ML20011F486

Decommissioning Plan for Bmi Columbus Operations

ML20011F486
Person / Time
Site:	07000008
Issue date:	12/31/1989
From:	Battelle Memorial Institute, COLUMBUS LABORATORIES
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ML20011F484	List: ML20011F483 ML20011F486
References
NUDOCS 9003060106
Download: ML20011F486 (58)

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DECOPNISSIONING PLAN FOR THE BATTELLE MEMORIAL INSTITUTE COLUMBUS OPERATIONS-to V.S~ NUCLEAR REGULATORY COPHISSION DECEMBER 1989 Prepared by; BATTELLE k::16 505 King Avenue 4

Columbus, Ohio 43201-D 4823ohn8eM83l[ga ld

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t-TABLE OF CONTENTS

.P_ ale 1.

GENERAL INFORMATION 1-1 2.

DESCRIPTION OF PLANNED DECOMMISSIONING ACTIVITIES 2-1 2.1 Decommissioning Objective, Activities, Tasks, and Schedules.......................

2-1 2.2 Decommissioning Organization and Responsibilities....-.

2-20 2.3 Training 2-27 2.4 Contractor Assistance...................

2-28 References...........................

2-29 3 ~.

DESCRIPTION OF METHODS USED FOR PROTECTION OF OCCUPATIONAL AND PUBLIC HEALTH AND SAFETY 3-1 3.1 - Facility Radiological History Information.........

3-1 Ensuring that Occupational Radiation Exp(osures 3.2 are as Low as is Reasonably Achievable ALARA) 3-14 3.3 Health Physics Program 3-15 3.4 Contractor Personnel 3...................

3.5 Radioactive Waste Management 3-18 References...........................

3-22 4.

PLANNED FINAL RADIATION SURVEY.................

4-1 References.................-

4-1 5.

FUNDING 5-1 References............................

5-1 6.

PHYSICAL SECURITY PLAN AND MATERIAL CONTROL AND ACCOUNTING PLAN PROVISIONS IN PLACE DURING DECOMMISSIONING 6-1 iii l

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t LIST OF TABLES Pace TABLE'2.1 BATTELLE BUILDINGS TO BE DECOMMISSIONING LISTED BY CATEGORY OF CONTAMINATION 2-8 TABLE 3.1

SUMMARY

OF RADIOLOGICAL CONTAMINATION..........

3-3 j

TABLE 3.2 BATTELLE NUCLEAR SERVICES AND DECONTAMINATION PROCEDURES ARE DIRECTLY RELEVANT TO RADIOLOGICAL SAFETY 3-16 1

l LIST OF FIGURES Paae FIGURE 2.1 BATTELLE COLUMBUS KING AVENUE SITE WITH BUILDING NUMBERS..........................

2-2 i

FIGURE 2.2 BUILDING NUMBERS AND LOCATIONS AT THE WEST JEFFERSON SITE 2-3 FIGURE 2.3 BUILDING 3 IS AN EXAMPLE OF A CATEGORY 1 CONTAMINATED BUILDING 2-9 FIGURE 2.4 BUILDING JN-1 IS A CATEGORY 2 CONTAMINATED BUILDING...

2-10 FIGURE 2.5 BUILDING 6 IS AN EXAMPLE OF A CATEGORY 3 CONTAMINATED BUILDING 2-11 FIGURE 2.6 DECOMMISSIONING SCHEDULE FOR THE FIFTEEN BUILDINGS.....

2-21 FIGURE 2.7 DOE ORGANIZATION CHART FOR THE BCLDP 2-22

. FIGURE 2.8 BATTELLE ORGANIZATION CHART OF KEY MANAGEMENT POSITIONS FOR THE BCLDP DECOMMISSIONING OPERATIONS 2-24 FIGURE 2.9 EXPANDED BATTELLE ORGANIZATION CHART FOR THE BCLDP DECOMMISSIONING OPERATIONS 2-26 FIGURE 3.1 ENVIRONMENTAL MONITORING AT THE WEST JEFFERSON NUCLEAR 3

. SCIENCES AREA SHOWED EVIDENCE OF S0IL CONTAMINATION IN THE PROXIMITY OF THE ABANDONED FILTER BEDS AND THE STORM SEWER OUTFALL (AREA 1) 3-11 iv m

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1.,J' GENERAL INFORMATION:

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-Licensee Name:

.Battelle Memorial Institute:-

' License Address:

505 King Avenue, Columbus', OH 43201-2693-

< License Number:

SNM-7 J

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DESCRIPTION OF-PLANNED DECOMMISSIONING ACTIVITIES Battelle Memorial' Institute (BMI) has continuously performed government-sponsored nuclear research at.its facilities in central Ohio.

Fifteen buildings or portions thereof,- which became radioactively contaminated as a result of-performance of work under the government contract, ' are to be decontaminated.

This section describes the planned activities for the decontamination and decommissioning (D&D) of the fifteen buildings.

Only twelve of the buildings were involved in activities under SNM-7.

i Battelle plans to continue to operate under the current license conditions and to request renewal of the license at the appropriate time.

Decontamination of selected facilities is being undertaken at this time to make these facilities available for unrestricted use in non-nuclear activities.

In addition, all of the decontamination activities planned are within the provisions of the current license.

Accordingly, this Decommissioning Plan is being submitted to the NRC for information and does not constitute a declaration to terminate License No. SNM-7 by Battelle.

I 2.1 Decommissioning Objective, Activities, Tasks, and Schedules 2.1.1 Need for Actio_n The fifteen buildings are contaminated as a result of nuclear research and development activities conducted since April 1943 for the U.S. Department

- of Energy (DOE) and its predecessor agencies -- the Energy Research and Development Administration (ERDA) the Atomic Energy Commission (AEC), and the Manhattan Engineer District (MED), -- as well as for commercial clients.

The buildings are owned by(NRC) license.Battelle and the facility maintains an active Nu Regulatory Commission L

Nine of the facilities are located at Battelle's King Avenue site, Columbus, Ohio (Figure 2.1), and the remaining six facilities are located at Battelle's West Jefferson site, West Jefferson, Ohio (Figure 2.2).

Portions of the BMI King Avenue site have radioactively contaminated research facilities and equipment contained in buildings which range from 30 to 60 years, across the street from The Ohio State University.

A moderate density residential area,- a river which passes through the city, and several commercial and industrial areas are within 1/2 mile of this site.

The West Jefferson site consists of similar, radioactively contaminated facilities including a number of hot cells which are highly contaminated.

The D&D of the BMI facilities will enhance environmental quality and assure public health and safety.

Battelle will perform the necessary D&D activities in compliance with the appropriate regulations.

The Chicago Operations Office of DOE shall i

maintain health and safety cognizance of the D&D project.

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FIGURE 2.1.BATTELLE COLUMBUS KING AVENUE SITE WITH BUILDING NUMBERS 1^

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Sewe Gas of earn L r-S JN.1. Hot Cell Laboratory JS 1 Hot Isostatic Processing JS 8 Pipe Research Facility JN 2 Administrative Buliding Facility and Site Facilities JS.8A Pipe Research Facility

' JN 3 Decommissioned Research JS.2 Engineering and Pilot Plant JS.9 Storage Reactor Building, Gasification JS 10 High Energy Containment JN.4 Hazardous Materials Laboratories Building Laboratory JS.3 General Engineering Building - JS 11 Ballistics Shop Building JN 6 Guardhouse JS.3A Rocket Laboratory JS.12 High Energy Ballistics

~ JM 1 Esportu.untal Ecology and JS 4 High Pressure Laboratory Research Laboratory

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Health Serv %es JS.5 Pipe Research Facility JS.13 Saillstics Preparation Building JM 2 Greenhouse JS 6 - High. Energy Fabrication JS.14 Ballistics Preparation Building JM.3 Medical Research and Laboratory JS.148 Ballistics Preparation Building Evaluation Facility JS 7 High Energy Laboratory JS 15 Ballistics Assembly Building FIGURE 2.2. BUILDING NUMBERS AND LOCATIONS AT THE WEST JEFERSON SITE 2-3

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-C 2.1.2 Objective Thet overall objective of.' this D&D project is to return the fifteen contaminated buildings and surrounding sites to unrestricted use in a timely, radiologically, and environmentally' safe manner.

To meet this objective, several alternatives were evaluated.

Close Facilities and Continue S&M. This option involves leaving e-the-facilities-intact while continuing surveillance - and maintenance (S&M) activities and monitoring which are directed at preventing radiation exposure to workers, the environment, and the public.

However, these facilities are an integral part of the Batte11e's Columbus operations. Accordingly, closing the facilities and continuing S&M indefinitely is not a feasible alternative.

Close Facilities and No Further Action.

The option of closing the facilities and doing nothing further is not feasible because of the radioactivity left inside the facilities. The facilities cannot be-left unattended.

Entombment.

Entombment is the encasement of radioactive materials and components in a structure of concrete and steel.

The structure must be sufficiently strong and long-lived to ensure retention of the radioactivity until it has decayed to levels that permit unrestricted use of the site. The entombment alternative permanently precludes Battelle from using the affected. facilities for alternative activities.

As noted earlier, these facilities are an integral part of Batte11e's Columbus operations.

Accordin to be a feasible alternative. gly, entombment is not considered Safe Storace Followed by Deferred Dismantlement.

Safe storage involves activities required to place and maintain facilities in a condition-such that risk to public safety is within acceptable bounds -and the facilities can.be safely stored for as long as desired.

This involves some facility and-site ' preparation followed by a period of continuing care that includes security and S&M.

Following the storage period, deferred dismantlement

.is initiated.

Safe storage with deferred dismantlement is not the preferred decommissioning alternative for the Battelle facilities, because it involves higher radiation exposures (estimated to be 6 man-rem per year deriving from S&M activities during the safe storage period) and higher. cost than immediate dismantlement.

Immediate Dismantlement.

This decommissioning alternative

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involves D&D of all the facilities designated for decommissioning operations. This includes removal from the sites of all fluids, piping, equipment, components, structures, and waste having radioactivity levels greater than those permitted for unrestricted use of the property.

This is the best alternative to meet the overall objective of the project based on radiation exposures.

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- Based-on an: evaluation of alternatives, within the overall objective' of returning the _affected buildings and ' sites to unrestricted use, immediate

. dismantlement'was selected with the following technical objectives:

Remove-and dispose of all contaminated equipment, and I

decontaminate or remove and dispose of the contaminated portions of the buildings with minimum costs consistent with safety, health, security, and environmental considerations in accordance with applicable regulations.

