ML20009H372

Decommissioning Plan

ML20009H372
Person / Time
Site:	07000734
Issue date:	06/30/1979
From:	GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:
References
13194, NUDOCS 8108100032
Download: ML20009H372 (37)

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GENERAL ATOMIC COMPANY l

DECOMMISSIONING PLAN

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GENERAL ATOMIC COMPANY DECO}DiISSIONING PIAN TABLE OF CONTENTS Preface / Introduction............................ iv 1..

General Facility Description...................

1-1 1.1 Flintkote Facilities.....................

1-1 1.1.1 Component & Fuel Manufacturing Bldg. (SVA) 1-1 1.1.2 HTGR Fuel Production Process Development Building (SV-3) 1-2 1.2 Main Site 1-2 1.2.1 Laboratory Building...................

1-2 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 Waste Processing Facility.

1-6 1.2.7 Experimental Building.................

1-7 2.

Radiological Safety Organization 2-1 3.

Discrete Facility Plans.

3-1 3.1 F11ntkote Facilities..

3-1 3.1.1 ' Component & Fuel Manufacturing Bldg. (SVA) 3-1 3.1.2 HIGR Fuel Production Process Development Building (SV-B). 3-3 3.2 Main Site 3-5 3.2.1 Laboratory Building.

3-5 3.2.2 Hot Cell Facility...................

3-6 3.2.3 TRIGA Reactors Building................

3-7 3.2.4 Experimental Area I Facility.............

3-11 3.2.5 TRIGA Fuel Fabrication Building............

3-12 3.2.6 Waste Processing Facility...............

3-13 3.2.7 Experimental Building.................

3-13 4.

Waste Processing & Disposal....................

4-1 1

5.

Cost Analysis..

5-1 6.

Financing.

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FIGURES 1.1 Plan View of Site j

1.2 HTGR Fuel Process Development Building 1.3 Hot Cell Facility Floor Plan 1.4 Plan View of the Hot Cell 1.5 TRIGA Reactor Building Floor Plan 1.6 TRIGA Reactor Facility Complex TABLES Table 5-1 Table of Costs by Facility 5-2 Table 5-2 Transportation and Burial Charges.

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i 13194 iii

GLNERAL ATOIIIC C0!TANY DECO:MISSIONING PLAN Preface.

General Atomic Company carries cut various activities which are licensed by the Nuclear Regulatory Commission and/or the State of California, an agree-ment state. These activities ca,a 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 Sici are licensed under S?cI-696; Docket 70-734. The byproduct and source material activities f

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.

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4 The plan gives general informatior on the methodology, costs and finan-cial arrangements considered relevant to the decocmissioning 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 i

be viewed as useful in the future.

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GENERm"~. ITOMC~

PRNMit11RTA 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 currently 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 nay be found in Sm!-696 renewal, Gulf E&EL Al2021 documents. Brief descriptions of the significant facili-ties are given below.

1.1 FLINTK01u FACILITIES 2

1.1.1 Component and Fuel Manufacturing Building (SV-A) (106,380 ft )

Located at 11220 Flintkote Avenue in Sorrento Valley north of the main complex, the Component and Fuel Manufacturing Building contains offices, shops, and an area used for fuel and componert fabrication. The building is 460 ft long and 120 ft wide with about two-thirds of the building of nigh bay construction. The east section of the building is divided into two floors for offices, a cafeteria, a laboratory and store rooms. Nonrelated activities carried out in the building include a machine shop, a sheet metal shop, and an assembly area for mechanical parts. 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 from other areas and activities.

Access to the fuel fabrication area is restricted to limit access to auth-orized personnel, to control Smi, to maintain control and monitoring of personnel, and to prevent the spread of contamination.

Separate ventilc-tion systems are maintained for facilities and areas involved in Smi pro-cessing.

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1.1.2 HTGR Fuel Production Process Development Building (SV-B) (15,200 ft )

Process development, pilot scale operaticus, and specialized fabrica-tion work related to fuel production ace conducted in a building adjacent co and north of the Component and Fuel Manufacturing Building. Process develop-ment is carried out in the east center portior. of the building within an area which has floor to ceiling partitions. The separate cutting, grinding, machining, and polishing operations, on other than SNM, is located in the southwest corner of the building. Figure 1.2 shows a plan view of the fac-111ty.

