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{{#Wiki_filter:}} | {{#Wiki_filter:Deconunissioning Cost Estimate for the Ward Center for Nuclear Studies at Cornell University Facilities Inventory Bldg. No. 2061 Rev July 2003 Prepared by: | ||
Duratek, Inc Prepared for: Commercial Operations Cornell University 1009 Commerce Park Drive, Suite 100 Oak Ridge, TN 37830 | |||
Decommissioning Cost Estimate Cornell University DECOMMISSIONING COST ESTIMATE for the Ward Center for Nuclear Studies at Cornell University Facilities Inventory Bldg. No. 2061 Rev 1 July 2003 Prepared By: a Paul Ely Senior Radiological Engineer Reviewed By: a T~ | |||
Doug ult, CHP Date Project Manager Approved B 463 Robin Shult v Date General Manager Commercial Operations Prepared By: | |||
Duratek, Inc. | |||
1009 Commerce Park Drive, Suite 100 Oak Ridge, TN 37830 r, (0F V | |||
Decommissioning Cost Estimate Cornell University PROPRIETARY STATEMENT This document is the property of the Cornell University and furnished with the understanding that the information herein will be held in confidence and will not be duplicated, used or disclosed either in whole or part without the written permission of Cornell University. | |||
Rev 1 Page i | |||
Decommissioning Cost Estimate Cornell University EXECUTIVE | |||
==SUMMARY== | |||
Duratek, Inc (Duratek) performed an independent cost estimate for decommissioning the Ward Center located in Ithaca, New York. This estimate was prepared at the request of the Cornell University. | |||
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 and the removal of these released buildings. The estimated decommissioning cost is $3,603,086 in terms of 2003 dollars. This estimate does not include the costs associated with fuel removal and transport from Ward Center to the Department of Energy (DOE). This estimate is for budgetary purposes only and is not a proposal for Duratek 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 Envirocare of Utah. Activated materials will be sent to the Barnwell South Carolina disposal facility. | |||
Rev 1 Page ii | |||
Decommissioning Cost Estimate Cornell University TABLE OF CONTENTS | |||
==1.0 INTRODUCTION== | |||
...........................................................................................................1 1.1 Purpose .............................. 1 1.2 Scope .............................. 1 1.3 Assumptions and Bases ............................. 2 2.0 GENERAL FACILITY DESCRITION ..... 4...................... | |||
3.0 DECOMMISSIONING CRITERIA .. ........................... 11 3.1 Radionuclides of Interest .................................. 11 3.2 Radiological Criteria for License Termination .............. .................... 12 3.3 Reactor complex.................................................................................................. 14 3.4 Office and Laboratory Wing .................................. 16 3.5 Utilities and Auxiliary Services .................................. 17 3.6 TRIGA Reactor .................................. 18 3.7 Relation of Ward Center to Other TRIGA reactors ....................... ........... 18 3.8 Outside Areas .................................. 19 4.0 ESTIMATIONMETHODS .................... 21 4.1 Cost Modifying Factors .............................. 21 4.2 Radioactive Waste Volume Estimates .............................. 25 4.3 Radioactive Waste Disposal Costs .............................. 25 4.4 Remediation Methods .............................. 26 4.5 Radioactive Waste Volume Reduction Costs ......... ..................... 27 4.6 Unit Costs .............................. 28 4.7 Final Surveys .............................. 29 5.0 FACILITIES, RADIOLOGICAL CONDITIONS AND DECOMMISSIONING SCENARIO ......................... 29 5.1 Remediation Summary ........................ 29 5.2 License Termination Surveys ........................ 33 | |||
==6.0 REFERENCES== | |||
.......... ........ 34 Rev 1 Page iii | |||
Decommissioning Cost Estimate Cornell University LIST OF APPENDICES APPENDIX A- 1 Contaminated Waste Volume Summary .......................................... 1 APPENDIX A- 2 Contaminated Waste Disposal Cost .......................................... 2 APPENDIX A- 3 Waste Shipping Container Cost .......................................... 3 APPENDIX A- 4 Waste Disposal Labor Estimate .......................................... 4 APPENDIX A- 5 Contaminated Waste Disposal Summary .......................................... 5 APPENDIX A- 6 Building Survey Labor Summary ......................................... 6 APPENDIX A- 7 Outdoor Area Survey Labor Summary ............... ........................... 7 APPENDIX A- 8 Instrument Lease Charges .......................................... 8 APPENDIX A- 9 Equipment Lease Charges ......................................... 9 APPENDIX A- 10 Demolition Estimate ......................................... 10 APPENDIX A- 11 Decontamination Costs ......................................... 11 APPENDIX A- 12 Miscellaneous Item Inventory Estimate ......................................... 12 Rev 1 Page iv | |||
Decommissioning Cost Estimate Cornell University LIST OF FIGURES Figure 2-1 Map of the Area Surrounding Cornell University .......................................... 5 Figure 2-2 Cornell University Campus ...... 6........................ | |||
Figure 2-3 Cornell University Ward Center Site .......................................... 7 Figure 2-4 Ward Center Basement Plan View ......................................... 8 Figure 2-5 Ward Center 1st Floor Plan View .......................................... 9 Figure 2-6 Ward Center 2nd Floor Plan View ......................................... 10 Figure 3-1 Ward Reactor Core and Thermal Column ......................................... 20 Figure 5-1 Ward Center Activated Concrete ......................................... 31 LIST OF TABLES Table 3-1 List of Expected Radionuclides ........................................... 11 Table 3-2 Acceptable License Termination Screening Values of Common Radionuclides for Building Surface Contamination ........................................... 13 Table 4-1: Decommissioning Cost Summary - Ward Center ........................................... 21 Table 4-2: Personnel Protective Equipment Protection Summary ......................................... 22 Table 4-3: Hazardous and Toxic Waste Productivity Factors: Light Work ........................... 23 Table 4-4: Hazardous and Toxic Waste Productivity Factors: Heavy Work ......................... 24 Table 4-5: Ward Center Unprocessed Radioactive Waste Summary .................................... 25 Table 4-6: Decontamination Methodology Comparison .......................... ................. 27 Table 4-7: Volume Reduction Methodology Cost Information ........................................... 28 Table 4-8: Decommissioning Cost Estimate Selected Unit Cost Factors .............................. 28 Table 5-1: Ward Center Planned Remediation Activities ................................. .......... 30 Table 5-2: Typical Final Survey Instrumentation ............... ............................. 33 Rev 1 Page v | |||
Decommissioning Cost Estimate Cornell University | |||
==1.0 INTRODUCTION== | |||
1.1 Purpose The Commercial Operations division of Duratek, Inc (Duratek) has prepared this document for the purpose of providing a decommissioning cost estimate for Ward Center for Nuclear Studies TRIGA Reactor and Zero Power Reactor at Cornell University. The cost estimate includes those activities and associated cost factors required to terminate the Ward Center TRIGA Reactor Nuclear Regulatory Commission (NRC) License R-80, Doc. No.50-157 and Zero Power Reactor Facility License R-89, Doc. No.50-97 and release of the reactor portions of the Ward Center for "unrestricted use." A New York State licensed gamma irradiation facility located in Ward Center will be closed August 30, 2003. The facility will be decommissioned and the New York State (NYS) license amended accordingly. The term "unrestricted use" means that there will be no future NRC restrictions on the use of the site. | |||
The decommissioning is projected to start within the next year. The cost estimate provided by this report is in terms of 2003 dollars. This estimate is intended to be used for funding and budgetary purposes and does not constitute a proposal or cost estimate for Duratek to perform work. | |||
1.2 Scope The scope of this report is to present the estimated costs derived for decommissioning the Ward Center. The specific areas covered by this estimate include: | |||
* TRIGA Reactor | |||
* TRIGA Bioshield and Beam Ports | |||
* Reactor complex | |||
* Office and Laboratory Wing | |||
* Zero Power Reactor 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. 6-1). 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 10CFR Part 20 (Ref. 6-2). | |||
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-Rev Page 1 | |||
Decommissioning Cost Estimate Cornell University 1757, ConsolidatedNMSS Decommissioning Guidance, Decommissioning Processfor MaterialsLicenses, Appendix B, (Ref. 6-3). | |||
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 surveys were estimated based on the size of the various areas being decommissioned and their prior radiological history. | |||
The cost estimate for the Ward Center utilizes a combination of unit price estimates and task-based estimates to arrive at a total cost in 2003 dollars for decommissioning all areas. The unit cost methodology is modeled after the method used in the Means Building Construction Cost Data(Ref. 6-4). 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. 6-5). 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. | |||
1.3 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 Ward Center to the DOE prior to the start of decommissioning, costs for these activities are not included in this estimate. | |||
* The Ward Center will be decontaminated and free released. | |||
Rev Page 2 | |||
Decommissioning Cost Estimate Cornell University | |||
* The Gamma Irradiation Facility will be closed and decommissioned by Cornell. | |||
* Some of the uncontaminated laboratory equipment located throughout the facility has a high intrinsic value and may be moved to another facility prior to decommissioning. | |||
* The use of radioactive materials at the Ward Center has been well controlled and contaminated areas are 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. | |||
* Cornell will provide security for the site, power will be available, and the Cornell University staff and management will be on site during decommissioning. | |||
* Radioactive waste with low specific activity will be sent to Envirocare of Utah. It was assumed that concrete, protective clothing waste, and miscellaneous dry active waste would qualify for disposal at Envirocare of Utah. | |||
* Radioactive waste not suitable for disposal at Envirocare of Utah will be sent to the Barnwell, South Carolina disposal site. | |||
* The site remediation 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 2003 RS Means Building Construction Cost Data for Binghamton, New York. | |||
Rev Page 3 | |||
Decommissioning Cost Estimate Cornell University 2.0 GENERAL FACILITY DESCRIPTION The regional location of the Ward Center is shown in Figure 2-1; Figure 2-2 depicts the Ward Center site and adjacent Cornell structures; the Ward Center site is depicted on Figure 2-3. Figure 24, Figure 2-5 and Figure 2-6 presents plan views of the three floors of the Ward Center. | |||
The Ward Center TRIGA Reactor is similar to the Oregon State University TRIGA Reactor that was used as the basis for the decommissioning estimate reported in NUREG/CR- 1756, Technology Safety and Costs of DecommissioningReference Nuclear Research and Test Reactors, March 1982 (Ref. 6-5). A full description of the facility is provided in FinalSafeguards Report to the U.S. Atomic Energy Commissionfor the Cornell University TRIGA Reactor (Ref. 6-6) and Supplement No. I to the Final Safeguards Report to the U.S. Atomic Energy Commissionfor the Cornell University TRIGA Reactor (Ref. 6-7). | |||
The Cornell University stopped routine operation of the Ward Center TRIGA Reactor on June 30, 2002 and plans to submit a request for a possession only license in 2003. The TRIGA is currently operated for short periods of time at low power levels in order to maintain operator qualifications. The University previously ceased operation of the ZPR reactor on September 6, 1996. | |||
The spent fuel is the property of DOE and was leased to Ward Center. This lease requires DOE to take possession of the fuel when the University is done with it. | |||
Aluminum-clad and stainless steal-clad fuel that has been used at Ward Center, will be shipped to the National Engineering and Environmental Laboratory in Idaho Falls, Idaho. | |||
Rev Page 4 | |||
Decommissioning Cost Estimate Cornell University Figure 2-1 Map of the Area Surrounding Cornell University | |||
:ornell Rev Page 5 | |||
Decommissioning Cost Estimate Cornell University Figure 2-3 Cornell University Ward Center Site I | |||
N ollister Hall Kimball Hall rNL l | |||
I N | |||
I A 5 t-l4M Trolley Foot Bride p M | |||
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111S Ws Stone Arch Gm Bridge e lp ha 9(c L 6 ps OAK AVENUE | |||
, ^ | |||
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I N CVT Rev 1 Page 7 | |||
Decommissioning Cost Estimate Cornell University 3.0 DECOMIISSIONING CRITERIA A Duratek engineers visited the Ward Center Facility in Ithaca, New York in February of 2003 to gather physical and radiological data. Facility sketches, building sketches, and radiological characterization data for affected areas were obtained. | |||
3.1 Radionuclides of Interest The base line radioactive material quantities were obtained from the estimate provided in NUREG/CR-1756, (Ref. 6-5). There are additional radionuclides reported in the characterization survey report (Ref. 6-8) 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, 60Co 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 1,500 curies of neutron activation products at the time of shutdown. The radionuclides that potentially exist in the Ward Center along with estimated inventories are presented in Table 3-1. | |||
Table 3-1 List of Expected Radionuclides Nudide Half-Life Inventory 3 | |||
H 12. Not Available 14c 5,730 1.11 | |||
'VAr 269 2.53 x 10-3 41 Ca 103,000 4.6 x 10-4 45ca 0.446 0.23 46sc 0.233 2.34 x 10-2 51Cr 0.0759 251 | |||
'4Mn 0.86 22.7 | |||
"'Fe 2.73 118 | |||
'"Fe 0.1222 4.74 "Co 0.74 Not Available 5Co 0.194 133 60Co 5.27 567 59Ni 76,000 0.11 6aNi 100 12.6 "1Zn 0.67 67.2 90Sr 29.1 Not Available 93Z.b 13.6 2.34 x 10-5 94Nb 20,000 2.6 x 10-4 | |||
'Nb 0.0961 2.08 x 10-2 Rev Page I | |||
Decommissioning Cost Estimate Cornell University | |||
_~~~~~~ | |||
Nuclide HIalf-Life i Inventory (Yr) Ci 9"Tc 213,000 Not Available 124sb 0.16 Not Available t5Sb 2.76 Not Available inI 15,700,000 Not Available 134CS 2.7 Not Available 37Cs 30.17 Not Available 14Ce 0.78 Not Available 52Eu 13.48 Not Available 154E, .8 Not Available MEu 4.96 Not Available 21 Pb 22.26 Not Available | |||
=_Ra 1,600 Not Available 3 | |||
M Th 77,000 Not Available 233 4 a U >159,200 Not Available 14.4 Not Available The list ofexpected radionuclides provided above is based on the assumption that operations ofthe Ward Center has resulted in the neutron activation ofreactor 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. | |||
3.2 Radiological Criteria for License Termination The overall objective of the Ward Center decommissioning is to remediate the facilities to a condition that corresponds to a calculated dose to the public of less than 25 mrem/year from applicable pathways. The facilities may then be released for unrestricted use. This dose limit appears in 10 CFR 20.1402, Radiological CriteriaforUnrestrictedUse (Ref. 6-9). | |||
The Derived Concentration Guideline Level (DCGL) is defined in MARSSIM (Ref. 6-10) 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 Ward Center 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. 6-3).); (2) screening levels derived using D and D, Version 2.0 (Ref. 6-11), for the specific radionuclides(s) using the code's default parameters. The assumed DCGLs for Rev Page 12 | |||
Decommissioning Cost Estimate Cornell University Ward Center were based on the look-up tables in NUREG-1757, Appendix B (Ref. 6-3). | |||
The proposed DCGLs for surface contamination are based on the screening tables in NUREG-1757, Appendix B (Ref. 6-3). 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 | |||
* The fraction of removable surface contamination does not exceed 0.1. | |||
Table 3-2 Acceptable License Termination Screening Values of Common Radionuclides for Building Surface Contamination Radionuclide Symbol Acceptable screening levels' for Unrestricted release (dpmll00cm2 ) | |||
Hydrogen-3 (Tritium) 3H 1.2E+08 Carbon-14 It 3.7E+06 Sodium-22 22Na 9.5E+03 Sulfur-35 35s 1.3E+07 Chlorine-36 36Cl 5.OE+05 54 Manganese-54 Mn 3.2E+04 Iron-55 "Fe 4.5E+06 Cobalt-60 60Co 7.lE+03 Nickel-63 63Ni 1.8E+06 Strontium-90 90Sr 8.7E+03 Technetium-99 99Tc 1.3E+06 Iodine-129 12I 3.5E+04 Cesium-137 '3 7CS 2.8E+04 | |||
'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 1. | |||
Rev 1 Page 13 | |||
Decommissioning Cost Estimate Cornell University Units are disintegrations per minute per 100 square centimeters (dpmf100 cm2 ). I dpm is equivalent to 0.0167 becquerel (Bq). The screening values represent surface concentrations of individual radionuclides that would be deemed in compliance with the 0.25 mSv/yr (25 mremyr) 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. | |||
3.3 Reactor complex The property, on which is situated the Cornell University Ward Center, was designated for construction in 1959. The Ward Center was constructed between 1959 and 1962. | |||
The structure does not have a history of spills or other contamination and it is anticipated that, at the time of decommissioning, remediation will be minimal. It is assumed that some of the ventilation system components and some miscellaneous equipment will be disposed as radioactive waste. | |||
Decommissioning of the structure will follow decommissioning of the reactor and reactor equipment. The structure will then be surveyed using a license termination type survey with any additional structural decontamination performed in conjunction with the surveys. | |||
The land area is not well defined, as there are no boundaries between the Ward Center and the nearby engineering buildings. Structurally and functionally the building consists of two main sections, the reactor complex, a relatively airtight reinforced concrete structure faced with brick veneer and an office and laboratory wing of reinforced concrete columns and beams faced with native stone. | |||
The reactor complex is 63 feet by 70 feet in plan and 45 feet in height. This portion of the building, containing approximately 5,500 square feet of floor space, houses the two reactors and their control rooms, associated experimental and service areas, and the gamma irradiation cell. The office and laboratory wing, which is U-shaped, consists of east and west sections approximately 26 feet wide and a north section approximately 33 feet wide. The total length of the U is approximately 176 feet, thus providing approximately 10,000 square feet of floor area. This wing of the facility houses, in a basement and two stories, a counting room, laboratories, offices, a classroom, and building utility rooms. | |||
The principal function of the reactor complex is to house the two reactors and their associated operational and experimental areas. The gamma irradiation facility is also located in the bay in the northeast comer; it is, however, functionally part of the office and laboratory wing. (The only access to the gamma cell from the reactor complex is through a 4 ft by 4 ft opening in the cell roof to permit heavy objects to be moved in and out by an overhead crane; normally the opening is kept closed by a removable concrete plug.) | |||
Rev 1 Page 14 | |||
Decommissioning Cost Estimate Cornell University The TRIGA reactor structure is approximately centered in the reactor complex and rises 25 ft above the basement floor level. The Zero Power Reactor is housed immediately north of the TRIGA in a self-contained, two-story high concrete cell. | |||
The south wall of the ZPR cell serves also as the north wall of the TRIGA pool. | |||
The remaining volume of the reactor complex is divided into rooms and working floor space on three levels: basement, first floor, and second floor. There are two stairways connecting the three levels. A pendant-operated 5-ton bridge crane mounted on rails running along the north and south walls, traverses the entire area of the bay. The crane can service both reactors and the gamma cell. | |||
