ML22340A011
| ML22340A011 | |
| Person / Time | |
|---|---|
| Site: | Aerotest |
| Issue date: | 01/11/2019 |
| From: | Croslin S Aerotest, EnergySolutions |
| To: | Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML22340A004 | List: |
| References | |
| CS-HP-PR-006, Rev 6 | |
| Download: ML22340A011 (1) | |
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ENERGYSou:lr.la\\{S CS-HP-PR-006 Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor Project No. 313150 California Prepared for:
Aerotest Operations, Inc.
Prepared by:
EnergySolutions, LLC LP&D Projects Group 151 Layfayette Drive Oak Ridge, TN 37830 Revision 6 Authored By:
11/27/2018 Steve Croslin, CHP, Radiological Engineer Reviewed By:
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L Non-Proprietary C Proprietary D Restricted Information D Safeguards Information D Sensitive Security Information Date 11 JAN 19 Date Date LJ New D Title Change
[]Revision 0Rewrite D Cancellation Effective Date:
1/11/19 Electronic documents, once printed, are uncootrollcd and may become outdated.
Refer to the intrawcb or the Document Control authority for the correct revision.
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 TABLE OF CONTENTS Section Page Page 2 of 95 LIST OF APPENDICES................................................................................................................. 5 LIST OF FIGURES........................................................................................................................ 6 LIST OF TABLES.......................................................................................................................... 8 1.0 ACRONYMS AND ABBREVIATIONS........................................................................... 9 2.0 EXECUTIVE
SUMMARY
.............................................................................................. 10
3.0 INTRODUCTION
............................................................................................................ 11 3.1 Purpose.................................................................................................................. 11 3.2 Scope..................................................................................................................... 12 3.3 Assumptions and Bases......................................................................................... 13 4.0 GENERAL SITE DESCRIPTION................................................................................... 15 4.1 Current and Assumed Facility Status.................................................................... 15 4.2 Proposed Action and Alternatives........................................................................ 16 4.3 Administrative Controls........................................................................................ 18 5.0 DECOMMISSIONING CRITERIA................................................................................. 26 5.1 Radionuclides of Interest...................................................................................... 26 5.2 Radiological Criteria for License Termination..................................................... 28 5.3 Facility Description............................................................................................... 30 5.3.1 Reactor Building....................................................................................... 30 5.3.2 Building Addition 1.................................................................................. 38 5.3.3 Tagging Area Building............................................................................. 39 5.3.4 Demineralizer Building............................................................................. 40 5.3.5 Heat Exchanger Building.......................................................................... 40 5.3.6 Cooling Towers......................................................................................... 41 5.3.7 Maintenance Office Building.................................................................... 41 5.3.8 Compressor Building................................................................................ 41 5.3.9 Chemical Shed.......................................................................................... 41 5.3.10 Class 1.1 Explosive Storage Container..................................................... 41 5.3.11 Storage Building....................................................................................... 41 5.3.12 Waste Storage Sump................................................................................. 41 5.3.13 Land Area.................................................................................................. 42 5.4 Relation of the ARRR to Other TRIGA reactors.................................................. 42 5.5 Outside Areas........................................................................................................ 42 6.0 ESTIMATION METHODS.............................................................................................. 67
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 3 of 95 6.1 Cost Modifying Factors........................................................................................ 67 6.2 Radioactive Waste Volume Estimates.................................................................. 71 6.3 Radioactive Waste Disposal Costs........................................................................ 71 6.3.1 Clive, Utah Radioactive Waste Direct Disposal Costs............................. 71 6.3.2 Radioactive Waste Processing and Burial Costs...................................... 71 6.4 Remediation Methods........................................................................................... 72 6.5 Radioactive Waste Volume Reduction Costs....................................................... 72 6.6 Unit Costs.............................................................................................................. 73 6.7 Final Surveys........................................................................................................ 74 7.0 FACILITY, CONDITIONS AND DECOMMISSIONING SCENARIO........................ 75 7.1 Remediation Summary.......................................................................................... 75 7.1.1 General Area Cleanup............................................................................... 76 7.1.2 Non-Reactor Remediation........................................................................ 76 7.1.3 TRIGA Reactor......................................................................................... 76 7.1.4 Demineralizer and Heat Exchange Buildings........................................... 77 7.1.5 Reactor High Bay Area............................................................................. 77 7.1.6 High Bay Area........................................................................ 78 7.1.7 Other Buildings......................................................................................... 79 7.1.8 Outdoor Areas........................................................................................... 79 7.2 License Termination Surveys............................................................................... 81 7.2.1 Survey Instrumentation............................................................................. 81
8.0 REFERENCES
................................................................................................................. 82
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 4 of 95 Summary of Technical Changes Revision Summary of Technical Changes 1 through 5 6
Updated the ARRR facility D&D cost estimate to reflect cost increases due to inflation and other major costs factors such as radioactive waste burial.
Updated the ARRR facility D&D cost estimate to reflect cost increases due to inflation (annual inflation rate of 3%) since the update on 2/28/2017 and the removal of legacy radioactive waste items from the site in 2017. Revised all tables, appendices and text references that contain cost information and revised other radioactive waste information, such as waste volume, where applicable.
The document was also updated to reflect the new owner of the facility, the current status of the facility, possible future operations, and potential licensing options.
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 LIST OF FIGURES Section Page Page 5 of 95 Appendix A-1 Contaminated Waste Volume Summary............................................................... 83 Appendix A-2 Contaminated Waste Disposal Cost...................................................................... 84 Appendix A-3 Waste Shipping Container Cost............................................................................ 85 Appendix A-4 Waste Disposal Support Labor Estimate.............................................................. 86 Appendix A-5 Radioactive Waste Container, Cask and Labor Summary...88 Appendix A-6 Building Survey Labor Summary.89 Appendix A-6 Building Survey Labor Summary..90 Appendix A-7 Outdoor Area Survey Labor Summary..91 Appendix A-8 Instrument Lease Charges..92 Appendix A-9 Equipment Lease Charges..93 Appendix A-10 Consumable Costs...94 Appendix A-11 Demolition Estimate........95 Appendix A-12 Miscellaneous Items Volume Estimate...96
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 LIST OF FIGURES Section Page Page 6 of 95 Figure 4-1: Aerotest Operations Site Location............................................................................. 20 Figure 4-2: Aerotest Aerial Image................................................................................................ 21 Figure 4-3: ARRR Local Area View............................................................................................ 22 Figure 4-4 General ARRR Arrangement Plan.............................................................................. 23 Figure 4-5 Plan Layout of ARRR Reactor Building..................................................................... 24 Figure 4-6: Cross Section of ARRR High Bay Reactor Building................................................ 25 Figure 5-1: Reactor & N-Ray Area with Shielding in Place........................................................ 43 Figure 5-2: ARRR Core and Support Structure............................................................................ 44 Figure 5-3: ARRR Reactor Tank Cutaway and N-Ray Facility................................................... 45 Figure 5-4: ARRR In-Core Irradiation Capsule............................................................................ 46 Figure 5-5: ARRR Machine Shop................................................................................................. 47 Figure 5-6: ARRR Chemistry Lab................................................................................................ 48 Figure 5-7: ARRR Preparation Lab.............................................................................................. 49 Figure 5-8: ARRR Sheet Metal Fabrication Area...................................................... 50 Figure 5-9: ARRR Sheet Metal Fabrication Area & HVAC Unit............................. 51 Figure 5-10: ARRR Storage Area.............................................................................. 52 Figure 5-11: ARRR Instrument Calibration Area...................................................... 53 Figure 5-12: ARRR Electronics Lab............................................................................................. 54 Figure 5-13: ARRR Shipping & Receiving.................................................................................. 55 Figure 5-14: ARRR N-Ray Setup Area........................................................................................ 56 Figure 5-15: Office Space............................................................................................................. 57 Figure 5-16: Customer Viewing Area........................................................................................... 58 Figure 5-17: Quality Control Room.............................................................................................. 59 Figure 5-18: Computer and Counting Room................................................................................ 60 Figure 5-19: Tagging Area............................................................................................................ 61 Figure 5-20: Tagging Area Back Room........................................................................................ 62 Figure 5-21: Backup Cooling Tower............................................................................................ 63 Figure 5-22: Main Cooling Tower................................................................................................ 64 Figure 5-23: Storage Building...................................................................................................... 65
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 7 of 95 Figure 5-24: Waste Storage Tanks................................................................................................ 66
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 8 of 95 LIST OF TABLES Table Page Table 5-1: List of Expected Radionuclides................................................................................... 26 Table 5-2: Acceptable License Termination Screening Values of Common Radionuclides for Building Surface Contamination................................................................................................... 29 Table 6-1: Decommissioning Cost Summary - ARRR................................................................ 67 Table 6-2: Personnel Protective Equipment Protection Summary............................................... 68 Table 6-3: Hazardous and Toxic Waste Productivity Factors: Light Work................................. 69 Table 6-4: Hazardous and Toxic Waste Productivity Factors: Heavy Work................................ 70 Table 6-5: ARRR Unprocessed Radioactive Waste Summary..................................................... 71 Table 6-6: Decontamination Methodology Comparison.............................................................. 72 Table 6-7: Volume Reduction/Treatment Methods Cost Information.......................................... 73 Table 6-8: Decommissioning Cost Estimate Selected Unit Cost Factors..................................... 73 Table 7-1: ARRR Planned Remediation Activities...................................................................... 75 Table 7-2: Typical Final Survey Instrumentation......................................................................... 81
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 9 of 95 1.0 ACRONYMS AND ABBREVIATIONS
° Degrees
°F Degrees Fahrenheit Aerotest Aerotest Operations, Inc.
AGN Aerojet-General Nucleonics AGNIR Aerojet-General Nucleonics Industrial Reactor ARRR Aerotest Radiography and Research Reactor CA State of California CDPH California Department of Public Health Ci Curies Co Cobalt COC Contaminants of Concern DOE U.S. Department of Energy HSA Historical Site Assessment L
Liter MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual mCi millicuries mR/hr MilliRoentgen per hour NRC U.S. Nuclear Regulatory Commission N-Ray Neutron Radiography pCi picocuries pCi/g picocuries per gram pCi/L picocuries per Liter RHB California Radiologic Health Branch (California Department of Health)
TRIGA Teaching Research Isotope General Atomic (reactor)
TS Technical Specification USNRC U.S. Nuclear Regulatory Commission
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 10 of 95 2.0 EXECUTIVE
SUMMARY
EnergySolutions performed an independent cost estimate for decommissioning the Aerotest Radiography and Research Reactor (ARRR) located in
, California. This cost estimate was originally prepared in 2012 at the request of Aerotest Operations, Inc., (Aerotest) and has been updated with this revision to reflect the new ownership, the current status of theARRR, possible future options and to provide the cost estimates in 2018 dollars.
This decommissioning cost estimate (DCE) was developed using a systematic approach, in accordance with applicable industry and regulatory guidance. Decommissioning regulatory criteria and guidance were identified and ARRR historical survey data were reviewed. Specific and general information regarding equipment and structures were used in determining decontamination and demolition methodologies in order to minimize overall decommissioning costs.
This estimate includes itemized costs for labor and equipment resources, radioactive waste and debris packaging, radioactive waste and debris shipping, radioactive waste burial activities, and the performance of final status surveys for buildings, property and structures. The estimated decommissioning cost is $3,080,126 in terms of 2018 dollars. All costs were escalated at a 3%
annual inflation rate and costs were adjusted for removal of legacy waste from the site in 2017.
The total estimated 2018 decommissioning cost is approximately 10% lower than the previous estimate of $3,427,040 from February 2017. This estimate does not include the costs associated with fuel removal and transport from ARRR to the Department of Energy (DOE). However, ARRR has a DOE contract amendment that establishes the fee for the disposal of the spent nuclear fuel generated by ARRR (U.S. Department of Energy Contract Amendment to DE-CR01-83NE44484). This decommissioning estimate is for budgetary purposes only and is not a proposal for EnergySolutions to perform the work.
A significant portion of the overall decommissioning costs is attributed to the disposal of radioactive waste. The radioactive waste disposal rates used for most of the waste in this estimate are based on shipping to a licensed disposal site at Clive, Utah.
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 11 of 95
3.0 INTRODUCTION
3.1 PURPOSE Aerotest Operations has provided Neutron Radiographic (N-Ray) Inspection Services since 1969, using the ARRR for the source of neutrons, mainly for neutron radiography. Aerotest Operations, Inc., (Aerotest) is the holder of Facility Operating License No. R-98 for the ARRR, located in California. The reactor facility had an earlier shutdown order lifted but is still without a loaded reactor core. The ARRR may be restarted for commercial operations if approved by the NRC. If a decision is made to decommission the ARRR, the basic steps needed to complete decommissioning are explained in this section.
After fuel removal, Aerotest would file the appropriate decommissioning amendment requests, together with a Decommissioning Plan with the NRC and the State of California. As with other facilities of this nature, the ARRR Facility is contaminated with varying amounts of radioactive material and small amounts of hazardous material. Decontamination and Decommissioning (D&D) of the ARRR would eliminate the potential for future inadvertent environmental releases and other potential liabilities. The goal of the D&D activities would be termination of the ARRR TRIGA Reactor Nuclear Regulatory Commission (NRC) License R-80, Docket No. 50-228 and release of the ARRR site for "unrestricted use." The term "unrestricted use" means that there will be no future restrictions on the use of the site, other than local ordinances such as the City of zoning ordinances. ARRR also maintains Radioactive Materials License number 2010-07 with the State of California. This license governs possession and use of radioactive materials independently of the reactor. The State of California, as an Agreement State, has regulatory authority and responsibility for these specific radioactive materials. The state is the primary authority responsible for oversight and approval of decommissioning the Site with respect to these materials. In addition, the State of California is authorized to implement RCRA requirements, and through this means can implement more restrictive cleanup requirements for the ARRR decommissioning than required by the NRC. The State rules for termination of a Radioactive Materials License are provided in Title 17 California Code of Regulations, Division 1, Chapter 5, Subchapter 4, Section 30256. Currently there are no radiation dose based release criteria for licensed facilities in California, but instead, case by case evaluations are performed of Decommissioning Plans by the California Department of Public Health (CDPH). Experience indicates that release limits that equate to a few millirem/year (mrem/yr) from residual radioactivity are generally accepted.
EnergySolutions has prepared this document for the purpose of providing a DCE for the ARRR.
The cost estimate includes those activities and associated cost factors required to terminate the ARRR Nuclear Regulatory Commission (NRC) License R-98, Doc. No. 50-228 and State of California Radioactive Materials License number 2010-07 for release of the facility for "unrestricted use." It should be understood that the estimate does not include costs for removable and disposition of remaining uncontaminated facility infrastructure, such as concrete and asphalt that remain at the site. Disposal of this remaining infrastructure will fall under the jurisdiction of the State of California and/or local rules and regulations, if applicable.
The ARRR decommissioning cannot be completed until after the fuel has been removed from the site, which is currently projected to be sometime after 2055. However, the cost estimate
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 12 of 95 provided in this report is based on prompt decommissioning (within the next several years),
rather than waiting until 2055 to perform decommissioning and costs are in terms of 2018 dollars. This cost estimate is solely intended to be used for funding and budgetary purposes and does not constitute a proposal or cost estimate for EnergySolutions to perform work.
3.2 SCOPE The scope of this report is to present the estimated costs derived for decommissioning the ARRR. The specific areas covered by this estimate include:
TRIGA Reactor TRIGA Reactor Shield and N-Ray Components Buildings Outdoor Areas This estimate has been prepared to provide a budgetary DCE and to support the requirements of 10 CFR 50.82(b), Termination of License - for Non-Power Reactor Licensees (Ref. 8.1). This estimate addresses activities related to the removal of hardware, structural materials, and miscellaneous materials as necessary to reduce levels of residual radioactivity to below the guideline values in the NRC criteria for license termination contained in Subpart E of 10 CFR Part 20 (Ref. 8.2).
The current NRC guidance for acceptable license termination screening values (meeting the 10 CFR 20.1402 criteria) of common radionuclides for building surface contamination and surface soil contamination are presented in NUREG-1757, Consolidated NMSS Decommissioning Guidance, Decommissioning Process for Materials Licenses, Appendix B, (Ref. 8.3). For the purposes of this estimate, it was assumed that license termination screening values of 12%
(3/25th) of the 10 CFR 20.1402 criteria would be acceptable to California (equivalent to 3 mrem/yr above background versus the NRC allowed 25 mrem/yr above background).
Decommissioning costs are directly related to the degree of remediation required and the amount of radioactive waste generated. The extent of remediation is based on radiological data, proven decontamination processes and data from similar projects. The volume of radioactive wastes was estimated based on data provided from facility drawings, equipment sizes, Characterization Surveys, routine facility radiological data, and proven volume reduction processes. Costs associated with the performance of Final Status Surveys were estimated based on the size of the various areas being decommissioned and their prior radiological history.
The cost estimate for ARRR utilizes a combination of unit price estimates and task-based estimates to arrive at a total cost in 2018 dollars for decommissioning all areas. The unit cost methodology is modeled after the method used in the Means Building Construction Cost Data (Ref. 8.4). The decommissioning work is first divided into units of work, such as removing a 2-inch pipe run, and then the unit cost per foot for pipe removal is multiplied by the total feet of pipe to arrive at the cost. A similar method is used for decontamination work, such as the decontamination of a concrete floor to a depth of 1/4 inch. The unit cost per square foot for concrete floor decontamination is multiplied by the total square feet of floor area to arrive at the cost. These estimates includes the craft labor, supervision, health physics support, waste
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 13 of 95 disposal, materials and equipment necessary to actually perform this task. Other work is priced using the task based methodology which is modeled after the method used by the Pacific Northwest Laboratory (PNL) to prepare the estimates presented in NUREG/CR-1756, Technology Safety and Costs of Decommissioning Reference Nuclear Research and Test Reactors, March 1982 (Ref. 8.5). The work is divided into various tasks, such as decontaminating pool walls, and then an estimate is generated for each task. The various costs derived from the two methods are combined and a project schedule is developed which defines the duration and man-loading for the project. The schedule and man-loading information were used in the development of costs for on-site project management, travel and living for non-local workers, equipment rental, home office support, and owner oversight.