Perform the decommissioning o)erations in accordance with ALARA (as low as reasonably achieva>1e) principles-L Perform the technical decommissioning operations within the-budget and time allocations.

Meet the requirements of the NRC regulations.

To accomplish the overall objective, the proposed activities and tasks of the D&D project will. include the following:

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(1) Conducting pre and post D&D radiological characterization surveys of eacn building and the surrounding areas.

F (2)

Removal of spent fuel, special nuclear and source material, LLW, TRU, and hazardous material required to prepare buildings for -

D&D.

(3)

Planning, engineering, and procuring for the D&D tasks.

(4)

Surveillance and maintenance.

(5)

D&D'of the 15 buildings and surrounding grounds, as necessary.

(6)

Packaging and transportation of all D&D waste to an appropriate storage or disposal facility.

(7)

Independent radiological verification surveys.

(8)

Restoration, as required, of buildings for structural integrity or safety.

As described in-the following sections, the type of operations required to achieve the objectives will vary among the buildings and the areas surrounding the buildings involved, depending on the nature of the previous radioactive material operations.

The concept of ALARA (as low as reasonably achievable)

I dose rates-for the workers is an important part of this technical objective.

The objectives will be achieved by utilizing a suitable mix of experienced Battelle staff and subcontractors. Battelle has a core of staff experienced in nuclear operations, waste management, and health physics.

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- and upon cost considerations.

The number of subcontractors utilized will be

limited so.that an experienced core of workers will be developed who will be able to carry out the decommissioning operations in a safe, cost effective, and efficient manner.

9 2.1.3 Description This section describes the overall plan to accomplish the activities and tasks proposed for D&D of the fifteen buildings and sites.

2.1.3.1 Brief History of Batte11e's Nuclear Activities As noted earlier, nine of the buildings involved in the decommissioning are

' located at the King Avenue site.

The nuclear research [2.1,2.2]

which was performed in the nine buildings includes processing and machining of enriched, 1

natural,'and depleted uranium and thorium fuel element fabrication, radio-tracer

. studies, radiochemical analyses, and powder metallurgy studies.

In addition, secure vault storage for accountable huclear material was provided in one of the buildings.

3 The remaining six buildings involved in the decommissioning project are located at the West Jefferson research site in two areas: (1) the Engineering Area in the southeastern portion, (2) the Nuclear Sciences Area in the northern -

portion. The majority of the nuclear research activities were conducted at the Nuclear Research Area.

However three buildings in the Engineering Area were also used for some nuclear resea,rch and are contaminated.

The oldest and most highly contaminated building in the Nuclear Sciences Area is the Hot Cell Building (JN-1). This building began operation in 1955 and has been-used continuously for nuclear research studies. Work conducted there t

included examinations and evaluations of power and research reactor fuels; post irradiation examination of fissile, control rod, source, -and structural materials and components; and examination of irradiation surveillance capsules.

'In addition, the facility has been the site of radiation source encapsulation, I

and physical and mechanical property studies of irradiated materials and structures.

The two other buildings at the Nuclear Sciences Area which are included in the decommissioning project are the old Critical Assembly Laboratory (JN-2) and the partially dismantled-Research Reactor Building (JN-3).

Both of these buildings are significantly less contaminated than the Hot Cell Building.

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old Critical Assembly Laboratory was originally used for reactor critical L

assembly experiments, direct energy conversion experiments, experiment assembly, g-special nuclear materials handling, and plutonium research activities.

Active i

nuclear experimentation in this building was terminated in 1970. Since then it has been used for administration offices.

However, it still houses a special nuclear materials vault and a radiochemistry laboratory which supports health physics and site environmental activities.

2-6

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The Battelle Research Reactor (BRR) was actively used from 1956 until 1974.

i I.t:was then partially-dismantled and its license changed to a possession only J

under SNM-7.

Since then it has been used for short term waste storage.

L The three, buildings at the Engineering Area which are included in the decommissioning project were used for fuel element fabrication and ballistics studies.

The Hot Isostatic-Pressure Bonding Facility was used to fabricate h

-military reactor' fuel elements using the hot isostatic pressure (HIP) fabrication technique. The other two buildings were used for studies involving

' explosive forming and bonding techniques and for ballistic studies using I'

nuclear materials.. These facilities are not under NRC license.

Section 3.1 provides detailed radiological history information.

L 2.1.3.2 Assessment of Contamination Levels Based on the past history of operations and the -levels of contamination present, the facilities undergoing D&D can be placed in three separate categories:

Category 1 - widely contaminated with low radioactivity levels; E

Category 2 - high radiation fields and extensive contamination in the hot cell L

and lower levels of contamination in the operating areas; Category 3 - low level contamination of isolated sections in-otherwise uncontaminated facilities.

Category 1.

Category 1 defines contamination levels which vary from low to moderately high and which are widespread throughout the building.

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buildings in this category are contaminated above background levels over wide areas of floors, walls, and ceilings, and contain contaminated equipment. Four l

buildings have this level of contamination as indicated in Table 2.1.

A typical example of such a contaminated building is shown in Figure 2.3.

Decommissioning this category building will require complete isolation of the building prior to L

initiation of -the operations.

All of the operations unrelated to L

decommissioning will be relocated, and uncontaminated equipment will be surveyed and removed from the facility. prior to decomissioning.

Category 2.

The Hot Cell Facility, Building JN-1, is the only-Category 2 building among those to~ be decomissioned (Table 2.1).

The operating cells of this bu'1 ding have very high radiation fields and extensive contamination on the ceilings, walls,. and floors.

The equipment inside the cell is also highly contaminated.

Other areas in the building have lower levels of contamination.

Decomissioning of this building will require special and remote operations, and extensive radiation protection precautions.

Figure 2.4 shows the highly contaminated areas of this builaing.

Cateoory 3.

Category 3 includes buildings which are only partially contaminated.

Non-nuclear research programs are currently being conducted in L

some areas of these buildings adjacent to areas scheduled for decommissioning.

Proposed decomissioni&g activities for these buildings include isolation of the areas to be decomissioned, and establishment of access control and other administrative procedures to prevent the spread of contamination during decomissioning.

A typical example of a Category 3 building is shown in Figure 2.5.

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BATTELLE BUILDINGS TO BE DECOWISSIONED f

LISTED BY CATEGORY 0F' CONTAMINATION-i c

L l Building Number Category

• H Kino Avenue Site Building A 3

Building 1 1

n Building 2.

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Building 4 3

Bui_1 ding 5 3

Building 6 3

Building 7

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Contamination level varies from low to moderately high and is widespread throughout the building, t

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Category 2:

Highly contaminated in hot cells; low to moderate contamination in other work areas.

Category 3:

Generally low contamination levels in small number of rooms.

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! '^" ' '^ I ' y e Periscopes and Microscopes e StorageCasksandContainers e CablesandSlings e TransferMechanism FIGURE 2.4. BUILDINGJN-115 A CATEGORY 2 CONTAMINATED BUILDING 2-10

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-2.1.3.3. Planning and Assessment u

Planning includes the preparation of project planning documents which will

- control and guide the decommissioning operations, preparation of documents to-L

-meet regu atory and institutional requirements, preparation of a cost estimate l

for the decomissioning operations, site characterization, and performance of operations in preparation for decontamination.

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Decomissioning of each building will be conducted as a separate campaign.

Therefore, a. separate Decommissioning Work' Plan is being prepared for each building. The Decomissioning Work P' ans include the following subjects:

Organization of the Project Decomissioning Operations Concept Safety and Environmental Assessment Decomissioning Operations Plan Work Breakdown Structure Decomissioning Operations -Schedule Waste Management

• - Support Functions.(QA, Health Physics, Radiological Safety Training)

The Site Characterization Plan (SCP) provides guidance for radiological characterization of locations surrounding the buildings to be decomissioned.

The SCP sets forth the procedures for a detailed characterization.

It includes the following subjects:

Site Sampling Plan Generic sampling approach for areas around buildings Sample analyses i

Reporting procedures Responsibility for Site Characterization Organization Relationships.

Concurrent with document preparation are the Surveillance and Maintenance l

(S&M). activities.

These operations are necessary to assure that the type _ and-L level of contamination in the fifteen buildings remains fixed and is not l

L inadvertently spread.

S&M activities include [2.3]:

J Environmental Monitoring -- a continued environmental

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monitoring program is required to maintain assurance that radioactive contamination has not escaped to the surrounding environment. The environmental monitoring includes collection and analysis of environmental water, air, soil, vegetation, agricultural crop, and sedimentation samples from areas surrounding the l

Battelle facilities. It also' includes maintenance of analytical and sample collection systems.

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• - Facility-Inspection and Maintenance --'this includes 1

regularly - scheduled inspection and maintenance of.

health,: safety, and radiation protection equipment and instrumentation.

A detailed schedule of inspection

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and maintenance is followed.

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' Operational' Health Physics -- a program of health l

physics radiation monitoring is conducted, including maintenance and' calibration of associated equipment and instrumentation.

A detailed schedule of health physics surveillance monitoring, personnel dosimetry, a

and equipment and instrument maintenance and calibration is followed.

Replacement of equipment, i

f filters, and filter -bed resins is performed as required.

All. S&M activities are conducted under an established nuclear quality assurance program. Emergency planning, training, and drills are also conducted as part of S&M.

4 In addition to the above activities, all fissile material was removed from the Battelle facilities and transported to the appropriate site for interim storage.

2.1.3.4 Decommissionino Operations The general sequence of D&D operations given below is based on the initial radiological survey _ information associated with the termination of research activities.

This general sequence will be defined specifically in the individual building D&D-lans as detailed radiological characterization information becomes availab e for each building.

Within the various categories of buildings, detailed and specific plans are being developed for.D&D of each building, since D&D of oach-building will-be performed independently of the other buildings.

- Each plan describes the sequence of-operations-in predecessor-successor

logic, the actual decontamination methods to be used and -the rationale for selection, waste management and other support functions, and schedules for completion of the work..

i 2.1.3.4.1 Cateoory 1 Sequence of D&D Operations The following is the proposed general sequence of operations for y

decommissioning Category I buildings:

1. Relocate the staff and non-nuclear operations from the building.

2-13

.g

~

-2.-Remove uncontaminated items including office furniture and

~

laboratory equipment.

3. Perform-a survey of the building and the equipment in the building to identify contaminated areas and equipment.

This will assist in selecting the appropriate decontamination -

procedures for specific areas.-

4. Prepare a staging area for handling and packaging contaminated equipment and waste removed during the decommissi'oning operations.

