Reed College - Research Reactor Decommissioning Cost
REED COLLEGE RESEARCH REACTOR DECOMMISSIONING COST ESTIMATEFebruary 2018Stephen L. Bump, CHP, CIH, PMPWilliam E. Kennedy, Jr, MSNETracy A. Ikenberry, CHPPrepared For:Reed College32-3 SE Woodstock Blvd.Portland, OR 972121835 Terminal DriveSuite 200Richland, WA 99354DMA-TR-083
EXECUTIVE SUMMARYAt the request of Reed College, NV5/Dade Moeller performed this Decommissioning Study to providecost estimates and to evaluate alternatives for the eventual decommissioning the Reed ResearchReactor (RRR) facility located in Portland, Oregon.This study uses information from a variety of sources, including the previous study performed byReed College in 2010, several U.S. Nuclear Regulatory Commission (NRC) guidance documents andreports, and the decommissioning plans, cost estimates, and experience from other universityresearch reactors. Wherever possible, current RRR-specific information and currentdecommissioning cost factors were used, particularly those related to low-level radioactive wastehandling and disposal.This study presents alternative decommissioning strategies: one called DECON, where the facility isqualified for unrestricted release within a couple of years after permanent cessation of reactoroperations; and one called SAFSTOR, where the facility is placed in a secure mode for severaldecades after permanent cessation of reactor operations to allow time for additional radioactivedecay before final decommissioning. Due to the uncertainties associated with SAFSTOR, the DECONstrategy is likely to be preferred for RRR decommissioning.In order to provide a frame of reference, three additional reactor decommissioning cost estimatesare shown in Table E-1. The University of Illinois shows actual costs for their decommissioningproject. This was included as it was completed approximately 10 years ago and indicates recentexperience. The Oregon State University number is included as it is the baseline reactor used by theNRC for these estimates. The Oregon State University reactor is approximately four times larger thanRRR. The University of Kansas Training Reactor was a similar size reactor with a similar use profileand was used as a base case for this report.Table E-1: Decommissioning Cost Estimate SummaryEstimate DescriptionDECON2010 EstimateSAFSTOR – 25 yearsSAFSTOR – 100 yearsUniversity of Illinois – Actual CostsUniversity of KansasCost – 2018 Dollars 3,000,000 2,850,000 5,147,500 4,253,650 4,300,000 1,030,000Cost Including Standby 4,400,000 4,190,000N/AN/AN/AN/AIt should be noted that SAFSTOR only delays the DECON option. At some point, the RRR will have tobe decommissioned. The SAFSTOR estimates include the DECON cost without escalation, but doesinclude the five years of standby time.This study includes estimated costs (in 2018 dollars) and a schedule duration estimate fordecommissioning planning, removal, and disposal of irradiated and radioactively contaminatedstructures and materials, final radiological surveys to demonstrate compliance with radiologicalcriteria for unrestricted release, facility demolition, and site restoration.The costs associated with reactor fuel removal and transport from the RRR to U.S. Department ofEnergy (DOE) facilities are excluded, since that function is typically funded by DOE and is performedReed College Decommissioning Cost EstimateNV5.COM i
before decommissioning commences. The RRR fuel is owned by the DOE. DOE is willing to take thefuel upon reactor shutdown; however, the State of Idaho has currently placed a moratorium onreceipt of fuel shipments. Decommissioning cannot proceed until the fuel is removed from thereactor and shipped to DOE. Cost for surveillance and maintenance of the reactor facility willcontinue until such time as the reactor can be defueled and the fuel shipped.There are four major risks, as discussed in Section 5.1.2, associated with decommissioning at thistime:1. As noted above, the DOE cannot currently receive fuel even if the budget for receipt of fuel isapproved.2. The State of Oregon may take longer than two years to approve the decommissioning planand final status survey plan.3. The NRC may take longer than two years to approve the decommissioning plan.4. Soil and or ground water contamination may be found under the reactor building.Reed College Decommissioning Cost EstimateNV5.COM ii