3.3 ASSUMPTIONS AND BASES The following assumptions and bases were utilized in developing the cost estimate.
The reactor fuel will have been removed and transported from ARRR to the DOE or placed in storage outside the pool prior to the start of decommissioning; costs for these activities are not included in this estimate.
ARRR will be decontaminated, all radioactive waste will be removed, and the facility will be released for unrestricted use.
Some of the uncontaminated materials and equipment located throughout the facility have a high intrinsic value and may be sold or moved to another facility prior to decommissioning. No credit has been taken for the sale of any items.
The use of radioactive materials at the ARRR has been well controlled and contaminated areas are minimal and well defined. Contamination outside of the defined areas is not anticipated and costs for remediation outside of currently contaminated areas are not included in this estimate.
Contaminated material will, for the most part, be shipped directly to a licensed radioactive waste disposal site. Some material may be shipped to a volume reduction or treatment facility (e.g., contaminated lead) for processing prior to disposal.
It is assumed for this cost estimate that some equipment and materials that have minimal contamination based on surveys (i.e., contamination below the applicable release limits) will be sent for disposal. Wastes will be managed per Reference 8.11.
Aerotest will provide security for the site, electrical power and water will be available, and ARRR staff and management will be on site during decommissioning.
Radioactive dry active waste (DAW) with low specific activity will be sent to the licensed facility in Clive, Utah for disposal. It is assumed that contaminated concrete, protective clothing waste and miscellaneous DAW generated by D&D activities will qualify for disposal at Clive, Utah.
Activated materials, when properly packaged, may all be suitable for disposal at Clive, Utah. If there is radioactive waste not suitable for disposal at Clive, Utah, it may be sent to a waste processor prior to disposal or to an interim storage facility until California has a licensed permanent disposal facility available.
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 14 of 95 The site decommissioning contractor will provide the demolition equipment and survey instrumentation at prevailing rates.
Local decontamination technicians and supervisors will be used to staff this project; therefore, no travel and living funds are included for local personnel. Health Physics technicians, site supervisors and project management personnel will not be local hires; therefore, funds for travel and living expenses are included.
Construction labor rates were obtained from the Means Building Construction Cost Data (Ref. 8.4) for Oakland, California, adjusted for inflation.
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 15 of 95 4.0 GENERAL SITE DESCRIPTION The property, on which the ARRR is situated, was designated for construction in 1963. The ARRR was constructed between 1963 and 1964. The ARRR site configuration is shown in Figure 4-1, Figure 4-2 and Figure 4-3. The land area is well defined, as there is a fence around the facility, except for the facility parking lot. The Reactor Building footprint is about 3,200 square feet and has two floor levels, and the total footprint for all buildings is 9,250 square feet.
Figure 4-4 provides a layout of the ARRR buildings, Figure 4-5 provides a plan view of the High Bay Reactor Building and Figure 4-6 provides a cross section view of the Reactor Building.
The areas listed in this section of the ARRR DCE include all rooms in all buildings, whether remediation could be required or not, based upon the characterization study and survey performed in May 2011.
In 1963 Aerotest began construction of a facility to house the TRIGA Reactor, and supporting systems (e.g., Instrumentation and Control Systems, Forced Cooling System, Water Demineralization System, Ventilation/Exhaust System, Radiation Monitoring Systems, etc.).
Following construction and reactor hardware installation, the TRIGA Reactor was brought to initial criticality in July of 1964. The TRIGA was routinely operational from that date until the NRC denied a renewal of the operating license in 2012. The TRIGA is currently in a restart program. Some anticipated facility conditions applicable to decommissioning are listed in the following section.
4.1 CURRENT AND ASSUMED FACILITY STATUS The following conditions are currently in place or it is assumed they will be in place during the decommissioning period :
ARRR utility services required for facility operation and maintenance under POS status conditions will remain active.
Manually actuated and automated fire alarm systems in the ARRR will remain operational.
All building utility services required for facility operation and maintenance are active and will be available as needed.
The license-required radiological monitoring and instrumentation systems will remain operational.
Existing physical security and material control and accounting plans approved by the Nuclear Regulatory Commission (as may be amended) will continue to be implemented.
The water demineralization system serving the ARRR is currently operational, although the status may change depending on requirements that are implemented by future license amendments.
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 16 of 95 4.2 PROPOSED ACTION AND ALTERNATIVES The Proposed Action and the Alternatives are as follows:
Proposed Action (Modified SAFSTOR) - In safe storage, the Aerotest Reactor would be placed and maintained in a condition that allows it to be safely stored and subsequently decontaminated to a USNRC and/or state of California level permitting eventual unrestricted release of the property. This would involve retention of the fuel onsite until the Department of Energy (DOE) is able to take the spent fuel. The DOE has agreed to take the fuel in 2055 at the earliest. This could change to an earlier date in the event DOE opens regional interim storage facilities.
Alternative 1 (DECON) - Decontamination and Decommissioning of the ARRR, including the reactor, followed by license termination and subsequent release of the site for unrestricted use. This is not currently a viable option as there is not a possibility for fuel removal in the near future; however, decommissioning of the facility could be performed if the fuel is placed in a suitable on-site dry storage container.
Alternative 2 (ENTOMB) - In entombment, radioactive materials are encased in a structurally long lived material such as concrete. The entombed structure is appropriately maintained and surveillance is continued until the radioactivity decays to a USNRC or state of California level permitting release of the property. This is not currently a viable option as the fuel must first be removed from the site and there is not a possibility for fuel removal in the near future.
No Action Alternative - A no-action alternative would leave the facility in its current status with the current support staff having to maintain the facility under the existing license conditions. This action would not likely be allowed without a license transfer to a new facility owner. This action would involve maintaining:
o The facility reactor operating license o Personnel to support facility maintenance and surveillance o Surveillance and maintenance of Reactor Pool Water Level, Purity and pH o The Reactor Facility Physical Security Plan The reactor tank still contains fuel and activated hardware items with gamma radiation levels over an estimated 500 R/hr on contact in 2011. The reactor tank does not have a history of leakage. However, keeping the facility in an inactive status for a long period of time may lead to a degradation of the tank, which could eventually require repairs or the decommissioning of that portion of the facility. The reactor tank integrity would need to be routinely monitored. Aerotest would incur expenses for maintenance and surveillance without making beneficial use of the facility.
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 17 of 95 In addition, the NRC requirement in 10 CFR 50.82(b)(1)(ii) providing for non-power reactor decommissioning without significant delay following permanent shutdown would have to be waived if the no action alternative were chosen.
Implementation of the Proposed Action would include retention of the fuel on site until the DOE is able to take the spent fuel. This could probably be accomplished using one of two scenarios:
(1) storing the fuel in the pool where it is currently located or (2) removal of the reactor fuel from the tank to an on-site dry storage container.
The scenario where the fuel is maintained in the pool would likely include the following tasks:
Storage of the fuel in storage racks on the pool or on the pool Continued operation and maintenance of the pool water demineralizer system.
Optional removal of the pool water cooling system including heat exchanger and cooling towers.
Decontamination and control of any contaminated areas.
Shipment of the low level radioactive waste (LLRW) currently on site or generated as a result of decommissioning activities.
Performance of surveys to confirm the facility status.
Submission of a Decommissioning Plan for license to the USNRC.
Daily site monitoring of operations, similar to current site requirements, to ensure systems are performing correctly and performing maintenance of the facility for continued occupancy.
Continuing to implement the existing physical security, radiological control, material control and accountability plans approved by the Nuclear Regulatory Commission (as may be amended).
Once the DOE has taken the fuel off site, a revision to the Decommissioning Plan would be made, as required.
The facility would be decontaminated and decommissioned, including the performance of Final Status Surveys and release of the facility for unrestricted use and termination of the ARRR license.
The scenario where the fuel is removed from the pool to dry storage on site would likely include the following tasks:
Removal of the reactor fuel from the tank to an on-site dry storage container.
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 18 of 95 Dismantlement, decontamination and/or packaging as low-level radioactive waste (LLRW) the ARRR Reactor components including the demineralizer system, the cooling system, the bioshield and the operating and control systems, but not the reactor tank.
Decontamination and control of any contaminated areas to prevent future contamination.
Shipment of any remaining low level radioactive waste (LLRW) currently on site and waste generated as a result of decommissioning activities.
Performance of surveys to confirm the facility status.
Submission of a Decommissioning Plan to the USNRC.
Continuing to implement the existing physical security, radiological control, material control and accountability plans approved by the Nuclear Regulatory Commission (as may be amended).
Once the DOE has taken the fuel off site, a revision of the Decommissioning Plan would be made, as required.
The facility would be decontaminated and decommissioned, including the performance of Final Status Surveys and release of the facility for unrestricted use and termination of the ARRR license.
4.3 ADMINISTRATIVE CONTROLS To minimize the risks of inadvertent exposure, contamination and/or radioactive releases, all decommissioning operations will be implemented in accordance with appropriate technical and administrative controls, including:
Performance of all project work pursuant to approved procedures implementing a USNRC-approved Decommissioning Plan. ARRR will continue to be responsible for assuring and demonstrating compliance with USNRC licenses, as well as other applicable federal, state or local laws, regulations, licenses and/or permits.
Utilization of containment structures, tents, and bags under negative pressure and/or appropriate contamination barriers to isolate operation areas and prevent inadvertent release of contaminants.
Employment of monitored, high efficiency particulate air (HEPA) filtration systems for air ventilation in contaminated work areas.
Maintenance of emergency ventilation, electrical power and supplies, as appropriate.
Application of ALARA principles by emphasizing radiation protection for workers and the general public, employing personnel and area dosimetry, using personal protective equipment and clothing, and conducting work through approved Radiological Work Permits. The term "ALARA" means as low as is reasonably achievable, taking into
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 19 of 95 account the state of technology and the economics of improvements in relation to the benefits to public health and safety, and other societal and socioeconomic considerations.
ARRR Health Physics staff will have the authority to stop any operations that they believe may involve unusual, unnecessary or excessive radiological risk to the worker, the public or the environment.
Maintenance of security access control to the work site and facility to restrict unauthorized individuals from the work area.
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 20 of 95 Figure 4-1: Aerotest Operations Site Location
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 21 of 95 Figure 4-2: Aerotest Aerial Image
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 22 of 95 Figure 4-3: ARRR Local Area View
Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor Figure 4-4 General ARRR Arrangement Plan CS-HP-PR-006 Revision 6 Page 23 of 95
Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor Figure 4-5 Plan Layout of ARRR Reactor Building CS-HP-PR-006 Revision 6 Page 24 of95
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 25 of 95 Figure 4-6: Cross Section of ARRR High Bay Reactor Building
Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor 5.0 DECOMMISSIONING CRITERIA CS-HP-PR-006 Revision 6 EnergySolutions radiological engineers visited ARRR in_, California in May of201 l to gather physical and radiological data for characterization of the facility. Facility sketches, building drawings, and radiological characterization data for affected areas and potentially affected areas were obtained.
5.1 RA.DIONUCLIDES OF INTEREST The baseline radioactive material quantities were obtained from the estimate provided in NUREG/CR-1756, (Ref. 8.5). There are additional radionuclides repo1ted in the characterization smvey repo1i (Ref. 8.6) that were not included in NUREG/CR-1756 and, therefore, do not have estimated quantities. After reactor shut down and for some time after, 6°Co and, to a smaller extent, 65Zn are the principal contributors to radiation dose from the reactor core and vessel.
Most (> 95%) of the radionuclide invento1y at the facility is found in the reactor pool. Excluding fuel, this amounts to about 34 Ci of neutron activation and fission products at the time of shutdown. The radionuclides that potentially exist in the ARRR along with estimated inventories as of September 2012 are presented in Table 5-1.
Table 5-1: List of Expected Radionuclides Nuclide Half-Life Inventory (yr)
Ci 3H
- 12.28
<28.7 l°Be 1,510,000 7.25 X 10-7 14c 5,730 6.48 X 10-3 22Na 2.60 J.67 X 10-2 355 0.2392 2.99 X 10-4 36Cl 301,000 2.85 X 10-4 37Ar 0.0960 J.85 X 10-5 39Ar 269 2.61 X 10-7 4tca 103,000 l.l0x 10-4 4sca 0.446 2.54 X 10-3 46Sc 0.233 2.04 X 10-5 51Cr 0.0759 J.03 X 10-4 54Mn 0.86 2.26 X 10-3 s5Fe 2.73 0.385 59fe 0.1222 J.56 X 10-4 ssco 0.194 J.00 X 10-4 60Co 5.27 0.896 S9Nj 76,000 1.34 X 10-4 63Ni 100 1.75 X 10-2 65z n 0.67 0.203 Page 26 of 95
Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor Nuclide Half-Life (yr) 90Sr 29.l 93"'Nb 13.6
~
20,000 93Mo 4,000 9;Zr 0.175 95Nb 0.0961 9~
0.0099 lOSAg 4.51 X 10-6 108mAg 418 109mAg J.26 X 10-6 llOAg 7.8Ox 10-7 llOmAg 418 109Cd 1.27 m"'Cd 14.1 llS"'Cd 0.122 113mm 0.000189 113Sn 0.315 llPmsn 0.803 121Sn 0.00309 121msn 55 123Sn 0.354 12*sb 0.16 msb 2.76 m"'I'e 0.328 m"'I'e 0.157 134Cs 2.7 137Cs 30.17 133Ba 10.51 139Ce 0.377 1*1ce 0.0890 l44Ce 0.78 1s2Eu 13.48 1s4Eu 8.8 1ssEu 4.96 1s3Gd 0.659 181w 0.332 iasw 0.206 203Hg 0.128 204-yl 3.78 Inventory Ci 0.454 3.68 X 10-9 2.15 X 10-8 1.19 X 10-8 1.21 X 10-2 1.36 X 10-2 9.54x 10-7 1.39 X 10-2 0.159 J.76 X 10-3 1.19 X 10-2 0.878 0.120 J.O7 X 10-3 8.13 X 10-6 6.74 X 10-4 6.74 X 10-4 2.17 X 10-2 2.19x 10-5 2.82 X 10-5 2.40 X 10-4 8.51 X 10-3 3.00 X 10-3 3.69 X 10-5 7.31 X 10-4 9.16 X 10-7 0.283 6.17xlO-4 6.94 X 10-9 l.llxlO-8 0.185 1 59 0.161 J.73 X 10-2 8.93 X 10-5 l.12x 10-7 5.12 X 10-7 4.42 X 10-6 5.82 X 10-5 CS-HP-PR-006 Revision 6 Page 27 of 95
Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor Nuclide Half-Life (yr) 205J>b 15,3000,000 210p0 0.3791 238Pu 87.7 239l40Pu 24,110 241Pu 14.35 241Am 432.2 242cm 0.446 Inventory Ci 9.80 X 10-5 1.75 X 10-2 4.35 X 10-4 6.95 X 10-4 1.32 X 10-2 3.59 X 10-3 5.62 X 10-4 CS-HP-PR-006 Revision 6
- Argon is a gas that will dissipate and will have an inventory close to zero. Tritium migrates easily and most of it will dissipate. The tritium inventory without dissipation is shown with a Jess than sign.
The list of expected radionuclides provided above is based on the assumption that operation of the ARRR has resulted in the neutron activation of reactor core components and other integral hardware or strnctural members which were situated adjacent to, or in close proximity to, the reactor core during operations. Specific items which are considered to have been exposed to neutron flux that produced activation include materials composed of aluminum, steel, stainless steel, graphite, cadmium, lead, concrete and possibly others. In addition, the activity in spent resin was estimated based on analytical results and an estimated spent resin invent01y.
5.2 RADIOLOGICAL C RITERIA FOR LICENSE T ERMINATION The overall objective of the ARRR decommissioning is to remediate the facilities to a condition that co1Tesponds to a calculated dose to the public of less than 3 mrem/year from applicable pathways. It is assumed that the facilities may then be released for unrestricted use. A 25 mrem/year dose limit appears in 10 CFR 20.1402, Radiological Criteria for Unrestricted Use (Ref. 8. 7) but this was reduced to 3 mrem/year for projected State of California requirements.
The Derived Concentration Guideline Level (DCGL) is defined in MARSSIM (Ref. 8.8) as the radionuclide-specific concentration within a survey unit co1Tesponding to the release criterion.
The DCGL is dependent upon several factors including the radionuclides of interest, applicable dose pathways, area occupancy and the future use of the facility. DCGLs assume a relatively unifo1m level of residual radioactivity across the survey unit.
For the ARRR it was assumed that the site qualified for a screening analysis to develop the DCGLs, which is generally conservative. A screening analysis can be based on one or more of cmTently available screening tools: (I) building surface contamination and surface soil contamination screening criteria are presented in NUREG-1757, Appendix B (Ref. 8.9), or (2) screening levels derived using the software DandD, Version 2.0 (Refs. 8.9 and 8.10), for the specific radionuclides using the code default parameters. The assumed DCGLs for ARRR were based on 12% of the look-up tables in NUREG-1757, Appendix H (Ref. 8.9), which is equivalent to a potential dose of 3 mrem/year from residual contamination. Table 5.2 shows the NRC acceptable screening values and the State of California screening levels that are assumed to be acceptable, for the major radionuclides of concern at the ARRR.
Page 28 of95
Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor CS-HP-PR-006 Revision 6 Buildings with surface contamination below 12% of the screening tables in NUREG-1757, Appendix B will be assumed to be acceptable for release for unrestricted use, provided that the following conditions are met:
Residual radioactivity has been reduced to levels that are "as low as is reasonably achievable" (ALARA),
The residual radioactivity is contained in the top layer of the building surface (i.e., there is no volumetric contamination), and The fraction of removable surface contamination does not exceed 0.1.