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.

1.2 IfAIN SITE 4

2 1.2.1 Laboratory Building (119,370 ft )

The Laboratory Building contains approximately 400 laboratories, offices, shops, and a few low-level caves for work with low-level raaio-activity. 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 laborator.12s are mostly covered with linoleum.

The walls are typically painted masonry or wa11 board. The radioactivity 2

found on these surfaces is usually <20 dpm/100 cm,

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2 1.2.2 Hot Cell Facility (6950 ft )

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The Hot Cell Facility is equipped to perfcrm 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 a high-level cell with three operating stations capa-l ble of handling activity levels of up to one million Ci of 1 MeV gamma, an adjacent low-level cell that can be used separately or in conjunction sith the high-level cell, and a metallog aphy cell equipped to provide complete l

metallurgical investigations including micro, metro, and stereo-photography.

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

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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.

The liigh-level cell, which is the largest of the cells and which has the most shielding, is 8 ft wide, 18 ft long, and 15 ft 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 lower 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 low-level cell is 10 ft long, 8-1/2 ft wide, and 15 ft high. The j

walls of this cell are formed by the high-level cell door, a 17-inch.-thick so'id steel door to the service area, a 36-in. front wall, and a 32-in.

ba a 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 othar two cells.

13194 1-3

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l The metallography cell measures 9 ft long, 5 ft wide, and 11-1/2 f t high. The walls are made of high densit-r concrete and range in thickness I

from 34 to 36 inches. Personnel access to the cell is through a 15-in.-thick l

solid steel sliding door to the service area. The front wall of the cell l'

has one operating station equipped with a viewing window, manipulators, and l

access holes. On the corner of the cell is an operating station equipped l

with a stereo-microscope and remote operated specimen stage for viewing snall 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 j

instrument is in use. When not in use the instrument is retracted into the l

cell wall, and a lead-filled shielding door located insice the cell is l

closed to protect the optical and electronic componatits.

l There are special storage tubes in the cells, one in the low-level cell floor and three in the high-level cell floor. 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 from the back wall of the cell and are located on 5 ft 6 M. centers. These tubes may be used to store radioactive and special nuclear materials to reduce radiation levels in the cells and to l

provide additional nuclear safety.

i Auxiliary hot areas within the facility include the hot change room, the hot machine shop, the equipment decontamination room, storage areas for supplies, equipment, and casks, the service gallery and loading dock, and the service corridor.

l The operating gallery is a normally clean area encompassing the oper-ating faces of the cells. Work performed in this area includes remote hot cell operations, photography, and other normally clean operations.

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1.2.3. TRICA Reactors Building (6730 ft )

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Located north of the Laboratory Building, the TRIGA Reactors Building provides an area for diversified experimental and irradiation studies usir.g the inherently-safe TRIGA Hark I and M rk 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 offf ces. In addition, a contiguous "avay from ructor" 1rradiated fuels laboratory exists. This laboratory utilizes the facility pteviously oc-cupied by the Mark III TRIGA reactor decommissioned in December 1975.

Specific uses of S :M in the reactor portions of the building are gener-ally governed by the terms of Utilisation Facility Licenses R-38 and R-67.

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

Within this building only the reactor pools present any significant decontamination pro;lem in decommissioning. The reactor pools are typi-cally 20 or 25 ft, deep. Thei.t diameter and shape varies as illustrated j

on Figure 1.5.

The Mark I pool holds apnroximately 4000 gal, of water. The Mark F pool and its storage channel holds approximately 24,000 gal of water. The Mark III pool holds 225,000 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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2 1.2.4 ' Experimental Area-I Facility (5800 ft )

l This area consists of a building with approximately 10 laboratories, related offices and a bunker for rsdiochemical analytical and R&D work which requires the close support.of the research reactors. There are about 2

1100 ft of the-total area located in a nearby undetground bunker which houses a high-level chemistry lab and associated storage. The facility is used mainly for radiochemical analysis work.

