ML14161A222
| ML14161A222 | |
| Person / Time | |
|---|---|
| Site: | Aerotest |
| Issue date: | 08/11/2010 |
| From: | Ely P EnergySolutions |
| To: | Aerotest, Office of Nuclear Reactor Regulation |
| References | |
| TAC MF2979 CS-HP-PR-006, Rev. 1 | |
| Download: ML14161A222 (103) | |
Text
ENERGYSOLUTIONS C S-HP-PR-006 Decommissioning Cost Estimate for the Aerotest Radiography and Research Reactor San Ramon, California Project No. 313150 Revision 1 Prepared for:
Aerotest Operations, Inc.
Prepared by:
EnergySolutions, LLC Technology, Engineering & Services 1009 Commerce Park Drive, Suite 100 Oak Ridge, TN 37830 Authored By: 10/4/12 Paul Ely, Engineer Date Reviewed By: 10/4/12 Steve Croslin, CHP Date Approved By: 10/4/12 Ben Sklar, Project Manager Date X Non-Proprietary W-New
-]Proprietary Title Change W-Restricted Information Revision
-- ] Safeguards Information W Rewrite W Sensitive Security Information - Cancellation Effective Date 10/5/12 Electronic documents, once printed, are uncontrolled and may become outdated.
Refer to the intraweb or the Document Control authority for the correct revision.
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 TABLE OF CONTENTS Section Page LIST O F FIG U RES ................................................................................................................ 4 LIST O F TA BLES .......................................................................................................................... 6 1.0 A CRO N Y M S AN D A BBREV IA TION S ....................................................................... 9 2.0 EX ECUTIV E SU M M A RY ......................................................................................... 10 3.0 IN TRO D UCTION ....................................................................................................... 11 3.1 Purpose ............................................................................................................. 11 3.2 Scope ..................................................................................................................... 12 3.3 A ssum ptions and Bases ...................................................................................... 13 4.0 G EN ERA L SITE D ESCRIPTION ............................................................................... 15 4.1 Current Facility Status ....................................................................................... 15 4.2 Proposed A ction and A lternatives .................................................................... 16 4.3 A dm inistrative Controls ..................................................................................... 18 5.0 D ECO M M ISSION IN G CRITERIA ............................................................................. 26 5.1 Radionuclides of Interest .................................................................................. 26 5.2 Radiological Criteria for License Term ination ................................................. 28 5.3 Facility Description .......................................................................................... 30 5.3.1 Reactor Building .................................................................................. 30 5.3.2 Building A ddition I ............................................................................. 38 5.3.3 Tagging A rea Building ........................................................................ 40 5.3.4 Dem ineralizer Building ......................................................................... 41 5.3.5 Heat Exchanger Building .................................................................... 41 5.3.6 Cooling Tow ers ..................................................................................... 41 5.3.7 M aintenance O ffice Building ................................................................ 41 5.3.8 Com pressor Building ........................................................................... 42 5.3.9 Chem ical Shed ..................................................................................... 42 5.3.10 Class 1.1 Explosive Storage Container ................................................. 42 5.3.11 Storage Building .................................................................................. 42 5.3.12 W aste Storage Tanks and Sum p .......................................................... 42 5.3.13 Land A rea ............................................................................................... 42 5.4 Relation of the A RRR to Other TRIG A reactors ............................................. 43 5.5 O utside A reas ................................................................................................... 43 6.0 ESTIM A TION M ETH O D S .......................................................................................... 72 6.1 Cost M odifying Factors .................................................................................... 72 Page 2 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 TABLE OF CONTENTS (CONTINUED)
Section Page 6.2 Radioactive Waste Volume Estimates ............................................................. 76 6.3 Radioactive Waste Disposal Costs ..................................................................... 76 6.3.1 C live U tah D isposal Costs .................................................................... 76 6.3.2 EnergySolutions Processing/Burial Costs ............................................. 76 6.4 Rem ediation M ethods ....................................................................................... 77 6.5 Radioactive Waste Volume Reduction Costs ................................................... 77 6 .6 U n it C o sts ......................................................................................................... . . 78 6.7 F inal Surveys ................................................................................................. . . 78 7.0 FACILITIES, RADIOLOGICAL CONDITIONS AND DECOMMISSIONING SC EN A R IO ................................................................................................................................... 80 7.1 Rem ediation Sum m ary ..................................................................................... 80 7.1.1 G eneral A rea C leanup ............................................................................ 81 7.1.2 Non-Reactor Remediation .................................................................... 81 7.1.3 T R IG A R eactor ................................................................................... . . 81 7.1.4 Demin and Heat Exchange Buildings .................................................... 82 7.1.5 Reactor H igh Bay A rea ......................................................................... 82 7.1.6 High Bay Mezzanine Area .................................................................... 83 7.1.7 O ther B uildings ................................................................................... . . 84 7.1.8 O utdoor A reas ..................................................................................... . . 84 7.2 License Term ination Surveys ........................................................................... 85 7.2.1 Survey Instrum entation ......................................................................... 85 8.0 R E FE R EN C E S .......................................................................................................... . . 88 8.1 10 CFR 50.82 Termination of License, part (b),for Non-Power Reactor Licensees
............................................................................................................................... 88 8.2 10 CFR 20 Subpart E - Radiological Criteria for License Termination ........... 88 8.3 NUREG 1537, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, February 1996 ........................................... 88 8.4 R.A. Means Company, Inc., Means Building Construction Cost Data, 2011, 69st A nnual Edition ............................................................................................... . . 88 8.5 NUREG/CR-1756, Technology Safety and Costs of Decommissioning Reference Nuclear Research and Test Reactors, March 1982 .......................................... 88 8.6 CS-HP-PR-008, Characterization Report for the AEROTEST Radiography &
Research Reactor, San Ramon, California, October 2011 ................................ 88 8.7 10 CFR 20.1402 Radiological Criteria for Unrestricted Use ............................ 88 Page 3 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 TABLE OF CONTENTS (CONTINUED)
Section Page 8.8 USEPA, 2000, U.S. NRC, U.S. DOE, and U.S. DOD, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM), Revision 1, NUREG-1575, EPA 402-R 0 16 .......................................................................................... . . 88 8.9 NUREG-1757, Consolidated NMSS Decommissioning Guidance, Decommissioning Process for Materials Licenses, September 2002 .............. 88 8.10 NUREG/CR-5512, "Residual radioactive contamination from decommissioning:
parameter analysis", Volume 3, October1999 ................................................. 88 List of Changed Pages by Revision Revision Changed Page Comment 10 Changed estimate value and date 12 Changed estimate date 13 Changed estimate date I 72 Changed values in Table 6-1 78 Changed lead rate in Table 6-7 78 Changed values in Table 6-8 90 Changed waste disposal costs in Table A-2 91 Changed unit disposal cost factors for Table A-3 93 Changed shipping labor costs in Table A-5 99 Changed labor rates and costs for Table A-I I 101 Changed volume reduction costs in Table A-] 3 Page 4 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 LIST OF APPENDICES Section Page Appendix A I Contaminated Waste Volume Summary .......................................................... 89 Appendix A 2 Contaminated Waste Disposal Cost ................................................................. 90 A ppendix A 3 W aste Shipping Container Cost ........................................................................ 91 Appendix A 4 W aste Disposal Labor Estimate ........................................................................ 92 Appendix A 5 Contaminated Waste Disposal Summary ........................................................ 93 Appendix A 6 Building Survey Labor Summary ................................................................... 94 Appendix A 7 Outdoor Area Survey Labor Summary ............................................................ 95 A ppendix A 8 Instrum ent Lease Charges ................................................................................ 96 A ppendix A 9 Equipm ent Lease Charges ................................................................................ 97 A ppendix A 10 C onsum able Costs ......................................................................................... 98 A ppendix A II D em olition Estim ate ...................................................................................... 99 A ppendix A 12 D econtam ination Costs ..................................................................................... 100 A ppendix A 13 V olum e Reduction Costs ................................................................................... 101 Appendix A 14 M iscellaneous Item Volume Estimate ............................................................... 102 Page 5 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 LIST OF FIGURES Figure Page Figure 4-1: Aerotest Operations Site Location ....................................................... 20 Figure 4-2: A erotest A erial Im age ............................................................................................ 21 Figure 4-3: A RR R Local A rea V iew ....................................................................................... 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: Layout V iew of A RR R Site .................................................................................. 44 Figure 5-2: A erial V iew of A R R R Site ..................................................................................... 45 Figure 5-3: Plan View of High Bay Reactor Building ............................................................. 46 Figure 5-4: Cross Section View of ARRR High Bay Reactor Building ................................... 47 Figure 5-5: Reactor & N-Ray Area with Shielding in Place ................................................... 48 Figure 5-6: ARRR Core and Support Structure ...................................................................... 49 Figure 5-7: ARRR Reactor Tank Cutaway and N-Ray Facility .............................................. 50 Figure 5-8: ARRR In-Core Irradiation Capsule ....................................................................... 51 Figure 5-9: A RR R M achine Shop ............................................................................................ 52 Figure 5-10: A RRR C hem istry Lab .......................................................................................... 53 Figure 5-11: A RRR Preparation Lab ....................................................................................... 54 Figure 5-12: ARRR Mezzanine Sheet Metal Fabrication Area ............................................... 55 Figure 5-13: ARRR Mezzanine Sheet Metal Fabrication Area & HVAC Unit ...................... 56 Figure 5-14: ARRR Mezzanine Storage Area ......................................................................... 57 Figure 5-15: ARRR Mezzanine Instrument Calibration Area ................................................. 58 Figure 5-16: A RR R Electronics Lab ........................................................................................ 59 Figure 5-17: A RRR Shipping & Receiving .............................................................................. 60 Figure 5-18: A RRR N -Ray Setup A rea .................................................................................... 61 Figure 5-19: O ffice Space ...................................................................................................... . . 62 Figure 5-20: C ustom er V iew ing A rea ........................................................................................ 63 Figure 5-21: Q uality C ontrol Room .......................................................................................... 64 Figure 5-22: Computer and Counting Room ........................................................................... 65 F igure 5-23: T agging A rea ...................................................................................................... . . 66 Figure 5-24: Tagging A rea Back Room ................................................................................... 67 Page 6 of 103
Decommissioning Cost Estimate for the CS-HP-PR-004 Aerotest Radiography and Research Reactor Revision 1 LIST OF FIGURES (CONTINUED)
Figure Page Figure 5-25: Backup Cooling Tow er ....................................................................................... 68 Figure 5-26: M ain C ooling Tow er ............................................................................................ 69 F igure 5-27: Storage B uilding ................................................................................................ . . 70 Figure 5-28: W aste Storage T anks ............................................................................................ 71 Figure 7-1: A RRR A ctivated Concrete ..................................................................................... 87 Page 7 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision I 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 B uilding Surface C ontam ination ............................................................................................... 29 Table 6-1: Decommissioning Cost Summary - ARRR .......................................................... 72 Table 6-2: Personnel Protective Equipment Protection Summary ........................................... 73 Table 6-3: Hazardous and Toxic Waste Productivity Factors: Light Work ............................. 74 Table 6-4: Hazardous and Toxic Waste Productivity Factors: Heavy Work ............................ 75 Table 6-5: ARRR Unprocessed Radioactive Waste Summary ................................................. 76 Table 6-6: Decontamination Methodology Comparison .......................................................... 77 Table 6-7: Volume Reduction Methodology Cost Information ............................................... 78 Table 6-8: Decommissioning Cost Estimate Selected Cost Factors ....................................... 78 Table 7-1: ARRR Planned Remediation Activities ................................................................. 80 Table 7-2: Typical Final Survey Instrum entation .................................................................... 85 Page 8 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 1.0 ACRONYMS AND ABBREVIATIONS 0 Degrees Degrees Fahrenheit Aerotest Aerotest Operations, Inc.
AGN Aerojet-General Nucleonics, a division of General Tire AGNIR Aerojet-General Nucleonics Industrial Reactor ARRR Aerotest Radiography and Research Reactor CA State of California Ci Curies Co Cobalt COC Contaminants of Concern DOE U.S. Department of Energy HISA 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 pCi PicoCuries pCi/g PicoCuries per Gram pCi/L PicoCuries per Liter RHB California Radiologic Health Branch of California Department of Health TRIGA Teaching Research Isotope General Atomic reactor TS Technical Specification USNRC U.S. Nuclear Regulatory Commission Page 9 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 2.0 EXECUTIVE
SUMMARY
EnergySolutions performed an independent cost estimate for decommissioning the Aerotest Radiography and Research Reactor located in San Ramon, Califomia. This estimate was prepared at the request of Aerotest Operations, Inc., (Aerotest).
This cost estimate was developed using a systematic approach. Decommissioning criteria were identified and survey data were reviewed. Specific and general information regarding equipment and structures was used in determining decontamination and demolition methodologies in order to minimize overall decommissioning costs.
This estimate includes itemized costs for manpower and equipment resources, radioactive waste volume reduction, packaging, shipping and burial activities, the performance of final status surveys for buildings and structures. The estimated decommissioning cost is $3,376,030 in terms of 2012 dollars. 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-CROI-83NE44484). This decommissioning estimate is for budgetary purposes only and is not a proposal for EnergySolutions to perform the decommissioning work.
A significant portion of the overall decommissioning costs is attributed to the disposal of radioactive waste. The radioactive waste disposal rate used for most of the waste in this estimate was based on shipping to the disposal site at Clive Utah.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1
3.0 INTRODUCTION
3.1 PURPOSE Aerotest Operations has provided Neutron Radiographic (N-Ray) Inspection Services since 1969 using the Aerotest Radiography and Research Reactor (ARRR) for the neutron source.
Aerotest Operations, Inc., (Aerotest) is the holder of Facility Operating License No. R-98 which authorizes the possession, use and operation of the ARRR, located in San Ramon, California.
Aerotest is a wholly owned subsidiary of OEA Aerospace, Inc., which is wholly owned by OEA, Inc. OEA, Inc., was purchased by Autoliv ASP, Inc., (Autoliv) in 2000. Autoliv is owned by Autoliv, Inc., a Delaware corporation with a Board of Directors and Executive Officers, the majority of whom are non-U.S. citizens. As a result of the purchase, Aerotest became a subsidiary of Autoliv and Autoliv, Inc.
