ML20203F958

Revised Decommissioning Plan

ML20203F958
Person / Time
Site:	General Atomics, 07000734
Issue date:	07/31/1986
From:	GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:
Shared Package
ML20203F949	List: ML20203F942 ML20203F958
References
NUDOCS 8607310214
Download: ML20203F958 (32)

Text

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l GA TECHNOLOGIES INC.  !

l DECOMMISSIONING ptAN I

l JUNE 1979 .

(REV. JULY 1986) l BA PHAIE BATA qw"anas, PDR

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GA TECHNOLOGIES INC.

DECOMMISSIONING PLAN TABLE OF CONTENTS

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Preface / Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . iv

1. General Facility Description . . .. . .. ... . . . . . . . . . . 1-1 1.1 Sorrento Valley Facilities (SV) . .. ...... . . . . . . . 1-1 1.1.1 Fuel Manufacturing Building (Bldg. 37) . . . . . . . . . 1-1 1.1.2 HTGR Fuel Production Process Development Building (Bldg. 39) . . .. . .. .. . .. . . . . . . . . . . . 1-2 1.1.3 Waste Processing Facility . ,

.. . . . . . . . . . . . . . 1-2 1.2 Main Site (MS) .. . .. .. . . . . .. . . . . . . . . . . . . 1-3 1.2.1 Laboratory Building . . . . .. .. . . . . . . . . . . . 1-3 1.2.2 Hot Cell Facility . . . .. . . . . . . . . . . . . . . . 1-3 1.2.3 TRIGA Reactors Building . . ... . . . . . . . . . . . . 1-5 1.2.4 Experimental Area I Facility . . . . . . . . . . . . . . 1-6 1.2.5 TRIGA Fuel Fabrication Building . . . . . . . . . . . . . 1-6 1.2.6 Experimental Building . . . .. ... . . . . . . . . . . 1-6

2. Radiological Safety Organization . . . . . . . . . . . . . . . . . . 2-1 3 Discrete Facility Plans . . . . . . . ... . . . . . . . . . . . . . 3-1 3.1 Sorrento Valley Facilities (SV) . . . . . . . . . . . . . . . . 3-1 3.1.1 Fuel Manufacturing Building (Bldg. 37) . . . . . . . . . 3-1 3.1.2 HTGR Fuel Production Process Development Building (Bldg. 39) . . . . . . . . . . . . . . . . . . . . . . . 3-3 3.1.3 ' Waste Processing Facility . . . . . . . . . . . ... . . . 34 3.2 Main Site (MS) . . . . . . . . . . . . . . . . . . . . . . . . . 3-5 3.2.1 Laboratory Building . . . . . . . . . . . . . . . . . . . 3-5 3.2.2 Hot cell Facility . . . . . . . . . . . . . . . . . . . . 3-5 3.2.3 TRIGA Reactors Building . . . . . . . . . . . . . . . . 3-6 3.2.4 Experimental Area I Facility . . . . . . . . . . . . . . 3-9 3.2.5 TRIGA Fuel Fabrication Building . . . . . . . . . . . . 3-10 3.2.6 Experimental Building . . . . . . . . . . . . . . . . . . 3-11 4 Waste Processing & Disposal . . . . . . . . . . . . . . . . . . . . 4 -1

5. Cost Analysis . . . . . . . . . . . . . .. . . . . . . . . . . . . . 5-1

6. Financing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 11

FIGURES 1.1 Plan View of Site 1.2 HTGR Fuel Process Development Building j 1.3 Hot Cell Facility Floor Plan i

1.4 Plan View of the Hot Cell 1.5 TRIGA Reactor Building Floor Plan 1.6 TRIGA Reactor Facility Complex TABLES Table 5- Table of Costs by Facility ... . . . . . .. . . . . . . 5-2 Table 5-2 Transportation and Burial Charges . . . . . . . . . . . . . 5-3 i

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GA TECHNOLOGIES INC.

DECOMMISSIONING PLAN Preface.

J GA Technologies Inc. carries out various activities which are licensed by the Nuclear Regulatory Commission and/or the State of California, an agree-ment state. These activities can generally be described as:

(1) broad nuclear research, (2) reactor fuel fabrication and (3) operation of two TRIGA research reactors The research and fuel fabrication activities involving SNM are licensed under SNM-696; Docket 70-734 The byproduct and source material activities

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are licensed under California Radioactive Material License 0145-80. The two TRIGA research reactors, the Mark I and Mark F, are NRC licensed respectively under R-38; Docket 50-89 and R-67; Docket 50-163 This decommissioning plan has been developed in response to an NRC imposed license condition.

