ML22340A011

CS-HP-PR-006, Revision 6, Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor - Redacted

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: ML22340A006 ML22340A007 ML22340A008 ML22340A009 ML22340A011 ML22340A012 ML22340A013 ML22340A014 ML22340A015 ML22340A016 ML22340A017
References
CS-HP-PR-006, Rev 6
Download: ML22340A011 (1)

Text

ENERGY~ Sou:lr.la\\{S

CS-HP-PR-006

Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor

California

Project No. 313150 Revision 6

Prepared for:

Aerotest Operations, Inc.

Prepared by:

EnergySolutions, LLC LP&D Projects Group 151 Layfayette Drive Oak Ridge, TN 37830

Authored By: 11/27/2018 Steve Croslin, CHP, Radiological Engineer Date "f. \\..

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Reviewed By:,"'-r.. ~-*',, v t.... e., X ___.(___ 11 JAN 19 Date

Approved By:

Date L Non-Proprietary LJ New C Proprietary D Title Change D Restricted Information []Revision D Safeguards Information 0Rewrite D Sensitive Security Information 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Electronic documents, once printed, are uncootrollcd and may become outdated.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

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

Page 2 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 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

Page 3 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

Summary of Technical Changes

Revision Summary of Technical Changes

1 through 5 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 6 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.

Page 4 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

LIST OF FIGURES

Section Page

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

Page 5 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

LIST OF FIGURES

Section Page

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

Page 6 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 Figure 5-24: Waste Storage Tanks................................................................................................ 66

Page 7 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 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

Page 8 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 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

Page 9 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 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 licen sed disposal site at Clive, Utah.

Page 10 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

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 restarte-d 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 mate rial. 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 Stat e of California is authorized to implement RCRA requirements, and through this means can impl ement 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 pur pose 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 uncontaminat ed facility infrastructure, such as concrete and asphalt that remain at the site. Disposal of this remaining infrastructure will fall under the jurisdiction of the Stat e 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

Page 11 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 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 Energy Solutions 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 rem oval of hardware, structural materials, and miscellaneous materials as necessary to reduce le vels 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 scr eening 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 tota l square feet of floor area to arrive at the cost. These estimates includes the craft labor, su pervision, health physics support, waste

Page 12 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 disposal, materials and equipment necessary to actu ally 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 th e 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. Contamin ation 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 so me 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.

Page 13 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

• 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.

Page 14 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 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 configur ation 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 characteriza tion 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 faci lity 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.

Page 15 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 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 allo ws 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 th e site and there is not a possibility for fuel removal in the near future.

• No Action Alternative - A no-action alternativ e 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.

Page 16 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 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.

Page 17 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

• 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 contaminat ed 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 isol ate operation areas and prevent inadvertent release of contaminants.

• Employment of monitored, high efficiency pa rticulate 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

Page 18 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6 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.

Page 19 of 95

D ecommi s sionin g Cos t E stimat e for the CS-HP-PR-00 6 A erot es t R a di ograph y and R e s ea r ch R e actor R ev ision 6

5.0 DEC O MM I SS IO NIN G C RIT E RIA

En er gySolutions radio l og ical engine ers visi ted ARRR in_, C ali fo rni a in May of2 0 1 l to gather phys ical an d rad i olog ic a l data for ch aracteri z a ti on o f the fac i lity. Facility sketche s, bui lding draw ings, and ra dio l og ical c harac teri zat i on data fo r a ffecte d ar eas and p o tentia lly affec ted ar e as wer e ob tained.

5. 1 RA.DIO NUC LID E S OF I N T ERE ST

Th e b ase line radioact ive m aterial quan tities were ob tain e d from the est imat e prov i ded in NUREG /C R-17 56, (Ref. 8.5). Th ere ar e addit io nal radionuc lides r ep o1te d in the charac ter i zat ion smv e y rep o1i (Ref. 8.6) th at w ere n ot inclu ded in NUREG /C R-1756 an d, ther e fore, do no t h av e es tim ated quantitie s. Afte r rea ctor shut down an d fo r so me tim e after, 6°Co an d, to a sma ll er extent, 65Z n a re th e pr incipal contrib uto rs to radia tion dose fro m the rea c tor core and vess el.

M ost (> 95%) of th e radi onucli de inve nto1y at the fac i lity is found in t he r eacto r p oo l. Excl udin g fuel, this am ounts to ab ou t 34 Ci of neu tron act ivat ion an d fissi on produ cts at t h e tim e of shutdow n. The ra dio nuclide s th at p otenti a lly ex ist in t h e ARRR a l on g w it h e stim ated inv entorie s as of S eptem ber 201 2 ar e present ed in Tab l e 5-1.

T a bl e 5-1: Li st of Ex p ect e d R a dionu clid es

N ucli d e H alf-Life In ve n t ory (y r ) 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

36C l 301,000 2.85 X 10-4

37Ar 0.0960 J.85 X 10- 5

39Ar 269 2.6 1 X 10-7

4t ca 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

Pa ge 26 of 95 Decommi ss ioning C os t E stimate for the C S-HP-PR-006 Aerote st Radiograph y and Re s earch Reactor Re v ision 6

Nuclide H alf-L ife In ve n tory (yr) Ci

90Sr 29.l 0.454

93"'Nb 13.6 3.68 X 10-9

~ 20,000 2. 15 X 10- 8 93Mo 4,000 1.19 X 10- 8 9;Zr 0. 175 1.21 X 10-2 95Nb 0.0961 1.36 X 10-2

9~ 0.0099 9.54x 10-7

lOSAg 4.51 X 10- 6 1.39 X 10-2 108mAg 418 0.159

109mAg J.26 X 10- 6 J.76 X 10- 3 llOAg 7.8Ox 10-7 1.19 X 10-2 llOmAg 418 0.878 109Cd 1.27 0.120

m "'Cd 14.1 J.O7 X 10- 3 llS"'Cd 0.122 8. 13 X 10-6

113mm 0.000189 6.74 X 10-4

113Sn 0.315 6.74 X 10-4

ll Pmsn 0.803 2.17 X 10-2

121Sn 0.00309 2. 19x 10- 5

121msn 55 2.82 X 10- 5

123Sn 0.354 2.40 X 10-4

12*sb 0.16 8.51 X 10- 3

msb 2.76 3.00 X 10- 3 m"'I'e 0.328 3.69 X 10- 5

m"'I'e 0.157 7.31 X 10-4

134Cs 2.7 9. 16 X 10-7

137Cs 30.17 0.283

133Ba 10.51 6. 17xlO -4

139Ce 0.377 6.94 X 10-9

1*1ce 0.0890 l.llxlO - 8

l44Ce 0.78 0.185 1s2Eu 13.48 1 59

1s4Eu 8.8 0.161 1ssEu 4.96 J.73 X 10-2 1s3Gd 0.659 8.93 X 10-5 181w 0.332 l.12x 10-7 iasw 0.206 5. 12 X 10-7 203Hg 0.128 4.42 X 10-6 204-yl 3.78 5.82 X 10- 5

P age 27 of 95 D ecommi ssionin g Cos t Es timat e for the CS-HP-PR-00 6 A erot es t R a diograph y and R es ea r ch R eactor R ev ision 6

Nuclide H alf-Life I n ve n tory (yr) Ci

205J>b 15,3000,000 9.80 X 10- 5

210p0 0.3791 1.75 X 10-2

238Pu 87.7 4.35 X 10-4

239l40Pu 24, 110 6.95 X 10-4

241Pu 14.35 1.32 X 10-2

2 41Am 432.2 3.59 X 10- 3

242cm 0.446 5.62 X 10-4

• Argon is a gas that will dissipate and will have an inven t ory close to zero. Tritium migrates easily and most of it wil l dissipate. The tritium inven t ory withou t diss ipation is shown with a Jess than si gn.