Table 5-2: Acceptable License Termination Screening Values of Common Radionuclides for Building Surface Contamination1 Radionuclide Symbol NRC acceptable California acceptable screenin2 levels1 for screenin2 levels3 for unrestricted release unrestricted release (dpm/100 cm2) 2
( dom/100 cm2 )
Hydrogen-3 3H 1.2E+08 l.4E+07 (Tritium)
Carbon-14 14c 3.7E+06 4.4E+05 Sodium-22 22Na 9.5E+03 1.1E+03 Sulfur-35 3ss 1.3E+07 1.6E+06 Chlorine-36 36Cl 5.0E+05 6.0E+04 Manganese-54 54Mn 3.2E+04 3.8E+03 Iron-55 ssFe 4.5E+06 5.4E+05 Cobalt-60 6oCo 7.1E+03 8.8E+02 Nickel-63 63Ni 1.8E+06 2.2E+05 Strontium-90 90Sr 8.7E+03 1.0E+03 Technetium-99 99Tc 1.3E+06 1.6E+05 Iodine-129 1291 3.5E+04 3.4E+03 Cesium-137 137Cs 2.8E+04 2.8E+04 Iridium-192 192Ir 7.4E+04 8.8E+03 1 Screening levels are based on the asswnption that the fraction of removable surface contamination is equal to 0.1. For cases when the fraction of removable contamination is undetermined or higher than 0.1, users may assume, for screening pwposes, that 100% of swface contamination is removable, and therefore the screening levels should be decreased by a factor of 10. Altematively, users having site-specific data on the fraction ofremovable contamination (e.g., within the 10% to 100% range) may calculate site-specific screening levels using DandD Version 2.
Page 29 of95
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 30 of 95 2 Units are disintegrations per minute per 100 square centimeters (dpm/100 cm2). One dpm is equivalent to 0.0167 Becquerel (Bq). The screening values represent surface concentrations of individual radionuclides that would be deemed in compliance with 12% of the 0.25 mSv/yr (25 mrem/yr) unrestricted release dose limit in 10 CFR 20.1402. For radionuclides in a mixture, the sum of fractions rule applies; see 10 CFR Part 20, Appendix B, Note 4 for an explanation. Refer to NUREG-1757 for further information on application of the values in this table.
3 For the purposes of this estimate, it was assumed that license termination screening values of 12%
(3/25th) of the 10CFR20.1402 criteria would be acceptable to California (equivalent to 3 mr/yr above background).
5.3 FACILITY DESCRIPTION The ARRR facility includes the reactor building and support buildings, as well as several support buildings that were added since the reactor was constructed. Figure 4-4 provides a layout view of the ARRR buildings and Figure 4-2 provides an overhead view of the site.
5.3.1 Reactor Building The reactor building is made of steel with internal rooms built of fire resistant framing and sheetrock covering. An automatic sprinkler system covers the entire building. The building has airflow control from the standpoint that certain rooms are maintained at a positive pressure relative to the reactor room. The building as a whole is not sealed or contained and requires no air-locks. The reactor control room and certain offices are housed in a single building. The control room and offices are in areas where a fresh air intake is used to maintain the positive pressure relative to the reactor room. The 40 feet x 80 feet main building has a that can cover the entire area. The reactor tank is embedded in the floor, extending 22 feet below and one foot above the floor surface. A 20 inch thick by 80 inch high block wall made of normal density concrete encloses the reactor area above the floor level. The top of this shield is covered with an 11 inch thick wooden shield. The floor in the N-Ray area is covered with an industrial grade carpet.
Figure 4-5 provides a plan view of the reactor building, Figure 4-6 provides a cross section view of the Reactor Building and Figure 5-1 is a photograph of the Reactor and N-Ray Area with shielding in place.
5.3.1.1 Reactor Tank and Core The ARRR was designed and constructed by Aerojet General Nucleonics (AGN) in 1964.
Figure 5-6 shows the ARRR Core and Support Structure. The reactor fuel elements, reflector elements, control rods, control rod drive mechanisms, and control rod drive controls were purchased from General Atomics and were incorporated without any significant changes. A standard G ring core grid plate design was provided by General Atomics and manufactured by Aerojet. All other components were designed and constructed by Aerojet or their subcontractors.
Figure 5-2 shows the ARRR Core and Support Structure.
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 31 of 95 The basic nuclear design and core geometry follow General Atomics TRIGA reactor design characteristics. The original core was comprised of all aluminum clad fuel elements; however, new fuel elements are stainless steel clad. The original fuel elements are enriched to 8 weight %
U-235 and the stainless steel clad fuel elements are 12 weight % U-235. As of June 2004, twenty of the stainless steel clad elements have been added.
The principal characteristics of the ARRR are as follows:
(1)
Fuel: < 20% enriched U-235.
(2)
Moderator: zirconium hydride and water.
(3)
Reflector: demineralized water and graphite.
(4)
Coolant: demineralized water.
(5)
Control: 1 safety rod, 1 shim rod, 1 regulating rod, all boron carbide.
(6)
Structural material: aluminum and stainless steel.
(7)
Shield (principal materials): demineralized water, concrete, lead, and wood.
(8)
Active core dimensions: 19.44 inches diameter (nominal) by 14 inches high for aluminum clad elements and 15 inches high for stainless steel elements.
5.3.1.2 Experimental Facilities (1)
The N-Ray Facility (Figure 5-3) consists of two parts: a vertical beam tube and the radiography facility. Note that this image does not show the additional concrete and wood biological shielding that was added at a later time. The vertical beam tube is a hollow sealed tube, located adjacent to the core on the east side of the reactor, which extends from the floor of the reactor tank to above the reactor tank water surface. This vertical beam tube, by providing a path that does not contain the water that acts as a shield, allows a beam of neutrons from the core to reach the radiography facility located above the reactor.
The vertical beam tube consists of a two-section tapered tube with rectangular cross section with the weight supported directly by the bottom of the reactor tank. The vertical beam tube has a total length of approximately 23 feet. The top of the beam tube terminates at the bottom of the reactor bridge structure. The external dimensions of the beam tube are about 8 inches by 10 inches near the base and tapers to 22 inches by 34 inches at the top. The top of the vertical beam tube is supported laterally at the top of the pool.
The lower 48 inches of the lower section of the vertical beam tube is filled with graphite for moderation of fast neutrons. The upper section of the vertical beam tube is filled with helium which is a better medium for collimated neutrons than air which scatters the neutrons. Both the upper and lower sections of the vertical beam tube are
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 32 of 95 equipped with fill and drain lines that are used to remove water or purge the vertical beam tube.
The lower 84 inches of the vertical beam tube is covered with lead for gamma shielding. This lead shield is 3 inches thick on the reactor side and 1 inch thick on the other three sides. The lead is protected from the pool water by welded sheets of aluminum. All components contacting the pool water are fabricated from aluminum or stainless steel.
The vertical beam tube includes an upper open/close pneumatically operated shutter and a lower electrically operated shutter mechanism that offers a selection of 5 aperture settings to provide varying depths of field or resolution. The lower aperture is located near the bottom of the vertical beam tube just above the graphite.
The neutron radiography facility is integrated into the shielded enclosure directly above the vertical beam tube. The shielded enclosure consists of 20 inch thick concrete block shielding stacked to a nominal height of 80 inches above the floor that surrounds the entire top of the reactor water tank. The neutron radiography facility is supported by 10 inch steel I beams that transmit the weight of the shielding to beams imbedded in the floor of the reactor building. This shielding supports the 11 inch thick wood (fir) beams that cover the reactor enclosure. This shielding provides operating personnel additional shielding.
This shielding enclosure is penetrated at the north and south ends on the east side of the reactor by the neutron radiography facility. Access to the top of the vertical beam tube is through openings on both the north and south ends with cross sectional dimensions of approximately 37 inches wide by 18 inches high. The facility was designed to allow the neutron radiography of contained detonating cords having lengths in excess of 25 feet. Concrete blocks in the shield structure may be moved as necessary to accommodate taller objects.
The top of the vertical beam tube is covered by a movable radiation shield called the neutron beam catcher. The beam catcher shield is wood that is 48 inches by 47 inches by 16.5 inches and has wheels that roll on tracks attached to the tunnel. The wheels allow the beam catcher shield to be rolled to the south end to radiograph large items on the north end. The beam catcher shield reduces the radiation level due to neutrons and gammas within the reactor room and at the exclusion area fencing.
Figure 5-1 is a photograph of the radiography facility with biological shielding in place.
(2)
The Graphite Thermal Column (Figure 5-3) is a large block of graphite, encased in aluminum, containing five rows of seven vertical holes through the graphite block.
The vertical holes allow specimens to be inserted into the graphite block for irradiation. The five rows of irradiation holes (A through E) are six inches apart with each row at an increasing radius from the core. The increasing radius of each row
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 33 of 95 allows samples being irradiated to be subjected to different ratios of thermal to fast neutrons.
There are seven irradiation holes in each row. The irradiation holes are 1.5 inches in diameter, similar to the reactor core grid plate, which allows the same capsules or devices that are inserted into the core to be inserted into the graphite thermal column.
The thermal column graphite block measures 4 feet along the radial axis of the core and is 2 feet wide and 2 feet deep. It is located on the south side of the reactor and positioned adjacent to the core. The thermal column is positioned using tapered pins and is bolted to the bottom of the reactor pool tank. Installation and removal of the whole assembly is accomplished with the facility crane and remote handling tools.
Two irradiation holes in the thermal column are configured for specific tasks:
One irradiation position in the first (A) row is fitted with an aluminum tube, identical in design to the glory hole (described later), that extends to the top of the reactor water tank above the wood (fir) block shield. Material to be irradiated is lowered through the tube into the thermal column. This tube has a rotating motor to slowly rotate the sample and thus provide an evenly distributed irradiation to the sample. A shield plug is placed in the top of the tube to reduce gamma scattering to acceptable levels and to prevent Argon-41 from coming up the tube.
A second position in the first (A) row is fitted with a detector calibration system. Small fission detectors can be calibrated against a standard in this facility.
A third position includes a one inch diameter neutron beam tube which can be located between the thermal column and N-ray tube and which extends to the area above the top reactor shield. This tube is used for the source of neutrons for the N-gage device.
The thermal column structure is also used to mount other experimental facilities. Four slotted beams, two on each side, are provided to allow experiments to be attached directly to the thermal column. Extensions of these beams allow experiments to be placed immediately adjacent to the reactor core.
(3)
The Glory Hole Facility is an aluminum tube, 1.5 inches in diameter, which will fit into any fuel element hole. The hollow tube extends from the lower grid plate to above the top of the wood (fir) shield on top of the reactor water tank. The tube is not filled with water and is used to lower material to be irradiated through the tube into the core region. The glory hole will accept capsules with a maximum diameter of 1.35 inches.
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 34 of 95 Technical Specifications allow a maximum of one glory hole facility that may be installed in selected locations in any of the seven rings in the core grid plates. At the ARRR, the glory hole is typically installed in the F-2 position of the core.
The glory hole may be used with or without an internal shield plug that reduces the radiation streaming at the top of the reactor water pool in the vicinity of the CRDs.
Technical Specifications require that the glory hole be purged with CO2 to prevent the formation of excessive amounts of 41Ar during reactor operation. When operated with a shield plug, the glory hole is purged prior to each insertion of the shield plug. When operated without a shield plug, the glory hole is purged continuously when the reactor is operating. Additionally, when operated without a shield plug, the installed gas sampling system must be selected to sample in the immediate vicinity of the glory hole so that corrective action can be taken to prevent the release of gaseous activity in excess of 10 CFR 20 limits.
(4)
The Central Core Irradiation Facility is a hexagonal section that can be removed from the center of the upper grid plate to allow insertion of specimens into the core region of highest flux. Use of the central core irradiation facility requires prior relocation of the central fuel element and the six elements from the B-ring. Technical Specifications limit the size of the central core irradiation facility to 16 square inches.
The facility will accommodate specimens up to about 4.4 inches in diameter.
(5)
The Triangular In-Core Irradiation Facilities consist of two sections cut out of the upper grid plate, each of which encompasses one D-ring and two E-ring holes. When fuel elements are placed in these locations, their lateral support is provided by special aluminum pieces. With the aluminum spacers removed, each of these triangular sections allows the insertion of circular experiments to a maximum of 2.35 inch diameter or triangular experiments to a maximum of 3.0 inches on a side.
(6)
The In-Core Irradiation Capsules (Figure 5-4), which are approximately the same size and shape as a fuel element, are used to irradiate samples and can be used in any open position of the core or in the graphite thermal column. The capsules are usually sealed at the top by a gasket and threaded fitting but also have provisions for bringing instrumented tubes to the surface.
In-core irradiation capsules are inserted and removed from the core using the fuel element handling tools. A transfer shield is used to transport the capsule within the ARRR building.
The capsules are designed to have a maximum inner void volume of 34 cubic inches in the active fuel region.
(7)
The Pneumatic Transfer Facility is designed to quickly transfer individual specimens into and out of the reactor core. The specimens are placed in a small polyethylene holder, "rabbit," which in turn is placed into the receiver. The rabbit travels through aluminum tubing to the terminus at reactor core centerline and then returns along the same path to the receiver. Directional CO2 flow moves the rabbit
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 35 of 95 between receiver and terminus. A solenoid valve directs air flow using a timer to regulate the exposure of the sample. A manual control, capable of overriding the automatic timer control, is also provided.
The pneumatic transfer facility may be located in any reactor core position. When installed, the facility is operated with dry CO2 and exhausted through a filter ventilation system, which is monitored for radioactivity. The in-core portion of the transfer facility has a maximum void volume of 34 cubic inches so that the effects on reactivity are similar to other experiments that are placed in the active core.
The pneumatic transfer facility is not currently installed in the reactor water tank because ARRR does not currently use a pneumatic transfer facility and most of the parts to this system are no longer on site.
(8)
The Beam Port was never finished but the ARRR was designed to facilitate future installation of a horizontal beam port. The ARRR reactor tanks concrete embedment includes one penetration consisting of one 24 inch outside diameter pipe about 13 feet long that butts up against the outside of the reactor tank on the center line of the core.
The pipe sleeve was provided so that a horizontal beam port could be installed without having to break through the concrete around the tank. However, the beam port facility was never installed and the reactor tank wall is not cut open at this location.
5.3.1.3 Coolant System The ARRR cooling system is comprised of three basic parts: the reactor water tank, the cooling system, and the demineralizer system. The pool water provides convection cooling, neutron and gamma shielding and neutron moderation. The cooling system provides heat removal to a cooling tower via a heat exchanger. A new cooling tower was installed several years ago and the old cooling tower with redwood louvers was retained as a backup for the new tower. The demineralizer system maintains the purity of the water. A fourth component is the reactor water tank makeup system. This system is comprised of a small ion exchange column connected to the city water supply and redundant level control valves for the reactor water tank. Figures 5-21 and 5-22 show the locations of the demineralizers, the heat exchanger and the cooling towers.
5.3.1.4 Radioactive Waste and Radiation Protection The ARRR generates very little radioactive waste. Most of the induced radioactivity is short half-life material and can be stored until the radioactivity decays. Radioactive waste is normally stored in the Radioactive Material Storage Room. The radioactive materials normally stored in the room include contaminated Personal Protective Equipment, radioactive sources, filters, contaminated or low level irradiated materials removed from reactor during repairs and modifications, and miscellaneous contaminated or irradiated items.
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 36 of 95 5.3.1.5 Radioactive Material Storage Area The Radioactive Material Storage Area is a locked room with restricted access and it is used to store contaminated demineralizers, contaminated Personal Protective Equipment, radioactive sources, used filters, contaminated or irradiated materials removed from the reactor during repairs and modifications, and miscellaneous contaminated or irradiated items. The floor in the room is covered with what appears to be 8-in by 8-in asbestos floor tiles.
5.3.1.6 Office Supply Room The Office Supply Room is located against the of the reactor building as shown on the general layout drawing in Figure 4-4. It is used to store office supplies and has a concrete floor and no false ceiling. The area was previously a tagging room that used acetone and Gd(NO3)3.
5.3.1.7 Machine Shop The Machine Shop is currently little utilized but it was used to machine repair parts and parts for new experimental facilities. There is a box of unused 8-in x 8-in asbestos floor tiles on the floor in the room and the floor is covered with similar tiles. The shop was reported to have been used to machine contaminated or activated parts in the distant past.
Figure 5-9 is a photograph of a portion of the Machine Shop.
5.3.1.8 Control Room The Control Room contains the reactor operating console and lies at the end of the utility trench. The floor is carpeted; there is a false ceiling, a viewing window into the N-Ray area and a locked door entry into the N-Ray area. No records indicating radiological or chemical use or storage were identified.
5.3.1.9 Chemistry Lab The Chemistry Lab is a small room on the that contains two work bench cabinets, a fume hood and two sinks, the Cold Sink which drains to the sewer and the Hot Sink which drains to an outdoor waste holdup and sampling tank. The regular sink has overflowed with tap water and flooded the Chemistry Room and the adjacent Preparation Lab and flowed down the stairs into the Radiography area before the water was shut off. The floor in the room is covered with what appears to be vinyl 12-in by 12-in floor tiles.
Figure 5-6 is a photograph of a portion of the Chemistry Lab including the Cold Sink.
5.3.1.10 Preparation Lab The Preparation Lab is a small room that contains a work table, marble weighing table and non-radioactive waste disposal drum. The floor in the room is covered with what appears to be vinyl 12-in by 12-in floor tiles.
Figure 5-7 is a photograph of a portion of the Preparation Lab.
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 37 of 95 5.3.1.11 N-Ray Gauge Office The N-Ray Gauge Office is a small room on the across a hallway from the Preparation lab that has a desk and work table for preparing the N-Ray gauges prior to use. The hallway and office floors are covered with what appears to be 8-in by 8-in asbestos floor tiles.
