ML20246P017

Decommissioning Plan,Univ of Washington Argonaut Reactor, Conversion to Subcritical Neutron Multiplying Facility & Robotics Lab

ML20246P017
Person / Time
Site:	05000139
Issue date:	08/31/1989
From:	WASHINGTON, UNIV. OF, SEATTLE, WA
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ML20246N987	List: ML20246N985 ML20246P011 ML20246P017 ML20246P310
References
NUDOCS 8909110019
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August, 1983.- 1I SPERT2B.PLN DECOMM'SSIONING PLAN

. UNIVERSITY OF WASHINGrION ARGONAUT REAC'IDR CONVERSION 'IO A SUBCRITICAL NEUTRON MULTIPLYING FACILITY and ROBOTICS LABORA'IORY

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'SPERT2B.PLN August, 1989 Table of Contents' Section Page l 1.0 Plan. Background and Management- 1.0-1 1.1' Summary Description- 1.1-1 1.2 Facility Operating History .

1.2-1 i 1.3 Current Radiological Status of Facility 1,3-1

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1.4 Decommissioning Alternative 1.4-1 )

1.5 Decommissioning Organization and Responsibilities 1.51'-

1.6 Regulations, Regulatory Guides and Standards 1.6-1 -

1.7 Training and Qualifications- 1.7-1 2.0 Occupational and Radiation Protection' Programs 2.0-1 2.1 Radiation Protection Program 2.1-1 2.2 Industrial Safety and Hygiene Program 2.2-1

.2.3 Contractor Assistance 2.3-1 l 2.4 Cost Estimate and Funding 2.4-1 3.0 Dismantling and Decontamination Tasks and Schedules 3.0-1 3.1 Tasks '3.1-1

-3.2 Schedule 3.2-1 3.3 Task Analysis 3.3-1 3.4 Safe Storage 3.4-1 4.0 Safeguards and Physical Security 4.0-1 5.0 Radiological Accident Analyses 5.0-1 6.0 Radioactive Materials and Waste Management 6.0-1 6.1. Fuel Disposal 6.1-1 6.2 Radioactive Waste Processing . 6.2-1 7.0 Technical and Environmental Specifications 7.0-1 8.0 Proposerl Termination Radiation Survey Plan 8.0-1 i'

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4 SPERT2B.PLN August, 1989 1.1 . Summary Description The reactor building is divided into two parts according to the difference in utilization of the two areas. The building is approximately 70 ft. by 76 ft. on the inside. An area 48 ft. by 70 ft. with about 30 ft.

of head room at the west end of the building is devoted to the reactor and associated facilities. The remaining area, 28 ft by 70 ft. is a two-story structure used for classroom, supervisory offices, graduate student study room, shop facilities, and control room. The floor of the building is of poured concrete. %e exterior walls of the reactor room are 'of 8 inch thick concrete poured to a height of 12 ft. 10 1/2 in, above the floor. The building is supported by a concrete column and beam structure.

The reactor room is isolated from the office-classroom-shop section of the building by two doors which are kept closed and locked at all times.

One of these doors is the personnel access door which gives egress into an anteroom in which the radiation frisker instruments are kept. All personnel exiting.the ta ctor room murt frisk themselves for beta-gamma and alpha contamination. The second dr..' is double and gives access to the machine shop area. The outside docc i the machine shop gives access to the loading dock.

The north, south, and west walls of the reactor room are constructed of r.0 in. thick monolithic reinforced concrete extending to a height of 12 ft.

l 10 1/2 in.'above the level of the finished floor. These walls rest on 1 ft.

3 5. thick concrete footings. The west, north, and south walls of the reau ,r room are mostly below grade as the site is situated on a hillside which rises from east to west. The floor of the reactor room is a concrete slab resting on undisturbed earth. The slab has a minimum thickness of 6 in, which increases to 18 in. under the reactor. The reactor rests on a concrete support pedestal 16 in. high.