Th e list of expected radio n uclides provided above i s based on t h e ass u mption th at operat i on of th e ARRR h as r esu lted in the n eutron act ivat i on of r eacto r core compo n en ts and other integra l har dwar e o r strnct ural members w h ich wer e situated adjace n t to, or in close proxim i ty to, th e reacto r core dur ing operations. Specific items w h ich are con si dered to h ave bee n exposed to neutro n flux th at produced activation include mater i als composed of aluminum, steel, sta inless steel, grap hite, cadmium, l ead, concrete and possibly oth ers. In additio n, the activity in spe n t res in was estimated based on ana lytical resu l ts and an estimated spent r es in inve n t01y.

5.2 RADIOLO G I CAL C RI TE RIA F OR LI CENSE T ERMINA TI ON

Th e overall objective of th e ARRR decommissio n ing i s to r emediate th e facilities to a cond i tion th at co1Tespo n ds to a calcu l ated dose to the public of less t h an 3 m r em/year from app licable pat h ways. It is assumed th at th e facilities may then be re l eased fo r unr estricte d use. A 25 mrem/year dose limit appears in 10 CFR 20.1402, Radiological Criteria for Unre s tricted Use (Ref. 8. 7) b u t thi s was r educed to 3 m r em/year fo r projected State of Califo rnia r equireme n ts.

Th e Derived Con centrat i on Gui deli n e Level (DCG L) i s defi n ed in MARSSIM (Ref. 8.8) as the radio nuc li de -specific con cen tratio n with in a s urvey unit co1Tespon ding to t h e release cri ter i on.

The DCGL is depende n t upon several factors inclu d in g th e rad i onucli des of inter est, app licable dose pat h ways, ar ea occupancy and th e future u se of the fac i lity. DCG L s assume a r elatively uni fo1m level of res i dual radioactiv i ty across the survey unit.

For the ARRR it was assumed that the site qualified fo r a scree n ing an alysis to develop th e DCG L s, whi ch is genera lly conservative. A scree nin g analysis can be based on o n e or mo r e of cm Tentl y ava i lable scree nin g too l s: (I) b u ilding surface con taminatio n and s ur face soil con taminatio n scree n ing cr iter ia ar e p resented in NUREG - 1757, Appe n dix B (Ref. 8.9), or (2) scree n ing l eve l s der ived using th e software DandD, Ver si on 2.0 (R efs. 8.9 an d 8.10), fo r the specific radionuclides using th e code default parameters. The assumed DCGLs for ARRR were based on 12% of t h e l ook -up tab l es in NUREG - 1757, Appe n dix H ( R ef. 8.9), w hich i s equ iva l en t to a pote n tial dose of 3 mrem/yea r from res i du al con tamination. T able 5.2 shows th e NRC acceptab l e scr eenin g va lues an d the State of Califo rnia screen ing l eve l s th at ar e assumed to be acceptab l e, fo r the major rad i on ucl i des of conce rn at th e ARRR.

Page 28 of95 D ecommi ss ionin g Cos t Es timat e for the CS-HP-PR-00 6 A erot es t R a di ograph y and R es ea r ch R e actor R ev ision 6

Bui ldings with surface contamination below 12% of th e screenin g tables in NUREG - 1757, Append ix B w i ll be as sumed to be acceptable for release for unr estri cted u se, provided th at the fo llowing cond itions are met:

• Residual radioactiv i ty h as bee n r educed to l eve ls th at ar e "as low as is rea son ab ly achievable " (ALARA),

• Th e r esidual rad i oact ivity is contained in t he top laye r of the bui lding sur face (i.e., th ere is no vo lumet r ic contaminatio n), and

• The fr act ion of removab l e surface contam ination does not exceed 0.1.

Tabl e 5-2: Accept abl e Licen se T er mination Scr ee nin g Valu es of C omm on Radi onuclid es fo r Buildin g Su r fa ce C ontaminati on 1

Radionuclide Sy mbol NRC a ccept a ble Ca liforni a acc eptable s cr eenin2 leve ls 1 for scr ee nin 2 leve ls3 for unr es tricted r e lease unr es trict e d rel e a se (dpm/100 cm 2 ) 2 ( dom /100 c m 2 )

Hydrogen - 3 3H 1.2E+ 08 l.4E+07 (Tri tium)

Carbo n - 14 14c 3.7E+ 06 4.4E+05

Sodium-22 22Na 9.5 E+ 03 1.1E+03 S ulfur -35 3ss 1.3E+07 1. 6E+06 Chl or ine - 36 36Cl 5.0E+05 6.0E+04 Man ganese -54 54Mn 3.2 E+ 04 3.8E+03 Iron - 55 ssF e 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 8.7 E+03 1.0E+03 Techneti um -99 99 T c 1.3E+06 1.6E+05 Iodine - 129 1291 3.5E+04 3.4E+03

Cesium - 137 137Cs 2.8 E+ 04 2.8E+04 Iri dium - 192 192Ir 7.4E + 04 8.8E+03

1 Screening l eve ls are based on the asswnp tion that the fraction of remova b l e surfac e contamina tion is equal to 0. 1. For cases wh en the fraction of removable contamination is unde termined or higher than 0. 1, users may assume, for screening pwposes, tha t 100% of swface contamina tion is removable, and therefore the screening l eve ls should b e decreased by a factor of 10. A ltema t ively, users having site specific data on the fraction ofremovable contamination (e.g., within the 10% to 100% range) may calculate site-specific screening l ev els using DandD V ersion 2.

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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 inte rnal 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 wh ole 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 fre sh 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 mech anisms, and control rod drive controls were purchased from General Atomics and were incorp orated 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.

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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

Page 31 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

equipped with fill and drain lines that are us ed 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 neut ron 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 th e core. The increasing radius of each row

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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 colu mn 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 accep table 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 cal ibrated 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 materi al to be irradiated through the tube into the core region. The glory hole will accept capsules with a maximum diameter of 1.35 inches.

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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 CO 2 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 sp acers 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 maxi mum 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 receive r. Directional CO2 flow moves the rabbit

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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 lo cated in any reactor core position. When installed, the facility is operated with dry CO 2 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 experiment s 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 r eactor 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 exchange r. 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 a nd 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 Materi al Storage Room. The radioactive materials normally stored in the room include contaminated Personal Protective Equipment, radioactive sources, filters, contaminated or low level irradiated materi als removed from reactor during repairs and modifications, and miscellaneous contaminated or irradiated items.

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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, contaminat ed 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 simila r tiles. The shop was reported to have been used to machine contaminated or activ ated 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 r eactor 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.

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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 st ore 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 Meta l 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 por tion 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 co mponents. 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.

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5.3.1.16 Offices and Restroom Areas

The Restrooms and Offices in the reactor buildin g 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.

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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 equi pment, 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 th e 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.

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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 us ed 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, de mineralizer 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 loca ted 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.

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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.

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5.3.13 Lan d Ar ea

A ll of the 0.9 acres that make up th e site are fenced in with a cha in link fe nce. The fence has a tmck gate tha t a ll ows access to the Shippin g and R eceiving ar ea and a personnel gate t h at enters the Reactor Building near the Con trol Room. Most of the o u tside area is paved as c an be see n in Figure 4 -2, Aerial V i ew of ARRR Site. There are seepages of groundwater upward through cracks in the pavemen t o n the n01t h end of the site t hat ar e collected and drained by a di tch just outside the n o1t h site fe nce.

5.4 RELATIO N OF THE ARRR TO OTHER TRIGA REACTOR S

The design of the ARRR fuel i s similar to those of approximatel y 50 TRI GA type re actors cunently operating worldwide with 24 in the U nit ed States.

The reactor and associated equipment w ill be decommissioned by r emoval o f the core, removing the wate r from the vessel, and removing act ivated and contam inated materials from the reactor.

Once t hi s h as been comp l eted, t he struct ure wi ll be surveyed u sing a license temiination type smvey with any add it ional deco n tamination perfo1med in conjunction with t he smveys.

5.5 O UT SIDE AREAS

There i s no histo1y of any spi lls of radioac t ive materials ou ts ide the iden t ified building process are as. Based on cmT ent smvey data, it is n ot anticipa ted that an y soil rem ediation will be required. There i s a discharge from the R eacto r Building to the sanita1y sewer system which mns ne ar t he building.