The plan gives general information on the methodology, costs and financial arrangements c6nsidered relevant to the deccmmissioning of our licensed facilities. With noted exceptions, our plans are to decontaminate for release for unrestricted use all laboratory buildings and fuel fabrication facilities. The exceptions are the Hot Cells and reactor pool tanks which may or may not be viewed as useful in the future.

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GA PRIVATE DATA

1. FACILITY DESCRIPTION This plan relates to the licensee's facilities in which radioactive material is used or generated. Figure 1.1 is a plan view of the site. The following describes the facilities which are currentiy involved in routine radioactive material processing. The areas given (in square feet) are those for the various buildings whose walls may provide boundaries for radioactive material. Additional facility descriptions inay be found in SNM-696 documents. l Brief descriptions of the significant facilities are given below.

1.1 SORRENTO VALLEY FACILITIES (SV) 1.1.1. Fuel Manufacturing Building (Bldg. 37) (116,048 ft )

Located at 11220 Flintkote Avenue in Sorrento Valley north of the main complex, the Fuel Manufacturing Building contains offices, shops, and an area used for fuel fabrication. The building is approximately 460 ft long and 120 ft wide with about two-thirds of the building of high bay construction. The east section of the building is divided into two floors for offices, labora-tories and store rocms. Nonrelated activities carried out in the building include a machine shop, a sheet metal shop, an assembly area for mechanical parts and non-nuclear experimental areas. Approximately one-half of the building area is devoted to fuel fabrication activities. The fuel fabrication area is bounded by two outside walls, a structural steel wall and a masonry wall, which separate it frem other areas and activities. Access to the fuel fabrication area is restricted to limit access to authorized personnel, to centrol StM, to maintain control and monitoring of personnel, and to prevent the spread of contamination. Separate ventilation systems are maintained for facilities and areas involved in SNM processing.

1-1

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1.1. 2 HTGR Fuel Production Rrocess Development Building (Bldg. 39) (15,209 f t')

Process development, pilot scale operations, and specialized fabrication work related to fuel production are conducted in a Juilding adjacent to and north of the Fuel Manufacturing Building. Process development is carried out l in the east center portion of the building within an area which has floor to ceiling partitions. Pilot-scale f'uel particle development activities are located in the southwest corner of the building. Figure 1.2 shows a plan view of the facility.

The areas used to work with radioactivity have covered floors, painted walls, etc. to effectuate cleaning of any radioactive contaminants from such surfaces. Current levels of radioactivity are <20 dpm (a)/100 cm of the building's affected portions.

2 1.1.3 Waste Processing Facility - gorrento Valley (Bldg. 41) (8,000 ft ).

Main Site (Bldg. 25) (600 ft )

During 1984, GA relocated the Waste Processing Facilities to Buildings 25 and 41. The majority of the new facilities are now located south of the Fuel Manufacturing Building and consist of about one-fourth of Building 41 (ap-proximately 2,000 ft ), yard storage area and a high level storage facility.

Building 41 contains a compactor and solidification equipment used for pro-cessing radioactive centaminated wastes. Building 25, which is located on the Main Site approximately 250 feet southwest of the TRIGA Reactor Building, contains the remainder of the Waste Processing facility equipment. In car-2 ticular, Building 25 (600 ft ) contains low level liquid waste treatment and filtration equipment.

The "old" Waste Processing Facility (including the evaporation ponds and process buildings) and surrounding canyon and ridge areas (approxi=ately 80 acres) are in the process of being decommissioned according to the following NRC approved plan: "NRC Docket 70-734: Plan for Obtaining Release of Certain Areas to Unrestricted Use," GA submittal letter 696-8023 dated cetober 1, 1985.

1-2

1.2 MAIN SITE (MS) 1.2.1 Laboratory Building (Bldg. 2) (119,370 ft 2)

The Laboratory Building contains approximately/400 laboratories, offices, shops, and a few low-level caves for work with low-level radioactivity. Most of the research activities involving metallurgy, chemistry, and experimental physics are conducted in this building. Several of these laboratories may involve rather small quantities of radioactive material. Typically such material will be found in laboratory hoods or special test equipment.

The floors of these laboratories are mostly covered with linoleum. The walls are typically painted masonry or wallboard. The radioactivity found on these surfaces is usually <20 dpm/100 cm .

1.2.2 Hot Cell Facility (Bldg. 23) (8000 ft 2)

The Hot Cell Facility is equipped to perform a wide range of investiga-tions of the physical, metallurgical, and chemical properties of irradiated specimens, including examinations of full-size power reactor fuel elements.