5. Remove contaminated furniture and equipment.

Decontaminate E

at a suitable location or dispose as radioactive waste as appropriate.

6. Design and install access control areas including. change rooms, showers, and a clean room.

7. Seal all

drains, vents, and other openings from the contaminated rooms to prevent the release of radioactive material during the decommissioning operations.

8. Remove exposed and contaminated plumbing, ducts, and electric s

equipment (including surface conduits and-hanging lights) and dispose as radioactive waste.

9. Decontaminate the floors, walls, and ceilings using the appropriate procedures as determined from the radiological surveys.

The principal decontamination method will be the removal' of the surface layers from the ceilings, walls and floors.

Care will. be taken to control the spread of contamination by the use of dust and liquid. collection

-equipment.

10...Remediate. sumps and sewer lines.

11. Perform interim radiological surveys to determine the progress and depth to which material must be removed to achieve complete decontamination.

12. When the radiological survey indicates.that the building has been successfully decontaminated and the waste removed, the independent verification contractor (IVC) will perform an independent confirmatory survey.

13. When the building is certified as releasable for unrestricted l

use, it will be - restored as required.

The restoration operations do not constitute a radiological hazard to the workers or the public.

2-14

y l>

2.1.3.4.2' Cateoory 2: Sequence of D&D Operations m

The-Hot Cell Building has been operated as a " closed system" with respect to release to the environment ~.- Thus, all radioactive materials handled-and' processed in the building,- and the associated waste generated were retained in the building.

The " closed system"' feature will be maintained - during - the decommissioning operations.-

The following is the. general sequence of

-decommissioning. operations:.

1. Continue throughout the decommissioning operations the

current, complete environmental monitoring procedures including sampling of air, water, and soil. These procedures-will be. modified - as necessary to-meet the needs-of the decommissioning project.

2. Prepare a staging area for handling and packaging contaminated equipment and waste removed during the decommissioning operations.

3. Remove all storage racks and other underwater equipment in the fuel storage pool. Volume reduce the racks and equipment and dispose as waste.

4. Clean the pool wall and floor surfaces with underwater vacuum cleaners.

5.' Reduce the volume of water in the pool using a water evaporation system.

Dispose of the slucge' residue by mixing in concrete.

6. Remotely remove'and dispose of stored waste and all equipment and fixtures in the cells and in other contamination control areas of the building.

7. Remotely remove surface contamination from the inner walls of

-the hot cells to reduce the radiation field to a level that will permit entry by workers.

8. Dispose of all waste generated by the remote cleaning operations in the cells.

9. Dismantle the hot cell rooms using appropriate methods which may include cutting, blasting, and core drilling operations.

For these operations a separate exhaust system from the building will be installed.

It will use HEPA filters to restrict the release of radioactive material to within regulatory limits.

10. Remediate sumps and sewer lines.

11., Dispose of the waste from the cell dismantling operations.

2-15

1 L

12. Clean the-remaining rooms in the building using appropriate methods.

13.Whentheradiolohcalsurveyindicatesthatthebuildinghas' i

been successfull decontaminated and the waste removed, the IVC will conduct an independent confirmatory survey.

i

14. When the building is certified as releasable for unrestricted use, it will be restored as required.

The restoration operations do not constitute a radiological hazard to the workers,or the public.

2.1.3.4.3 Cateaory 3: Sequence of D&D Operations

]

The primary concern during decommissioning operations in these buildings will. be to isolate the contaminated areas and. prevent the spread of contamination to clean - areas.

-The-following is the general sequence of operations proposed for_ decommissioning Category 3 buildings:.

1. Activities in clean areas adjacent or near the contaminated areas will be relocated.

l

2. Access control areas will be established near the contaminated areas.

The access control areas will provide for change rooms, showers, and clean areas.

3. Remove uncontaminated -items including office furniture and laboratory. equipment.

4. Perform radiological surveys of the contaminated areas and the equipment in those areas. This will' assist in selecting the L,

appropriate decontamination procedures for specific areas.

1

5. Prepare a staging area for handling and packaging contaminated equipment and waste removed during-the decommissioning operations.-

6. Remove contaminated furniture and equipment.

Decontaminate at a suitable location or dispose as radioactive waste as deemed appropriate.

7. Seal all

drains, vents, and other openings from the contaminated areas to prevent the release of radioactive l

i, material during the decommissioning operations.

3

8. Remove exposed and contaminated plumbing, ducts, and electric equipment (including surface conduits and hanging lights) and dispose as radioactive waste, u

2-16 l

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9.' Decontaminate the. floors,; walls, and ceilings using the

+

appropriate procedures as determined from the. radiological surveys..

The principal decontamination method will be the removal of the surface layers from the ceilings, walls and floors.

Care will be taken to control to spread of contamination by use of dust and liquid collection equipment.

a 1

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10. Remediate sumps and sewer lines.

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11. Perform interim radiological surveys to determine the progress and depth to which material must be removed to achieve complete decontamination, j

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12. When the radiological survey indicates that the area has been i

successfully decontaminated and the waste has been removed, the IVC will conduct an independent confirmatory survey,

13. When the area is certified as releasable for unrestricted use,

{

it.will be restored as required.

The restoration operations do not constitute a radiological hazard to the workers or the u

L public.

2.1.3.4.4 Soil Remediation 1

In some instances,-soil near or under the buildings may be contaminated.

The ground near'the buildings, especially along buried sewer lines, and under the buildings will be surveyed to ascertain the presence of radioactivity greater than naturally occurring for the vicinity.

All soil found to be-contaminated will' be evaluated to detemine the appropriate remedial action.

Such-action could include leaving it undisturbed, providing appropriate cover, or. removal and. shipment to a burial site.

The areas affected by the soil removal will be restored as appropriate.

2.1.3.5 Environmental Safety and Assessment

-Key environmental safety and health aspects of the D&D project _have been i

assessed.

In this assessment, the potential for radiological exposure and impacts on human health and the environment,.non-radiological impacts such as chemical, physical, and biological, and socioeconomic impacts focusing on transportat on and employment have been considered in detail.

Estimates of potential exposures which may be experienced by D&D workers,-

Battelle staff, or the public were derived based on information that is already available about the source term.

The results showed that unrier normal g-operations, the exposure rates in all D&D areas - will be well below the

- appropriate guidelines [2.4-2.7].

Even under upset conditions where all mitigative measures become inoperable, the estimated exposure was three orders

.I of magnitude and five orders of magnitude below these guidelines for West Jefferson and King Avenue, respectively.

2-17

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Addition' ally,in, the. conclusion was-that i

scenarios were considered for release of radionuclides to the environment. _ Aga such releases were extremely unlikely and that. the environmental consequences of. any release were

-insignificant.-

In any case, in the interest-of maintaining doses as -low as

-reasonably achievable, all pr'eventive,' administrative, and protective measures a

will be employed to the maximum practical extent. Additionally, monitoring of exposure rates, airborne concentrations, and surface contamination ~ will be maintained in the work area, adjacent areas, and peripheral areas to evaluate -

the effectiveness of contamination controls and to detect and ma) trends. Such'

' preventive:and mitigative measures will also prevent and control contamination transported by air movement - as well as by other transfer vectors.

These measures include:

t Enclosure and isolation of the work areas.

Control of traffic and movement of equipment and materials in and out of the work area enclosure.

Exhaust ventilation of the work area to maintain the enclosed

- area-negative with res)ect to surrounding areas and capture and remove from the ex1austed air stream a major portion of the aerosols with standard HEPA filters.

Change areas for workers in the staging area.

'i Continuous monitoring and sampling of the air in the D&D areas and in'the exhaust stream.

Use of personal dosimeters and breathing zone air samplers.

For. decontamination procedures such as certain kinds of blasting, scabbling, c. rilling, and spalling, a local exhaust pickup will be located as near as possible to the position where the aerosol is. generated.

Where. feasible, a fine water spray will be used to reduce the amount of dust which becomes airborne.

A-major portion of-the decontamination process' in the Hot s:

Laboratory will be done remotely with manipulators.

Use of approved containers for waste transfers.

In general, it is concluded that decommissioning can be. accomplished in a safe manner.

j 2-18 l

L b

2.1.4 Procedures Battelle will conduct the decommissioning activities and tasks in o

accordance with approved procedures which are responsive to Quality Levels I and

!! as defined.in the proposed QA Plan for the overall project. Administrative procedures, technical procedures, work instructions, and work permits are used l

to control activities in the conduct of D&D operations.

The processes to be controlled are:

Welding, cutting, and brazing Non-destructive examinations Chemical cleaning Grit and sandblasting i

Chipping and scabbling Concrete cutting Demolition processes Explosives handling Packaging radioactive wastes Packaging other wastes (non radioactive).

Individual procedures will be developed and approved for controlling each process and/or special process, and shall include:

Applicable codes, standards, and specifications Definition of responsibility Prerequisites including qualification and certification requirements Sequence of operations Acceptance criteria Record keeping requirements.

The procedures needed will be identified by the Project Technical Manager and developed by hods.the designated project staff.These documents are prepared by specified met Documents are prepared or revised in draft by task members, task leaders, or the Project Technical Manager. All documents are appropriately approved prior to-release or use.

I 2.1.4.1 Document Control All procedures are controlled. The review, comment, revision, and approval process for the procedures is documented. The Project Technical Manager or the Project QA Manager assigns the approvals needed for controlled documents. These documents require at least tw approvals in addition to the originator before implementation.

They also require a QA approval either by the Project QA

-Manager or the Nuclear QA Manager.

The Project QA Manager retains the original copy of the approval page, and l

is responsible for issuing copies of new and/or revised procedures to individuals designated by Project management to receive them.

The Project QA Manager maintains logs of document distribution.

He also publishes a monthly I

2-19

e log of all active project procedures indicating their revision status and date

- C of issue; this is distributed to predetemined, responsible personnel.

All l

project personnel are required to have the proper procedure in hand before work is started and assure they have the proper version of the document, j

Methods for document revision and accomplishing activities under approved, temporary procedures are specified.

The life of a temporary procedure is 1

limited to a maximum of sixty days. After sixty days, the temporary procedure

)

expires or must be incor> orated into an existing or new procedure. The Project QA Manager is responstble for assuring that the temporary procedure is terminated or incorporated into an existing or new procedure.

2.1.5 Schedules Decommissioning activities for the Battelle nuclear facilities began in 1988 with the initiation of Planning and Assessment.

Figure 2.6 shows the planned schedule for decomissioning each of the fifteen buildings and the surrounding site.

Development of the associated milestones is part of the preparation of the individual building D&D Plans.