2 1.2.5 T/. IGA Fuel Fabrication Building (7500 ft )

The TRIGA fuel fabrication building, approximately 60 ft x 125 f t, in constructed of reinforced concrete prefabricated panels of about 7-1/2

-in. thich for the walls. The roof is prestressed concrete approximately 4 in. thick. The building contains storage vaults, drum storage area, op-erations 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 requirements. 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 plenurts and blower's, sec., which require routine servicing by persons not needed in material access areas.

2 1.2.6 Waste Processing Facility (61,000 ft )

This area is located 1000 ft east of the Hot Cell Facility.

Included in the area are a service building and various storage areas. Adjacent :o 2

j this facility are evaporation por.ds that occupy approximately 4800 ft and an incinerator for contaminated waste. Located within the service building is a trash compactor used to reduce volume of non-combustible waste.

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2 1.2.7 ' Experimental Building (45,000 ft )

l 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 metale lurgical and chemical pilot plant work areas are subjectea to the appropri-ate controls to minimize the possibility of uncontrolled spread or release of radicoctivity to other areas. The support personnel for these activities utilize a fraction of the offices available. The other offices are used by such groups as accounting, fusion engineering, etc.

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2. RADIOLOGICAL SAFETY MATERIAL CONTROL ORGANIZATION General Atomic Compary has established an organizational structure which provides for independent menagement review and approval of all work involving racioactive materials. The facility managers have responsibility to implement work in accordance with approved work plans. The Nuclear Material Control Division (NMCD) establishes policies and criteria appli-cable to work plans to assure that radiological exposures are "As Low As Reasonably Achievable" (AI ARA), material volumes are minimized consistently, and the activities are consistent with applicable licenses and the state and federal regulations. The NMCD also accomplishes various inspections and ongoing surveillances to monitor personnel exposures and assure that work is j

being accomplished in accordance with the approved work plan. NMCD main-tains the liaison with State of California and Federal agencies effecting requirements upon our licensed activities.

Details of the organization structure and respective responsibilities can be found in the SNM-696 license renewal documents. More specifically information can be found in SUM-696, Part II - License specifications (Gulf-E&ES-A12000), sections 3 and 4, as well as in SNM-696, Part I -

Demonstration Volume (Gulf EGES - A12001), sections 1 and '4.

The extensive i

capability of the Health Physics Department is described in section 4 of the 1

l Demonstration Volume mentioned above.

1 The relevant components of this organi:stion would be maintained to re-l view and monitor the decommissioning activities to assure that regulatory l

and license requirements are met.

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3.

DISCEITE FACILITf PLANS 3.1 FLIUTKOTE FACILITIES 2

3.1.1 Component & Fuel Manufacturing Bida. (SVA) (106,380 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 vall, floor and structural surfaces have contamination o

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

The basic plan would be to remove all radicactive materials frem pro-cess equipcent. All excess material would be transferred te another licen-see or disposed of at a licensed burial site. Appropriate closure and sur-voys would be made to assure that naterial accountability requirements are a

met. Process equipment would be cleaned as appropriate, packaged for transfer to another fuel facility or to licensed burial. Once valuable equipment is recoved, :onventional decontanination using soap and water can begin, removing surface contamination using successive top to bottom clean downs. Linited sand blasting and facility substructure removal will be acecmplished as ne cessary. This may apply to 10% of the facility struc-

tures, i

i When surfaces above floor icvel have been essentially all decontami-nated, the floor surfaces will be decontaminated by a combination of sand-blasting, chipping or complete removal as appropriate. Hot drains beneath the floor will be recoved to assure that no radioactive materials have 4

leaked into aljacent soil. Mote specific details follow.

Basic assumptions used in the SVA decommissioning are:

1.

The building will continue to be used in other industrial activities not involving radioactive material.

3-1

2.

All nuclear fuel and their scraps 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 an-other licensee.

4.

NRC Safeguards approvals will be obtained prior to embark-ing 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 cottamination survey will be conducted. These data will be used to classify areas according to severit e of cleanup required. Specific procedure and coded caps will be developed to guide the decontamination effort. They will be approved by Health Physics.