The facility includes high-level cell with three operating stations capable of handling activity levels of up to one million Ci of 1 MeV gamma, an ad-jacent low-level cell that can be used separately or in conjunction with the high-level cell, and a metallography cell equipped to provide ccmplete met-allugical investigations including micro , macro , and stereo-photography'.

Supporting areas include a service gallery, physical test room, machine shop, manipulator repair, decontamination room, and an X-ray rocm.

The Hot Cell Building consists of office space, three Hot Cells, an operating gallery , and hot and cold auxiliary areas. Figures 1.3 and 1.4 show the plan view of the facility and details of the cells and shielding.

1-3 1

The high-level cell, which is the largest of the cells and which has the most shielding, is 8 f t wide, 18 f t long, and 15 f t high. The cell walls range from 42-in.-thick high-density concrete on the front and end to 60-in.-

thick conventional concrete on the rear. A two-section steel door separates this cell from the adjacent low-level cell; the low /r section is 21 in. thick and 11 ft, high, and the upper section is 12 in, thick and 3-1/2 ft high.

There are three operating stations, two on the front wall and one on the end wall, each with a viewing window and two master-slave manipulators.

The icw-level cell is 10 ft long, 8-1/2 ft wide, and 15 ft high. The walls of this cell are formed by the high-level cell door, a 17-inch.-thick solid steel door to the service area, a 36-in. front wall, and a 32-in. back wall of high-density concrete. The front wall has a viewing window with manipulators and various shielded access holes. There are also shielded transfer tubes connecting the low-level cell to the other two cells.

The metallography cell measures 9 ft long, 5 ft wide, and 11-1/2 ft high.

The walls are made of high density concrete and range in thickness from 34 to 36 inches. Personnel access to the cell is through a 15-in.-thick solid steel sliding door to the service area. The front wall of the cell has one opera-ting station equipped with a viewing windcw, manipulators, and access holes.

On the corner of the cell is an cperating station equipped with a stereo-microscope and remote operated specimen stage for viewing small specimens.

The side wall of the cell contains a metallograph mounted in such a manner that the stage can be retracted into the cell when the instrument is in use.

When not in use the instrument is retracted into the cell wall, and a lead-filled shielding door located inside the cell is closed to protect the optical and electronic components.

There are special storage tubes in the cells, one in the icw-level cell ficor and three in the high-level cell flocr. The tubes are 12.25 in. inside

, diameter and 6 ft 1 in, deep with 18-5/8-in.-thick gasketed plugs. The tubes are located 2 ft frem the back wall of the cell and are located on 5 f t 6 in.

centers. These tubes may be used to store radioactive and special nuclear materials to reduce radiation levels in the cells and to provide additional nuclear safety.

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PAPRNATE DATA Auxiliary hot areas within the facility include the hot change room, the hot machine shop, the equipment decontamination room, storage areas for sup-plies, equipment, and casks, the service gallery and loading dock, and the service corridor.

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The operating gallery is a normally clean area encompassing the operating faces 'of the cells. Work performed in this area inc'ludes remote hot cell operations, photography, and other normally clean operations.

1.2.3. TRIGA Reactors Building (Bldg. 21) (8471 ft )

Located north of the Laboratory Building, the TRIGA Reactors Building provides an area for diversified experimental and irradiation studies using the inherently-safe TRIGA Mark I and Mark F reactors. Included within the building are associated reactor control consoles, a low-level counting room, a small shop, a neutron beam tube room, and the reactor's administrative of-fices. In addition, a contiguous "away from reactor" irradiated fuels lab-oratory exists. This laboratory utilizes the facility previously occupied by the Mark III TRIGA reactor decommissioned in December 1975.

Specific uses of SNM in the reactor portions of the building are gener-al? y governed by the terms of Utilitation Facility Licenses R-38 and R-67.

SNM that is not within the reactor pools may be under our NRC SNM-696 license as is the material in the "away frcm reactor" laboratory.

Within this building only the reactor pools present any significant decontamination problem in decommissioning. The reactor pools are typically 20 or 25 ft. deep. Their diameter and shape varies as illustrated on Figure 1.5. The Mark I pool holds approximately 4000 gal. of water. The Mark F pool and its storage channel holds approximately 24,000 gal. of water. The Mark III pool holds ~25,000 gal. of water.

Each of the pools have either an aluminum or steel liner. Surrounding the pool lines at the region nearest the reactor core is a concrete shield to assure that adjacent soil and soil waters will not be activated.