The reactor complex is a reinforced concrete structure. The interior surface of the concrete is coated with a vapor barrier and painted to provide a smooth surface capable of being readily decontaminated. Personnel access to the reactor complex section may be gained from the office and laboratory wing through only three doors, one at each floor level. A large door on the west wall at the basement level provides truck access to the bay for loading and unloading freight. Since the grade is a relatively steep slope from the north to the south, the basement of the entire building is underground at the front (north) end and above grade in the rear, permitting truck unloading at the basement level of the reactor complex. | |||
The roof of the reactor complex is flat and consists of pre-stressed concrete beams, concrete roof slabs, 1-in. rigid vapor barrier insulation, and built-up roofing. All floors in the bay are protected with a Phenoline coating (except for the observation room, the second floor laboratory room, and the two control rooms, where asphalt tile is used). | |||
3.3.1 Basement Plan The ZPR cell and the TRIGA pool occupy the central portion of the basement, running on the north-south axis of the building. All other facilities in the basement are on either side of these two centrally located reactor structures. The northeast corner of the basement contains the gamma irradiation cell. Immediately west of the ZPR pit is a corridor permitting personnel access from the office and laboratory wing to the reactor complex. The isotope-and-fuel storage room occupies the northwest corner of the basement and immediately south of it is the reactor equipment room. The remaining basement floor area is available for experimental setups, in particular those utilizing neutron beams from the TRIGA. | |||
3.3.2 First Floor Plan Continuations of the ZPR cell and TRIGA pool occupy the north central portion of the first floor of the reactor complex. At the northeast corner is the roof of the gamma irradiation cell. At the northwest comer is the ZPR control room, which is connected by a labyrinth to the ZPR cell. The cell Rev 1 Page 15 | |||
Decommissioning Cost Estimate Cornell University broadens out at this level to include a grid-plate-and- fuel storage area. A removable grating in the ZPR cell floor affords access to the basement area of the cell. Access to the ZPR control room is either from a stairway platform in the main reactor area or from the ZPR laboratory in the west section of the office and laboratory wing. At the nose of the TRIGA and slightly below the first floor level is the top surface of the TRIGA thermal column shielding; this surface forms a working area around the vertical access to the thermal column. | |||
3.3.3 Second Floor Plan Access to the second floor of the reactor complex is afforded by stairways inside the bay and by a door into the north section of the office and laboratory wing. The second floor includes a balcony, or catwalk, around most of the perimeter of the bay. The TRIGA control room is situated on this floor, and immediately adjacent to it is the observation room, which permits viewing reactor operations without interfering with the operators. | |||
A laboratory room is located at the northwest corner adjacent to the observation room. Also at this level are the isotope handling room and a platform and working area surrounding the top of the TRIGA pool. | |||
3.4 Office and Laboratory Wing 3.4.1 General The U-shaped office and laboratory wing houses a classroom, offices, utility rooms, and a number of laboratory rooms. In addition, the main personnel entrance to the entire Laboratory is at the front (north) of the building at the first floor level of this wing. Two emergency exits are located at the basement level of this wing, one at the southeast and one at the southwest corner; the latter is also a delivery entrance. | |||
The east and west sections of the office and laboratory wing consist of a basement and one story. The north section has in addition a setback second story. A centrally located enclosed stairwell and an adjacent elevator interconnect the three floors. | |||
For radiation safety purposes, all parts of the building except the classroom and first floor offices and service rooms are off-limits to unescorted visitors. The principal control point for entrance to the restricted area of the building is the stairwell door opposite the lobby (The other three entrances--elevator, ZPR laboratory door, and rear delivery door-- may be opened only with keys that will be issued only to authorized personnel). | |||
Rev Page 16 | |||
Decommissioning Cost Estimate Cornell University 3.4.2 Gamma Irradiation Cell The gamma irradiation cell and associated setup room and cold work area form a block of three rooms at the basement level. Although the cell proper and the set-up room are physically located within the reactor complex to permit utilization of the 5-ton crane for loading and unloading materials in the cell, functionally they are part of the laboratory wing. | |||
3.4.3 Basement Plan The basement level of the office and laboratory wing houses (in addition to the cold work area) a corridor, a chemistry laboratory, a machine shop, two rooms for introductory laboratory courses, a darkroom, a counting room, a men's toilet, a general laboratory room, and the electrical and mechanical utility rooms. All of these rooms open off the corridor, which may also be used to reach an entrance to the reactor complex. Two subterranean rooms are attached to the west wall of the basement: one is the transformer vault, accessible only from a stairway outside the building, and the other is the waste storage tank room, which opens off the general laboratory room. | |||
The chemistry laboratory includes two hoods with suitable filters for work with low-level radioactive chemicals in addition to standard chemical laboratory equipment and utilities. | |||
3.4.4 First Floor Plan The first floor level of the office and laboratory wing consists of the lobby, a classroom, an office for the Reactor Supervisor and a secretary-receptionist, three faculty laboratory-offices, a faculty office, an office for the University Health Physicist and the University Radiation Safety Officer, an electronics maintenance room, the ZPR laboratory, a pantry, storage rooms, and toilet rooms. The stairwell and elevator are directly across the corridor from the lobby. | |||
The ZPR laboratory also opens into the ZPR control room in the reactor complex. | |||
3.4.5 Second Floor Plan On the second floor are six laboratory-office rooms opening off a corridor that also leads to a door into the reactor complex. | |||
3.5 Utilities and Auxiliary Services Conventional utility services normal to the operations of a laboratory of this nature are provided, together with the auxiliary services required for the reactors Rev Page 17 | |||
Decommissioning Cost Estimate Cornell University and the gamma irradiation facility. Compressed air, combustion gas, water, and electricity are supplied to all laboratory rooms including those that have been designed for dual use as laboratory-offices. The compressor for the air is located in the mechanical utility room. Necessary outlets for standard laboratory services are provided in the experimental areas of the reactor complex. The water system includes water purification equipment for the reactor cores as well as equipment for temporary storage of contaminated water. | |||
3.6 TRIGA Reactor The Ward Center reactor is a 500-kilowatt TRIGA Mark II reactor. The reactor and reflector assembly are located at the bottom of a plastic coated concrete tank 25 feet deep. Approximately 20 feet of water above the core provides vertical shielding. The core is shielded radially by a minimum of 6 feet of ilmenite concrete (235 b/ft3), 1.5 feet of water and 1.0 feet of graphite reflector. | |||
There are several experimental and irradiation facilities associated with the TRIGA reactor. A graphite thermal column approximately 4 feet by 4 feet by 8 feet extends for the outer face of the reflector assembly into the concrete shield structure. A track-mounted heavy concrete door provides horizontal access and shielding for the thermal column. There are two nesting coaxial removable plugs or square cross section in the center of the thermal-column door. Vertical access to the thermal column is also provided. Inside the thermal column near the inner end are a 32-inch by 32-inch by 36-inch hohlraum block and a 24-inch by 24-inch by 28-inch removable graphite block. The pool, which is approximately 11 feet by 12 feet in cross section, permits access to the flattened face of the reflector. | |||
Seven beam ports are provided for beam experiments and for the insertion of specimens for irradiation: two 3-inch thermal beam ports, four 6-inch radial beam ports, and one 4-inch throughport. The centerlines of all beam ports are located in the same horizontal plane approximately 2-feet 10-inches above the pool and room floors, which are at the same elevation. | |||
3.7 Relation of Ward Center to Other TRIGA reactors The design of the Ward Center 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, draining 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. | |||
Rev Page 18 | |||
Decommissioning Cost Estimate Cornell University 3.8 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 natural surface drainage around the Ward Center site from roof drainage and storm run-off is routed to Cascadilla Creek by utilizing natural drainage and storm sewers. | |||
The sanitary sewer and nearby storm sewers will be surveyed at locations just upstream and downstream locations relative to the Ward Center. In addition soil sampling, and license termination surveys of paved areas and unpaved areas will be performed in areas adjacent to the Ward Center in accordance with current regulatory requirements. | |||
Rev Page 19 | |||
Decommissioning Cost Estimate Cornell University Figure 3-1 Ward Reactor Core and Thermal Column Rev Page 20 | |||
Decommissioning Cost Estimate Cornell University 4.0 ESTIMATION METHODS The estimated cost to decommission the Ward Center is $3,603,086. This section of the cost estimate report provides an overview of the considerations and factors that influenced the decommissioning cost estimate. Table 4-1 provides a summary of the costs associated with each area of the facility. | |||
Table 4-1: Decommissioning Cost Summary - Ward Center Operation Man- Labor Plus Equipment, Radwaste Total Cost hours Trav. & Liv. Contracts & Shipping & | |||
I Supplies Disposal TRIGA Reactor 746 $54,191 $27,775 $212,973 $294,939 TRIGA Bioshield & 5338 $424,827 $273,787 $741,581 $1,440,196 Reactor Bay 2374 $189,406 $52,730 $244,492 $486,628 Wing aoay 926 $74,416 $16,941 $11,028 $102,384 Zero Power Reactor 128 $10,272 $2,338 $1,518 $14,128 Characterization 1040 $90,220 $4,274 $0 $94,494 Surveys _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ | |||
Final Surveys 4160 $360,880 $17,097 $0 $377,977 Planning, Training, 272 $21,370 $0 $0 $21,370 | |||
& Mobilization __ _ _ __ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ | |||
Owner Oversight & 693 $50,353 $0 $0 $50,353 Licensing 15676 I $1,275,934 $394,943 $12159______ | |||
Totals 15676 $1,275,934 $394,943 $1,211,592 $2,882,469 25% CONTINGENCY $720,617 I GRAND TOTAL $3,603,086 4.1 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 Rev Page 21 | |||
Decommissioning Cost Estimate Cornell University personnel protection described in Table 4-2. The Productivity Factors related to these levels of personnel protection are provided in Table 4-3 for Light Work and in Table 4-4 for Heavy Work. | |||
Table 4-2: Personnel Protective Equipment Protection Summary Level A: The highest available level of respiratory, skin, and eye protection Level B: The highest level of respiratory protection, but less skin protection than Level A. Level B is the minimum level recommended for initial site entries, or for other entry conditions dealing with unknown hazards. | |||
Level C: The same level of skin protection as Level B, but a lower level of respiratory protection. | |||
Level D Modified: Skin protection similar to or the same as Level C, without respiratory protection. | |||
Level D: Standard work uniform suitable for construction work: no respiratory protection and minimal skin protection. | |||
Rev 1 Page 22 | |||
I ( Decommissioning Cost Estimate | |||
( | |||
Cornell University Table 4-3: Hazardous and Toxic Waste Productivity Factors: Light Work Level A Level B Level C Level D Modified Level D Variables U/M 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.Deritylosses Min. 78 69 60 74 69 64 55 51 44 4 4 3 5 5 5 D.Totaltimelostper-hr.WD Min. 298 319 340 257 274 290 218 242 273 110 127 142 67 70 81 E.Productivitytimeper8-hr.WD Min. 182 161 140 223 206 191 262 238 207 370 353 338 413 410 399 F. Productivity time on clan site Min. 430 430 430 430 430 430 430 430 430 430 430 430 430 43 4 30 G. HTW Productivity Factor 0.42 037 033 0.52 0.44 0.6186 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/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. | |||
Rev 1 Page 23 | |||
I Decommissioning Cost Estimate Cornell University Table 4-4: Hazardous and Toxic Waste Productivity Factors: Heavy Work Level A Level B Level C Level D Modified Level D Variables U/M T<70 70<T T>85 T<70 70<T T>85 T<70 70<T T>85 T<70 70<T T>S5 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 G. HTW Productivity Factor 0.28 0.22 0.15 0.40 036 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 = 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/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. | |||
Rev 1 Page 24 | |||
Decommissioning Cost Estimate Cornell University 4.2 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 Ward Center decommissioning, the cost for radioactive waste processing, shipping, and disposal is anticipated to be about 40% of the total decommissioning cost. This is a normal fraction for radioactive facilities. | |||
Radioactive waste volume estimates are discussed in the following section. Table 4-5 provides a volume summary for each area of the Ward Center. Information about most waste items are provided in Appendix A-12. | |||
Table 4-5: Ward Center Unprocessed Radioactive Waste Summary Direct Generated Decon Direct Barnwell Envirocare Envirocare Envirocare Total Disposal Disposal Disposal Disposal Disposal Volume Volume Volume Volume Volume Area Description (ftA3) (ftA3) (f J (ftA3) (ftA3) | |||
TRIGA Reactor 120 4 0 25 149 TRIGA Bioshield & 24 29 0 3,294 Beam ports 3,347 Reactor bay 0 12 0 1,146 1,158 Office & Laboratory 0 31 21 0 Wing 52 Zero Power Reactor 0 4 1 2 7 TOTALS 144 [ 80 22 4,467 [ 4,714 43 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 at Duratek followed by disposal at Envirocare of Utah and direct radioactive waste disposal at Envirocare of Utah and Barnwell, South Carolina. The following sections describe the pricing for each facility. | |||
4.3.1 Envirocare of Utah Disposal Costs The costs to transport waste to the Envirocare of Utah disposal site are based on a transport distance of 2,180 miles, at a rate of $2.36 per mile. | |||
The cost to dispose of the waste at the Envirocare of Utah site are based on a disposal fee of $189.91 per cubic foot. | |||
Rev Page 25 | |||
Decommissioning Cost Estimate Cornell University 4.3.2 Barnwell South Carolina Disposal Costs The costs to transport waste to the Barnwell South Carolina disposal site are based on a transport distance of 897 miles, at a rate of $2.36 per mile. | |||
The cost to dispose of the waste at the Barnwell site is based on an average disposal fee of $1,680 per cubic foot for radioactive hardware. | |||
4.3.3 Duratek Processing/Burial Costs The cost to transport waste to the Duratek central volume reduction facility in Oak Ridge Tennessee are based on a transport distance of 762 miles at a rate of $2.36 per mile. Waste processing at the Duratek central volume reduction facility was not included in this estimate because there was not a significant cost advantage to waste processing. | |||
Typical unit disposal cost factors are listed in Appendix A-3. | |||
4.4 Remediation Methods The goal in choosing remediation methods is to select the minimum cost option to accomplish a task There are many factors which need to be considered when selecting a method such as contamination levels, degree of penetration of contamination into substrate material, equipment cost, support equipment costs, material and chemical costs, the generation of secondary waste volumes (waste in addition to the removed contaminated material), processing rates, labor requirements, and applicability to various tasks. Typical decontamination processes are summarized in Table 4-6. For each decontamination method, this table shows application information, the process cost per square foot of area decontaminated, and the amount of secondary waste generated. These unit factors are applied to specific areas or equipment requiring remediation to determine the most cost-effective process. | |||
Rev Page 26 | |||
Decommissioning Cost Estimate Cornell University Table 4-6: Decontamination Methodology Comparison Penetration I Process Secondary depth Crew Cost Waste Volume Methodology Application (in) Size ($/ft (ft'/l 000 ft.) | |||
McDonald U-5 Scabbler Floor concrete 1/4 2.0 $0.98 0 McDonald U-5 Scabbler Floor concrete 1/2 2.0 $1.86 0 McDonald 3WCD Scabbler Wall concrete 1/8 2.0 34.45 0 Blastrac IOD Shot Blaster Floor concrete 1/16 1.1 S0.43 0.53 Blastrac OD Shot Blaster Floor concrete 1/8 1.1 $0.54 0.53 LTC 10-6OPn Special All surfaces 1/32 1.3 $1.71 0.53 Vacuum Blaster LTC 10-6OPn Special Al surfaces 1/16 1.3 33.08 0.53 Vacuum Blaster EDCO CPU-OC Floor Plane Floor concrete 1/2 2.0 $1.62 0 C02 Blasting All Surfaces 0 2.0 34.52 0 Hydrolaser (5-10,000 psi) All Surfaces 0 2.0 30.91 9.07 Hands-On-Decon Non-Porous surfaces 0 1.0 32.01 8.33 4.5 Radioactive Waste Volume Reduction Costs The volume reduction processes analyzed for use are summarized in Table 4-7. | |||
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. | |||
Rev 1 Page 27 | |||
Decommissioning Cost Estimate Cornell University Table 4-7: Volume Reduction Methodology Cost Information VR Methodology l | |||
Applicability I Transport Container Type [ Total VR Cost (Sb) | |||
Super Compaction Dry active waste B-25 for Envirocare S5.59 20 lb/ft Disposal Incidental Lead Decontamination Bricks and Sheet Custom Box $7.25 Survey & Release Low Density Waste 55 Gal Drum $1.45 Low Density Drums Survey & Release Waste at greater than B-25 Box S0.66 Medium Density Boxes 20 7< 60 lb/ft 3 Survey &Release Waste at greater than B-25 Box $0.52 High Density Boxes 60 b/tV 4.6 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 4-8: Decommissioning Cost Estimate Selected Unit Cost Factors Unit Cost Factor Unit Cost Rate Units Radioactive Soil and Rubble Disposal at Envirocare of Utah $189.81 cubic foot Waste Transportation to Envirocare of Utah $2.36 mile Transportation Distance to Envirocare of Utah 2,180 miles B-25 Waste Disposal Container Cost $843.75 each Management and Supervision $116.50 hour Engineer $97.08 hour Radiation Protection Supervisor $101.94 hour Laborer Foreman $44.54 hour Administrative Assistant $42.00 hour Instrument Technician $66.00 hour Radiation Protection Technician $66.00 hour Laborer $40.95 hour Fee 20% | |||
Rev 1 Page 28 | |||
Decommissioning Cost Estimate Cornell University 4.7 Final Surveys Final survey costs are estimated based on the facility radiation survey information presented in NUREG- 1757, MNSS DecommissioningStandardReview Plan (Ref. | |||
6-11). The number of sample points for the various areas being surveyed and the type of survey being performed were determined. The time to perform each of these surveys is estimated, and the product of these two items is the labor time to perform the surveys. Equipment and material cost to perform the surveys is added along with staff support costs to determine a total cost. The survey requirements are based on NUREG-1575, Multi-Agency RadiationSurvey and Site InvestigationManual (MARSSIM) Ref. 6-10). 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. | |||
5.0 FACILITIES, RADIOLOGICAL CONDITIONS AND DECOMMISSIONING SCENARIO Decommissioning of the Ward Center requires that residual radioactive materials be removed from the site to allow removal of the decommissioned facilities from the NRC license. For the purposes of this cost estimate, the end of the decommissioning project occurs when the Ward Center has been remediated to release limits, the Final Status Survey has been performed, documented and submitted to the NRC. | |||
5.1 Remediation Summary Remediation will be required for the Ward Center, 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. | |||