Logically one of the steps would be to remove equipment used in the pro-cessing of the material. Coaters, grinders, blenders, fudnaces, screening I

l 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 y

10 ft

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Next structures not considered part of the base building would be dis-mantled and similarly packaged. Equipment platforms and support mezzanines 3

are typical of such struccures. Estimates indicate 6500 ft of this mater-I tal. 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 j

facility, we estimate that 10,000 gal of mop water will be generated. Also 3

i generated will be approximately 500 ft of wipes, etc. The waste water and j

wipes will be transferred to the vaste processing facility for concentration, I

compactions and/or solidification.

Removal of residual radioactivity on the basic facility structure may l

require _ sandblasting, chipping, etc. The estimated volume of sandblasting 3

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

l Finally waste drains, ventilation ducts, filter plenums and other col-1ection 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.

1 Following C?mmission approvel, excavated areas will be backf1119d and finished appropriate t( intended new use.

2 3.1.2 HTCR Fuel Production Process Development Building (SV-B) (15,200 ft )

Up to ene-third of the SV-B Building has been used essentially as a R&D laboratory experimenting with HTGR fuels production processes. Radioactive-ly contaminated areas outside specific equipment are small, well localized and have low level concentrations. Building surface contamination levels of

<20 dpm (a)/100 cm ate typical for the facility.

Decontamination of this facility is not atypical of any routine decon-tamination involving noderate spill of particulate material in such a labor-atory. Maintaining ALARA dictttes that major portions of the facility are routinely kept below the levels. established for release to unrestricted ac-cess and/or use.

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s While no specific decontanination plan evaluation of wastes generation has been developed for this facility or other general R&D labs, a general plan for all such labs is as follows.

j 1.

Survey each area and identify seurces of radiation by type, quantity and difficulty to clean up.

i i

2.

Excess material and equipnent will be removed.

3.

Areas of highest radiation / contamination will be cleaned and removed.

1 4.

Repeat steps 1 anu 3 as required until localized sources are removed.

5.

Perform a top to bottort clean down.

i 4

j 6.

Survey the laboratory.

7.

Reclean as necessary.

1 i

8.

Resurvey and document results and await inspection prior to I

i NRC release from licensing.

d 1

1 i

3 13194 3-4

a 3.2 MAIN SITE 2

3.2.1 Laboratory Building (119,370 ft )

The plans for decontamination of any laboratory involved with radio-active material would be to either decontaminate the laboratory equipment or remove it as appropriate. Refer to the general plan in Sec. 3.1.2.

This would be followed by iterative decontamination of any surrounding areas exhibiting radi +ctivity until surveys indicate acceptable levels.

GAC routinely decontaminates these laboratories to assure that person-nel exposures are at ALARA levels. Radiation levels of the order of 2

2

<10 dpm (a)/100 cm or 100 dpm (SY)/100 cm are routinely achieved after such a decontamination activity.

J a

4 J

4 3-5

3.2.2 Hot Cell Facility (6950 ft )

The Hot Cells in 1978 and early 1979 wera substantially refurbished with new windows, overhauled manipulators and renovated in-cell equipment.

During this activity readily removable contamination was removt a thor-ough 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 radioactive materials in-cell and cell support equipment. Such materials would be placed in appropriate packaging, typically Type A and B, or large quantity as authorized by DOT and NRC. A thorough vashdown would be accom-plished. These residues would be processed in our waste processing facil-ity.

Residual radiation levels would be assessed. Sandblasting of the contaminated surfaces would be accomplished to remove the radioactive material lodged on the exposed surfaces. Again a thorough vashdown and a radiation survey would be accomplished.

At this point contact decontamination is probably feasible, and an evaluation of the options for final decommissioning can be'made. Alterna-tives such as cell entombment, demolition or practicability for release to unrestricted use would be made. The selected alternative will be pursued with Cocmission concurrence.

Believing that cell entombment would not be a desirable alternative, we have considered the extreme case of complete demolition and transport to the nearest licensed radioactive burial site. The demolition of the Hot Cell facility will involve the packaging and transport of up to 20,000 ft 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 be evaluated.

3-6 13194

2 3.2.3. TRICA Reactors Building (6730 ft )

The plan and cost estimates for the currently operated Mark I and Mark F TRIGA reactors is based largely on recent experience gained in the 2 Hw (th) TRIGA Mark III decommissioning (1975) and other decontamination activi-ties accomplished at our Eot 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 future use not necessarily involving radioactive materials or SMI.

2.