The ARRR is between two waters hed s: an d. The smTound ing ar ea slopes gen t ly dow n ward to the north and to the south. The site st01m wate r mn off i s to the n01th and west toward. - Creek is the principal local drainage, with Creek an Creek being tributai. Creek meanders n01thward through an and ultimately joins, w hich discharges into Sui sun Bayneai* There is a dra ina ge ditch l ocated just past t he site boundaiy to the n o1t h of the facili ty.

The sanita1y sewe r and nearby st01m sewers will be sm veyed at accessible loca t ions downst r eam of the site. In addition, soil sampling and license te1mination smveys of paved ai*eas and m1paved areas w ill be perfo1med in ai*eas adjac ent to the ARRR in accordance w it h cmTent regulato1y r equiremen ts.

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Figure 5-2: ARRR Core and Support Structure

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Radiation Beam catcher Shield

. ~*.!:."~

Neutron Radiography Facility

Reactor Core

Thermal Column

Figure 5-3: ARRR Reactor Tank Cutaway and N-Ray Facility

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Figure 5-7: ARRR Preparation Lab

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Figure 5-15: Office Space

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Figure 5-24: Waste Storage Tanks

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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 th e considerations and factors that influenced the DCE. Table 6-1 provides a summary of the co sts associated with each area of the facility.

Table 6-1: Decommissioning Cost Summary - ARRR

Ope rati on Labo rHrs Labo r,Equip,contracts,Rad was teship&

trave l,l i vi ng supplie s disposal Total TRI GARe actor 6, 147 $652, 802 $121, 135 $446, 379 1, 220, 316$

TRI GAShielding &N RayCompone nts i ncluded above i ncluded above $30, 343 $102, 660 133, 003$

Buil di ngs 2, 454 $260, 576 $80, 630 $99, 345 440, 551$

OutdoorAreas 477 $50, 634 $54, 528 $102, 629 207, 791$

De commi ss i on i ngP l a n n i n g 240 $26, 221 $0 $0 26, 221$

Characte ri zati onS u r v e y s 409 $48, 837 $2, 676 $0 51, 514$

Fi nalS u r v e y s 1, 820 $210, 998 $12, 145 $0 223, 142$

Pl anni ng,Trai ni ng,&Mo b i l i z a t i o n 404 $42, 027 $0 $0 42, 027$

Ove rsi ght&Li ce n s i n g 916 $119, 535 $0 $0 119, 535$

Subtotal s 12, 867 1, 411, 631$ 301, 456$ 751, 014$ 2, 464, 100$

25%Contingency 616, 025$

Total 3, 080, 126$

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 prot ection 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.

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T a bl e 6-2: Per sonn el P r otec tive E qu ipm ent Prot ec ti on Summ a r y

Prot e cti o n Le ve l Per sonn el Pr ote c ti v e E quipm e nt R e quir e ment Le ve l A : The hig h est av ai l able le ve l of re spirato 1y, skin, and eye protecti on The hig h est l ev e l of re spirato ry prote ction, but less skin L eve l B : prot ecti on th an L eve l A. L eve l B is th e minimum leve l re comm en ded for ini tia l s ite entri es, or fo r oth er ent1y co ndit io ns dea ling with unkn own haz ards.

Le ve l C: The same le v el of skin prote ct io n as L ev e l B, bu t a l ower leve l of res pirat01y prot ecti on.

L eve l D M odified: Skin prot ecti on s ilnil ar to o r th e s am e as L eve l C, w ithout re spira to1y prote cti on.

Leve l D : Stand ard wo rk uni fo1m su itable for co n strncti on work: n o re spira tory prot ecti on an d 1ninimal skin prot ectio n.

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6.2 RADIO ACTIVE WAS T E VO L UME ES TI MATES

The volume of rad i oactive waste r equ iring trea t men t and/or disposal can be a ve1y significant factor due to the hig h costs of rad i oactive waste disposal. For t h e ARRR decomm ission ing, t h e cost fo r radioact ive waste process ing, shippin g, and disposa l is antic ipated to be about 3 1 % of th e total decommissio nin g cost. This is a typ i cal fractio n fo r re l atively clean rad i oactive faci lit i es. Radioact i ve waste vo lume estimates that result from decommission ing are d iscu ssed in th e fo ll owing sectio n. In 20 17 a sign i fican t amo unt legacy waste (total vo lun1e of 1,920 cu bic feet) was shipped offsite fo r disposal, w hich r educed t he waste volume, transportat i on an d d isposa l costs compa r ed to previous estimates.. T able 6 -5 provides a vo lume summaiy for each ar ea of the ARRR. Info n natio n about th e vo lume of mos t waste items i s provided in Appe ndix A-12.

T abl e 6-5: ARRR Unpro cessed Radioa ctive Wa ste Summ ary*

Ge n era te d D eco n Dir ec t C live C live C live T otal Di sp osa l Dis p osa l D isp osa l Di sp osa l Vol um e Vo lum e Vo lum e Vo lum e A r ea Desclioti on (f t " 3) (f t " 3) (ft " 3) (f t " 3)

TRIGA Reac tor 64 0 349 413 TRIGA Biosh iel d & N - Ray Components 0 0 285 285 Build ings 34 62 456 552 Outdoor Areas 6 0 708 714 Pool Water 5 5 6 16 Lead 13 0 13 26 TOTAL S 122 67 18 17 2006

6.3 RADIO ACTIVE WAS T E DI SP OSAL C O ST S

A significant po1i ion of th e overall decommiss i onin g cost i s gen erally attributed to th e tran sport,

treatment an d disposal of radioac t ive waste. Thi s cost estimate includes rad i oactive waste process ing th at is followed by d isposa l an d direct radioactive waste disposal at Clive, Utah. T h e fo llowin g sectio ns describe t h e pri cing for each optio n.

6.3.1 C live, Utah R adioact ive Waste Direct Disposal Costs

Th e costs to tran spo1i low level radioac t ive waste to th e Clive, Utah disposal site ar e based on a tran spo1i distance of 609 miles, at a rate of $5.40 per m i le. The cost to dispose of t he waste at th e U tah site is based on a disposal fee of $131 per cub i c foot for l ow l eve l waste deb r is an d

$253 per cubic foot fo r transp01iat i on an d disposa l of dem ineralizer res in from th e pool wate r clean -up an d lead that m u st be encapsulated prior to b m ial.

6.3.2 Radioac t ive Waste Process ing an d Bm i al Costs

Th e costs to tran spo1i waste to a volume r educ tion/waste processing fac ility in Oak Ridge or Elw in, Tennessee are based on t r anspo 1i d i stan ces of 2437 and 2561 miles respec tive ly, at a rate

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of $3.42 per mi l e. However, waste process ing an d volume redu ction wer e n ot included in t his estimate because there was n ot a significant cost advantage.

6.4 RE MED IATIO N ME TH O D S

Th e goal in choosing remed iation met h ods is to select the minimum cost option to accomp lish a task. T h ere are many factors whi ch n eed to be cons idered wh en se lectin g a met h od such as con taminatio n levels, degree of penetratio n of contaminatio n into substrate mate r ial, equipme nt cost, suppo1t equipme nt costs, mate r ial an d chemica l costs, th e generation of secondaiy waste vo lumes (waste in additio n to the removed contam inated mate rial), processing rates, labor requireme nts, and applicabi lity to various tasks. Typ ical decontaminatio n processes ai*e summa r ized in Table 6-6. F or each deco ntaminat i on met h od, this table shows applicat i on info n natio n, the process cost per squai*e foot of ai*ea decontaminated, and th e amo unt of seconda1y waste gen erated. These unit facto r s may be applied to speci fic ar eas or equ ipment requ iring remed iati on to dete n n ine the most cost -effective process.