A concrete service trench 5 ft. wide and 2 ft, deep extends south from under the reactor to the process pit which is 6 ft. 6 in wide, 14 ft. long, and 5 ft, deep. The concrete walls of the process pit vary from 8 in, to 10 in.-in thickness. Thirty-six 4 in. diameter by 5 ft. .~il in. deep steel-lined fuel storage holes are embedded in the concrete at the southwest corner of the reactor room. Each hole has a removable shield plug made of 5 in. diameter heavy iron pipe, 3 ft. 8 in. long, filled with concrete. The j L shield plugs are recessed below floor level, and 6 in. thick removable l concrete slabs cover the plug tops to the level of the floor.

A 3-ton bridge crane services the reactor room area. The crane is used to lift the shield blocks, the fuel-transfer cask, and other heavy items.

A 13 ft. 2 in. by 14 ft. 5 in, counting room is located in the northwest corner of the building. The interior concrete walls of this roon are two feet thick to reduce background radiation. The counting room contains a well-shielded cadmium and copper lined counting cave.

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SPERT2B.PLN August, 1980' l.2 Facility Operating History The University of Washington Nuclear Reactor has operated normally since April, 1961. The initial power was 10 kilowatts. In April, 1967 the power wcs increased to 100 kilowatts. The reactor ceased critical operation on June 30, 1988 after generating a total of 304,443 kilowatt-hours of thermal energy.

There has been only one significant incident in which radioactivity has been dispersed around the facility. On June 13, 1972, an experiment was being carried out on the top of the reactor for the purpose of measuring delayed neutrons from fissionable materials. One of the target foil sets was of plutonium. During the course of the experiment, some or all of the 5 foils broke inside of their holder. Some particulate activity escaped the holder and contaminated the reactor building. Most of the activity was confined to the reactor room itself.

Following decontamination of the facility, all rooms containing surfaces on which contamination had been found were painted and a layer of linoleum tile was laid down. No smearable activity has been detected on accessible surfaces after this procedure. It is suspected that there still are low levels of activity trapped in the interstices of the overhead bridge crane and in the ventilation system. No alpha-activity has been detected in any air sample taken following the cleanup.

It is not intended to disturb the tiling on the flor: .uring the conversion of the critical facility to sub-critical operc .an so that any particulate activity will remain isolated. No release of activity due to crane activities has ever been detected during the 16 years following the cleanup. It is not expected that use of the crane during the conversion will result in spreading of contamination. Because there will be removal of radioactive components from the reactor, there will be radiation surveillance throughout the project. Any alpha activity will be detected and analyzed. If plutonium is identified (via the 60 key line of americium-241), further decontamination will be carried out.

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I i p' SPERT28.PLN, August, 1989 1.3 -Current' Radiological Status of the Facility The radioactive irradiated fuel has been removed from the core of the UWNR'and will be shipped to the. Idaho National Engineering Laboratory. The only remaining radioactivity in the facility is due to activation of the.

components of the' reactor, including trace element contaminants of the major constituents.

Although the University of Washington ARGONAUT Reactor is similar in design to'other ARGONAUT Reactors around the country, the residual radioactivity contained in the reactor components will depend on the specific trace element composition of its component parts. These

= concentrations are site specific since the source of the components of the concrete and the specific source of metallic elements vary from site to site.; As a result, it is not possible to predict exactly what' specific

-radionuclides and what activity levels will be found. These activities will be experimentally determined by sampling and counting.

An estimate of the residual radioactivity can be n.ade by utilizing the determination of the residual radioactivity in'the UCLA ARGONAUT reactor as given in the deconunissioning plan' for that facility. For long lived activity, the. activities in the UHNR can be taken to be proportional to the ratio of the. total' energy ocnerate.1 in'the two facilities. For activities whose half-lives are less than the operat.!ng lifetime of the UWNR, we use a scale factor proportional t-) the power level during the last period of operation of duration equal to the mean-life of the activity, corrected for decay between shut-down and masurement. In one m n-life, the activation reaches about 63% of saturation. While this is not an exact procedure, the unknown trace. element composition of the UWNR does not justify any more detailed a computation.

Table 1.3-1 lists the residual activat!on products in the UCLA reactor and the scale factor based on the operating history of the UWNR, the average power of the UCLA reactor of 2.5 kW, the.tctal. generated energy of the UCLA reactor of 5.3E5 kWH, and the total generated energy of the UWNR of 3.0E5 kWH. It is assumed that the interval between shutdown and start of removal of components with residual activity is 12 months. 'Ihe interval between shutdown and the date of the UCLA Phase I plan is 21 months. A decay correction of 9 months is therefore applied to the scale factor.