The N-Ray Gauge Office has a doorway to the hall and a doorway that accesses the top of the bioshield.
5.3.1.12 Storage Area The Storage Area is an open topped portion of the that is next to the N-Ray area. This area contains the control room HVAC system, a storage area for spare mechanical parts of all sorts, a storage area for irradiated items, and wall mounted cabinets just off the mezzanine and over the bioshield that are used to store reactor pool tools. The floor in the area is mostly bare wood but a small portion is covered with room is covered with what appear to be 8-in by 8-in asbestos floor tiles.
Figure 5-8 is a photograph of the northern portion of the Sheet Metal Fabrication Area and Figure 5-9 is a photograph of the Sheet Metal Fabrication Area and HVAC System.
5.3.1.13 Sheet Metal Fabrication Area The Sheet Metal Fabrication Area is an open topped portion that is just an extension of the Storage Area. It is currently a storage area for spare mechanical parts and the floor is covered with what appear to be 8-in by 8-in asbestos floor tiles.
Figure 5-10 is a photograph of the Storage Area.
5.3.1.14 Instrument Calibration Area The Mezzanine Storage Area is an open topped portion that is next to the Chemistry Lab and Preparation Lab. This area is used for instrument calibrations and coating of Exposure Trays. It contains a drawing table used for reviewing drawings and calibrating instruments at fixed distances from sources, a coating mixer, drawing storage drawers and files, and miscellaneous other equipment and HVAC components. The floor is covered with what appear to be 8-in by 8-in asbestos floor tiles.
Figure 5-11 is a photograph of the Instrument Calibration Area.
5.3.1.15 Electronics Lab The Electronics Lab is a small room that is next to the Instrument Calibration Area. This area contains spare electrical parts of all sorts and the floor is covered with what appear to be 8-in by 8-in asbestos floor tiles. No records indicating radiological use or storage were identified. Records indicate that there may have been a PCB oil spill in the room that was cleaned up immediately after the spill.
Figure 5-12 is a photograph of the Electronics Lab.
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 38 of 95 5.3.1.16 Offices and Restroom Areas The Restrooms and Offices in the reactor building are as shown on the general layout in Figure 4-4. Rooms 14 and 15 are restrooms with what appears to be vinyl 12-in by 12-in floor tiles, false ceilings and drains that connect to the city sewer system. Room 17 is the General Managers Office, Room 18 is a hallway and the Business Office, and Room 19 is the Accounting Office. These offices have floors covered with industrial grade carpet and they have false ceilings. No records indicating radiological or chemical use or storage were identified.
5.3.2 Building Addition 1 Building Addition 1 is a 45 foot by 60 foot steel structure with internal rooms built using fire resistant framing and a double layer or sheetrock. An automatic sprinkler system covers the entire building. The building as a whole is not sealed or contained and requires no air-locks. This area provides essential support functions for the N-Ray operation. This building contains the shipping and receiving, N-Ray Setup Area, Counting Room, office space, film viewing room for customers, Quality Control Room, Dark Room, Explosive Store Room & Safe, and the Film Storage Room as shown on the general layout in Figure 4-4.
5.3.2.1 Shipping & Receiving The Shipping and Receiving area is sometimes referred to as the garage as it has a garage type rollup door. This area has large metal shelves and a high ceiling, is approximately 25-foot by 14.5-foot by 13 foot tall. It includes a bare concrete floor and the doorway into the Film Storage area. No records indicating radiological use or storage were identified.
Figure 5-13 is a photograph of the Shipping & Receiving area.
5.3.2.2 N-Ray Setup Area The N-Ray setup area includes a large portion of the Building Addition 1 structure, approximately 38.5 foot by 34-foot. The floors are bare concrete, the ceilings are over 13 feet in height and there are doorways to the outside, and operating areas. This area also includes several heavy duty work tables that are used to setup the exposure trays for N-Ray radiography work.
No records indicating radiological use or storage were identified.
Figure 5-14 is a photograph of the N-Ray Setup Area.
5.3.2.3 Film Storage Room The Film Storage Room is a 9.8-foot by 6-foot by 8-foot tall room located at the end of the area as shown in Figure 5-13. There is also space between the roof of the Film Storage Room and the ceiling of the Building 1 Addition that is used for temporary storage of miscellaneous items. This room was used as a second explosive storage safe when two non-compatible explosives needed to be stored in-house at the same time.
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 39 of 95 5.3.2.4 Explosive Storage Safe The Explosive Storage Safe is a 9.8-foot by 6-foot by 8-foot tall room located at the of the Shipping & Receiving area as indicated in the layout drawing shown in Figure 4-4.
Some of the items that are radiographed contain explosive initiators and that are temporarily stored in this room before and after radiography. No records indicating radiological or chemical use or storage were identified.
5.3.2.5 Offices and Film Handling Areas There is a hallway, Office Space area, a Customer Viewing Room, a Quality Control Room and a Dark Room located along the eastern wall of the Building 1 Addition. The Office Space area is a 16-foot by 13-foot by 8-foot tall room with carpeted floor and drywall finished walls and ceiling that includes desks and work tables for staff use as shown in Figure 5-15. The film viewing room for customers (Customer Viewing Room) is a 16-foot by 10-foot by 8-foot tall room with carpeted floor and drywall finished walls and ceiling that includes facilities for clients to view completed radiographs as shown in Figure 5-16. This room also has a closet that holds the fixer sump and backup replenishment tanks along with a water heater. The Quality Control Room is a 16-foot by 9-foot by 8-foot room with tiled floor and drywall finished walls and ceiling. This room includes film processing equipment, facilities for temporary storage of radiographs, and equipment for viewing radiographs as shown in Figure 5-17. The Dark Room is a 16-foot by 11-foot by 8-foot tall room with vinyl tiled floor and black drywall walls and ceiling, as shown on the general layout in Figure 5-1. This room is utilized for film processing and it contains a sump that receives overflow from the developer along with running water. The sump water is passed through a filter and then steel wool. The steel wool collects excess silver that is then removed by an independent contractor for processing. The processed water passes down the sewer. Activated silver was present from neutron activation of the film emulsion and there is a potential for plating out of silver in the sewer pipes. There were no other indications of radiological use or storage.
5.3.2.6 Computer and Counting Room The Computer and Counting Room is an 11-foot by 7.5-foot room located at the southwest corner of the N-Ray Setup area as indicated in the layout drawing shown in Figure 4-4. This room has a shielded cave with sodium iodide detector and instrumentation and supplies for counting samples as well as exempt sources for performing instrument response checks.
Figure 5-18 is a photograph of the Computer and Counting Room.
5.3.3 Tagging Area Building The Tagging Area Building is a 20 foot by 40 foot steel structure with internal rooms built of fire resistant framing and sheetrock covering except for the wall toward the Reactor Building which is a cinderblock wall. An automatic sprinkler system covers the entire building. The building as a whole is not sealed or contained and requires no air-locks. It contains the Tagging Area, the Tagging Area Back Room, a Safe, and an entry vestibule as shown on the general layout in Figure 4-4.
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 40 of 95 5.3.3.1 Tagging Area The Tagging Area includes a 35-foot by 19-foot portion of the Tagging Area Building as shown in Figure 4-4. The floors are bare concrete, the ceiling is over 12 feet in height and there are doorways to the outside, and operating areas. This area also includes many heavy duty work tables that are used to setup the exposure trays for N-Ray radiography work. No records indicating radiological use or storage were identified.
Figure 5-19 is a photograph of the Tagging Area with the entry vestibule shown at the back.
5.3.3.2 Tagging Area Back Room The Tagging Area Back Room is a portion of the tagging operation that was walled off and contains several pieces of equipment used in the tagging operations. No records indicating radiological use or storage were identified.
Figure 5-20 is a photograph of the Tagging Area Back Room.
5.3.3.3 Safe The safe is 6.5-foot by 7-foot by 3-foot tall locked room that is used to if there is any on site.
5.3.3.4 Entrance Hallway The Entrance Hallway is a by 4.5-foot by 8-foot by 8-foot tall room that connects to the outside, the Reactor Building and the Tagging Area as shown on the general layout in Figure 4-4.
It has a concrete floor with drywall on walls and ceiling. No records indicating radiological or chemical use or storage were identified.
5.3.4 Demineralizer Building The Demineralizer Building is a 7.5-foot by 3.6-foot by 7-foot tall small metal structure on the of the Reactor Building as shown in general layout Figure 4-4. It contains the demineralizer system which includes a pump, demineralizer bed, filters, gauges, valves and typically a used resin bed left in the building for decay prior to removal of the resin for disposal.
5.3.5 Heat Exchanger Building The Heat Exchanger Building is a 12-foot by 4-foot by 7-foot tall metal structure built with a shallow concrete basin for the floor. It is located at the east side of the Reactor Building as shown in Figure 4-4. It contains a stainless steel shell and tube heat exchanger, a primary side stainless pump with 5-HP motor, a flow switch and various valves. This building also contains a water monitor (radiation detector) and check source.
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 41 of 95 5.3.6 Cooling Towers There are two cooling towers located close to the Heat Exchanger Building. The old cooling tower is currently a backup system in case the current tower is out of service for any reason. The old tower is approximately 8-foot by 16-foot by 7-foot tall with a painted steel shell, blower on top and redwood vanes on the interior as shown in the photograph in Figure 5-21. The new tower is approximately 6-foot by 5.5-foot by 8-foot tall with a painted steel shell, blower on top and galvanized steel packing on the interior as shown on Figure 5-22.
Located in the area between the Heat Exchanger building and the Backup Cooling Tower is the heat exchanger secondary side (iron and bronze) pump with 5-HP motor, piping and valves. No records indicating radiological use or storage were identified.
5.3.7 Maintenance Office Building 5.3.8 The Maintenance Office Building is a 12.5-foot by 9.5-foot by 7-foot tall wood structure with metal roof on the of the High Bay Building. The remaining structure consists of concrete and lead. Compressor Building The Compressor Building is a 14-foot by 8-foot by 8-foot tall metal structure on the south side of the Operations Building. It contains two conventional piston type air compressors and three oil-filled vacuum pumps. No records indicating radiological use or storage were identified.
5.3.9 Chemical Shed The Chemical Shed is a 6.5-foot by 4-foot by 6-foot tall metal structure mounted on wooden skids, located the of the Operations Building as shown on Figure 4-4. No records indicating radiological use or storage were identified.
5.3.10 Class 1.1 Explosive Storage Container Class 1.1 Explosive Storage Container is a 6-foot by 4-foot by 4-foot tall metal box on skids located on the northeast corner of the Storage Building. It has not been used. No records indicating radiological or chemical use or storage were identified.
5.3.11 Storage Building The Storage Building also known as the forklift garage is an un-insulated 24 foot by 26 foot steel structure built of fire resistant framing and metal walls and ceiling. The Storage Building is not connected to any other buildings and it has a garage door that opens to the and a personnel door that opens to the
. It is used for forklift parking, equipment and supply storage, and fabrication area. The interior of this building is shown in Figure 5-23.
5.3.12 Waste Storage Sump The former steel Waste Storage Tanks have been removed and disposed of and new polypropylene tanks have been installed in a secondary containment. The below grade Sump is located on the south end of the Reactor Building as shown on Figure 4-4.
Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor 5.3.13 Land Area CS-HP-PR-006 Revision 6 All of the 0.9 acres that make up the site are fenced in with a chain link fence. The fence has a tmck gate that allows access to the Shipping and Receiving area and a personnel gate that enters the Reactor Building near the Control Room. Most of the outside area is paved as can be seen in Figure 4-2, Aerial View of ARRR Site. There are seepages of groundwater upward through cracks in the pavement on the n01t h end of the site that are collected and drained by a ditch just outside the no1t h site fence.
5.4 RELATION OF THE ARRR TO OTHER TRIGA REACTORS The design of the ARRR fuel is similar to those of approximately 50 TRI GA type reactors cunently operating worldwide with 24 in the United States.
The reactor and associated equipment will be decommissioned by removal of the core, removing the water from the vessel, and removing activated and contaminated materials from the reactor.
Once this has been completed, the structure will be surveyed using a license temiination type smvey with any additional decontamination perfo1med in conjunction with the smveys.
5.5 O UTSIDE AREAS There is no histo1y of any spills of radioactive materials outside the identified building process areas. Based on cmTent smvey data, it is not anticipated that any soil remediation will be required. There is a discharge from the Reactor Building to the sanita1y sewer system which mns near the building.
The ARRR is between two watersheds:
and
. The smTounding area slopes gently downward to the north and to the south. The site st01m water mnoff is to the n01th and west toward Creek is the principal local drainage, with Creek an Creek being tributai.
Creek meanders n01thward through Bayneai*
the facility.
an and ultimately joins
, which discharges into Suisun There is a drainage ditch located just past the site boundaiy to the no1t h of The sanita1y sewer and nearby st01m sewers will be smveyed at accessible locations downstream of the site. In addition, soil sampling and license te1mination smveys of paved ai*eas and m1paved areas will be perfo1med in ai*eas adjacent to the ARRR in accordance with cmTent regulato1y requirements.
Page 42 of95
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 43 of 95 Figure 5-1: Reactor & N-Ray Area with Shielding in Place
Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor Figure 5-2: ARRR Core and Support Structure CS-HP-PR-006 Revision 6 Page 44 of 95
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 45 of 95 Figure 5-3: ARRR Reactor Tank Cutaway and N-Ray Facility Reactor Core Thermal Column
~*.!:."~
Radiation Beam catcher Shield Neutron Radiography Facility
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 46 of 95 Figure 5-4: ARRR In-Core Irradiation Capsule LEAD BALLAST SEAL IRRADIATION VOLUME
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 47 of 95 Figure 5-5: ARRR Machine Shop
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 48 of 95 Figure 5-6: ARRR Chemistry Lab
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 49 of 95 Figure 5-7: ARRR Preparation Lab
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 50 of 95 Figure 5-8: ARRR Sheet Metal Fabrication Area
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 51 of 95 Figure 5-9: ARRR Sheet Metal Fabrication Area & HVAC Unit
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 52 of 95 Figure 5-10: ARRR Storage Area
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 53 of 95 Figure 5-11: ARRR Instrument Calibration Area
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 54 of 95 Figure 5-12: ARRR Electronics Lab
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 55 of 95 Figure 5-13: ARRR Shipping & Receiving
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 56 of 95 Figure 5-14: ARRR N-Ray Setup Area
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 57 of 95 Figure 5-15: Office Space
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 58 of 95 Figure 5-16: Customer Viewing Area
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 59 of 95 Figure 5-17: Quality Control Room
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 60 of 95 Figure 5-18: Computer and Counting Room
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 61 of 95 Figure 5-19: Tagging Area
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 62 of 95 Figure 5-20: Tagging Area Back Room
Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor Figure 5-21: Backup Cooling Tower CS-HP-PR-006 Revision 6 Page 63 of 95
Aerotest Radiography and Research Reactor Revision 6 Page 64 of 95 Figure 5-22: Main Cooling Tower
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 65 of 95 Figure 5-23: Storage Building
Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor Figure 5-24: Waste Storage Tanks CS-HP-PR-006 Revision 6 Page 66 of 95
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 67 of 95 6.0 ESTIMATION METHODS The estimated cost to decommission the ARRR is $3,080,126 in 2018 dollars. This section of the cost estimate report provides an overview of the considerations and factors that influenced the DCE. Table 6-1 provides a summary of the costs associated with each area of the facility.
Table 6-1: Decommissioning Cost Summary - ARRR 6.1 COST MODIFYING FACTORS There are modifying factors that significantly affect the overall cost for remediation. One of these factors is an adjustment for productivity related to personnel protection requirements and working temperatures. The degree of protection required depends upon the extent of contamination and specific activities to be performed in a given area. As the level of personnel protection increases, so does the impact on individual productivity and task duration.
Adjustments were made to account for the implementation of personnel protective measures where applicable. This estimate used the standardized levels of personnel protection described in Table 6-2. The Productivity Factors related to these levels of personnel protection are provided in Table 6-3 for Light Work and in Table 6-4 for Heavy Work.
Operation LaborHrs
- Labor, travel,living Equip,contracts, supplies Radwasteship&
disposal Total TRIGAReactor 6,147
$652,802
$121,135
$446,379 1,220,316 TRIGAShielding&NRayComponents includedabove includedabove
$30,343
$102,660 133,003 Buildings 2,454
$260,576
$80,630
$99,345 440,551 OutdoorAreas 477
$50,634
$54,528
$102,629 207,791 DecommissioningPlanning 240
$26,221
$0
$0 26,221 CharacterizationSurveys 409
$48,837
$2,676
$0 51,514 FinalSurveys 1,820
$210,998
$12,145
$0 223,142 Planning,Training,&Mobilization 404
$42,027
$0
$0 42,027 Oversight&Licensing 916
$119,535
$0
$0 119,535 Subtotals 12,867
1,411,631 301,456 751,014 2,464,100 25%Contingency 616,025 Total 3,080,126
Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor CS-HP-PR-006 Revision 6 Table 6-2: Personnel Protective Equipment Protection Summary Protection Level Personnel Protective Equipment Requirement Level A:
The highest available level of respirato1y, skin, and eye protection The highest level of respiratory protection, but less skin Level B:
protection than Level A. Level B is the minimum level recommended for initial site entries, or for other ent1y conditions dealing with unknown hazards.
Level C:
The same level of skin protection as Level B, but a lower level of respirat01y protection.
Level D Modified:
Skin protection silnilar to or the same as Level C, without respirato1y protection.
Level D:
Standard work unifo1m suitable for constrnction work: no respiratory protection and 1ninimal skin protection.
Page 68 of 95
Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor Table 6-3: Hazardous and Toxic Waste Productivity Factors: Light Work Variables U/M Level A Level B Level C Level D Modified T<70 70<T T>85 T<70 70<T T>85 T<70 70<T T>85 T<70 70<T T>85 A. Standard losses Min.