ACRONYMSCFRCiCode of Federal RegulationscurieDOEDOTU.S. Department of EnergyU.S. Department of TransportationFTEfull-time equivalentKUTRkWUniversity of Kansas Training ReactorkilowattLLRWlow-level radioactive wasteMARSSIMmremMulti-Agency Radiation Survey and Site Investigation ManualmilliremN/ANRCnot applicableU.S. Nuclear Regulatory CommissionRCTRRRradiological control technicianReed Research ReactorSARSafety Analysis ReportµCimicrocurieReed College Decommissioning Cost EstimateNV5.COM iii
TABLE OF CONTENTSAcronyms . iii1.0Introduction. 11.11.2Objectives of the Study . 1Facility Description . 21.2.11.2.21.2.31.2.42.0Reactor Description . 2Reactor Coolant System . 6Secondary Cooling System . 7Experimental Facilities . 7Regualtory Requirements . 72.12.22.32.42.5Nuclear Waste Policy Act . 7Low-Level Radiaoctive Waste Policy Acts . 8Radiological Criteria for License Termination . 8Radionuclides of Concern . 9Other Requirements for License Termination . 93.0Facility Operating History and Radiological Characterization . 104.0Decommissioning Alternatives . 114.1DECON . 114.1.14.1.24.1.34.2SAFSTOR . 144.2.14.35.0Period 1: Preparations . 11Period 2: Decommissioning Operations. 12Period 3: Site Restoration . 14SAFSTOR Activities and Requirements . 14Cold Shutdown (Standby) . 15Cost Estimate . 165.1Financial Components of the Cost Model . 165.1.15.1.25.1.35.1.45.2DECON Alternative Cost Estimate Methodology. 185.2.15.2.25.36.1Basis of the DECON Alternative Cost Estimate . 18Comparison to KUTR Actual Costs . 23SAFSTOR Cost Estimate . 235.3.15.3.26.0Contingency . 16Financial Risk . 16Site-Specific Considerations . 17Assumptions . 1725 Year SAFSTOR Alternative Cost Estimate . 24100 Year SAFSTOR Analysis Cost Estimate . 24Radioactive Wastes . 25Primary Coolant Options . 26Reed College Decommissioning Cost EstimateNV5.COM iv
6.2Solid Waste Cost Saving Opportunities . 276.2.16.2.26.2.3Solid Waste Volume Reduction . 27Direct Contracting with U.S. Ecology . 27Low Specific Activity Shipping . 277.0Schedule Estimate . 278.0Summary . 289.0References . 29LIST OF TABLESTable E-1: Decommissioning Cost Estimate Summary . iTable 2-1: Isotopes of Concern . 9Table 5-1: DECON Activity Summary . 22Table 5-2: DECON Cost Estimate Summary . 23Table 5-3: 25 Year SAFSTOR Cost Estimate . 24Table 5-4: 100 Year SAFSTOR Cost Estimate . 24Table 6-1: Accountable Radioactive Sources . 25Table 6-2: Radioactive Waste Summary . 26Table 8-1: Decommissioning Cost Estimate Comparison . 28LIST OF FIGURESFigure 1-1: Cutaway View of a Typical TRIGA Reactor . 3Figure 1-2: Reflector and Reflector Plate . 5Figure 1-3: Upper and Lower Grid Plates . 6Reed College Decommissioning Cost EstimateNV5.COM v
1.0 INTRODUCTIONThis Decommissioning Study consists of assessing the various decommissioning alternatives andestimated costs related to decommissioning the Reed Research Reactor (RRR). This evaluation isbased on information contained in the 2007 Safety Analysis Report (SAR) (Reed, 2007) submitted tothe U.S. Nuclear Regulatory Commission (NRC) as part of the relicensing application, on otherdocuments supplied by Reed College, interviews with Reed College personnel, and field verificationof pertinent data and information.This review is required in part by 10 CFR 50.75, “Reporting and Recordkeeping for DecommissioningPlanning,” and 10 CFR 50.82, “Termination of License” (NRC, 2017). There are multiple guidancedocuments available to assist with cost estimating. The most germane, NUREG/CR-1756 (NRC,1983), is no longer in print or available from the NRC. As a replacement, the NRC has publishedNUREG-1757, Volumes 1, 2, and 3, Consolidated Decommissioning Guidance, (NRC 2006a, 2006b,and 2006c), which supersedes a number of previously issued NRC regulatory guidance documents,and NUREG-1537, Guidelines for Preparing and Reviewing Applications for the Licensing of NonPower Reactors (NRC, 1996). These guidance documents provide NRC-accepted methodologies forlicensees to use in demonstrating compliance with applicable sections of Title 10 of the Code ofRegulations (CFR), which are enforced by the NRC. It is noted that NUREG-1757 specifically doesnot apply in total to 10 CFR 50 licensees such as the RRR; however, parts of NUREG 1757 areapplicable such as the radiological criteria. The applicable radiological criteria are reflected whereappropriate.1.1OBJECTIVES OF THE