The NRC's position and regulations in 10 CFR 50.38 do not allow issuing a license for a production or utilization facility to an. alien or an entity that is owned , controlled, or dominated by foreign interests. There was a good faith effort over several years to sell the facility and transfer the license to a non-foreign entity. This effort failed and Aerotest was forced to close its neutron radiography testing facility in the latter part of 2010. Aerotest currently plans to submit a request for a possession only license (POL) in 2011. The POL period will continue until all fuel is removed from site, at which time the process for decommissioning and license termination will commence. The TRIGA reactor is currently operated for short periods of time at low power levels in order to maintain operator qualifications. There are no plans to resume regular reactor operations.
Consequently, Aerotest plans to proceed with decommissioning and termination of the associated reactor license after removal of fuel from the site. After fuel removal, Aerotest will file the appropriate decommissioning amendment requests, together with a decommissioning plan with the NRC. As with other facilities of this nature, the ARRR Facility is contaminated with varying small amounts of radioactive material and small amounts of hazardous material.
Decontamination and Decommissioning (D&D) of the ARRR will eliminate the potential for future inadvertent environmental releases. The goal of the proposed D&D activities is termination of the ARRR TRIGA Reactor Nuclear Regulatory Commission (NRC) License R-80, Docket No. 50-228 and release of the ARRR for "unrestricted use." The term "unrestricted use" means that there will be no future restrictions on the use of the site other than those imposed by the City of San Ramon zoning ordinances.
The Commercial Services division of EnergySolutions has prepared this document for the purpose of providing a decommissioning cost estimate 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 release of the facility for "unrestricted use." ARRR also maintains radioactive materials license number 2010-07 with the State of California. This license governs possession and use of several radioactive materials independent of the reactor. The State of California, as an Agreement State, .has regulatory authority and responsibility for these radioactive materials. The state is the primary authority responsible for decommissioning the Site with respect to these materials. In addition the State of Page I1 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 California is authorized to implement RCRA corrective action requirements, and through this means can implement more restrictive cleanup requirements for the ARRR decommissioning than required by the NRC. The State rules for termination of a radioactive materials license are provided in Title 17 California Code of Regulations, Division 1, Chapter 5, Subchapter 4, Section 30256.
Currently no dose based release criteria in California and there is a case by case evaluation of decommissioning plans performed by the California Department of Public Health (CDPH).
Experience indicates that release limits that equate to a few mrem/yr are accepted.
The decommissioning is projected to start within a year, but not be completed until fuel is removed from the site which is currently projected to be sometime after 2055. However, the cost estimate provided by this report and is based on prompt decommissioning rather than waiting until 2055 to finish decommission and is in terms of 2012 dollars. This estimate is intended to be used for funding and budgetary purposes and does not constitute a proposal or cost estimate for EnergySolutions to perform work.
3.2 SCOPE The scope of this report is to present the estimated costs derived for decommissioning the ARRR. The specific areas covered by this estimate include:
a TRIGA Reactor 0 TRIGA Reactor Shield and N-Ray Components 0 Buildings
- Outdoor Areas This estimate has been prepared to provide a budgetary decommissioning cost estimate and to support the requirements of 10 CFR 50.82(b), Termination of License - for Non-Power Reactor Licensees (Ref. 8.1). This estimate addresses activities related to the removal of hardware, structural materials, and miscellaneous materials as necessary to reduce levels of residual radioactivity to below the guideline values in accordance with the NRC criteria for license termination in Subpart E of I OCFR 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, ConsolidatedNMSSDecommissioning Guidance, Decommissioning Processfor Materials Licenses, Appendix B, (Ref. 8.3). For the purposes of this estimate, it was assumed that license termination screening values of 12%
( 3 /2 5 th) of the 10 CFR 20.1402 criteria would be acceptable to California (equivalent to 3 mr/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, radiological data, and proven volume reduction processes. Costs associated with the performance of final status Page 12 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 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 2012 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 of cost per foot of pipe is multiplied by the 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 of cost per square foot of concrete floor area is multiplied by the square feet of floor area to arrive at the cost. The estimate includes the craft labor, supervision, health physics support, waste disposal, materials and equipment necessary to actually perform this task. Other work is priced using the task based methodology which is modeled after the method used by PNL (Pacific Northwest Laboratory) 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 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 is used in the development of on site project management costs, travel and living costs, equipment rental costs, home office support costs, and owner oversight costs.
3.3 ASSUMPTIONS AND BASES The following assumptions and bases were utilized in developing the cost estimate.
The reactor fuel will have been removed and transported from ARRR to the DOE or placed in storage outside the pool prior to the start of decommissioning; costs for these activities are not included in this estimate.
- ARRR will be decontaminated and free released.
- Some of the uncontaminated materials and equipment located throughout the facility has a high intrinsic value and may be sold or moved to another facility prior to decommissioning. No credit has been taken for the sale of any items.
The use of radioactive materials at the ARRR has been well controlled and contaminated areas are minimal and well defined. Contamination outside of the defined areas is not anticipated and costs for remediation outside of these areas are not included in this estimate.
Contaminated equipment will for the most part be shipped directly to a licensed radioactive waste disposal site. Some easily decontaminated equipment will be decontaminated on-site, surveyed for unrestricted release, and then sent to a landfill for disposal. Some equipment may be shipped to a volume reduction facility for processing prior to disposal.
Aerotest will provide security for the site, power will be available, and the ARRR staff and management will be on site during decommissioning.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision I Radioactive waste with low specific activity will be sent to Clive, Utah. It was assumed that concrete, protective clothing waste and miscellaneous dry active waste would 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 disposal facility available.
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 them. Health Physics technicians and supervisors and project management personnel will not be local hires; therefore, funds for travel and living expenses were included.
Construction labor rates were obtained from RS Means Building Construction Cost Data for Oakland, California.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 4.0 GENERAL SITE DESCRIPTION The property, on which the ARRR is situated, was designated for construction in 1963. The ARRR was constructed between 1963 and 1964. The ARRR site configuration is shown in, Figure 4-1, Figure 4-2 and Figure 4-3. The land area is well defined, as there is 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 decommissioning estimate include all rooms in all buildings, whether remediation could be required or not based upon the characterization study 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 October 15, 2010. The TRIGA is currently operated only for short periods of time at low power levels in order to maintain operator qualifications. Aerotest plans to request that the USNRC issue an amendment to the TRIGA facility license to place the reactor in a Possession-Only-Status. The specific detailed conditions of this status are not known at this time. Some anticipated conditions are listed below.
4.1 CURRENT FACILITY STATUS It is anticipated that the TRIGA Reactor will be placed in "Possession-Only-Status" (POS),
through an amendment to the USNRC License No. R-98, in 2011. The following conditions are anticipated for POS status:
0 ARRR utility services required for facility operation and maintenance under POS status conditions will remain active.
0 Manually actuated and automated fire alarm systems in the ARRR will remain operational.
a All building utility services required for facility operation and maintenance are active.
- The license-required radiological monitoring and instrumentation systems remain operational.
0 Existing physical security and material control and accounting plans approved by the Nuclear Regulatory Commission (as may be amended) will continue to be implemented.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 The water demineralization system serving the ARRR is currently operational although the status may change depending on requirements that are implemented in the amended license.
4.2 PROPOSED ACTION AND ALTERNATIVES The Proposed Action and the Alternatives are as follows:
Proposed Action (Modified SAFSTOR) - In safe storage, the Aerotest Reactor would be placed and maintained in a condition that allows it to be safely stored and subsequently decontaminated to a USNRC or state of California level permitting 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 I (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.
Alternative 2 (ENTOMB) - In entombment, radioactive materials are encased in a structurally long lived material such as concrete. The entombed structure is appropriately maintained and surveillance is continued until the radioactivity decays to a USNRC or state of California level permitting release of the property. This is not currently a viable option as the fuel must first be removed from the site and there is not a possibility for fuel removal in the near future.
No Action Alternative - A no-action alternative would leave the facility in its current status with the current support staff having to maintain the facility under the existing license conditions. This action would not 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 with some items reading over an estimated 500 R/hr on contact. The reactor tank does not have a history of leakage. However keeping the facility in this status over a long period of time may lead to a degradation of the tank that could lead to repairs or the decommissioning of that portion of the facility. The tank integrity would need to be monitored. Aerotest would incur expenses for maintenance of the facility without making beneficial use of the facility.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 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.
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, either (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 location.
The scenario where the fuel is maintained in the pool would likely include the following tasks:
0 Move some or all of the fuel out of the core to storage racks on the pool floor or on the pool walls.
- Continued operation and maintenance of the pool water demineralizer system.
0 Optional removal of the pool water cooling system including heat exchanger and cooling towers.
0 Decontamination of any contaminated areas.
0 Shipment of the low level radioactive waste (LLRW) currently on site or generated as a result of decommissioning activities.
0 Performance of surveys to confirm the facility status and submission of a request to the USNRC for a Possession Only Status (POS) through an amendment to the USNRC License No. R-98, in 2011.
- 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.
Existing physical security, radiological control, material control and accounting plans approved by the Nuclear Regulatory Commission (as may be amended) will continue to be implemented.
Once the DOE has taken the fuel off site, a revision of the decommissioning plan would be made, if required.
The facility would be decontaminated and decommissioned, including the performance of Final Status Surveys and release of the subject areas 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:
0 Removal of the reactor fuel from the tank to an on-site dry storage location.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1
- Dismantlement, decontamination 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 tank.
0 Decontamination of any contaminated areas.
0 Shipment of the low level radioactive waste (LLRW) currently on site or generated as a result of decommissioning activities.
0 Performance of surveys to confirm the facility status and submission of a request to the USNRC for a Possession Only Status (POS), through an amendment to the USNRC License No. R-98, in 2011.
0 Existing physical security, radiological control, material control and accounting plans approved by the Nuclear Regulatory Commission (as may be amended) will continue to be implemented.
- Once the DOE has taken the fuel off site, a revision of the decommissioning plan would be made, if required 0 The facility would be decontaminated and decommissioned, including the performance of Final Status Surveys and release of the subject areas for unrestricted use and termination of the ARRR license.
4.3 ADMINISTRATIVE CONTROLS To minimize the risks of inadvertent exposure, contamination and/or radioactive releases, all decommissioning operations will be implemented in accordance with appropriate technical and administrative controls, including:
Performance of all project work pursuant to approved procedures implementing a USNRC-approved Decommissioning Plan. ARRR will continue to be responsible for assuring and demonstrating compliance with USNRC licenses, as well as other applicable federal, state or local laws, regulations, licenses and/or permits.
Utilization of containment structures, tents, and bags under negative pressure and/or appropriate contamination barriers to isolate operation areas and prevent inadvertent release of contaminants.
Employment of monitored, high efficiency particulate air (HEPA) filtration systems for air ventilation in contaminated work areas.
Maintenance of emergency ventilation, electrical power and supplies, as appropriate.
Application of ALARA principles by emphasizing radiation protection for workers and the general public, employing personnel and area dosimetry, using personal protective equipment and clothing, and conducting work through approved Radiological Work Permits. The term "ALARA" means as low as is reasonably achievable, taking into Page 18 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 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.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 4-1: Aerotest Operations Site Location Page 20 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 4-2: Aerotest Aerial Image Page 21 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 4-3: ARRR Local Area View Page 22 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1
- 1. Office Space
- 2. Customer Viewing Room
- 3. Quality Control Room CS-HP-PR-006 Revision
- 4. Dark Room PG 2
- 5. Explosive Storage & Safe
- 6. Film Storage
- 7. Shipping & Receiving L46 PD C
. PD5
- 8. N-Ray Setup Area
- 9. Computer and Counting Room
- 10. Lunch Room
- 11. High Bay N-Ray Exposure Area
- 12. Reactor Enclosure
- 13. Control Room
- 14. Men's Room z
- 15. Ladies' Room
- 16. Emp4oyee's Lockers 17 General Marager's O1Mice PD 7 1S. Bjsiress Office 19 Accounting Office
- 20. Machine S-iop
- 21. Offir.e Supply Room
- 22. Tagging Area
- 23. South End Radiography
- 24. Deminearlizer Building
- 21. Maintenance Office
- 26. Heat Ex&w'nge Buildrg 44
- 27. Backup Cooling Tower
- 28. Compressor Building
- 29. Sa fe 30 *aste Storage Ta-:s & Sump
- 31. N-Ray Cauge Offic*
32 Preparation Lab 33 Ciemicel Lab
- 34. Stocago
,35,Inst-hnent Calibration Area 39 Sheet Metal Fah.ir**Tioo A-ep
- 37. Electronics Lab
- 38. Class 1.1 Exploswe Stor-qe
- 39. Main Cooling Tower
- 42. Storage Buildig
- 43. Paddng. Area
- 44. ParkingAra
- 45. RadKiative Mateial Stzvavg R 4( C1n,*iral Shed Figure 4-4 General ARRR Arrangement Plan Page 23 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Ire- im lipp- or- - -
Figure 4-5 Plan Layout of ARRR Reactor Building Page 24 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 A - Am, P eOd7Mf0 Figure 4-6: Cross Section of ARRR High Bay Reactor Building Page 25 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 5.0 DECOMMISSIONING CRITERIA EnergySolutions engineers visited ARRR in San Ramon, California in May of 2011 to gather physical and radiological data. Facility sketches, building sketches, and radiological characterization data for affected areas were obtained.
5.1 RADIONUCLIDES OF INTEREST The base line radioactive material quantities were obtained from the estimate provided in NUREG/CR-1756, (Ref. 8.5). There are additional radionuclides reported in the characterization survey report (Ref. 8.6) that were not included in NUREG/CR-1756 and therefore do not have estimated quantities. After reactor shut down and for some time to come, 6 0Co and, to a smaller extent, 65Zn are the principal contributors to radiation dose from the reactor core and vessel.
Most (>95%) of the radionuclide inventory at the facility is found in the reactor pool. Excluding fuel, this amounts to about 34 Ci of neutron activation and fission products at the time of shutdown. The radionuclides that potentially exist in the ARRR along with estimated inventories are presented in Table 5-1.