160 160 160 140 140 140 128 128 128 76 76 76 B. Scheduled/heat stress breaks Min.
60 90 120 43 65 86 35 63 101 30 47 63 C. Dexterity losses Min.
78 69 60 74 69 64 55 51 44 4
4 3
D. Total time lost per 8-hr. WD Min.
298 319 340 257 274 290 218 242 273 110 127 142 E. Productivity time per 8-hr. WD Min.
182 161 140 223 206 191 262 238 207 370 353 338 F. Productivity time on clean site Min.
430 430 430 430 430 430 430 430 430 430 430 430 G. HTW Productivity Factor 0.42 0.37 0.33 0.52 0.48 0.44 0.61 0.55 0.48 0.86 0.82 0.79 Notes:
CS-HP-PR-006 Revision 6 Level D T<70 70<T T>85 32 32 32 30 33 44 5
5 5
67 70 81 413 410 399 430 430 430 0.96 0.95 0.93 Standard delays account for all time losses independent of temperature variations. They include safety meetings, instrnctions, putting on and talcing off of PPE, decontamination, switching air supply/filters, monitoring delays, and cleanup.
Scheduled/heat stress breaks acconnt for all paid rest periods pe1* workday.
Dexterity losses are based on subjective opinions of the percentage that PPE slows do'wn a 1101mal worker because of factors such as discomfort, chunsiness, weight, and restricted breathing and communication. The number of minutes actually worked is reduced by the percentage representing the average response for that particular PPE level.
Values for A, B, and C were derived by averaging the survey responses for each PPE level. Responses that varied greatly from the average were subject to omission at the author's discretion.
Total paid time = 480 minutes.
50-minute delay on clean site = IO-minute safety meeting and instrnctions + IO-minute cleanup + 30-minute breaks.
Calculations:
D= A+B+C U/M = unit of measm*e E = 480 -D WD = workday F = 480 - 50 Min. = minutes G = EIF T = temperattu*e (Fahrenheit)
Level A-protection is used in extreme emergency situations onlv. Productivitv factors for Level A should be used with caution because thev were extrapolated from 2 data points.
Page 69 of95
Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor Table 6-4: Hazardous and Toxic Waste Productivity Factors: Heavy Work Val'iables U/M Level A Level B Level C Level D Modified T<70 70<T T>85 T<70 70<T T>85 T<70 70<T T>85 T<70 70<T T>85 A. Standard losses Min.
220 220 220 204 204 204 135 135 135 76 76 76 B. Scheduled/heat stress breaks Min.
60 105 150 50 75 123 64 131 178 30 90 165 C. Dexterity losses Min.
80 62 44 52 46 35 44 34 26 28 24 18 D. Total time lost per 8-hr. WD Min.
360 387 414 306 325 362 243 300 339 134 190 259 E. Productivity time per 8-hr. WD Min.
120 93 66 174 155 118 237 180 141 346 290 221 F. Productivity time on clean site Min.
430 430 430 430 430 430 430 430 430 430 430 430 G. HTW Productivity Factor 0.28 0.22 0.15 0.40 0.36 0.27 0.55 0.42 0.33 0.80 0.68 0.51 Notes:
CS-HP-PR-006 Revision 6 LevelD T<70 70<T T>85 28 28 28 30 45 60 11 10 10 69 83 98 411 397 382 430 430 430 0.96 0.92 0.89 Standard delays account for all time losses independent of temperature variations. They include safety meetings, instructions, putting on and taking off of PPE, decontamination, switching aii: supply/filters, monitoring delays, and cleanup.
Scheduled/heat stress breaks account for all paid rest periods per workday.
Dexterity losses are based on subjective opinions of the pe1*centage that PPE slows down a n01mal worker because of factors such as discomfort, clumsiness, weight, and restricted breathing and communication. The number of minutes actually worked is reduced by the percentage representing the average response for that particular PPE level.
Values for A, B, and C were derived by averaging the smvey responses for each PPE level. Responses that varied greatly from the average were subject to omission at the author's discretion.
Total paid time = 480 minutes.
50-m.inute delay on clean site = 10-m.inute safety meeting and instructions + 10-m.inute cleanup + 30-minute breaks.
Calculations:
D= A+ B + C U/M = mi.it of measm*e E = 480 - D WD = workday F = 480 - 50 Min. = minutes G = E/F T = temperature (Fahrenheit)
Level A-protection is used in extreme emergency situations only. Productivity factors for Level A should be used with caution because they were extrapolated from 2 data points.
Page 70 of 95
Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor 6.2 RADIOACTIVE WASTE VOLUME ESTIMATES CS-HP-PR-006 Revision 6 The volume of radioactive waste requiring treatment and/or disposal can be a ve1y significant factor due to the high costs of radioactive waste disposal. For the ARRR decommissioning, the cost for radioactive waste processing, shipping, and disposal is anticipated to be about 31 % of the total decommissioning cost. This is a typical fraction for relatively clean radioactive facilities. Radioactive waste volume estimates that result from decommissioning are discussed in the following section. In 2017 a significant amount legacy waste (total volun1e of 1,920 cubic feet) was shipped offsite for disposal, which reduced the waste volume, transportation and disposal costs compared to previous estimates.. Table 6-5 provides a volume summaiy for each area of the ARRR. Infonnation about the volume of most waste items is provided in Appendix A-12.
Table 6-5: ARRR Unprocessed Radioactive Waste Summary*
Generated Decon Direct Clive Clive Clive Total Disposal Disposal Disposal Disposal Volume Volume Volume Volume Area Descliotion (ft"3)
(ft"3)
(ft"3)
(ft"3)
TRIGA Reactor 64 0
349 413 TRIGA Bioshield & N-Ray Components 0
0 285 285 Buildings 34 62 456 552 Outdoor Areas 6
0 708 714 Pool Water 5
5 6
16 Lead 13 0
13 26 TOTALS 122 67 1817 2006 6.3 RADIOACTIVE WASTE DISPOSAL C OSTS A significant po1i ion of the overall decommissioning cost is generally attributed to the transport, treatment and disposal of radioactive waste. This cost estimate includes radioactive waste processing that is followed by disposal and direct radioactive waste disposal at Clive, Utah. The following sections describe the pricing for each option.
6.3.1 Clive, Utah Radioactive Waste Direct Disposal Costs The costs to transpo1i low level radioactive waste to the Clive, Utah disposal site are based on a transpo1i distance of 609 miles, at a rate of $5.40 per mile. The cost to dispose of the waste at the Utah site is based on a disposal fee of $131 per cubic foot for low level waste debris and
$253 per cubic foot for transp01iation and disposal of demineralizer resin from the pool water clean-up and lead that must be encapsulated prior to bmial.
6.3.2 Radioactive Waste Processing and Bmial Costs The costs to transpo1i waste to a volume reduction/waste processing facility in Oak Ridge or Elwin, Tennessee are based on transpo1i distances of 2437 and 2561 miles respectively, at a rate Page 71 of 95
Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor CS-HP-PR-006 Revision 6 of $3.42 per mile. However, waste processing and volume reduction were not included in this estimate because there was not a significant cost advantage.
6.4 REMEDIATION METHODS The goal in choosing remediation methods is to select the minimum cost option to accomplish a task. There are many factors which need to be considered when selecting a method such as contamination levels, degree of penetration of contamination into substrate material, equipment cost, suppo1t equipment costs, material and chemical costs, the generation of secondaiy waste volumes (waste in addition to the removed contaminated material), processing rates, labor requirements, and applicability to various tasks. Typical decontamination processes ai*e summarized in Table 6-6. For each decontamination method, this table shows application infonnation, the process cost per squai*e foot of ai*ea decontaminated, and the amount of seconda1y waste generated. These unit factors may be applied to specific areas or equipment requiring remediation to detennine the most cost-effective process.
Table 6-6: Decontamination Methodology Comparison Penetration Pi-oc.ess Secondary depth Crew Cost Waste Volume Methodology Applic.ation (in)
Size
($/ft2)
(ft3 /1,000 ft2)
McDonald U-5 Scabbier Floor concrete l/4 2.0
$1.42 0
McDonald U-5 Scabbier Floor concrete l/2 2.0
$2.51 0
McDonald 3WCD Scabbier Wall concrete 1/8 2.0
$5.69 0
Blastrac 1 OD Shot Blaster Floor concrete 1/16 1.1
$0.49 0.53 Blastrac 1 OD Shot Blaster Floor concrete 1/8 1.1
$0.63 0.53 L TC 10-60Pn Special All swfaces 1/32 1.3
$2.55 0.53 Vacumn Blaster L TC 10-60Pn Special All swfaces l/16 1.3
$4.22 0.53 Vaculllll Blaster CO2 Blasting All Surfaces 0
2.0
$5.21 0
Hydrolaser (5-10,000 psi)
All Smfaces 0
2.0
$1.08 9.07 Hands-on-Decon Non-Porous 0
1.0
$2.47 8.33 surfaces 6.5 RADIOACTIVE W ASTE VOLUME REDUCTION COSTS The volume reduction and waste treatment processes analyzed for use are summarized in Table 6-7. For each volume reduction method, the table shows application infonnation, transportation container type, and the total process cost per unit weight. These unit factors may be applied to specific items of equipment requiring disposal to detennine the most cost-effective process. The radioactive waste generated at the ARRR facility will include inadiated hardware, activated concrete, HEP A ventilation systems, fume hoods, steel, lead, and secondaiy waste generated Page 72 of95
Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor CS-HP-PR-006 Revision 6 during the decontamination work, such as protective clothing and materials used during manual decontamination work.
Table 6-7: Volume Reduction/Treatment Methods Cost Information Transport Total Cost VR Methodology Applicability Container Type
($/lb)
Super Compaction D1y active waste B-25 for Clive Utah
$6.46 20 lb/ft3 Disposal Lead Decontamination Bricks and Sheet Custom Box
$5.14 Survey & Release Low Density Waste 55 GalDrnm
$2.49 Low Density Dnnns Survey & Release Waste at greater than B-25 Box
$1.33 Medium Density Boxes 20 7< 60 lb/ft3 Survey & Release Waste at greater than B-25 Box
$0.96 High Density Boxes 60 lb/ft:3 6.6 UNIT C OSTS A number of unit cost factors were used to generate the total decommissioning cost estimate.
The main unit cost factors are listed in Table 6-8, so that individual decommissioning costs can be updated when required and the effects of revised unit costs can be evaluated.
Table 6-8: Decommissioning Cost Estimate Selected Unit Cost Factors Unit Cost Factor Unit Cost Rate Units Low Level Radioactive Waste Disposal at Clive, Utah
$131.00 cubic foot Resin and Lead Disposal at Clive, Utah
$253.00 cubic foot Waste Transportation to Clive, Utah
$5.40 mile Transportation Distance to Clive, Utah 609 miles B-25 Waste Disposal Container Cost
$2,530.00 each Management and Supervision
$159.60 hour6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> Engineer
$125.40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> Radiation Protection Supervisor
$129.00 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> Laborer Foreman
$85.00 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> Administrative Assistant
$41.12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Instrnment Technician
$81.51 hour5.902778e-4 days <br />0.0142 hours <br />8.43254e-5 weeks <br />1.94055e-5 months <br /> Radiation Protection Technician
$81.51 hour5.902778e-4 days <br />0.0142 hours <br />8.43254e-5 weeks <br />1.94055e-5 months <br /> Laborer
$78.69 hour7.986111e-4 days <br />0.0192 hours <br />1.140873e-4 weeks <br />2.62545e-5 months <br /> Fee 15%
Page 73 of95
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 74 of 95 6.7 FINAL SURVEYS Final survey costs are estimated based on the facility radiation survey information presented in NUREG-1757, NMSS Decommissioning Standard Review Plan (Ref. 8.9). The number of sample points for the various areas being surveyed and the type of survey being performed were determined. The time to perform each of these surveys is estimated, and the product of these two items is the labor time to perform the surveys. Equipment and material cost to perform the surveys is added along with staff support costs to determine a total cost. The survey requirements are based on NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) Ref. 8.8). A spreadsheet was developed which incorporates facility dimensions, labor rates and support cost ratios to estimate the final survey cost. The facility buildings survey labor estimate is summarized in Appendix A-6 and the open land and miscellaneous areas survey labor estimate is summarized in Appendix A-7.
Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor CS-HP-PR-006 Revision 6 7.0 FACILITY, CONDITIONS AND DECOMMISSIONING SCENARIO Decommissioning of the ARRR requires that residual radioactive materials be removed from the site to allow removal of the decommissioned facilities from the NRC license and State of California License. For the purposes ofthis cost estimate, the end of the decommissioning project occurs when the ARRR has been remediated to release limits and the Final Status Survey has been completed, documented and the survey results submitted to the NRC and the State of California.
7.1 REMEDIATION
SUMMARY
Remediation will be required for the ARRR buildings and systems, but it is not anticipated that remediation of sewers and outdoor areas will be required. Table 7-1 below is a brief summaiy of the anticipated remediation activities, with applicable assumptions and bases. Additional facility info1mation, radiological info1mation, and decommissioning plans are presented in greater detail in the document sections that follow.
Table 7-1: ARRR Planned Remediation Activities Building or Area Remediation Activities General Area Perfo1m a general facility clean up to remove all incidental equipment and materials, which includes both radioactive and non-radioactive waste on site prior to decommissioning. This activity is perfo1med as pait of prepai*ation activities that can be completed at any time prior to reactor decommissioning.
Non-Reactor Remove all equipment and materials not associated with operation of the Remediation reactor. This includes equipment used in the preparation for N-Ray activities and the N-Ray components outside the reactor tank. These activities are perfo1med as pait of prepai*ation work that can be completed at any time prior to reactor decommissioning.
TRI GA Reactor Empty water from the reactor tank. Remove the activated reactor core, vessel internals, bridge, and reactor vessel. Remove Beam catcher, bioshield wood and bioshield blocks. Remove N-Ray components including neutron guide, exposure tray and shields. Leave beam po1t in place, as it is unused and not activated. Cut out activated concrete surrounding the reactor tank and dispose of as radioactive waste.
Demin. & Heat Remove the Demineralizer and Heat Exchange Systems, decontaminate the Exchange Systems concrete pads in each building and demolish the buildings.
Reactor High Bay Remove all equipment and materials from the Reactor High Bay building Building that are not pa1t of the structure or utilities. Remove contaminated po1tions of the HV AC system, if anv.
Other Buildings Remove all equipment and materials from other buildings that are not pait of the structure or utilities.
Outdoor Areas Remove all equipment and materials outside of buildings that are not pa1t of site utilities. This includes the Cooling Towers, Waste Tank System, Shielding, spare ion exchange columns, etc.
Page 75 of 95
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 76 of 95 7.1.1 General Area Cleanup Perform a general facility clean up to remove all incidental equipment and materials, both radioactive and non-radioactive. This activity should start soon after it is determined that the facility will be decommissioned. The goal is to dispose of items and materials not required for reactor operation and maintenance using existing staff and current procedures.
7.1.2 Non-Reactor Remediation Remove all equipment not associated with operation and maintenance of the reactor. This includes equipment used in the preparation of items for N-Ray, N-Ray components outside the reactor tank, equipment in the Tagging Area, Chemical Lab, Machine Shop, Quality Control Room, Dark Room, Etc. These activities are performed as part of preparation work that can be completed prior to reactor decommissioning to save money and speed up the decommissioning if desired or they can be left to the Decommissioning Contractor. These remediation activities are discussed further by specific area in the sections below.
7.1.3 TRIGA Reactor Remove beam catcher and wood shield over reactor tank, characterize them and ship them for disposal.
Remove concrete blocks around reactor tank area, decontaminate them and survey them for disposal as clean waste.
Remove the reactor core, core stand, thermal column, fuel racks, vertical beam tube, and other items inside the reactor pool and ship them for disposal.
Remove reactor tools, characterize them and ship them for disposal.
The reactor bridge and items attached to the bridge will be removed and shipped for disposal.
The reactor pool will be emptied and the water processed for disposal as non-radioactive waste.
An activation analysis performed by Georgia Tech and reported in the Characterization Survey Report (Ref. 8.6) indicates that near the core there will be activated concrete and activated rebar in the concrete. Radionuclides currently in excess of the anticipated California limits, Table 5-2, include C-14, Ca-41, Ca-45, Mn-54, Fe-55 and Co-60.
However, if there is a lengthy storage period prior to decommissioning (~50 years), the only remaining radionuclide of concern will be C-14. The C-14 will be less than NRC limits but close to anticipated State of California derived limits for soil and a good case could be made to leave it in place, as it is encapsulated in concrete deeply below grade.
In this case, the tank and concrete would be removed down to 6-feet below grade and the rest of the structure left in place, as the concrete is not contaminated. In the case of
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 77 of 95 prompt decommissioning, about one foot of concrete near the core may need to be removed. The location of the activated concrete is shown in Figure 7-1.
The activation analysis also indicated slightly elevated activity in the soil; Ca-45 and Mn-54 exceed the anticipated State of California limits, but not the NRC limits. If the tank and concrete is being removed during a prompt decommissioning scenario, then up to a foot of soil near the core would be removed. In the case of delayed decommissioning
(~50 years), the Ca-45 and Mn-54 will have decayed to less than the anticipated State of California limits.
In the case of delayed decommissioning (~50 years), the reactor pool tank will be decontaminated and the tank left in place. In this case, the tank and concrete would be removed down to 6-feet below grade and the rest left in place, as the tank and concrete will not be contaminated. The Co-60 in the tank walls will have decayed to insignificant levels and the activity in the concrete behind the aluminum tank will also have decayed, as indicated above. In the case of prompt decommissioning, the pool liner would be removed for disposal as radioactive waste.
The unused beam port is not activated and will be left in place.
The reactor pool trenches will be decontaminated and the concrete left in place.