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O a 1.2.4 Experimental Area Facility I (Bldg. 27) (6188 ft 2)

This area consists of a building with approximately 10 laboratories, related offices for radiochemical, analytical chemistry and R&D work which frequently requires the close support of the researdt reactors. About 1100 ft of the total area is located in a nearby underground bunker which houses a high-level chemistry lab, three shielded boxes, and associated storage. The shielded boxes are constructed of epoxy coated stainless steel and incorporate mini-manipulators for handling in-cell remote processes.

2 1.2.5 TRIGA Fuel Fabrication Building (Bldg. 22) (7500 ft ) l The TRIGA fuel fabrication building, approximately 60 ft x 125 f t, is constructed of reinforced concrete prefabricated panels of about 7-1/2 in, thick for the walls. The roof is prestressed concrete approxi-mately 4 in.

thick. The building contains storage vaults, drum storage area, operations associated offices, locker and restrooms, as well as the fuel fabrication areas. The building has two truck roll-up doors and a personnel door, as well as an appropriate number of emergency exits to meet industrial safety require-ments. At one end of the building is a pad providing outside space for a bottled gas farm, liquid nitrogen storage tank, air-conditioning units, high-efficiency air filter plenums and blowers, etc. , which require routine ser-vicing by persons not needed in material access areas.

2 1.2.6 Excerimental Building (Bldg. 9) (54,090 ft ) ,

This building houses offices, engineering and metallurgical, as well as chemical pilot plant activities. The major activity involving the use of radioactive material is the chemical pilot plant activity. The metallurgical and chemical pilot plant work areas are subjected to the appropriate centrols to minimize the possibility of uncontrolled spread or release of radioactivity to other areas. Support personnel for activities involving radioactive mat-erial use a fraction of the office space available. The other offices are used by support personnel for other projects, telecommunications, and medical.

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2. RADIOLOGICAL SAFETY MATERIAL CONTROL ORGANIZATION GA Technologies Inc. has established an organizational structure which provides for independent management review and approval of all work involving radioactive materials. The facility managers have jresponsibility to implement work in accordance with approved work plans. Licensing and Nuclear Compliance l (LNC) establishes policies and criteria applicable to work plans to assure that radiological exposures are "As Low As Reasonably Achievable" (ALARA),

material volumes are minimized consistently, and the activities are consistent with applicable licenses and the state and federal regulations. LNC also accomplishes various inspections and engoing surveillances to monitor personnel exposures and assure that work is being accomplished in accordance with the approved work plan. LNC maintains the liaison with State of California and Federal agencies effecting requirements upon our licensed activities.

Details of the organization structure and rcspective responsibilities can be found in the SNM-696 license. More specifically information can be found in SM4-696, Part II - License specifications, sections 3 and 4 The extensive capability of the Health Physics Department is described in section 4 of the -

S:N-696 Demonstration Volume.

The relevant components of this organization would be maintained to re-view and monitor the decccmissioning activities to assure that regulatory and license requirements are met. ,

2-1

3 DISCRETE FACILITY PLANS I

3.1 SORRENTO . VALLEY FACILITIES 2

3.1.1 Fuel Manufacturing Bldg. (Bldg. 37) (116.048 ft )

The SVA Fuel Fabrication Facility has been used to process uranium and thorium into HTGR fuels. Radioactivity in this facility is largely that of materials within process equipment, with some contamination of the walls, floors , etc. Typical wall, floor and structural surfaces have contamination 2

levels of the order of 500 dpm (a)/100 cm ,

The basic plan would be to remove all radioactive materials from process equipment. All excess material would be transferred to another licensee or disposed of at a licensed burial site. Appropriate closure and surveys would be made to assure that material accountability requirements are met. Process equipment would be cleaned as appropriate, packaged for transfer to another fuel facility or to authorized burial. Once valuable equipment is removed, conventional decontamination using soap and water can begin, removing surface contamination using successive top to bottem clean downs. Limited sand blast-ing and facility substructure removal will be acecmplished as necessary. This may apply to 10% of the facility structures.

When surfaces above floor level have been essentially all decontaminated, the floor surfaces will be decontaminated by a ccmbination of sandblas;ing, ,

chipping or complete removal as appropriate. Hot drains beneath the floor will be removed to assure that no radioactive materials have leaked into adjacent soil. More specific details follow.

Basic assumptiens used in the SVA decommissioning are:

! 1. The building will contir.ue to be used in other industrial activities i

not involving radioactive material.