Tabl e 6-6: Decontamination Me thod olo gy C ompari son

Pen e tra tio n Pi-oc.ess S e co ndar y d e p t h C r ew Cos t W a s t e Vo lum e Me thod ology A ppli c.a ti o n (in ) S ize ($/ft2 ) (f t 3 /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

B las trac 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 B las ter L TC 10- 60Pn Special All swfaces l/16 1.3 $ 4.22 0.53 Vaculllll B las ter

CO2 Blas t ing All Surfaces 0 2.0 $5.21 0

Hydrolaser (5 - 10,000 psi) All Smfaces 0 2.0 $ 1.08 9.07

Hands - on-De con Non-Porous 0 1.0 $2.47 8.33 surfaces

6.5 RADIO ACTIVE W AS T E VO L UME RED UC TI ON COS T S

The volume r eduction an d waste treatme nt processes an alyzed for use ar e summa r ized in Table 6-7. For each volume reduction method, th e table sh ows applicat i on info n nation, tran spor tatio n container type, an d the total process cost per unit we i ght. These unit factors may be applied to specific items of equipment r equ iring disposa l to detenn in e the most cost -effective process. The radioactive waste generated at th e ARRR fac i lity wi ll inclu de inadiated h ardware, activated con crete, HE P A ve ntilation systems, fume hoods, steel, lead, and seco n daiy waste gen erate d

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dur ing th e deco n tamination work, s u ch as protective clot hing and material s used during manual deco n tamination work.

T a ble 6-7: Volum e R edu ction /Tr eatm ent Me tho d s Cost Inform a tion

Trans port Total C ost VR Me thodolo gy Applic a bili ty Co ntainer Typ e ($/lb)

Su per Compact i on D1y active waste B-25 for Clive Utah $6.46 20 lb/ft 3 Disposa l Lead Deconta min ati on B ricks and Sheet Cu stom Box $5. 14 Survey & Release Low Density Waste 55 GalDrnm $2.49 Low Density D nnns Survey & Release Waste at g r eater th an B -25 Box $ 1. 33 Med ium De nsity Boxes 20 7< 60 lb/ft 3 Survey & Release Waste at greater th an B -25 Box $0.96 Hi gh D ens i ty Boxes 60 lb/ft:3

6.6 UNI T C O ST S

A n umbe r of unit cost facto r s were u sed to generate t he total decommission ing cost esti mate.

Th e ma in unit cost facto rs are listed in Tab l e 6-8, so t hat indiv i du al decommiss i onin g costs can be updated whe n r equired an d the effects of rev ised uni t costs can be evaluated.

Tabl e 6-8: Decommi ss ioning Cost Es timat e Selecte d Unit C ost F act ors U nit C ost F actor U nit C ost Rate U nit s Low Level Radioactive Waste Disposa l at C live, Utah $13 1.00 cub i c foot Resin and Lead Disposa l at C live, Utah $253.00 cub i c foot Waste Transportat i on to Clive, Utah $5.40 mile Transportat i on Distan ce to Clive, Utah 609 mi l es B-25 Waste Disposal Con tainer Cost $2,530.00 each Man ageme n t and Superv i sion $ 159.60 h our Eng ineer $ 125.40 h our Rad i ati on P rotection Superv i sor $ 129.00 h our L abo r er For ema n $85.00 h our Admin i strat ive Assistant $ 41.12 h our Instrnme n t T echn i cian $8 1.51 h our Radi ati on Protectio n Tec hnician $8 1.51 h our Labo r er $78.69 h our Fee 15%

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6.7 FINAL SURVEYS

Final survey costs are estimated based on the faci lity 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 su rveys 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 summari zed in Appendix A-6 and the open land and miscellaneous areas survey labor esti mate is summarized in Appendix A-7.

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7. 0 F A C ILITY, C O NDITIO NS AND DEC O MM I SS IO NIN G SCEN ARIO

Decommission ing of t he ARRR requ ires t h at r esidua l ra dioac tive mate r ials be removed from the site to allow removal of th e decomm issioned fac i lities from th e NRC license and State of Californ i a L i cense. Fo r the purposes ofthis cost estimate, the en d of the decommission ing project occurs wh en the ARRR has been remedia ted to r elease limi ts an d the F inal Status Surv ey has been completed, documented and the survey r esu lts submitted to the NRC an d t h e State of Californ i a.

7. 1 RE ME DIATI ON SUMM AR Y

Remed iati on w i ll be r equired fo r th e ARRR bui l dings an d systems, but it is n ot antic ipated that remed iati on of sewer s and outdoo r areas w i ll be r equired. Tab l e 7-1 below is a brief summaiy of th e antic ipated r emediatio n activ i ties, with app li cab l e assumptions and bases. Add i tion al faci li ty info1ma tion, rad iological info1mat ion, and decommissio ning p l an s are presented in greate r detail in t h e document sect i on s th at fo ll ow.

Tabl e 7-1 : ARRR Plann e d R em e diation Ac ti vi ti es Buildin g or Area Remediation A c ti v i t i es Gen eral Ar ea Perfo 1m a gen eral facility clean up to r emove a ll incidental equ ipme nt and ma teri als, whic h inclu des both radioact ive and non-radioactive waste o n site prior to decommissio ning. This activity is per fo1med as pait of pr epai*ation activ i ties th at can be completed at any time pr ior to reacto r decomm ission ing.

Non-Reac tor Remove a ll equipment and mate r ials n ot assoc iated w it h operation of th e Remedia t ion reactor. This inclu des equipme nt used in t h e prepara t ion for N-Ray activ i ties an d th e N-Ray compo nents outs i de the r eacto r tank. These activ i ties ar e perfo1med as pait of pr epai*ation work that can be completed at any time pr ior to reacto r decommission ing.

TRI GA R eacto r E mp ty water from the r eacto r tank. R emove t h e activated r eacto r core,

vessel int ernals, br idge, and r eacto r vessel. Remove Beam catch er, bios hield wood an d bios hield blocks. Remove N-Ray compo n ents including neut ron guide, expos ure tray and shie l ds. Leave beam po1t in place, as i t is unused an d not activate d. Cu t out activated concr ete surrounding the r eacto r tank an d dispose of as rad i oactive waste.

Dem in. & Heat Remove the Demineralizer and Heat Exch ange Systems, decontam in ate the Exch an ge Systems conc r ete pads in each buil ding and demo lish th e buil dings.

Reactor H igh Bay Remove a ll equipment an d ma terials from th e Reacto r Hi gh Bay build ing Buil ding tha t are n ot pa1t of th e struct ur e or utili ties. Remove cont amina ted po1tion s of the HV AC system, if anv.

Oth er Bui ldings R emove a ll equipment and ma terials from oth er buil dings t hat are not pait of the structure o r u tilities.

Outdoor Ar eas Remove all equ ip ment and ma terials o utside of bu ildings th at ar e not pa1t of site u tiliti es. T his in cludes the Cooling Towers, Waste Tank System,

Shie l ding, spare ion exchange column s, etc.

Page 75 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

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

Page 76 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

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 ta nk walls will have decayed to insignificant levels and the activity in the concrete behi nd 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 dispos al. 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 ar e 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 build ing 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 dis posal 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.

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• 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 rem oved 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 ma terial 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 fr om site. The asbestos floor tile will be surveyed, removed and sent for disposal as asbestos waste or radioactive waste.

Page 78 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

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 dis posal 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 surv eyed at accessible areas and released for continued use.

Page 79 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

Activated concrete near core removed

Activated concrete below core removed -------------.

Figure 7 1: ARRR Activated Concrete

Page 80 of 95 D ecommi ss ionin g Cos t Es timat e for the CS-HP-PR-00 6 A erot es t R a di ograph y and R es ea r ch R e actor R ev i sion 6

7.2 LI CENSE T ERMINATION SURVEYS

License t ennin atio n surveys, or fi n al status rad i ati on surveys, will be per fo1med in the applicable ar eas of the sit e using th e guidance prov i ded in NUREG - 157 5, Mu lti-Agency Radiation Survey and Site Investigatio n Man ual (MARSSIM), (Ref. 8.8). The s m veys w i ll b e perfo 1med in accordance with plans and procedmes spec i fically developed for the ARRR facility.