Rev 1 Page 29 | |||
Decommissioning Cost Estimate Cornell University Table 5-1: Ward Center 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. | |||
TRIGA Reactor Empty water from reactor tank. Remove activated reactor core and vessel internals and reactor vessel. Cut out activated concrete (5-ft thick layer) from bioshield monolith surrounding reactor tank and disposal as radioactive waste. | |||
Beam Tubes Remove activated beam tubes including shields. Cut out a 1-foot thickness of activated concrete surrounding beam tubes. | |||
First and Second Floors Remove contaminated portions of HEPA and HVAC systems. Remove demineralizer system and heat exchanger. Remove contaminated portions of the rabbit system and fume hoods. | |||
Reactor complex Perform a general area clean up and remove all contaminated equipment and materials. | |||
Office Areas & Labs Perform a general area clean up and remove all contaminated equipment and materials. | |||
ZPR Reactor Remove contaminated filter and ion exchange column. | |||
S.1.I TRIGA Reactor | |||
* The reactor core, core stand, reflector, fuel rack and other items inside the reactor pool will be removed and shipped for disposal. | |||
* The reactor pool will be emptied and the reactor pool surface decontaminated to eliminated easily removable radioactive material. | |||
5.1.2 TRIGA Bioshield & Beamports | |||
* The thermal column will be removed for disposal. | |||
* The beam port plugs will be removed for disposal. | |||
* The activated concrete in the bioshield concrete monolith surrounding the reactor core will be removed (Figure 5-1). It was estimated that all the high density concrete would require removal plus 3-feet of regular concrete under the pool and up to 2-feet of rock under the pool in some areas. An activation analysis performed by Georgia Tech and reported in Appendix C of the "Characterization Survey Report" (Ref. 6-8) indicates the concrete removal required. In general about five feet of concrete surrounding the core will be removed. | |||
* The activated beam tubes including shields will be removed including removal of a 1-foot thickness of activated concrete surrounding beam tubes. All the beam tubes are in the high density concrete that is being removed anyway. | |||
Rev Page 30 | |||
( ( Decommissioning Cost Estimate Cornell University Figure 5-1 Ward Center Activated Concrete A | |||
ZPRIPit A | |||
ELEVATION A-A PLAN VIEW Rev Page 31 | |||
Decommissioning Cost Estimate Cornell University 5.1.3 Reactor complex There are several different types of areas to be decommissioned in the Reactor Building. The activities for the major areas are outlined below: | |||
* There will be a general area cleanup to remove all unnecessary materials from the facility prior to decontamination and demolition. | |||
* All other process equipment will be removed and shipped directly for disposal as radioactive waste. This includes the heat exchanger, ion exchange system, and recirculation pumps, piping, drain piping and rabbit system, etc. | |||
* Equipment and materials in the hoods on the upper level will be removed and shipped directly for disposal as radioactive waste. The hoods will be decontaminated, removed from the facility, surveyed for free release and disposed of as salvage or clean waste. | |||
* The floor surfaces and structural surfaces are assumed to be free of contamination. The ventilation systems will be surveyed, decontaminated if required and released for disposal as salvage, or disposal as clean waste. The HEPA filters will be removed from the ventilation system, surveyed, decontaminated if required and released for disposal as clean waste. | |||
* The reactor tank concrete remaining after activated concrete removal will be surveyed for free release. This concrete will then be left in place. | |||
5.1.4 Office and Laboratory Wing | |||
* The offices and laboratories and miscellaneous equipment will be surveyed in place for release. | |||
5.1.5 ZPR Reactor | |||
* The contaminated filter and ion exchange column will be removed and disposed of a radioactive waste. The remainder of the ZPR will be surveyed in place for release. | |||
5.1.6 Outdoor Areas | |||
* The sanitary and storm sewers will be surveyed at accessible areas and released for continued use. In addition, soil sampling, and license termination surveys of paved areas and unpaved areas around the Reactor Building will be performed in accordance with current regulatory requirements. | |||
Rev Page 32 | |||
Decommissioning Cost Estimate Cornell University 5.2 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 (MARSSM), (Ref. 6-10). The surveys will be performed in accordance with specifically developed plans and procedures. | |||
5.2.1 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 5-2. | |||
Table 5-2: Typical Final Survey Instrumentation Detector l Calibration Instrnment/Detector l Type l Radiation Detected Source I Use Ludlum Model 2350 wt. Direct alpha and direct 43-68, 43-98, 43-94 or Gas-flow proportional 99Tc (beta surveys; Beta 43-106 detector (126cm 2) Alpha or beta 230 Th (a) scans on solid surfaces. | |||
Ludlum Model 2350/ | |||
SP-1 13-3m or SP- 99Tc (Direct beta pipe 175-3m GM Pipe Detector Alpha or beta 2Th (a) survey. | |||
Direct beta surveys; Ludlum Model 2350 wt. Shielded GM Beta scans on solid 44-40 detector (15.5cm 2) Beta 99Tc (suritces. | |||
Ludlum Model 2350 wt. Gamma exposure rate 37 44-2 or 44-10 detector Nal (TI) Scintillator Gamma 1 Cs and gamma scans. | |||
Eberline Teletector Gamma exposure Model 6112B Ion Chamber Gamma 6Co (y)rate Eberline SAC-4 Scaler 230 Counter ZnS scintillator Alpha Th (a) Smear counting Eberline BC-4 Scaler Counter Shielded GM Beta 99Tc Smear counting Tennelec Planchette Shielded Gas-flow 2 | |||
Counter or Equal proportional Alpha and Beta 99Tc (1), Th (a) Smear counting EG&G NOMAD Nuclide identification Gamma Spectrometer or Gamma energy and and quantification of Equal1 HPGe intensity Mixed gamma soil and sand samples. | |||
Rev 1 Page 33 | |||
Decommissioning Cost Estimate Cornell University | |||
==6.0 REFERENCES== | |||
6.1 10 CFR 50.82 Terminationof License, part (b)for Non-PowerReactor Licensees 6.2 10 CFR 20 Subpart E - Radiological Criteria for License Termination 63 NUREG 1537, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, February 1996 6.4 R.A. Means Company, Inc., 2003, Means Building Construction Cost Data, 2001, 61st Annual Edition 6.5 NUREG/CR-1756, Technology Safety and Costs of Decommissioning Reference Nuclear Research and Test Reactors, March 1982 6.6 Final Safeguards Report to the U.S. Atomic Energy Commission for the Cornell University TRIGA Reactor, May 1961 6.7 Supplement No. 1 to the Final Safeguards Report to the U.S. Atomic Energy Commission for the Cornell University TRIGA Reactor, September 1980 6.8 Characterization Survey Report for the Ward Center for Nuclear Studies at Cornell University, Facilities Inventory Bldg. No. 2061, March 2003 6.9 10 CFR 20.1402 Radiological Criteria for Unrestricted Use 6.10 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-97-016 6.11 NUREG-1757, Consolidated NMSS Decommissioning Guidance, Decommissioning Process for Materials Licenses, September 2002 Rev 1 Page 34 | |||
Decommissioning Cost Esimate Conell UniveIsity APPENDIX A- 1 Contaminated Waste Volume Summary | |||
( | |||
( | |||
k II ( | |||
i Ii APENDIX A-1 I CONTAMINATED WASTE VOLUME | |||
==SUMMARY== | |||
Decon* Barnwell Generated* | |||
Area Bamwell Decon* | |||
Description Direct Bury Envirocare Envirocare CODE Waste Volume Waste Volume Envirocare Direct Bury AREA Waste Volume Waste Volume Total | |||
. TR1GA Reactor (tA3 (ftA3) (ftA3) | |||
Waste Volume Waste Volume (f6- 3) 2 TRIGA Bloshleld & Beam Ports O 120 (ft3) (ftA3) 4 0 3 Reactor Bay 0 24 25 149 29 0 4 Office & Laboratoy Wing 0 a 3,294 3,347 0 12 0 5 Zero Power Reactor 0 31 1,14& 1,158 0 21 0 TOTALS: 0 4 52 0 1 2 144 80 7 | |||
* Notes: | |||
22 4,48 4,714 . | |||
I Decon Waste Volume: This Isthe volume of-waste generated directly I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ | |||
by a decontamination 2 Generated Waste Volume: This is Is a function of labor hours for eachthe volume of protective clothing waste generated by all operations on activity. site and | |||
Decommissioning Cost Estimate Cornell Univezsi y APPENDIX A- 2 Contaminated Waste Disposal Cost | |||
( | |||
(. | |||
I" | |||
( C_ | |||
APENDIX A.2 CONTAMINATED WASTE DISPOSAL COST Decon Barnwell Generated Area Barnwell Decon Envirocare Description Direct Bury Envirocare Total Disposal Envirocare Direct Bury Disposal Disposal Waste Cost Disposal Disposal I TRIGA Reactor Cost Cost Disposal | |||
$0 Cost Cost 2 TRIGA Bloshleld & Beam Ports $201,768 $733 Cost | |||
$0 $0 $5,182 3 Reactor Bay $40,068 $6,037 $207,683 | |||
$0 $0 $675,878 4 Office & Laboratory Wing. $0 $2,561 $721,982 | |||
$0 $0 $235,126 5 Zero Power Reactor $0 $6,370 $237,686 | |||
$0 $4,351 $0 TOTALS: $0 $804 $261 $10,721 Note: $0 $241,836 $16505 $410 $1,478 | |||
: 1. Shading Indicates a named field $4,812 $916,596 linked | |||
: 2. Direct burial &generated waste shippedto another spreadsheet. $1,179,5 to Bamwell. | |||
WASTE DISPOSAL PACKAGING | |||
& SHIPPING COST Decon. Barwell Generated Area Barnwel Decon Envirocare Description Direct Bury Envirocare Total Pack & Enrirocare Direct Bury Pack & Pack & Pack & Waste Ship Ship Pack & Pack & | |||
cost Ship Ship I Cost Cost Ship Ship TRIGA Reactor Cost cost 2 TRIGA Bloshleld & Beam Ports $0 $235 Cost | |||
$17 $0 3 $0 $47 $120 $373 Reactor Bay $140 $0 4 $0 $0 $15,707 $15,894 Office & Laboratory Wing $60 $0 5 Zero Power Reactor $0 $0 $5,464 $5,524 | |||
$148 $101 | |||
$0 $0 $0 $249 - | |||
TOTALS: $19 $6 | |||
'Notes: $0 $282 $10 $34 | |||
$384 $107 I Shading indicates a named field linked | |||
$21,301 $22,074 2 to another spreadsheet. | |||
B-25 Box of waste to Barnwell equal to: | |||
$2,119 | |||
Decommissioning Cost Estimate Comell University APPENDIX A- 3 Waste Shipping Container Cost I | |||
( | |||
1 (, | |||
( | |||
APENDIX A-3 WASTE SHIPPING CONTAINER COST Total B.25* Waste Area Waste Waste Container Description Volume Contalners Cost (ftA3) (Es.) M$ | |||
ITRIGAReactor 149 1.7 $1,395 2 TRIGA Bloshleld & Beam Ports 3,347 37.2 $31,378 3 Reactor Bay 1158 12.9 $10,859 4 Office & Laboratory Wing 52 0.6 $490 5 Zero Power Reactor 7 0.1 $67 TOTALS: 4,714 53 $44,719 | |||
* Notes: | |||
I The number of waste containers Is rounded up to next full container. | |||
UNIT DISPOSAL COST FACTORS Decon waste disposal rate forBarnwell: $1,q81A0 per cubic foot DAW waste disposal rate for BarnwelI: $1,681A0 per cublc foot DAW waste disposal rate for Envirocare: $189.81 per cubl foot Estimated mileage rate to Barnwell: $2.38 per mile Estimated transport distance to Barnwel: 762 miles Estimated mileage rate to Envirocare: $2.36 per mile Estimated transport distance to Envirocare: 2,180 miles Average direct bury waste densIty: 160.0 blcubic foot Average generated waste density (Envirocare waste): 25 bicublc foot Truck transport waste weight limit: 44,000 pounds Truck transport waste volume lmit: 12 -25 Boxes 8.25 box Internal volume: 90 cubic feet tImated cost of used -25 shipping containers: $543.75 each Locel industrial Waste Landfill Shipping & Disposal Rate: $27.30 per cubic yard Labor rate for shipping: $66.00 rer hour | |||
Decommissioning Cost Estimate Comell jnivemity APPENDIX A- 4 Waste Disposal Labor Estimate I | |||
C.I (7 | |||
APENDIX A4 WASTE DISPOSAL SUPPORT LABOR ESTIMATE B-25 Radloactive* Waste Area Waste Waste Shipment Description Containers shipments Labor | |||
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.__ _ _ _ _ _ _ _ (E (Ea.) (m an hr) 1 TRIGAReactor 1.7 0.1 2.5. | |||
2 TRIGA Bloshleld & Beam Ports 37.2 3.1 58.1 3 Reactor Bay 12.9 1.1 19.4 4 Office & Laboratory Wing 0.6 0.0 0.9 5 Zero Power Reactor 0.1 0.0 0.1 I I TO~~~~~~~~~1TALS: 53.0 5.0 80.0 Note I The number of waste shipments Is rounded up to next full shipment. | |||
Estimated waste loading operator time: 4 hr per load Estimated HP Tech time per red or mixed waste load: 4 hr per load Estimated HP shipper time per rad or mixed waste load: 8 hr per load Estimated clean waste shipping volume limit i 1176 ftA3 per load Estimated radwaste shipping volume limit: 12 B-25 Boxes WASTE DISPOSAL CASK COSTS Uners & Radloactive' Waste' Area Cask Cask Shipment Description Rental Rental Labor | |||
[(Ea.) Cost iman-hr) 1 TRIGA Reactor 2 $14,400 72 2 TRIGA Bloshleld & Beam Ports 0.0 0 3 Reactor Bay 0.0 0 4 Offlce & Laboratory Wing 0.0 0 6 Zero Power Reactor 0.0 0 TOTAL 2.0 $14,400 72 | |||
'Notes: | |||
I The number of waste shipments Is rounded up to next ful shipment. | |||
Decommissioning Cost Estimate Cornell University APPENDIX A- 5 Contaminated Waste Disposal Summary | |||
( | |||
( | |||
( le-APENDIXA-5 CONTAMINATED WASTE DISPOSAL | |||
==SUMMARY== | |||
LOG CODE B-25' Waste Radioactive' Total Waste Waste Waste Container Waste Volume Waste Shipment Containers Cost Shipment (ftA3) Shipments Labor 1 (ea.) ($) Labor 149 (o .) (man-hr) 2 1. $15,795 2.1 cost 3,347 37.2 74.5 $4,917 3 .1,158 $31,378 3.1 56.1 4 12.9 s10,859 1.1 3,705 52 0.6 -19A $1,282 5 7 $490 0.0 0.9 Total 0.1 $87 0.0 $58 | |||
-4,714 53.0 0.1 $8 | |||
'Notes: $58,590 7.0 151.1 I The number of waste containers $9,970 are rounded up to next fuN container. | |||
2 The number of waste shipments are rounded up to next full shipment. | |||
7,. | |||
Decommissioning Cost Estimate Cornell nivesity APPENDIX A- 6 Building Survey Labor Summary r ( | |||
C' (-K' Ci APPENDIX NON-IMPACTED BUILDING A-6 AREA SURVEY ENTER BELOW ENTER SURVEY ENTER OPTNL ENTER ENTER ENTER ENTER ENTER BUILDING PACKAGE AREA ENTER LOC ROOM AREA AREA AREA FLOOR+ U. WALL+ | |||
NAME NUMBER REQRD WIDTH LENGTH ENTER SURVEY CODE DESCRIPTION HEIGHT L WALL CEILNG DIRECT BELOW BELOW ? BELOW BELOW Survey PACKAGE URVEY 4IWard BELOW BELOW SURVEY SURVEY Center Exterior (ft) if Sketchs PREP LABOR Exterior (e) CODE CODE Y 100A 124.0 each ye) e) 40.0 2 a 5 8 24.4 TOTALS a 241 | |||
f | |||
( ,C. | |||
APPENDIX A-6 IMPACTED BUILDING AREA SURVEY 2 Reactor Blo*hleld Exterior Exterior 4 Gamma Cell y 22.0 27.5 Eterlior Exterlor 22.0 2 5 4 Basement y 12.5 3 8 42 4 lntvoductory Lb ow tp. I 1.0 16.0 1 4 Y 4 2 8 Basement I Introduto LaboratorytHo.2 '15.33 24.7 13.0 22 4 N 1 4 Basement 3 15.33 21.0 13.0 8 24 4 Dark Room 1 4 B nt N 600 15.3 1 5 Cotm Room 13.0 1 4 4 Basement H 15.33 18.0 10 Hall M Coridor No. 1 13.0 1 4 4 Basement Y B.00 83.0 14 6 Machine shop 13.0 1 4 4 Basement Y 1933 23.3 8 34 6-Nail Hllwaynr Room 13.0 1 4 4 Basement N 5.00 11.00 8 26 S Chemit Laboratory 13.0 1 4 4 Basement H 2500 32.33 . | |||
2A Cold WorkAre 13.0 1 4 4 Basement Y 11.33 15.7 2 2-H*l Hallway near Room 2 16.5 1 4 Basement N 5.33 a 8 2m Set-Up Rom 13.3 13.0 1 2 4 Basement N 10.7 4 2C Gammi Cell 13.0 1.0 1 10 4 Basement Y 9.00 4 ELEV ElevatorShaft 9.0 1.0 1 1' 4 Basement N 6.00 5 8 stairW stahwayNo.1 8.0 41.8 3 20 4 Basement N 8.83 6 134hall Hallway ner Room 13 13.3 14.0 2 17 4 Basement N 8.00 a 13 Mens Tonet No. 1 10.0 1S.0 1 10 4 Basement N 11.33 4 R12 hotope& Fuel 8torage Room 18.7 9.0 1 9 4 Ba Y 6.00 4 R3 ReaetorEqulpiment oom 19.8 13.0 1 131 4 Basement Y _ 16.1t 4 8 R344all H"s2ynearRoomR3 19.8 14.0 1 2 4 Basement _ N 6.25 4 8 Containment Ar 25.5 13.0 1 23 5 Basement Y 48.00 4 ZPR Pit 70.0 45.6 I 12 2 B"sement y 13.50 6 8 SPR Pool 14.0 20.0 3 13 4 Y 6 8 | |||
-Basement 7 Laboratory 11.00 11.5 25.0 32 4 Y 3 6 Basement 74He11 HallwnerRoom7 18.33 18.3 13.0 8 29 4 N 1 4 Basement 9 6.00 39.0 13.0 8 23 4 Elet-tical Utility Roo 1 4 Basement Y 10.00 18 18 11 Mechanical Utlt Room 13.0 1 4 4 Basement Y 14.33 18.1 8 20 15 Waste Hold41p Tank Room 13.0 1 4 4 Basement Y 1200 160 8 22 17 TransformerVault 10.0 1 4 4 Basement N 12.00 21.0 8 20 Star #S StairwayNo. 6.0 1 4 4 latFloor N 4.00 6.o 14 106 staff Offle 8.0 2 5 4 letFlor Y 11.17 15.3 12 102 SuperrsorsOfflee 9.0 1 4 4 1st Floor N 15.30 15.5 8 20 100 Lobby 9.0 1 4 4 lstFloor N 12.83 15.3 13 101 HP OMce 9.0 1 4 4 istFloor Y 11.92 15.3 12 10S StaffLab-OffloeNo.1 9.0 1 4 4 1stFloor HN 14.75 15.3 8 20 Hall #2 Corridor No. 2 9.0 1 4 4 . 1stFloor N 0.00 72.0 13 | |||
* 112 statf Lab-Otce No. 2 9.0 1 4 4 lstFloor Y 12.17 18.3 2 112-Hall HallnesrRoomli2 9.0 . 1 4 4 1stFloor N 6L00 24.5 8 21 116 talLaWbOMceNo.3 9.0 1 4, I1 4 1st Floor 118 Class, Conference & seminar N 11.50 183 9.0 12 N 1 4 28.00 31.9 9.0 13 1 4 N | |||
24] | |||
I (C o( C APPENDIX A-6 IMPACTED BUILDING AREA SURVEY 4 lotFloor 110 J"nltmCloset 4 let Floor N 3.00 4.0 114 Pantr 9.0 1 4 4 lot Floor N 4.00 8.0 81 108 Women's Tollet 9.0 1 4 4 la Floor Y 10.00 11.3 8 104 Stock & oe Room No. 1 9.0 1 4 4 ltFloor Y 7.83 11.3 8 18 ELEV Elevator Car 9.0 1 4 4 letFloor Y 4.00 5.0 8 1 StalrF1 StalrwavyNo.1 7.0 1 4 4 lst Floor N 8.83 13.3 8 10 103 Stoc& a Room No. 2 11.0 2 a 4 et Floor Y 7.83 11.3 16 107 Men'a Tle No. 2 11.0 I 4 4 lt Floor N 11.33 13.7 8 18 109 Eltrunlos Room 11.0 1 4 4 iat Foor N 12.33 18.3 11 10mmall Halway near Room 109 11.0 1 4 5 I tFloor 800 13.0 13 111 ZPRLaboratoq 11.0 1 4 5 lat For y 2.00 31.0 1I 113 ZPR Con Room 11.0 1 4 a lot Foor N 18.50 24.0 8 32 115 Closet 9.0 1 4 a lst Floor N 3.00 &8 18 117 ZPR Enty Hag 9.0 1 4 5 let For N .25 17.5 ZPR to" Ars 11.0 1 4 5l 1tFloor Y 12.00 13.3 1 ZPRTankkArsa 11.0 1 4 4 lotFloor N 13.50 14.0 8 20 Stsfr#3 ft! No.3 Ler 11.0 2 _ | |||
4 lutFloor Y 8.00 10.3 18 Stalr#3 8tu r No.3Patfo 7.0 1 4 4 letFloor N 2.75 28.5 8 17 Stalr 3 StlrlmvNo.3,Upper, 2.0 1 4 4 istFloor N 2.75 65 12 stalr #2 Stslvy No. 2, 4.0 1 4 4 2nd Floor N 600 10.5 81 204 Lob4Ofioe No. 2 11.0 1 4 4 2ndFloor Y -12.50 153 9 202 Lab.OletNo.3 11.0 1 4 4 2ndFloor N 12.50 13.8 8 20 201 mab.ofiNo.4 11.0 1 4 4 2nd Floor N 10.19 12.6 12 203 Lab-Oofl No. 11.0 1 4 4 2nd Floor N 12.50 15.3 11 206 Lab-Otloe No. 1 11.0 1 4 4 2nd Floor N 14.17 16.3 12 Hal 3 Corrdor N 3 11.0 1 4 4 2ndFloor Y 5.00 27.5 13 stairpi EtwlrwaNo.1 11.0 1 4 4 2nd Floor N 8.83 13.3 8 20 205 Lab4.mce No. 8 2.0 1 4 4 2nd Floor Y 11.33 14.2 11 205-Hall Halby near Room s 11.0 1 4 4 2ndFloor. N .00 14.2 8 20 Topof Gem Ce 11.0 1 4 4 2nd Floor N 11.00 13.0 10 R.202 Isotope Handllna Roorn 11.0 1 4 a 2nd Floor Y 12.33 14.5 11 R-205 Above ZPRAre 9.0 1 4 | |||
: 4. 2nd Floor N 17.80 21.0 8 2 R.201 Latboraory 11.0 2 5 4 2nd Floor N 9.17 19.5 24 R-203 Obseation Room 9.0 1 4 4 2nd Floor Y 16.17 19.5 12 R205 8PR Control Room 9.0 1 4 4 2nd Floor N 19.50 21.3 8 2 Stair#2 StairwayNo. 2 9.0 1 4 N 6.oo 10.5 1 2.0 1 4 | |||
. 9 | |||
. ~~~~~~ ~ ~~~TOTALS 248 1,425 | |||
Decommissioning Cost Estimate | |||
- - University | |||
~~~~~~~~~~~~~~~~Cornell APPENDIX A- 7 Outdoor Area Survey Labor Summary | |||
( | |||
( | |||
APPENDIX NON-IMPACTED OPEN LANDA-7 PAVED AREA SURVEY ENTER BELOW ENTER ENTER SURVEY ENTER ENTER OPTIONAL SURFACE ENTER AREA PACKAGE AREA AREA Random SURVEY LOC TYPES REQRD WIDTH LENGTH 10% | |||
CODE BELOW DESCRIPTION Survey PACKAGE SUR BELOW ? BELOW BELOW Sketchs 4 AsphalttTAasume Area 65 PREP LABOR feet by 250 fWt near Reactor (YIN) (It) (ft) | |||
Bulding t (each) Mrs) Hours Yl 651 2501 3 4 5.1 TOTALS 3 4 5.1 | |||
APPENDIX A-7 IMPACTED UNPAVED OPEN LAND AREA SURVEY ENTER BELOW ENTER SURVEY OPTIONAL ENTER ENTER ENTER SUB ENME SURFACE PACKAGE AREA LOC AREA AREA SURFACE RandoM DIRECT TYPES REQRD WIDTH LENGTH ACTIVITY Survey CODE BELOW DESCRIPTION SURVEY BELOW ? BELOW BELOW DEPTH Sketcho 4 Soll , soll Under Reatr Buiding LABOR (N 00 ft ft each Mm) | |||
Y 55 901 3 2 25 TOTALS: 25 | |||
I'- | |||
,( a . | |||
I APPENDIX NON-IMPACTED OPEN LAN A-7 UNAVED AREA SURVEY ENTER BELOW ENTER OPTIONAL SURFACE ENTER SURVEY ENTER ENTER ENTER LOC AREA PACKAGE AREA AREA TYPES Random Rndom SURVEY CODE BELOW DESCRIPTON REORD WIDTH LENGTH 10% | |||
SuMy Survey PACKAGE 4 Gree- & BELOW ? BELOW BELOW SURVEY 20 moterbordwraroundRewotuildt" G (YIN) Sketchs swetd PReP (I) (I) (ech) LABOR | |||
___, Hour. (iMM) (") | |||
Y 65 250 3 1.001 TOTALS 4 5.8 | |||
.... 3 I I 3 1.0l 4 S.s | |||
C~ ~~ ( | |||
APPENDIX A-7 DRAIN & SEWER SURVEY CATCH BASIN & CLEAN-OUT SURVEY BASIN SURVEY DURATION (hrs): 4 BASIN SURVEY CREW SIZE (men): I ENTER ENTER SURVEY BELOW ENTER BASIN PACKAGE SURVEY OPTIONAL AREA DIAMETER REQRD PACKAGE SURVEY LOC DESCRIPTION BELOW ? PREP LABOR CODE BELOW (ft) (YIN) (hrs) (hrs) 4 Manhole on 24" Storm Sewer to NW of Reactor Building 5.0 r 4 8.0 4 Manhole on 24" Storm Sewer to SE of Reactor Buildng 5.0 N 4.0 4 Manhole on 24 Sanitary Sewer to Westd of Reactor Building 5.0 Y 4 8.0 4 Manhole on 24" Sanitary Sewer to North of Reactor Building 5.0 N 4.0. | |||
TOTALS 8 24 DRAIN PIPE SURVEY PIPE SURVEY RATE (ftthr): 40 PIPE SURVEY CREW SIZE(men):. 3 ENTER .ENTER ENTER SURVEY S O>PTIONAL ENTER PIPE PIPE PACKAGE SURVEY LOC AREA DIAMETER LENGTH REQRD PACKAGE SURVEY CODES DESCRIPTION BELOW BELOW ? PREP LABOR BELOW BELOW (ft) (ft)h) (h) 4 Storm Drain 24 150 Y 4 15.3 4 SantarySewer 24 150 Y 4 15.3 | |||