The deccmmissioning will occur in two phases separated by time to allow short-lived (< month) isotopes to decay.

3.

All radioactive fuels will be removed from the facility and '

disposed of via transfer to another licensee or to a govern-ment-approved repository pending reprocessing if permi ted.

4.

Radioactivity levels prior to decommissioning will be at or below levels specified in Table I of Regulatory Guide 1.86 dated June 1974.

These assumptions are consistent with the above-mentioned ragulatory guide. Note: In place entombment will not be considered for our research reactors. The reactor pool liners and the concrete shields surrounding them may be left in place and buried if analysis indicates that they contain no significant radioactivity.

Such evidence was presented in the Decomnissio-ning of the TRIGA Mark III reactor (Sec. 3.2.3.4).

In addition to the above, appropriate approvals or authorizations will be sought of Nuclear Research Regulation (NRR).

3-7

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 licensed packages authorized for such centents.

The non-radioactive components will be removed to interim storage awaiting final disposition, nost 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 those with much longer ones. The first group will be allowed co decay and be appropriately disposed of as Low Level or LSA waste. Such items may include: core grid places, aluminum support structures, underwater storage racks, ion chambers, etc.

Other items will likely include: control rods, lazy susan steel support structures, etc.

Pdol water ( 4000 gal.) from the reactor tank will be sampled and analyzed for radioactivity. The activity level of the pool water when the reactor is operating is between 0.01 to 0.1 Uci/cc. puci/cc levels are achieved shortly after reactor operations have ceased.

If radioactivity levels prohibit release to the severage system and cannot be removed with the resin bed exchange system, the water will ie transferred to the solar evap-orative ponds, concentrated and ultimately solidified with other wastes destined for burial.

Having allowed the reactor to cool (~6 months), one of two courses of action could be followed:

1.

Upon determination that radioactivity levels of the tank and biological 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 dis-posed of at an appropriately licensed waste burial site.

3-8

3.2.3.2 Mark Y Plan The fuels will be removed from the facility in a manner similar to the Mark I except that burini of IIEU fuels is not considered as appropriate in light of current safeguards policy.

The handling of components will be similar to that mentioned in the

~

Mark I plan above.

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

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 level in the pool water is rougtly that of the Mark I.

Portions of the Gunite layer and steel tank, as required, will be removed, 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.

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

3-9

r l

o

?

l l

l 3.2.3.3 Reactor Facility Waste Water Storage Tank l

This tank contains low level waste water typically from decon opera-tions or the drain from an occasional experiment.

l This plan provides for removing any waste water to-the evaporative 1

ponds for routine processing through the licensed waste yard activity. The tank internals may be decontaminated if practicable. Otherwise the tank l

will be removed, cut up and packaged for burial.

l l

l The concrete caisson which holds the tank will be surveyed for any leaked radioactivity. None is expected.

3.2.3.4 Mark III Pool The Mark III Pool is a remnant part of the TRIGA Mark III reactor facil-ity which was decommissioned in 12/10/75.

Since the reactor's decommission-ing the building and reactor pool have been used for certain "away from reactor" irradiated fuel experiments licensed under 10 CFR 70 and our Agree-ment State license. During the reactor's decommissioning calculations were made and measurements were taken to show that induced activity in the concrete biological shield, as well as the soils beyond, were below those specified in 10 CFR 20.304. Refer to Docket 50-227, GAC letter #100-634 i

dated 10/29/75.

The decoanissioning of this facility will involve the removal of any experiment and experi= ental 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 /

i radiation levels and approval for~ release to unrestricted use, the pool l

cavity can be backfilled and capped appropriate to next user requirenent.

3-10

3.2.4 Experimental Area I The experimental Area building contains radio chemistry laboratories

]

primarily associated with activation analysis of materials, fission product j

analysis, etc. Two of the labs have been equipped to use gram quantities of plutonium in solids, solutions and precipitates within closed enclosures i

f-such as gloveboxes.

The decommissioning of chis laboratory facility will include special considerations for keeping plutonium contaminated equipment and residues 1

j separate from other radioactive wastes.

J This building was designed and equipped as a radio chemistry facility, j

secordingly the floors and work surfaces were sealed. Special cabinets, i

hoods, sinks, etc., were provided to assure ease of cleaning and minimal i

contamination spread.