7.2.1 S m v ey Instrume n tat ion

Sel ectio n and use of instrumentat i on w i ll ensme sens it iv it ies ar e suffic i en t to detect th e i den t i fied nuclide s at the min imum detection requi r eme n ts. A list of typical final s m vey instrume n t at ion,

radiatio n detected, and calibrat i on som ces are provided in Tab l e 7-2.

Tabl e 7-2: T y p ica l Final Su rvey In strum entation

In strum e nt / De t ector Radiation Ca librati o n Det ector Typ e Dete c t ed Sour ce Us e Ludlum Model Direct alpha and 2350 wt. 43-68, Gas-flow 99Tc ( ~) direct beta 43 -98, 43-94 or 43-proportional Alpha or beta 2(126 cm2) scans on solid 30Tb (a.) smveys ; Beta 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 detector smfaces. cm 2) scans on solid

Ludlum Model Nal (Tl) Gamma exposure 2350 wt. 44-2 or Scintillato r Gamma 137Cs rate and gamma 44-10 detector scans.

Eberline Teletect or Ion Chamber Gamma 6oCo (y) Gamma expo sure Model 6112B ra te 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

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

Page 82 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

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 285 Components 0 0 285 Buildings 34 62 456 552 Outdoor Areas 6 0 708 714 PoolWater 5 5 6 16 Lead 13 0 13 26 TOTALS: 122 67 1817 2006 1Generated wasteincludesprotectiveclothingandequipmentgeneratedbysiteoperations 2Decon wasteisvolumegeneratedbydecontaminationprocesses(includesitemssuchas sandblastinggrit,etc.)

Page 83 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

Appendix A-2 Contaminated Waste Disposal Cost Tab l eA2 Rad i o acti v eWaste Packaging,Shi ppi ng&Di s p o s alCosts ARRR,CA

- Rad i o acti v eWaste Di s p o s alCosts

Generated Decon Clive To tal Are aDescription Clive Clive Di re ctBuri al W as te Disposal Disposal Disposal Disposal Costs Costs Costs Costs TRI GAR e a ct o r 7, 146$ $ 426, 110$ 433, 256$

TRI GABi os hi e l d&N RayCompone nts $ $ 52, 666$ 52, 666$

Bui l di ngs 6,598$ 9, 243$ 67, 770$ 83, 611$

OutdoorA r e a s 3, 901$ $ 79, 413$ 83, 314$

To t al s 17,645$ 9, 243$ 625, 959$ 652, 847$

Rad i o acti v eWaste Packaging&Shi ppi ngCosts*

Generated Decon Clive To tal Are aDescription Clive Clive Di re ctBuri al W as te Pack/Ship Pack/Shi p Pack/Ship Pack/Ship Costs Costs Costs Costs TRI GAR e a ct o r 473$ $ 12, 651$ 13, 123$

TRI GABi os hi e l d&N RayCompone nts $ $ 49, 994$ 49, 994$

Bui l di ngs 298$ 542$ 14, 894$ 15, 734$

OutdoorAreas 50$ $ 19, 265$ 19, 315$

To t al s 821$ 542$ 96, 804$ 98, 166$

• D o esnoti nc l udelabor

To talRad i o acti v eWaste Packaging,Shi ppi ng&Di s p o s alCosts*

G e n e rate d De con Di re ctBuri al Total Are aDe s cri p ti o n W as te W as te W as te Al lWaste TRI GAR e a ct o r 7, 619$ $ 438, 761$ 446, 379$

TRI GABi os hi e l d&N RayCompone nts $ $ 102, 660$ 102, 660$

Bui l di ngs $ 9, 7856, 896$ 82, 664$ 99, 345$

OutdoorA r e a s 3, 951$ $ 98, 678$ 102, 629$

To t al s 18, 466$ 9, 785$ 722, 763$ 751, 014$

Page 84 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

Appendix A-3 Waste Shipping Container Cost TableA3 WasteShipping Container (B25) Costs ARRR,CA Total B25 Waste Waste Waste Container AreaDescription Volume Containers Costs (ft3) (Each)* ($)

TRIGAReactor 403 5 $11,499 TRIGABioshield &NRay Components 285 4 $8,132 Buildings 552 6 $15,751 Outdoor Areas 714 8 $20,373 Totals 1,954 23 $55,755

• Numberofcontainersroundedtonextwholenumber

Page 85 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

Appendix A-4 Waste Disposal Support Labor Estimate TableA4 WasteDisposal SupportLaborandB25 ContainersCosts ARRR,,CA B-25 Waste Waste WasteShipment

AreaDescription Containers(ea) Shipments Labor(Manhours)

TRIGAReactor 4.8 0.7 13.6 TRIGABioshield &NRay Components 3.8 1.5 81.6 Buildings 6 1 18 Outdoor Areas 8 1.3 25 PoolWater 0.2 N/A 1 Lead 0.3 N/A 1 Totals: 23.1 4.5 140.2 Notes:

Numberofwasteshipments roundeduptonextwholenumber Does notincludecask shipments(seebelow)

WasteDisposal SupportLabor,CaskRental&Transportation Costs ARRR, CA Liners/Cask CaskRental & CaskSupport AreaDescription Rental(ea) TransportCosts Labor(Manhours)

TRIGAReactor 0$ 0 TRIGABioshield &NRay Components 1$38,560 72 Buildings 0$ 0 Outdoor Areas 0$ 0 Totals: 1$38,560 72 Notes:

Transportationcosts includetruckrentaland drivercosts

Page 86 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

Appendix A-5 Radioactive Waste Container, Cask and Labor Summary TableA5 RadioactiveWasteContainer,CaskandLaborSummary ARRR,,CA

Cask&Waste Waste To talWaste B 25 C ontai ne r Radi oacti ve Shi pme nt Shi pme nt Are aDe s cri p ti o n Volume(ft3) Containe rs Cost* Shipme nts Labor(Man hrs) LaborCost TRI GARe actor 413 4. 8 11, 499$ 0. 7 13. 6 1, 078$

TRI GABi oshi e l d&N RayCompone nts 285 3.8 42, 718$ 1. 5 81. 6 6, 467$

Buil dings 552 6 16, 909$ 1. 0 18 1, 426$

OutdoorAreas 714 8 21, 871$ 1. 3 25 1, 981$

PoolWate r 16 0. 2 563$ 0. 2 Le ad 26 0. 3 845$ 0. 3 Total s : 2006 23. 1 94, 405 5 138. 2 10, 952$

Notes:

Nu mb e rofco n ta i n e rs tobe rounded uptonextwhol e number,ifneeded Nu mb e rofwa s te shipments tobe rounded uptonextwhol e number,ifneeded

• As s u me s 1Typ e Aca s kshipment

Page 87 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

Appendix A-6 Building Survey Labor Summary IM P ACTED B UI LDING AREA SURVEY Table A-6 ARRR, California SURVEY UP PER GAMMA PACKAGE AREA AREA AREA FLOOR + U. WALL + FLOOR + W ALL + SURVEY SURVEY DIRECT BUILDING ROOM AREA REQRD WIDTH LENGTHHEIGHTL. WALL CEILING Survey L. WALL CEILING ROOF or PKG SURVEY LOC NAME NUMBER DESCRIPTION ? SURVEY SURVEY Sketchs SURVEY SURV EY S URV EY 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-IM P ACTED B UILDING AREA SURVEY Table A-6 ARRR, California SURVEY PACKAGEAREA AREA AREAFLOOR +U. WALL +ENTER FLOOR + U. WALL + SURVEY DIRECT BUILDING ROOM AREA REQRD WIDTHLENGTHHEIGHTL. WALLCEILINGSurvey L. W ALL CEILING ROOF TOTAL PACKAGE SURVEY LOC NAME NUMBER DESCRIPTION ? SURVEYSURVEY 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

Page 88 of 95 D ecommi ssionin g Cos t Es timat e for the CS-HP-PR-00 6 A erot es t R a diograph y and R es ea r ch R eactor R ev ision 6