Decomissioning of each of the 15 buildings is generally independent of each other. As shown in the project schedule (Figure 2.6), the activities for each building will be parallel.

Thus from Figure 2.6, it is seen that the critical path for the decomissic,ning activities is the timely completion of the activities of the building which will require the most time, Building JN-1.

5)ecific activities and milestones for decomissioning this building as well as t1e other 14 buildings are being planned as part of the building-specific D&D plans.

2.2 Decommissionino Oroanization and Responsibilities These D&D activities will be conducted by Battelle under contract to DOE through its Chicago Operations Office.

The D&D is referred to as the Battelle Columbus Laboratories Decommissioning Project (BCLDP).

Battelle will function as the decomissioning operations contractor (DOC) and will be responsible for all decomissioning operations including procurement of appropriate subcontractors, when needed.

The DOE organization chart showing the lines of authority and responsibility or the project is presented in Figure 2.7.

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HGURE 2.6. DECOMW5500MNG SCHEDULE FOR THE RFTEEN SUILDINGS 4

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Departmetnt of Departmetnt of Energy Energy Headquarters Chicago Operations i

DOE.HQ DOE.CH i

Direction and t

Program Manager

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Project Manager Surplus Facilities BCLDP Management

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Program Independent Verification Contractor Battelle DOC FIGURE 2.7. DOE ORGANIZATION CHART FOR THE BCLDP

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'2.2.1 Department of Eneroy - Chicano Operations (CH)

The Manager, CH, will be responsible for the field management of the BCLDP.

He will have line management authority for overall project implementation and contract administration.

The Assistant Manager for Project and Technology Management will select the Project Manager for the BCLDP and monitor project perfomance.

The Project Manager will be responsible for executing the specified scope of work.

i i

2.2.2 Decomissionino Operations Battelle will perfom or subcontract the performance of decomissioning operations, as necessary, to ensure that all activities are performed within the requirements for occupational radiological and industrial

safety, environmental srotection, site security, and cost and schedule.

Battelle activities wil' include preparation of detailed work procedures, engineering and design functions, decomissioning activities, property and waste disposal functions, and transportation of packaged waste material to a disposal site.

In addition, Battelle will be responsible for subcontractors' on-site work performance.

After the completion of decommissioning activities, independent verification surveys will be >erformed to ensure that decommissioned facilities are suitable for unrestrictec use.

I The Battelle organization chart of key decomissioning positions is presented in Figure 2.8.

The primary responsibilities for safety in decomissioning operations rests with this mancgement team. The Project Manager will be Dr. Joseph W. Ray. Dr. Ray has 30 years experience at Battelle in areas including nuclear systems safety and security and nuclear engineering and analysis.

He is a past chair of Battelle's Radiological Safety Committee and its Nuclear Safety. Subcommittee.

He has been responsible for planning and/or L

management of a number of major projects, including a reactor safety project for NRC. As Vice President of D&D Operations, Dr. Ray is currently ressonsible for managing work in nuclear D&D, health physics and nuclear operat'ons safety, nuclear quality assurance, and nuclear facilities operations.

The Quality Assurance Manager will be Donald E. Lozier.

Mr. Lozier has 37 years experience with Battelle in both nuclear materials and operations and quality assurance.

From 1972 through 1981, he managed the development, training,-and implementation of the Battelle Nuclear Materials Quality Assurance Program at the West Jefferson Nuclear Site.

During this time, Mr. Lozier was responsible for QA activities related to

safety, emergency

training, environmental radiological monitoring, personnel and facility radiological monitoring, radioactive waste packaging and transportation, and decontamination /

decomissioning of the pluton'ium laboratory facility. Mr. Lozier is presently Nuclear Operations QA Manager for the West Jefferson Nuclear Site.

I 2-23

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i DCLDP Decommissioning

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Operations Project Manager Dr. Joseph W. Ray t

Quality Assurance Manager

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Donald E. Lorier Health, Safety &

Decontamination Decommissioning Environment Operations Engineering a

Manager Manager Acting Marager 1

Harley L Toy V. Pasupathi

! Joseph W. Ray FIGURE 2.8.

BATTELLE ORGANIZATION CHART OF KEY MANAGEMENT POSITIONS FOR THE 3CLDP DECOMMI5510NING OPERATIONS k

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L 2-24

i The Manager of Health, Safety and Environment will be Harley L. Toy i

Mr. Toy has 30 years experience in nuclear materials accountability and regulatory compliance.

While serving as Batte11e's Nuclear Materials j

Accountability Representative, he supervised the management and control of all nuclear materials, implemented nuclear criticality safety and health safety, and coordinated security. Presently, as NRC/00E Compliance Coordinator and Site Manager for Batte11e's West Jefferson Nuclear Site, Mr. Toy is responsible for all experimental research and support services, including health physics, environmental monitoring, transportation, and safeguards.

The Manager of Decontamination Operations will be V.

Pasupathi.

Mr. Pasupathi has 12 years experience in Batte11e's Columbus Laboratories. His

]

areas of expertise include the design of irradiation experiments and the investigation of radiation effects on structures and materials. Mr. Pasupathi is currently Manager of D&D Technology for Batte11e's Nuclear Operations Department.

l The Acting Manager for Decomissioning Engineering is Dr. Joseph Ray.

]

An expanded organization chart for decomissioning operations is shown in Figure 2.9.

The positions shown in this chart will be filled by Battelle or subcontractor

staff, as

needed, to ensure safe decontamination and C

decommissioning operations. Battelle currently has 35 dedicated staff assigned J

to the BCLDP whose collective nuclear experience totals more than 700 person-years. These seasoned staff members have a wide breadth of kncwledge of nuclear and non-nuclear safety and well-tested abilities to identify and solve safety problems.

Battelle also maintains an independent Health and Safety Services Department (SS) which shares the responsibility for safe operation throughout Battelle by consulting, reviewing,lity to interdict any activities deemed to surveillance, and training in safety matters.

SS has authority and responsibi constitute an unacceptable environmental, radiological, or human health and safety hazard.

SS shares a 3 art of its responsibility for the control of potential radiological hazarcs with the Radiological Safety Comittee (RSC).

Review of decomissioning operations will be a primary function of the RSC. Like the SS, the RSC has the responsibility and authority to interdict any decomissioning operation believed to constitute an unacceptable potential for radiological hazard [2.8].

2.2.3 Oroanization Communications The BCLDP will require effective comunications between participants for routine matters and emer written or oral, among on gency conditions. Informal comun cations, either site project team members will occur as needed.

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The Battelle document on emergency plan and procedures for West Jefferson North (2.9) identifies the types of emergencies that might occur and the immediate responses to be taken.

The plan also presents the emergency communications procedures to be followed.

This plan will be modified as appropriate and used during decommissioning operations.

2.3 Trainino 2.3.1 Radiolooical Safety Trainino A radiological safety training plan has been developed as part of the overall decommissioning project.

Radiological training is administered by the Health Physics (HP) supervisor with the assistance of the Radiological Safety 1

Officer (RS0).

The HP supervisor is responsible for developing suitable training materials and modules, and for developing criteria for detemining and documenting training effectiveness.

l Training modules cover pertinent radiological safety information for operations staff, supervisor i

wearers, visitors, and womeny personnel, subcontractor employees, respirator at-risk.

Satisfactory completion of training is required before allowing any person to work in a radiation area. Retraining is l

required every two years.

Specific subjects in core training include:

biological effects of radiation, risks associated with exposure, ALARA and dose limits, radiation survey instruments, self-monitoring, doaimetry, personnel decontamination, and responsibilities of employees, subcontractors, and mana s)ecific training will cover

physical, chemical, gement.

Facility-and radiological claracteristics of materials involved and quantities expected in specific locations, and procedures for maintaining ALARA exposures.

This training plan will also cover contractor personnel assigned to 080 work.

Such personnel will be accepted only upon documented verification of successful completion of the training requirements.

2.3.2 OA Trainino All Battelle personnel serfoming process activities will be qualified by a related procedure and cert'fied. QA indoctrination and training are given by their Technical managers and the Project and Nuclear QA managers. This training is administered by means of classroom presentations, practical demonstrations, video tapes, readings, bulletins, and other means as appropriate.

The instruction is to ensure adequate knowledge of QA program requirements, g

familiarization with the technical procedures and maintenance of proficiency (retraining). Project training requirements are also documented in the QA Plan for inspection and audit personnel.

2-27

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. The Project Manager designates those who are to be trained and the Nuclear l

QA Manager maintains records of the attendance and proficiency,irements for and issues i

certification of qualifications.

Training and certification requ special process personnel, radiation

workers, etc.,

are controlled by requirements in procurement documents and technical procedures given in the QA j

Plan.

Requalification and recertification for special processes is performed at the frequency prescribed by the applicable procedure, code, or standard.

If there is none, requalification and recertification is performed every 12 months.

The Batteile Nuclear QA Manager and the Project Manager approve the personnel

)

qualified to perform $3ecial process qualifications and certification.

Subcontractors are required to provide evidence of qualifications and certifications of their employees to perform processes.

2.4 Contractor Assistance It is expected that Battelle will accomplish some of the decommissioning activities by using subcontractors. As discussed in Section 2.3, administrative l

controls are in place to ensure adequate health and safety protection during D&D activities employing contractor personnel. Placement of a contract is based on objective evidence of the contractors' capability and QA program, and/or successful past perfonnance, documented evidence of qualifications and certifications of the subcontractor employees, and successful completion of the t

radiological safety training program.

The evaluation is made jointly by the Project requestor and the Project QA Manager.

Since the scope of the D&D effort requiring contractor assistance has not been defined, information on subcontractor name, address, and license number cannot be provided at this time. However, this information will be compiled as the scope of activities is defined and the list of qualified bidders is l

developed.

2-28

j e

e REFERENCES 1

+

2.1 "Battelle Columbus. 40 Years of Energy Research for the U.S. Government",

)

Internal Report, Battelle Columbus Division, June 1984.

1 2.2 "The U.S.

Government and Battelle--Partners in Nuclear Research.

1943 - Present", Report prepared by Battelle for the U.S. Department of Energy, October 1985.

2.3 "Battelle Columbus Surplus Facilities Surveillance and Maintenance Program Plan, Revision 1",

Prepared by Battelle Nuclear Services, October 1989.

2.4

" Termination of Operating Licenses for Nuclear Reactors",

USAEC Regulatory Guide 1.86, June 1974.

_2.5' "Radionuclide Release into the Environment: Assessment of Doses to Man",

ICRP Publication 29, International Commission on Radiological Protection, 1978.