STUDYThe primary objectives are to identify the alternatives available to Reed College with regards todecommissioning and to estimate the associated costs. Note that the removal of reactor fuel isdone before commencement of decommissioning operations; therefore, this task is not included aspart of decommissioning costs.There are two decommissioning alternatives to be considered for the RRR:DECON – in this alternative, the RRR would proceed into decommissioning mode after thefuel is removed and shipped for long-term storage or disposal. During DECON, all radioactivematerial is removed and shipped for disposal, and final release surveys are performed toallow the site to be used for any purpose Reed College chooses. The primary advantages arethat costs are estimated for the disposal pathways and labor using current information andthe costs of long-term stewardship are avoided. The primary disadvantages are there may bemore low-level radioactive waste volume and activity to dispose of under this scenariobecause additional time for radioactive decay is not provided.SAFSTOR – in this alternative, the RRR is put is a safe shutdown configuration, the fuel isremoved and shipped for disposal, and the facility is put in a cold, dark, and dry conditionwhile the majority of the remaining radioactive constituents allowed to decay for a period oftime pending ultimate demolition and removal. The primary advantage to this alternative isthe reduction in radioactive inventory to be disposed as low-level radioactive waste (LLRW).The disadvantages are the long-term stewardship cost, the potential for significant increaseReed College Decommissioning Cost EstimateNV5.COM 1
in labor cost, the potential for loss of (or having to use costlier) radioactive waste disposaloptions, potentially resulting in a significant increase in disposal cost.The other objective of the study is to generate cost estimates for each of the two decommissioningalternatives. Best estimates, based on historical and industry data, have been used to developthese numbers. Contingency numbers have been specified as directed by the NRC.1.2FACILITY DESCRIPTIONThe RRR is owned and operated by Reed College, a private undergraduate educational institutionlocated in Portland, Multnomah County, Oregon. The reactor was obtained in 1968 through a grantfrom the U.S. Atomic Energy Commission and is currently operated under NRC License R-112 andthe regulations in Chapter 1 of 10 CFR. The facility supports education and training, research, andpublic service activities. The reactor is in the Psychology Building, in an area constructed for thatpurpose, near the southeast corner of the Reed College campus in southeast Portland. The licenseecontrols access to Reed College facilities and infrastructure. City and college maps are supplied inChapter 2, Site Characteristics (Reed, 2007). Latitude and longitude, building plans, universalTransverse Mercator coordinates, population details, and other relevant information is provided inChapter 2 (Reed, 2007). The campus has approximately 1,300 students while the city of Portlandhas approximately 639,000 residents.The operations boundary of the reactor facility encompasses the reactor room and control room. Thesite boundary encompasses the entire building and 250 feet (76 m) from the center of the reactorpool, including the Psychology and Chemistry Buildings.1.2.1Reactor DescriptionThe RRR TRIGA reactor is a water-moderated, water-cooled thermal reactor operated in an openbelow-ground, water-filled tank. The reactor is fueled with heterogeneous elements clad withaluminum or stainless steel, consisting of nominally 20% enriched uranium in a zirconium hydridematrix. In 1968, the RRR TRIGA was licensed to operate at a steady-state thermal power of250 kW. In 2007, Reed College applied for a renewal of the Operating License (NRC,2011). Thiswas granted by the NRC in April 2012 (NRC, 2012). An application was made concurrently with thelicense renewal application to operate up to a maximum steady-state thermal power level of 500 kW.This upgrade allocation was withdrawn in 2010 during the NRC license renewal review process.Reactor cooling is by natural convection. The 250 kW-core consists typically of 79 fuel elements,each containing as much as 39 grams of 235U. There are currently 101 fuel elements in the RRRinventory. The reactor core is in the form of a right circular cylinder of about 9 inches (23 cm) radiusand 15 inches (38 cm) depth, positioned with axis vertical on one focus of a 10-foot (3 m) by 15-foot(4.6 m) tank with a 5-foot (1.5 m) radius on each long end. Criticality is controlled, and shutdownmargin is assured, by three control rods in the form of aluminum or stainless-steel clad boroncarbide or borated graphite. A sectional view of a typical TRIGA reactor is shown in Figure 1-1.Reed College Decommissioning Cost EstimateNV5.COM 2