App end ix A-7 Outd oo r A re a Surve y L abor Summar y NON-IMP AC TED PAVED AREA SURVE Y Ta b le A-7 ARR R Ca lifo rn ia I SU Rll£Y P/CKAGE Ml.EA NI.EA Nu imer Random Random SUR ll£Y 10%

SU RF/CE NlEA REQRD WIDT H LENGTH No.o f No. of No.of o f Surv ey Surv ey PACKAGE SU Rll£Y LOC TYP ES DESCRIPTION ? SU RVEY alpha be ta ganma Exp Rate Sketchs Sketch PREP LJBOR CODE IY/NI lftl lftl BLOC KS Scans Scan s Scans Msn m ts leachl HOIKS lhrsl Hour s 4 Aspha lt East Paled Area y 22 142 5 0.50 0.50 0.5 0.5 2 0.67 4 4.7 4 Aspha lt North Paled Area y so 11 0 8 0.80 0.80 0.8 0.8 2 0.67 4 4.7 4 Aspha lt Wes t 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 UNP AVE D AREA SURVEY Tabl eA-7 ARRR, aliforn ia ENTER SUR VE Y EtlTER ENTER EtlTER BB. OW ENTER ENTER PACKAGE AREA AREA lllmb<< lll b<< Ra ndom Random SIJIMY 101.

OPTIONAL SURFAC E AR£A ~ WIJTH LENC1H lllmbe, ol ol Su rvey Si.vty PACMGE SIM!VEY LOC TYPES DESCRIPTION ? BELOW BB.OW SlJMY of E:q Rtt, Soil Skettlls stt1th1 PRE P IABOfl CODE BELOW BB. OW IYINI lftl lftl 8LOO(S Scans Msnn nts Sa ple s jeachl HotrS (In) (hr,)

4 I S,& lrtes lfr t l~ 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

T a b le A-7 ARRR, - California C A TC H BAS I N & C L EA N-O UT S U RV E Y

BASIN SU RVEY DU R A110N (hrs): 4 BASIN SU RVEY CREW SIZ E (men ): 1 EN TER ENTER S U RVE Y BEL OW ENTER BASIN PAC KAGE SURVE Y OPTIONAL AREA DIAMETER REQRD PACKAGE S U RVEY LOC OESCR I P110N BELOW 7 PR EP LA BO R CODE BELOW (fl) ( Y IN) (h rs) ( h rs )

4 Wa ste Su m p 5.0 y 4 8.0 4 Ma rllo le on Storm Sewer 5.0 N 4.0

TOTALS 4 12 DRAIN PIPE SURV EY

PIPE SU RV EY RATE (ft/h r): 40 PIPE SU RVEY CR EW S IZ E (m en ): 3 ENTER ENTER ENTER S URVEY OP110N A L ENTER PIPE PI PE PACKAG E SU RVEY LOC AREA DIAMETER LENGTH R EQRD PA C KA GE SURV EY CODES DESCRIPTION BELOW BELOW 7 PR EP LABOR B EL OW B ELOW (ft) (ft) ( Y/ N) (hrs) (hrs) 4 Storm Dra in 24 150 y 4 15.3 4 Sa nita ry Sewer 24 150 y 4 15.3

TOTA LS 8 3 1

Page 89 of 9 5 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

Appendix A-8 Instrument Lease Charges

Table A-8 INST RUMENT COST S ARRR, California 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 IT E M INSTRUMENT MONTHLY INST RUMENTS 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 111Y $60 $479 $120 25 Ludlum Alarm Ratemeter, Model 177 $103 133Y $51 $1,231 $308 32 Ludlum Data Logger, Model 2350-1 $239 333Y $359 $2,873 $718 RADIATION DETECTORS FOR PORTABLE INSTRUMENTATION 44 Ludlum 50cm2 Alpha Scintillator, Model 43-5 $86 122Y $43 $684 $171 47 Ludlum 125cm2 Gas Proportional Detector, Model 43-68 $46 133Y $23 $547 $137 52 Ludlum Gamma Scintillator D etector, Model 44-10 $103 122Y $51 $821 $205 SUPPORT EQUIPMENT FOR RADIATION PROTECTION INSTRUMENT A 58 Ludlum Floor Monitor Cart, Model 239-1F $120 1 2 2Y $60 $958 $239 SEMI-POR TABLE R ADIATION PR OTEC TION IN STRU MEN TATION 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 111Y $137 $1,094 $274q GAMMA SPECTROSCOPY EQUIPMENT C a nbe rra In-S i tu Ob jec t C ounti ng S ys tem (IS OC S ) i nc lud i ng : HP Ge D ete cto r 82 (GC4020 or RE5020 available), Inspector-2K MCA, Big-MAC Dewar, 1" or $7,695 111Y $3,848 $30,780 $7,695 2" Lead Collimator/Shields, Mobile Cart or Tri-Pod.

Canberra Laboratory Gamma Spectroscopy System wi th D i p Sti ck HPGe 83 Detector, Laboratory Dewar, Digital MCA, Low Background Shield/Table, PC, and Genie-2K Software 84 GC 3020 Detector (30% Relati ve Effi ci ency) $2,822

87 Canberra Portable Gamma Spectroscopy System with Intregal HPGe Detector/Dewar, Inspector MCA, Laptop Computer, and Genie-2K Software EG&G Laboratory Gamma Spectroscopy System with Dip Stick HPGe 90 Detector, Laboratory Dewar, DSpec MCA, Low Background Shield/Table, PC, and Gamma Vision Software 92 GEM-35190-P Detector (35% Relative Efficiency) $2,565 EG&G Portable HGPe Gamma Spectroscopy System with PopTop HPGe 93 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 111Y $51 $410 $103 106 Th-230 47mm Alpha Source $103 111Y $51 $410 $103 109 Mixed Gamma, 250 ml Sand Marinelli, 133N $239 111Y $120 $958 $239 113 Mixed Gamma, 47mm Filter Paper $239 111Y $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 T OT AL INSTRUMENT LEASE COST $3,769 $41,823 $11,219

Page 90 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

Appendix A-9 Equipment Lease Charges

Table A-9 EQUIPMENT COST S ARRR, California 4 D&D M onths Duration -

1.0 F INAL S URV E Y M o n th s D u r a tio n

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 NORC LE A N Tri ple Head E lectri c HE P A V acuum : $1,345 1Y $5,381 OFFICE EQUIPMENT 11 Data Analysis Computer System : $182 12 Download Notebook Computers : $135 11Y $538 $135 SAMPLING EQUIPMENT 14 FISHER SCIENTIFIC -Top Loading Scale, 0-3 kg Model XE4100 : $171 11Y $684 $171 15 FISHER SCIENTIFIC - Class F S.S. Weight Set, 1mg-2kg CAT.# 0221531 : $40 11Y $160 $40 16 FISHER SCIENTIFIC - Oven, ISOTEMP 5.0 120VAC CAT.# 13247750G : $277 11Y $1,108 $277 23 Portable Multigas Monitor $156 1 1Y $625 $156 26 3/4" x 50' Air Hose $40 5Y $798 159 40'-45' Electric,Articulating Boom lift $2,394 1N 2$4,788 193 25 Ton Crane Truck.10 cents per mile over 50 Day/200Week/800Month $7,068 1N 1$7,068 T OT AL EQUIPM ENT LEASE COST $32,817 $888

Page 91 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

Appendix A-10 Consumable Costs

Table A-10 CONSUMABLE COST S 4 D&D M onths Duration ARRR, California 1.0 Final Survey Months Duration *-