7.1.4 Demineralizer and Heat Exchange Buildings The Demineralizer and Heat Exchange Systems are contaminated and will be removed, characterized and shipped for disposal.
The Demineralizer and Heat Exchange Buildings are contaminated and will be removed, characterized and shipped for disposal. The lead shielding in the Demineralizer Building will be sent offsite for processing and disposal. The spare demineralizer in the building will be characterized and shipped offsite as radioactive waste. The concrete pads in the Demineralizer and Heat Exchange Buildings are contaminated and the pads will either be decontaminated by concrete surface removal and the remaining pads disposed of as clean waste or the pads disposed of as radioactive waste along with the rest of the building.
7.1.5 Reactor High Bay Area All equipment in the Reactor High Bay Building that is not part of the structure or utilities will be removed for disposal and contaminated building surfaces will be decontaminated. It is anticipated that this activity will include the following items:
Radwaste Room: The room waste will be characterized and sent offsite for disposal as radioactive waste. The lead will be sent offsite for processing and disposal. The asbestos floor tile will be removed and sent for disposal as radioactive waste. The floor will be decontaminated by surface concrete removal and 10% of the lower walls will be decontaminated by surface concrete removal. About 25% of the walls will be decontaminated by a hand wipe down.
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 78 of 95 Machine Shop: Any remaining small tools, supplies cabinets and tables will be surveyed and removed from site. The large equipment including Drill Press, Milling Machine and Lathe will also be surveyed, decontaminated if necessary and removed from site. The asbestos floor tile will be surveyed, removed and sent for disposal as asbestos waste or radioactive waste.
Office Areas, Locker Room and Supply Room: Any remaining furniture, supplies cabinets and tables will be surveyed and removed from site. Any asbestos floor tile will be surveyed, removed and sent for disposal as asbestos waste or radioactive waste.
Restrooms: In general, these rooms do not require any remediation. Any items and materials in the supply closet in the mens restroom will be surveyed and removed from site.
Control Room and Lunch Room: The control room cabinets will be surveyed and removed from site. Any remaining furniture, monitors, supplies, sink, cabinets and tables will be surveyed and removed from site. The asbestos floor tile under the sink area will be surveyed, removed and sent for disposal as asbestos waste or radioactive waste.
Main High Bay Area: An area of about 40-foot by 40-foot around the reactor pit will be decontaminated by surface concrete removal. The HVAC ductwork and heating and cooling units will be surveyed and any contaminated items removed for disposal as radioactive waste. The roof insulation material will be surveyed and removed for disposal if any contamination is found. In addition, the overhead lights will be surveyed and removed for disposal if any contamination is found. The florescent light bulbs and ballasts will be removed for separate disposal as they contain hazardous materials.
Mercury in the bulbs and probably PCBs in the ballasts.
7.1.6 High Bay Area N-Ray Gauge Office, Preparation Lab, Hallway and Chemical Lab: In the Chemical lab the hood and support bench along with the lab benches and sinks will be surveyed and removed from site. In the Preparation Lab, the marble weighing benches will be surveyed and removed from site. Any remaining equipment, furniture, supplies and cabinets in any of these rooms and will be surveyed and removed from site. The asbestos floor tile will be surveyed, removed and sent for disposal as asbestos waste or radioactive waste.
Sheet Metal Fabrication Area, Storage Area, Calibration Area and Electronics Lab: The radioactive items on the table top in the Sheet Metal Fabrication Area and the shield cave made from cement blocks on the floor will characterized and shipped for disposal as radioactive waste. Any remaining equipment, furniture, supplies and cabinets in any of these areas will be surveyed and removed from site. The asbestos floor tile will be surveyed, removed and sent for disposal as asbestos waste or radioactive waste.
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 79 of 95 7.1.7 Other Buildings Tagging Building: The Tagging room furnace, stainless tables, sink, tank and dryer will be surveyed and removed from site. Any remaining equipment, furniture, supplies and cabinets in the room will be surveyed and removed from site.
Storage Building: The Storage Building is sometimes referred to as the Forklift Garage.
The materials and supplies in this building have not been in a radioactive material area and will be removed from site. The equipment could have been used in a radioactive materials area and will be surveyed and removed from site.
Maintenance Office: The Maintenance Office and the contents have never been in a radioactive materials area. The contents will be removed from site or to an appropriate hazardous material disposition site as appropriate.
Chemical Shed: The Chemical Shed and the shed contents have never been in a radioactive materials area will removed to an appropriate hazardous material disposition site as appropriate. The building will be demolished and sent to an industrial landfill.
Compressor Building: The compressors and vacuum pump have never been in a radioactive materials area. The compressors will be surveyed and removed from site.
The vacuum pump oil will be sampled to insure that the vacuum pumps are not contaminated internally and they will be surveyed and removed from site.
7.1.8 Outdoor Areas Cooling Towers: The main and secondary cooling towers with associated pumps and controls have never been used with contaminated water and are maintained outside of radioactive materials areas. The cooling towers and the rest of the system will be demolished and removed from site.
Waste Sump: The waste sump is potentially contaminated. The Waste Sump pump, valves, and controls will be characterized and shipped for disposal as radioactive waste.
The concrete sump will be excavated, including bottom pad, and shipped for disposal as radioactive waste.
Shield Blocks: There are quarter circle shield blocks in the vicinity of the waste tanks and the demineralizer system that were used to shield the fence line from high dose rates.
These blocks were never in a contaminated area and will be shipped offsite.
The sanitary and storm sewers will be surveyed at accessible areas and released for continued use.
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 80 of 95 Figure 7 1: ARRR Activated Concrete Activated concrete near core removed Activated concrete below core removed -------------.
Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor 7.2 LICENSE T ERMINATION SURVEYS CS-HP-PR-006 Revision 6 License tennination surveys, or final status radiation surveys, will be perfo1med in the applicable areas of the site using the guidance provided in NUREG-157 5, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM), (Ref. 8.8). The smveys will be perfo1med in accordance with plans and procedmes specifically developed for the ARRR facility.
7.2.1 Smv ey Instrumentation Selection and use of instrumentation will ensme sensitivities are sufficient to detect the identified nuclides at the minimum detection requirements. A list of typical final smvey instrumentation, radiation detected, and calibration som ces are provided in Table 7-2.
Table 7-2: Typical Final Survey Instrumentation Instrument/
Detector Radiation Calibration Detector Type Detected Source Use Ludlum Model Direct alpha and 2350 wt. 43-68, Gas-flow 99Tc (~)
direct beta 43-98, 43-94 or 43-proportional Alpha or beta 230Tb (a.)
smveys; Beta (126 cm2) scans on solid 106 detector smfaces.
Ludlum Model 99Tc (~)
Direct beta pipe 2350/ SP-113-3m GM Pipe Detector Alpha or beta 230Tb (a.)
or SP-175-3m smvey.
Ludlum Model Direct beta 2350 wt. 44-40 Shielded GM (15.5 Beta 99Tc (~)
smveys; Beta cm2) scans on solid detector smfaces.
Ludlum Model Nal (Tl)
Gamma exposure 2350 wt. 44-2 or Scintillator Gamma 137Cs rate and gamma 44-10 detector scans.
Eberline Teletector Ion Chamber Gamma 6oCo (y)
Gamma exposure Model 6112B rate Eberline SAC-4 ZnS scintillator Alpha 230Tb (a.)
Smear counting Scaler Counter Eberline BC-4 Shielded GM Beta 99Tc (~)
Smear counting Scaler CoU11ter Tennelec Low-Shielded Gas-flow Backgrom1d Propo1tional Alpha and Beta 99Tc (~),230Th (a.)
Smear collllting CoU11ter or Equal EG&GNOMAD Nuclide identification and Gamma HPGe Gamma energy Mixed gamma quantification of Spectrometer or and intensity soil and sand Equal samples.
Page 81 of 95
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 82 of 95
8.0 REFERENCES
8.1 10 CFR 50.82, TERMINATION OF LICENSE, PART (B) FOR NON-POWER REACTOR LICENSEES, USNRC, NOVEMBER 2014 8.2 10 CFR 20 SUBPART E, RADIOLOGICAL CRITERIA FOR LICENSE TERMINATION, USNRC, AUGUST 2007 8.3 NUREG 1537, GUIDELINES FOR PREPARING AND REVIEWING APPLICATIONS FOR THE LICENSING OF NON-POWER REACTORS, USNRC, FEBRUARY 1996 8.4 MEANS BUILDING CONSTRUCTION COST DATA, 2011, 69TH ANNUAL EDITION, R.A.
MEANS COMPANY, INC., SEPTEMBER 2010 8.5 NUREG/CR-1756, TECHNOLOGY SAFETY AND COSTS OF DECOMMISSIONING REFERENCE NUCLEAR RESEARCH AND TEST REACTORS, USNRC, JULY, 1983 8.6 CS-HP-PR-008, CHARACTERIZATION REPORT FOR THE AEROTEST RADIOGRAPHY &
RESEARCH REACTOR,
, CALIFORNIA, ENERGYSOLUTIONS, OCTOBER 2011 8.7 10 CFR 20.1402, RADIOLOGICAL CRITERIA FOR UNRESTRICTED USE, USNRC 8.8 MULTI-AGENCY RADIATION SURVEY AND SITE INVESTIGATION MANUAL (MARSSIM),
REVISION 1, NUREG-1575, EPA 402-R-97-016, DOE/EH-0624, USEPA, U.S. NRC, U.S.
DOE, AND U.S. DOD, AUGUST 2000 8.9 NUREG-1757, CONSOLIDATED NMSS DECOMMISSIONING GUIDANCE, DECOMMISSIONING PROCESS FOR MATERIALS LICENSES, USNRC, SEPTEMBER 2006 8.10 NUREG/CR-5512, "RESIDUAL RADIOACTIVE CONTAMINATION FROM DECOMMISSIONING:
PARAMETER ANALYSIS, VOLUME 3, USNRC, OCTOBER 1999 8.11 STATE OF CALIFORNIA EXECUTIVE ORDER D-62-02, 9/13/2002
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 83 of 95 Appendix A-1 Contaminated Waste Volume Summary TableA1 ContaminatedWasteVolumeSummary
- ARRR,
,CA
Generated Decon DirectBurial Total Area Waste1 Waste2 Waste AllWaste Description ft3 ft3 ft3 ft3 TRIGAReactor 64 0
349 413 TRIGABioshield&NRay Components 0
0 285 285 Buildings 34 62 456 552 OutdoorAreas 6
0 708 714 PoolWater 5
5 6
16 Lead 13 0
13 26 TOTALS:
122 67 1817 2006 1Generatedwasteincludesprotectiveclothingandequipmentgeneratedbysiteoperations 2Deconwasteisvolumegeneratedbydecontaminationprocesses(includesitemssuchas sandblastinggrit,etc.)
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 84 of 95 Appendix A-2 Contaminated Waste Disposal Cost TableA2 RadioactiveWastePackaging,Shipping&DisposalCosts ARRR
,CA RadioactiveWasteDisposalCosts Generated Decon Clive Total AreaDescription Clive Clive DirectBurial Waste Disposal Disposal Disposal Disposal Costs Costs Costs Costs TRIGAReactor 7,146
426,110 433,256 TRIGABioshield&NRayComponents
52,666 52,666 Buildings 6,598 9,243 67,770 83,611 OutdoorAreas 3,901
79,413 83,314 Totals 17,645 9,243 625,959 652,847 RadioactiveWastePackaging&ShippingCosts*
Generated Decon Clive Total AreaDescription Clive Clive DirectBurial Waste Pack/Ship Pack/Ship Pack/Ship Pack/Ship Costs Costs Costs Costs TRIGAReactor 473
12,651 13,123 TRIGABioshield&NRayComponents
49,994 49,994 Buildings 298 542 14,894 15,734 OutdoorAreas 50
19,265 19,315 Totals 821 542 96,804 98,166
- Doesnotincludelabor TotalRadioactiveWastePackaging,Shipping&DisposalCosts*
Generated Decon DirectBurial Total AreaDescription Waste Waste Waste AllWaste TRIGAReactor 7,619
438,761 446,379 TRIGABioshield&NRayComponents
102,660 102,660 6,896 9,785 82,664 99,345 OutdoorAreas 3,951
98,678 102,629 Totals 18,466 9,785 722,763 751,014 Buildings
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 85 of 95 Appendix A-3 Waste Shipping Container Cost TableA3 WasteShippingContainer(B25)Costs ARRR
,CA
Total B25 Waste
Waste Waste Container AreaDescription
Volume Containers Costs
(ft3)
(Each)*
($)
TRIGAReactor
403 5
$11,499 TRIGABioshield&NRayComponents 285 4
$8,132 Buildings
552 6
$15,751 OutdoorAreas
714 8
$20,373
Totals 1,954 23
$55,755
- Numberofcontainersroundedtonextwholenumber
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 86 of 95 Appendix A-4 Waste Disposal Support Labor Estimate TableA4 WasteDisposalSupportLaborandB25ContainersCosts
- ARRR,
,CA
B25Waste Waste WasteShipment AreaDescription Containers(ea)
Shipments Labor(Man hours)
TRIGAReactor 4.8 0.7 13.6 TRIGABioshield&NRay Components 3.8 1.5 81.6 Buildings 6
1 18 OutdoorAreas 8
1.3 25 PoolWater 0.2 N/A 1
Lead 0.3 N/A 1
Totals:
23.1 4.5 140.2 Notes:
Numberofwasteshipmentsroundeduptonextwholenumber Doesnotincludecaskshipments(seebelow)
WasteDisposalSupportLabor,CaskRental&TransportationCosts
- ARRR,
CA
Liners/Cask CaskRental&
CaskSupport AreaDescription Rental(ea)
TransportCosts Labor(Man hours)
TRIGAReactor 0
0 TRIGABioshield&NRay Components 1
$38,560 72 Buildings 0
0 OutdoorAreas 0
0 Totals:
1
$38,560 72 Notes:
Transportationcostsincludetruckrentalanddrivercosts
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 87 of 95 Appendix A-5 Radioactive Waste Container, Cask and Labor Summary TableA5 RadioactiveWasteContainer,CaskandLaborSummary
- ARRR,
,CA Cask&
Waste Waste TotalWaste B25 Container Radioactive Shipment Shipment AreaDescription Volume(ft 3)
Containers Cost*
Shipments Labor(Manhrs)
LaborCost TRIGAReactor 413 4.8 11,499 0.7 13.6 1,078 TRIGABioshield&NRayComponents 285 3.8 42,718 1.5 81.6 6,467 Buildings 552 6
16,909 1.0 18 1,426 OutdoorAreas 714 8
21,871 1.3 25 1,981 PoolWater 16 0.2 563 0.2 Lead 26 0.3 845
0.3 Totals
2006 23.1 94,405
5 138.2 10,952 Notes:
Numberofcontainerstoberoundeduptonextwholenumber,ifneeded Numberofwasteshipmentstoberoundeduptonextwholenumber,ifneeded
- Assumes1TypeAcaskshipment
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 88 of 95 Appendix A-6 Building Survey Labor Summary IMPACTED BUILDING AREA SURVEY Table A-6
- ARRR, California SURVEY UPPER GAMMA PACKAGE AREA AREA AREA FLOOR + U. WALL +
FLOOR +
WALL +
SURVEY SURVEY DIRECT BUILDING ROOM AREA REQRD WIDTH LENGTH HEIGHT L. WALL CEILING Survey L. WALL CEILING ROOF or PKG SURVEY LOC NAME NUMBER DESCRIPTION
?
SURVEY SURVEY Sketchs SURVEY SURVEY SURVEY SMEAR PREP LABOR CODE (Y/N)
(ft)
(ft)
(ft)
CODE CODE (each)
POINTS POINTS POINTS POINTS (hrs)
(hrs)
Exterior Exterior 3
N-Ray 9
Computer & Counting Room Y
7.33 10.8 13.7 1
4 1
45 30 49 4
14 3
Reactor 10 Lunch Room N
12.75 20.3 9.5 1
4 1
99 30 84 14 3
Reactor 11 High Bay N-Ray Exp Area Y
20.92 25.5 22.5 1
4 2
162 30 126 4
24 3
Reactor 12 Reactor Enclosure N
25.50 25.8 22.5 1
4 1
189 33 145 22 3
Reactor 13 Control Room Y
12.75 26.0 9.5 1
4 1
119 30 98 4
20 3
Reactor 14 Men's Room N
6.92 8.3 9.5 1
4 1
37 30 44 9
3 Reactor 15 Ladies Room N
5.75 8.33 9.5 1
4 1
33 30 41 9
3 Reactor Entry Hallway N
4.17 13.7 9.5 1
4 1
41 30 47 10 3
Reactor 16 Employee's Lockers N
8.67 9.5 9.5 1
4 1
46 30 49 10 3
Reactor 17 Sandy's Office Y
10.33 13.2 9.5 1
4 1
63 30 61 4
15 3
Reactor 18 Business Office N
10.33 23.4 9.5 1
4 1
97 30 83 14 3
Reactor 19 Accounting Office N
9.83 11.3 9.5 1
4 1
55 30 56 11 3
Reactor 20 Machine Shop Y
11.67 12.7 9.5 1
4 1
66 30 63 4
16 3
Reactor 21 Office Supply Room N
11.42 13.8 8.0 1
4 1
70 30 65 12 3
Tagging Bldg 22 Tagging Area Y
18.67 35.3 12.3 1
5 3
194 30 146 4
30 3
Reactor 23 South End Radiography N
10.33 17.4 7.0 1
4 1
77 30 70 13 3
Maintenance 25 Maintenance Building N
9.33 12.4 7.0 1
4 1
57 30 57 11 3
Tagging Bldg 29 Safe N
2.83 6.5 4.0 1
4 1
30 30 39 9
3 Reactor Stairs to Mezzanine N
4.00 12.0 22.5 1
4 1
37 30 44 9
3 Reactor Mezzanine Hallway N
4.00 21.1 16.0 1
4 1
59 30 58 11 3
Reactor 31 N-Ray Gauge Office Y
8.67 9.0 8.0 1
4 1
44 30 48 4
14 3
Reactor 32 Preparation Lab N
8.50 10.1 8.0 1
4 1
47 30 50 10 3
Reactor 33 Chemical Lab N
10.50 11.2 8.0 1
4 1
57 30 57 11 3
Reactor 34 Sheet Metal Fabrication Area N
18.00 24.4 12.0 1
4 1
142 30 112 18 3
Reactor 35 Instrument Calibration Area N
15.25 20.5 12.0 1
4 1
111 30 92 15 3
Reactor 36 Storage N
13.33 61.6 12.0 1
4 1
256 30 187 27 3
Reactor 37 Electronics Lab N
8.83 20.5 8.0 1
4 1
80 30 72 13 3
Reactor 45 LLRW Storage room Y
8.17 8.6 12.0 1
4 2
41 30 47 4
14 TOTALS 2,356 843 2,090 32 404 NON-IMPACTED BUILDING AREA SURVEY Table A-6
- ARRR, California SURVEY PACKAGE AREA AREA AREA FLOOR + U. WALL + ENTER FLOOR +
U. WALL +
SURVEY DIRECT BUILDING ROOM AREA REQRD WIDTH LENGTH HEIGHT L. WALL CEILING Survey L. WALL CEILING ROOF TOTAL PACKAGE SURVEY LOC NAME NUMBER DESCRIPTION
?