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SPERT2B.PLN August, 1989 Table 1.3-1 Potential IMNR Residual Activity Component Isotope Mean Life Scale Factor Metallic Parts Mn-54 450 d 0.65 Fe-55 3.9 y 0.53 Co-60 7.6 y 0.47 Zn-65 352 d 0.79 Graphite' Co-60 7.6 y 0.47 Eu-152 19.3 y 0.57 Eu-154 12.3 y 0.44 Lead Ag-108 190 y 0.58 Ag-110 360 d 0.76 Magnetite Concrete Mn-54 454 d 0.65 Co-60 7.6 y 0.47 Cs-134 3.0 y 0.62 Eu-152 10.3 y 0.57 Eu-154 l' ;. 3 y 0.44 The average scale factor for all of these activation products is 0.6, which will be used to estimate the UWNR residual activity based on the reported residual activities in the UCIA ARG0talTI facility. On this basis, the total residual activities in the various components of the system are shown in Table 1.3-2.

Table 1.3-2 Estimated IMNR Residual Activities Component Estimated Volume Scaled Activity l

(cu. ft.) (Ci) l Metallic Parts 95 0.9 l Graphite 205 <2.5 ,

Lead 2.3 <0.06 i Magnetite concrete 521 0.9 1

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'l.4' Decommissioning Alternative

'Ihe decommissioning alternative selected is partial dismantlement and conversion of the facility to a research and teaching facility which will include a laboratory for robotics and a laboratory for nuclear engineering

' teaching, training and research organized around a neutron multiplying suberitical facility. Access to the facility will remain controlled with

.all radiation precautions followed as are currently in place. There will be no hazard to the public since the current radiation levels present no hazard and the radiation levels associated with the suberitical will be even lower.

There are.no radiation hazards associated with the robotics laboratory. The dismantlement includes removal of the highly-enriched ARGONAUT fuel, the fuel boxes, the control rod assemblies, some or all of the graphite, some or all of the lead, most of the concrete, the shield tank, and the cooling system components. The concrete pedestal and pad may be left in place as a foundation for new equipment.

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-1.5~ Decommissioning Organization and Responsibilities i

l President, l l University of l l Washington l l l I

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.I I l l Dean, College l l lof Engineering l 1 I l 1 I I I

.l. Director, l l Chairman, Dept l l Environmental l lof Nuclear Eng.l l Health and Safety l l l l

l- l l Capital l lClCl l l l Projects l_l o l o l l Radiation Safety l.......l Director, UWNR l.. lnlnl l Officer l l l Project ltlsl l l l ~l Manager l lrlul l l lal1l l l _ l l c'l t'l

-l Radiation MonitorEl l Assistant Director l l' ltlal l l.......l for l l lolnl l l l Reactor Operations l l lrltl l 1 1 I I I I I l l Technical Services l l l Supervisor l l l l l l l 1 I

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1. President: The chief executive officer of the University.

2. Executive Vice-President: Deputy chief executive officer of the University, reporting to the President.

3. Provost: Chief academic officer of the Universitn reporting to the President.

, 4. Dean, College of Engineering: Chief executive and academic officer of the College of Engineering, reporting to the Provost.

5. Director, Dcpartment of Environmental Health and Safety: Senior staff person in charge of the staff functions responsible for all aspects of industrial health and safety at the University, reporting to the Executive Vice-President.

6. Chairman, Department of Nuclear Engineering: Chief executive and academic officer of the Department of Nuclear Engineering, reporting to the Dean, College of Engineering.

7. Director, University cf Washington Nuclear Reactor: Professor in charge of the UWNR. The director is a professional nuclear engineer, professor of Nuclear Engineering, and Senior Reactor Operator reporting to the Chairman, Department of Nuclear Engineering.

8. Radiation Safety Officer: Senior Staff Person in charge of the Office of Radiation Safety, reporting to the Director, Department of Environmental Health and Safety. The RSO is a Certified Health Physicist expert in all aspects of radiation safety. The RSO serves an advisory function to the Director, UWNR.