Table 5-1: List of Expected Radionuclides Nuclide I Half-Life I Inventory (yr) Ci 3
H* 12.28 <28.7 1uBe 1,510,000 7.25 x 10-7 14c 5,730 6.48 x 10-3 22 Na 2.60 1.67 x 10-2 35S 0.2392 2.99 x 10-4 36 CI 30!,000 2.85 x 10-4 37 Ar* 0.0960 1.85 x 10-5 39Ar* 269 2.61 x 10-7 41 Ca 103,000 1.10 x 10-4 4
SCa 0.446 2.54 x 10-3 46Sc 0.233 2.04 x 10-5 5
'Cr 00759 1.03 x 10-4 54 Mn 0.86 2.26 x 10-3 55 Fe 2.73 0.385 59 Fe 0 1222 1.56 x 10-4 5
8Co 0.194 1.00 x 10-4 6L)Co 5.27 0.896 "Ni 76,000 1.34 x 10-4 63 Ni 100 1.75 x 10-2 65 Zn 0.67 0.203 F7S1r 29.1 0.454 Page 26 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Nuclide Half-Life Inventory (yr) Ci
')mNb 13.6 3.68 x 10-9 94 Nb 20,000 2.15 x 10-8 93Mo 4,000 1.19 x 10-8 95 Zr 0.175 1.21 x 10-2 95 Nb 0.0961 1.36 x 10-2 95
`'Nb 0.0099 9.54 x 10-7 08 1 Ag 4.51 x 10-6 1.39 x 10-2
'usmAg 418 0.159 109-A8 1.26 x 10-6 1.76 x 10-3 1
uAg 7.80 x 10-7 1.19 x 10-2
" "t'mAg 418 0.878
'"Cd 1.27 0.120 u3mCd 14.1 1.07x 10-3
"'smCd 0.122 8.13 x 10-6 "m'In 0.000189 6.74 x 10-4 13Sn 0.315 6.74 x 10-4 tt*Sn 0.803 2.17 x 10-2 1'Sn 0.00309 2.19 x 10-5
""Sn 55 2.82 x 10-5 0.354 2.40 x 10-4
"'Sn 124Sb 0.16 8.51 x 10-3
'"Sb 2.76 3.00 x 10-3 123-Te 0.328 3.69 x 10-5 25
"'Te 0.157 7.31 x 10-4
".'4Cs 2.7 9.16 x 10-7 1'TCs 30.17 0.283
"'"Ba 10.51 6.17x 10-4
"'"Ce 0.377 6.94 x 10-9
"Ce 0.0890 1.1 I x 10-8
"'"Ce 0.78 0.185 "52Eu 13.48 1.59 154Eu 8.8 0.161
'55Eu 4.96 1.73 x 10-2 153Gd 0.659 8.93 x 10-5 191W 0.332 1.12 x 10-7 IKSW 0.206 5.12 x 10-7 20""Hg 0.128 4.42 x 10-6
-,nTI 3.78 5.82 x 10-5 205*Pb 15,3000,000 9.80 10-5 Page 27 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Nuclide 1 Half-Lifey 1 Inventory
- I Iy) Ci 2po 0.3791 1.75 x 10-2 238Pu 87.7 4.35 x 10-4 23914°Pu 24,110 6.95 x 10-4 241Pu 14.35 1.32 x 10-2 2'*Am 432.2 3.59 x 10-3 0.446 5.62 x 10-4 Argon is a gas and will dissipate and will have an inventory close to zero. Tritium migrates easily and will dissipate The tritium inventory without dissipation is shown with a less than sign.
The list of expected radionuclides provided above is based on the assumption that operations of the ARRR has resulted in the neutron activation of reactor core components and other integral hardware or structural members which were situated adjacent to, or in close proximity to, the reactor core during operations. Specific items, which are considered to have been exposed to neutron activation, include materials composed of aluminum, steel, stainless steel, graphite, cadmium, lead, concrete and possibly others. In addition the activity in spent resin was estimated based on analytical results and an estimated spent resin inventory.
5.2 RADIOLOGICAL CRITERIA FOR LICENSE TERMINATION The overall objective of the ARRR decommissioning is to remediate the facilities to a condition that corresponds to a calculated dose to the public of less than 3 mrem/year from applicable pathways. The facilities may then be released for unrestricted use. A 25 mrem/year dose limit appears in 10 CFR 20.1402, Radiological Criteriafor UnrestrictedUse (Ref. 8.7) but this was reduced to 3 mrem/year for projected California requirements.
The Derived Concentration Guideline Level (DCGL) is defined in MARSSIM (Ref. 8.8) as the radionuclide-specific concentration within a survey unit corresponding to the release criterion.
The DCGL is dependent upon several factors including the radionuclides of interest, applicable dose pathways, area occupancy and the future use of the facility. DCGLs assume a uniform level of residual radioactivity across the survey unit.
For the ARRR it was assumed that the site qualified for a screening analysis to develop the DCGLs. A screening analysis can be based on one or more of the currently available screening tools: (1) building surface contamination and surface soil contamination are presented in NUREG-1757, Appendix B (Ref. 8.9); (2) screening levels derived using D and D, Version 2.0 (Ref. 8.9and 8.10), for the specific radionuclides(s) using the code's default parameters. The assumed DCGLs for ARRR were based on 12% of the look-up tables in NUREG-1757, Appendix H (Ref. 8.9).
The proposed DCGLs for surface contamination are based on 12% of the screening tables in NUREG-1757, Appendix B (Ref. 8.9). Buildings with surface contamination below these levels will be deemed acceptable for release for unrestricted use provided that:
Residual radioactivity has been reduced to levels that are "as low as is reasonably achievable" (ALARA),
The residual radioactivity is contained in the top layer of the building surface (i.e., there is no volumetric contamination), and Page 28 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 The fraction of removable surface contamination does not exceed 0.1.
Table 5-2: Acceptable License Termination Screening Values of Common Radionuclides for Building Surface Contamination Radionuclide Symbol NRC Acceptable California Acceptable screening levels'for screening levels' for Unrestricted release Unrestricted release (dpm/1OOcm2) 2 (dpm/OOcm 2 )
Hydrogen-3 3H 1.2E+08 1.4E+07 (Tritium)
Carbon-14 I4C 3.7E+06 4.4E+05 22 Sodium-22 Na 9.5E+03 1.1E+03 Sulfur-35 35S 1.3E+07 1.6E+06 Chlorine-36 36C1 5.OE+05 6.0E+04 Manganese-54 54Mn 3.2E+04 3.8E+03 Iron-55 55 Fe 4.5E+06 5.4EE+05 Cobalt-60 60 Co 7.1E+03 8.8E+02 Nickel-63 63Ni 1.8E+06 2.2E+05 90 Strontium-90 Sr 8.7E+03 I.0E+03 Technetium-99 99Tc 1.3E+06 1.6E+05 lodine-129 1291 3.5E+04 3.4E+03 Cesium-137 137 Cs 2.8E+04 2.8E+04 Iridium-192 192Ir 7.4E+04 8.8E+03 1 Screening levels are based on the assumption that the fraction of removable surface contamination is equal to 0. 1. For cases when the fraction of removable contamination is undetermined or higher than 0.1, users may assume, for screening purposes, that 100% of surface contamination is removable, and therefore the screening levels should be decreased by a factor of 10. Alternatively, users having site-specific data on the fraction of removable contamination (e.g., within the 10% to 100% range) may calculate site-specific screening levels using DandD Version 2..
2 Units are disintegrations per minute per 100 square centimeters (dpm/100 cm 2 ). 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. Refer to NUREG-1757 for further information on application of the values in this table.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision I 3 For the purposes of this estimate, it was assumed that license termination screening values of 12% ( 3 /2 5th) of the I0CFR20.1402 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 5-1 provides a layout view of the ARRR buildings and Figure 5-2 provided an overhead view of the site.
5.3.1 Reactor Building The reactor building is made of steel with internal rooms built of fire resistant framing and sheetrock covering. An automatic sprinkler system covers the entire building. The building has airflow control from the standpoint that certain rooms are maintained at a positive pressure relative to the reactor room. The building as a whole is not sealed or contained and requires no air-locks. The reactor control room and certain offices are housed in a single building. The control room and offices are in areas where a fresh air intake is used to maintain the positive pressure relative to the reactor room. The 40 feet x 80 feet main building has a 3 ton capacity bridge crane 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 5-3 provides a plan view of the reactor building, Figure 5-4 provides a cross section view of the Reactor Building and Figure 5-5 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. The reactor fuel elements, reflector elements, control rods, control rod drive mechanisms, and control rod drive controls were purchased from General Atomics and were incorporated without any significant changes. A standard "G" ring core grid plate design was provided by General Atomics and manufactured by Aerojet. All other components were designed and constructed by Aerojet or their subcontractors. Figure 5-6 shows the ARRR Core and Support Structure.
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:
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision I (1) Fuel: < 20% enriched U-235.
(2) Moderator: zirconium hydride and water.
(3) Reflector: demineralized water and graphite.
(4) Coolant: demineralized water.
(5) Control: I safety rod, I shim rod, I 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 5-7) 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 equipped with fill and drain lines that are used to remove water or purge the vertical beam tube.
The lower 84 inches of the vertical beam tube is covered with lead for gamma shielding. This lead shield is 3 inches thick on the reactor side and I inch thick on the other three sides. The lead is protected from the pool water by welded sheets of Page 31 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 aluminum. All components contacting the pool water are fabricated from aluminum or stainless steel.
The vertical beam tube includes an upper open/close pneumatically operated shutter and a lower electrically operated shutter mechanism that offers a selection of 5 aperture settings to provide varying depths of field or resolution. The. lower aperture is located near the bottom of the vertical beam tube just above the graphite.
The neutron radiography facility is integrated into the shielded enclosure directly above the vertical beam tube. The shielded enclosure consists of 20 inch thick concrete block shielding stacked to a nominal height of 80 inches above the floor that surrounds the entire top of the reactor water tank. The neutron radiography facility is supported by 10 inch steel "I" beams that transmit the weight of the shielding to beams imbedded in the floor of the reactor building. This shielding supports the 11 inch thick wood (fir) beams that cover the reactor enclosure. This shielding provides operating personnel additional shielding.
This shielding enclosure is penetrated at the north and south ends on the east side of the reactor by the neutron radiography facility. Access to the top of the vertical beam tube is through openings on both the north and south ends with cross sectional dimensions of approximately 37 inches wide by 18 inches high. The facility was designed to allow the neutron radiography of contained detonating cords having lengths in excess of 25 feet. Concrete blocks in the shield structure may be moved as necessary to accommodate taller objects.
The top of the vertical beam tube is covered by a movable radiation shield called the neutron beam catcher. The beam catcher shield is wood that is 48 inches by 47 inches by 16.5 inches and has wheels that roll on tracks attached to the tunnel. The wheels allow the beam catcher shield to be rolled to the south end to radiograph large items on the north end. The beam catcher shield reduces the radiation level due to neutrons and gammas within the reactor room and at the exclusion area fencing.
Figure 5-5 is a photograph of the radiography facility with biological shielding in place.
(2) The Graphite Thermal Column (Figure 5-7) is a large block of graphite, encased in aluminum, containing five rows of seven vertical holes through the graphite block.
The vertical holes allow specimens to be inserted into the graphite block for irradiation. The five rows of irradiation holes (A through E) are six inches apart with each row at an increasing radius from the core. The increasing radius of each row 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 "coregrid plate, which allows the same capsules or devices that are inserted into the core to be inserted into the graphite thermal column.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 The thermal column graphite block measures 4 feet along the radial axis of the core and is 2 feet wide and 2 feet deep. It is located on the south side of the reactor and positioned adjacent to the core. The thermal column is positioned using tapered pins and is bolted to the bottom of the reactor pool tank. Installation and removal of the whole assembly is accomplished with the facility crane and remote handling tools.
Two irradiation holes in the thermal column are configured for specific tasks:
" One irradiation position in the first ('A') row is fitted with an aluminum tube, identical in design to the glory hole (described later), that extends to the top of the reactor water tank above the wood (fir) block shield. Material to be irradiated is lowered through the tube into the thermal column. This tube has a rotating motor to slowly rotate the sample and thus provide an evenly distributed irradiation to the sample. A shield plug is placed in the top of the tube to reduce gamma scattering to acceptable levels and to prevent Argon-41 from coming up the tube.
" A second position in the first ('A') row is fitted with a detector calibration system. Small fission detectors can be calibrated against a standard in this facility.
" A third position includes a one inch diameter neutron beam tube which can be located between the thermal column and N-ray tube and which extends to the area above the top reactor shield. This tube is used for the source of neutrons for the N-gage device.
The thermal column structure is also used to mount other experimental facilities. Four slotted beams, two on each side, are provided to allow experiments to be attached directly to the thermal column. Extensions of these beams allow experiments to be placed immediately adjacent to the reactor core.
(3) The Glory Hole Facility is an aluminum tube, 1.5 inches in diameter, which will fit into any fuel element hole. The hollow tube extends from the lower grid plate to above the top of the wood (fir) shield on top of the reactor water tank. The tube is not filled with water and is used to lower material to be irradiated through the tube into the core region. The glory hole will accept capsules with a maximum diameter of 1.35 inches.
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 CR.Ds.
Technical Specifications require that the glory hole be purged with CO2 to prevent the formation of excessive amounts of 41Ar during reactor operation. When operated with a shield plug, the glory hole is purged prior to each insertion of the shield plug.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 When operated without a shield plug, the glory hole is purged continuously when the reactor is operating. Additionally, when operated without a shield plug, the installed gas sampling system must be selected to sample in the immediate vicinity of the glory hole so that corrective action can be taken to prevent the release of gaseous activity in excess of 10 CFR 20 limits.
(4) The Central Core Irradiation Facility is a hexagonal section that can be removed from the center of the upper grid plate to allow insertion of specimens into the core region of highest flux. Use of the central core irradiation facility requires prior relocation of the central fuel element and the six elements from the B-ring. Technical Specifications limit the size of the central core irradiation facility to 16 square inches.
The facility will accommodate specimens up to about 4.4 inches in diameter.
(5) The Triangular In-Core Irradiation Facilities consist of two sections cut out of the upper grid plate, each of which encompasses one D-ring and two E-ring holes. When fuel elements are placed in these locations, their lateral support is provided by special aluminum pieces. With the aluminum spacers removed, each of these triangular sections allows the insertion of circular experiments to a maximum of 2.35 inch diameter or triangular experiments to a maximum of 3.0 inches on a side.
(6) The In-Core Irradiation Capsules (Figure 5-8), approximately the same size and shape as a fuel element, are used to irradiate samples and can be used in any open position of the core or in the graphite thermal column. The capsules are usually sealed at the top by a gasket and threaded fitting but also have provisions for bringing instrumented tubes to the surface.
In-core irradiation capsules are inserted and removed from the core using the fuel element handling tools. A transfer shield is used to transport the capsule within the ARRR building.
The capsules are designed to have a maximum inner void volume of 34 cubic inches in the active fuel region.