Figure 1-1: Cutaway View of a Typical TRIGA Reactor1.2.1.1Reactor TankThe reactor core is located at the bottom of a below grade aluminum tank, which is 10 feet (3 m)wide and 15 feet (4.6 m) long with a 5-foot (1.5 m) radius at each end. The tank is 25 feet (7.6 m)deep and is bolted at the bottom to a 24 inch (61 cm) thick poured concrete slab. The tank has aminimum wall thickness of 0.25 inches (0.64 cm) and is surrounded by approximately 2.5 feetReed College Decommissioning Cost EstimateNV5.COM 3
(0.76 m) of concrete. A 2-inch (5 cm) by 2-inch (5 cm) aluminum channel used for mounting theneutron detectors and underwater lights is welded around the top of the tank. The top of the tank issurrounded by a steel frame 11 feet (3.4 m) wide and 16 feet (4.9 m) long, which is fabricated of10-inch (25.4 cm) structural-steel channel and is recessed in the top of the shield structure. Thetank is filled with demineralized water to a depth of 24.5 feet (7.5 m), providing approximately20 feet (6 m) of shielding water above the top of the core.1.2.1.2Center-Channel AssemblySupport for the various irradiation facilities, the control rod drive mechanisms, and the tank covers isprovided by the center-channel assembly at the top of the reactor tank (Figure 1-1). This assemblyconsists of two 8-inch (20 cm) structural-steel channels with six 16-inch (41 cm) wide by 0.625-inch(1.59 cm) thick steel cover plates bolted end-to-end to the flanges of the channels with socket-headscrews. The assembly has the shape of an inverted U, is 11 feet (3.3 m) long, and is positioneddirectly over the center of the reactor. The assembly is attached by two steel angle brackets at eachend to the 10-inch (25.4 cm) steel channels that form the recessed frame around the top of thetank. Each angle bracket is attached to each channel with four 1/2-13 by 1.5 inch (3.8 cm)stainless steel machine bolts. The brackets are made of 6-inch (15 cm) by 6-inch (15 cm) steelangle, 0.5 inches (1.3 cm) thick and 6 inches (15 cm) long. The channel assembly is designed tosupport a shielded isotope cask, weighing 4.5 tons (4,100 kg), placed over the specimen-removaltube.1.2.1.3Reactor-Tank CoversThe top of the reactor tank is closed at one end by four hinged covers that are flush with the floor.The covers are made of aluminum grating formed from 0.1875-inch (0.77 cm) by 1.5-inch (3.8 cm)aluminum bars. A sheet of 0.25 inch (0.635 cm) thick plastic is inserted in the bottom of eachgrating section to limit the entry of foreign matter into the tank while still permitting visualobservation of the reactor.1.2.1.4Reflector PlatformThe reflector platform is a square, all-welded aluminum-frame structure. It rests on four legs that areheld down by aluminum anchor bolts welded to the bottom of the aluminum tank.1.2.1.5ReflectorThe reflector surrounding the core (Figure 1-2) consists of a ring-shaped block of graphite having aninside diameter of approximately 18 inches (46 cm), a radial thickness of 12 inches (30 cm), and aheight of 22 inches (56 cm). Water is kept from contact with the graphite by a welded aluminumcontainer which encases the entire reflector. Provision for the isotope-production facility (rotaryspecimen rack) is made in the form of a ring-shaped well in the top of the reflector. The rotaryspecimen rack mechanism does not penetrate the sealed reflector assembly at any point. Thereflector assembly rests on the reflector platform. Support is provided by two aluminum channelswelded to the bottom of the reflector container.Reed College Decommissioning Cost EstimateNV5.COM 4