9. Project Manager, Capital Projects: The Project Manager is a senior facilities engineer responsible for coordinating University, Federal, State and local regulations and procedures for large projects, reporting to the Director, Capital Projects. The Project Manager serves an advisory function to the Director, UWNR.

10. Assistant Director for Reactor Operations: Responsible for the day-to-day operation of the Nuclear Reactor Laboratory, reporting to the Director, UWNR. The Assistant Director is an M.S. graduate of the Radiological Sciences Program, expert in radiation safety, activation analysis, reactor operations, and is a Senior Reactor Operator.

11. Technical Services Supervisor: Responsible for maintaining operational building equipment, reporting to the Director, UWNR. The TSS is a graduate chemical engineer and a Senior Reactor Operator.

12. Radiation Monitors: The radiation monitors are trained technicians who are responsible for radiation monitoring at the University, reporting to the RSO.

13. Temporary Technical Support: Personnel as needed for the purposes of decommissioning, reporting to the Assistant Director for Reactor Optrations or to the TSS. l I

14. Consultant / contractor: An off-campus consultant or contractor will be contracted to aid in the preparation and planning of several of the tasks.

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.1.6 Regulations, Regulatory Guides and Standards:

The decommissioning of the IMNR and the conversion of the facility to a neutron multiplying suberitical facility and robotics laboratory will be governed by the applicable'Federec1 and State of Washington regulations, regulatory guides, and standards. These include:-

Radiation Protection 10CFR'.0 . Radiation Protection and Surveys Reg Guide 1.86 Radiation Survey-as applicable Worker Safety OSHA and WISHA Worker Health and Regulations Safety Transportation 10CFR71 Packaging and 49CTR Transportation of Spent Fuel and Low Level' Waste Environment 40CFR- Environmental Impact NUREG 0586 1.6-1 i

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SPERT2B.PLN August, 1989 1.7 Thaining and Qualifications University personnel who will be assigned to the task of converting the

- UWNR to a neutron multiplying subcritical facility and robotics laboratory

- will come from the regular UWNR staff, the staff of the University of Washington Radiation Protection Officer, and the University of Washington Facilities Management Office. The first two groups are comprised of-individuals who are well-trained and qualified radiation workers. Personnel from the Facilities Management Office will be. briefed on.the facility layout, the radiation environment and hazard, and proper procedures for working at the facility during its decommissioning as a critical facility and recommissioning as a sub-critical facility. 4 There will be a radiation monitor present during all operations which might involve exposure to radiation or radioactivity.

The training program will include familiarization of the facility layout and the details of the reactor itself. Types and sources of radiation and radiation levels in the IMNR will be described. Proper handling of radioactive materials will be described. Radiation exposure >

- regulations and limits will be described.

Only contractors whose personnel to be assigned to this project are already trained in radiation work will be used. Training beyond that necessary to familiarize them with the radioactive sources in the reactor facility itself will not be done for contractor personnel.

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SPERT2B.PLN August, 1989 2.0 Occupational and Radiation Protection Programs 2.1 Radiation Protection Program occupational radiation protection will follow the procedures already established for the University of Washington Nuclear Engineering Laboratory as described in the Operating Procedures. These procedures are designed to conform with all federal and state regulations.

l The facility is surveyed for radioactivity twice weekly by monitors from the staff of the Radiation Safety Officer. The survey includes

, counting of wipe samples and air particulate filter samples from two 60 cfh l air samplers permanently stationed in the reactor room.

Aic is collected from the reactor room through ducting, passed through HEPA filters, and discharged via a roof stack. There is a gross beta-gamma monitor in the duct line.

Individuals exiting the reactor room are required to frisk their hands and feet for beta-gamma and alpha activity. The beta-gamma detector is a Technical Associates Model PUG-1 Pancake G-M Tube. The alpha detector is an Eberline Model RM-15 Zns thin-window screened alpha detector.

All workers who will be participating in the decommissioning of the ARGONAUT and the re: commissioning of the suberitical facility will have film badges which ace processed monthly. In addition to the film badges, workers will wear pencil dosimeters to monitor their daily exposure. -

Survey instruments available at the UWNR are listed in Table 2.1-1.