Routine decontamination is accomplished. Removable contamination out-i 2

j side work stations or surfaces is typically found to be <50 dpm (SV)/100 cm j

or less.

In the plutonium work areas action levels for decontamination are 2

5 dpm (a)/100 cm,

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

j

}

The facility would be decontaminated for eventual release to unrestrie-

)

ted use.

1 i.

1 The waste volume generated from this facility is anticipated to be less 3

j than 2000 ft ; of this up to 350 ft may have slight plutonium contamination on the surfa:es of metal glove boxes and other used laboratory supplies or equipment.

i 3-11

I 3.2.5 TRICA Fuel Fabrication Facility This facility has been used to manufacture uranium metal alloys and as-semble them into reactor fuel rods. The alloy operations involve essentially l

the conversion of enriched uranium metal into a UZr metal alloy and aizing the alloyed pieces vita lathes, milling machine, and a centerless grinder.

The plan for decommissioning involves the:

1.

disconnect and removal of production equipment; l

l 2.

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

l 3.

decontamination of facility floor, walls and other surfaces I

remaining in the building.

4.

releasing the facility for unrestricted use.

During step 1, equipment of value to others will be cleaned appropriately and shipped. Such equipment may include the vacuum cooling furnace, several lathes, a milling machine, centerless grinder, portable welder, etc.

Resi-l l

dual equipment will be cleaned of surface contamination and packaged for transport to licensed burial, most probably as LSA wastes. An upper limit l

3 for the volume of such packaged waste is - 500 ft.

Materials removed in step 2 vill be compacted and packed for vaste burial. Such material can be placed in 1 or 2 4'x4'x8' wooden boxes.

l The remaining facility surfaces will be contact decontaminated for ev-t entual 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 2

the walls and ceilings have contamination levels of <20 dpm (a)/100 cm.

13194 3-12

Routine duct surveys. indicate the absence of significant radioactivity since the fa:ility is generally free from airborne radioactivity.

Decontamination waste waters, etc., will be removed to the waste process-ing facility for final treatmen. and handling prior to transport to licensed burial. Only small quantities are expected.

3.2.6 Waste Processing Facilitz The vasta processing facility will remain available for handling other facility wastes. Finally this facility will be dismantled. We plan to de-activate the facility sequentially beginning with the dismantling of the combustible material incinerators and trash compactors. Then the evaporation panels would be dismantled. Finally other surfaced work areas and Butler buildings would be disnantled and packaged for transport to burial. This includes removal of asphalt surfaces which are contaminated.

l The volume of material resulting frca the above will be approximately 65,000 ft.

Of this 47,000 ft.3 will be slightly contaminated asphalt, con-

]

crete and building rubble.

Contamination levels found in the vicinity but outside of actual pro-2 cessing stations and equipment is routinely less than 50 dpm (a)/100 cm,

i j

3.2.7 _ Experimental Euilding This building is used for varioue pilot pinnt prototype and scale model testing of fuel fabrication and reprocessing plant equipment. This facility 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 isotopes to simulate fission products and serve as tracers.

3-13

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 found that contamination levels of approximately 20 dpm (a)/100 cm. There is no significant (SV) activity.

S 3-14

)

1 4.

WASTE PROCESSING & DISPOSAL GAC has facilities for processing radioactive materials, preparing them for shipment and has long term contracts for the transport and burial of such materials. The waste processing facilities include solar evaporative ponds, combustible waste incinerator, compactors and waste solidification equipment. These facilities have previously been described in detail in the SNM-696 renewal, Demonstration Volume (Gdf E&ES A12001), sections 3.12 and 3.13.

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

Large equipment sub-facility structures, etc., will be packaged at the respective facilities surveyed and appropriately transported in accordance with DOT requirements. Typically.such mat zial is placed in 4'x4'x8' wooden boxes to facilitate material handling, to control contamination spread and to meet regulatory requirements.

Our p1tas for disposal assume the availability of a l'icensed waste dis-posal site such as Nuclear Engineering's site at Beatty, Nevada. Disposal at this site is assumed for this costing effort.