SURVEY SURVEY Sketchs SURVEY SURVEY SURVEY SMEAR PREP LABOR CODE (Y/N)
(ft)
(ft)
(ft)
CODE CODE (each)
POINTS POINTS POINTS POINTS (hrs)
(hrs) 3 N-Ray Setup Building Exterior Exterior Y
45.0 60.7 13.7 2
5 2
10 10 30 50 4
13.4 3
Tagging Area Building Exterior Exterior Y
18.7 39.8 12.7 2
5 2
10 10 30 50 4
13.4 3
Storage Building Exterior Exterior Y
24.0 24.3 11.0 1
4 2
10 10 30 50 4
10.6 3
Maintenance Office Exterior Exterior Y
9.3 12.4 7.0 1
4 2
10 10 30 50 4
10.6 3
Compressor Building Exterior Exterior Y
7.7 14.2 8.0 1
4 2
10 10 30 50 4
10.6 3
High Bay Reactor Building Exterior Exterior Y
40.2 81.9 22.5 2
5 2
10 10 30 50 4
13.4 3
N-Ray Setup Building 1
Office Space Y
13.0 16.1 8.0 1
1 1
10 10 20 4
6.3 3
N-Ray Setup Building 2
Customer Viewing Rm N
10.3 16.1 8.0 1
1 1
10 10 20 2.3 3
N-Ray Setup Building 3
Quality Control Room N
8.9 16.1 8.0 1
1 1
10 10 20 2.3 3
N-Ray Setup Building 4
Dark Room N
10.8 16.1 8.0 1
1 1
10 10 20 2.3 3
N-Ray Setup Building 5
Explosive Strg & Safe N
6.0 9.8 8.0 1
1 1
10 10 20 2.3 3
N-Ray Setup Building 6
Film Storage N
6.0 9.8 8.0 1
1 1
10 10 20 2.3 3
N-Ray Setup Building 7
Shipping & Receiving N
14.5 25.3 13.7 1
2 1
10 10 20 2.8 3
N-Ray Setup Building 8
N-Ray Setup Area N
33.8 38.5 13.7 1
2 1
10 10 20 2.8 3
Compressor Building 28 Compressor Building Y
7.7 14.2 8.0 1
2 1
10 10 20 4
6.8 3
Storage Building 42 Storage Building Y
24.0 24.3 11.0 1
2 1
10 10 20 4
6.8 TOTALS 160 160 180 500 36 109
Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor CS-HP-PR-006 Revision 6 Appendix A-7 Outdoor Area Survey Labor Summary NON-IMP ACTED PAVED AREA SURVEY Table A-7 ARRR California I
SURll£Y P/CKAGE Ml.EA NI.EA Nuimer Random Random SURll£Y 10%
SURF/CE NlEA REQRD WIDTH LENGTH No.of No.of No.of of Survey Survey PACKAGE SURll£Y LOC TYPES DESCRIPTION
?
SURVEY alpha beta ganma Exp Rate Sketchs Sketch PREP LJBOR CODE IY/NI lftl lftl BLOCKS Scans Scans Scans Msnmts leachl HOIKS lhrsl Hours 4
Asphalt East Paled Area y
22 142 5
0.50 0.50 0.5 0.5 2
0.67 4
4.7 4
Asphalt North Paled Area y
so 110 8
0.80 0.80 0.8 0.8 2
0.67 4
4.7 4
Asphalt West Pal<ing Loi y
so 203 14 1.40 1.40 1.4 1.4 2
0.67 4
4.7 TOTALS 27 3
3 3
3 6
2.0 12 14.1 NON-IMPACTED UNPAVED AREA SURVEY TableA-7
- ARRR, alifornia ENTER SURVEY EtlTER ENTER EtlTER BB.OW ENTER ENTER PACKAGE AREA AREA lllmb<<
lllb<< Random Random SIJIMY 101.
OPTIONAL SURFACE AR£A
~
WIJTH LENC1H
- lllmbe, ol ol Survey Si.vty PACMGE SIM!VEY LOC TYPES DESCRIPTION
?
BELOW BB.OW SlJMY of E:qRtt, Soil Skettlls stt1th1 PREP IABOfl CODE BELOW BB.OW IYINI lftl lftl 8LOO(S Scans Msnnnts Saples jeachl HotrS (In)
(hr,)
4 I S
,& lrtes lfr tl~dscmd I
y I
271 111o 4
0.4 0.4 0.4 I
0.3l 4
- 4.
I Grm II h ISo Y11 I
y I
~I ii) 3 0.3 0.3 03 I
0.3l 4
4i I
I I
I I
TOTALS 7
1 1
1 2 8.7 8
u Table A-7 ARRR,-
California CATCH BASIN & CLEAN-OUT SURVEY BASIN SURVEY DURA110N (hrs):
4 BASIN SURVEY CREW SIZE (men):
1 ENTER ENTER SURVEY BELOW ENTER BASIN PACKAGE SURVEY OPTIONAL AREA DIAMETER REQRD PACKAGE SURVEY LOC OESCRIP110N BELOW 7
PREP LABOR CODE BELOW (fl)
(YIN)
(h rs)
(h rs )
4 Waste Sump 5.0 y
4 8.0 4
Marllole on Storm Sewer 5.0 N
4.0 TOTALS 4
12 DRAIN PIPE SURVEY PIPE SURVEY RATE (ft/hr):
40 PIPE SURVEY CREW SIZE (men):
3 ENTER ENTER ENTER SURVEY OP110NAL ENTER PIPE PIPE PACKAGE SURVEY LOC AREA DIAMETER LENGTH REQRD PACKAGE SURVEY CODES DESCRIPTION BELOW BELOW 7
PREP LABOR BELOW BELOW (ft)
(ft)
(Y/N)
(hrs)
(hrs) 4 Storm Drain 24 150 y
4 15.3 4
Sanitary Sewer 24 150 y
4 15.3 TOTALS 8
31 Page 89 of95
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 90 of 95 Appendix A-8 Instrument Lease Charges Table A-8 4 D&D Months Duration 1.0 Final Survey Months Duration 0.5 Characterization Survey Months Duration CHAR SURVEY D&D FINAL SURVEY D&D D&D CHAR SURVEY D&D FINAL SURVEY NUMBER NUMBER NUMBER FULL ALTERNATE INSTRUMENT INSTRUMENT INSTRUMENT ITEM INSTRUMENT MONTHLY INSTRUMENTS INSTRUMENTS INSTRUMENTS PROJECT MONTHLY LEASE LEASE LEASE NUMBER DESCRIPTION RENTAL RATE REQUIRED REQUIRED REQUIRED DURATION DURATION COST COST COST PORTABLE RADIATION PROTECTION INSTRUMENTATION 22 Ludlum MicroR Meter, Model 19
$120 1
1 1
Y
$60
$479
$120 25 Ludlum Alarm Ratemeter, Model 177
$103 1
3 3
Y
$51
$1,231
$308 32 Ludlum Data Logger, Model 2350-1
$239 3
3 3
Y
$359
$2,873
$718 RADIATION DETECTORS FOR PORTABLE INSTRUMENTATION 44 Ludlum 50cm2 Alpha Scintillator, Model 43-5
$86 1
2 2
Y
$43
$684
$171 47 Ludlum 125cm2 Gas Proportional Detector, Model 43-68
$46 1
3 3
Y
$23
$547
$137 52 Ludlum Gamma Scintillator Detector, Model 44-10
$103 1
2 2
Y
$51
$821
$205 SUPPORT EQUIPMENT FOR RADIATION PROTECTION INSTRUMENTA 58 Ludlum Floor Monitor Cart, Model 239-1F
$120 1
2 2
Y
$60
$958
$239 SEMI-PORTABLE RADIATION PROTECTION INSTRUMENTATION 69 Overhoff Tritium Monitor, Model 357
$1,197 LABORATORY & ANALYTICAL COUNTING INSTRUMENTATION 73 Ludlum Model 2929 Scaler with Dual Alpha/Beta 43-10-1 Sample Counter
$274 1
1 1
Y
$137
$1,094
$274 q
GAMMA SPECTROSCOPY EQUIPMENT 82 Canberra In-Situ Object Counting System (ISOCS) including: HPGe Detector (GC4020 or RE5020 available), Inspector-2K MCA, Big-MAC Dewar, 1" or 2" Lead Collimator/Shields, Mobile Cart or Tri-Pod.
$7,695 1
1 1
Y
$3,848
$30,780
$7,695 83 Canberra Laboratory Gamma Spectroscopy System with Dip Stick HPGe Detector, Laboratory Dewar, Digital MCA, Low Background Shield/Table, PC, and Genie-2K Software 84 GC3020 Detector (30% Relative Efficiency)
$2,822 87 Canberra Portable Gamma Spectroscopy System with Intregal HPGe Detector/Dewar, Inspector MCA, Laptop Computer, and Genie-2K Software 90 EG&G Laboratory Gamma Spectroscopy System with Dip Stick HPGe Detector, Laboratory Dewar, DSpec MCA, Low Background Shield/Table, PC, and Gamma Vision Software 92 GEM-35190-P Detector (35% Relative Efficiency)
$2,565 93 EG&G Portable HGPe Gamma Spectroscopy System with PopTop HPGe Detector, Portable Dewar, NOMAD MCA, Laptop Computer, and Gamma Vision Software 95 GMX-45220-P-S (45% Relative Efficiency)
$3,078 IN-SITU PIPE MONITORING EQUIPMENT AND DETECTORS SEALED SOURCES AND COUNTING STANDARDS 105 Tc-99 47mm, Beta Source
$103 1
1 1
Y
$51
$410
$103 106 Th-230 47mm Alpha Source
$103 1
1 1
Y
$51
$410
$103 109 Mixed Gamma, 250 ml Sand Marinelli, 133N
$239 1
1 1
Y
$120
$958
$239 113 Mixed Gamma, 47mm Filter Paper
$239 1
1 1
Y
$120
$958
$239 PORTABLE INDUSTRIAL HYGEIGENE FIELD INSTRUMENTATION 118 TSI Portacount Plus Respirator Fit Tester and Accessories, Model 8020
$1,026 SEMI PORTABLE DECONTAMINATION EQUIPMENT TOTAL INSTRUMENT LEASE COST
$3,769
$41,823
$11,219
- ARRR, California INSTRUMENT COSTS
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 91 of 95 Appendix A-9 Equipment Lease Charges Table A-9 4 D&D Months Duration 1.0 FINAL SURVEY Months Duration D&D FINAL SURVEY D&D D&D D&D FINAL SURVEY MONTHLY NUMBER NUMBER FULL ALTERNATE EQUIPMENT EQUIPMENT ITEM COMMERCIAL ITEMS ITEMS PROJECT MONTHLY LEASE LEASE NUMBER DESCRIPTION RENTAL RATE REQUIRED REQUIRED DURATION DURATION COST COST DECON EQUIPMENT 10 NORCLEAN Triple Head Electric HEPA Vacuum :
$1,345 1
Y
$5,381 OFFICE EQUIPMENT 11 Data Analysis Computer System :
$182 12 Download Notebook Computers :
$135 1
1 Y
$538
$135 SAMPLING EQUIPMENT 14 FISHER SCIENTIFIC -Top Loading Scale, 0-3 kg Model XE4100 :
$171 1
1 Y
$684
$171 15 FISHER SCIENTIFIC - Class F S.S. Weight Set, 1mg-2kg CAT.# 0221531 :
$40 1
1 Y
$160
$40 16 FISHER SCIENTIFIC - Oven, ISOTEMP 5.0 120VAC CAT.# 13247750G :
$277 1
1 Y
$1,108
$277 23 Portable Multigas Monitor
$156 1
1 Y
$625
$156 26 3/4" x 50' Air Hose
$40 5
Y
$798 159 40'-45' Electric,Articulating Boom lift
$2,394 1
N 2
$4,788 193 25 Ton Crane Truck.10 cents per mile over 50 Day/200Week/800Month
$7,068 1
N 1
$7,068 TOTAL EQUIPMENT LEASE COST
$32,817
$888 EQUIPMENT COSTS
- ARRR, California
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 92 of 95 Appendix A-10 Consumable Costs Table A-10 4 D&D Months Duration
- ARRR, California 1.0 Final Survey Months Duration 0.5 Characterization Survey Months Duration CHAR.
D&D FINAL SURVEY ITEM ITEM UNIT UNITS UNITS UNITS CHAR.
D&D FINAL SURVEY NUMBER DESCRIPTION RATE REQUIRED REQUIRED REQUIRED COST COST COST 0 PPE/Consumables 27 Electrical tape
$5 16 2
$0
$77
$10 40 Smears with peal back envelope, 250 per box
$38 16 8
$0
$613
$307 41 Planchets, aluminum C5A, 100 per bag
$29 40 20
$0
$1,150
$575 42 Tritium Smears
$13 4
2
$0
$51
$26 43 Tritium/C-14 counting vials (500/case)
$180 80 50
$0
$14,436
$9,022 44 Liquid Scintillation cocktail (4L/case)
$493
$0
$0
$0 45 DI WATER, 500 ml Bottle
$63 2
1
$0
$126
$63 48 Marinelli beaker, 250 ml sample container, 100 per case w lids
$559 5
2
$0
$2,796
$1,118 49 Cotton swab, with 6" or 8" wood shank, 100 per pack
$5
$0
$0
$0 50 PETRI DISHES, Ea
$182 48 24
$0
$8,731
$4,365 51 ZIP-LOCK FREEZER BAGS, 25 per Box
$8 20 20
$0
$153
$153 52 Hefty EZ Foil Giant Lasagna Pan 11 x 9 x 3
$4 40 25
$0
$178
$111 53 LIQUID NITROGEN, 160 liter
$153 12 4
$0
$1,840
$613 54 P-10 GAS, INSTRUMENT GRADE, 80 cf
$259 24 4
$0
$6,228
$1,038 55 Batteries, D Cell (Case of 72)
$88 5
1
$0
$439
$88 56 Tygon Tubing 1/8"+1/4"x 50'
$92 4
2
$0
$367
$184 57 TWEEZERS / FILTER FORCEPS, VWR PT. # 30033-042 OR EQUAL, Ea
$23 2
1
$0
$47
$23 60 Eberline, soil, Gamma Scan (HPGe) gammma)
$160 20
$0
$0
$3,194 66 Eberline, soil, Full Envirocare analysis
$3,762 1
2
$0
$3,762
$7,523 67 Asbestos Analysis
$80 10
$0
$799
$0 68 1/4" Sieve stainless Sample Prep
$222 4
1
$0
$887
$222 0 H&S Supplies and Equipment
$0 95 8' Fiberglass Step Ladder
$332 2
1
$0
$664
$332 103 PRINTER/COPIER PAPER
$51 4
1
$0
$204
$51 104 LOG BOOK, 8.5" X 11"
$6 4
1
$0
$22
$6 105 NOTE PADS, POCKET SIZE, Ea
$12 24 2
$0
$279
$23 106 LEGAL PADS, 8.5"X 11", Ea
$10 24 2
$0
$241
$20 107 SHARP ES, Box
$18 8
2
$0
$147
$37 108 Sawzall
$319 2
$0
$639
$0 109 2-inch Vacuum Hose (25-ft)
$241 4
$0
$966
$0 110 Minuteman/Hako X839 HEPA Vacuum
$1,301 1
$0
$1,301
$0 111 Vacuum Tool Kit for Minuteman System
$292 1
$0
$292
$0 112 HEPA Filter for Minuteman/HAKO Vacuum
$458 1
$0
$458
$0 113 Cloth Filter Bag for Minuteman/HAKO
$227 4
$0
$907
$0 114 Extension Cords Heavy Duty (50-ft sections)
$63
$0
$0
$0 115 2' 12/3 SJTW Yellow Jacket GFCI
$86
$0
$0
$0 116 Angle lock box (45 cubic foot)
$1,916 4
2
$0
$7,665
$3,832
$0
$93,841
$37,547 CONSUMABLE COSTS
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 93 of 95 Appendix A-11 Demolition Estimate Table A-11 Demolition Estimate
- ARRR, California LABOR BASED DEMOLITION COSTS: Labor by man-hour Management, Supervision, & HP Support Labor Not Included Util Operator &
DEMOLITION LOC WBS Craftsmen Laborers Craftsman HP Tech LABOR TOTAL CODE No.