These instruments are stored at the UWNR in the anteroom to the reactor room. They are maintained by the reactor staff. Calibration is done at the University of Washington Regional Calibration Facility using a Shepard Cs-137 calibration source.

Gamma calibration is done using a Shepard Cs-137 calibration source at the Northwest Regional Instrument Calibration Facility located on the campus of the University of Washington. Alpha calibration is done with a Thorium-230 source at 1 inch and at contact. Beta calibration is done with a Chlorine-36 source at 1 inch and at contact. Neutron calibration is done with a Pu-Be source. The calibrations are done by qualified staff from the University; of Washington Nuclear Engineering Laboratory.

Table 2.1-1 Survey Instruments at the UWNR Ir.st . Manufacturer Model Radiation No. No. Detected

1. Eberline Instrument Co. RM-15 Alpha

2. Eberline Instrument Co. PAC-lSAGA Alpha

3. Eberline Instrument Co. PAC-lSAGA Alpha

4. Keithley Co. 36100 Beta, Gamma

5. Technical Associates PUG-1 Beta, Gamma

6. Bicron Co. RSO-5 Gamma

7. Canberra Co. GR-1920 Gamma (spectrometer)

8. Tracerlab SNOOPY Neutrons

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SPERT28.PLN August,~1989 2.2 Industria1L Safety and Hygiene Program-E .

Partial dismantlement procedures will be de' signed with the assistance of a project manager assigned by the Facilities.= Management Office..

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tProced.tres.to' insure. compliance with all OSHA, WISHA and University 1

regulations'will'be specified by that office. If an outside~ contractor-is: -

' hired to implement the decommissioning, he will be responsible by the terms  :

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of the contrach for complying with all relevant regulations. i h--

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SPERT2B.PLN August, 1989 )

.. l 2.3 contractor Assistance {

No decision to let an outside contract for decommissioning has been made. It is expected that a consultant or contractor will be employed for cssistance on several of the tasks.

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'SPERT2B.PLN August, 1989 2.4 Cost Estimate and Funding Cost estimating performed by the University Architects Office with

< consultation with the Facilities Management Office and the Capital Projects Office. Assumptions given in Appendix I.

Task Done Cost ($) Time by (est) months (est) la. Decommissioning / decontamination plan Cnsltnt 20,000 12 8

lb. Environmental impact statement Cnsltnt 21,000 9

-2. Identify radwaste for removal NucE N/A 2

-3. Remove all coldwaste NucE 5,000 0.5 10,000 b

4. Assay waste for residual radioactivity NucE 2 c

5. ' Inventory for residual radioactivity NucE N/A 1

6. Remove and dispose of internals Cntrctr 750,000 12

7. Disassemble / dispose of surplus graphite 'Cntrctr item 6 item 6

8. Empty / remove / dispose of shield tank Cntretr item 6 item 6 9.. Dispose of shield blocks Cntrctr item 6 item 6 10a. Determine extent of concrete activity Cntretr item 6 item 6 10b. Remove / dispose residual concrete (radwaste) Cntrctr item 6 item 6 10c. Remove / dispose residual concrete (coldwaste) Cntrctr item 6 ~ item 6 d

11. Remove / store lead bricks and curtain NucE 2,500 0.5

12. Survey building for contamination Cntretr 20,000 2

13. . Cleanup building as necessary Cntretr 55,000 3

14. Remove asbestos Cntrctr 75,000 6'

15. Demolish / survey for residual radioactivity -N/A N/A N/A Subtotal 958,500 31.5 Contingencies and fees 0 50% 479,250 Total (rounded) 1,440,000 32

• Part of package of tasks (item 6)

a. Concurrent with item 1; does not increase total time.

b. Concurrent with item 2; does not increase total time.

c. Concurrent with item 2; does not increase total time.

d. Concurrent with item 6; does not increase total time. {

e. Concurrent activity; does not increase total time Funding.for these expenses will be provided by the University of Washington as indicated in the attached statement of financial responsibility.