-TOTALS 83 | |||
Decommissioning Cost Estimate Cornell Univensity APPENDIX A- 8 Instrument Lease Charges | |||
( j ( | |||
APPENDIX A-8 Table COMMERCIAL CLIENT INSTRUMENT COSTS 6 D&D Months Duration 2.0 Final Survey Months Duration 0.5 Characterization Survey Months Duration CHAR SURVEY D&D FINAL SURVEY D&D D MONTHLY NUMBER NUMBER NUMBER FULL ALTERNATE ITEM INSTRUIMENT COMMS:ZAL INSTRUMENTS INSTRUMENTS INSTRUMENS PROJECT MONTHLY No. DESCRIPTION RENTAL RATE REQUIRED REQUIRED REQUIRED DURATION DURATION RADIATION PROTECTION AND MEASUREMENT INSTRUMENTATIONISYSTEMS _ . | |||
I Becton Dickson - TRITON, Model III Tuithim Monitor: $737 2 MICROSPEC-2, Nal(TI) Gamma Spec System W/Detector, PC, Software, Case &Accessories: S524 __._. | |||
3 GENI PC, Gamma Spec System W/Detector, PC. Software. Case &Accessories Model 4610J GC4511 $5,546 1 1 1 Y 4 INSPECTOR, Portable Gamma Spec WIDetedor. PC. Software, M-1 Insitu Cal, Tripod & Accessories: $4,037 5 Q2 Low Level Waste Assay System WI(3) HPGe Detedors, PC, Vault Shield WISCale, Turntable & Acc.: $4,974 6 GTSD Mod. Q2 Waste Assay System W/(3) HPG. Detectors, PC. Modular Shield W/Scale, Turntable & $2998 7 DCA - Portable Area MonItor 3090-3: $46 _ . | |||
8 Ebetline -FASTRACK n DosWety Wh PC, Printer, lea DR200 lea DR200R, 30ea DD100 & $821 9 Eberlne - Dosimeter Meter Reader Model DR-200: $216 .___. | |||
10 Ebeffine -Dosimeter Res e Check Station Model DR-200 OPT7: $553 . . . _. | |||
11 Ebedlne -FASTRAC 11,PC Dose Mawgeet Prgram ith Utf: $216 . | |||
12 Ebedline -Dital Dosimeter Model DD-100: 552 13 Ebewline - Personal Contamination Monitor, Model PCM-1B w/ Accessories: $2590 14 Ebedine - Personal Contamination Monitor, Model PCM-1C w/ Accssores: $3.353 15 Eberflne - Personal Contaminaion Monitr Model PCM-2 Base Unit: $4.193 16 Ebedne- Portable Aha Counter, Model SAC-4: $194 I . _ Y 17 Ebedlhe- Portable Beta Counter, Model BC-4: $162 1 1 Y 18 Ebedln - Portable GM §M srmKModel E-520 wI HP-270 & SK-I: $258___________ | |||
19 Eberlne - Portable GM Survy tun Model E-520 WI HP-260 &SK-1: $272 _ | |||
20 Eberlne - Portable High R e n Chamber, Model R07 W/Low & i Detectors 5 Extension $ | |||
S179 : | |||
21 Ebedfne - Portable Ion Chamber Instrument Model R02: $78 _ ___ | |||
22 Ebedlne - Portable Ion Chamber stum Model R02A: $78 . _ | |||
23 Eberline - Scintillation Portal Monitor, Model PM-7 WIPC, Software, Calibration Jb. Remote ALam & 60 $3,295 . | |||
24 Ebelne - Tool Contamination Monitor Model TCM-2 with e Detector: $1,654 . _ | |||
25 Ebedlne - TELETECTOR Gamma Dose Rate Meter Model 61 12B w/ Accessories: $200 26 EG&G -NOMAD, Portable PC Based Gamma Spec Anlyzer W/HPGe Detector, PC, Software & Acc.: $1,292 . _ | |||
27 Void $383 28 F&J - BUCK Pmp K5t 6 Personal Air an, Calibrator Chaqe & Case: $908 . _ | |||
29 F&J - Model HV-1 Hig Volhme Air Samplerwith Sample Head: $56 1 . _ | |||
30 F&J - MODEL LV-1, Low Volime Air mler with Sample Head: $46 2 Y 31 F&J - MODEL LV-14M GOOSENECK LOW VOLUME AIR SAMPLER WITH SAMPLE HEAD: $106 ___ ___ | |||
32 LUDLUM - MODEL 12 SURVEY METER WITH 44-9 PANCAKE GM PROBE & CASE: 583 33 LDLUM - MODEL 12 SURVEY METER WITH 43-5 ALPHA SCINTILLATION. PROBE &CASE: $98 - _ | |||
34 LUCLUM - MODEL 19 MICRO R METER WITH HARD CASE $44 .1 1 1 Y 35 LUDLUM - MODEL 177 ALARM RATE METER WnlH 44-9 PROBE AND CASE: $41 1 3 3 Y 36 Ludlurn - Model 239-1F Floor Monitor Cart W/O Model 12 Meter &WIModel 43-37 425 cne Gas Flow D$ S163 . 2 _ | |||
37 Ludlun -Model 2350 Data Logger t WKe d Barode Reader Pelican Case & Detectors # 38 Thm $180 3 3 4 : | |||
38 Ludlun - Model 2350 Data Logger Kit Wld, Barcode Reader, Pelican Case (No Detectors): $114 _ | |||
39 LUDLUM - MODEL 43-5 ALPHA SCINTILLATION DETECTOR: 668 I 3 2 Y ._ _ | |||
40 LUDLUM - MODEL 43.68 100 am2 GAS PROPORTIONAL DETECTOR: $59 _ | |||
41 LUDLVM - MODEL 44-1 BETA SCINTILLATION DETECTOR $60 _ | |||
42 LUDLUM - MODEL 44-2 HIGH ENERGY GAMMA SCINTILLATION DETECTOR: $60 _ | |||
43 LUDLUM - MODEL 44-38 ENERGY COMPENSATED GM DETECTOR: $18 _ _ | |||
( ( N APPENDIX A-8 Table COMMERCIAL CLIENT INSTRUMENT COSTS 6 D&D Months Duration 2.0 Final Survey Months Duration 0.5 Characterization Survey Months Duration CHAR SURVEY D D FINAL SURVEY D4D MONTHLY NUMBER NUMBER NUMBER FULL ALTERNATE ITEM INSTRUUENrr COMMERCIAL INS TRnENTS INSTRUMENTS INSTRUMENTS PROJECT MONTHLY No._ ____ ____ ____ ____ ____ ____ ____ ____DESC_ _7O__- RENTAL RATE REQUIRED REQUIRED REQUIRED DURATION DURATION 5_ 4_ _0_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __.__ _ | |||
44 LDLUM - MOOEL 44-40 SHIELDED GM PANCAKE DETECTOR: S40 4 LDLUM - BETA AIR MNITOR (CAM). MODEL 3332: .$472 ___. _ | |||
46 1LUDLUM - MODEL 77-3 STRETCH SCOPE XTELETTOR). 5211 . | |||
47 NE TECHNOLOGY - MODEL CM7A CONTAMINATION MONITOR WITH DPSHA PROBE: $463 .___ | |||
48 Padcard - PC Based IWd Siilan Counsr W/ Aloha I Beta Oplm & Accessoes / A2550P2: S1,684 49 Quatr*ad - SCOUT-1, Nal(TI) Gamma Spec Syem WlDetedor, PC, Software, Case & Accessories: S1.308 50 REUTER-STOKES - PRESSURIZED ION CHAMBER RSS-122: $886 51 TENNELC - MODEL LB S100-2080411 PC BASED ALPHAIBETA COUNTER SYSTEM: $1,691 RADIATION PROTECTION AND MEASUREMENT INSTRUMENTATION/SYSTEMS 52 TSI -MODEL 8020 PORTACOUNT, RESPIRATOR FIT TESTER: $588 53 XETEX - MODEL 330A TELESCAN DOSE RATE METER WI CASE & ACCESSORIES: 5388 INSTRUMENTATION SOURCES (MAY BE CHARGED AS CONSUMABLE OR RENTAL1 54 GAMMA SPEC. NIST TRACEABLE MIXED SOIL EQUIVALENT I LITER MARINELLI: 568 1 1 1I Y . | |||
55 GAMMA SPEC. NIST TRACEABLE MIXED WATER EOUIVALENT I LITER MARINEWI: $62 . | |||
56 GAMMA SPEC. NIST TRACEABLE MIXED FILTER PAPER EQUIVALENT: $62 1 1 1 Y . | |||
57 GAMMA SPEC. NIST TRACEABLE MIXED POINT SOURCE: $60 . | |||
58 02 GAMMA SPEC. NIST TRACEABLE MIXED 30 INCH UNE SOURCE: $228 _ . | |||
59 Q2 GAMMA SPEC. NIST TRACEABLE MIXED 6 INCH QC SOURCE: $166 . | |||
60 ALPHAIBETA COUNTER BC-4, NIST To.99 47mm LINEARITY 4 SOURCE SET: $264 . | |||
61 NIST To-99 47mm SOURCE PER EACH (1, 10 100 OR 1000 n): 565 2 2 2 Y . | |||
62 ALPHAfBETA COUNTER SAC-4. NIST Th-230 47mm UNEARITY 4 SOURCE SET: $317 _ _ | |||
63 NIST Th-230 47mm SOURCE PER EACH (1, 10, 100 OR 1000 nCa4: $65 2 2 2 Y . | |||
64 CM7A NIST ALPHA CALJCHECK SOURCE WITH ALUMINUM CASE/HOLDER: $68 __. | |||
65 CMA NIST BETA CALCHECK SOURCE WITH ALUMINUM CASEIHOLDER: 568 _ | |||
66 TCM-2 & PCM -B. NIST CALICHECK SOURCE: $375 __ | |||
67 PM -7, NIST CAL/CHECK SOURCE: 5211 _ | |||
DECON EQUiPMENT 68 LTC VAC>U-BLAST STEEL SHOT BLASTER: S1,450 _ | |||
69 PENTEI VAt;PAt; MODEL 9AVAtCUUM: S1,982 _ 1 2 70 PENTEK SIJIRREL I FLOOR SCABBLER . S1,134 71 PENTEK CORNER CUTTER NEEDLE GN: 5329 _ | |||
72; MCDONALD AIR TOOL MODEL U5 5 PISTON FLOOR SCABBLER: _ 865 - | |||
732MCDONALD AIR TOOL MODEL 3WCW, 3 PISTON WALL SCABBLER: S293_ _ | |||
74 MCDONALD AIR TOOL MODEL HS, SINGLE PISTON SCABBLER: 594 _ | |||
75 2000 CFM HEPA VENTILATION UNIT MODEL 1990C: 5119 _ | |||
76 HAKO TWIN HEAD ELECTRIC HEPA VACUUM: $138 ___ | |||
77 NORCLEAN TRIPLE HEAD ELECTRIC HEPA VACUUM: S554 .1 Y _ | |||
MBTELEST EUIPMENT 7c1FLUKE - 8060A DVM WITI1 HV PROBE. CASE AND LEADS: $M14 79 EBERLINE - bIP-2 MINIPULSER AND LUDLUM MODEL 500 MINIPULSER: S430 -_ | |||
( (0 C' APPENDIX A-8 Table COMMERCIAL CLIENT INSTRUMENT COSTS 6 D&D Months Duration 2.0 Final Survey Months Duration 0.5 Characterization Survey Months Duration CHARSURVEY D&D FINAL SURVEY D&D D&D MONTHLY NUMBER NUMBER NUMBER FU1 ALTERNATE ITEM INSTRUMENT' COMMERCIAL INSTRUMENTS INSTRUMENTS INSTRUMENTS PROJECT MONTHLY No. DESCRIP77ON RENTAL RATE REQNiRED REQtfRED REQUIRED DUtRATION DURATION 80 TEKTRONKX- MODEL 2225 100 MHZ PORTABLE OSCILLOSCOPE WITH BATTERY PACK: $513 . | |||
81F&J AIR FLOW CALIBRATOR MODEL D.12: $200 . | |||
82 F&J AIR FLOW CALIBRATOR MODEL D-814: $200 . . | |||
83 FIELO SERVICE TOOL KIT: $130 . | |||
OFFICE EQUIPMENT 84 DATA ANALYSIS COMPUTER SYSTEM: $205 1 1 1 Y . | |||
85 DOWNLOAD NOTEBOOK COMPUTERS: $151 1 1 2 Y . | |||
86 HP MODEL IIP LASER JET PRINTER: $83 1 1 1 Y 87 HP MODEL 4L LASER JET PRINTER: 83 88 HP OFFICE JET FAX/COPIER: S62 SAMPLING EQUIPMENT _ . | |||
89 BICO - JAW CRUSHER. MODEL 241-36X35: $297 _ | |||
90 FISHER SCIENTIFIC-TOP LOADING SCALE, 0-3 kg MODEL XE4100: $46 1 . 1 91 FISHER SCIENTlFIC- CLASS F S.S. WEIGHT SET, mg-2kg CAT.# 0221531: $14 1 1 1 Y 92 FISHER SCIENTIFIC- OVEN, ISOTEMP 5.0 120VAC CAT.# 13247750G: $124 1 1 1 Y 93 FORESTRY SUPPLIERS - SOIL SAMPLING AUGER KIT. CAT.# 67352: $289 _ | |||
IGLOBAL POSITIONING SYSTEM 94 TRIMBLE NAVIGATION - SITE SURVEYOR SYSTEM, MODEL 40DSE: $1.766 _ | |||
COMMUNICATIONS EQUIPMENT 95 MOTOROLA - MODEL HT1000, 16 CHANNEL UHF RADIO WITH ACCESSORIES: $213 . _ | |||
TOTAL INSTRUMENT LEASE COST | |||
Decommissioning Cost Estimate Cornell University APPENDIX A- 9 Equipment Lease Charges | |||
( | |||
APPENDIX A-9 COMMERCIAL CLIENT EQUIPMENT COSTS 6 D&D Months Duration 2.0 FINAL SURVEY Months Duration D&D FINAL SURVEY D&D D&D D&D FINAL SURVEY MONTHLY NUMBER NUMBER FULL ALTERNATE EQUIPMENT EQUIPMENT ITEM EQUIPMENT . COMMERCIAL ITEMS ITEMS PROJECT MONTHLY LEASE LEASE NUMB ER DESCRIPTION RENTAL RATE REQUIRED REQUIRED DURATION DURATION COST COST | |||
. DECON EQUIPMENT . . . ._._. | |||
I LTC VAC-U-BLAST Steel Shot Blaster: $1,450 . . ._._._;___ | |||
2 PENTEK VAC-PAC Model 9A Vacuum: $1,982 . ._.___ . | |||
3 PENTEK-SQUIRREL IlIl Floor Scabbler: $1,134 . I 4 PENTEK CORNER CUTTER Needle Gun: $329 ._._. | |||
5 MCDONALD AIR TOOL Model U-5, 5 Piston Floor Scabbler: $865 . | |||
6 MCDONALD AIR TOOL Model 3WCW, 3 Piston Wall Scabbler: $293 7 MCDONALD AIR TOOL Model HS, Single Piston Scabbler: $94 _ | |||
812000 CFM HEPA Ventillation Unit Model 1990C: $119 . | |||
9 HAKO Twin Head Electric HEPA Vacuum: $138 _ __.___- | |||
10 NORCLEAN Triple Head Electric HEPA Vacuum: $554 . | |||
OFFICE EQUIPMENT 11 Data Analysis Computer System: $205 . . _ | |||
12 Download Notebook Computers: $151 . I 13 HP Model IIIP LaserJet Printer: $83 . | |||
14 HP Model 4L Laser Jet Printer: $83 ._.___._. - | |||
15 HP Office Jet FAX/Copier: $62 . | |||
16 35mm Camera $67 1 1 N 2 $134 $134 17 Fax machine $24 18 Telephone $5 ._. | |||
19 Office Trailer, 50' x 10' . | |||
20 Toilet, portable chemical . | |||
21 Desk $135 . . . . | |||
22 File Cabinet, 5 drawer x 28" $129 . | |||
23 File Cabinet, fireproof, 4 drawer- $381 . . | |||
24 Work Tables, 30" x 60" $51 . . . . . | |||
25 Coat Racks, 36" x 21" x 60" $91_1 | |||
( c; C, APPENDIX A-9 COMMERCIAL CLIENT EQUIPMENT COSTS 6 D&D Months Duration 2.0 FINAL SURVEY Months Duration D&D FINAL SURVEY D&D . D&D D&D FINAL SURVEY MONTHLY NUMBER NUMBER FULL ALTERNATE EQUIPMENT EQUIPMENT ITEM EQUIPMENT COMMERCIAL ITEMS ITEMS PROJECT MONTHLY LEASE LEASE NUMBER DESCRIP77ON RENTAL RATE REQUIRED REQUIR URAT7ON DURATON COST COST 26 Draft Table .$238 ... . | |||
_ 27 Desk Cha_rs _ $57 _ | |||
.28 Molded Plastic Chairs $14 . | |||
29 Microwave oven $97 . . | |||
30 Coffee Machine $149 . | |||
31 Refrigerator $342 32 Waste Containers (7 gallon) $11 . . | |||
33 Waste Containers (35 gallon) $53 34 Draft Table Stool $57 . . , | |||
35 Plan Holders (P&ID) $91 36 Break Room Folding Tables $101 37 Molded Plastic Chairs $14 . , . | |||
38 Multi-Media Board, 36" x 60" $34 . ._in SAMPLING EQUIPMENT | |||
.39 BICO - Jaw Crusher, Model 241-36:35: $497 40 FISHER SCIENTIFIC -Top Loading Scale, 0-3 kg Model XE41 00: $46 41 FISHER SCIENTIFIC - Class F S.S. Weight Set, mg2kg CAT.# 0 $14 . _ ._. | |||
42 FISHER SCIENTIFIC - Oven, ISOTEMP 5.0 120VAC CAT.# 13247 $124 43 FORESTRY SUPPLIERS - Soil Sampling Auger Kit, CAT.# 67352 $289 ._.__ | |||
COMMUNICATIONS EQUIPMENT . _ | |||
44 MOTOROLA- Model HTI000. 16 Channel UHF Radio with Access $116 . I | |||
;___ _ TOOLS . ._. | |||
45 Full Set Misc Tools w/Chest * $93 _ . | |||
46 34" Impact Wrench $128 . | |||
47 314" Impact Socket Set $23 . . | |||
48 Set of -ffing Slings $56 3 . . $1,008_ | |||
( APPENDIX A-9 COMMERCIAL CLIENT EQUIPMENT COSTS 6 D&D Months Duration 2.0 FINAL SURVEY Months Duration MONTHLY 1.NUMBER D&D | |||
-_ FINAL SURVEY NUMBER D&D FULL D&D ALTERNATE EQUIPMENT EQUIPMENT D&D FINAL SURVEY ITEM EQUIPMENT COMMERCIAL ITEMS ITEMS PROJECT MONTHLY LEASE LEASE NUMBER DESCRIPTION RENTAL RATE REQUIRED REQUIRED OUR4 7ON DURATION COST COST | |||
-49 Drm Heaters - Evaporation $28 . . . | |||
50 8' Fiberglass Step Ladder $45 3 1 y $810 $90 51 4 Outlet GFCI Circuit Guard $62 | |||
.52 Air Compressor (2-1/2 HP, 5.5 CFM) $74 53 1 x 150' Air Hose $28 6 Y . $1,008 54 Air Chipplnq Hammer with Chisels $96 55 Electic Drills 1/2 Inch $46 56 8-114'Circuilar Saw $35 _ _ _ _ _ _ _ _ _ _ | |||
57 Milwaukee Heavy Duty Straight Grinder $90 . _._. | |||
58 Long Handled Shovels $10 . . . .. _. | |||
59 Snow Shovels $5 . | |||
60 Steel Pry Bar $2 . ._-_. | |||
61 Long Handeled Pry Bar Set $15 . . , | |||
62 Electrc Paint Sprayer (for fixative agents) $20 : | |||
63 Cutting Torch $109 _ Y $654 64 Band Saw $57 2 Y $684 65 Drum handling cart $36 . . | |||
66 Extension cord, 100 ft. 1213,15A $33 67 lighting standard, 2 500 W halogen quartz $37 I Y $222 68 Stringlght 100f, 10 lamp $11 : | |||
69 110,000 BTU Oil-Fired Space Heater $60 .___. | |||
HEAVY EQUIPMENT RENTAL _ | |||
70 Truck Mounted Hydraulic Crane, 25 Ton $10,692 1 N -1 $10,692 71 40' Telescoping Boom Uft $6,831 _ N 2 $13,662 72 TruckThree ade dump,6 ton payload $8,118 . . - | |||
73 Oxyacetylene Cutting Outfits $386 1 Y $2,316_ | |||
74 1-14 C.Y. Backhoe Loader $5,643 N 1 , | |||
75 Backhoe Aftachment, 1000 ft-b Hydraulic Hammer $6,138 I __ N 2 $12,2761 | |||
( C ( | |||
APPENDIX A-9 COMMERCIAL CLIENT EQUIPMENT COSTS 6 D&D Months Duration 2.0 FINAL SURVEY Months Duration D&D FINAL SURVEY D&D D&D D&D FINAL SURVEY MONTHLY NUMBER NUMBER FULL ALTERNATE EQUIPMENT EQUIPMENT ITEM EQUIPMENT COMMERCIAL ITEMS ITEMS PROJECT MONTHLY LEASE LEASE NUMBER DESCRIPTION RENTAL RATE REQUIRED REQUIRED DURATION DURATION COST COST 76 Hydraulic Grapple with Shear Attachment for Loader $1,871 . . . : . | |||
77 Service Truck $1,634 _ 1 Y _ $9,804 | |||
_______ SAFETY EQUIPMENT . | |||
78 Respirators $45 79 Tripod Lifeline Rescue System $192 . Y $1,152 80 Portable Axdal Electric Blower W/25' Ducting $166 1 Y $996 81 Confined Space Safety Harness $25 I _ _____ Y ____ $150 _____ | |||
82 Portable Multigas Monitor $174 . Y $1,044 83 FirstAid Kit $25 2 1 Y $300 $50 84 Respirator Porta Count . . $490 | |||
_ ___ { | |||
85 Heat Stress Monitor $86 : . . l | |||
[ I I I f TOTAL EQUIPMENT LEASE COST $56,9121 $274 | |||
Decommissioning Cost Estimate Comell University APPENDIX A- 10 Demolition Estimate | |||
APPENDIX A-1 0 Demolition Estimate LABOR BAED DEMOLITION COSTS: Labor by man hour MamnMmnt SupewtIlon, &HP Support Labor Not Includd Uff Operator& DEMOLITION LOC Craftmn Laborers Craftsman HP Tech LABOR TOTAL CODE AREA $44.54 $40.95 $44.54 $66.00 hours PRICE 3 Geneal Cleanup 173.33 1733 $,9 1 Remove Reactor Cote and Internals 67.606.93 74.5 S3 2 Drain Reactor Pool 24.27 3.47 27.7 $1.222 5 Remove ZPR Reactor Core and Related Internals 24.27 3.47 27.7 ii222 I ShI Reactor Core and Related Intemals 104.00 104.0 56.864 3 Remove Reactor Bu~ldina Equipmen 417.73 22.53 440.3 S18,593 3 Remove Heat Exchanwr 8.67 1.73 10.4 $469 4 Peeuw & Ship Contam. Materials &Radioactive Wastes 173.33 3.47 176.8 S7.327 1,034.8 $46,021 | |||
C (1~ (1S APPENDIX A-10 TASK BASED DEMOLITON COSTS 42% Hardous ToxcrWaste Poductft Factor. Level C,Heavy Work 70. a5YF Peent Labor Coot 65.00% MATERIAL LABOR EQUIPMENT MATERIAL LABOR EQUIPMENT LOC Average Hourly Labor Rate *40.95 UNIT UNIT UNIT TOTAL TOTAL TOTAL TOTAL CODE AREA QUANTITY UNIT PRICE PRICE PRICE PRICE PRICE PRICE PRICE 2 1r8.CutBloshleldCon 1,213 aquarefeet $39.81 $118.84 S48.050 $144.150 S192.200 2 Remove Concrete under Pool 30 cubic yard $0.00 $8.28 $3.0 S0 $4,878 $2,607 $7A83 2 Remov Rock underPool 20 cubicyard $0.00 $8828 $36.50 $0 $3251 $1,738 $4,989 SO $58,177 $148,495 24,7 | |||
Deconunissioning Cost Eslimate Comell University APPENDIX A- 11 Decontamination Costs i | |||
I | |||
\ | |||
(7) ( I C . I I | |||
APPENOOX AM1 COS I O!COO4TAM#4AVIOIN DISPOSAL , --- | |||
PECIFP AREA SU P O SI V .C SA MAL U Wrn SF4Y1ROCAIW - | |||
A~ Now Alpw sow0686 E wSrPtii-NOW APP. bW9TH~OOLY owP~m AR0 OF"ff a M CE MA tf I A6#AL PN WASTE ESNITY D. | |||
CONTAK VOUMPE CMTML 66622T. | |||
r DMIAL | |||
$Was"WR PRO02S CoST mm"6S cmS m6.awU cm6 AM~W CODE 64429 I 11 M I 10.37 821m1 4 206 12 2 60.7 I Ro611,PA9 w 3 | |||
mc wod U4 6ct4or.1$ | |||
~ | |||
Mcid tomS-tv oma om 4m j 636t 12 VS 60. 68 as $%, I $AU14 102.83 11 SPECIFIC ARE&S RPACE M few Now No~~~~~U8w Jsawf Noj T | |||
JNIfRADAECM FCSANLYM was8 R~t GM TDGNEAE FEO IPW0 IAE c Loc OM WASTE. WAST 0RC0.00 ES~IMES GAI am ft UWACE CONTAK OORT~~~~~~~~k cot CS OA APP. AREA METHODOLOGY LLR WFR VOL. DES *e T -ew 7 | |||
O 89c SS 0O w2. I H u~~~~ 1O , f t~~~ | |||
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0.MM WAT 0.0 UNLI0 LAE OA MEHOOLGYA a O E "P | |||
1, | |||
Decommissioning Cost Estimate Comell Univenity APPENDIX A- 12 Miscellaneous Item Inventory Estimate | |||
C) I ( | |||
APPENDIX A-12 MISCELLANEOUS ITEM VOLUME ESTIMATE NO. MATL PERCENT ENVIRO DESCRIPTION LOC WBS OF OF BULK UNIT UNIT TOTAL TOTAL DIRECT DISPOSAI CODE No. UNITS UNITS CONST. DENSITY WEIGHT VOLUME WEIGHT VOLUME BURY WEIGHT TRIG3) A) 3 ) 3 (Vol %) (lb) | |||
TRMEA RQar Activated Hardware 1 Ea 2 Misc 6,000 60.0 12,000 120.01- 100% 12,00( | |||
Pool Fuel Storage Wells I Ea 4 Alurinum 168.6 103 6.3 414 25.3 100% 41A Thermal Column I Ea I Graphite &Al 100.0 2,849 28.5 2,849 28.5 0% | |||
0 0.0 C | |||
TRIGA Beam Port Plugs &Shielding C 0 0.0 C Horizontal Access Removable Graphite Block 2 Ea I Graphite 100.0 933 9.3 933 9.3 100% 933 Horontal Acoess Hohlam Block 2 Ea I Hohlraum 100.0 2.133 21.333 2133 21.3 100% 2,133 Horizontal Access Graphite Block 2 ft I Graphite 100.0 5,467 64.0 5,467 64.0 iO0% 5,467 Horzontal Access Lead 2 Ea I Lead 708.0 3.776 5.3 3,776 5.3 00% 3,776 Horizontal Access Boral Can W thick 2 t2 1 Boral 168.6 281 1.7 281 1.7- 0 HorzOntal Rolling Door Plug (llrnenite Concrete) 2 Ea 1 HO Concrete 230.4 0 0 0. t% 0 Vertical Access Lead-1 2 Ea I Lead 708.0 1,785 2.5 1,785 2. !00% 0 Vertical Access Plug Lead 2 Ea I Lead 708.0 2,366 3.34. 2,366 3.3 rS0 0 % 0 Vertical Access Plug Graphite 2 Ea I Graphite 100.0 1,797 17.97 1,797 18.0 )00% 0 Vertical Access Plug Boral Can 118" Thick 2 ft2 I Boral 168.6 83 0.495 83 0.5 0 Vertical Access Center Plug (Ilmenite Concrete) 2 Ea 1 HD Concrete 230.4 3,612 15.68 3,612 15.7 0% 0 Vertical Access Top Plug (Ilmenfte Concrete) 2 Ea I HO Concrete 230A 10.443 45.3 10,443 45.3 0% 0 Vertical Access Lead-2 2 Ea I Lead 708.0 2,589 3.7 2,589 3.7 '100# 2,589 Vertical Access Lead3 2 Ea 1 Lead 708.0 3,068 4.3 3,068 4.3 100% 3,068 0 | |||
Activated TRIGA Boshleld Concrete with BSem Tube Part 0 Activated Concrete 2 ft3 2 HD Concrete 230.4 292,077 1,267.9 584,155 2,535.8 100% 584.155 Activated Rock 2 ft 2 Rock 100.0 28.000 280.0 58,000 560.0 100% 56,000 Reactor Bay Reactor Building General Cleanup Waste 3 ft3 360 40.0 14,400 360 100% 14,400 Waste Generated During Pool Draining 2 If 90 15.0 1,350 90 100% 1,350 Waste Generated During Reactor Building Equipment Removal 3 ft 180 40.0 7,200 180 100% 7,200 Waste Generated During Piping Removal 3 ft3 180 15.0 2,700 180 100% 2,700 Waste Generated During Heat Exchanger Removal 3 ft 90 40.0 3,600 90 100% 3,600 Waste Generated During Removal of Rabit Transfer Systern 3 ft 180 40.0 7,200 180 100% 7,200 (P ' | |||
C | |||
) I | |||
() ( > | |||
APPENDIX A-12 MISCELLANEOUS ITEM VOLUME ESTIMATE NO. MArL PERCENT ENVIRO DESCRIPTION LOC WBS OF OF BULK UNIT UNIT TOTAL TOTAL DIRECT DISPOSAI asN CODE No. UNITS UNITS CONST. DENSITY WEIGHT VOLUME WEIGHT VOWME BURY WIHT gbftA3) _pj W3) ps (ftm31 (vol %I (Ib ChaOM Filer 3 Ea 1 50.0 3,462 69.2 3,462 69. 100% 3.4 Mbmed4 Demloeralzer 3 Ea I 50.0 4,330 86.6 4,330 86.?0 100% 4,33C ZPR Watr System I " | |||
water dean up filter 5 ft3 2 50.0 50 1.0 100 2.0 100% 100 i | |||
I TOTALS: 738,093 4,702 't 100% 714,877}} |
Latest revision as of 12:40, 25 March 2020
ML032400205 | |
Person / Time | |
---|---|
Site: | 05000157, 05000097 |
Issue date: | 07/31/2003 |
From: | Ely P, Schult D, Shult R Duratek |
To: | Cornell Univ, NRC/FSME |
References | |
Download: ML032400205 (77) | |
Text
Deconunissioning Cost Estimate for the Ward Center for Nuclear Studies at Cornell University Facilities Inventory Bldg. No. 2061 Rev July 2003 Prepared by:
Duratek, Inc Prepared for: Commercial Operations Cornell University 1009 Commerce Park Drive, Suite 100 Oak Ridge, TN 37830
Decommissioning Cost Estimate Cornell University DECOMMISSIONING COST ESTIMATE for the Ward Center for Nuclear Studies at Cornell University Facilities Inventory Bldg. No. 2061 Rev 1 July 2003 Prepared By: a Paul Ely Senior Radiological Engineer Reviewed By: a T~
Doug ult, CHP Date Project Manager Approved B 463 Robin Shult v Date General Manager Commercial Operations Prepared By:
Duratek, Inc.