2.6

" Limits for Intakes of Radionuclides by Workers", ICRP Publication 30, International Commission on Radiological Protection, 1979-1982.

2.7

" Health and Environmental Protection Standards for Uranium and Thorium Hill Tailings", 40 CFR Part 192, Code of Federal Regulations, July 1988.

2.8 "CharteroftheRadiologicalSafetyCommittee(RSC)",BattelleColumbus Division Document, March 1989.

2.9

" Emergency Plan and Procedures, West Jefferson North", Battelle Columbus Division Document, Revised October 1989.

l 2-29 L

3.

DESCRIPTION OF METHODS USED FOR PROTECTION OF OCCUPATIONAL AND PUBLIC HEALTH AND 5AFETY 1

This chapter provides a description of the methods that will be used to ensure protection of workers, and the environment against radiation hazards during decommissioning.

3.1 Facility Radiological History Information Battelle has completed nearly 1000 government and commercially sponsored t

research projects involving nuclear materials since April 1943.

Since a description of these projects has been compiled elsewhere [2.1,2.2), the following section of this chapter is intended to provide an overview of Batte11e's involvement in this nuclear work.

Subsequently, more detailed information is presented of the current contamination status of the King Avenue and West Jefferson sites.

3.1.1 Overview Batte11e's first studies associated with atomic energy development began in 1942, on the fabrication of uranium, a metal whose properties had yet to be characterized.

The scope of atomic energy research was restricted initially, but increased rapidly after 1954, when the Atomic Energy Ccmmission (AEC) lifted restrictions on industry's involvement in atomic energy research/ development.

Batte11e's accomplishments in this field during the war years helped to make it possible to build and operate reactors for producing plutonium, not long after the feasibility of the chain reaction had been demonstrated.

Although the emphasis during the first decade of nuclear research was oriented heavily towards weapons development, by the early 1950s several different types of reactor systems were being assessed.

In the decade after World War II, nuclear-related research was greatly expanded at Battelle.

Development work on extractive metallurgy and plant corrosion resulted in an ion-exchange process which is the basis for recovery of most of the world's uranium.

Through a long association with the Naval Reactor Branch via the Naval Reactor Program, beginning in the early 1950s, extensive work was perfonned on alloy and fabricat< on process development, corrosion chemistry studies, and engineering analyses.

Nevertheless, reactor development was the main research theme throughout the first 20 years, and dominated Batte11e's research and development program.

The very nature of research being performed made it mandatory that a remote handling facility be built.

Thus in 1955, Battelle expanded the existing nuclear facilities by building the first privately-owned nuclear research center in the world. This facility -- the Nuclear Sciences Area, located at the north end of the Wast Jefferson site, included a research reactor, critical assembly facility, hot cells, and later a plutonium laboratory which has since been fully 3-1

' decommissioned. At the south end of the West Jefferson site, several autoclaves J

were. constructed, for use in hot isostatic pressing, a Battelle-developed i

technique for fabricating nuclear reactor fuel elements.

In the Hot Cell Facility, virtually all phases of experimentation connected with the radiation stability of materials have been conducted.

Evaluation of such experiments has formed the basis for developing better commercial nuclear fuels, control rod eaterials, and reactor structural materials. An additional i

capability of the Hot Cell Facility was created by the integration of a mechanical test cell to study the mechanical properties of irradiated materials.

Typical areas of research have included:

Postirradiation examination of commercial PWR & BWR fuel and control rod materials Nuclear fuel failure inspection Spent fuel shipping and storage container development Nuclear plant reliability analysis and qualification for NRC licensing Commercial reactor hardware testing and refurbishment The above overview gives some indication of the breadth and scope of Battelle's association with government and commercially sponsored nuclear energy research pro This background material leads naturally to a discussion on residualradgrams.ological contamination which exists as a result of the work which has been performed in previous years.

3.1.2 Current Contamination Status The basis of the current assessment of the radiological contamination in the various facilities at King Avenue and West Jefferson sites is the radiological survey information on the facilities.

The key findings of this 1983-1984 survey are presented in Table 3.1 which lists the locations of contamination within each building, the types of operations perfonned, the estimated contamination inventory, and the types of isotopes involved.

Results indicated a

significant amount of contamination in facilities / buildings which had been intimately associated with activities i

involving nuclear material, with contamination to a lesser extent in contiguous areas.

Radioactive contaminants which were detected were transuranics-(TRU),

mixed fission products (MFP), activation products, uranium, thorium, beryllium, carbon-14, and cobalt-60. The type of contaminant and extent of contamination varied from facility to facility, being dependent on the nuclear work previously performed. Most of the contamination at the King Avenue sites, for example, is due to uranium, thorium, and associated daughter products.

This status also applies to the South Area of the West Jefferson Site.

On the other hand, the g

bulk of TRU, MFP, and activation product contamination is confined to the Nuclear Sciences Area of the West Jefferson Site.

The contamination status of each building is described in more detail below.

3-2 t

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TAALE 3.1.

SipeWIRY OF RADIOLOGICAL CosimimTION In TNE BATTELLE FACILITIES i

i 3ervey Estlested Instrument Centaelmatien location */

1 Type of Reading leventory (Year Type of Bellding Activity /Arees use (dpolitecE) of Investery)

Redioisetepes Contaminaties i

4 I

A flisc RSS/

Encarselatten of 1.5 K - 200 K 10 CI ('73) 5, Ih, Brale system First, fourth highly enriched 5 daughters 3

1 floors for AIR feel elements; pliet 3

plant operation i

w I

Misc RBS/

Wrantes are 0.5 K - le K 0.3 CI ('M)

5. Th, Brain system, da First fl6er processing; ere daughters e pipment.

beneficiation enheest stack and ducts, stedles piping (sledge) 1 Feendry processlag of ore 1 K - 15 K 2.0 L! ('M)

W. Th.

(toes) daughters 2

feetal Werkleg Ore processing IK-4K

<1 CI

('MJ U-230, Trenches tab (tens); setal daughters; 5, (debris),

workleg Th daughters piping (sledge),

egelpeest, debris, sledge 2

Weldlag Lab noteral, enriched.

3 K - 15 K 10-3 CI ('M)

5. Th.

pipio, depleted W eelding daughters (sledge),

and fabrication treach (debeis),

ew i m et, stacks

. y.~

o l

i l

TABLC 3.1 (Centinued)

Servey Estimeted Instrument Contaminatten tscatlen*/

i Type of Ileading Inventory (Year Type of I

Building Activity / Areas Use (dyn/ISOce) ofleventery) medleisstepes Contaelmation i

2 flisc RSS/

IIeat treatment:

3.5 K - 5 K 10-3 CI ('M) 5, n, sobris/ sledge l pipes (sledge i

5econd floor electroplattag daughters 3

5-235 Area neceivtag and W

<1 Cf

('84)

5. Th, Pipes (sledge) i distrihetien daughters I

point for all enfrradiated i

w searce a 5-235 i

esterial 3

feelt Lab.

5-235 esterials, 5K-50K

<1 CI

('83)

W, Th, Sledge; boods, (1954-1975) dau6ters drain lines, t

metallographic trench 4

research; tons of (debris),

searce esterial egelpment, stacks

-l 3

Pueder seteral 5 storage 5 K - 30 K

<1 CI

('83)

5. Th, pipes leetallergy Las searce processing daughters (sledge);

trench (debris),

[

egelpeemt, l

stacks

[

3 seisc RSS Ceraefcs research; 8K-200K

<1 CI

('83) 5 Th, Pipes (sledge) metallegraphic (locallaed) daughters trench research eslag (debris),

[

tens of searce stacks t

esterial

?

i i

f i

1

.s

=. -..

+

TABLE 3.1 (Coatinued)

Servey Estlested i

instrument Cer,tanimation tocation*/

Type of Reading

' laveatory (Year Type of 4

Building Activity / Areas use (dpe/100 M )

ofInventory)

Radielsetepes Coatanteation 4

4 Radlecheelstry Radiaciwelcal IS

<1 CI

('M)

W. NP, Resideal Laboratory analyses daughters activity in rem 6laing i

sections of drata system W

4 Misc Labs /

Metall 50 K 0.1 CI ('M) 5, it, Piping.

E 5econd, fourth one atten (locallred) daughters; N P (sledge),

floors fact ity treach (debris),

eg=ipment 5

Machlee Shop Machielog and 1 K - 30 K

<1 CI

('M)

5. Th, Trench griedlag of daughters; N P (debris);

esteral, enriched, drala lines, depleted W; egelpeent llium ining i

5 Coating Lab Coatlag 6 K - le K 4.1 CI ('M)

5. Th.

Piping );

(sledge daughters; IEF e983petat, l

exhaust ducts.

l stacks i

I 5

Misc Ree/

Americion 2 K - 40 K

<1 CI

('M)

5. Th.

Piping l

First, second procession; daughters (sludge) fleers corrosion e*',

.w4 =

__,___._______._m__

TASLE 3.1 (Continued)

Servey Estiested Instrument Centaminetten location */

Type of Reading Inventory (Year Type of Building Activity / Areas Use (dpa/ISOcE) ofInventery)

Radioisotopes Centamination F

j 6

Misc ASS /

Alley studies; 1 K - 14 K

<1 CI

('M)

5. Th, Fleer drains i

Ground, first chemical analyses; daughters (sledge);

floors Co-40 Irradiation.

drain lines, 1

equipment, ducts w

1 Misc R88 Analytical I K - 100 K

<1 CI

('84) 3 Th.

Drain lines cheelstry on daughters (sledge),

searce enterials; trench (debris),

corrosien

~

equipment, enheest ducts 9

Misc RSS/

Mandling of NB

<I CI

('84) 5, Th, train lines i

Ground floor materal and daughters (sledge);

depleted 9; trench krypten studies (debris),

egulpnent i

l I

[

b

-t I'

TABLE 3.1 (Continued) l Servey Estimated i

Instrument Centasiesties Location */

i Type of Reedlag Inventory (Veer Type of Building Activity / Areas Use (dpm/lGOcsk) ofInventery)

Radleiseteses Centanteetion i

l JN-1 Ilot cells Feel element B

6,000 Cl**

N P; W, Th, Drain lines development;

('89) activatten (sledge),

enanlaation of pr

• ts (AP);

closed tank trradiated feel:

Co-40 (weter),

4 criticality egelyment experiments y

Jg.2 Former Feel element B

<1 CI

('M) 185, M P, AP Tanks I

w critical' development; (closed)*

assently lab; examination of stored water; Accountability. Irradiated feel; drain lines Lab; Radio-W-235, pistenfam (sledge);

chemistry lab storage; radio-trench chemical analyses (debris) j Jn-3 Retired Reacter studies; M

N TW, MP, AP

Piplag, research meterial trench hose of reacter irradiations contalement),

l enternal hold-1 ep tank l

(meter);

i enternal drain system; dralmage system (siedge)

Sellding surface contamination is common to all buildings.