Figure 1-2: Reflector and Reflector Plate1.2.1.6Grid PlatesThe top grid plate (Figure 1-3) is made of aluminum and is 19.44 inches (49.35 cm) in diameter and0.75 inches (1.9 cm) thick. This plate provides accurate lateral positioning of the core components.It rests on six pads welded to the top of the reflector container. Two stainless steel dowel pins, whichfit tightly in the pads and loosely in the grid plate, orient the grid plate.The bottom grid plate (Figure 1-3), in addition to providing accurate spacing between the fuelmoderator elements, carries the entire weight of the core. This plate is of aluminum and is16 inches (40.6 cm) in diameter and 0.75 inches (1.9 cm) thick. It is supported by six L-shaped lugswelded to the underside of the reflector container. Two stainless steel dowel pins, which fit tightly inthe lugs and loosely in the plate, orient the grid.Reed College Decommissioning Cost EstimateNV5.COM 5
Figure 1-3: Upper and Lower Grid Plates1.2.2Reactor Coolant SystemDuring full power operation, the nuclear fuel elements in the reactor core are cooled by naturalconvection of the primary tank water. To remove the bulk heat to the environment, the primarywater is circulated through a heat exchanger where the heat is transferred to a secondary coolingloop. A cleanup loop maintains primary water purity with a filter and demineralizer to minimizecorrosion and production of long-lived radionuclides that could otherwise occur. The primary coolantprovides shielding directly above the reactor core.Reed College Decommissioning Cost EstimateNV5.COM 6
1.2.3Secondary Cooling SystemThe secondary cooling system provides the interface for heat rejection from the primary coolantsystem to the environment. The secondary system is an open system, with the secondary pumpdischarging through a primary-to-secondary heat exchanger, then through a forced-draft coolingtower.1.2.4Experimental FacilitiesStandard experimental facilities at the RRR TRIGA , as supplied by the vendor (General Atomics),include the central thimble, rotary specimen rack, and pneumatic specimen tube. Samples can alsobe lowered into the pool near the core for individually designed in-pool irradiations.1.2.4.1Central ThimbleThe reactor is equipped with a central thimble for access to the point of maximum flux in the core.The central thimble consists of an aluminum tube that fits through the center holes of the top andbottom grid plates terminating with a plug below the lower grid plate. The tube is anodized to retardcorrosion and wear. The thimble is approximately 20 feet (6.1 m) in length, made in two sections,with a watertight tube fitting. Although the shield water may be removed to allow extraction of avertical thermal-neutron and gamma-ray beam, four 0.25-inch (6.3 mm) holes are located in the tubeat the top of the core to prevent expulsion of water from the section of the tube within the reactorcore.1.2.4.2Rotary Specimen RackA 40-position rotary specimen rack is in a well in the top of the graphite radial reflector. A rotationmechanism and housing at the top of the reactor allows the specimens to be loaded into indexedpositions and allows rotation of samples for more uniform exposure across a set of co-irradiatedsamples. Although the rotary specimen rack would allow for large-scale production of radioisotopes,it is primarily used for neutron activation analysis on about 200 samples per year.1.2.4.3Pneumatic Specimen TubeA pneumatic transfer system, permitting applications with short-lived radioisotopes, rapidly conveys aspecimen from the reactor core to a remote receiver. The in-core terminus is located at location F-5in the outer ring of fuel element positions.2.0 REGUALTORY REQUIREMENTSThis section provides a summary of the most relevant regulatory requirements that control thedecommissioning process.2.1NUCLEAR WASTE POLICY ACTThe Nuclear Waste Policy Act of 1982 provided for the development of repositories for the disposalof high-level radioactive waste and spent nuclear fuel and established a program of research,development, and demonstration regarding the disposal of high-level radioactive waste and spentReed College Decommissioning Cost EstimateNV5.COM 7