1009 Commerce Park Drive, Suite 100 Oak Ridge, TN 37830 r, (0F V
Decommissioning Cost Estimate Cornell University PROPRIETARY STATEMENT This document is the property of the Cornell University and furnished with the understanding that the information herein will be held in confidence and will not be duplicated, used or disclosed either in whole or part without the written permission of Cornell University.
Rev 1 Page i
Decommissioning Cost Estimate Cornell University EXECUTIVE
SUMMARY
Duratek, Inc (Duratek) performed an independent cost estimate for decommissioning the Ward Center located in Ithaca, New York. This estimate was prepared at the request of the Cornell University.
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 and the removal of these released buildings. The estimated decommissioning cost is $3,603,086 in terms of 2003 dollars. This estimate does not include the costs associated with fuel removal and transport from Ward Center to the Department of Energy (DOE). This estimate is for budgetary purposes only and is not a proposal for Duratek 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 Envirocare of Utah. Activated materials will be sent to the Barnwell South Carolina disposal facility.
Rev 1 Page ii
Decommissioning Cost Estimate Cornell University TABLE OF CONTENTS
1.0 INTRODUCTION
...........................................................................................................1 1.1 Purpose .............................. 1 1.2 Scope .............................. 1 1.3 Assumptions and Bases ............................. 2 2.0 GENERAL FACILITY DESCRITION ..... 4......................
3.0 DECOMMISSIONING CRITERIA .. ........................... 11 3.1 Radionuclides of Interest .................................. 11 3.2 Radiological Criteria for License Termination .............. .................... 12 3.3 Reactor complex.................................................................................................. 14 3.4 Office and Laboratory Wing .................................. 16 3.5 Utilities and Auxiliary Services .................................. 17 3.6 TRIGA Reactor .................................. 18 3.7 Relation of Ward Center to Other TRIGA reactors ....................... ........... 18 3.8 Outside Areas .................................. 19 4.0 ESTIMATIONMETHODS .................... 21 4.1 Cost Modifying Factors .............................. 21 4.2 Radioactive Waste Volume Estimates .............................. 25 4.3 Radioactive Waste Disposal Costs .............................. 25 4.4 Remediation Methods .............................. 26 4.5 Radioactive Waste Volume Reduction Costs ......... ..................... 27 4.6 Unit Costs .............................. 28 4.7 Final Surveys .............................. 29 5.0 FACILITIES, RADIOLOGICAL CONDITIONS AND DECOMMISSIONING SCENARIO ......................... 29 5.1 Remediation Summary ........................ 29 5.2 License Termination Surveys ........................ 33
6.0 REFERENCES
.......... ........ 34 Rev 1 Page iii
Decommissioning Cost Estimate Cornell University LIST OF APPENDICES APPENDIX A- 1 Contaminated Waste Volume Summary .......................................... 1 APPENDIX A- 2 Contaminated Waste Disposal Cost .......................................... 2 APPENDIX A- 3 Waste Shipping Container Cost .......................................... 3 APPENDIX A- 4 Waste Disposal Labor Estimate .......................................... 4 APPENDIX A- 5 Contaminated Waste Disposal Summary .......................................... 5 APPENDIX A- 6 Building Survey Labor Summary ......................................... 6 APPENDIX A- 7 Outdoor Area Survey Labor Summary ............... ........................... 7 APPENDIX A- 8 Instrument Lease Charges .......................................... 8 APPENDIX A- 9 Equipment Lease Charges ......................................... 9 APPENDIX A- 10 Demolition Estimate ......................................... 10 APPENDIX A- 11 Decontamination Costs ......................................... 11 APPENDIX A- 12 Miscellaneous Item Inventory Estimate ......................................... 12 Rev 1 Page iv
Decommissioning Cost Estimate Cornell University LIST OF FIGURES Figure 2-1 Map of the Area Surrounding Cornell University .......................................... 5 Figure 2-2 Cornell University Campus ...... 6........................
Figure 2-3 Cornell University Ward Center Site .......................................... 7 Figure 2-4 Ward Center Basement Plan View ......................................... 8 Figure 2-5 Ward Center 1st Floor Plan View .......................................... 9 Figure 2-6 Ward Center 2nd Floor Plan View ......................................... 10 Figure 3-1 Ward Reactor Core and Thermal Column ......................................... 20 Figure 5-1 Ward Center Activated Concrete ......................................... 31 LIST OF TABLES Table 3-1 List of Expected Radionuclides ........................................... 11 Table 3-2 Acceptable License Termination Screening Values of Common Radionuclides for Building Surface Contamination ........................................... 13 Table 4-1: Decommissioning Cost Summary - Ward Center ........................................... 21 Table 4-2: Personnel Protective Equipment Protection Summary ......................................... 22 Table 4-3: Hazardous and Toxic Waste Productivity Factors: Light Work ........................... 23 Table 4-4: Hazardous and Toxic Waste Productivity Factors: Heavy Work ......................... 24 Table 4-5: Ward Center Unprocessed Radioactive Waste Summary .................................... 25 Table 4-6: Decontamination Methodology Comparison .......................... ................. 27 Table 4-7: Volume Reduction Methodology Cost Information ........................................... 28 Table 4-8: Decommissioning Cost Estimate Selected Unit Cost Factors .............................. 28 Table 5-1: Ward Center Planned Remediation Activities ................................. .......... 30 Table 5-2: Typical Final Survey Instrumentation ............... ............................. 33 Rev 1 Page v
Decommissioning Cost Estimate Cornell University
1.0 INTRODUCTION
1.1 Purpose The Commercial Operations division of Duratek, Inc (Duratek) has prepared this document for the purpose of providing a decommissioning cost estimate for Ward Center for Nuclear Studies TRIGA Reactor and Zero Power Reactor at Cornell University. The cost estimate includes those activities and associated cost factors required to terminate the Ward Center TRIGA Reactor Nuclear Regulatory Commission (NRC) License R-80, Doc. No.50-157 and Zero Power Reactor Facility License R-89, Doc. No.50-97 and release of the reactor portions of the Ward Center for "unrestricted use." A New York State licensed gamma irradiation facility located in Ward Center will be closed August 30, 2003. The facility will be decommissioned and the New York State (NYS) license amended accordingly. The term "unrestricted use" means that there will be no future NRC restrictions on the use of the site.
The decommissioning is projected to start within the next year. The cost estimate provided by this report is in terms of 2003 dollars. This estimate is intended to be used for funding and budgetary purposes and does not constitute a proposal or cost estimate for Duratek to perform work.
1.2 Scope The scope of this report is to present the estimated costs derived for decommissioning the Ward Center. The specific areas covered by this estimate include:
- TRIGA Reactor
- TRIGA Bioshield and Beam Ports
- Reactor complex
- Office and Laboratory Wing
- Zero Power Reactor 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. 6-1). 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 10CFR Part 20 (Ref. 6-2).
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-Rev Page 1
Decommissioning Cost Estimate Cornell University 1757, ConsolidatedNMSS Decommissioning Guidance, Decommissioning Processfor MaterialsLicenses, Appendix B, (Ref. 6-3).
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 surveys were estimated based on the size of the various areas being decommissioned and their prior radiological history.
The cost estimate for the Ward Center utilizes a combination of unit price estimates and task-based estimates to arrive at a total cost in 2003 dollars for decommissioning all areas. The unit cost methodology is modeled after the method used in the Means Building Construction Cost Data(Ref. 6-4). 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. 6-5). 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.
1.3 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 Ward Center to the DOE prior to the start of decommissioning, costs for these activities are not included in this estimate.
- The Ward Center will be decontaminated and free released.
Rev Page 2
Decommissioning Cost Estimate Cornell University
- The Gamma Irradiation Facility will be closed and decommissioned by Cornell.
- Some of the uncontaminated laboratory equipment located throughout the facility has a high intrinsic value and may be moved to another facility prior to decommissioning.
- The use of radioactive materials at the Ward Center has been well controlled and contaminated areas are 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.
- Cornell will provide security for the site, power will be available, and the Cornell University staff and management will be on site during decommissioning.
- Radioactive waste with low specific activity will be sent to Envirocare of Utah. It was assumed that concrete, protective clothing waste, and miscellaneous dry active waste would qualify for disposal at Envirocare of Utah.
- Radioactive waste not suitable for disposal at Envirocare of Utah will be sent to the Barnwell, South Carolina disposal site.
- The site remediation 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 2003 RS Means Building Construction Cost Data for Binghamton, New York.
Rev Page 3
Decommissioning Cost Estimate Cornell University 2.0 GENERAL FACILITY DESCRIPTION The regional location of the Ward Center is shown in Figure 2-1; Figure 2-2 depicts the Ward Center site and adjacent Cornell structures; the Ward Center site is depicted on Figure 2-3. Figure 24, Figure 2-5 and Figure 2-6 presents plan views of the three floors of the Ward Center.
The Ward Center TRIGA Reactor is similar to the Oregon State University TRIGA Reactor that was used as the basis for the decommissioning estimate reported in NUREG/CR- 1756, Technology Safety and Costs of DecommissioningReference Nuclear Research and Test Reactors, March 1982 (Ref. 6-5). A full description of the facility is provided in FinalSafeguards Report to the U.S. Atomic Energy Commissionfor the Cornell University TRIGA Reactor (Ref. 6-6) and Supplement No. I to the Final Safeguards Report to the U.S. Atomic Energy Commissionfor the Cornell University TRIGA Reactor (Ref. 6-7).
The Cornell University stopped routine operation of the Ward Center TRIGA Reactor on June 30, 2002 and plans to submit a request for a possession only license in 2003. The TRIGA is currently operated for short periods of time at low power levels in order to maintain operator qualifications. The University previously ceased operation of the ZPR reactor on September 6, 1996.
The spent fuel is the property of DOE and was leased to Ward Center. This lease requires DOE to take possession of the fuel when the University is done with it.
Aluminum-clad and stainless steal-clad fuel that has been used at Ward Center, will be shipped to the National Engineering and Environmental Laboratory in Idaho Falls, Idaho.
Rev Page 4
Decommissioning Cost Estimate Cornell University Figure 2-1 Map of the Area Surrounding Cornell University
- ornell Rev Page 5
Decommissioning Cost Estimate Cornell University Figure 2-3 Cornell University Ward Center Site I
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I N CVT Rev 1 Page 7
Decommissioning Cost Estimate Cornell University 3.0 DECOMIISSIONING CRITERIA A Duratek engineers visited the Ward Center Facility in Ithaca, New York in February of 2003 to gather physical and radiological data. Facility sketches, building sketches, and radiological characterization data for affected areas were obtained.
3.1 Radionuclides of Interest The base line radioactive material quantities were obtained from the estimate provided in NUREG/CR-1756, (Ref. 6-5). There are additional radionuclides reported in the characterization survey report (Ref. 6-8) 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, 60Co 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 1,500 curies of neutron activation products at the time of shutdown. The radionuclides that potentially exist in the Ward Center along with estimated inventories are presented in Table 3-1.
Table 3-1 List of Expected Radionuclides Nudide Half-Life Inventory 3
H 12. Not Available 14c 5,730 1.11
'VAr 269 2.53 x 10-3 41 Ca 103,000 4.6 x 10-4 45ca 0.446 0.23 46sc 0.233 2.34 x 10-2 51Cr 0.0759 251
'4Mn 0.86 22.7
"'Fe 2.73 118
'"Fe 0.1222 4.74 "Co 0.74 Not Available 5Co 0.194 133 60Co 5.27 567 59Ni 76,000 0.11 6aNi 100 12.6 "1Zn 0.67 67.2 90Sr 29.1 Not Available 93Z.b 13.6 2.34 x 10-5 94Nb 20,000 2.6 x 10-4
'Nb 0.0961 2.08 x 10-2 Rev Page I
Decommissioning Cost Estimate Cornell University
_~~~~~~
Nuclide HIalf-Life i Inventory (Yr) Ci 9"Tc 213,000 Not Available 124sb 0.16 Not Available t5Sb 2.76 Not Available inI 15,700,000 Not Available 134CS 2.7 Not Available 37Cs 30.17 Not Available 14Ce 0.78 Not Available 52Eu 13.48 Not Available 154E, .8 Not Available MEu 4.96 Not Available 21 Pb 22.26 Not Available
=_Ra 1,600 Not Available 3
M Th 77,000 Not Available 233 4 a U >159,200 Not Available 14.4 Not Available The list ofexpected radionuclides provided above is based on the assumption that operations ofthe Ward Center has resulted in the neutron activation ofreactor 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.
3.2 Radiological Criteria for License Termination The overall objective of the Ward Center decommissioning is to remediate the facilities to a condition that corresponds to a calculated dose to the public of less than 25 mrem/year from applicable pathways. The facilities may then be released for unrestricted use. This dose limit appears in 10 CFR 20.1402, Radiological CriteriaforUnrestrictedUse (Ref. 6-9).
The Derived Concentration Guideline Level (DCGL) is defined in MARSSIM (Ref. 6-10) 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 Ward Center 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. 6-3).); (2) screening levels derived using D and D, Version 2.0 (Ref. 6-11), for the specific radionuclides(s) using the code's default parameters. The assumed DCGLs for Rev Page 12
Decommissioning Cost Estimate Cornell University Ward Center were based on the look-up tables in NUREG-1757, Appendix B (Ref. 6-3).
The proposed DCGLs for surface contamination are based on the screening tables in NUREG-1757, Appendix B (Ref. 6-3). 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
- The fraction of removable surface contamination does not exceed 0.1.
Table 3-2 Acceptable License Termination Screening Values of Common Radionuclides for Building Surface Contamination Radionuclide Symbol Acceptable screening levels' for Unrestricted release (dpmll00cm2 )
Hydrogen-3 (Tritium) 3H 1.2E+08 Carbon-14 It 3.7E+06 Sodium-22 22Na 9.5E+03 Sulfur-35 35s 1.3E+07 Chlorine-36 36Cl 5.OE+05 54 Manganese-54 Mn 3.2E+04 Iron-55 "Fe 4.5E+06 Cobalt-60 60Co 7.lE+03 Nickel-63 63Ni 1.8E+06 Strontium-90 90Sr 8.7E+03 Technetium-99 99Tc 1.3E+06 Iodine-129 12I 3.5E+04 Cesium-137 '3 7CS 2.8E+04
'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 1.
Rev 1 Page 13
Decommissioning Cost Estimate Cornell University Units are disintegrations per minute per 100 square centimeters (dpmf100 cm2 ). I dpm is equivalent to 0.0167 becquerel (Bq). The screening values represent surface concentrations of individual radionuclides that would be deemed in compliance with the 0.25 mSv/yr (25 mremyr) 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.
3.3 Reactor complex The property, on which is situated the Cornell University Ward Center, was designated for construction in 1959. The Ward Center was constructed between 1959 and 1962.
The structure does not have a history of spills or other contamination and it is anticipated that, at the time of decommissioning, remediation will be minimal. It is assumed that some of the ventilation system components and some miscellaneous equipment will be disposed as radioactive waste.
Decommissioning of the structure will follow decommissioning of the reactor and reactor equipment. The structure will then be surveyed using a license termination type survey with any additional structural decontamination performed in conjunction with the surveys.
The land area is not well defined, as there are no boundaries between the Ward Center and the nearby engineering buildings. Structurally and functionally the building consists of two main sections, the reactor complex, a relatively airtight reinforced concrete structure faced with brick veneer and an office and laboratory wing of reinforced concrete columns and beams faced with native stone.
The reactor complex is 63 feet by 70 feet in plan and 45 feet in height. This portion of the building, containing approximately 5,500 square feet of floor space, houses the two reactors and their control rooms, associated experimental and service areas, and the gamma irradiation cell. The office and laboratory wing, which is U-shaped, consists of east and west sections approximately 26 feet wide and a north section approximately 33 feet wide. The total length of the U is approximately 176 feet, thus providing approximately 10,000 square feet of floor area. This wing of the facility houses, in a basement and two stories, a counting room, laboratories, offices, a classroom, and building utility rooms.
The principal function of the reactor complex is to house the two reactors and their associated operational and experimental areas. The gamma irradiation facility is also located in the bay in the northeast comer; it is, however, functionally part of the office and laboratory wing. (The only access to the gamma cell from the reactor complex is through a 4 ft by 4 ft opening in the cell roof to permit heavy objects to be moved in and out by an overhead crane; normally the opening is kept closed by a removable concrete plug.)
Rev 1 Page 14
Decommissioning Cost Estimate Cornell University The TRIGA reactor structure is approximately centered in the reactor complex and rises 25 ft above the basement floor level. The Zero Power Reactor is housed immediately north of the TRIGA in a self-contained, two-story high concrete cell.
The south wall of the ZPR cell serves also as the north wall of the TRIGA pool.
The remaining volume of the reactor complex is divided into rooms and working floor space on three levels: basement, first floor, and second floor. There are two stairways connecting the three levels. A pendant-operated 5-ton bridge crane mounted on rails running along the north and south walls, traverses the entire area of the bay. The crane can service both reactors and the gamma cell.
The reactor complex is a reinforced concrete structure. The interior surface of the concrete is coated with a vapor barrier and painted to provide a smooth surface capable of being readily decontaminated. Personnel access to the reactor complex section may be gained from the office and laboratory wing through only three doors, one at each floor level. A large door on the west wall at the basement level provides truck access to the bay for loading and unloading freight. Since the grade is a relatively steep slope from the north to the south, the basement of the entire building is underground at the front (north) end and above grade in the rear, permitting truck unloading at the basement level of the reactor complex.
The roof of the reactor complex is flat and consists of pre-stressed concrete beams, concrete roof slabs, 1-in. rigid vapor barrier insulation, and built-up roofing. All floors in the bay are protected with a Phenoline coating (except for the observation room, the second floor laboratory room, and the two control rooms, where asphalt tile is used).
3.3.1 Basement Plan The ZPR cell and the TRIGA pool occupy the central portion of the basement, running on the north-south axis of the building. All other facilities in the basement are on either side of these two centrally located reactor structures. The northeast corner of the basement contains the gamma irradiation cell. Immediately west of the ZPR pit is a corridor permitting personnel access from the office and laboratory wing to the reactor complex. The isotope-and-fuel storage room occupies the northwest corner of the basement and immediately south of it is the reactor equipment room. The remaining basement floor area is available for experimental setups, in particular those utilizing neutron beams from the TRIGA.
3.3.2 First Floor Plan Continuations of the ZPR cell and TRIGA pool occupy the north central portion of the first floor of the reactor complex. At the northeast corner is the roof of the gamma irradiation cell. At the northwest comer is the ZPR control room, which is connected by a labyrinth to the ZPR cell. The cell Rev 1 Page 15
Decommissioning Cost Estimate Cornell University broadens out at this level to include a grid-plate-and- fuel storage area. A removable grating in the ZPR cell floor affords access to the basement area of the cell. Access to the ZPR control room is either from a stairway platform in the main reactor area or from the ZPR laboratory in the west section of the office and laboratory wing. At the nose of the TRIGA and slightly below the first floor level is the top surface of the TRIGA thermal column shielding; this surface forms a working area around the vertical access to the thermal column.
3.3.3 Second Floor Plan Access to the second floor of the reactor complex is afforded by stairways inside the bay and by a door into the north section of the office and laboratory wing. The second floor includes a balcony, or catwalk, around most of the perimeter of the bay. The TRIGA control room is situated on this floor, and immediately adjacent to it is the observation room, which permits viewing reactor operations without interfering with the operators.