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2. All nuclear fu3l cnd th2ir scrcps will be accounted for and transferred to another licensee or returned to the government.

3 Equipment of value may be sold and/or transferred to another licensee. j

4. NRC Safeguards approvals will be obtained prior to embarking on the facility decommissioning.

5. Building ventilation systems will be operated to control airborne concentrations and dispersal of radioactive material.

Following the removal of process materials and valuable equipment, a contamination survey will be conducted. These data will be used to classify areas according to severity of cleanup required. Specific procedure and coded maps will be developed to guide the decontamination effort. They will be ap-proved by Health Physics.

Logically one of the steps would be to remove equipment used in the pro-cessing of the material. Coaters , grinders , blenders, furnaces, screening machines are examples of such equipment. Such equipment would be placed in '

wooden boxes nominally 4'x4'x8', each box limited to approx. 0.5 ton. Our estimates indicate 170 boxes will be required with a total volume of 21.8 x 10 ft .

Next, structures not considered part of the base building would be dis-mantled and similarly packaged. Equipment platforms and support mezzanines are typical of such structures. Estimates indicate 6500 f 3t of this material.

This will require on the order of 50 boxes of up to 1 ton each.

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With equipment and substructures removed, the top to bottom cleandown will begin. Extrapolating our ongoing experience of decontaminating the facility, we estimate that 10,000 gal, of mop water will be generated. Also generated will be approximately 500 ft3 of wipes, etc. If the radioactivity levels in the water prohibit the controlled release-to the sewerage system, the water will be concentrated and ultimately solidified with other wastes for burial. The wipes will be transferred to the waste processing facility for concentration, compactions and/or solidification.

Removal of residusi radioactivity on the basic facility structure may require sandblasting, chipping, etc. The estimated volume of sandblasting 3

materials and residue is 370 ft . These materials will be placed in approx-imately 50 metal drums and transferred to waste burial.

Finally waste drains, ventilation ducts, filter plenums and other col-lection systems can be removed, packaged and transferred to waste burial.

Radioactive surveys of the facility will be taken. Their results will be documented and made available to the Commission.

Following Commission approval, excavated areas will be backfilled and finished appropriate to intended new use.

3.1.2 HTGR Fuel Production Erecess Develoceent Building (Bldg. 39) (15,20p f t-) .

Up to one-third of the SV-B Building has been used essentially as a R&D la'coratory experimenting with HTGR fuels production processes. Radioactively contaminated areas outside specific equipment are small, well localized <20 d;m (c)/100 cm are typical for the facility.

Decontamination of this facility is not atypical of any routine decontam-ination involving moderate spill of particulate material in such a laboratory.

Maintaining ALARA dictates that major portions of the facility are routinely kept below the levels established for release to unrestricted access and/or use.

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Whilo na sp;cific d2ctnttmination plan syclu2ticn cf wast 3s gIniraticn has been developed for this facility or other general R&D labs, a general plan for all such labs is as follows.

1. Survey eacn area and identify sources of radiation by type, quantity and difficulty to clean up.

2. Excess material and equipment will be removed.

3. Areas of highest radiation / contamination will be cleaned and r emoved .

4. Repeat steps 1 and 3 as required until localized sources are r emoved .

5. Perform a top to bottom clean down.

6. Survey the laboratory.

7. Reclean as necessary.

8. Resurvey and document results and await inspection prior to NRC release from licensing.

3.1.3 Waste Processing Facility The waste processing facility will remain available during the decommis-sioning efforts for handling other facility wastes. Finally, this facility will be dismantled. We plan to deactivate the facility sequentially beginning with the dismantling of the trash compactor. Other surfaced work areas and buildings would then be decontaminated or dismantled as necessary and packaged for transport to burial. This includes removal of asphalt surfaces which are con taminated .

The volume of material resulting from the above will be approximately 3

10,000 ft . Of this, 5,000 ft will be slightly contaminated asphalt, con-crete, and building rubble.

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Contcmination icvals fcund in tha vicinity, but cutsida of actuel prc-2 cessing stations and equipment, is routinely less than 50 dpm ( )/100 cm ,

3.2 MAIN SITE 2

3.2.1 Laboratory Building (Bldg. 2) (119,370 ft )

The plans for decontamination of any laboratory involved with radioactive material would be to either decontaminate the laboratory equipment or remove it as appropriate. Refer to the general plan in Sec. 3 1.2. Ihis would be followed by iterative decontamination of any surrounding areas exhibiting raciventivity until surveys indicate acceptable levels.