0.5 Characterization Survey Months Duration CHAR. D&D FINAL SURVEY ITEM ITE M 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 42 $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 21 $0 $126 $63 48 Marinelli beaker, 250 ml sample container, 100 per case w lids $559 52 $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 51 $0 $439 $88 56 Tygon Tubing 1/8"+1/4"x 50' $92 42 $0 $367 $184 57 TWEEZERS / FILTER FORCEPS, VWR PT. # 30033-042 OR EQUAL, Ea $23 21 $0 $47 $23 60 Eberline, soil, Gamma Scan (HPGe) gammma) $160 20 $0 $0 $3,194 66 Eberline, soil, Full Envirocare analysis $3,762 12 $0 $3,762 $7,523 67 Asbestos Analysis $80 10 $0 $799 $0 68 1/4" Sieve stainless Sample Prep $222 41 $0 $887 $222 0 H&S Supplies and Equipment $0 95 8' Fiberglass Step Ladder $332 21 $0 $664 $332 103 PRINTER/COPIER PAPER $51 41 $0 $204 $51 104 LOG BOOK, 8.5" X 11" $6 41 $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 82 $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 42 $0 $7,665 $3,832

$0 $93,841 $37,547

Page 92 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

Appendix A-11 Demolition Estimate

Table A-11 D e m o lit io n E s t im a t e ARRR, C a lifo r n ia

- LABOR BASED DEMOLITION COSTS: Labor by man-hour M an agemen t, S u pervisio n, & H P 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 ho ur s P RIC E 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

T ASK BASED DEM OLIT ON COST S 67% Haz ardous & 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 TOTA L TOTA L TOTA L TOTA L C OD E No. A RE A QUA NTITY UNIT P RIC E P RIC E P RIC E P RIC E P RIC E P RIC E P RIC E 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

Page 93 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

Appendix A-12 Miscellaneous Items Volume Estimate

LOC WB S NUMB ER MATERIAL B ULK UNIT UNIT TOTA L TOTA L VOL CLIVE D ESC R IP T ION CODE/ OF OF DENS ITY WEIGHT VO L U M E WEI GH T VOL U M E %D I R E C T D I S P O S A L DISPSTN UNITS UNITS CONS TRUCT (lb/ f t ^3) (lb) (ft^3) (lb) (f t^3) BURY WT ( l b) VOL

. (f t^3)

TRIGA Rector I I I I I I I I I A c t i v at ed Har dwar e 1 Ea 2 Mi sc 100.0 60.0 16,0002,000 120.0 100% 12,000 120 CLIVE P ool Tank Cy l i nder 1 Ea 1 A l 12,6315. 2,631 15. 100% 2,631 15 CLIVE P ool Tank B ot t om ( est i mat ed@ 3/ 4" ) 1 Ea 1 A l 5. 858 5. 185800% 858 5 CLIVE P ool Tank t op Fl ange ( A l angl e 1 Ea 1 A l 0.6 110 101 0.6 100% 101 1 CLIVE P ool Int er i or A l A ngl e Ri ng @ 7' 1 Ea 1 A l 0.5 95 0.5 19500% 95 1 CLIVE,-

P ool Fuel Rac k A l A ngl e Ri ng @ 7' 1 Ea 1 A l 0.1 24 0.1 12400% 24 0 CLIVE P ool Tank Conc r et e Li ner ( Nomi nal 2' wi t h 1 Ea 1 Conc. 1265,795,935. 265,795 1,935. 0% 0 LEA VE P ool Tank Conc r et e S uppor t pad ( 1-f t wi t h 1 Ea 1 Conc. 121,14354. 21,143 154. 0% 0 LEA VE P ool Ex per i ment / Fuel Rac k s 1 Ea 3 A l 2. 66 5. 12200% 66 5 CLIVE,-

Reac t or P ool Wat er 1 ft 3 1,738 Wat er 62. 1.0 108,494 1,738. 0% VR62 Ther mal Column (Gr aphit e) 1 Ea 1 Car bon 140.0 154.0 2 247 154.0 100% 2 247 5 CLIVE2,247 Ther mal C ol umn ( A l umi num) 1 Ea 1 A l 175.0 5. 114 646 5. 100% 146 5 CLIVE S hel l ( t aper s 8x 10 t o 22x 34) 5/ 8" wal l 1 Ea 1 A l 15. 66. 963 66. 196300% 963 66 CLIVE B eam Tube Gr aphi t e ( 9" x 11" ' x 4' ) 1 f t 3 3. Car bon 140.0 1.0 385 3. 100% 385 3 CLIVE14 0 B eam Tube Lead 1 ft 3 3.30 Lead 708.0 1.0 2,334 3. 100% 2,334 3 CLIVE708 B eam Tube S hut t er 1 Ea 1 A l / S S 100.0 0 67 67 0.7 16700% 67 1 CLIVE Regul at i ng Cont r ol Rods ( B 4C) 1 Ea 1 Mi sc 187 0.0 5 0.0 1500% 50 CLIVE Shim & Saf et y Cont r ol Rods (B4C) 1 Ea 2 Misc 187 0.1 21 0.1 100% 21 0 CLIVE11 Cont r ol Rod Dr i v e Connec t i ng Rod 1 Ea 3 A l 175 0.1 42 0.2 11400% 42 0 CLIVE Cont r ol Rod Ex t ensi on Tube 1 Ea 3 A l 22 0.4 29 110. 100% 29 1 CLIVE Cont r ol Rod Dr i v e A ssembl y 1 Ea 3 Mi sc 38 0.8 90 2. 13000% 90 2 CLIVE Cont r ol Rod Gui de Tube ( ~ l engt h: f uel + 1 Ea 3 A l 58 0.0 7 0.1 1200% 70 CLIVE Neut r on S our c e Hol der 1 Ea 1 A l 175 0.1 1199 0.1 100% 19 0 CLIVE Gl or y Hol e 1 Ea 1 A l 175 0.2 39 0.2 13900% 39 0 CLIVE Ver t i c al Tube (3/ 16" wal l) 1 E a 1 A l 7. 19 13 6 19. 10 0 % 13 6 19 C L I V E13 6 Ver t i c al Tube Lead di sk s i n t ube bot t om 1 Ea 1 Lead 708 1991. 991 1. 100% 991 1 CLIVE Lg. Component Ir r adi at i on B ox ( 20c f, 1 Ea 1 A l 4.0 20.0 81 20.0 18100% 81 20 CLIVE Top Gr i d P l at e ( 5/ 8" ) 1 Ea 1 A l 175 0.1 24 0.1 12400% 24 0 CLIVE,_

B ot t om Gr i d P l at e ( 3/ 4" ) 1 Ea 1 A l 175 0.2 29 0.2 12900% 29 0 CLIVE Inst r ument Gui de Tube 1 Ea 4 A l 15 120. 80 6. 100% 80 5 CLIVE Cont r ol Inst r ument Chamber s 1 Ea 2 Mi sc 59 0.3 40 0.7 12000% 40 1 CLIVE Cor e Cy l i ndr i c al S hr oud ( 50% c ut out ) ) 1 Ea 1 A l 11 116 44. 164 14. 100% 164 14 CLIVE Cor e Cy l. S hr oud A t t ac h. A ngl e 1 A l l 1 A l 11 0.7 8 0.7 1800% 81 CLIVE Cor e S uppor t T-B eams 1 Ea 4 A l 37 0.9 13125 3. 100% 125 3 CLIVE S uppor t B r i dge 10- i nc h S t eel I-B eams 1 Ea 2 CS 101 4. 758 8. 137900% 758 8 CLIVE S uppor t B r i dge 10- i nc h S t eel I-B eams 1 Ea 2 CS 101 0.6 16428 1. 100% 128 1 CLIVE S uppor t B r i dge 10- i nc h S t eel I-B eams 1 Ea 2 CS 101 0.7 17040 1. 100% 140 1 CLIVE S uppor t B r i dge 3/ 4" CRD Dr i v e Mount i ng 1 Ea 1 A l 175 0.3 57 0.3 15700% 57 0 CLIVE S uppor t B r i dge Tr ead P l at e 1 1 Ea 2 CS 491 0.2 17549 0.3 100% 149 0 CLIVE S uppor t B r i dge Tr ead P l at e 2 1 Ea 2 CS 491 0.1 75 0.2 13700% 75 0 CLIVE,_