A laboratory room is located at the northwest corner adjacent to the observation room. Also at this level are the isotope handling room and a platform and working area surrounding the top of the TRIGA pool.
3.4 Office and Laboratory Wing 3.4.1 General The U-shaped office and laboratory wing houses a classroom, offices, utility rooms, and a number of laboratory rooms. In addition, the main personnel entrance to the entire Laboratory is at the front (north) of the building at the first floor level of this wing. Two emergency exits are located at the basement level of this wing, one at the southeast and one at the southwest corner; the latter is also a delivery entrance.
The east and west sections of the office and laboratory wing consist of a basement and one story. The north section has in addition a setback second story. A centrally located enclosed stairwell and an adjacent elevator interconnect the three floors.
For radiation safety purposes, all parts of the building except the classroom and first floor offices and service rooms are off-limits to unescorted visitors. The principal control point for entrance to the restricted area of the building is the stairwell door opposite the lobby (The other three entrances--elevator, ZPR laboratory door, and rear delivery door-- may be opened only with keys that will be issued only to authorized personnel).
Rev Page 16
Decommissioning Cost Estimate Cornell University 3.4.2 Gamma Irradiation Cell The gamma irradiation cell and associated setup room and cold work area form a block of three rooms at the basement level. Although the cell proper and the set-up room are physically located within the reactor complex to permit utilization of the 5-ton crane for loading and unloading materials in the cell, functionally they are part of the laboratory wing.
3.4.3 Basement Plan The basement level of the office and laboratory wing houses (in addition to the cold work area) a corridor, a chemistry laboratory, a machine shop, two rooms for introductory laboratory courses, a darkroom, a counting room, a men's toilet, a general laboratory room, and the electrical and mechanical utility rooms. All of these rooms open off the corridor, which may also be used to reach an entrance to the reactor complex. Two subterranean rooms are attached to the west wall of the basement: one is the transformer vault, accessible only from a stairway outside the building, and the other is the waste storage tank room, which opens off the general laboratory room.
The chemistry laboratory includes two hoods with suitable filters for work with low-level radioactive chemicals in addition to standard chemical laboratory equipment and utilities.
3.4.4 First Floor Plan The first floor level of the office and laboratory wing consists of the lobby, a classroom, an office for the Reactor Supervisor and a secretary-receptionist, three faculty laboratory-offices, a faculty office, an office for the University Health Physicist and the University Radiation Safety Officer, an electronics maintenance room, the ZPR laboratory, a pantry, storage rooms, and toilet rooms. The stairwell and elevator are directly across the corridor from the lobby.
The ZPR laboratory also opens into the ZPR control room in the reactor complex.
3.4.5 Second Floor Plan On the second floor are six laboratory-office rooms opening off a corridor that also leads to a door into the reactor complex.
3.5 Utilities and Auxiliary Services Conventional utility services normal to the operations of a laboratory of this nature are provided, together with the auxiliary services required for the reactors Rev Page 17
Decommissioning Cost Estimate Cornell University and the gamma irradiation facility. Compressed air, combustion gas, water, and electricity are supplied to all laboratory rooms including those that have been designed for dual use as laboratory-offices. The compressor for the air is located in the mechanical utility room. Necessary outlets for standard laboratory services are provided in the experimental areas of the reactor complex. The water system includes water purification equipment for the reactor cores as well as equipment for temporary storage of contaminated water.
3.6 TRIGA Reactor The Ward Center reactor is a 500-kilowatt TRIGA Mark II reactor. The reactor and reflector assembly are located at the bottom of a plastic coated concrete tank 25 feet deep. Approximately 20 feet of water above the core provides vertical shielding. The core is shielded radially by a minimum of 6 feet of ilmenite concrete (235 b/ft3), 1.5 feet of water and 1.0 feet of graphite reflector.
There are several experimental and irradiation facilities associated with the TRIGA reactor. A graphite thermal column approximately 4 feet by 4 feet by 8 feet extends for the outer face of the reflector assembly into the concrete shield structure. A track-mounted heavy concrete door provides horizontal access and shielding for the thermal column. There are two nesting coaxial removable plugs or square cross section in the center of the thermal-column door. Vertical access to the thermal column is also provided. Inside the thermal column near the inner end are a 32-inch by 32-inch by 36-inch hohlraum block and a 24-inch by 24-inch by 28-inch removable graphite block. The pool, which is approximately 11 feet by 12 feet in cross section, permits access to the flattened face of the reflector.
Seven beam ports are provided for beam experiments and for the insertion of specimens for irradiation: two 3-inch thermal beam ports, four 6-inch radial beam ports, and one 4-inch throughport. The centerlines of all beam ports are located in the same horizontal plane approximately 2-feet 10-inches above the pool and room floors, which are at the same elevation.
3.7 Relation of Ward Center to Other TRIGA reactors The design of the Ward Center 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, draining 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.
Rev Page 18
Decommissioning Cost Estimate Cornell University 3.8 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 natural surface drainage around the Ward Center site from roof drainage and storm run-off is routed to Cascadilla Creek by utilizing natural drainage and storm sewers.
The sanitary sewer and nearby storm sewers will be surveyed at locations just upstream and downstream locations relative to the Ward Center. In addition soil sampling, and license termination surveys of paved areas and unpaved areas will be performed in areas adjacent to the Ward Center in accordance with current regulatory requirements.
Rev Page 19
Decommissioning Cost Estimate Cornell University Figure 3-1 Ward Reactor Core and Thermal Column Rev Page 20
Decommissioning Cost Estimate Cornell University 4.0 ESTIMATION METHODS The estimated cost to decommission the Ward Center is $3,603,086. This section of the cost estimate report provides an overview of the considerations and factors that influenced the decommissioning cost estimate. Table 4-1 provides a summary of the costs associated with each area of the facility.
Table 4-1: Decommissioning Cost Summary - Ward Center Operation Man- Labor Plus Equipment, Radwaste Total Cost hours Trav. & Liv. Contracts & Shipping &
I Supplies Disposal TRIGA Reactor 746 $54,191 $27,775 $212,973 $294,939 TRIGA Bioshield & 5338 $424,827 $273,787 $741,581 $1,440,196 Reactor Bay 2374 $189,406 $52,730 $244,492 $486,628 Wing aoay 926 $74,416 $16,941 $11,028 $102,384 Zero Power Reactor 128 $10,272 $2,338 $1,518 $14,128 Characterization 1040 $90,220 $4,274 $0 $94,494 Surveys _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _
Final Surveys 4160 $360,880 $17,097 $0 $377,977 Planning, Training, 272 $21,370 $0 $0 $21,370
& Mobilization __ _ _ __ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _
Owner Oversight & 693 $50,353 $0 $0 $50,353 Licensing 15676 I $1,275,934 $394,943 $12159______
Totals 15676 $1,275,934 $394,943 $1,211,592 $2,882,469 25% CONTINGENCY $720,617 I GRAND TOTAL $3,603,086 4.1 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 Rev Page 21
Decommissioning Cost Estimate Cornell University personnel protection described in Table 4-2. The Productivity Factors related to these levels of personnel protection are provided in Table 4-3 for Light Work and in Table 4-4 for Heavy Work.
Table 4-2: Personnel Protective Equipment Protection Summary Level A: The highest available level of respiratory, skin, and eye protection Level B: The highest level of respiratory protection, but less skin protection than Level A. Level B is the minimum level recommended for initial site entries, or for other entry conditions dealing with unknown hazards.
Level C: The same level of skin protection as Level B, but a lower level of respiratory protection.
Level D Modified: Skin protection similar to or the same as Level C, without respiratory protection.
Level D: Standard work uniform suitable for construction work: no respiratory protection and minimal skin protection.
Rev 1 Page 22
I ( Decommissioning Cost Estimate
(
Cornell University Table 4-3: Hazardous and Toxic Waste Productivity Factors: Light Work Level A Level B Level C Level D Modified Level D Variables U/M 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.Deritylosses Min. 78 69 60 74 69 64 55 51 44 4 4 3 5 5 5 D.Totaltimelostper-hr.WD Min. 298 319 340 257 274 290 218 242 273 110 127 142 67 70 81 E.Productivitytimeper8-hr.WD Min. 182 161 140 223 206 191 262 238 207 370 353 338 413 410 399 F. Productivity time on clan site Min. 430 430 430 430 430 430 430 430 430 430 430 430 430 43 4 30 G. HTW Productivity Factor 0.42 037 033 0.52 0.44 0.6186 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/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.
Rev 1 Page 23
I Decommissioning Cost Estimate Cornell University Table 4-4: Hazardous and Toxic Waste Productivity Factors: Heavy Work Level A Level B Level C Level D Modified Level D Variables U/M T<70 70<T T>85 T<70 70<T T>85 T<70 70<T T>85 T<70 70<T T>S5 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 G. HTW Productivity Factor 0.28 0.22 0.15 0.40 036 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 = 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/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.
Rev 1 Page 24
Decommissioning Cost Estimate Cornell University 4.2 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 Ward Center decommissioning, the cost for radioactive waste processing, shipping, and disposal is anticipated to be about 40% of the total decommissioning cost. This is a normal fraction for radioactive facilities.
Radioactive waste volume estimates are discussed in the following section. Table 4-5 provides a volume summary for each area of the Ward Center. Information about most waste items are provided in Appendix A-12.
Table 4-5: Ward Center Unprocessed Radioactive Waste Summary Direct Generated Decon Direct Barnwell Envirocare Envirocare Envirocare Total Disposal Disposal Disposal Disposal Disposal Volume Volume Volume Volume Volume Area Description (ftA3) (ftA3) (f J (ftA3) (ftA3)
TRIGA Reactor 120 4 0 25 149 TRIGA Bioshield & 24 29 0 3,294 Beam ports 3,347 Reactor bay 0 12 0 1,146 1,158 Office & Laboratory 0 31 21 0 Wing 52 Zero Power Reactor 0 4 1 2 7 TOTALS 144 [ 80 22 4,467 [ 4,714 43 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 at Duratek followed by disposal at Envirocare of Utah and direct radioactive waste disposal at Envirocare of Utah and Barnwell, South Carolina. The following sections describe the pricing for each facility.
4.3.1 Envirocare of Utah Disposal Costs The costs to transport waste to the Envirocare of Utah disposal site are based on a transport distance of 2,180 miles, at a rate of $2.36 per mile.
The cost to dispose of the waste at the Envirocare of Utah site are based on a disposal fee of $189.91 per cubic foot.
Rev Page 25
Decommissioning Cost Estimate Cornell University 4.3.2 Barnwell South Carolina Disposal Costs The costs to transport waste to the Barnwell South Carolina disposal site are based on a transport distance of 897 miles, at a rate of $2.36 per mile.
The cost to dispose of the waste at the Barnwell site is based on an average disposal fee of $1,680 per cubic foot for radioactive hardware.
4.3.3 Duratek Processing/Burial Costs The cost to transport waste to the Duratek central volume reduction facility in Oak Ridge Tennessee are based on a transport distance of 762 miles at a rate of $2.36 per mile. Waste processing at the Duratek central volume reduction facility was not included in this estimate because there was not a significant cost advantage to waste processing.
Typical unit disposal cost factors are listed in Appendix A-3.
4.4 Remediation Methods The goal in choosing remediation methods is to select the minimum cost option to accomplish a task There are many factors which need to be considered when selecting a method such as contamination levels, degree of penetration of contamination into substrate material, equipment cost, support equipment costs, material and chemical costs, the generation of secondary waste volumes (waste in addition to the removed contaminated material), processing rates, labor requirements, and applicability to various tasks. Typical decontamination processes are summarized in Table 4-6. For each decontamination method, this table shows application information, the process cost per square foot of area decontaminated, and the amount of secondary waste generated. These unit factors are applied to specific areas or equipment requiring remediation to determine the most cost-effective process.
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Decommissioning Cost Estimate Cornell University Table 4-6: Decontamination Methodology Comparison Penetration I Process Secondary depth Crew Cost Waste Volume Methodology Application (in) Size ($/ft (ft'/l 000 ft.)
McDonald U-5 Scabbler Floor concrete 1/4 2.0 $0.98 0 McDonald U-5 Scabbler Floor concrete 1/2 2.0 $1.86 0 McDonald 3WCD Scabbler Wall concrete 1/8 2.0 34.45 0 Blastrac IOD Shot Blaster Floor concrete 1/16 1.1 S0.43 0.53 Blastrac OD Shot Blaster Floor concrete 1/8 1.1 $0.54 0.53 LTC 10-6OPn Special All surfaces 1/32 1.3 $1.71 0.53 Vacuum Blaster LTC 10-6OPn Special Al surfaces 1/16 1.3 33.08 0.53 Vacuum Blaster EDCO CPU-OC Floor Plane Floor concrete 1/2 2.0 $1.62 0 C02 Blasting All Surfaces 0 2.0 34.52 0 Hydrolaser (5-10,000 psi) All Surfaces 0 2.0 30.91 9.07 Hands-On-Decon Non-Porous surfaces 0 1.0 32.01 8.33 4.5 Radioactive Waste Volume Reduction Costs The volume reduction processes analyzed for use are summarized in Table 4-7.
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.
Rev 1 Page 27
Decommissioning Cost Estimate Cornell University Table 4-7: Volume Reduction Methodology Cost Information VR Methodology l
Applicability I Transport Container Type [ Total VR Cost (Sb)
Super Compaction Dry active waste B-25 for Envirocare S5.59 20 lb/ft Disposal Incidental Lead Decontamination Bricks and Sheet Custom Box $7.25 Survey & Release Low Density Waste 55 Gal Drum $1.45 Low Density Drums Survey & Release Waste at greater than B-25 Box S0.66 Medium Density Boxes 20 7< 60 lb/ft 3 Survey &Release Waste at greater than B-25 Box $0.52 High Density Boxes 60 b/tV 4.6 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 4-8: Decommissioning Cost Estimate Selected Unit Cost Factors Unit Cost Factor Unit Cost Rate Units Radioactive Soil and Rubble Disposal at Envirocare of Utah $189.81 cubic foot Waste Transportation to Envirocare of Utah $2.36 mile Transportation Distance to Envirocare of Utah 2,180 miles B-25 Waste Disposal Container Cost $843.75 each Management and Supervision $116.50 hour Engineer $97.08 hour Radiation Protection Supervisor $101.94 hour Laborer Foreman $44.54 hour Administrative Assistant $42.00 hour Instrument Technician $66.00 hour Radiation Protection Technician $66.00 hour Laborer $40.95 hour Fee 20%
Rev 1 Page 28
Decommissioning Cost Estimate Cornell University 4.7 Final Surveys Final survey costs are estimated based on the facility radiation survey information presented in NUREG- 1757, MNSS DecommissioningStandardReview Plan (Ref.
6-11). The number of sample points for the various areas being surveyed and the type of survey being performed were determined. The time to perform each of these surveys is estimated, and the product of these two items is the labor time to perform the surveys. Equipment and material cost to perform the surveys is added along with staff support costs to determine a total cost. The survey requirements are based on NUREG-1575, Multi-Agency RadiationSurvey and Site InvestigationManual (MARSSIM) Ref. 6-10). 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.
5.0 FACILITIES, RADIOLOGICAL CONDITIONS AND DECOMMISSIONING SCENARIO Decommissioning of the Ward Center requires that residual radioactive materials be removed from the site to allow removal of the decommissioned facilities from the NRC license. For the purposes of this cost estimate, the end of the decommissioning project occurs when the Ward Center has been remediated to release limits, the Final Status Survey has been performed, documented and submitted to the NRC.
5.1 Remediation Summary Remediation will be required for the Ward Center, 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.
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Decommissioning Cost Estimate Cornell University Table 5-1: Ward Center 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.
TRIGA Reactor Empty water from reactor tank. Remove activated reactor core and vessel internals and reactor vessel. Cut out activated concrete (5-ft thick layer) from bioshield monolith surrounding reactor tank and disposal as radioactive waste.
Beam Tubes Remove activated beam tubes including shields. Cut out a 1-foot thickness of activated concrete surrounding beam tubes.
First and Second Floors Remove contaminated portions of HEPA and HVAC systems. Remove demineralizer system and heat exchanger. Remove contaminated portions of the rabbit system and fume hoods.
Reactor complex Perform a general area clean up and remove all contaminated equipment and materials.
Office Areas & Labs Perform a general area clean up and remove all contaminated equipment and materials.
ZPR Reactor Remove contaminated filter and ion exchange column.
S.1.I TRIGA Reactor
- The reactor core, core stand, reflector, fuel rack and other items inside the reactor pool will be removed and shipped for disposal.
- The reactor pool will be emptied and the reactor pool surface decontaminated to eliminated easily removable radioactive material.
5.1.2 TRIGA Bioshield & Beamports
- The thermal column will be removed for disposal.
- The beam port plugs will be removed for disposal.
- The activated concrete in the bioshield concrete monolith surrounding the reactor core will be removed (Figure 5-1). It was estimated that all the high density concrete would require removal plus 3-feet of regular concrete under the pool and up to 2-feet of rock under the pool in some areas. An activation analysis performed by Georgia Tech and reported in Appendix C of the "Characterization Survey Report" (Ref. 6-8) indicates the concrete removal required. In general about five feet of concrete surrounding the core will be removed.
- The activated beam tubes including shields will be removed including removal of a 1-foot thickness of activated concrete surrounding beam tubes. All the beam tubes are in the high density concrete that is being removed anyway.
Rev Page 30
( ( Decommissioning Cost Estimate Cornell University Figure 5-1 Ward Center Activated Concrete A
ZPRIPit A
ELEVATION A-A PLAN VIEW Rev Page 31
Decommissioning Cost Estimate Cornell University 5.1.3 Reactor complex There are several different types of areas to be decommissioned in the Reactor Building. The activities for the major areas are outlined below:
- There will be a general area cleanup to remove all unnecessary materials from the facility prior to decontamination and demolition.
- All other process equipment will be removed and shipped directly for disposal as radioactive waste. This includes the heat exchanger, ion exchange system, and recirculation pumps, piping, drain piping and rabbit system, etc.
- Equipment and materials in the hoods on the upper level will be removed and shipped directly for disposal as radioactive waste. The hoods will be decontaminated, removed from the facility, surveyed for free release and disposed of as salvage or clean waste.
- The floor surfaces and structural surfaces are assumed to be free of contamination. The ventilation systems will be surveyed, decontaminated if required and released for disposal as salvage, or disposal as clean waste. The HEPA filters will be removed from the ventilation system, surveyed, decontaminated if required and released for disposal as clean waste.
- The reactor tank concrete remaining after activated concrete removal will be surveyed for free release. This concrete will then be left in place.
5.1.4 Office and Laboratory Wing
- The offices and laboratories and miscellaneous equipment will be surveyed in place for release.
5.1.5 ZPR Reactor
- The contaminated filter and ion exchange column will be removed and disposed of a radioactive waste. The remainder of the ZPR will be surveyed in place for release.
5.1.6 Outdoor Areas
- The sanitary and storm sewers will be surveyed at accessible areas and released for continued use. In addition, soil sampling, and license termination surveys of paved areas and unpaved areas around the Reactor Building will be performed in accordance with current regulatory requirements.
Rev Page 32
Decommissioning Cost Estimate Cornell University 5.2 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 (MARSSM), (Ref. 6-10). The surveys will be performed in accordance with specifically developed plans and procedures.
5.2.1 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 5-2.
Table 5-2: Typical Final Survey Instrumentation Detector l Calibration Instrnment/Detector l Type l Radiation Detected Source I Use Ludlum Model 2350 wt. Direct alpha and direct 43-68, 43-98, 43-94 or Gas-flow proportional 99Tc (beta surveys; Beta 43-106 detector (126cm 2) Alpha or beta 230 Th (a) scans on solid surfaces.
Ludlum Model 2350/
SP-1 13-3m or SP- 99Tc (Direct beta pipe 175-3m GM Pipe Detector Alpha or beta 2Th (a) survey.
Direct beta surveys; Ludlum Model 2350 wt. Shielded GM Beta scans on solid 44-40 detector (15.5cm 2) Beta 99Tc (suritces.
Ludlum Model 2350 wt. Gamma exposure rate 37 44-2 or 44-10 detector Nal (TI) Scintillator Gamma 1 Cs and gamma scans.
Eberline Teletector Gamma exposure Model 6112B Ion Chamber Gamma 6Co (y)rate Eberline SAC-4 Scaler 230 Counter ZnS scintillator Alpha Th (a) Smear counting Eberline BC-4 Scaler Counter Shielded GM Beta 99Tc Smear counting Tennelec Planchette Shielded Gas-flow 2
Counter or Equal proportional Alpha and Beta 99Tc (1), Th (a) Smear counting EG&G NOMAD Nuclide identification Gamma Spectrometer or Gamma energy and and quantification of Equal1 HPGe intensity Mixed gamma soil and sand samples.
Rev 1 Page 33
Decommissioning Cost Estimate Cornell University
6.0 REFERENCES
6.1 10 CFR 50.82 Terminationof License, part (b)for Non-PowerReactor Licensees 6.2 10 CFR 20 Subpart E - Radiological Criteria for License Termination 63 NUREG 1537, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, February 1996 6.4 R.A. Means Company, Inc., 2003, Means Building Construction Cost Data, 2001, 61st Annual Edition 6.5 NUREG/CR-1756, Technology Safety and Costs of Decommissioning Reference Nuclear Research and Test Reactors, March 1982 6.6 Final Safeguards Report to the U.S. Atomic Energy Commission for the Cornell University TRIGA Reactor, May 1961 6.7 Supplement No. 1 to the Final Safeguards Report to the U.S. Atomic Energy Commission for the Cornell University TRIGA Reactor, September 1980 6.8 Characterization Survey Report for the Ward Center for Nuclear Studies at Cornell University, Facilities Inventory Bldg. No. 2061, March 2003 6.9 10 CFR 20.1402 Radiological Criteria for Unrestricted Use 6.10 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-97-016 6.11 NUREG-1757, Consolidated NMSS Decommissioning Guidance, Decommissioning Process for Materials Licenses, September 2002 Rev 1 Page 34
Decommissioning Cost Esimate Conell UniveIsity APPENDIX A- 1 Contaminated Waste Volume Summary
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i Ii APENDIX A-1 I CONTAMINATED WASTE VOLUME
SUMMARY
Decon* Barnwell Generated*
Area Bamwell Decon*
Description Direct Bury Envirocare Envirocare CODE Waste Volume Waste Volume Envirocare Direct Bury AREA Waste Volume Waste Volume Total
. TR1GA Reactor (tA3 (ftA3) (ftA3)
Waste Volume Waste Volume (f6- 3) 2 TRIGA Bloshleld & Beam Ports O 120 (ft3) (ftA3) 4 0 3 Reactor Bay 0 24 25 149 29 0 4 Office & Laboratoy Wing 0 a 3,294 3,347 0 12 0 5 Zero Power Reactor 0 31 1,14& 1,158 0 21 0 TOTALS: 0 4 52 0 1 2 144 80 7
- Notes:
22 4,48 4,714 .