GA routinely decontaminates these laboratories to assure that personnel exposures are at ALARA levels. Radiation levels of the order of <10 dpm (a)/100 cm or 100 dpm (Sy)/100 cm2 are routinely achieved after such a de-2 contamination activity.

2 3.2.2 Hot Cell Facility (Bldg. 23) (8000 ft )

The Hot Cells in 1978 and early 1979 were substantially refurbished with new windows, overhauled manipulators and renovated in-cell equipment. During this activity readily removable contamination was removed by a thorough clean down including the sandblasting of cell surfaces. Radiation levels of 3 mrem fixed ( Sa) were achieved with moderate effort involving 1200 manhours. ,

The plan for decommissioning the Hot Cell would include removal of radio-active materials in-cell and cell support equipment. Such materials would be i placed in appropriate packaging, typically Type A and is, or large quantity as

, authorized by DOT and NRC. A thorough washdown would be accomplished. W.ese i

residues would be processed in our waste processing facility. Residual radi-ation levels would be assessed. Sandblasting of the contaminated surfaces I would be accomplished to remove the radioactive material lodged on the exposed surfaces. Again a thorough washdown and a radiation survey would be acccm-l l plished.

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At this point, contact decontamination is probably feasible, and an evaluation of the options for final decommissioning can be made. Alternatives such as cell entombment, demol,ition or practica-bility for release to unre-stricted use would be evaluated. The selected alternative will be pursued with Commission concurrence. >

Believing that cell entombment would likely not be a desirable alterna-tive, we have considered the extreme case of complete demolition and transport to the nearest authorized radioactive burial site. The demolition of the Hot Cell facility will involve the packaging and transport of up to 20,000 ft3 of concrete as a worst case. To minimize the cost of disposal for such a large volume, engineering solutions such as surface chipping, etc. , will ba eval-uated.

3.2.3 TRIGA Reactors Building (Bldg. 21) (8471 ft )

The plan and cost estimates for the currently operated Mark I and Mark F TRIGA reactors is based largely on experience gained in the 2 Mw (th) TRIGA Mark III decommissioning (1975) and other decontamination activities accomp-lished at our Hot Cell as late as September 1978 through February 1979 Basic assumptions in the plan for decommissioning the TRIGA reactors' facility are:

1. The building will remain. as desirable for some f,uture use not neces-sarily involving radioactive materials or SNM.

2. The deco ==issioning will occur in two phases separated by time to allow short-lived (< month) isotcpes to decay, i

3 All radioactive fuels will be removed from the facility and disposed of via transfer to another licensee or to a government-approved repository pending reprocessing if permitted.

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4 Radioactivity levels prior to decommissioning will be at or below levels specified in Table I of Regulatory Guide 1.86 dated June 1974 Theseassumptionsarecon:istentwiththeabovd-mentionedregulatory guide. Note: In place entombment wf.11 not be considered for our research reactors. However, the reactor poci liners and the concrete shields surround-ing them may be left in place and buried if analysis indicates that they contain no significant radioactivity. Such evidence was presented in the Decommissioning of the TRIGA Mark III reactors (Sec. 3.2 3.4). In addition to the above, appropriate approvals or authorizations will be sought of Nuclear Research Regulation (NRR) .

3.2.3.1 Mark I Plan The fuel will be removed from the reactor and shipped to another lic-ensee, burial or repository facility. Any such shipments will be made in NRC i

l licensed packages authorized for such contents.

The non-radioactive components will be removed to interim storage await-ing final disposition, most probably sale to another reactor licensee or as junk. Such components would include the console, reactor bridge, rod drives and connecting rods, etc.

Radioactive components will be separated into two or more groups, e.g.,

those with relatively short half lives and these with much longer ones. The first group will be allowed to decay and be appropriately disposed of as Low Level or LSA waste. Such items may include: core grid plates, aluminum sup-port struc-tures, underwater storage racks, ion chambers, etc. Other items will likely include: control rods, lazy susan steel support structures, etc.

Pool water (_4000 gal.) frem the reactor tank will be sampled and ana-lyzed for radioactivity. The activity level of the pool water when the re-actor is operating is between 0.01 to 0.1 uci/cc. ppci/cc levels are achieved 3-7

S shortly after reactor operations have ceased. If radioactivity levels pro-hibit release to the sewerage system and cannot be removed with the resin bed exchange system, the water will be processed, concentrated and ultimately solidified with other wastes destined for burial. ,

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Having allowed the reactor to cool (26 months), one of two courses of could be followed:

1. Upon determination that radioactivity levels of the tank and biolog-ical concrete shield materials are within acceptable limits, we will fill the tank in.