We are aware, however, of the provisions of 10 CFR 20 affecting waste disposal and burial. No specific plans have been formulated at this time f-which include burial at an authorized site locally, i.e.,

a municipal landfill.or other property either government owned or private.

i i

The waste processing facility is not used to process transuranic wastes. Such wastes are packaged at the generating facility. These pack-aged wastes may.or may not be transported to the vaste facility while awaiting transport to burial. Most likely such material could not be buried rt Beatty, Nev., but at some other authorized facility. The volume'of such material and its transport cost are co:'paratively insignificant.

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PRWATE= DATA-5.

COST MIALYSIS The task of decornissioning each of the major facilitie has been l

broken down into work subtasks. The time and materials cost have been l

developed for the respective subtasks. From the analysis of c:ese costs and knowledge of the materials requiring disposal, overell costs for decomission-ing the respective facilities have been tabulated. Contingency factors have l

been considered and are indicated. Cost associated with property ownership t

l such as taxes, occupancy, depreciation, etc., are not included in this analysis because they do not directly relate to decomissioning activity.

The cost estimates for decomissioning the respective major facilities, as well as the miscellaneous R&D labs (lumped), are shown on Table 5-1.

The costs element associated with the transportation and burial charr,es are given in Table 5-2.

All the costs are stated in 15'79 dollars and assume continued availability of'lio nsed burial such as the Nuclear Engineering disposal at Beatty, Nov.

l l

t SENE!!AHrTOMIC'a-+-4 --W

-PRWkTE-DATA

""'dA @/0 13194 J

5-1

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PRIVATEDATA-TAF.LF 5-1 TABLE OF COSTS BY FACILITY

($000)

Structure Waste Equipment Decontamination Waste Transport Facility Removal Demolition Packagiag

& Disposal Total CASE I SYA

$531.0

$365.0.

$122.0

$389.0

$1,407.0 20.0 20.0 SVB TFFF 21.0 17.0 2.7 18.0 59.7 EA-1 20.0 25.0 5.0 6.0 56.0 L Bldg. Labs.

70.0 46.0 15.0 54.8 185.8 Mk. III Pool and Lab.

3.0 5.4 5.0 1.0 14.4 Ilot cell

• 154.0 332.0 136.0 140.0 762.0 Waste Yard 154.0 71.1 71.0 296.1 TRICA Facility Mk. I 4.5 9.6 5.0 1.0 20.1 1&. F 8.1 10.0 5.0 1.0 24.1 8.0 Sump Tank 2.0 4.0 2.0 Case I Sub-Total

$814.6

$988.0

$368.8

$681.8

$2,853.2 Contingency 1,127.0 TOTAL - Case I

$814.6

$988.0

$368.8

$681.8

$3,980.2 CASE II 960.0 llot cell (demolition)**

960.0 TOTAL - Case I & II

$814.6

$1948.0

$368.8

$681.8

$4,940.2

• Does not include complete demolition of Ilot Cell.

• • Includes llot Cell Demolition but not packaging and transport to licensed burial.

GENERAt-ATOMIC-e%4 4a;

-PRIVATE = DATA

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PRIVATE: DATA ~

TABLI: 5-2 l

TRANSPORTATION & BURIAL CHAP.GES Transportation Assumed sole use vehicle

$779/ load i

j' with 40,000 lb. gross ut. limit or 80 55 galb m drums or 18 Typical Boxes 3

Burial Charge (Basic)

$5.75/ft 55 gallon barrels C $52.00 each 4x4x8' boxes

@ $608.00 each i

[

l 1ENERAl= ATOM 10> d-##~*h PRWATE= DATA.

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• PRivhTEDali 6.

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

of decommissioning. We find that posting and maintenance of a bond for such j

purpose does not appropriately provide such insurance.

General Atomic has operated its facilities since 1957 under government contract or licenses issued by state and federal regulatccy agencies.

l During this period we have decommissioned several principal projects and l

l their facilities. Examples are:

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

l I

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

i l

(3) Accelerator Pulsed Fast Assembly (R-105), and (4) The 2MW TRICA Mark III Reactor (R-100), used on a government space nuclear program.

Each of these facilities were decommissioned and returned to other unrestrict-ed use.

Some of the facilities were decommissioned with company funds charged l

against accrued reserves while others were decommissioned with govern =ent funds.

l The costs identified in previous sections are relatively small in re-lation to the overall operations of GAC and the resources of CAC's owners.