An appresteete 24,000 Cl Co-60 source is present in the het cell and is expected to be sold er donated to another licensee.

W = not determined.

l m

3.1.2.1 King Avenue Site Buildino A (Corporate Office Buildino).

Previous operations in this building included the encapsulation of highly enriched uranium for ATR fuel elements. At one time, a substantial portion of the building was contamirated with uranium. Subsequently, all areas of the building have been decontaminated with the exception of approximately 200 linear feet of drain line, four floor drains and about 100 square feet of concrete. Contamination is due to uranium, thorium and associated decay products.

Buildino 1 (Foundry). Uranium ore processing and ore beneficiation studies were perfonned in this facility, in support of feed material processing centers operated by other contractors for the AEC. A foundry and melting, cutting, and grinding facilities are located within this building.

The second floor of this building was at one time substantially contaminated but most of the original contamination has been removed.

Areas totalling about 75 square feet on the second floor are still contaminated, together with the drain system.

Other parts of this building which are contaminated include the foundry area, and both ground and third floors.

Contamination is due to uranium, thorium and associated decay products.

Buildino 2 (Metalworking Buildino).

Building 2 was used extensively for major AEC research activities including the electroplating of Hanford reactor slugs,. heat treatment and fabrication of uranium and thorium alloys, rolling studies, alloy development and fuel element fabrication.

Most of the area contaminated by the electroplating activities has been cleaned.

Radioactivity has been detected at several locations on floors and also in trenches on one side of the building.

Contamination is again due to uranium, thorium, and daughter products, i

Building 3 (Materials Buildino).

This building housed powder metallurgy, l

melting, metallographic, and ceramics research facilities, in addition to other research activities involving the use of enriched, natural, and depleted uranium.

Contaminated areas (uranium, thorium, and daughter products) are spread throughout this building, from the ground to the second floor, and include equipment, building surfaces, and drains. In ddition, survey data indicatedarelativelyhighconcentrationofuranium(10' pg/g)insludgefrom a Building 3 sump.

Building 4 (Radiochemistry Laboratory).

Building 4 once contained a radiochemistry laboratory, which supported research activities in other facilities, and an encapsulation facility for highly enriched uranium.

The radiochemistry laboratory -- floors, walls, ventilation system, and floor drains and drain lines -- has been decontaminated.

Other parts of the drain system still remain, however, and are contaminated with a mixture of uranium and mixed fission products (MFP).

l 3-8 L

I Buildina 5 (Machine Shop).

The machine shop areas are housed in this building and produced substantial work for AEC/ERDA/00E programs.

The work enriched uranium.g, grinding t.nd milling operations on depleted, natural, and involved machinin Part of the floor of this room was replaced due to contamination.

However, areas of contamination -- from MFP as well as from uranium and thorium -- still exist within this room, particularly in the exhaust ventilation system, and drain system sumps.

Small areas of contamination also remain in the mezzanine and second floors.

Buildinas 6 and 7 (Chemistry Buildinas).

Analytical chemistry activities in support of the DOE / Navy program took place in this building.

The work involved alloy studiet corrosion research, chemical and instrumental analyses.

Low levels of contaimation exist in the ground and first floors only of Building. 6, and in the first through fourth floors of Building 7.

The contamination in both buildings is due to uranium and thorium, j

Buildina 9 (Mechanical Enaineerina Buildina).

A variety of AEC/ERDA/ DOE research programs were conducted in Building 9, involving the handling of natural and depleted uranium.

Minimal surface contamination exists in this building, in one area of the ground floor.

However, drain lines are expected to be slightly contaminated with uranium and thorium.

3.1.2.2 West Jefferson Site Buildina JN-1 (Hot Cells).. JN-1 was originally constructed to su) port fuel development research being conducted at Battelle for the AEC.

Inittally, the facility was used for hot cell examinatior, of fuel specimens which had been irradiated in the Battelle Research Reactor.

Subsequent work in this facility involved the examination of fuel from commercial power reactors and in support of DOE programs.

Due to the nature and extent of contamination.which exists within the hot cell area, a formal radiological survey has not been performed.

Extensive contamination from transuranics, fission

products, activation i

)roducts, uranium / thorium and decay products, and Co-60 exists throughout the lot cell laboratories.

Buildina JN-2 (Critical Assembly Laboratory).

This building was used for a zero power organic-moderated critical assembly and other criticality experiments.

Subsequently, the facility housed a slutonium laboratory, which

)

l was later modified to accommodate a radiochemical la) oratory. The building also 1

contains a vault for storage of plutonium and highly-enriched uranium.

Contamination exists in those areas described, in addition to an underground storage tank and the associated hot drain system.

L 3-9

Buildino JN-3 (Reactor Buildino).

Building JN-3 housed the research reactor which was built and operated in support of fuel development programs conducted by the AEC. This reactor was decommissioned in the mid seventies and was brought to retired reactor status.

Subsequently, the building was used to store waste generated from previous D&D activities in the Plutonium Laboratory.

TRU, MFP, and activation products are present, either as surface contamination, or in sludge / water / soil media in drain lines and around the containment building t

itself.

3.1.2.3 Site Soil at the West Jefferson Nuclear Sciences Area Data presented in the most recent Battelle annual environmental report

[3.1)indicatethattherehavebeennosignificantradionuclidereleasestothe environment from site activities.

Furthermore, the ongoing environmental monitoring program and the results obtained in su) port of this program suggest that in general there appears to be no major shte contamination.

As noted earlier, a detailed site characterization plan has been prepared and is being implemented.

?

Recent data on radionuclide activities of soil / sediment samples collected by Battelle, show that there are two relatively small areas within the West Jefferson north site which have elevated activities of certain radionuclides.

1 One such area is in two abandoned fi Mer beds (Figure 3.1) which had been remediated.

While the recent re.sults indicate loca'ized Cs-137 and Am-241 activities higher than had been predicted on the basis of the remediation itself, these same results show that the residual contamination is confined to a small area within the remediated region.

The second area is located near the storm sewer outfall (Location #1 in laboratory)).

Figure 3.1 which serves buildings JN-1 and JN-4 (the former plutonium Once again, low levels of mixed fission products, and transuranic contamination have been identified along a narrow band which originates from this outfall.

Either area may require some remediation in the form of soil excavation.

The extent of such a remediation effort will be determined from the site characterization work, i

I 3-10

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es2 Islesegem vues vuessee-se Get Gessed 90euse e

ac Airr useit OGripeE de CT uusese Coelung Tommer K'"e

.P./ # ' **

'%:7 l

g,@' ~ p --- 7 w

W k}

N7;; g assede Site Filter

"*'* Si 'd'

s'

.N'- '

'N.

)-

I I

's

~

.h.

f

,f ( k k

g[l

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[

it g

U

. G ;

fisem med nf f

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j pRx o

i.'s kN N

1 7

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~f& fW Y / /fI w.

i I

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see 2ee 1

4 feet

{

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/

/

i HGUltE3.1. ENVIRONMENTAL MONITORING AT THE WEST JEFFERSON NUCLEAR SOENCES AREA SHOWED EVIDENCE OF SOlt CONTAMINATION IN THE PROXIMITY Of THE ASANDONED HLTER BEDS AND THk iTiJRM SEWER OUTFALL (AREA 1) i 4

I 3.1.3 Operational Occurrences 1

3.1.3.1 Procedure In response to NRC Regulation 10 CFR Part 21 of 1977 [3.2), Battelle 1

developed a procedure for reporting of defects and noncompliance [3.3][.3.4]

A careful evaluation of the revised NRC regulation issued in November 1988 showed that Batte11e's original procedure for reporting would not have to be changed to comply with the revised regulation.

This Battelle procedure requires the staff member recofy his Manager,nizing a "

that has radiological implications to imediately noti who documents the deviation by initiating a Form D-21, "Part 21 Initial Deviation Report", and forwards it to the Battelle Radiological Safety Officer (RS0), or in his absence the NRC Compliance Coordinator.

This document serves as the official record for all identified deviations. The Form D-21 remains open until the evaluation is resolved.

This log report, along with the final evaluation report, is maintained by the RSO for inspection purposes by NRC.

The appropriate Manager, together with the RSO and the NRC Compliance Coordinator arranges for evaluation of the deviation to determine present or potential radiological safety hazards.

The evaluation must reflect a thorough and comprehensive investigation to determine if a substantial radiological safety hazard resulted or could have resulted from the deviation.

If in the evaluation of a deviation or an item of noncompliance it is determined that a substantial safety hazard did result or could have resulted, J

the Manager imediately notifies the Battelle Responsible Officer in a written report which must include the following infomation i

Identification of the facility, the activity, or the basic component which " fails to comply" or contains a defect l

Nature of the defect or " failure to comply" and the safety hazard which was or could be created The date on which the infomation of such defect or " failure to comply" was obtained Any advice related to the defect or failure.

The Battelle Responsible Officer must initially notify NRC of a defect or noncompliance within two days after he is notified.

b l

3.1.3.2 Previous Occurrences Previous operational occurrences such as spills, releases, or other accidents, were evaluated according to the above procedure.

Except for two incidents, the RSO found that the deviation did not constitute a substantial safety hazard and was not reportable to the NRC under 10 CFR Part 21 and Battelle's license conditions.

For each nonreportable incident, the RSO filed 3-12

an internal memorandum.

The memorandum serves as the formal documentation of the evaluation and the final detemination. All these memoranda are maintained in the Battelle Responsible Officer files.

None of these non repor' table incidents resulted in significant residual contamination since the contamination was largely removed following the occurrence.

In one of the two incidents reported to the NRC, the Security Access Control Center (SACC) alam panel at the West Jefferson Nuclear Science Area became inoperative at 5:00 p.m. October 17, 1977, and was not restored to operation until 8:00 p.m. on October 21, 1977.

As a result of this outage, facility alarms at the Hot Cell Laboratory (JN-1), the fomer plutonium laboratory (JN-4), Vault Area (JN-2), and Retired Battelle Research Reactor (JN-3) were not continuously monitored durino nonworkino hours. The evaluation concluded that this outage could have constituted a su3stantial safety hazard since a condition such as fire, stack release, or criticalit undetected for approximately one hour during nonworking hours.y could have gone A security guard makes hourly clock rounds at each of the above facilities.