(7) The Large Component Irradiation Box is an aluminum box with an internal volume of up to 20 cubic feet that can be installed in the reactor water tank. The walls of the box are thin to minimize parasitic neutron absorption.
The large component irradiation box can be installed, as needed, by being lowered onto the movable table and bolted in place with remote handling equipment. The box is positioned on the movable table using tapered locating pins and bolted to the movable table that is, in turn, bolted to the bottom of the ARRR reactor water tank.
To remove or install the experiment box, the movable table is required to be moved two or more feet away from the reactor core. The movable table is positioned remotely relative to the reactor core but has positive mechanical stops that prevent moving the box closer than 5 centimeters from the outer ring. When at the position closest to the core, the large component irradiation box cannot encompass more than a 1200 arc of the core.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 The large component irradiation box must be purged of air prior to exposure to neutrons. Therefore, when installed, the large component irradiation box is pressurized with CO 2 to 0.5 psi above the water pressure. The box is weighted with lead to eliminate buoyancy.
The large component irradiation box is not currently installed in the reactor water tank, because ARRR does not currently use and has no plans for future use of the large component irradiation box.
(8) The Pneumatic Transfer Facility is designed to quickly transfer individual specimens into and out of the reactor core. The specimens are placed in a small polyethylene holder, "rabbit," which in turn is placed into the receiver. The rabbit travels through aluminum tubing to the terminus at reactor core centerline and then returns along the same path to the receiver. Directional C02 flow moves the rabbit between receiver and terminus. A solenoid valve directs air flow using a timer to regulate the exposure of the sample. A manual control, capable of overriding the automatic timer control, is also provided.
The pneumatic transfer facility may be located in any reactor core position. When installed, the facility is operated with dry 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 experiments that are placed in the active core.
The pneumatic transfer facility is not currently installed in the reactor water tank because ARRR does not currently use a pneumatic transfer facility and most of the parts to this system are no longer on site.
(9) The Beam Port was never finished but the ARRR was designed to facilitate future installation of a horizontal beam port. The ARRR reactor tank's concrete embedment includes one penetration consisting of one 24 inch outside diameter pipe about 13 ft long that butts up against the outside of the reactor tank on the center line of the core.
The pipe sleeve was provided so that a horizontal beam port could be installed without having to break through the concrete around the tank. However, the beam port facility was never installed and the reactor tank wall is not cut open at this location.
5.3.1.3 Coolant System The ARRR cooling system is comprised of three basic parts: the reactor water tank, the cooling system, and the demineralizer system. The pool water provides convection cooling, neutron and gamma shielding and neutron moderation. The cooling system provides heat removal to a cooling tower via a heat exchanger. A new cooling tower was installed several years ago and the old cooling tower with redwood louvers was retained as a backup for the new tower. The demineralizer system maintains the purity of the water. A replacement demineralizer with a much larger capacity was obtained several years ago and it was used for a short period. Because of its large size it could be operated for a long period before change out of the resin was required.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 However this also resulted in the accumulating of greater quantities of radioactive isotopes which raised radiation levels in the resin bed to unacceptable levels and further used of the large bed demineralizer was halted. 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. Figure 5-1 provides locations for the demineralizers, the heat exchanger and the cooling towers.
5.3.1.4 Radioactive Waste and Radiation Protection The ARRR generates very little radioactive waste. Most of the induced radioactivity is short half life material and can be stored until the radioactivity decays. Radioactive waste is stored in the Radioactive Material Storage Room as located in Figure 5-1. The radioactive materials stored in the room include demineralizer resin removed from the demineralizers and stored in a drum, contaminated Personal Protective Equipment, radioactive sources, filters, contaminated or irradiated materials removed from reactor during repairs and modifications, and miscellaneous contaminated or irradiated items.
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 demineralizer resin removed from the demineralizers and stored in drums, contaminated Personal Protective Equipment, radioactive sources, used filters, contaminated or irradiated materials removed from 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.
Figure 4 20 is a photograph of the Radioactive Material Storage Area which encompasses two of the six (6) fuel storage pits.
5.3.1.6 Office Supply Room The Office Supply Room is located against the south wall of the reactor building as shown on the general layout drawing in Figure 5-1. 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(NO 3) 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 8x8 asbestos floor tiles on the floor in the room and the floor is covered with similar tiles. The shop was reported to have been used to machine contaminated or activated parts in the distant past.
Figure 5-10 is a photograph of a portion of the Machine Shop.
Page 36 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 5.3.1.8 Control Room The Control Room contains the reactor operating console and lies at the end of the western 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 mezzanine 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 and flooded the Chemistry Room and the adjacent Preparation Lab and flowed down the stairs into the South End 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 5-10 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 on the mezzanine 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 5-1 1 is a photograph of a portion of the Preparation Lab.
5.3.1.11 N-Ray Gauge Office The N-Ray Gauge Office is a small room on the mezzanine 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 Mezzanine Storage Area The Mezzanine Storage Area is an open topped portion of the mezzanine that is next to the N-Ray area. This area contains the control room HVAC system, a storage area for spare mechanical parts of all sorts, a storage area for irradiated items, and wall mounted cabinets just off the mezzanine and over the bioshield that are used to store reactor pool tools. The floor in the area is mostly bare wood but a small portion is covered with room is covered with what appear to be 8-in by 8-in asbestos floor tiles.
Figure 5-12 is a photograph of the northern portion of the Sheet Metal Fabrication Area and Figure 5-13 is a photograph of the Sheet Metal Fabrication Area and HVAC System.
Page 37 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 5.3.1.13 Sheet Metal Fabrication Area The Sheet Metal Fabrication Area is an open topped portion of the mezzanine that is just an extension of the Mezzanine Storage Area. It is currently a storage area for spare mechanical parts and the floor is coveredwith what appear to be 8-in by 8-in asbestos floor tiles.
Figure 5-14 is a photograph of the Mezzanine Storage Area.
5.3.1.14 Instrument Calibration Area The Mezzanine Storage Area is an open topped portion of the mezzanine that is next to the Chemistry Lab and Preparation Lab. This area is used for instrument calibrations and coating of Exposure Trays. It contains a drawing table used for reviewing drawings and calibrating instruments at fixed distances from sources, a coating mixer, drawing storage drawers and files, and miscellaneous other equipment and HVAC components. The floor is covered with what appear to be 8-in by 8-in asbestos floor tiles.
Figure 5-15 is a photograph of the Instrument Calibration Area.
5.3.1.15 Electronics Lab The Electronics Lab is a small room on the mezzanine 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 5-16 is a photograph of the Electronics Lab.
5.3.1.16 Offices and Restroom Areas The Restrooms and Offices in the reactor building are as shown on the general layout in Figure 4
- 12. 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 Manager's 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 I Building Addition I 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 5-1.
Page 38 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 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, approximately 25-ft by 14.5-ft by 13 feet tall, metal shelving, a bare concrete floor and the doorway into the Film Storage area.
No records indicating radiological use or storage were identified.
Figure 5-17 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 I structure, approximately 38.5ft by 34-ft, as shown in Figure 5-1. 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 5-18 is a photograph of the N-Ray Setup Area.
5.3.2.3 Film Storage Room The Film Storage Room is a 9.8-ft by 6-ft by 8-ft tall room located at the end of the Shipping &
Receiving area as shown in Figure 5-17. There is also space between the roof of the Film Storage Room and the ceiling of the Building I 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.
5.3.2.4 Explosive Storage Safe The Explosive Storage Safe is a 9.8-ft by 6-ft by 8-ft tall room located at the northeast corner of the Shipping & Receiving area as indicated in the layout drawing shown in Figure 5-1. 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-ft by 13-ft by 8-ft tall room with carpeted floor and drywall finished walls and ceiling that includes desks and work tables for staff use as shown in Figure 5-19. The film viewing room for customers is a 16-ft by 10-ft by 8-ft tall room with carpeted floor and drywall finished walls and ceiling that includes facilities for clients to view completed radiographs as shown in Figure 5-20.
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-ft by 9-ft by 8-ft room with tiled floor and drywall finished walls and ceiling. This room includes film processing equipment, facilities for temporary storage of radiographs, and equipment for viewing radiographs as shown in Page 39 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision I Figure 5-21. The Dark Room is a 16-ft by I l-ft by 8-ft tall room with vinyl tiled floor and black drywall walls and ceiling, as shown on the general layout in Figure 4 12. This room is utilized for film processing and it contains a sump that receives overflow from the developer along with running water. The sump water is passed through a Filter and then steel wool. The steel wool collects excess silver that is then removed by an independent contractor for processing. The processed water passes down the sewer. Activated silver was present from neutron activation of the film emulsion and there is a potential for plating out of silver in the sewer pipes. There were no other indications of radiological use or storage.
5.3.2.6 Computer and Counting Room The Computer and Counting Room is an 1 I-ft by 7.5-ft room located at the southwest comer of the N-Ray Setup area as indicated in the layout drawing shown in Figure 5-1. 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 5-22 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 5- I.
5.3.3.1 Tagging Area The Tagging Area includes a 35-ft by 19-ft portion of the Tagging Area Building as shown in Figure 5-1. 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 5-23 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 5-24 is a photograph of the Tagging Area Back Room.
Page 40 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 5.3.3.3 Safe The safe is 6.5-ft by 7-ft by 3-ft tall locked room that is used to store new reactor fuel if there is any on site.
5.3.3.4 East Entrance Hallway The East Entrance Hallway is a by 4.5-ft by 8-ft by 8-ft tall room that connects to the outside, the Reactor Building and the Tagging Area as shown in Figure 5-1. 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-ft by 3.6-ft by 7-ft tall small metal structure on the east side of the Reactor Building as shown in Figure 5-1. It contains the demineralizer system which includes a pump, demineralizer bed, filters, gauges, valves and typically a used resin bed left in the building for decay prior to removal of the resin for disposal.
5.3.5 Heat Exchanger Building The Heat Exchanger Building is a 12-ft by 4-ft by 7-ft tall metal structure built with a shallow concrete basin for the floor. It is located at the east side of the Reactor Building as shown in Figure 5-1. 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.
5.3.6 Cooling Towers There are two cooling towers located close to the Heat Exchanger Building. The old tower is currently a backup system in case the current tower is shut down for any reason. The old tower is approximately 8-ft by 16-ft by 7-ft tall with a painted steel shell, blower on top and redwood vanes on the interior as shown on Figure 5-25. The new tower is approximately 6-ft by 5.5-ft by 8-ft tall with a painted steel shell, blower on top and galvanized steel packing on the interior as shown on Figure 5-26.
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 The Maintenance Office Building is a 12.5-ft by 9.5-ft by 7-ft tall wood structure with metal roof on the East side of the High Bay Building. There is a plywood panel addition on the south exterior of the building that houses a backup demineralizer that is much larger than the regular demineralizer. The backup demineralizer was obtained several years ago and it was used for a short period. Because of its large size it could be operated for a long period before change out of Page 41 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 the resin was required. However this also resulted in the accumulating of greater quantities of radioactive isotopes which raised radiation levels in the resin bed to unacceptable levels and further used of the large bed demineralizer was halted. The backup demineralizer is disconnected and left in place.
5.3.8 Compressor Building The Compressor Building is a 14-ft by 8-ft by 8-ft 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-ft by 4-ft by 6-ft tall metal structure mounted on wooden skids located the south side of the Operations Building as shown on Figure 5-1. 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-ft by 4-ft by 4-ft tall metal box on skids located on the northeast comer 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 east and a personnel door that opens to the south. It is used for forklift parking, equipment and supply storage, and fabrication area. The interior of this building is shown in Figure 5-26.
5.3.12 Waste Storage Tanks and Sump The Waste Storage Tanks and Sump are located on the south end of the Reactor Building as shown on Figure 5-1. There is a larger tank and a smaller tank and a below grade sump. The smaller tank is out of service and lying on its side awaiting repair as the painted surface had shown signs of corrosion. These tanks are shown in Figure 5-28.
5.3.13 Land Area All of the sites 0.9 acres are fenced in with a chain link fence. The fence has a truck gate that allows access to the Shipping and Receiving area and a personnel gate that enters the Reactor Building near the Control Room as indicated on Figure 5-1. Most of the outside area is paved as can be seen in Figure 5-2. There are seepages of groundwater upward through cracks in the pavement on the north end of the site that are collected and drained by a ditch just outside the north site fence.
Page 42 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 5.4 RELATION OF THE ARRR TO OTHER TRIGA REACTORS The design of the ARRR fuel is similar to those of approximately 50 TRIGA type reactors currently operating worldwide with 24 in the United States.
The reactor and associated equipment will be decommissioned by removal of the core, removing the water from the vessel, and removing activated and contaminated materials from the reactor.
Once this has been completed, the structure will be surveyed using a license termination type survey with any additional decontamination performed in conjunction with the surveys.
5.5 OUTSIDE AREAS There is no history of any spills of radioactive materials outside the identified building process areas. Based on current survey data, it is not anticipated that any soil remediation will be required. There is a discharge from the Reactor Building to the sanitary sewer system which runs near the building.
The ARRR is between two watersheds: Alameda Creek and Walnut Creek. The surrounding area slopes gently downward to the north and to the south. The site storm water runoff is to the north and west toward Walnut Creek. San Ramon Creek is the principal local drainage, with Bollinger Creek and San Catanio Creek being tributary. San Ramon Creek meanders northward through Danville and Alamo, and ultimately joins Walnut Creek, which discharges into Suisun Bay near Martinez. There is a drainage ditch located just past the site boundary to the north of the facility.
The sanitary sewer and nearby storm sewers will be surveyed at accessible locations downstream of the site. In addition soil sampling and license termination surveys of paved areas and unpaved areas will be performed in areas adjacent to the ARRR in accordance with current regulatory requirements.
Page 43 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1
- 1. Office Space
- 2. Customer Viewing Room
- 3. Quality Control Room
- 4. Dark Room PG 2"
- 5. Explosive Storage & Safe
- 6. Film Storage 3 46 VPDC JD 2
- 7. Shipping & Receiving _
____PD_5 _
- 8. N-Ray Setup Area
- 9. Computer and Counting Room *
- 10. Lunch Room 22
- 11. High Bay N-Ray Exposure Area L2 PDA
- 12. Reactor Enclosure PD B
- 13. Control Room _ _ ____F__I 1*. Lm'..-Q.,t -
- t !c .. " -.. 'l4*[, *l. p.,
- 21. Office Supply Room I O13 14 181 _
- 22. Tagging Area I 8 11 10__1__
- 23. South End Radiography
- 24. Demineralizer Building *7PD2PD3 PD
- 25. Maintenance Office
- 26. Heat Exchange Building 9
- 27. Backup Cooling Tower
- 28. Compressor Building 4d
- 31. N-Ray Gauge Office TG 1 Dow0-
- 32. Preparation Lab TG 43 PG1
- 33. Chemical Lab .31 [2
. ..... ... . .. '---.~ LS,fe.d " /- '":* // , //
ra.*
. rThi - Fr ,ioi*1e. } ,.-.rj, . / /;-*
ITY t*~~'- rs rN. F Dc~ro n .7
- 42. j*'*-rdge idir Tr&,. ."/ :;
Tr/ ",/
- 43. Parking Area
- 44. Parking Area
- 45. Radioactive Material Storage Area
- 46. Chemical Shed AEROTEST OPERATIONS, INC.