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-3.0 Dismantling and Decontamination Tasks and Schedules 3.1 Taiks 3.1.1 Task List Table 3.1-1 lists the tasks required for decommissioning the UWNR and preparing the facility for conversion to a suberitical reactor facility. J Table 3.1-1 Decommissioning Tasks

1. Prepare a Decommissioning and Decontamination Plan (DDP)

2. Identify reactor components to be removed (radwaste)

3. Remove all surplus non-reactor non-radioactive material from building (coldwaste)

4. Assay waste for residual radioactivity

5. Prepare inventory of residual radioactivity

6. Remove and dispose of surplus metallic reactor internals (except lead)

7. Disassemble and dispose of surplus reactor graphite

8. Empty, remove and dispose of shield tank (as radwaste if necessary)

9. Dispose of concrete shield blocks (as radwaste if necessary)

10. Determine extent of concrete activation

11. Remove activated part of biological shield and dispose of as low-level radwaste

12. Remove non-activated part of biological shield and dispose of as normal trash

13. Remove and store lead bricks and the lead curtain.

14. Survey building for radioactive contamination and do cleanup as necessary.

3.1.2 Task Descriptions

'l. Prepare a Decommissioning and Decontamination Plan (DDP): The DDP will be prepared according to the Guidance and Requirements document prepared by the Standardization and Special Projects Branch, Division of Licensing, Office of Nuclear Reactor Regulation, U.S.N.R.C., August 15, 1984.

2. -Identify all reactor components to be removed as radwaste: The installation of a suberitical facility and robotics laboratory in place of the ARGONAUT reactor will require removal of the fuel boxes, the control rods and shrouds, some or all of the graphite, reactor internals, the removable concrete shield blocks, and any other part of the structure which will be surplus to the needs of the subcritical and robotics laboratory.

3. There are various non-radioactive supplies and equipment stored in the ,

reactor enclosure and secured store room. Tra surplus non-radioactive '

materiel will be identified, surveyed for removable contamination, and removed from the building.

4. Assay waste for residual radioactivity: Residual radioactivity in i surplus reactor components will depend in large part on the impurities (trace elements) in these components.

These impurities are unknown. In order to estimate the amount of residual radioactivity, the surplus components will

• 4e to be surveyed to identify ,

the radioisotopes present. This will be done by gamma ray spectroscopy

s SPERT2B.PLN August, 1989 using the portable germanium detector in and around the core after the ,

center graphite is removed.

By using a well-shielded detector, the radioisotopes in each component can be reasonably well identified. After the radioisotopes have been identified, small samples of the surplus components will be taken for quantitative evaluation of radioactivity levels. Assay of the concrete will be done by taking small samples of the concrete shield plugs in the beam ports. This assay will indicate how much of the concrete shield itself contains residual radioactivity at levels sufficient to classify it as low-level radwaste.

5. Prepare inventory of residual radioactivity: Once the radioactivity assay is complete, the total radioactivity inventory of the surplus materiel can be estimated from the known amounts of surplus components.

6. Remove and dispose of surplus metallic reactor internals: All of the i metallic reactor internals identified as surplus will be removed and i packaged as low-level waste. This material will be shipped in approved containers to a low-level waste burial site for disposal. Removal procedures will be developed so that personnel exposures will be minimized.

7. Disassemble and dispose of surplus reactor graphite: The first disposal attempt will be to identify any facility around the country which wishes to reuse the graphite and to package it and ship it there. If no facility wishes to use the surplus graphite, that part which was surveyed to contain low-level activity will be packaged and sent to a low-level radwaste disposal site. The part of the surplus graphite which does not have low-level radioactivity above the regulatory lower limit will be disposed of as ordinary trash.

8. Empty, remove and dispose of shield tank: The water in the shield tank will analyzed for residual radioactivity. If no radioactivity is found, the water will be disposed of into the sanitary sewer. If radioactivity is found, the water will be sent through a demineralized to remove the activity. Tritium will not be removed. If the water activity can be reduced to below the regulatory limit for sewer disposal, it will be disposed of via that route. If the water activity levels cannot be reduced below sewer disposal limits, the water will be disposed of as low-level radwaste in 55 gallon drums.