2. If the radioactivity in the materials are excessive and long-lived, the tank and/or shield will be removed and disposed of at an appro-

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priately authorized waste burial site.

l 3.2 3.2 Mark F Plan The fuels will be removed from the facility in a manner similar to the I except that burial of HEU fuels is not considered as appropriate in of current safeguards policy.

The handling of components will be similar to that mentioned in the I plan above.

Radiation levels will be determined for the pool's steel tank and its inside layer of Gunite.

The radioactivity level of the pool water (24,500 gal.) will be deter-mined and disposed of in a fashion similar to that of the Mark I. Activity in the pool water is roughly that of the Mark I.

Portions of the Gunite layer and steel tank, as required, will be re-moved, packaged and disposed of as radioactive waste. Previous experience indicates that any induced activity in the concrete biological shield will be below 10 CFR 20 exempt concentrations.

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Upon verification of the above the tank will be filled and covered with a layer of concrete.

3.2.3 3 Mark III Pool J

The Mark III Pool is a remnant part of the TRIGA Hark III reactor facil-ity which was decommissioned 'in 12/10/75. Since the reactor's decommissioning the building and reactor pool have been used for certain "away from reactor" irradiated fuel experiments licensed under 10 CFR 70 and our Agreement State license. During the reactor's decommissioning calculations were made and measurements were taken to show that induced activity in the concrete bio-logical shield, as well as the soils beyond, were below those specified in 10 CFR 20.304 Refer to Docket 50-227, GA letter #100-634 dated 10/29/75.

The decommissioning of this facility will involve the removal of any experiment and experimental equipment, the removal and treatment of 25,000 gallons of slightly contaminated pool water, tank liner decontamination, and radiation survey. Upon commission verification of the contamination / radiation levels and approval for release to unrestricted use, the pool cavity can be backfilled and capped appropriate to next user requirement. ,

3.2.4 Excerimental Area I (Bldg. 27) (6188 ft )

The experimental Area building contains radiochemistry laboratories primarily associated with activation analysis of materials, fission product, etc., as well as analytical chemistry laboratories. Two of the labs have been equipped to use gram quantities of plutonium in solids, solutions and precipi-tates within closed enclosures such as gloveboxes.

The decommissioning of this laboratory facility will include special considerations for keeping plutonium contaminated equipment and residues separate from other radioactive wastes, i

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This building was designed and equipped as a radio chemistry facility, accordingly the floors and work surfaces were sealed. Special cabinets, hoods, sinks, etc., were provided to assure ease of cleaning and minimal contamination spread.

Routine decontamination is accomplished. Removable contamination outside work stations or surfaces is typically found to be <50 dpm (sy)/100 cm or2 less. In the plutonium work areas action levels for decontamination are 5 dpm (a)/100 cm .

Equipment such as hoods, sinks, cabinets, etc., not a part of building partitions would be removed. F1cor coverings would be removed.

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The facility would be decontaminated for eventual release to unrestricted use.

The waste volume generated from this facility is anticipated to be less than 2000 ft3; of this up to 350 ft3 may have slight plutonium contamination on the surfaces of metal glove bcxes and other used laboratory supplies or equipment.

2 3.2.5 TRIGA Fuel Fabrication Facility (Bldg. 22) (7500 ft ) l This facility has been used to manufacture uranium metal alloys and as-semble them into reactor fuel rods. The alloy operations involve essentially the conversion of enriched uranium metal into a UZr metal alloy and sizing the alloyed pieces with lathes, milling machine, and a centerless grinder.

The plan for decommissioning involves the:

1. disconnect and removal of production equipment;

2. removal of process specific facility equipment such as station ducts, elephant trunks, water cooling lines, etc.;

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3. decontamination of facility floor, walls and other surfaces remaining in the building.

4. releasing the facility for unrestricted use.

J During step 1, equipment of value to others will be cleaned appropriately and shipped. Such equipment may include the vacuum cooling furnace, several l athes, a milling machine, centerless grinder, portable welder, etc. Residual equipment will be cleaned of surface contamination and packaged for to author-ized burial, most probably as LSA wastes. An upper limit for the volume of such packaged waste is 500 ft.3 Materials removed in step 2 will be compacted and packed for waste buri-al. Such material can be placed in 1 or 2 4'x4'x8' wooden boxes.

