homeowner in Ohio *
Oil Spill Clean-up by Homeowner in Ohio * HALLWAY WITH OIL TANK AND ENCLOSURE (NOVEMBER 2005) This picture is taken before we purchased the property. The house is built on a slab foundation. There was
More informationFuel Cycle R&D to Safeguard Advanced Ceramic Fuel Skills Strategic Options
Fuel Cycle R&D to Safeguard Advanced Ceramic Fuel Skills Strategic Options Fuel Cycle R&D to Safeguard Advanced Ceramic Fuel Skills The Nuclear Renaissance and Fuel Cycle Research and Development Nuclear
More information