Figure 5-1: Layout View of ARRR Site Page 44 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 5-2: Aerial View of ARRR Site Page 45 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Pge406o10I Figure 5-3: Plan View of High Bay Reactor Building Page 46 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 AT A 1POWDo 1 Figure 5-4: Cross Section View of ARRR High Bay Reactor Building Page 47 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 5-5: Reactor & N-Ray Area with Shielding in Place Page 48 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 N
N
.9
.~# ---
I Figure 5-6: ARRR Core and Support Structure Page 49 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Radiation Beam Catcher Shield Reactor Core Thermal Column Figure 5-7: ARRR Reactor Tank Cutaway and N-Ray Facility Page 50 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision I LEAD BALLAST SEAL IRRADIATION VOLUME Figure 5-8: ARRR In-Core Irradiation Capsule Page 51 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 5-9: ARRR Machine Shop Page 52 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 5-10: ARRR Chemistry Lab Page 53 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 I
Figure 5-11: ARRR Preparation Lab Page 54 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 5-12: ARRR Mezzanine Sheet Metal Fabrication Area Page 55 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 5-13: ARRR Mezzanine Sheet Metal Fabrication Area & HVAC Unit Page 56 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 5-14: ARRR Mezzanine Storage Area Page 57 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 5-15: ARRR Mezzanine Instrument Calibration Area Page 58 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 5-16: ARRR Electronics Lab Page 59 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 5-17: ARRR Shipping & Receiving Page 60 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 5-18: ARRR N-Ray Setup Area Page 61 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 5-19: Office Space Page 62 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 5-20: Customer Viewing Area Page 63 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 5-21: Quality Control Room Page 64 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 5-22: Computer and Counting Room Page 65 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 5-23: Tagging Area Page 66 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 5-24: Tagging Area Back Room Page 67 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 5-25: Backup Cooling Tower Page 68 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 5-26: Main Cooling Tower Page 69 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 5-27: Storage Building Page 70 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Figure 5-28: Waste Storage Tanks Page 71 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 6.0 ESTIMATION METHODS The estimated cost to decommission the ARRR is $3,376,030. This section of the cost estimate report provides an overview of the considerations and factors that influenced the decommissioning cost estimate. Table 6-1 provides a summary of the costs associated with each area of the facility.
Table 6-1: Decommissioning Cost Summary - ARRR Man- Labor Plus Equipment, Radwaste Operation hours Trav. & Liv. Contracts & Shipping & Total Cost Supplies Disposal TRIGA Reactor 6,147 $591,527 $97,714 $329,135 $1,018,377 TRIGA shielding & 76 $0 $26,816 $76,349 $103,165 N-Ray Components Buildings 2,727 $261,150 $64,981 $314,779 $640,910 Outdoor Areas 530 $48,929 $43,935 $365,814 $458,678 Decommissioning 240 $22,800 $0 $0 $22,800 Planning Characterization 455 $47,712 $2,335 $0 $50,046 Surveys Final Surveys 1,820 $190,846 $9,338 $0 $200,184 Planning, Training, 404 $36,544 $0 $0 $36,544
& Mobilization Oversight Licensing& 1,527 $140,120 $0 $0 $140,120 NRC Verification $0 $0 $0 $30,000 Survey Totals 13,926 $1,339,629 $245,118 $1,086,077 $2,700,824 25% CONTINGENCY $675,206 GRAND TOTAL $3,376,030 6.1 COST MODIFYING FACTORS There are modifying factors that significantly affect the overall cost for remediation. One of these factors is an adjustment for productivity related to personnel protection requirements and working temperatures. The degree of protection required depends upon the extent of contamination and specific activities to be performed in a given area. As the level of personnel protection increases, so does the impact on individual productivity and task duration.
Adjustments were made to account for the implementation of personnel protective measures where applicable. This estimate used the standardized levels of personnel protection described in Page 72 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 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.
Table 6-2: Personnel Protective Equipment Protection Summary Protection Level Personnel Protective Equipment Requirement lA: The highest available level of respiratory, skin, and eye protection The highest level of respiratory protection, but less skin protection than Level A. Level B is the minimum level Level B: recommended for initial site entries, or for other entry conditions dealing with unknown hazards.
The same level of skin protection as Level B, but a lower level of respiratory protection.
Skin protection similar to or the same as Level C, without respiratory protection.
Standard work uniform suitable for construction work: no Lrespiratory protection and minimal skin protection.
Page 73 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Table 6-3: Hazardous and Toxic Waste Productivity Factors: Light Work Variables U/M Level A Level B Level C Level D Modified Level D T<70 70<T T>85 T<70 70<T T>85 T<70 70<T T>85 T<70 70<T T>85 T<70 70<T T>85 A. Standard losses Min. 160 160 160 140 140 140 128 128 128 76 76 76 32 32 32 B. Scheduled/heat stress breaks Min. 60 90 120 43 65 86 35 63 101 30 47 63 30 33 44 C. Dexterity losses Min. 78 69 60 74 69 64 55 51 44 4 4 3 5 5 5 D. Total time lost per 8-hr. WD Min. 298 319 340 257 274 290 218 242 273 110 127 142 67 70 81 E. Productivity time per 8-hr. WD Min. 182 161 140 223 206 191 262 238 207 370 353 338 413 410 399 F. Productivity time on clean site Min. 430 430 430 430 430 430 430 430 430 430 430 430 430 430 430 G. HTW Productivity Factor 0.42 0.37 0.33 0.52 0.48 0.44 0.61 0.55 0.48 0.86 0.82 0.79 0.96 0.95 0.93 Notes:
" Standard delays account for all time losses independent of temperature variations. They include safety meetings, instructions, putting on and taking offofPPE, decontamination, switching air supply/filters, monitoring delays, and cleanup.
" Scheduled/heat stress breaks account for all paid rest periods per workday.
" Dexterity losses are based on subjective opinions of the percentage that PPE slows down a normal worker because of factors such as discomfort, clumsiness, weight, and restricted breathing and communication. The number of minutes actually worked is reduced by the percentage representing the average response for that particular PPE level.
" Values for A, B, and C were derived by averaging the survey responses for each PPE level. Responses that varied greatly from the average were subject to omission at the author's discretion.
- Total paid time = 480 minutes.
- 50-minute delay on clean site = 10-minute safety meeting and instructions + 10-minute cleanup + 30-minute breaks.
- Calculations: D:= A + B + C U/M = unit of measure E = 480 - D WD = workday F = 480 - 50 Min. = minutes G E/- T = temperature (Fahrenheit)
Level A-protection is used in extreme emergency situations only. Productivity factors for Level A should be used with caution because they were extrapolated from 2 data points.
Page 74 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Table 6-4: Hazardous and Toxic Waste Productivity Factors: Heavy Work Variables U/M Level A Level B Level C Level D Modified Level D T<70 70<T 1>85 T<70 70<T 1>85 T<70 70<T T>85 T<70 70<T T>85 T<70 70<T T>85 A. Standard losses Min. 220 220 220 204 204 204 135 135 135 76 76 76 28 28 28 B. Scheduled/heat stress breaks Min. 60 105 150 50 75 123 64 131 178 30 90 165 30 45 60 C. Dexterity losses Min. 80 62 44 52 46 35 44 34 26 28 24 18 11 10 10 D. Total time lost per 8-hr. WD Min. 360 387 414 306 325 362 243 300 339 134 190 259 69 83 98 E. Productivity time per 8-hr. WD Min. 120 93 66 174 155 118 237 180 141 346 290 221 411 397 382 F. Productivity time on clean site Min. 430 430 430 430 430 430 430 430 430 430 430 430 430 430 430 C. HTW Productivity Factor 0.28 0.22 0.15 0.40 0.36 0.27 0.55 0.42 0.33 0.80 0.68 0.51 0.96 0.92 0.89 Notes:
- Standard delays account for all time losses independent of temperature variations. They include safety meetings, instructions, putting on and taking off of PPE, decontamination, switching air supply/filters, monitoring delays, and cleanup.
" Scheduled/heat stress breaks account for all paid rest periods per workday.
" Dexterity losses are based on subjective opinions of the percentage that PPE slows down a normal worker because of factors such as discomfort, clumsiness, weight, and restricted breathing and communication. The number of minutes actually worked is reduced by the percentage representing the average response for that particular PPE level.
- Values for A, B, and C were derived by averaging the survey responses for each PPE level. Responses that varied greatly from the average were subject to omission at the author's discretion.
- Total paid time = 480 minutes.
- 50-minute delay on clean site = I 0-minute safety meeting and instructions + I0-minute cleanup + 30-minute breaks.
" Calculations: D= A + B + C U/M unit of measure E = 480 - D WD workday F = 480 - 50 Min. = minutes G = E/F T = temperature (Fahrenheit)
- Level A-protection is used in extreme emergency situations only. Productivity factors for Level A should be used with caution because they were extrapolated from 2 data points.
Page 75 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006
.Aerotest Radiography and Research Reactor Revision 1 6.2 RADIOACTIVE WASTE VOLUME ESTIMATES The volume of radioactive waste requiring treatment and disposal can be a very significant modifying factor due to the high cost for radwaste disposal. For the ARRR decommissioning, the cost for radioactive waste processing, shipping, and disposal is anticipated to be about 27%
of the total decommissioning cost. This is a normal fraction for relatively clean radioactive facilities. Radioactive waste volume estimates are discussed in the following section. Table 6-5 provides a volume summary for each area of the ARRR. Information about most waste items is provided in Appendix A 14.
Table 6-5: ARRR Unprocessed Radioactive Waste Summary Generated Decon Direct Clive Clive Clive Total Disposal Disposal Disposal Disposal Volume Volume Volume Volume Area Description (ftA3) (ftA3) (ftA3) (ft^3)
TRIGA Reactor 54 0 349 403 TRIGA Bioshield & N-Ray Components 0 0 284 284 Buildings 34 62 967 1,064 Outdoor Areas 6 0 1,476 1,481 TOTALS 94 62 3,0763,3 6.3 RADIOACTIVE WASTE DISPOSAL COSTS A significant portion of the overall decommissioning cost is generally attributed to the burial of radioactive waste. This estimate includes waste processing followed by disposal at Clive Utah and direct radioactive waste disposal at Clive Utah. The following sections describe the pricing for each facility.
6.3.1 Clive Utah Disposal Costs The costs to transport waste to the Clive Utah disposal site are based on a transport distance of 609 miles, at a rate of $2.97 per mile. The cost to dispose of the waste at the Clive Utah site is based on a disposal fee of $242 per cubic foot.
6.3.2 EnergySolutions Processing/Burial Costs The cost to transport waste to the EnergySolutions central volume reduction facility in Oak Ridge Tennessee are based on a transport distance of 2437 miles at a rate of $2.97 per mile.
Waste processing at the EnergySolutions central volume reduction facility was not included in this estimate because there was not a significant cost advantage to waste processing.
Typical unit disposal cost factors are listed in Appendix A 3.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 6.4 REMEDIATION METHODS The goal in choosing remediation methods is to select the minimum cost option to accomplish a task. There are many factors which need to be considered when selecting a method such as contamination levels, degree of penetration of contamination into substrate material, equipment cost, support equipment costs, material and chemical costs, the generation of secondary waste volumes (waste in addition to the removed contaminated material), processing rates, labor requirements, and applicability to various tasks. Typical decontamination processes are summarized in Table 6-6. For each decontamination method, this table shows application information, the process cost per square foot of area decontaminated, and the amount of secondary waste generated. These unit factors are applied to specific areas or equipment requiring remediation to determine the most cost-effective process.
Table 6-6: Decontamination Methodology Comparison Penetration Process Secondary depth Crew Cost Waste Volume 3
Methodology Application (in) Size ($/ft.) (ft /1000 ft)
McDonald U-5 Scabbler Floor concrete 1/4 2.0 $1.24 McDonald U-5 Scabbler Floor concrete 1/2 2.0 $2.20 0 McDonald 3WCD Scabbler Wall concrete 1/8 2.0 $4.98 0 Blastrac 10D Shot Blaster Floor concrete 1/16 I.I $0.43 053 Blastrac IOD Shot Blaster Floor concrete 1/8 I.I $0.55 0.53 LTC 10-60Pn Special All surfaces 1/32 1.3 $2.23 0.53 Vacuum Blaster LTC 10-60Pn Special All surfaces 1/16 1.3 $3.70 0.53 Vacuum Blaster C02 Blasting All Surfaces 0 2.0 $4.56 0 Hydrolaser (5-10,000 psi) All Surfaces 0 2.0 $0.94 9.07 Hands-On-Decon Non-Porous surfaces 0 1.0 $2.16 8.33 6.5 RADIOACTIVE WASTE VOLUME REDUCTION COSTS The volume reduction processes analyzed for use are summarized in Table 6-7. For each volume reduction method, this table shows application information, transportation container type, and the total process cost per unit weight. These unit factors are applied to specific items of equipment requiring disposal to determine the most cost-effective process. The radioactive waste generated at this facility will include irradiated hardware, activated concrete, HEPA ventilation systems, fume hoods, steel, lead, and secondary waste generated during the decontamination work such as protective clothing and materials used during manual decontamination work.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Table 6-7: Volume Reduction Methodology Cost Information Transport Total VR Cost VR Methodology Applicability Container Type ($/Ib)
Super Compaction Dry active waste B-25 for Clive Utah $6.18 20 lb/ft3 Disposal Incidental Lead Bricks and Sheet Custom Box $4.92 Decontamination Survey & Release Low Density Waste 55 Gal Drum $2.38 Low Density Drums Survey & Release Waste at greater than B-25 Box $1.27 Medium Density Boxes 20 7< 60 lb/ft3 Survey & Release Waste at greater than B-25 Box $0.92 High Density Boxes 60 lb/ft3 6.6 UNIT COSTS A number of unit factors were used to generate this cost estimate. The main unit factors are listed in Table 4-8 so project costs can be updated when required and the effects of changing unit costs can be evaluated.