I Decon Waste Volume: This Isthe volume of-waste generated directly I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
by a decontamination 2 Generated Waste Volume: This is Is a function of labor hours for eachthe volume of protective clothing waste generated by all operations on activity. site and
Decommissioning Cost Estimate Cornell Univezsi y APPENDIX A- 2 Contaminated Waste Disposal Cost
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APENDIX A.2 CONTAMINATED WASTE DISPOSAL COST Decon Barnwell Generated Area Barnwell Decon Envirocare Description Direct Bury Envirocare Total Disposal Envirocare Direct Bury Disposal Disposal Waste Cost Disposal Disposal I TRIGA Reactor Cost Cost Disposal
$0 Cost Cost 2 TRIGA Bloshleld & Beam Ports $201,768 $733 Cost
$0 $0 $5,182 3 Reactor Bay $40,068 $6,037 $207,683
$0 $0 $675,878 4 Office & Laboratory Wing. $0 $2,561 $721,982
$0 $0 $235,126 5 Zero Power Reactor $0 $6,370 $237,686
$0 $4,351 $0 TOTALS: $0 $804 $261 $10,721 Note: $0 $241,836 $16505 $410 $1,478
- 1. Shading Indicates a named field $4,812 $916,596 linked
- 2. Direct burial &generated waste shippedto another spreadsheet. $1,179,5 to Bamwell.
WASTE DISPOSAL PACKAGING
& SHIPPING COST Decon. Barwell Generated Area Barnwel Decon Envirocare Description Direct Bury Envirocare Total Pack & Enrirocare Direct Bury Pack & Pack & Pack & Waste Ship Ship Pack & Pack &
cost Ship Ship I Cost Cost Ship Ship TRIGA Reactor Cost cost 2 TRIGA Bloshleld & Beam Ports $0 $235 Cost
$17 $0 3 $0 $47 $120 $373 Reactor Bay $140 $0 4 $0 $0 $15,707 $15,894 Office & Laboratory Wing $60 $0 5 Zero Power Reactor $0 $0 $5,464 $5,524
$148 $101
$0 $0 $0 $249 -
TOTALS: $19 $6
'Notes: $0 $282 $10 $34
$384 $107 I Shading indicates a named field linked
$21,301 $22,074 2 to another spreadsheet.
B-25 Box of waste to Barnwell equal to:
$2,119
Decommissioning Cost Estimate Comell University APPENDIX A- 3 Waste Shipping Container Cost I
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APENDIX A-3 WASTE SHIPPING CONTAINER COST Total B.25* Waste Area Waste Waste Container Description Volume Contalners Cost (ftA3) (Es.) M$
ITRIGAReactor 149 1.7 $1,395 2 TRIGA Bloshleld & Beam Ports 3,347 37.2 $31,378 3 Reactor Bay 1158 12.9 $10,859 4 Office & Laboratory Wing 52 0.6 $490 5 Zero Power Reactor 7 0.1 $67 TOTALS: 4,714 53 $44,719
- Notes:
I The number of waste containers Is rounded up to next full container.
UNIT DISPOSAL COST FACTORS Decon waste disposal rate forBarnwell: $1,q81A0 per cubic foot DAW waste disposal rate for BarnwelI: $1,681A0 per cublc foot DAW waste disposal rate for Envirocare: $189.81 per cubl foot Estimated mileage rate to Barnwell: $2.38 per mile Estimated transport distance to Barnwel: 762 miles Estimated mileage rate to Envirocare: $2.36 per mile Estimated transport distance to Envirocare: 2,180 miles Average direct bury waste densIty: 160.0 blcubic foot Average generated waste density (Envirocare waste): 25 bicublc foot Truck transport waste weight limit: 44,000 pounds Truck transport waste volume lmit: 12 -25 Boxes 8.25 box Internal volume: 90 cubic feet tImated cost of used -25 shipping containers: $543.75 each Locel industrial Waste Landfill Shipping & Disposal Rate: $27.30 per cubic yard Labor rate for shipping: $66.00 rer hour
Decommissioning Cost Estimate Comell jnivemity APPENDIX A- 4 Waste Disposal Labor Estimate I
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APENDIX A4 WASTE DISPOSAL SUPPORT LABOR ESTIMATE B-25 Radloactive* Waste Area Waste Waste Shipment Description Containers shipments Labor
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.__ _ _ _ _ _ _ _ (E (Ea.) (m an hr) 1 TRIGAReactor 1.7 0.1 2.5.
2 TRIGA Bloshleld & Beam Ports 37.2 3.1 58.1 3 Reactor Bay 12.9 1.1 19.4 4 Office & Laboratory Wing 0.6 0.0 0.9 5 Zero Power Reactor 0.1 0.0 0.1 I I TO~~~~~~~~~1TALS: 53.0 5.0 80.0 Note I The number of waste shipments Is rounded up to next full shipment.
Estimated waste loading operator time: 4 hr per load Estimated HP Tech time per red or mixed waste load: 4 hr per load Estimated HP shipper time per rad or mixed waste load: 8 hr per load Estimated clean waste shipping volume limit i 1176 ftA3 per load Estimated radwaste shipping volume limit: 12 B-25 Boxes WASTE DISPOSAL CASK COSTS Uners & Radloactive' Waste' Area Cask Cask Shipment Description Rental Rental Labor
[(Ea.) Cost iman-hr) 1 TRIGA Reactor 2 $14,400 72 2 TRIGA Bloshleld & Beam Ports 0.0 0 3 Reactor Bay 0.0 0 4 Offlce & Laboratory Wing 0.0 0 6 Zero Power Reactor 0.0 0 TOTAL 2.0 $14,400 72
'Notes:
I The number of waste shipments Is rounded up to next ful shipment.
Decommissioning Cost Estimate Cornell University APPENDIX A- 5 Contaminated Waste Disposal Summary
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SUMMARY
LOG CODE B-25' Waste Radioactive' Total Waste Waste Waste Container Waste Volume Waste Shipment Containers Cost Shipment (ftA3) Shipments Labor 1 (ea.) ($) Labor 149 (o .) (man-hr) 2 1. $15,795 2.1 cost 3,347 37.2 74.5 $4,917 3 .1,158 $31,378 3.1 56.1 4 12.9 s10,859 1.1 3,705 52 0.6 -19A $1,282 5 7 $490 0.0 0.9 Total 0.1 $87 0.0 $58
-4,714 53.0 0.1 $8
'Notes: $58,590 7.0 151.1 I The number of waste containers $9,970 are rounded up to next fuN container.
2 The number of waste shipments are rounded up to next full shipment.
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Decommissioning Cost Estimate Cornell nivesity APPENDIX A- 6 Building Survey Labor Summary r (
C' (-K' Ci APPENDIX NON-IMPACTED BUILDING A-6 AREA SURVEY ENTER BELOW ENTER SURVEY ENTER OPTNL ENTER ENTER ENTER ENTER ENTER BUILDING PACKAGE AREA ENTER LOC ROOM AREA AREA AREA FLOOR+ U. WALL+
NAME NUMBER REQRD WIDTH LENGTH ENTER SURVEY CODE DESCRIPTION HEIGHT L WALL CEILNG DIRECT BELOW BELOW ? BELOW BELOW Survey PACKAGE URVEY 4IWard BELOW BELOW SURVEY SURVEY Center Exterior (ft) if Sketchs PREP LABOR Exterior (e) CODE CODE Y 100A 124.0 each ye) e) 40.0 2 a 5 8 24.4 TOTALS a 241
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APPENDIX A-6 IMPACTED BUILDING AREA SURVEY 2 Reactor Blo*hleld Exterior Exterior 4 Gamma Cell y 22.0 27.5 Eterlior Exterlor 22.0 2 5 4 Basement y 12.5 3 8 42 4 lntvoductory Lb ow tp. I 1.0 16.0 1 4 Y 4 2 8 Basement I Introduto LaboratorytHo.2 '15.33 24.7 13.0 22 4 N 1 4 Basement 3 15.33 21.0 13.0 8 24 4 Dark Room 1 4 B nt N 600 15.3 1 5 Cotm Room 13.0 1 4 4 Basement H 15.33 18.0 10 Hall M Coridor No. 1 13.0 1 4 4 Basement Y B.00 83.0 14 6 Machine shop 13.0 1 4 4 Basement Y 1933 23.3 8 34 6-Nail Hllwaynr Room 13.0 1 4 4 Basement N 5.00 11.00 8 26 S Chemit Laboratory 13.0 1 4 4 Basement H 2500 32.33 .
2A Cold WorkAre 13.0 1 4 4 Basement Y 11.33 15.7 2 2-H*l Hallway near Room 2 16.5 1 4 Basement N 5.33 a 8 2m Set-Up Rom 13.3 13.0 1 2 4 Basement N 10.7 4 2C Gammi Cell 13.0 1.0 1 10 4 Basement Y 9.00 4 ELEV ElevatorShaft 9.0 1.0 1 1' 4 Basement N 6.00 5 8 stairW stahwayNo.1 8.0 41.8 3 20 4 Basement N 8.83 6 134hall Hallway ner Room 13 13.3 14.0 2 17 4 Basement N 8.00 a 13 Mens Tonet No. 1 10.0 1S.0 1 10 4 Basement N 11.33 4 R12 hotope& Fuel 8torage Room 18.7 9.0 1 9 4 Ba Y 6.00 4 R3 ReaetorEqulpiment oom 19.8 13.0 1 131 4 Basement Y _ 16.1t 4 8 R344all H"s2ynearRoomR3 19.8 14.0 1 2 4 Basement _ N 6.25 4 8 Containment Ar 25.5 13.0 1 23 5 Basement Y 48.00 4 ZPR Pit 70.0 45.6 I 12 2 B"sement y 13.50 6 8 SPR Pool 14.0 20.0 3 13 4 Y 6 8
-Basement 7 Laboratory 11.00 11.5 25.0 32 4 Y 3 6 Basement 74He11 HallwnerRoom7 18.33 18.3 13.0 8 29 4 N 1 4 Basement 9 6.00 39.0 13.0 8 23 4 Elet-tical Utility Roo 1 4 Basement Y 10.00 18 18 11 Mechanical Utlt Room 13.0 1 4 4 Basement Y 14.33 18.1 8 20 15 Waste Hold41p Tank Room 13.0 1 4 4 Basement Y 1200 160 8 22 17 TransformerVault 10.0 1 4 4 Basement N 12.00 21.0 8 20 Star #S StairwayNo. 6.0 1 4 4 latFloor N 4.00 6.o 14 106 staff Offle 8.0 2 5 4 letFlor Y 11.17 15.3 12 102 SuperrsorsOfflee 9.0 1 4 4 1st Floor N 15.30 15.5 8 20 100 Lobby 9.0 1 4 4 lstFloor N 12.83 15.3 13 101 HP OMce 9.0 1 4 4 istFloor Y 11.92 15.3 12 10S StaffLab-OffloeNo.1 9.0 1 4 4 1stFloor HN 14.75 15.3 8 20 Hall #2 Corridor No. 2 9.0 1 4 4 . 1stFloor N 0.00 72.0 13
- 112 statf Lab-Otce No. 2 9.0 1 4 4 lstFloor Y 12.17 18.3 2 112-Hall HallnesrRoomli2 9.0 . 1 4 4 1stFloor N 6L00 24.5 8 21 116 talLaWbOMceNo.3 9.0 1 4, I1 4 1st Floor 118 Class, Conference & seminar N 11.50 183 9.0 12 N 1 4 28.00 31.9 9.0 13 1 4 N
24]
I (C o( C APPENDIX A-6 IMPACTED BUILDING AREA SURVEY 4 lotFloor 110 J"nltmCloset 4 let Floor N 3.00 4.0 114 Pantr 9.0 1 4 4 lot Floor N 4.00 8.0 81 108 Women's Tollet 9.0 1 4 4 la Floor Y 10.00 11.3 8 104 Stock & oe Room No. 1 9.0 1 4 4 ltFloor Y 7.83 11.3 8 18 ELEV Elevator Car 9.0 1 4 4 letFloor Y 4.00 5.0 8 1 StalrF1 StalrwavyNo.1 7.0 1 4 4 lst Floor N 8.83 13.3 8 10 103 Stoc& a Room No. 2 11.0 2 a 4 et Floor Y 7.83 11.3 16 107 Men'a Tle No. 2 11.0 I 4 4 lt Floor N 11.33 13.7 8 18 109 Eltrunlos Room 11.0 1 4 4 iat Foor N 12.33 18.3 11 10mmall Halway near Room 109 11.0 1 4 5 I tFloor 800 13.0 13 111 ZPRLaboratoq 11.0 1 4 5 lat For y 2.00 31.0 1I 113 ZPR Con Room 11.0 1 4 a lot Foor N 18.50 24.0 8 32 115 Closet 9.0 1 4 a lst Floor N 3.00 &8 18 117 ZPR Enty Hag 9.0 1 4 5 let For N .25 17.5 ZPR to" Ars 11.0 1 4 5l 1tFloor Y 12.00 13.3 1 ZPRTankkArsa 11.0 1 4 4 lotFloor N 13.50 14.0 8 20 Stsfr#3 ft! No.3 Ler 11.0 2 _
4 lutFloor Y 8.00 10.3 18 Stalr#3 8tu r No.3Patfo 7.0 1 4 4 letFloor N 2.75 28.5 8 17 Stalr 3 StlrlmvNo.3,Upper, 2.0 1 4 4 istFloor N 2.75 65 12 stalr #2 Stslvy No. 2, 4.0 1 4 4 2nd Floor N 600 10.5 81 204 Lob4Ofioe No. 2 11.0 1 4 4 2ndFloor Y -12.50 153 9 202 Lab.OletNo.3 11.0 1 4 4 2ndFloor N 12.50 13.8 8 20 201 mab.ofiNo.4 11.0 1 4 4 2nd Floor N 10.19 12.6 12 203 Lab-Oofl No. 11.0 1 4 4 2nd Floor N 12.50 15.3 11 206 Lab-Otloe No. 1 11.0 1 4 4 2nd Floor N 14.17 16.3 12 Hal 3 Corrdor N 3 11.0 1 4 4 2ndFloor Y 5.00 27.5 13 stairpi EtwlrwaNo.1 11.0 1 4 4 2nd Floor N 8.83 13.3 8 20 205 Lab4.mce No. 8 2.0 1 4 4 2nd Floor Y 11.33 14.2 11 205-Hall Halby near Room s 11.0 1 4 4 2ndFloor. N .00 14.2 8 20 Topof Gem Ce 11.0 1 4 4 2nd Floor N 11.00 13.0 10 R.202 Isotope Handllna Roorn 11.0 1 4 a 2nd Floor Y 12.33 14.5 11 R-205 Above ZPRAre 9.0 1 4
- 4. 2nd Floor N 17.80 21.0 8 2 R.201 Latboraory 11.0 2 5 4 2nd Floor N 9.17 19.5 24 R-203 Obseation Room 9.0 1 4 4 2nd Floor Y 16.17 19.5 12 R205 8PR Control Room 9.0 1 4 4 2nd Floor N 19.50 21.3 8 2 Stair#2 StairwayNo. 2 9.0 1 4 N 6.oo 10.5 1 2.0 1 4
. 9
. ~~~~~~ ~ ~~~TOTALS 248 1,425
Decommissioning Cost Estimate
- - University
~~~~~~~~~~~~~~~~Cornell APPENDIX A- 7 Outdoor Area Survey Labor Summary
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APPENDIX NON-IMPACTED OPEN LANDA-7 PAVED AREA SURVEY ENTER BELOW ENTER ENTER SURVEY ENTER ENTER OPTIONAL SURFACE ENTER AREA PACKAGE AREA AREA Random SURVEY LOC TYPES REQRD WIDTH LENGTH 10%
CODE BELOW DESCRIPTION Survey PACKAGE SUR BELOW ? BELOW BELOW Sketchs 4 AsphalttTAasume Area 65 PREP LABOR feet by 250 fWt near Reactor (YIN) (It) (ft)
Bulding t (each) Mrs) Hours Yl 651 2501 3 4 5.1 TOTALS 3 4 5.1
APPENDIX A-7 IMPACTED UNPAVED OPEN LAND AREA SURVEY ENTER BELOW ENTER SURVEY OPTIONAL ENTER ENTER ENTER SUB ENME SURFACE PACKAGE AREA LOC AREA AREA SURFACE RandoM DIRECT TYPES REQRD WIDTH LENGTH ACTIVITY Survey CODE BELOW DESCRIPTION SURVEY BELOW ? BELOW BELOW DEPTH Sketcho 4 Soll , soll Under Reatr Buiding LABOR (N 00 ft ft each Mm)
Y 55 901 3 2 25 TOTALS: 25
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I APPENDIX NON-IMPACTED OPEN LAN A-7 UNAVED AREA SURVEY ENTER BELOW ENTER OPTIONAL SURFACE ENTER SURVEY ENTER ENTER ENTER LOC AREA PACKAGE AREA AREA TYPES Random Rndom SURVEY CODE BELOW DESCRIPTON REORD WIDTH LENGTH 10%
SuMy Survey PACKAGE 4 Gree- & BELOW ? BELOW BELOW SURVEY 20 moterbordwraroundRewotuildt" G (YIN) Sketchs swetd PReP (I) (I) (ech) LABOR
___, Hour. (iMM) (")
Y 65 250 3 1.001 TOTALS 4 5.8
.... 3 I I 3 1.0l 4 S.s
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APPENDIX A-7 DRAIN & SEWER SURVEY CATCH BASIN & CLEAN-OUT SURVEY BASIN SURVEY DURATION (hrs): 4 BASIN SURVEY CREW SIZE (men): I ENTER ENTER SURVEY BELOW ENTER BASIN PACKAGE SURVEY OPTIONAL AREA DIAMETER REQRD PACKAGE SURVEY LOC DESCRIPTION BELOW ? PREP LABOR CODE BELOW (ft) (YIN) (hrs) (hrs) 4 Manhole on 24" Storm Sewer to NW of Reactor Building 5.0 r 4 8.0 4 Manhole on 24" Storm Sewer to SE of Reactor Buildng 5.0 N 4.0 4 Manhole on 24 Sanitary Sewer to Westd of Reactor Building 5.0 Y 4 8.0 4 Manhole on 24" Sanitary Sewer to North of Reactor Building 5.0 N 4.0.
TOTALS 8 24 DRAIN PIPE SURVEY PIPE SURVEY RATE (ftthr): 40 PIPE SURVEY CREW SIZE(men):. 3 ENTER .ENTER ENTER SURVEY S O>PTIONAL ENTER PIPE PIPE PACKAGE SURVEY LOC AREA DIAMETER LENGTH REQRD PACKAGE SURVEY CODES DESCRIPTION BELOW BELOW ? PREP LABOR BELOW BELOW (ft) (ft)h) (h) 4 Storm Drain 24 150 Y 4 15.3 4 SantarySewer 24 150 Y 4 15.3
-TOTALS 83
Decommissioning Cost Estimate Cornell Univensity APPENDIX A- 8 Instrument Lease Charges
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APPENDIX A-8 Table COMMERCIAL CLIENT INSTRUMENT COSTS 6 D&D Months Duration 2.0 Final Survey Months Duration 0.5 Characterization Survey Months Duration CHAR SURVEY D&D FINAL SURVEY D&D D MONTHLY NUMBER NUMBER NUMBER FULL ALTERNATE ITEM INSTRUIMENT COMMS:ZAL INSTRUMENTS INSTRUMENTS INSTRUMENS PROJECT MONTHLY No. DESCRIPTION RENTAL RATE REQUIRED REQUIRED REQUIRED DURATION DURATION RADIATION PROTECTION AND MEASUREMENT INSTRUMENTATIONISYSTEMS _ .
I Becton Dickson - TRITON, Model III Tuithim Monitor: $737 2 MICROSPEC-2, Nal(TI) Gamma Spec System W/Detector, PC, Software, Case &Accessories: S524 __._.
3 GENI PC, Gamma Spec System W/Detector, PC. Software. Case &Accessories Model 4610J GC4511 $5,546 1 1 1 Y 4 INSPECTOR, Portable Gamma Spec WIDetedor. PC. Software, M-1 Insitu Cal, Tripod & Accessories: $4,037 5 Q2 Low Level Waste Assay System WI(3) HPGe Detedors, PC, Vault Shield WISCale, Turntable & Acc.: $4,974 6 GTSD Mod. Q2 Waste Assay System W/(3) HPG. Detectors, PC. Modular Shield W/Scale, Turntable & $2998 7 DCA - Portable Area MonItor 3090-3: $46 _ .
8 Ebetline -FASTRACK n DosWety Wh PC, Printer, lea DR200 lea DR200R, 30ea DD100 & $821 9 Eberlne - Dosimeter Meter Reader Model DR-200: $216 .___.
10 Ebeffine -Dosimeter Res e Check Station Model DR-200 OPT7: $553 . . . _.
11 Ebedlne -FASTRAC 11,PC Dose Mawgeet Prgram ith Utf: $216 .
12 Ebedline -Dital Dosimeter Model DD-100: 552 13 Ebewline - Personal Contamination Monitor, Model PCM-1B w/ Accessories: $2590 14 Ebedine - Personal Contamination Monitor, Model PCM-1C w/ Accssores: $3.353 15 Eberflne - Personal Contaminaion Monitr Model PCM-2 Base Unit: $4.193 16 Ebedne- Portable Aha Counter, Model SAC-4: $194 I . _ Y 17 Ebedlhe- Portable Beta Counter, Model BC-4: $162 1 1 Y 18 Ebedln - Portable GM §M srmKModel E-520 wI HP-270 & SK-I: $258___________
19 Eberlne - Portable GM Survy tun Model E-520 WI HP-260 &SK-1: $272 _
20 Eberlne - Portable High R e n Chamber, Model R07 W/Low & i Detectors 5 Extension $
S179 :
21 Ebedfne - Portable Ion Chamber Instrument Model R02: $78 _ ___
22 Ebedlne - Portable Ion Chamber stum Model R02A: $78 . _
23 Eberline - Scintillation Portal Monitor, Model PM-7 WIPC, Software, Calibration Jb. Remote ALam & 60 $3,295 .
24 Ebelne - Tool Contamination Monitor Model TCM-2 with e Detector: $1,654 . _
25 Ebedlne - TELETECTOR Gamma Dose Rate Meter Model 61 12B w/ Accessories: $200 26 EG&G -NOMAD, Portable PC Based Gamma Spec Anlyzer W/HPGe Detector, PC, Software & Acc.: $1,292 . _
27 Void $383 28 F&J - BUCK Pmp K5t 6 Personal Air an, Calibrator Chaqe & Case: $908 . _
29 F&J - Model HV-1 Hig Volhme Air Samplerwith Sample Head: $56 1 . _
30 F&J - MODEL LV-1, Low Volime Air mler with Sample Head: $46 2 Y 31 F&J - MODEL LV-14M GOOSENECK LOW VOLUME AIR SAMPLER WITH SAMPLE HEAD: $106 ___ ___
32 LUDLUM - MODEL 12 SURVEY METER WITH 44-9 PANCAKE GM PROBE & CASE: 583 33 LDLUM - MODEL 12 SURVEY METER WITH 43-5 ALPHA SCINTILLATION. PROBE &CASE: $98 - _
34 LUCLUM - MODEL 19 MICRO R METER WITH HARD CASE $44 .1 1 1 Y 35 LUDLUM - MODEL 177 ALARM RATE METER WnlH 44-9 PROBE AND CASE: $41 1 3 3 Y 36 Ludlurn - Model 239-1F Floor Monitor Cart W/O Model 12 Meter &WIModel 43-37 425 cne Gas Flow D$ S163 . 2 _
37 Ludlun -Model 2350 Data Logger t WKe d Barode Reader Pelican Case & Detectors # 38 Thm $180 3 3 4 :
38 Ludlun - Model 2350 Data Logger Kit Wld, Barcode Reader, Pelican Case (No Detectors): $114 _
39 LUDLUM - MODEL 43-5 ALPHA SCINTILLATION DETECTOR: 668 I 3 2 Y ._ _
40 LUDLUM - MODEL 43.68 100 am2 GAS PROPORTIONAL DETECTOR: $59 _
41 LUDLVM - MODEL 44-1 BETA SCINTILLATION DETECTOR $60 _
42 LUDLUM - MODEL 44-2 HIGH ENERGY GAMMA SCINTILLATION DETECTOR: $60 _
43 LUDLUM - MODEL 44-38 ENERGY COMPENSATED GM DETECTOR: $18 _ _
( ( N APPENDIX A-8 Table COMMERCIAL CLIENT INSTRUMENT COSTS 6 D&D Months Duration 2.0 Final Survey Months Duration 0.5 Characterization Survey Months Duration CHAR SURVEY D D FINAL SURVEY D4D MONTHLY NUMBER NUMBER NUMBER FULL ALTERNATE ITEM INSTRUUENrr COMMERCIAL INS TRnENTS INSTRUMENTS INSTRUMENTS PROJECT MONTHLY No._ ____ ____ ____ ____ ____ ____ ____ ____DESC_ _7O__- RENTAL RATE REQUIRED REQUIRED REQUIRED DURATION DURATION 5_ 4_ _0_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __.__ _
44 LDLUM - MOOEL 44-40 SHIELDED GM PANCAKE DETECTOR: S40 4 LDLUM - BETA AIR MNITOR (CAM). MODEL 3332: .$472 ___. _
46 1LUDLUM - MODEL 77-3 STRETCH SCOPE XTELETTOR). 5211 .