As required, the Battelle Responsible Officer notified the NRC on November 11, 1977 [3.5] within two days after receiving the results of the evaluation.

Since no radioactivity was released during this occurrence, there is no residual contamination due to this specific incident.

The other noncompliance incident reported to NRC involved a release of airborne radioactive material within the Hot Cell facility and subsequent surface contamination.

This occurred at the Hot Cell facility on May 3, 1980, during unloading operations of a failed spent fuel assembly received from the Connecticut Yantee Atomic Power Company.

There was no release of radioactive material from the building.

The data from bioassay procedures, including in-vivo counting, have established that resultant radiation exposures were well within prescribed standards as set forth in 10 CFR Part 20.

Pulmonary depositions were a fraction of a percent of the permissible body burden.

An evaluation of this deviation in accordance with 10 CFR Part 21 procedures detemined that this incident was reportable to the NRC as a defect l

l in that it could have created a substantial safety hazard to staff in the area t

and the environment.

Accordingly, the Battelle Responsible Officer notified the NRC on July 18, 1980 [3.6] within two days of the evaluation. However, the surface contamination was largely removed following the occurrence and subsequent monitoring has shown no significant residual contamination.

3.1.4 Radiation Levels

)

The 1984 radiological survey of the facilities showed that with the exception of the hot cell (Building JN-1), the contamination was widespread but that the radiation levels were very low, in the range of 0.1-0.2 mR/hr (beta-gamma). Although no measurements were made in t'he hot cells as part of the 1984 survey, the presence of radioactive materials currently stored in the cells and contamination from past operations indicates very high radiation fields within 3-13 1

the cells and in the controlled-access areas.

The operating areas outside the i

i cells have average radiation levels of less than 0.5 mR/hr.

Clearly, during decommissioning operations in the hot cells, radiation levels will be continuously monitored and all operations will be performed in keeping with the ALARA considerations described in the next section.

3.2 Ensurino that Occupational Radiation Exposures Are As Low As 15 Reasonably Achievable (ALARA)

Routine radiation protection coverage is supervised by Battelle's Health Physics Group (HPG).

Through provisions of the Health Physics Plan, the HPG supplies HP support to D&D operations in the areas of personnel and area dosimetry, area monitoring, environmental monitoring, bioassays, HP technician

coverage, radiological work pemit (RWP) review and

approval, ALARA determinations, radiation worker training, data and record maintenance, and reporting.

The HP Plan also provides for overseeing effective operation, repair and calibration of radiological monitoring instrumentation, and provision and checking of personnel protective equipment and respirators. The Plan addresses emergency procedures with respect to organizational structure, off-site releases, handling of contaminated personnel, and interfaces with local civil authorities.

Batte11e's ALARA program is administered through a series of reviews and approvals before radiological work can proceed.

The reviews are conducted at charter that outlines its responsibilities (2.8]y Comittee operating under a an administrativ~e level by a Radiological Safet At an operational level, the HPG serves to review proposed work on a task-by-task basis.

Items for review include procedures, worker exposure history, l

and radiation safety requirements.

Added to the review process is the audit function of the Radiological Safety Officer (RS0).

The heart of the ALARA program is the implementation of the Health Ph sics r

Plan. A key factor is the training of personnel.

Battelle has a Radiolo ical Safety Training Program designed to provide individuals with suffi ient information and understanding to conduct radiological and related operations in a safe and effective manner.

Quality assurance (QA) serves a vital role in the ALAPA program in controlling activities through precise procedures in operations, safetyr and health physics. Additionally, instrumentation calibration comes under QA, which assures that the evaluations made are determined from at. curate data.

3-14

3'. 3 Health Physics Program Radiation safety during D&D will be controlled through the Health Physics Plan for the project.

The basic purpose of this plan is to assure the safety i

of the workers, Battelle staff, the public, and the environment; and to employ 4

appropriate standards for compliance with requirements and regulations. Through l

- provisions of the plan, Batte11e's Health Physics Services group will supply i

Health Physics (HP) su) port to the decommissioning operations in the areas of i

i personnel and area dos < metry,ker training, HP data and record maintenance, and determinations, radiation wor HP reporting.

The plan identifies potential sources of radiation or contamination exposure to the workers or the public.

It also identifies the methods that will be employed to reduce and control these exposures.

In addition, the plan specifies emergency procedures in regard to organizational structure, off-site releases, handling contaminateo personnel, and interfaces

)

with local civil ~ authorities and other services, i

The HP program will be conducted through implementation of a set of HP

. procedures.

The normal functions of the HP Services Group are controlled by a set of nuclear services procedures.

In addition, several procedures are being i

prepared specifically for the D&D project.

Table 3.2 is a list of both normal nuclear services (NS) procedures and procedures specific to the D&D project.

The procedures in Table 3.2 address all aspects of radiological safety including the methods, frequency and procedure for effluent monitoring and location of monitors and collection devices on Battelle property and surrounding areas.

Other procedures in Table 3.2 specify the methods for conducting radiation surveys, and for personnel monitoring.

The type of instrumentation to be used is specified as well as the frequency and accuracy requirements for instrument calibration.

Instruments and equipment which will be used for performing radiation and contamination surveys and personnel monitoring will be selected to meet the specific needs of the D&D project.

The criteria for instrument selection include the type of radioactive material (alpha, beta, and gamma emitters),(solid or gas). quantity (either physical amount or activity), and p characteristics Instruments are available and in nonnal use by the HP Services Group for monitoring these types of radiation.

In addition, the procedures present the methods which will be employed in the D&D' project for contamination control by restricting access to decontamination operations area through satellite staging areas and the use of special and temporary ventilation systems.

The HP program and implementation of the HP procedures are subject to the same QA procedures as other functions of the D&D project including audits, inspections, and management reviews.

3-15 r

-. - -. - - - - - - - - - - -.. - - - ~.,.

,+

a,

,,.,-,-,.---,..5

[

i L

TABLE 3.2 BATTELLE NUCLEAR SERVICES AND DECONTAMINATION PROCEDURES ARE DIRECTLY RELEVANT TO RADIOLOGICAL SAFETY NS-NS-5 R-1 08 24-83 Documentation and Notification Procedures fcr Personnel Dosimetry Data NS-NS-7 R-0 02-01-S3 Procedure for Operating-the Harshaw Model 2271 Automatic TL Detector / Dosimeter Identifier System NS-NS-8 R-1 07-17-85 Environmental Quality Assurance Procedures for DOE /EML Interlaboratory Comparison Program i

NS-NS-8.5 R-0 11-21-83 Control of Effluent and Environmental.

Monitoring Responsibilities Within the Nuclear Services Group NS-NS-8.6 R-1 03-28-86 Measures Implemented to Assure Operational Control of Radiological Stack Emissions and Liquid Effluents from the Nuclear Science Area to Unrestricted Areas NS-NS-9 R-2 04-10-85 Routine Environmental Radiological Monitoring Schedule NS-NS-10 R-1 03-02-83 Procedure for the Collection of Environmental Radiological Air Samples 1

NS-NS-10.1 R-0 07-07-81 Procedure for the Collection of Environmental Hazardous Chemical Air Samples NS-NS-11 R-2 02-24-83 Procedure for the Collection of l

Environmental Radiological Water and Liquid l

Effluent Samples NS-NS-11.1 R-0 07-07-81 Procedure for the Collection of r

l-Environmental Hazardous Chemical Water Samples NS-NS-12 R-1 06-13-84 Procedure for the Collection of Environmental Radiological Soil Samples NS-NS-13 R-1 05-07-84 Procedure for the Collection of.

g Environmental Radiological Vegetation H

Samples-Annual Grass 3-16 4

.r--

i L

1

-TABLE 3.2 (Continued) l NS-NS-17 R-2 05-15-85 3 eta-Gama Radiation Monitoring of Nuclear Sciences Area NS-NS-18 R-0 11-07-78 Smear Surveys - Collection, Counting and L

Documentation NS-NS-18.1 R-0 02-07-79 Smear Surveys - Shipping Packages Containing Radioactive Material NS-NS-18.5 R-0 10-18-88 Radioactive Contamination Monitoring Requirements for Facility Wall, Ceiling, and Floor Surfaces i

NS-NS-18.7 R-3 06-20 Procedure for Establishing a Surface Grid

~

for Walls, Floors and Ceilings for a Detailed Radiological Survey NS-NS-21 R-0 11-19-80 Preparation of Soil Samples for Radiochemical Analysis NS-NS-22 R-0 08-25-81

' Procedure for Pulverizing Soil and Rock Samples NS-NS-100 R-0 02-01-79 Calibration Intervals c

PS-0P-040 R-0 09-11-89 Removal of Material from Specific Locations on Contaminated Surfaces DD-0P-120-R-0 09-25-89 Installation of Contamination Control Barriers 1

DD-0P-130 R-0 09-25-89 Installation of Access Control Barriers DD-0P-150-R-0 09-15-89 Installation of Satellite Staging Area and Equipment DD-0P-140 R-0 10-05-89 Installation and Operation of Coritamination Control Ventilation in SSA and D&D Areas DD-OP-141 R-0 09-28-89 Installation of Temporary Lighting and Electrical Service DD-0P-220-R-0 09-28-89 Operation of the Satellite Staging Area 3-17

-+

_.n...

-'-r-

-v

-n

5 i

8.4 Contractor Personnel All contractor personnel will-be subject to the same policies and programs

'of training; and certification 'as Battelle personnel, including the i

assurance (QA), radiological safety _ training, and health physics plans. quality

Thus,

'the safety of contractor personnel will be ensured when they are working in D&D

?

areas.

y I'

3.5 Radioactive Waste Management A' radioactive ~ waste management plan-for the project has been deYeloped.

This plan details the work required to collect, process, sackage, characterize, classify,- provide storage areas, and ship liquid and solid radioactive waste, scrap, and salvage material from the decontraination and decommissioning (D&D) of fifteen buildings and their surrounding earth / soil. All waste material from

the D&D operations will be. reduced in volume if feasible.

The shi

' containers for radioactive wastes will be sealed, labeled for shipping,pping and 1

loaded onto trucks-for transportation to permanent disposal facilities.

All waste management operations will be perfonned in accordance with approved technical procedures responsive to the applicable guidelines. Overall control of the waste management operations is through Section. 2.2 of this document.

3.5.1 }Laste Manaaement Guidelines The waste from the.Battelle D&D project will be segregated by radioactive material content, physical form,-and chemical content, and sent to storage and L.

dis)osal facilities in the Department.of Energy's (DOE) Hanford Reservation in l-Was11ngton State.