Table 6-8: Decommissioning Cost Estimate Selected Cost Factors Unit Cost Factor Unit Cost Rate Units Radioactive Soil and debris Disposal at Clive Utah $242.46 cubic foot Waste Transportation to Clive Utah $2.97 mile Transportation Distance to Clive Utah 609 miles B-25 Waste Disposal Container Cost $2,220 each Management and Supervision $144.23 hour Engineer $133.93 hour Radiation Protection Supervisor $113.33 hour Laborer Foreman $71.91 hour Administrative Assistant $36.06 hour Instrument Technician $73.66 hour Radiation Protection Technician $73.66 hour Laborer $71.11 hour Fee 15%
6.7 FINAL SURVEYS Final survey costs are estimated based on the facility radiation survey information presented in NUREG-1757, MNSS 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 Page 78 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 determined. The time to perform each of these surveys is estimated, and the product of these two items is the labor time to perform the surveys. Equipment and material cost to perform the surveys is added along with staff support costs to determine a total cost. The survey requirements are based on NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) Ref. 8.8). A spreadsheet was developed which incorporates facility dimensions, labor rates and support cost ratios to estimate the final survey cost. The facility survey labor estimate is summarized in Appendix A 6 and the open land and miscellaneous area survey labor estimate is summarized in Appendix A 7.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 7.0 FACILITIES, RADIOLOGICAL CONDITIONS AND DECOMMISSIONING SCENARIO Decommissioning of the ARRR requires that residual radioactive materials be removed from the site to allow removal of the decommissioned facilities from the NRC license and State of California License. For the purposes of this cost estimate, the end of the decommissioning project occurs when the ARRR has been remediated to release limits; the Final Status Survey has been performed, documented and submitted to the NRC and the State of California.
7.1 REMEDIATION
SUMMARY
Remediation will be required for the ARRR, it is not anticipated that remediation in sewers and outdoor areas will be required. The following is a brief summary of the anticipated remediation activities, with applicable assumptions and bases. The remediation activities are summarized in Table 5-1 below. Additional facility information, radiological information, and decommissioning plans are presented in greater detail in the document sections that follow.
Table 7-1: ARRR Planned Remediation Activities Building or Area Remediation Activities General Area Perform a general facility clean up to remove all incidental equipment and materials, both radioactive and non-radioactive. This activity is performed as part of preparation activities that can be completed prior to reactor decommissioning.
Non-Reactor Remove all equipment and materials not associated with operation of the Remediation reactor. This includes equipment used in the preparation of items for N-Ray and the N-Ray components outside the reactor tank. These activities are performed as part of preparation work that can be completed prior to reactor decommissioning.
TRIGA Reactor Empty water from reactor tank. Remove activated reactor core and vessel internals, bridge and reactor vessel. Remove Beam catcher, bioshield wood and bioshield blocks. Remove N-Ray components including neutron guide, exposure tray and shields. Leave beam port in place as it is unused and not activated. Cut out activated concrete surrounding reactor tank and dispose of as radioactive waste.
Demin & Heat Remove the Demin and Heat Exchange Systems, decontaminate the Exchange Systems concrete pads in the demin and heat exchange buildings and demolish the buildings.
Reactor High Bay Remove all equipment and materials from the Reactor High Bay building Building that are not part of the structure or utilities. Remove contaminated portions of the HVAC system if any.
Other Buildings Remove all equipment and materials from the other buildings that are not part of the structure or utilities.
Outdoor Areas Remove all equipment and materials outside the buildings that are not part of site utilities. This includes the Cooling Towers, Waste Tank System,
__ _ . Shielding, spare ion exchange columns, etc.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 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 California 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 left in place as the concrete is not contaminated. In the case of prompt decommissioning, about one foot Page 81 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 of concrete near the core may need to be removed. The prompt decommissioning activated concrete to be removed 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 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 will be removed. In the case of delayed decommissioning (-50 years), the Ca-45 and Mn-54 will have decayed to less than the anticipated 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 are not contaminated. The Co-60 in the tank walls will have decayed away and the activity in the concrete behind the aluminum tank will have decayed away also as indicated above. In the case of prompt decommissioning, the pool liner will 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 Demin and Heat Exchange Buildings The Demin and Heat Exchange Systems are contaminated and will be removed, characterized and shipped for disposal.
The Demin and Heat Exchange Buildings are contaminated and will be removed, characterized and shipped for disposal. The lead shielding in the Demin Building will be sent offsite for processing and disposal. The spare demineralizer in the building will be characterized and shipped offsite as radioactive waste. The concrete pads in the Demin and Heat Exchange Buildings are contaminated and the pads will either be decontaminated by concrete surface removal and the remaining pads disposed of as clean waste or the pads disposed of as radioactive waste along with the rest of the building.
7.1.5 Reactor High Bay Area All equipment in the Reactor High Bay Building that is not part of the structure or utilities will be removed for disposal and contaminated building surfaces will be decontaminated. It is anticipated that this activity will include the following items:
Radwaste Room: The room waste will be characterized and sent offsite for disposal as radioactive waste. The lead will be sent offsite for processing and disposal. The asbestos floor tile will be removed and sent for disposal as radioactive waste. The floor will be decontaminated by surface concrete removal and 10% of the lower walls will be decontaminated by surface concrete removal. About 25% of the walls will be decontaminated by a hand wipe down.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Machine Shop: Any remaining small tools, supplies cabinets and tables will be surveyed and removed from site. The large equipment including Drill Press, Milling Machine and Lathe will also be surveyed, decontaminated if necessary and removed from site. The asbestos floor tile will be surveyed, removed and sent for disposal as asbestos waste or radioactive waste.
Office Areas, Locker Room and Supply Room: Any remaining furniture, supplies cabinets and tables will be surveyed and removed from site. Any asbestos floor tile will be surveyed, removed and sent for disposal as asbestos waste or radioactive waste.
Restrooms: In general these rooms do not require any remediation. Any items and materials in the supply closet in the men's 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-ft by 40-ft around the reactor pit will be decontaminated by surface concrete removal. The HVAC ductwork and heating and cooling units will be surveyed and any contaminated items removed for disposal as radioactive waste. The roof insulation material will be surveyed and removed for disposal if any contamination is found. In addition the overhead lights will be surveyed and removed for disposal if any contamination is found. The florescent light bulbs and ballasts will be removed for separate disposal as they contain hazardous materials.
Mercury in the bulbs and probably PCB's in the ballasts.
7.1 .6 High Bay Mezzanine Area
- N-Ray Gauge Office, Preparation Lab, Hallway and Chemical Lab: In the Chemical lab the hood and support bench along with the lab benches and sinks will be surveyed and removed from site. In the Preparation Lab the marble weighing benches will be surveyed and removed from site. Any remaining equipment, furniture, supplies and cabinets in any of these rooms and will be surveyed and removed from site. The asbestos floor tile will be surveyed, removed and sent for disposal as asbestos waste or radioactive waste.
Sheet Metal Fabrication Area, Storage Area, Calibration Area and Electronics Lab: The radioactive items on the table top in the Sheet Metal Fabrication Area and the shield cave made from cement blocks on the floor will characterized and shipped for disposal as radioactive waste. Any remaining equipment, furniture, supplies and cabinets in any of these areas will be surveyed and removed from site. The asbestos floor tile will be surveyed, removed and sent for disposal as asbestos waste or radioactive waste.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 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. On the south side of the Office there is an added structure that contains a large demineralizer undergoing decay. This demineralizer will be characterized and shipped for disposal as radioactive waste.
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.
Spare Demin Units: There are three large spare demineralizers that were obtained from the University of California at Berkeley. One unit was in the small addition to the Maintenance Office. Two of these units were never used at ARRR and are stored on the north side of the Storage Building. These units will be characterized and disposed of as radioactive material.
Waste Sump and Tanks: The waste sump and waste tanks are potentially contaminated.
The two waste tanks will be drained if required, surveyed for potential contamination, decontaminated if necessary and shipped offsite for disposal. The Waste Sump pump, valves, and controls will be characterized and shipped for disposal as radioactive waste.
The concrete sump will be excavated, including bottom pad, and shipped for disposal as radioactive waste.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Shield Blocks: There are quarter circle shield blocks in the vicinity of the waste tanks and the demin system that were used to shield the fence line from high dose rates. These blocks were never in a contaminated area and will be shipped offsite.
The sanitary and storm sewers will be surveyed at accessible areas and released for continued use.
7.2 LICENSE TERMINATION SURVEYS License termination surveys, or final radiation surveys, will be performed in the applicable areas of the site using the guidance provided in NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM), (Ref. 8.8). The surveys will be performed in accordance with specifically developed plans and procedures.
7.2.1 Survey Instrumentation Selection and use of instrumentation will ensure sensitivities are sufficient to detect the identified nuclides at the minimum detection requirements. A list of typical final survey instrumentation, radiation detected, and calibration sources are provided in Table 7-2.
Table 7-2: Typical Final Survey Instrumentation Instrument/ Detector Radiation Calibration Detector _T ype Detected Source Use Direct alpha and Ludlum Model direct beta 2350 wt. 43-68, Gas-flow surveys; Beta 43-98, 43-94 or proportional 99Tc (13) scans on solid 43-106 detector (126cm 2) Alpha or beta 23°Th ((X) surfaces.
Ludlum Model 2350/ SP-1 13-3m GM Pipe 99Tc (13) Direct beta pipe or SP-175-3m Detector Alpha or beta 23Th) survey.
Direct beta Ludlum Model surveys; Beta 2350 wt. 44-40 Shielded GM scans on solid detector (15.5cm 2) Beta 99Tc surfaces.
Ludlum Model Gamma exposure 2350 wt. 44-2 or Nal (TI) rate and gamma 44-10 detector Scintillator Gamma 137Cs scans.
Eberline Teletector Model Gamma exposure 6112B Ion Chamber Gamma 6°Co (,) rate Eberline SAC-4 Scaler Counter ZnS scintillator Alpha 23°Th (x) Smear counting Eberline BC-4 99 Scaler Counter Shielded GM Beta Tc (13) Smear counting Page 85 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision I Instrument/ Detector Radiation Calibration Detector Type Detected Source Use Tennelec Planchette Shielded Gas-Counter or Equal flow proportional Alpha and Beta 99Tc (p3), 2 30Th (a) Smear counting Nuclide EG&G NOMAD identification and Gamma quantification of Spectrometer or Gamma energy soil and sand Equal HPGe and intensity Mixed gamma I samples.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Activated concrete near core removed Activated concrete below core removed Figure 7- 1: ARRR Activated Concrete Page 87 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1
8.0 REFERENCES
8.1 10 CFR50.82 TERMlNATIONOFLICENSE, PART (B) FORNON-POWERREA CTORLICENSEES 8.2 10 CFR 20 SUBPART E - RADIOLOGICAL CRITERIA FOR LICENSE TERMINATION 8.3 NUREG 1537, GUIDELINES FOR PREPARING AND REVIEWING APPLICATIONS FOR THE LICENSING OF NON-POWER REACTORS, FEBRUARY 1996 8.4 R.A. MEANS COMPANY, INC., MEANS BUILDING CONSTRUCTION COST DATA, 2011, 69ST ANNUAL EDITION 8.5 NUREG/CR-1756, TECHNOLOGY SAFETY AND COSTS OF DECOMMISSIONING REFERENCE NUCLEAR RESEARCH AND TEST REACTORS, MARCH 1982 8.6 CS-HP-PR-008, CHARACTERIZATION REPORT FOR THE AEROTEST RADIOGRAPHY &
RESEARCH REACTOR, SAN RAMON, CALIFORNIA, OCTOBER 2011 8.7 10 CFR 20.1402 RADIOLOGICAL CRITERIA FOR UNRESTRICTED USE 8.8 USEPA, 2000, U.S. NRC, U.S. DOE, AND U.S. DOD, MULTI-AGENCY RADIATION SURVEY AND SITE INVESTIGATION MANUAL (MARSSIM), REVISION 1, NUREG-1 575, EPA 402-R-97-016 8.9 NUREG-1 757, CONSOLIDATED NMSS DECOMMISSIONING GUIDANCE, DECOMMISSIONING PROCESS FOR MATERIALS LICENSES, SEPTEMBER 2002 8.10 NUREG/CR-5512, "RESIDUAL RADIOACTIVE CONTAMINATION FROM DECOMMISSIONING:
PARAMETER ANALYSIS", VOLUME 3, OCTOBER1999 Page 88 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Appendix A 1 Contaminated Waste Volume Summary Table A41 CONTAMINATED WASTE VOLUM MMAY ARRR, San Ramon California CODE 2
3
'4 Baildings
~~
Outdoor Arons6 prcM(ti
~
1eAREA scipteon DeGenerWated door eM TGneraled &N-Ray Components Des sul tems TOTLS tretedde Wadte vdume a
0 4
en.)
( _
volume M))(.
0 a
Vat.
Waste tR^3*
__m.W tall 284 9a7 IA4Y6 3,076 1 Waate* Voame Total 284 1,064 1*uM 3,3 I Decon Wade Volume: This Is the volume of waste generated dlretly by a decontaminaton prawns ( this Includes such items blstn Wit, treated chefmclds, etc.).
2 Generatedl Waste Volume: This is the volurme of protective clothing waste ge~nerated by all operations on site and Is a functio of Mor*hours for each activity.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Appendix A 2 Contaminated Waste Disposal Cost Table A-2 CONTAMINATED WASTE DISPOSAL COST ARRR, San Ramon California Generated eon
.. C* ve ToW Area Clive Clive Direct Bry Waste Description Disposal Disposal Disposal Disposal cost Cost Cost Cost 1 mGA Reactor $12300 $0 $79,116 $91,419 2 13141ihlosield
&Mt-RaN Conponets so so $64.449 $64449 14 21,14 $241,007 4 OUMdooArlin $131 $, $334.391 U165,706 TOTALS: *21,370 $14,107 $697,102 $356 Note 1.Shading mctea a named taild Iinked to anedier speadshleet.
- 2. Dired burlal &generated waste shipped to Bernwell.