The remaining facility surfaces will be contact decontaminated for eventual release to unrestricted use. Current contamination levels of the facility floors and walls are the order of 100 dpm (a)/100 cm and are well within established guidelines for release to unrestricted use. Typically the walls and ceilings have contamination levels of <20 dpm (c)/100 cm .

Routine duct surveys indicate the absence of significant radioactivity since the facility is generally free frca airborne radioactivity.

Decontamination waste waters, etc., will be removed to the waste pro- .

l cessing facility for final treatment and handling prior to transport to authorized burial. Only small quantities are expected.

2 3.2.6 Excerimental Building (Bldg. 9) (54,090 ft )

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This building is used for various pilot plant prototype and scale medel testing of fuel fabrication and reprocessing plant equipment. This facility I typically contains no significant radioactivity except inside the specialized equipment designed to contain high level irradiated material. Such testing involves depleted uranium, natural thorium and a few selected short-lived l

l isotopes to simulate fission products and serve as tracers.

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We would plan to remove any contaminated prototype equipment and carry ,

out any required decontamination in preparation for the buildings eventual release for unrestricted use.

Recently taken radiation and wipe surveys foun'd that contamination levels of approximately 20 dpm (n)/100 cm . There is no significant ( SY) activity.

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4. WASTE PROCESSING & DISPOSAL GA has facilities for processing radioactive materials, preparing them for shipment, and has experience in contracting for the transport and burial of such materials. The waste processing facilities,dnclude a compactor, waste solidification equipment, and liquid filtration equipment.

The waste processing facility will be the focal point for those wastes which are to be concentrated or solidified prior to transport to burial. It is expected such materials will be processed and packaged in a manner similar to our normal process waste streams.

Large equipment sub-facility structures, etc., will be packaged at the respective facilities surveyed and appropriately transported in accordance with DOT requirements. Typically such material is placed in DOT-approved containers to facilitate material handling, to control contamination spread and to meet regulatory requirements.

Our plans for disposal assume the availability of an authorized waste disposal site such as U. S. Ecology's site at Hanford, Washington.

We are aware, however, of the provisions of 10 CFR 20 affecting waste disposal and burial. No specific plans have been fermulated at this time which include burial at an authorized site locally, i.e., a municipal landfill or other property either government owned or private.

The waste processing facility is not used to process transuranic wastes.

Such wastes are packaged at the generating facility. These packaged wastes may or may not be transported to the waste facility while awaiting transport to burial. Most likely such material could not be buried at Beatty, Nev., but at seme other authorized facility. The volume of such material and its trans-l port cost are ccmparatively insignificant.

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Y TABLE 5-1 TABLE OF COSTS BY FACILITY

($000)

Structure Waste Packaging Equipment Decontamination Transport Facility Removal Demolition & Disposal Total Fuel Manufacturing #37 $ 759.0 $ 228.0 $4,E78.0 $5,565.0 Fuel Prod. Proc. Dev. #39 -

40.0 -

40.0 Waste Processing Facility -

100.0 100.0 200.0 Laboratory Building 70.0 46.0 134.0 250.0 Hot Cell

• 1,600.0 400.0 600.0 2,600.0 TRIGA Reac., Mark I & Mark F 225.0 100.0 550.0 875.0 Experimental Area #27 3.0 6.0 6.0 15.0 TRIGA Fuel Fabric. Fac. #22 100.0 200.0 150.0 450.0 Experimental Building #9 -

10.0 10.0 20.'d SUBT0TAL 2,757.0 1,130.0 6,128.0 10,015.0 Contingency 3,000.0 TOTAL $2,757.0 $1,130.0 $6,128.0 $13,015.0**

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• Does not include complete demolition of Hot Cell estimated to cost $500,000

• • The Waste Yard was decontaminated in 1985.

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6. FINANCING The license condition imposing this plan's submittal requires that it discuss "the financial arrangements that have be6n made or will be made to insure that adequate funds will be available to cover the costs at the time of decommissioning.

GA Technologies Inc. has operated its facilities since 1957 under government contract or licenses issued by state and federal regulatory agencies. During this period we have decommissioned several principal projects and their facilities. Examples are:

(1) HTGR Critical Reactor Facility (R-104),

(2) Thermionic Critical Reactor Facility (CX-23),

(3) Accelerator Pulsed Fast Assembly (R-105),

(4) The 2MW TRIGA Mark III Reactor (R-100), used on a government space nuclear program, and (5) Waste Yard, used for all programs.

Each of these facilities was decommissioned and returned to other unrestricted use. Some of the facilities were decommissioned with company funds charged against accrued reserves while others were decommissioned with government fands.

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