AREA
$79.57
$78.69
$79.57
$81.51 hours5.902778e-4 days <br />0.0142 hours <br />8.43254e-5 weeks <br />1.94055e-5 months <br /> PRICE 3
General Cleanup 200.00 50.00 250.0
$19,813 1
Remove Reactor Core and Internals 80.00 40.00 120.0
$9,556 1
Empty Reactor Pool 40.00 20.00 60 0
$3,148 1
Ship Reactor Core and Related Internals 40.00 20.00 40 0
$3,148 3
Remove Reactor Building Equipment 400.00 100.00 400.0
$31,476 3
Remove Heat Exchanger System 40.00 20.00 40 0
$3,148 3
Remove Demin System 40.00 20.00 40 0
$3,148 3
Package & Ship Contam. Materials & Radioac ive Wastes 160.00 40.00 160.0
$12,590 0.0
$0 1,110.0
$86,025 TASK BASED DEMOLITON COSTS 67% Hazardous & Toxic Waste Productivity Factor: Level C, Heavy Work, 70 - 85ºF Percent Labor Cost 65.00%
MATERIAL LABOR EQUIPMENT MATERIAL LABOR EQUIPMENT LOC WBS Average Hourly Labor Rate $24.97 UNIT hrs UNIT UNIT TOTAL TOTAL TOTAL TOTAL CODE No.
AREA QUANTITY UNIT PRICE PRICE PRICE PRICE PRICE PRICE PRICE 1
Remove Concrete Around Pool 72 EA cubic yard
$148.57
$0.00
$15,963
$0
$15,963 1
Remove Concrete Under Pool 5.7 EA cubic yard
$148.57
$0.00
$1,270
$0
$1,270 1
Remove Wooden Shielding 3.2 Ton 85.8
$1,584.46
$0.00
$7,647
$0
$7,647 1
Remove Bioshield Blocks 82.4 Ton 2,197.4
$1,584.46
$0.00
$195,840
$0
$195,840 3
Remove Overhead Lights 12 EA
$52.85
$0.00
$951
$0
$951 3
Remove Ventilation Ducting 150 L.F.
$14.26
$0.00
$3,207
$0
$3,207 3
Remove RX Bldg HVAC Unit 2.0 Ton 53.3
$1,584.46
$0.00
$4,751
$0
$4,751 4
Remove Main Cooling Tower 0.88 Ton 23.4
$1,584.46
$0.00
$2,088
$0
$2,088 4
Remove Secondary Cooling Tower 2.6 Ton 69.0
$1,584.46
$0.00
$6,154
$0
$6,154 3
Remove Compressors 0.19 Ton 5.0
$1,584.46
$0.00
$449
$0
$449 3
Remove Vacuum pumps 0.21 Ton 5.6
$1,584.46
$0.00
$499
$0
$499 3
Remove Lathe 0.18 Ton 4.8
$1,584.46
$0.00
$428
$0
$428 3
Remove Drill Press 0.23 Ton 6.0
$1,584.46
$0.00
$534
$0
$534 3
Remove Milling Machine 0.54 Ton 14.4
$1,584.46
$0.00
$1,283
$0
$1,283 3
Remove Demin Shed Floor Slab 0.34 EA cubic yard
$148.57
$0.00
$76
$0
$76 3
Remove HX Bldg Floor Slab 0.34 EA cubic yard
$148.57
$0.00
$76
$0
$76 3
Remove main Control Cabinet 0.44 Ton 11.8
$1,584.46
$0.00
$1,056
$0
$1,056 1
Remove Bridge 0.65 Ton 17.4
$1,584.46
$0.00
$1,554
$0
$1,554 4
Large Waste Tank 0.64 Ton 17.1
$1,584.46
$0.00
$1,526
$0
$1,526 4
Small Waste Tank 0.51 Ton 13.7
$1,584.46
$0.00
$1,221
$0
$1,221 3
Spare Large Demin Units (2 ea) 0.37 Ton 9.8
$1,584.46
$0.00
$874
$0
$874 3
Large Demin Unit in Decay Mode 0.49 Ton 13.1
$1,584.46
$0.00
$1,166
$0
$1,166 3
Demin Lead Shielding 0.89 Ton 23.6
$1,584.46
$0.00
$2,102
$0
$2,102 3
Tagging Room Furnace 0.63 Ton 16.7
$1,584.46
$0.00
$1,485
$0
$1,485 3
Chem Lab Hood 0.27 Ton 7.1
$1,584.46
$0.00
$633
$0
$633 3
Chem Lab Hood Support Bench 0.21 Ton 5.7
$1,584.46
$0.00
$507
$0
$507 3
Chem Lab Benches 0.57 Ton 15.2
$1,584.46
$0.00
$1,352
$0
$1,352 4
Demolish Chemical shed 163 CF 24.4
$8.91
$0.13
$2,178
$32
$2,210 4
Demolish Demin Building 188 CF 28.2
$8.91
$0.13
$2,512
$37
$2,549 4
Demolish Heat Exchanger Building 324 CF 48.6
$8.91
$0.13
$4,329
$63
$4,392 0.00 0.00
$0
$0
$0
$0.0
$263,710.3
$131.6
$263,842
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 94 of 95 Appendix A-12 Miscellaneous Items Volume Estimate DESCRIPTION NUMBER OF UNITS MATERIAL OF CONSTRUCT UNIT VOLUME (ft ^3)
TOTAL WEIGHT (lb)
TOTAL VOLUME (f t^3)
VOL
%DIRECT BURY DISPSTN TR IGA Rect or Activated Hardware 1
Ea 2
Misc 100.0 60.0 12,000 120.0 100%
12,000 120 CLIVE Pool Tank Cylinder 1
Ea 1
Al 15.
2,631 15.
100%
2,631 15 CLIVE Pool Tank Bot tom (est imated@ 3/ 4")
1 Ea 1
Al 5.
858 5.
100%
858 5
CLIVE Pool Tank t op Flange (Al angle 1
Ea 1
Al 0.6 101 0.6 100%
101 1
CLIVE Pool Int erior Al Angle Ring @ 7' 1
Ea 1
Al 0.5 95 0.5 100%
95 1
CLIVE Pool Fuel Rack Al Angle Ring @ 7' 1
Ea 1
Al 0.1 24 0.1 100%
24 0
CLIVE Pool Tank Concret e Liner (Nominal 2' with 1
Ea 1
Conc.
1,935. 265,795 1,935.
0%
0 LEAVE Pool Tank Concrete Support pad (1-f t with 1
Ea 1
Conc.
154.
21,143 154.
0%
0 LEAVE Pool Experiment / Fuel Racks 1
Ea 3
Al 2.
66 5.
100%
66 5
CLIVE React or Pool Wat er 1
f t 3 1,738 Water 62.
1.0 108,494 1,738.
0%
VR Thermal Column (Graphit e) 1 Ea 1
Carbon 140.0 154.0 2 247 154.0 100%
2 247 5
CLIVE Thermal Column (Aluminum) 1 Ea 1
Al 175.0 5.
146 5.
100%
146 5
CLIVE Shell (t apers 8x10 t o 22x34) 5/8" wall 1
Ea 1
Al 15.
66.
963 66.
100%
963 66 CLIVE Beam Tube Graphite (9"x11"'x4')
1 f t 3 3.
Carbon 140.0 1.0 385 3.
100%
385 3
CLIVE Beam Tube Lead 1
f t 3 3.30 Lead 708.0 1.0 2,334 3.
100%
2,334 3
CLIVE Beam Tube Shut t er 1
Ea 1
Al/ SS 100.0 0 67 67 0.7 100%
67 1
CLIVE Regulating Control Rods (B4C) 1 Ea 1
Misc 187 0.0 5
0.0 100%
50 CLIVE Shim & Saf ety Control Rods (B4C) 1 Ea 2
Misc 187 0.1 21 0.1 100%
21 0
CLIVE Cont rol Rod Drive Connect ing Rod 1
Ea 3
Al 175 0.1 42 0.2 100%
42 0
CLIVE Cont rol Rod Ext ension Tube 1
Ea 3
Al 22 0.4 29 1.
100%
29 1
CLIVE Control Rod Drive Assembly 1
Ea 3
Misc 38 0.8 90 2.
100%
90 2
CLIVE Control Rod Guide Tube (~ length: fuel +
1 Ea 3
Al 58 0.0 7
0.1 100%
70 CLIVE Neut ron Source Holder 1
Ea 1
Al 175 0.1 19 0.1 100%
19 0
CLIVE Glory Hole 1
Ea 1
Al 175 0.2 39 0.2 100%
39 0
CLIVE Vert ical Tube (3/16" wall) 1 Ea 1
Al 7.
19 136 19.
100%
136 19 CLIVE Vertical Tube Lead disks in tube bott om 1
Ea 1
Lead 708 1.
991 1.
100%
991 1
CLIVE Lg. Component Irradiation Box (20cf, 1
Ea 1
Al 4.0 20.0 81 20.0 100%
81 20 CLIVE Top Grid Plate (5/ 8")
1 Ea 1
Al 175 0.1 24 0.1 100%
24 0
CLIVE Bott om Grid Plate (3/ 4")
1 Ea 1
Al 175 0.2 29 0.2 100%
29 0
CLIVE Inst rument Guide Tube 1
Ea 4
Al 15 1.
80 6.
100%
80 5
CLIVE Control Instrument Chambers 1
Ea 2
Misc 59 0.3 40 0.7 100%
40 1
CLIVE Core Cylindrical Shroud (50% cut out))
1 Ea 1
Al 11 14.
164 14.
100%
164 14 CLIVE Core Cyl. Shroud Att ach. Angle 1
All 1
Al 11 0.7 8
0.7 100%
81 CLIVE Core Support T-Beams 1
Ea 4
Al 37 0.9 125 3.
100%
125 3
CLIVE Support Bridge 10-inch St eel I-Beams 1
Ea 2
CS 101 4.
758 8.
100%
758 8
CLIVE Support Bridge 10-inch St eel I-Beams 1
Ea 2
CS 101 0.6 128 1.
100%
128 1
CLIVE Support Bridge 10-inch St eel I-Beams 1
Ea 2
CS 101 0.7 140 1.
100%
140 1
CLIVE Support Bridge 3/4" CRD Drive Mount ing 1
Ea 1
Al 175 0.3 57 0.3 100%
57 0
CLIVE Support Bridge Tread Plate 1 1
Ea 2
CS 491 0.2 149 0.3 100%
149 0
CLIVE Support Bridge Tread Plate 2 1
Ea 2
CS 491 0.1 75 0.2 100%
75 0
CLIVE Bioshield & N - Ray Radiation Beam Catcher Shield 2
Ea 1
Misc 84.
16.
1,314 16.
100%
1,314 16 CLIVE Shield Blocks Full (40x20x20) 2 Ea 72 Conc.
142 9.
94,519 667.
0%
0 LND FIL Shield Blocks Full wit h holes (40x20x20) 2 Ea 2
Conc.
142 9.
2,626 19.
0%
0 LND FIL Shield Blocks Half-height (40x20x10) 2 Ea 12 Conc.
142 5.
7,877 56.
0%
0 LND FIL Shield Blocks Half -length (20x20x20) 2 Ea 4
Conc.
142 656 5.
2 626 19.
0%
0 LND FIL Shield Blocks Special large (48.75x20x20) 2 Ea 4
Conc 142 1,600 11.
6,400 45.
0%
0 LND FIL Shield Blocks Special large (80x20x20) 2 Ea 1
Conc.
142 2,626 19.
2,626 19.
0%
0 LND FIL Wooden (f ir) beams 2
Ea 1
Wood 31 206.250 6,438 206.
100%
6,438 206 CLIVE Movable Exposure Tray 2
Ea 1
Al 10 57.870 579 58.
100%
579 58 CLIVE Tray End Shield 2
Ea 2
Misc 500 2.
2,315 5.
100%
2,315 5
CLIVE Misc Lead bricks 2
Ea 4
Lead 708 0.037 105 0.15 0%
0 VR React or Tools (1 B-25 Box Full) 3 Ea 1
Misc 24.
37.
1,076 90.0 100%
1,076 90 CLIVE LOC WBS CODE/
UNITS BULK UNIT DENSITY WEIGHT (lb/ ft ^3) (lb)
CLIVE DISPOSAL WT (lb) VOL (f t^3) 6,000 2,631 858 101 95 24 265,795 21,143 22 62 2,247 146 963 140 708 67 5
11 14 10 30 2
19 39 136 991 81 24 29 20 20 164 8
31 379 64 70 57 75 37 160 1,313 1,313 656 6,438 579 1,157 26 876 I
I I
I I
I I
I I
I f
I I
I I I
I I
I I
I
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Page 95 of 95 Appendix A-12 Miscellaneous Items Volume Estimate (Continued)
Radwast e Room Cardboard box/berillium supplier 3
Ea 1
Misc 0 3 10 0.3 100%
10 0.3 CLIVE Lead shields on back wall 3
Ea 20 Lead 0.7 393 13.
0%
00.0 VR Shielded shipping container 3
Ea 1
Lead 10 600 1.0 0%
00.0 LEAVE Small box of lead wool (12" x 18" x 3")
3 Ea 1
Lead 0.4 212 0.4 100%
212 0.4 CLIVE Active chemicals (U3O8, thorium nitrate, 3
Ea 1
Misc 0 3 10 0.3 100%
10 0.3 CLIVE Coffee can of lead from east trench 3
Ea 1
Lead 0.1 42 0.1 100%
42 0.1 CLIVE Proportional counter 3
Ea 1
Misc 0 2 7
0.2 100%
70.
CLIVE Ion chamber detector 3
Ea 1
Misc 0 2 7
0.2 100%
70.
CLIVE Ion chambers 3
Ea 2
Misc 0 3 14 0.7 100%
14 0.7 CLIVE Metal waste can with shot ~8"x8"x12" tall 3
Ea 1
Lead 252 0.4 252 0.4 100%
252 0.4 CLIVE Box of liquid standards 3
Ea 1
Misc 40 10 40 1.0 100%
40 1.0 CLIVE Lead shielding on back wall 3
Ea 1
Lead 0 3 100 0.3 0%
00.0 VR Lead seals in coffee can 3
Ea 1
Lead 0.1 28 0.1 100%
28 0.1 CLIVE Grindex Instrument by Brick Cave 3
Ea 1
Misc 0 2 26 0.2 100%
26 0.2 CLIVE Lead Sheet by brick cave (12 bricks 3
Ea 1
Lead 0.4 315 0.4 0%
00.0 VR Original shutter ~ 2 mR/hr 3
Ea 1
Mixed 0.7 67 0.7 100%
67 0.7 CLIVE Lead form small brick cave (~40 bricks 3
Ea 1
Lead 2.
1,540 2.
0%
00.0 VR Buildings Lead form brick cave (~156 bricks 3
Ea 1
Lead 7.
4,798 7.
0%
00.0 VR Bucket of irradiated lead shot ~12"dia x 3
Ea 1
Lead 0 5 278 0.5 100%
278 0.5 CLIVE GE fission detector 3
Ea 1
Mixed 0 0 1
0.0 100%
1 0.0 CLIVE Proportional counter 3
Ea 1
Mixed 0 2 7
0.2 100%
70.
CLIVE Chemical Shed 3
Ea 1
Metal 61.
1,223 61.
0%
00.0 LND FIL Heat Exchange Building 3
Ea 1
Mixed 256 0 5,120 256.0 100%
5,120 256.0 CLIVE Heat Exchanger 3
Ea 1
Mixed 7.
334 7.
100%
334 7.
CLIVE Heat Exchanger Pump 3
Ea 1
Mixed 6 0 150 6.0 100%
150 6.0 CLIVE Heat Exchanger piping 3
Ea 1
Aluminum 8 0 241 8.0 100%
241 8.0 CLIVE Misc Supports and Instruments 3
Ea 1
Mixed 600 20 0 600 20.0 100%
600 20.0 CLIVE Demineralizer Building 3
Ea 1
Mixed 3,081 154.
3,081 154.
100%
3,081 154.
CLIVE Demin Pump 3
Ea 1
Mixed 60 2.
60 2.
100%
60 2.
CLIVE Air Sampler 3
Ea 1
Mixed 30 10 30 1.0 100%
30 1.0 CLIVE Demin Lead Shielding 3
Ea 24 Lead 74 0.10 1,770 3.
0%
0 0.0 VR Florescent Light Fixture (PCB 3
Ea 12 Mixed 3.
0.06 40 0.7 100%
40 0.7 CLIVE Florescent Light Fixture (Bulbs) 3 Ea 24 Glass & Metal 1.0 0.10 24 2.
100%
24 2.
CLIVE Reactor Building General Cleanup Waste 3
ft 3 60 30.0 1,800 60 100%
1,800 60 CLIVE Out door Areas Waste Sump Cylinder 4
Ea 1
Concrete 6,912 58.
6,912 58.
100%
6,912 58.
CLIVE Waste Sump Pump 4
Ea 1
Mixed 60 2.
60 2.
100%
60 2.
CLIVE Waste Sump Bottom Slab 4
Ea 1
Concrete 2,160 18 0 2,160 18.0 100%
2,160 18.0 CLIVE Waste Sump Misc Piping & Supports 4
Ea 1
Mixed 300 10 0 300 10.0 100%
300 10.0 CLIVE Cooling Tower (Marley) 4 Ea 1
Mixed 1,758 264 0 1,758 264.0 30%
527 79.2 CLIVE/LF Cooling Tower Pump 4
Ea 1
Mixed 150 6 0 150 6.0 100%
150 6.0 CLIVE Spare Cooling Tower 4
Ea 1
Mixed 5,181 864.
5,181 864.
0%
5,181 0.
LND FIL Fuel Shipping Containers (4 ea) 4 Ea 4
Steel & Conc 888 8.
3,552 30.0 100%
3,552 30.0 CLIVE 10 20 600 212 10 42 7
7 7
100 28 26 315 67 1,540 4,798 241 278 1
7 1,223 5,120 334 150