47 NE TECHNOLOGY - MODEL CM7A CONTAMINATION MONITOR WITH DPSHA PROBE: $463 .___
48 Padcard - PC Based IWd Siilan Counsr W/ Aloha I Beta Oplm & Accessoes / A2550P2: S1,684 49 Quatr*ad - SCOUT-1, Nal(TI) Gamma Spec Syem WlDetedor, PC, Software, Case & Accessories: S1.308 50 REUTER-STOKES - PRESSURIZED ION CHAMBER RSS-122: $886 51 TENNELC - MODEL LB S100-2080411 PC BASED ALPHAIBETA COUNTER SYSTEM: $1,691 RADIATION PROTECTION AND MEASUREMENT INSTRUMENTATION/SYSTEMS 52 TSI -MODEL 8020 PORTACOUNT, RESPIRATOR FIT TESTER: $588 53 XETEX - MODEL 330A TELESCAN DOSE RATE METER WI CASE & ACCESSORIES: 5388 INSTRUMENTATION SOURCES (MAY BE CHARGED AS CONSUMABLE OR RENTAL1 54 GAMMA SPEC. NIST TRACEABLE MIXED SOIL EQUIVALENT I LITER MARINELLI: 568 1 1 1I Y .
55 GAMMA SPEC. NIST TRACEABLE MIXED WATER EOUIVALENT I LITER MARINEWI: $62 .
56 GAMMA SPEC. NIST TRACEABLE MIXED FILTER PAPER EQUIVALENT: $62 1 1 1 Y .
57 GAMMA SPEC. NIST TRACEABLE MIXED POINT SOURCE: $60 .
58 02 GAMMA SPEC. NIST TRACEABLE MIXED 30 INCH UNE SOURCE: $228 _ .
59 Q2 GAMMA SPEC. NIST TRACEABLE MIXED 6 INCH QC SOURCE: $166 .
60 ALPHAIBETA COUNTER BC-4, NIST To.99 47mm LINEARITY 4 SOURCE SET: $264 .
61 NIST To-99 47mm SOURCE PER EACH (1, 10 100 OR 1000 n): 565 2 2 2 Y .
62 ALPHAfBETA COUNTER SAC-4. NIST Th-230 47mm UNEARITY 4 SOURCE SET: $317 _ _
63 NIST Th-230 47mm SOURCE PER EACH (1, 10, 100 OR 1000 nCa4: $65 2 2 2 Y .
64 CM7A NIST ALPHA CALJCHECK SOURCE WITH ALUMINUM CASE/HOLDER: $68 __.
65 CMA NIST BETA CALCHECK SOURCE WITH ALUMINUM CASEIHOLDER: 568 _
66 TCM-2 & PCM -B. NIST CALICHECK SOURCE: $375 __
67 PM -7, NIST CAL/CHECK SOURCE: 5211 _
DECON EQUiPMENT 68 LTC VAC>U-BLAST STEEL SHOT BLASTER: S1,450 _
69 PENTEI VAt;PAt; MODEL 9AVAtCUUM: S1,982 _ 1 2 70 PENTEK SIJIRREL I FLOOR SCABBLER . S1,134 71 PENTEK CORNER CUTTER NEEDLE GN: 5329 _
72; MCDONALD AIR TOOL MODEL U5 5 PISTON FLOOR SCABBLER: _ 865 -
732MCDONALD AIR TOOL MODEL 3WCW, 3 PISTON WALL SCABBLER: S293_ _
74 MCDONALD AIR TOOL MODEL HS, SINGLE PISTON SCABBLER: 594 _
75 2000 CFM HEPA VENTILATION UNIT MODEL 1990C: 5119 _
76 HAKO TWIN HEAD ELECTRIC HEPA VACUUM: $138 ___
77 NORCLEAN TRIPLE HEAD ELECTRIC HEPA VACUUM: S554 .1 Y _
MBTELEST EUIPMENT 7c1FLUKE - 8060A DVM WITI1 HV PROBE. CASE AND LEADS: $M14 79 EBERLINE - bIP-2 MINIPULSER AND LUDLUM MODEL 500 MINIPULSER: S430 -_
( (0 C' APPENDIX A-8 Table COMMERCIAL CLIENT INSTRUMENT COSTS 6 D&D Months Duration 2.0 Final Survey Months Duration 0.5 Characterization Survey Months Duration CHARSURVEY D&D FINAL SURVEY D&D D&D MONTHLY NUMBER NUMBER NUMBER FU1 ALTERNATE ITEM INSTRUMENT' COMMERCIAL INSTRUMENTS INSTRUMENTS INSTRUMENTS PROJECT MONTHLY No. DESCRIP77ON RENTAL RATE REQNiRED REQtfRED REQUIRED DUtRATION DURATION 80 TEKTRONKX- MODEL 2225 100 MHZ PORTABLE OSCILLOSCOPE WITH BATTERY PACK: $513 .
81F&J AIR FLOW CALIBRATOR MODEL D.12: $200 .
82 F&J AIR FLOW CALIBRATOR MODEL D-814: $200 . .
83 FIELO SERVICE TOOL KIT: $130 .
OFFICE EQUIPMENT 84 DATA ANALYSIS COMPUTER SYSTEM: $205 1 1 1 Y .
85 DOWNLOAD NOTEBOOK COMPUTERS: $151 1 1 2 Y .
86 HP MODEL IIP LASER JET PRINTER: $83 1 1 1 Y 87 HP MODEL 4L LASER JET PRINTER: 83 88 HP OFFICE JET FAX/COPIER: S62 SAMPLING EQUIPMENT _ .
89 BICO - JAW CRUSHER. MODEL 241-36X35: $297 _
90 FISHER SCIENTIFIC-TOP LOADING SCALE, 0-3 kg MODEL XE4100: $46 1 . 1 91 FISHER SCIENTlFIC- CLASS F S.S. WEIGHT SET, mg-2kg CAT.# 0221531: $14 1 1 1 Y 92 FISHER SCIENTIFIC- OVEN, ISOTEMP 5.0 120VAC CAT.# 13247750G: $124 1 1 1 Y 93 FORESTRY SUPPLIERS - SOIL SAMPLING AUGER KIT. CAT.# 67352: $289 _
IGLOBAL POSITIONING SYSTEM 94 TRIMBLE NAVIGATION - SITE SURVEYOR SYSTEM, MODEL 40DSE: $1.766 _
COMMUNICATIONS EQUIPMENT 95 MOTOROLA - MODEL HT1000, 16 CHANNEL UHF RADIO WITH ACCESSORIES: $213 . _
TOTAL INSTRUMENT LEASE COST
Decommissioning Cost Estimate Cornell University APPENDIX A- 9 Equipment Lease Charges
(
APPENDIX A-9 COMMERCIAL CLIENT EQUIPMENT COSTS 6 D&D Months Duration 2.0 FINAL SURVEY Months Duration D&D FINAL SURVEY D&D D&D D&D FINAL SURVEY MONTHLY NUMBER NUMBER FULL ALTERNATE EQUIPMENT EQUIPMENT ITEM EQUIPMENT . COMMERCIAL ITEMS ITEMS PROJECT MONTHLY LEASE LEASE NUMB ER DESCRIPTION RENTAL RATE REQUIRED REQUIRED DURATION DURATION COST COST
. DECON EQUIPMENT . . . ._._.
I LTC VAC-U-BLAST Steel Shot Blaster: $1,450 . . ._._._;___
2 PENTEK VAC-PAC Model 9A Vacuum: $1,982 . ._.___ .
3 PENTEK-SQUIRREL IlIl Floor Scabbler: $1,134 . I 4 PENTEK CORNER CUTTER Needle Gun: $329 ._._.
5 MCDONALD AIR TOOL Model U-5, 5 Piston Floor Scabbler: $865 .
6 MCDONALD AIR TOOL Model 3WCW, 3 Piston Wall Scabbler: $293 7 MCDONALD AIR TOOL Model HS, Single Piston Scabbler: $94 _
812000 CFM HEPA Ventillation Unit Model 1990C: $119 .
9 HAKO Twin Head Electric HEPA Vacuum: $138 _ __.___-
10 NORCLEAN Triple Head Electric HEPA Vacuum: $554 .
OFFICE EQUIPMENT 11 Data Analysis Computer System: $205 . . _
12 Download Notebook Computers: $151 . I 13 HP Model IIIP LaserJet Printer: $83 .
14 HP Model 4L Laser Jet Printer: $83 ._.___._. -
15 HP Office Jet FAX/Copier: $62 .
16 35mm Camera $67 1 1 N 2 $134 $134 17 Fax machine $24 18 Telephone $5 ._.
19 Office Trailer, 50' x 10' .
20 Toilet, portable chemical .
21 Desk $135 . . . .
22 File Cabinet, 5 drawer x 28" $129 .
23 File Cabinet, fireproof, 4 drawer- $381 . .
24 Work Tables, 30" x 60" $51 . . . . .
25 Coat Racks, 36" x 21" x 60" $91_1
( c; C, APPENDIX A-9 COMMERCIAL CLIENT EQUIPMENT COSTS 6 D&D Months Duration 2.0 FINAL SURVEY Months Duration D&D FINAL SURVEY D&D . D&D D&D FINAL SURVEY MONTHLY NUMBER NUMBER FULL ALTERNATE EQUIPMENT EQUIPMENT ITEM EQUIPMENT COMMERCIAL ITEMS ITEMS PROJECT MONTHLY LEASE LEASE NUMBER DESCRIP77ON RENTAL RATE REQUIRED REQUIR URAT7ON DURATON COST COST 26 Draft Table .$238 ... .
_ 27 Desk Cha_rs _ $57 _
.28 Molded Plastic Chairs $14 .
29 Microwave oven $97 . .
30 Coffee Machine $149 .
31 Refrigerator $342 32 Waste Containers (7 gallon) $11 . .
33 Waste Containers (35 gallon) $53 34 Draft Table Stool $57 . . ,
35 Plan Holders (P&ID) $91 36 Break Room Folding Tables $101 37 Molded Plastic Chairs $14 . , .
38 Multi-Media Board, 36" x 60" $34 . ._in SAMPLING EQUIPMENT
.39 BICO - Jaw Crusher, Model 241-36:35: $497 40 FISHER SCIENTIFIC -Top Loading Scale, 0-3 kg Model XE41 00: $46 41 FISHER SCIENTIFIC - Class F S.S. Weight Set, mg2kg CAT.# 0 $14 . _ ._.
42 FISHER SCIENTIFIC - Oven, ISOTEMP 5.0 120VAC CAT.# 13247 $124 43 FORESTRY SUPPLIERS - Soil Sampling Auger Kit, CAT.# 67352 $289 ._.__
COMMUNICATIONS EQUIPMENT . _
44 MOTOROLA- Model HTI000. 16 Channel UHF Radio with Access $116 . I
- ___ _ TOOLS . ._.
45 Full Set Misc Tools w/Chest * $93 _ .
46 34" Impact Wrench $128 .
47 314" Impact Socket Set $23 . .
48 Set of -ffing Slings $56 3 . . $1,008_
( APPENDIX A-9 COMMERCIAL CLIENT EQUIPMENT COSTS 6 D&D Months Duration 2.0 FINAL SURVEY Months Duration MONTHLY 1.NUMBER D&D
-_ FINAL SURVEY NUMBER D&D FULL D&D ALTERNATE EQUIPMENT EQUIPMENT D&D FINAL SURVEY ITEM EQUIPMENT COMMERCIAL ITEMS ITEMS PROJECT MONTHLY LEASE LEASE NUMBER DESCRIPTION RENTAL RATE REQUIRED REQUIRED OUR4 7ON DURATION COST COST
-49 Drm Heaters - Evaporation $28 . . .
50 8' Fiberglass Step Ladder $45 3 1 y $810 $90 51 4 Outlet GFCI Circuit Guard $62
.52 Air Compressor (2-1/2 HP, 5.5 CFM) $74 53 1 x 150' Air Hose $28 6 Y . $1,008 54 Air Chipplnq Hammer with Chisels $96 55 Electic Drills 1/2 Inch $46 56 8-114'Circuilar Saw $35 _ _ _ _ _ _ _ _ _ _
57 Milwaukee Heavy Duty Straight Grinder $90 . _._.
58 Long Handled Shovels $10 . . . .. _.
59 Snow Shovels $5 .
60 Steel Pry Bar $2 . ._-_.
61 Long Handeled Pry Bar Set $15 . . ,
62 Electrc Paint Sprayer (for fixative agents) $20 :
63 Cutting Torch $109 _ Y $654 64 Band Saw $57 2 Y $684 65 Drum handling cart $36 . .
66 Extension cord, 100 ft. 1213,15A $33 67 lighting standard, 2 500 W halogen quartz $37 I Y $222 68 Stringlght 100f, 10 lamp $11 :
69 110,000 BTU Oil-Fired Space Heater $60 .___.
HEAVY EQUIPMENT RENTAL _
70 Truck Mounted Hydraulic Crane, 25 Ton $10,692 1 N -1 $10,692 71 40' Telescoping Boom Uft $6,831 _ N 2 $13,662 72 TruckThree ade dump,6 ton payload $8,118 . . -
73 Oxyacetylene Cutting Outfits $386 1 Y $2,316_
74 1-14 C.Y. Backhoe Loader $5,643 N 1 ,
75 Backhoe Aftachment, 1000 ft-b Hydraulic Hammer $6,138 I __ N 2 $12,2761
( C (
APPENDIX A-9 COMMERCIAL CLIENT EQUIPMENT COSTS 6 D&D Months Duration 2.0 FINAL SURVEY Months Duration D&D FINAL SURVEY D&D D&D D&D FINAL SURVEY MONTHLY NUMBER NUMBER FULL ALTERNATE EQUIPMENT EQUIPMENT ITEM EQUIPMENT COMMERCIAL ITEMS ITEMS PROJECT MONTHLY LEASE LEASE NUMBER DESCRIPTION RENTAL RATE REQUIRED REQUIRED DURATION DURATION COST COST 76 Hydraulic Grapple with Shear Attachment for Loader $1,871 . . . : .
77 Service Truck $1,634 _ 1 Y _ $9,804
_______ SAFETY EQUIPMENT .
78 Respirators $45 79 Tripod Lifeline Rescue System $192 . Y $1,152 80 Portable Axdal Electric Blower W/25' Ducting $166 1 Y $996 81 Confined Space Safety Harness $25 I _ _____ Y ____ $150 _____
82 Portable Multigas Monitor $174 . Y $1,044 83 FirstAid Kit $25 2 1 Y $300 $50 84 Respirator Porta Count . . $490
_ ___ {
85 Heat Stress Monitor $86 : . . l
[ I I I f TOTAL EQUIPMENT LEASE COST $56,9121 $274
Decommissioning Cost Estimate Comell University APPENDIX A- 10 Demolition Estimate
APPENDIX A-1 0 Demolition Estimate LABOR BAED DEMOLITION COSTS: Labor by man hour MamnMmnt SupewtIlon, &HP Support Labor Not Includd Uff Operator& DEMOLITION LOC Craftmn Laborers Craftsman HP Tech LABOR TOTAL CODE AREA $44.54 $40.95 $44.54 $66.00 hours PRICE 3 Geneal Cleanup 173.33 1733 $,9 1 Remove Reactor Cote and Internals 67.606.93 74.5 S3 2 Drain Reactor Pool 24.27 3.47 27.7 $1.222 5 Remove ZPR Reactor Core and Related Internals 24.27 3.47 27.7 ii222 I ShI Reactor Core and Related Intemals 104.00 104.0 56.864 3 Remove Reactor Bu~ldina Equipmen 417.73 22.53 440.3 S18,593 3 Remove Heat Exchanwr 8.67 1.73 10.4 $469 4 Peeuw & Ship Contam. Materials &Radioactive Wastes 173.33 3.47 176.8 S7.327 1,034.8 $46,021
C (1~ (1S APPENDIX A-10 TASK BASED DEMOLITON COSTS 42% Hardous ToxcrWaste Poductft Factor. Level C,Heavy Work 70. a5YF Peent Labor Coot 65.00% MATERIAL LABOR EQUIPMENT MATERIAL LABOR EQUIPMENT LOC Average Hourly Labor Rate *40.95 UNIT UNIT UNIT TOTAL TOTAL TOTAL TOTAL CODE AREA QUANTITY UNIT PRICE PRICE PRICE PRICE PRICE PRICE PRICE 2 1r8.CutBloshleldCon 1,213 aquarefeet $39.81 $118.84 S48.050 $144.150 S192.200 2 Remove Concrete under Pool 30 cubic yard $0.00 $8.28 $3.0 S0 $4,878 $2,607 $7A83 2 Remov Rock underPool 20 cubicyard $0.00 $8828 $36.50 $0 $3251 $1,738 $4,989 SO $58,177 $148,495 24,7
Deconunissioning Cost Eslimate Comell University APPENDIX A- 11 Decontamination Costs i
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Decommissioning Cost Estimate Comell Univenity APPENDIX A- 12 Miscellaneous Item Inventory Estimate
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APPENDIX A-12 MISCELLANEOUS ITEM VOLUME ESTIMATE NO. MATL PERCENT ENVIRO DESCRIPTION LOC WBS OF OF BULK UNIT UNIT TOTAL TOTAL DIRECT DISPOSAI CODE No. UNITS UNITS CONST. DENSITY WEIGHT VOLUME WEIGHT VOLUME BURY WEIGHT TRIG3) A) 3 ) 3 (Vol %) (lb)
TRMEA RQar Activated Hardware 1 Ea 2 Misc 6,000 60.0 12,000 120.01- 100% 12,00(
Pool Fuel Storage Wells I Ea 4 Alurinum 168.6 103 6.3 414 25.3 100% 41A Thermal Column I Ea I Graphite &Al 100.0 2,849 28.5 2,849 28.5 0%
0 0.0 C
TRIGA Beam Port Plugs &Shielding C 0 0.0 C Horizontal Access Removable Graphite Block 2 Ea I Graphite 100.0 933 9.3 933 9.3 100% 933 Horontal Acoess Hohlam Block 2 Ea I Hohlraum 100.0 2.133 21.333 2133 21.3 100% 2,133 Horizontal Access Graphite Block 2 ft I Graphite 100.0 5,467 64.0 5,467 64.0 iO0% 5,467 Horzontal Access Lead 2 Ea I Lead 708.0 3.776 5.3 3,776 5.3 00% 3,776 Horizontal Access Boral Can W thick 2 t2 1 Boral 168.6 281 1.7 281 1.7- 0 HorzOntal Rolling Door Plug (llrnenite Concrete) 2 Ea 1 HO Concrete 230.4 0 0 0. t% 0 Vertical Access Lead-1 2 Ea I Lead 708.0 1,785 2.5 1,785 2. !00% 0 Vertical Access Plug Lead 2 Ea I Lead 708.0 2,366 3.34. 2,366 3.3 rS0 0 % 0 Vertical Access Plug Graphite 2 Ea I Graphite 100.0 1,797 17.97 1,797 18.0 )00% 0 Vertical Access Plug Boral Can 118" Thick 2 ft2 I Boral 168.6 83 0.495 83 0.5 0 Vertical Access Center Plug (Ilmenite Concrete) 2 Ea 1 HD Concrete 230.4 3,612 15.68 3,612 15.7 0% 0 Vertical Access Top Plug (Ilmenfte Concrete) 2 Ea I HO Concrete 230A 10.443 45.3 10,443 45.3 0% 0 Vertical Access Lead-2 2 Ea I Lead 708.0 2,589 3.7 2,589 3.7 '100# 2,589 Vertical Access Lead3 2 Ea 1 Lead 708.0 3,068 4.3 3,068 4.3 100% 3,068 0
Activated TRIGA Boshleld Concrete with BSem Tube Part 0 Activated Concrete 2 ft3 2 HD Concrete 230.4 292,077 1,267.9 584,155 2,535.8 100% 584.155 Activated Rock 2 ft 2 Rock 100.0 28.000 280.0 58,000 560.0 100% 56,000 Reactor Bay Reactor Building General Cleanup Waste 3 ft3 360 40.0 14,400 360 100% 14,400 Waste Generated During Pool Draining 2 If 90 15.0 1,350 90 100% 1,350 Waste Generated During Reactor Building Equipment Removal 3 ft 180 40.0 7,200 180 100% 7,200 Waste Generated During Piping Removal 3 ft3 180 15.0 2,700 180 100% 2,700 Waste Generated During Heat Exchanger Removal 3 ft 90 40.0 3,600 90 100% 3,600 Waste Generated During Removal of Rabit Transfer Systern 3 ft 180 40.0 7,200 180 100% 7,200 (P '
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) I
() ( >
APPENDIX A-12 MISCELLANEOUS ITEM VOLUME ESTIMATE NO. MArL PERCENT ENVIRO DESCRIPTION LOC WBS OF OF BULK UNIT UNIT TOTAL TOTAL DIRECT DISPOSAI asN CODE No. UNITS UNITS CONST. DENSITY WEIGHT VOLUME WEIGHT VOWME BURY WIHT gbftA3) _pj W3) ps (ftm31 (vol %I (Ib ChaOM Filer 3 Ea 1 50.0 3,462 69.2 3,462 69. 100% 3.4 Mbmed4 Demloeralzer 3 Ea I 50.0 4,330 86.6 4,330 86.?0 100% 4,33C ZPR Watr System I "
water dean up filter 5 ft3 2 50.0 50 1.0 100 2.0 100% 100 i
I TOTALS: 738,093 4,702 't 100% 714,877