Where hazardous material is present and separate from i

radioactive waste, the hazardous constituent will be removed first.

If mixed waste (MW) is. present, decontamination operations will be perfonned so as to minimize = the volume of mixed waste.

All major sources of transuranic (TRU) waste will be removed before removing the more widely spread low level waste

'(LLW) for that facility in which TRU is present.

Where cost effective, decontamination will be preferred over disposal.

Aggressive methods will be used to remove surface contamination such that the remaining structural members can be removed as uncontaminated materials.

3.5.2 Waste Transfer and Interim Storag Because of the segregation requirements imposed for waste acceptance at the Hanford Reservation, enclosed staging areas with restricted access will be used for transfer, sorting, and repackaging waste, as necessary.

In addition, all required certification measurements for transport will be taken in these areas.

3-18

Waste will-be - stored on-site on an interim basis only until sufficient waste of similar radioactive material content and physical form has been accumulated to~make up a waste shipment.

Batte11e's proposed waste management plan ' provides 'for shipment of waste packages as truckload quantities are accumulated.

Therefore,. no more than eighty SS-gallon. drums or twenty 4x4x7 foot boxes,-the size of a full shipment, are expected to be stored.

All interim transfer packages will be stored in the enclosed staging areas from where all waste shipments will originate.

3.5.3 Waste Characterization The method for determining the curie content of a waste package for the gamma-ray emitting species is based on high resolution gamma-ray spectroscopy and gross radiation field measurements. Radionuclide rattos and gross radiation field measurements at a defined distance, plus dose rate curves ~ for each detected isotope, are used to calculate individual isotopic and total curie contents for each waste package. The difficult-to-measure radionuclides, such as the TRU isotopes, are determ.ned either from these inferential calculations, based on the isotopic ratios of the wastes and using the ORIGEN2 computer code, or by analysis of samples taken from the wastes.

Characterization of highly radioactive items, which would be heavily shielded in packaging, is performed by sampling and laboratory analysis before packaging, and the activity. of the radionuclides scaled up to the-estimated activity in the final waste package.

l 3.5.4 Waste Volumes and Volume Reduction - Liquids

. Contaminated liquids that must be treated for disposal include liquids in drains, pipes, and sumps; 20,000 cubic feet (150,000 gallons) of spent fuel pool water; several hundred gallons of cell door hydraulic oil; contaminated mercury; and any contaminated liquids generated during the D&D activities themselves.

Wherever feasible,. contaminated liquids generated 'during D&D will be treated to. remove contamination and recycled.

Such treatment will include settling and filtration through a system capable of removing 10 micron particles, ion exchange, evaporation, and solidification.

Solidifying agents that may be used include cement, concrete,.or silica-based immobilizing agents such as Aquaset. - - Alternatively, an extruder-evaporator solidification. method may be used.

With an extruder-evaporator, a volume reduction factor of 8 or more can be expected.

If cement is used, the resulting volume of solidified L

waste will be about 1.67 times greater than the volume of the original liquid waste residue.

As with D&D generated liquids, s)ent fuel pool water will be evaporated following extended filtration.

Liqu ds from drains, pipes, and sumps will similarly be collected and solidified in concrete,

Aquaset, or other solidification. agents.

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l The hydraulic oil will be collected using. a pump and suction tube and

'l solidified using Petroset.

The small amounts of-licuid mercury present will either be cleaned up by distillation or be mixed with zine to solidify the mercury.

-3.5.5 Waste volumes and Volume Reduction - Solids Preliminary radiological surveys at the BCLDP sites show that nearly all contamination -is present as solid materials.-

Volume reduction for these materials will be achieved through compaction; size reduction; chemical or ultrasonic cleaning; and immobilization in concrete.

Incineration is not being considered.

1 3.5.6 Waste Packages Because TRU waste will be shipped to DOE's Hanford Reservation, it will be packaged-in accordance with the disposal site requirements

[3.7].

Similarly, LLW will also be packaged to meet the disposal and storage requirements imposed by the Westinghouse Hanford Company, the contractor operating the disposal site on the DOE Hanford-Reservation, in containers t

approved by DOE.

3.5.7 Packagina, Classification, and Certification During D&D, all reasonable efforts will be made to segregate, minimize, and treat waste, with the potential to change it to a lower classification, through decontamination activities.

Nonetheless,.two principal categories of L

radioactive waste will be generated as a result of the Battelle D&D o)erations:

LLW and TRU waste.

These wastes will be classified according to t1eir principal radioactive elements; the activity level, in curies, of each isotope; their physical form; and their specific activity.

~

The bulk of the waste-that will be generated is LLW.

The inventory of TRU waste _is not expected to exceed 59,700 cubic feet (7,961 55-gallon drums).

-After classification, the waste will be placed in approved containers and' certified to meet or exceed the Hanford Reservation requirements.

Detailed L

certification plans for LLW and TRU waste have been prepared for approval by l

the Hanford site.

3-20 1

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-3.5.8 Loadino and Transportation

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All radioactive waste generated during the D&D of Battelle facilities will j

be~ shipped to the Hanford-Reservation by truck.

Wastes will be shipped based on DOT regulations.

There is a' certain potential for non-radiological injury or death as a result of a truck accident.

The overall accident rate for truck transport is 1.06 x 108 per kilometer, and there are 0.51 injuries and 0.03 fatalities per truck accident [3.8].

Based on these rates, it is estimated that waste shi)ments might lead to 1.26 accidents, 0.6 injuries, and 0.04 fatalities. The num)er of. trucks used to transport waste is not expected to have any significant

~

impact on traffic at either site.

During maximum transport activity, it is estimated that a total of six truck shipments will originate during 1993 from the King-Avenue site and.40 truck shipments during 1996 from the West Jefferson site. This maximum transport activity would be equivalent to a comon 18-wheel, tractor-trailer rig leaving the King Avenue site every 2 months and slightly less than once a week from the West Jefferson site, i

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REFERENCES 3.1l " Environmental Report on Radiological an'd ' Non-Radiological Parameters",

Annual: Report, Submitted by Battelle to the U.S. Department of Energy, September 1989.-

3.2 " Reporting of Defects and Noncompliance",. Regulation 10 CFR Part 21, l

U.S. Nuclear Regulatory Commission, June 10, 1977.

" Procedures and Responsibilities for Im Reporting of Defects and Noncompliance",plementation of 10 CFR Psrt 21, 3.3 Battelle-Columbus Laboratories, December 5, 1977.

3.4 " Criteria and Proc'edures for the Reporting of Defects", Regulation 10 CFR 3

Parts 21 and 50, U.S. Nuclear Regulatory Commission, November 4, 1988.

3.5 Docket No. 70-8, 10 CFR Part 21 Report, Letter to the U.S.

Nuclear Regulatory Commission, November 11, 1977.

'3.6 Docket No. 70-8, 10 CFR Part 21 Report,'

Letter to the U.S. Nuclear Regulatory Commission, July 18, 1980..

3.7 "Hanford Site Radioactive Solid Waste Acceptance Criteria", Report WHC-EP-l 0063-1, Westinghouse Hanford Company, September 1989.

1 3.8 '" Decommissioning Plan for the Shippingport Station Decomissioning Project",

Report DOE No.

RL/SFM-83-4, U.S.

Department of Energy, September 1983.

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PLANNED FINAL RADIATION SURVEY m

A. comprehensive radiological survey by an independent veri fication -

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contractor (IVC) will be the final stage of the D&D project, aimed at providing confirmation that each site and all buildings which have been decontaminated /-

)

decommissioned can be released for unrestricted use, During the D&D ~ activities, detailed recordsL will be maintained on th'e progress of the ' effort.

As-detailed in the QA Plan, the individual building i

D&D plans, and the technical procedures, specific criteria will be established j

for the decontamination effort in each area. The following information. will be-1 provided to the IVC:

m A list of buildings to be surveyed, with detailed floor l

plans Detailed information on contamination (type and levels of

'[

activity)ineachbuildingpriortoD&D Detailed information on the scope of the decontamination L,

effort including :the methods used and the resultant reduction in contamination achieved Criteria for radioactivity levels which are acceptable for-unrestricted use based-on - existing regulatory documents

[2. 4 ~,2. 7,4.1] together with ALARA considerations.

An external: radiological survey on the King Avenue and West Jefferson sites

_(soil) will also be included as part of the fina1Lyerification, to be performed once all buildings on each site have been surveyed.

At the end of the final survey, Battelle will explicitly describe the radiation and contamination levels expected-'upon release of the buildings for unrestricted use. These levels will not be different from existing or accepted guidance.

REFERENCES 4.1 Annex C Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special' Nuclear Material, U.S. Nuclear Regulatory Commission, y

July 1982.

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FUNDING f

- Decomissioning of these facilities will be conducted under a cost share agreement withLthe U.S. Department of Energy (DOE), under which DOE's share is

' expected:to be'90 percent.

Radioactive waste from the decomissioning will be-disposed of ' at ' DOE disposal sites.-

Decomissioning of. these facilities is included fn DOE's Environmental Restoration and Waste Management Five Year Plan 4

[5.1]. Decomissioning costs, including decontamination and waste disposal, are estimated to be approximately $50 million in 1989 dollars. Final cost estimates for-each-. building will be developed as the building :. characterizations are completed.

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1 REFERENCES 5.1 Environmental Restoration and Waste Management.

Five-Year Plan, Report 00E/S-0070, U.S. Department of Energy, September 1989.

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PHYSICA. SECURITY PLAN AND MATERIAL CONTROL AND ACCOUNTING PLAN PROVISION $

Q IN PLACT DURING DECOMISSIONING-eMW fi 4

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Battelle's NRC. facility operating. license conditions willinot be changed tot conduct the decommissioning project. :- Hence, no changes 'are proposed-to the-R'

~ NRC-approved physical - security-plan. and-special: nuclear materi al. control and' q

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ACCESSION NBR 9003060104 DOC.DATE:- 90/02/27 NOTARIZED: NO DOCKET #

l FACIL:70-0008 Battelle Memorial Institute, Columbus, OH, 07000008

- AUTH.NAME AUTHOR AFFILIATION TOY,H.L.

Battelle Memorial Institute, Columbus Laboratories RECIP.NAME RECIPIENT AFFILIATION SJOBLOM,G.L.-

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-NOTES:FAC TYPE: Advanced Fuel R&D & Pilot Plants 07000008 j

RECIPIENT COPIES RECIPIENT COPIES A'

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TOTAL NUMBER OF COPIES REQUIRED: LTTR 11 ENCL 6

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