It should be noted General Atomic Company is a partnership of Gulf 011 Corp-oration and Scallop Nuclear, Inc., a Royal Dutch /Shell Company. The rela-tionship of these companies to General Atomic and their financial responsi-bility have been described in our Smi-696 renewal Demonstration document, Gulf E&ES-Al2001, section I.

There has been no significant change from the information presented therein.

GENERAL.=ATGMIC %h-%

PRIVATE-BATA- *gle^ p% 13134 6-1

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GENERAL AToMcC COMPANY

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SAN DIEoo. CALIFORNIA 92138

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In ReE 7

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Refer to: 696-1065 gmss sooo June 15,1979 /

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V es. -

V Mr. Leland C. Rouse, Chief dj e

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Fuel Processing S Fabrication Branch g-g z

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1. ' l '. O 'o m Division of Fuel Cycle & "aterial Safety \\@3 4%

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U.S. Nuclear Regulatory Co:=ission

'9 Washington, D.C. 20555

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j~V SUM-696; Dochet 70-734. Submittal of Decor =1ssie

.y/

,i lan.

Sabj ect:

Dear Mr. Rouse:

General Atomic Company (GAC) received scendment #2 to its license. Accompany-ing the amendment were several new license conditions.

Submitted herewith is our plan for deco==1ssioning our facilities.

The attached plan generally describes the facilities in which licensed activities are accomplished. General Atomic does net anticipate any near term decommissioning of its facilities. The plans for decc=missioning each of the facilities must then be semewhat vague and general. We have heuever tried to anticipate (1) the level of effcrt recuired, (2) specific problens to be faced at each of the major facilities (3) che amount of wastes generated and (4) the costs and destination of waste burial.

The belated submission of this plan is in part due te our tr.itual interest in utilizing most relevant information available. As you were nade aware, GAC was involved in a major renovatien of our Hot Call from early fall 1973 to early spring 1979. This activity included cell decontamination, basic e : nip-ment replacecent, e.g.,

call seals, windows, etc., overhaul of ventilation systems, etc., as well as the packaging and abipnent of waste mr.terials.

From this experience more accurate extrapolatien to our total deco:rsissioning activity could be made. Not Cell renovation and related activity is now complete.

We believe that information presented in the plan shovs that the cost of deco:ninsioning uranium fuel f abrication facilities, research reactors, miscellaneous R&D laboratories, etc., to be sufficiently small that the Commission need not require set aside cash reserves, honds or other guar-antces such as may be appropriate for pcuer resctors, reprocessing facili-ties or plutonium Zuel fabrication facilitias.

We look forward to ycur conclusion of a review of nuclear facility decomis-sioning policy 5:hich is supportive of our ^3elief, namely that decorrtissioning costs of most Part 70 licenced uraniuc3-mk recessing facilities are sm:11 A D / g/

compared to resources available to n

CCC'ETW 3

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( myra > j 13134

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Leland C. Rouse 696-1065 Our plan contains private and financial information of the type described in 10CFR2.790. Accordingly we request that it be withheld from public disclosure.

Very truly yours, e

William R. Mowry

/

Licensing Administrator Nucles

A?.erials Control Division WRM:hes Attachments: 1.

10 CFR 2.790 Affidavit.

2.

General Atomic Company Decocmissioning Plan, dated June 1979, 4 copies.

13134

696-1065 June 15, 1979 AFFIDAVIT Issued pursuant to 10CTR 2.790(b)(1), Request for Withholding Infor-mation.

General Atomic Ccmpany is required to provide certain detailed infor-mation relating to its costs and plans for decorur.issioning their facilities.

This information is required by Condition #18 of NRC license 696; Dochet 70-734. The information supplied as attachment 2 to our letter 696-1065, dated June 15, 1979. is considered Private Data of the type within 10CFR 2.790(a)(4).

In addition certain facility descriptions and layouts may be within that classification under 10CFR2.790(d).

I certify that I have reviewed the above referenced submittal, Attach-ment 2 and approve of its withholding under 10CF"2.790(b)(1) and (d).

H. N. We11 houser

?Twne/f'l479 Date

//

13134