nuclear fuel. This Act created a fund supported by the utilities that was supposed to result in theopening of Yucca Mountain (or a similar repository) for the disposal of spent nuclear fuel. Utility fuelwould have priority over research reactor fuel such as that in use at RRR. The RRR fuel is owned bythe U.S. Department of Energy (DOE) and, historically, it was intended to be returned to DOE after theRRR permanently ceases reactor operations so Reed College would not be responsible for its finaldisposal.However, the only repository for DOE research reactor fuel is at the Idaho National Laboratory.Currently, the State of Idaho has placed a moratorium on any further fuel receipts of researchreactor fuel until DOE has a path forward for disposal of the used fuel. Without a national repositorysuch as Yucca Mountain, such a path forward is not being developed. If this situation persists, therewill be an impact on research reactors since at shutdown there may be no provisions for shipping thefuel to DOE and the individual reactors may need to develop and maintain facilities to safely, andsecurely, store the fuel2.2LOW-LEVEL RADIAOCTIVE WASTE POLICY ACTSThe Low Level Radioactive Waste Policy Act of 1980 implemented Congress’s belief thatcommercially-generated LLRW (i.e., radioactive waste that is not generated by DOE activities) couldbest be managed on a regional basis and set up the framework for interstate compacts that wouldbe ratified by Congress. To encourage the development of new sites, the compacts would be allowedto exclude or limit waste from generators located in states that are not parties to those compacts(called “nonparty” or “out-of-compact” states). At that time, only three commercial LLRW disposalsites existed in the United States in Nevada, South Carolina, and Washington. These three statessoon formed compacts with their neighboring states (called the “sited” compacts). Because of thelack of progress toward establishing new LLRW disposal sites, Congress passed the Low LevelRadioactive Waste Policy Amendments Act of 1985 to create penalties for delays and allowed thesited compacts to ban importation of out-of-compact waste at the end of 1995.The state of Oregon is part of the Northwest Compact, which allows the RRR to send its waste to theU.S. Ecology Site near Richland, Washington. This greatly reduces the uncertainty surrounding wastedisposal pathways and helps minimize transportation costs. The U.S. Ecology Site is licensed toreceive all demolition waste except for the fuel and any highly radioactive reactor components, whichwould be classified as greater than Class C waste by the NRC. There is no disposal pathway foreither of these classes of waste.2.3RADIOLOGICAL CRITERIA FOR LICENSE TERMINATIONSince the RRR is licensed by the NRC, radiological criteria for terminating its license are specified in10 CFR 20, Subpart E. The criteria used for license termination are largely dependent upon thefuture use scenario for the facility. For example, if a restricted use scenario is chosen, it is possiblethat a 100 mrem/year dose distinguishable from background to the average member of a criticalgroup would be an acceptable
The primary objectives are to identify the alternatives available to Reed College with regards to decommissioning and to estimate the associated costs. Note that the removal of reactor fuel is done before commencement of decommissioning operations; therefore, this task is not included as part of decommissioning costs.
2. TUBULAR REACTOR DESCRIPTIONS 3 3. GENERAL EVALUATION OF TUBULAR REACTORS 10 3.1 Design Basis and Requirements 10 3.2 General Evaluation 11 4. EVALUATION OF SPECIFIC REACTOR DESIGNS 19 4.1 Modec Constant Diameter Tubular Reactor 19 4.2 Dickinson Tubular Reactor Designs 22 4.3 Welch and Slegwarth Annular Reactor 23 4.4 Li and Gloyna Reactor 24
From handling point of view, the RSG-GAS building houses the crane with the capacity of 30 tons. By using this crane and the space available in the reactor building, the decommissioning of the reactor core plant would be easily handled out of the building through material access available in 0.00 m level o
NUCLEAR PHYSICS AND REACTOR THEORY Module 4 Reactor Theory (Reactor Operations) Reactor Theory (Operations) i TABLE OF CONTENTS . number of neutrons produced by fission in subsequent generations due to the introductio
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OIG conducted an Audit of NRC's Decommissioning Funds Program (OIG-16-A-16) that included a review of NRC's oversight of the decommissioning funds of both reactors and materials. The audit report was issued in June 2016. During that audit, OIG was not able to verify the accuracy of the Inventory List of material licensee decommissioning
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