9. Dispose of concrete shield blocks: Some of the concrete shield blocks may contain residual radioactivity. These blocks will be disposed of as low-level radioactive wr.ste. The blocks that are assayed to be below regulatory limits for radioactivity will be disposed of as ordinary trash.

10. Determine extent of concrete activation: Assay of the concrete will be done by taking small samples of the concrete shield plugs in the beam ports.

The concrete pedestal and pad will be sampled by coring. Grana-ray l spectroscopy will be used to identify and estimate the lev'el of any activation products in the concrete. These assays will indicate how much of the concrete shield itself contains residual radioactivity at levels sufficient to classify it as low-level radwaste.

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11. Remove activated part of the biological shield and ship as low-level radwaste: _ Based on the radioactive surveys of the concrete biological shield, remove concrete in two campaigns; low-level radioactively contaminated concrete and non-contaminated concrete. The concrete with low-level contamination will be packaged and sent to a low-level waste burial site.

12. Remove non-activated part of the biological shield and dispose of as normal trash: The uncontaminated concrete will be disposed of as normal trash.

13. Remove and store lead bricks and the lead curtain: Because of the difficulty of disposing of metallic lead as waste whether or not it contains low-level radioactivity, the lead will be stored on site. Plans for permanent disposition will have to be worked out. The level of residual radioactivity may be low c.nough to re-utilize the lead as radiation shielding for low-level counting.

14. Survey building for radioactive contamination and do cleanup as necessary: Following the decommissioning of the UWNR, the entire building will be surveyed for contamination by the University radiation monitors.

Any contamination found will be cleaned up. Re-utilization of the facility for construction of the suberitical assembly and robotics laboratory will not begin until the building is shown to be free of residual removable contamination on any accessible surface.

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7 SPERT2B.PLN August, 1989 3.2 ' Schedule The detailed schedule of tasks will be evaluated after the specific disposal option is selected.

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'SPERT2B.PLN August, 1989

-3.3 Task Analysis The tasks will be analyzed after the specific disposal option is selected.

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~SPERT2B.PLM August, 1989 3.4 Safe Storage Safe Storage is not an applicable option.

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- 4.'O Safeguards'and Physical; Security

The high. enrichment ARGONAUT fuel'will have-been sent off-site to INEL.

'There is no remaining safeguards problem during decommissioning. Physical

. security of.the,. building is based on the building being locked at all times.

. Keys are issued on a need-to-possess basis only and. regularly surveyed and.

recorded.

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' SPERT2B.PLN. August, 1989 1 h 5.0'.. Radiological Accident Analyses j

.The reactor-fuel will have been sent off-site under the' operating license prior to the start of decommissioning activities. We remaining activity in the: building is either in the form of sealed-sources or as low :

level activation activity inLreactor components. During decommissioning, there are no credible accidents that pose a radiological hazard to personnel-l: oi::the. general public.

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'6.0 Radioactive Materials and Waste Management 6.1 Fuel Disposal l All of the ARGOtWJT fuel, both irradiated and non-irradiated will have been sent off-site.

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f ; ;-i u SPERT2B.Pm . August, 1989 6.'2 Radioactive Waste Processing.

.-The' amount of the IMNR components that are radioactive will not be

..known until'the fuel is removed and samples of the components'can be.

analyzed.- Radioactivation at some level will have occurred-in the~ concrete, the graphite, the. lead , the control elements and the other metallic components.

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(! 'lSPERT2B.PLN.. August, 1989 jp .7.0.LTechnical

and Environmental Specifications-The technical and environmental' specifications will be developed after P , lthe contractor is' chosen.- The specifications will-depend.on the details ofi 0 .the decows.issioning procedures to be followed and will- be developed jointly:

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i= SPetr2B.PLN August, 1989 8.0' Proposed Termination Radiation Survey Plan:

'At'the' completion of the decommissioning phase when all of the components of the ARGONAUT.havn been removed and sent off-site.as waste and. ..

all. cleanup procedures completed, the facility will be subjected to a

. standard radiation survey by the radiation morators. The cleanup will leave 1the. facility--:in a state which meets all radiation standards. The facility is to be used as before as an academic. teaching, training and experimental laboratory. A termination-radiation survey is not required since.the building'.will not be. released for unrestricted use.

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