WASTE DISPOSAL PACKAGING & SHIPPING COST Generated becon Clive Total Area Clive Clive Direct BWy Waste Oescrlptlon Pack & Pack & Pack & Pack &
Slip ip Ship Smip Cost Cost Cost Cost I TRIGA Reator $91 $0 SW5 $676 2 TRIGA oseid&N-RayCompones $0 $0 $476 $476 3 an $57 $104 $1,620 $i 781 4 Outdoor Areas $10 $0 $2,471 $2,481 TOTALS: $158 $104 $5,152 $5,414
- Notes: M E 6 1 Shading indicates a named field linked to another spreadsheet.
2 These are ekdusive use shlpments and thee is a nminirrm cost for shipping oa Page 90 of 103 I
Decommissioning Cost Estimate for the CS-HIP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Appendix A 3 Waste Shipping Container Cost Table A-3 WASTE SHIPPING CONTAINER COST ARRR, San Ramon California Total B-25" Waste Area Waste Waste Container Description Volume Containers Cost J11-3) (Ea.) ($
1 TRIGA Reactor 403 4.5 $9,951 2 TRIGA Bloshleld & N-Ray Components 284 3.2 $7,016 3 Buildings 1,064 11.8 $26,235 4 Outdoor Areas 1,481 16.5 $36,543 TOTALS: 3,233 36 $79,920 Notes:
1 The number of waste containers is rounded up to next full container.
UNIT DISPOSAL COSTFACTORS DAW W*ste diSO rt,,0 fO( CiveG: $22w.bU per cubic Toot Estimated transpod distance to VR Mte: 2,437 MODS Estimated mtiles" rate to Clive : $2.97 per mile Estimated trarmport dstance to Clive: 609 amles Average direcit burymate densty": 27.5 Ib/cMc foot Average generated waste density (Clive ast*): 25 lblcublc foot Truck transport vste weight lmit: ",000 pounds Truck transport weste "wiumouniit: 12 1-25 Boxes B-25 box Intearne volume ; 90 cublc feet Estimeted cost of used W-25 shipping containers: $2,220.00 each Local industridal Waste Landf Shipping & Disposal Rate: $25.00 per cubic yard Labor rate for shipinog: £71.50 ner hour
$71.50 per hour Page 91 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Appendix A 4 Waste Disposal Labor Estimate Table A-4 WASTE DISPOSAL SUPPORT LABOR ESTIMATE ARRR, San Ramon California 8-25 Radloactive* Waste Area Waste Waste Shlpment Description Containers Shipnmens Labor (Ea. (Efa.) (-r 1 TRIGA Reactor 4.5 0.4 6,0 2 TRIGA Bloshleld & N.Ray Components 3.2 0.3 4.2 3 Bulldings 11.8 1.0 158 4 Outdoor Areas 16"5 1.4 21.9 TOTALS: 36.0 3.0 48.0
- Notes:
1 The number of weste shipments Is rounded up to next full shipment.
Estimated waste loading operator time: 4 hr per load Estimated HP Tech time per rad or mixed vwsts load: 4 hr per load Estmated HP shlipper time per red or mixed waste load: I hrper load Estimated dean waste slipping volume limit: 1176 IIA3 per load Estimated radmste shipping volume Emit: 12 5-25 Boxes WASTE DISPOSAL CASK COSTS ARRR, San Ramon California Liners & Radloactve' Waste Area Cask Cask SNpment D psclripon Rental Rental Labor (Es.) cost Imnw-hr) 1 TM" Reactor 0.0 0 2 TRIGA Blostield &N-4Ray Components 1 $19,800 72 3 Oundlngs 00 0 4 O rldoorAreas 0.0 0 TOTALS: 1.0 $19,600 72 Notes:
1 The number of waste shipments Is rounded up to next IUIE shipment.
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Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Appendix A 5 Contaminated Waste Disposal Summary rable A-S CONTAMINATSD WASTE DISPOSAL
SUMMARY
ARRR, San RaMrn C&IfomM Taw Wa. ico i Wait. apw SnMon Wat. Vokawe Conlcos Col sr Labor Labor
_ _M)_ 1=7) ($) 4e0) (.Mmt.l) cost 1 403 41 $,961j 0.4 80 $427 M.284 1.2 $ __*_1_ M_3 761.i $5,44 31.094 1lt_8 $26 235 1t0 Me $I'll?
1.481 t6. S36,53 1.4 21,9 $1,5*9 rc33 36.0 W54 4.0 11s.6 ,563 1 The nurra of oawiwrs we roilde up tonat futl MtOtwwer 2 Them~ wstoOtvrt am ramded uPtwo nextANitmer Page 93 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Appendix A 6 Building Survey Labor Summary NON-IMPACTED BUILDING AREA SURVEY Table A4 ARRR, San Ramon California ENTER SURVEY ENTER ENTER ENTER ENTER ENTER BELOW ENTER ENTER ENTER PACKAGE AREA AREA AREA FLOOR- U.WALL÷ ENTER FLOOR- U WALL. SURVEY ODIECT OPTNL BUILDING ROOM AREA REGRD WIDTH LENGTH HEIGHT L. WALL CELING SlTuV L.WALL CEILING ROOF TOTAL PACNAGEEJR4mY OC N4AME NJE.ER DE5CRIP11ON ? BELOW BE.OW BELOW SLRVEY SURVEY Skgtchs SUg Y SURVY UY SURVEYSMEAR PREP LAeOR CODE BLOW BELOW CODE CODE (ech) POITS POITS POINTS G.'s 0)
J NNrelEoln 3 High941R-,0 0540 IMPACTED BUILDING AREA SURVEY Table A-6 ARRR, San Ranon California ENTER SURVEY ENTER ENTER ENTER ENTER ENTER UPPR GAA BELOW ENTER ENTER ENTER PACKAGE AREA AREA AMA FLOOR+U. WALL÷ EN111- FLUOR* WAt* SURVY SUIRVEY DIRECT OPTNL BUILDING ROOM AREA REORD WIDTH LENGTH HEIGHT LWALL CEILING SUVwj LWeALL CEIJIG ROOF .R PACKA6E SURVEY LOC NAME NUMBER DESCRIPTION ? BELOW BELOW BELOW SURVEY SURVEY Sketchs SURVEYs9RwEY SU6RVEYSEAR PREP LABOR CODE BELOW BELOW BELOW (YIN) (It) (3 NO) CODE CODE (inch) POINTS PONTS POINTS POINTS ) Oft 49 4 14 126 4 24 146 22 so 4 2X 41 41 i 49 1(
61 4 1.
93 14 soI 93 4 14 66 12 i46 4 32 76 1 57 1 39 44 NA 1
__48_ 4 _ 14 112 1!
62 1!
191 21 72 11 47 4 14 2 = 22 d 103 of 94 Page Page 94 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Appendix A 7 Outdoor Area Survey Labor Summary NON-IMPACTED UNPAVED AREA SURVEY Table A-?
!- "~- -'-"
ARRR, San Revie Calfambla NON-IMPACTED PAVED AREA SURVEY TabO A-? A aRI Smi Rmon" California ENTER ViY HTI Ia"ERN BELOW SEN STER PACKAGE AREA AREA N OPTINONAL.IRI'ACE AREA REGMO V00N IBIGTH N. 0iw W ~Ruld~mMn 4 U NSY ACKiA" %V r,*WW 1U LOC IYPE DESCRIPTION 7r SELO BELOW G tA 4ý*ft 0 E.r4,PUWI$Ch, PAwW w CODE BEILO Sao" 2r' eOin) S-1 .1.,B - .5 Ms.Ws (MONH1A onw) 4 1 Aw- I" P..d All. 44 1? 2 0 2 51 4 1 Table A-7 ARRR, San Ramon California CATCH BASIN & CLEAN-OUT SURVEY 081I SURVEY DURATION (lyE?: 4 BASKN SURVEY CREW USIZ mon): i ENTER ENTER SURVEY BELOW ENTER BASH PACKAGE SURVEY OPTIONAL AREA DIAMETER REORD PACKAGE SURVEY LOC DESCRIPTION BELOW 7 PREP LABOR CODE BELOW (? (YIN) 2%,) ((e
"" w "imtp :A IF4 4 merohp".YE" on aln 41 TOTALS 4 12 DRAIN PIPE SURVEY PIPESURVEYRATE=(~t 40 PIPE SURVEY CREW SIZE 3 3men):
ENTER ENTER SURVEY OPTIONAL ENTER PIPE PIPE PACKAGE SURVEY COT AREA DIAMETER LENGTH REORD PACKAGE SURVEY CODES DESCRIPTION BELOW BELOW 7 PREP LABOR BELOW BELOW (111) Qf (YIN) Wer) this) 4 Siam~Drain 24 16 y 4 16.3 4 Santary Sew 24 150 y 4 161 TOTALS 8 31 Page 95 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Appendix A 8 Instrument Lease Charges TWOA4 INSIRUMINT COSTS AM Owm IRmo CaWNm-A 4 OW ROM i - I -- - - - --- i -- ! 1 T*TfiLMVMW*wM" "M 1 M99t771M Page 96 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Appendix A 9 Equipment Lease Charges TiM* A4 INSiNUMET COMt ARRK Son Ftwo.n Csac8 4 08 46"Ow IAAU R" " q Uwew.
OActhIcw"u. hOqWM." D&n~l.
VAN" WMUA RAA 4VIEWT W I1AAOIF M~~LT TMrkwo O( IWIW7Vi4WMDA =4"k7 .
Ltý.awv IAUM Page 97 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Appendix A 10 Consumable Costs Tail. A-tO CONSUVALE COMtS
.C0 F .,wy ." vow AR, OwRwnon CoaTII Page 98 of 103 10 of 9Pa
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Appendix A 11 Demolition Estimate Table A-11 Demolition Estimate ARRR, San Ramon California LABOR BASED DEMOLITIONCOSTS- Labor be rnan-hour oanagenrent.Surpoeeision.& HP Support Labor Notncludedo LltliOperator & OEMOLITION LOC WEE Cratttmen Laborers Caftsrnan HP Tloh LABOR TOTAL CL0E No. AREA "9.80 $69.03 $69580 $71.50 hours PRICE 3 General Cleanup 20000 50.00 2500 317.300 1 Remove Reactor Core and Internals 80 00 40.00 1200 B0.392 I Ep Raor o Pool 40.00 20.00 6e0 T 2.761 Shp eactar Core and Related Internals 4000 2000 400 02.00 3 Ron-os- Reactor Buildina Eovomenrt 400 0 10000 4000 $27,l10 3 . I . HealE;IrhMn,nrS'ý e 40101
[0n0 2n non 4n n S2.761 3 Remve DernonSystem 40 00 2000 40 0 $2.76c 3 Pacae &,Ship Contai M tenal, &Radioactoe Wastes 16010 4000 1600 $11.044 02.O1' 1,110.0 $75,460 TASK BASED DEMOLIWON COSTS 67% Haxardous & Toxic Waste Produotivity Factor. Level C. Heavy Work, 70 - 85OF Percent Labor Coot 65.00% MATERIAL LABOR EQUIPMENT MATERIAL LABCO EQUIPMENT LCO: WS Average Hourly Labor Rate $24.90 UNIT hre UNIT LtNIT TOTAL TOTAL TOTAL TOTAL CODE No AREA QUANTITY UNIT PRICE PRICE PRICE PRICE PRICE PRICE PRICE Remoce Coocrete ArOund Pool 72 EA cubic yard 041 62 00 0 T4.472 $0 $4 472 I Reonc Concrete Under Pool 0.7 EA cub-c yare 041 2 $000 $300 $0 0300 Remove ,:aoden Chieldrng 3.2 Ton 85 8 $40 2 $OT 02.142 $0 02,142 I Renove Bioshield Blocks 82.4 Ton 2 1974 42 44-1 .0 00 354.808 $0 054.868 3 Rerove *verhead Lights 12 EA T 1401 T020 $066 $0 $256 3 Remoe Ventilation Dutting 100 L.F 040 0 0o00 $098 $0 1686 3 Remove RX BldgHVAC Unit 20 Ton 53 3 $44302 00 0n
$1.331 T0 $1.331 4 Renrve Main Cooing Tnr. 0.88 Ton 23 4 $44392 $000 $585 s0 $585 4 Remove Secondary Caoling Tower 2.6 Ton 69.0 0443.92 $0.00 $1.724 $0 $1,724 3 Remove Corrpresrs 0.19 Ton 50 $44382 $000 $0128 $0 1126 0 Remove Vacuum pumps 0 21 Ton 5B $443 82 $000 0140 $0 140 0 Reroa, Lathe 0.1o Ton 48 0443 92 $0 00 $120 $S $120 0 Remoe D il Press 0.23 Ton 6.0 $443.92 $0.00 $100 $0 1150 0 Remove Milleg Machine 054 Ton 14.4 044382 $000 $359 $0 0359 3 Remove Demn Shed Floor Slob 0 34 EA cub,cyard 418*2 $0000 $21 $0 $21.
3 Remove Ha 8149Floor Slab 0.34 EA cubicyard 041.62 00.00 T2t $0 $21 3 Remove n-in Conrral Cabinet 0.44 Ton 11 8 $44392 $000 $295 $0 0298 I Reoverdge 0 65 Ton 174 0443 9 0 0000 $435 TO 0425 4 Large Waste TonE 0.64 Ton 17.1 0443092 000 0420 00 $427 4 SmOalWante Tank 0.51 Ton 13.7 044302 T0 00 $342 $0 $342 3 Spare L'rge Dernin Units (2 la) 0 37 Ton 0B 043 92 0o 02 $245 T0 $245 3 Large DemninUnitin Decay Made 049 Ton 13.1 .443 02 0O 02 $327 $0 $327 3 Denin Lead Shielding 0.00 Ton 23.0 044000 00 0089 50 0089 3 TaggingRoomFumace 63 Ton 18.7 044032 0000 $41860 $416 S hoemLab Hood 027 Ton 7t1 4438 2 0o00 $177 00 $177 3 ChemnLab Hood SupportGench 0 21 Ton 07 043 92 0c0o $142 $0 $142 3 Chem Lab Benches 0.57 Ton 15.2 $443.92 S0.00 $379 $0 $379 4 Demolish Cherrm. shed 163 CF 24 0250 T0103 0810 $32 $042 4 DmolishDermo BRaIding 18 Cp 28.2 $2 50 $013 704 037 $740 4 Eemolilh H at EoochoangerBulong 324 CT 48.6 02.50 $0.13 S1.213 ;63 $1.276 0.00 0 00 $0 $0 $0 60.0 $73.883.4 6131.9 $74.015 Page 99 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Appendix A 12 Decontamination Costs mat*i M m Itlllt Ci vi rj 1 J
- - r ~,--1 iH--+/--i--~
~ - - -
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- 1 - * ~ ~ ~4'.~- *C~ *C - - - @4 04 @4t 0 44*4 Cr
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Page 100 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Appendix A 13 Volume Reduction Costs TI.b A413 VOUJMI NRJCTWN COSTS AtInk SwRamnC*IW*rMfl SUWKC MAISFMAYOIAJMWRBOATlON CAST AAIALYMNS-C4.FVS UPM4guOIAi.