Bioshield & N-Ray I Radi at i on B eam Cat c her S hi el d 2 Ea 1 Mi sc 84. 116 06. 1,314 16. 100% 1,314 16 CLIVE S hi el d B l oc k s Ful l ( 40x 20x 20) 2 Ea 72 Conc. 142 9. 94,511, 3 139 667. 0% 0 LND FIL S hi el d B l oc k s Ful l wi t h hol es ( 40x 20x 20) 2 Ea 2 Conc. 142 9. 2,626 11, 3 139. 0% 0 LND FIL S hi el d B l oc k s Hal f - hei ght ( 40x 20x 10) 2 Ea 12 Conc. 142 5. 7,877 56. 0% 0 LND FIL656 S hi el d B l oc k s Hal f - l engt h ( 20x 20x 20) 2 Ea 4 Conc. 142 656 5. 2 626 19. 0% 0 LND FIL S hi el d B l oc k s S pec i al l ar ge ( 48.75x 20x 20) 2 Ea 4 Conc 142 1f,600 11. 6,400 45. 0% 0 LND FIL S hi el d B l oc k s S pec i al l ar ge ( 80x 20x 20) 2 Ea 1 Conc. 1I I I I,-42 2,626 19. 2,626 19. 0% 0 LND FIL Wooden ( f i r ) beams 2 Ea 1 Wood 31 206.250 6,438 206. 1I I I 6,43800% 6,438 206 CLIVE Mov abl e Exposur e Tr ay 2 Ea 1 Al 10 57.870 579 58. 100% 579 58 CLIVEI I I,_ 579 Tr ay End S hi el d 2 Ea 2 Mi sc 500 2. 2,311, 15 75 5. 100% 2,315 5 CLIVE Mi sc Lead br i c k s 2 Ea 4 Lead 708 0.037 12605 0.15 0% 0 VR Reac t or Tool s ( 1 B - 25 B ox Ful l ) 3 Ea 1 Mi sc 24. 37. 1876,076 90.0 100% 1,076 90 CLIVE

Page 94 of 95 Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 6

Appendix A-12 Miscellaneous Items Volume Estimate (Continued)

Radwaste Room Car dboar d box / ber i l l i um supplier 3 Ea 1 Misc 0 3 10 0.3 100% 10 0.3 CLIVE10 Lead shi el ds on bac k wal l 3 Ea 20 Lead 0.7 393 1203. 0% 00.0 VR Shielded shipping c ont ai ner 3 Ea 1 Lead 1 0 600 1600.0 0% 00.0 LEA VE S mal l box of l ead wool ( 12" x 18" x 3" ) 3 Ea 1 Lead 0.4 212122 0.4 100% 212 0.4 CLIVE Act ive chemicals (U3O8, t hor i um ni t r at e, 3 Ea 1 Misc 0 3 10 0.3 100% 10 0.3 CLIVE10 Cof f ee c an of l ead f r om east t r enc h 3 Ea 1 Lead 0.1 42 0.1 14200% 42 0.1 CLIVE Propor t i onal c ount er 3 Ea 1 Mi sc 0 2 7 0.2 1700% 70. CLIVE Ion c hamber det ec t or 3 Ea 1 Mi sc 0 2 7 0.2 1700% 70. CLIVE Ion c hamber s 3 Ea 2 Mi sc 0 3 174 0.7 100% 14 0.7 CLIVE Met al wast e c an wi t h shot ~8" x 8" x 12" t al l 3 Ea 1 Lead 252 0.4 252 0.4 100% 252 0.4 CLIVE B ox of l i qui d st andar ds 3 Ea 1 Mi sc 40 1 0 40 1.0 100% 40 1.0 CLIVE Lead shi el di ng on bac k wal l 3 Ea 1 Lead 0 3 110 000 0.3 0% 00.0 VR Lead seal s i n c of f ee c an 3 Ea 1 Lead 0.1 28 0.1 12800% 28 0.1 CLIVE Gr i ndex Inst r ument by B r i c k Cav e 3 Ea 1 Mi sc 0 2 26 0.2 12600% 26 0.2 CLIVE Lead S heet by br i c k c av e ( 12 br i c k s 3 Ea 1 Lead 0.4 313155 0.4 0% 00.0 VR Or i gi nal shut t er ~ 2 mR/ hr 3 Ea 1 Mi x ed 0.7 67 0.7 16700% 67 0.7 CLIVE Lead f or m smal l br i c k c av e ( ~40 br i c k s 3 Ea 1 Lead 2. 11,540,540 2. 0% 00.0 VR Buildings Lead f or m br i c k c av e ( ~156 br i c k s 3 Ea 1 Lead 7. 4,798 7. 0% 00.0 VR4,798 B uc k et of i r r adi at ed l ead shot ~12" di a x 3 Ea 1 Lead 0 5 278 0.5 127800% 278 0.5 CLIVE GE f i ssi on det ec t or 3 Ea 1 Mi x ed 0 0 1 0.0 1100% 1 0.0 CLIVE P r opor t i onal c ount er 3 Ea 1 Mi x ed 0 2 7 0.2 1700% 70. CLIVE Chemi c al S hed 3 Ea 1 Met al 611,223. 1,223 61. 0% 00.0 LND FIL Heat Ex c hange B ui l di ng 3 Ea 1 Mi x ed 256 0 5,15,12020 256.0 100% 5,120 256.0 CLIVE Heat Ex c hanger 3 Ea 1 Mi x ed 7. 334 7. 133400% 334 7. CLIVE Heat Ex c hanger P ump 3 Ea 1 Mi x ed 6 0 115 050 6.0 100% 150 6.0 CLIVE Heat Ex c hanger pi pi ng 3 Ea 1 A l umi num 8 0 241 8.0 124100% 241 8.0 CLIVE Mi sc S uppor t s and Inst r ument s 3 Ea 1 Mi x ed 600 20 0 600 20.0 100% 600 20.0 CLIVE Demi ner al i z er B ui l di ng 3 Ea 1 Mi x ed 3,081 154. 3,081 154. 100% 3,081 154. CLIVE Demi n P ump 3 Ea 1 Mi x ed 60 2. 60 2. 100% 60 2. CLIVE A i r S ampl er 3 Ea 1 Mi x ed 30 1 0 30 1.0 100% 30 1.0 CLIVE Demi n Lead S hi el di ng 3 Ea 24 Lead 74 0.10 1,770 3. 0% 0 0.0 VR Fl or esc ent Li ght Fi x t ur e ( P CB 3 Ea 12 Mi x ed 3. 0.06 40 0.7 100% 40 0.7 CLIVE Fl or esc ent Li ght Fi x t ur e ( B ul bs) 3 Ea 24 Gl ass & Met al 1.0 0.10 24 2. 100% 24 2. CLIVE Reac t or B ui l di ng Gener al Cl eanup Wast e 3 ft 3 60 30.0 1,800 60 100% 1,800 60 CLIVE Outdoor Areas Wast e S ump Cy l i nder 4 Ea 1 Conc r et e 6,912 58. 6,912 58. 100% 6,912 58. CLIVE Wast e Sump Pump 4 Ea 1 Mix ed 60 2. 60 2. 100% 60 2. CLIVE Wast e S ump B ot t om S l ab 4 Ea 1 Conc r et e 2,160 18 0 2,160 18.0 100% 2,160 18.0 CLIVE Wast e S ump Mi sc P i pi ng & S uppor t s 4 Ea 1 Mi x ed 300 10 0 300 10.0 100% 300 10.0 CLIVE Cool i ng Tower ( Mar l ey ) 4 Ea 1 Mi x ed 1,758 264 0 1,758 264.0 30% 527 79.2 CLIVE/ LF Cool i ng Tower P ump 4 Ea 1 Mi x ed 150 6 0 150 6.0 100% 150 6.0 CLIVE S par e Cool i ng Tower 4 Ea 1 Mi x ed 5,181 864. 5,181 864. 0% 5,181 0. LND FIL Fuel S hi ppi ng Cont ai ner s ( 4 ea) 4 Ea 4 S t eel & Conc 888 8. 3,552 30.0 100% 3,552 30.0 CLIVE

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