777,7 ".7" 4 ~ M 197
- r9 t,777 977.9W .7U ~m a* I9 44ftnt L.~*97 07..
77$ a 7., 9tfa 77 7:7 no 9 AS7 74 0*71 I P"1ý Page 101 of 103 I
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Appendix A 14 Miscellaneous Item Volume Estimate Table A-14 MISCELLANEOUS ITEM VOLUME ESTIMATES ARRR, Son Raottn Ceilfosla 010U01ERMATERIAL PERCENT. CLIVE CLIVE CEO~SI.00TI(3J LOC "SS 0 : a 0: SLL LDJIT I241T TOOTAL TOTAL DIRECT I CASPO1L0I0SPOSI C(0DE N) UNITS UNITS C0*0*1RUCT DENITY 1 IGHT VO4UME WVIGHT VOLUM BURY WE.IGHT VOLUME0 DFPSTH P007 TC*u C s I 1(a 2.31
. 15.1 2.631 051 ;00% 2301 1t CLNE PONlTak*S*.u:mtematrA 2w)l I Ea I A, 859 4 052 42g 00% 25 I CLOVE PoolTwi-op FIwo (AtMgO1.3.E.3111) 1 52 I N 101 06 101 06 100% 101 1 CLIVE fPa lrýo= AItAngie Rg (I NOL3SX3 .9"2Ow 1 Es I A0 85 05 95 05 000% 25 CVE P5dFud Fo.L ATA.I, Ro*oQ 7(L3 53E 1 A A01 "0 01 24 04 24 0 CLIVE Pea Ts C re LUser (Nsro Tvsdr retoo 7s I I Cot 266.,M 5 202 70.,72 1.03532 0% 0 0.0000' PEOTorECo`trlserwaOut 0* C V1l Onsal I E, I Cost 21.143 15309 21.143 153.0 0% 0 ( LEAVE PtuE v*en*I lIaS Ftowl 1 0. 3 A) 32 Is5 dO 145 0% es 5 CLUE Rez=.o PoO*WOw 1 0 .730 Water 824 62 10 103904 1.7372 0% VR TheroIwMs(G rhpbCe) I E3 I Carbt 1400 ?.241 140 2,.147 1540 00% 2.247 1 CLOVE Ioasrl"ACorbsrl urmrrus 1 05 I A 1750 145 40 142 42 100% 142 t CLIVE Shell2ILVM5E212108r0 Es A 1142 963 08' 05W &01 000 8093 CE CLIVE eoarTou80sofr o(.oxl 0 0' 275 CArltu 0400 140 10 25 228 0m 25 CLIVE El.ArTube Leao T" 32^ Led 10o00 700 10 2.134 33 10010 2320 0 .JUVE h 1 0 ( 0 0 00% 21 CLIVE
."'T"'. S"luo= I Es0 1 MoIt SmSrctiICsuRoos(ECO I Ba E. 1 2 Mo4 21 IT=00% 21 0 CLIVE COoRod RmD_ heCr.onne3 Rod Ea " A 175 21 01 42 02 100 42 G CLIVE Cesdsol Rw EslsrosoTodo EsA 9 A] 22 00 04 29 1 3000%s 29 ICULVE C., o~~d C-CoO"Rod owun ute(Etx02s Im"
~Asrssrty Isolo 12-s) 0 I
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E a 9
3 Moot AJ 22 80 3
2 72 00 00 7
2 4 1005 o: 000%
00 T7 2 CLIVE o CLOVE W."5-lNWol I E"
- 70* I A 22 01 0 1000o% 09 CLIVE EsorrmPorI 5 shws3 (oU .- 1O) 1 E CS 21 827 402 027 408 100% 227 4: CLIVE GryHo.'e I E.' A 27s0 39 02 392 2 100% 30 ECLIVE VaMc TUT.13116 wt) 1 Es I N 72 13 12 130 1E8E 100D0 I0 I0 COIVE Vernal Tubt Lead 03t .tDub BUD.om I Ea I L8tt 703 921 1 1 04 14.00% So1 I CLIVE L.roeCsqo-el 10l=asaoaou700 . .Olir.9K)s I Es I A 42 81 200 21 200 000M 8I 3£ CLOVE TOpoPll. (527) I Ea I At 175 24 011 24 01 100% 24 0 CUVE 2ontmGnd PXe (3W0w) E3 I Al 105 32 02 29 02 10% 29 C CLIVE I Gs.rtotdeTr 0 Esub, 4 00 0 20 04 so 28 00% 02 CLIVE Iorul-tot Ch*t erm I Es 2 M?% Be 10 03a 0 07 000 I 40 0(CIVE COJV Cywd,,ai
, nu*oO W5 OAOOV1lCsdO) 31" I ED I A 0 4 14 1004 14.4 100% lO4 12 CLIVE C-CeOiAdtsal rssd s&sKomeAr.e(je 2IM)lO A AI I Al 00 2 07 2 07 a00% 2 I CIVE Cort $Wooo'T-Oso I Es 4 A 37 31 0.9 020 34 000% 125 1 COIE Sopb %do. l04101isaJ'oel I-Boos13 1 E. 2 CS 101 279 32 750 75 100% 750 0 CLIVE 9upwonD'0I'Zch Ah0t"et.*s I Esa 2 CS ;0 ,4 00 '2 23 ;129 100% CLIVE Sun0 Sanga 1 10-1rs Scot I-5el-Beams E 2 CS 02 70 0 I 240 24 000% 140 0 CLOVE exortoooordgt 3146CROCWSM~owstoPlate I Es I Au 70 57 0.3 57 03 10011, 07 C CLIVE
!ooooorlg I ad Plate I I Eu 2 CS 491 75 02 149 03 10o% 149 C CLIVE 3S0= Bri"g:eTleadPL I sEa 2 CS 420 37 01 70 02 000% 75 OCLIVE Rso0AOe~.5,_C=rrctoosr 0u2 Odý 1401s00)1 Es I Mot 233 22W 150 1.314 15? 1Tom 0.314 2£ CLOVE-l,. 2 CS I3?7 o*o 2 Ltad 240 Parse 2 1 P*smhn 507 -£B "
sm."'S f F."Oýs2(020t0c 2 "E 72 CR* 202 1,313 9a 94AI0 60B.7 0% 0 - UJORL Ssld BlIac.kIsd w tr sl(4s20rs 20 2 . 2 CRY 242 1,313 93 2,062 100 01 0 B UODFIL dzel slQa0s
- 149hsL 4EVc 200.'s 1) 2 Es 1? C 20 002 40 7.877 00 0 0 01 UD0FIL 0 BusC'80"9 44e glih(012a,320? 2 Es PO LD:
tolSlobs 0.004 Wlses049750020)2 2 Es 0 300.
SIAsdSloedrsoooul 1.oiSeO5sflfO) 2 Ea, 0 CJD L020 Vleden (If. iEs*s 2 E I Wso 3 GA M 511 2824304 CLOVE MuonblsEqwo PTray 2 E 0 A] 0 57 2 57870 2 57 57e0% 5O0 SCLVE TroyEed 5SK-d 2 Eu 2 M 0C3 11 2315 22315 46 100%. 7.315 CLIVE Mic Lem!O bki. 2 Ea 4 Load 700 20 0037 I05 0501 0 0 £ VIR Molt 24 2i2 311/ 1012 80u0 000% 0,502 80 CONE I0 MIx 223 40 193 42 1007% 4E CLIVE0 Moo" 0 0G 7 02 02 CLOVE 27 03 27 02 0 00%
000% 27 00 CLIVE Moat 10 03 10 02 03 CLOVE e3 0 B0 20 2.0 CLOVE 10 02 10 03 00o% 03 CLIVE SiennAaaooa -1 Load 20 07 3s 131 0£ VR 0%
Lead o I a0 6 00 o0 000%
o% Or LEAVE Load 202 04 202 04 272 00 CLOVE Moo 20 01.3 a0 03 00 02 CLOVE Lead .42 01 47 02 00 l0 0 CLOVE 09.+m*h+*
000 gaeps 000,0 O5Afaiet, Moot 03 11 00 CLIVE tuts.311u1*on -abrle l 23J 03 00 10001 01 d mchz-N t .1.) 01 02 CLOVE Mix 7 02 7 02 000% (320£ 02 Mix 7 02 7 CLOVE MIt 183 48 023 100% s0 42 CONE Moo 7 03 14 0? CLOVE Mi so 05 so I0005 0s ClOVE 04 20 Lem 04 262 00 100% 202 20 04 CLIVE 315 000% 0a CLOVE 00 00%
i00 00 100 00% 10 00 CLIVE U U1@91§00 00 0 10 r7 08%
00% 40 CLIVE 02 03 M00% 7 In CLIVE 02 Load 10 03 1t00 01 0% 0£ 010 375 02 00 CLOVE 23 02 CLVE 2- OruW (12 -
IO.. n ct00 . 305 0.1 04 305 2" 04 090 a0 VR Uo~ed 07
- f - 1 c-l (140 y0b0 a m1 27 07 87 07 6?0 8' Le=I 0.540 22 0.540 22 100005 0% 00 VR CaolntesSof Lead Brick CA"i 20 02 20 100% I00 Has055 SlAcans "trig Lead 20 Lema 4.79 02 1.790 Be 100% 00. VR 5.26 272 0.8 208 05 100% O0 CLIVE 00 0 M2ued 0 00 I 100% aCE CLOVE 1mu2 7 02 7 03 02 CLOVE Os O 08 2o 00 0£ CLIVE 0
Mo*a 0 0 0 0£ CLIVE Chen.-lil Ziled 0.22 1l 1.r33 2220 0£E 0100130.
H*Exhaqr 8.,Idnlg 22120 2020 5.129 021 fi.10 H-:,4E.dI5n5 11m, 21 CLIVE 3N4 07 334 70 ;00% CLIVE M~ed 150 20 150 3341 8£ SOI CLOVE meatEnhjqc, "* Ai,ýiium 08 100%
241 00 241 CLOVE Page 102 of 103
Decommissioning Cost Estimate for the CS-HP-PR-006 Aerotest Radiography and Research Reactor Revision 1 Table A-14 MISCELLANEOUS ITFM VOLUME ESTIMATES ARRR, San Rmon CalJfomia HWA4U11 MAIUAWI P'LI4.L J41 C.LJVL 1JVL 2F.,RIPTI("CN ICC 3F O F ( W BULK L2ItT UNIT TOTTAI. TOTAL. DIF-CT DI.50e3AI 31.SF30, COOD No UI*TJ5 UN5ITSCCI"SSIJCT DENS3ITY WEIGHT VOLU.IME WVeIHT VOLLME BU1RY VCEh-IT VO9UME 0 I2P21 l,
_IIbA3 l (11) 1 i l '3 1 fib3
) I0 ) a!ol ! I ) f 1, p "]
W. a1)upolsu1 12nuuit 3 Lu.ou I3 UU1 2I2 1U%
7ul 533 21)1 (ViE, 0 fumfhirah r .13 , I Mi.e" 3ml $-A1I 3n0 1541 11111% 331 414I CJJVF D- nalirn 3 F., I FRP&0Re, A4 33 334 33 111% 1rA 32 (+/-.V1 3s,lnLIlan2.d. uh 3 Eu I FRV&N 1 1 154 3.3 114 33 13U% 14 3- CU.Y Oem. NPlp 3 C. 1 Mied 1D 153 0 I1 100% GD I5 CLIVE D0,FiEM. 3a ., air1eys 1 1129
.3 1. 03 1n3% 3 02 (Q.1 f
Ar,S-.q 3 Eu I MLtH 3D0 30 30 10 103n. 30 1G C.vE OnDrrnLead Stchldig 3 La 74 Lni. 14 11.10 1.110 2.3 3% U o3 VR
.ittFpinn5Sppo-r't1t 2 0. 1 M,8 233 10 211nn 01 n3% 230 :03 CI.uVr L.,r e OeMn Ll inr rMt*e , 3 F., I AI .32 21I 243 1n3%
i1) ,12 24.. 0,tvr FloumvwnlL~hI-o F"dz'IFurCh M.J111T-r* 3 E. 12 M51.3l1 33 01US 4U VI 13U3% 41 Cl 013Uvk) rioresejmUgT*lrf(jilbm) 3 E'. 24 lass&MeMaI 10 010 24 24 103% 24 24 CIUVE RPnnr hCdn G-AerC3le.-qrmWure 3 f 31fi) 3a0U,.ONO 3610 13n3% I.33) 31f. 0A13F 1VZ ,,-pJ nr'Cytnnlel I F.; 1 (3.3, re, A.912 6576 1.15112 76I H11% r0612 £7 (',CIVE8 Wý " .3).urn)
S10 Pun1) 4 E5 I 33 III13 0 83 I 1005 50 151 Cl2E WaI 3,urrpll Wit*l It 4 Ln. OIlc'imd 2.100 300 2.0u 100 I0U% 2,1510 19U L0,WL W '"6;_lrpMi=.lv3AnFlpmpp* 4 E0 I Mn-.d 313111 0 333o 00 rInn% 3110 Inc 00A0F LwgeWase.Tah 4 En I 253 1053
-Kn/Jri~/t~k~ Oar% U.85 3003 CUIVS Irn -ALr1W"'. 4 Eu 1 CS 025 154 030% 15J28 154 131VI)
C~oCnITTwnrMIdey) 4 Ca I 51e)11) =1.750 2640 100% 1.750 204G COUV C.oohnnTcver'PoM 4 01) 3 51.13 333 610 130 s 0 1335$ 130 30 (A31F 51p1)I.COUuIIwj Tuý' 4 E 1 MI LnI 5.t1)3 w1e5 5.111 W3*36 1UU% 5.I111 035 (01[3V
- DarMLargeUeln1Urd: 4 Ca 2I 3AM55 33U 24.5 06 4'1.1 333% T150 41 IUV FTITAsippn0.;T,414 4 Sa 4 tei C-n 17 3322 15a 3 n% 1.3,52 210 CANS TOTALS: 607.414 7.90 84A.8 3 .0DM6 Page 103 of 103