ML19269C310
| ML19269C310 | |
| Person / Time | |
|---|---|
| Site: | 07000036 |
| Issue date: | 01/15/1979 |
| From: | ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | |
| Shared Package | |
| ML19269C309 | List: |
| References | |
| NUDOCS 7901310071 | |
| Download: ML19269C310 (13) | |
Text
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LICENSE SNM-33 DECOMMISSIONING PLAN
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COMBUSTION ENGINEERING, INC.
NUCLEAR FUEL MANUFACTURING HEliATITE PLANT 790131 60 7/
January 15, 1979 21'7f:,
TABLE OF CONTENTS Page No.
l.0 INTRODUCTION 1
2.0 PURPOSE 1
3.0 DECONTAMINATION PLAN 2
3.1 Decontamination Guidelines 2
3.2 Decontamination Procedure 3
3.2.1 Bulk Removal of Radioactive futerial 3
3.2.2 Disposal of Equipment 4
3.2.3 Precleaning of Facilities 4
3.2.4 Presurvey 5
3.2.5 Liquid Effluent System 6
3.2.6 Walls 6
3.2.7 Floors 6
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3.2.8 Ventilation System 6
3.2.9 Demolition 7
3.2.10 Sequence 7
3.3 Final Decontamination Report and Release 7
4.0 ESTIMATED COST FOR DECONTAMINATION 9
APPENDIX A Decontamination Cost Breakdown 10 APPENDIX B Previous Decontamination Costs 11
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1.0 INTRODUCTION
Combustion Engineering, Inc. is authorized to conduct operation of its Hematite, Missouri facilities under NRC License Number SNM-33.
Although there are no federal regulations currently in effect which would require decontamination and decommissioning of this facility, in April,1977 NRC requested C-E to " submit your plans for decommission-ing, identifying and discussing the major considerations involved for your facilities and site, and any financial arrangements made to defray these expenses".
In a letter dated December 8,1978, NRC further defined the details required in this plan, including the ne.ed for financial arrangements to insure that the funds will be available and comnitted to cover the costs of decontamination.
Combustion Engineering, Inc., will, after termination of all licensed activities in the facilities covered by NRC License Number SNM-33, follow this plan and decontaminate the facilities as required to release them for unrestricted use.
2.0 PURPOSE The purpose of this plan is to describe the course of' action to be taken by Combustion Engineering,Inc. when it becomes necessary to decommission the Hematite Facility licensed under SNM-33. The object of the decommissioning action is to prepare the site and facilities involved for release for unrestricted use by the company. e
3.0 DECONTAMINATION PLAN Most radioactive materials are stored, processed, or retained in the Oxide Building and Buildings 240 and 255 on the Hematite site.
Accordingly, the procedures noted below will be applied to these buildings to decantaminate them to the levels noted in Paragraph 3.1.1.
All other facilities will be surveyed to assure that contamination levels are below those noted in Paragraph 3.1.1.
3.1 Decontamination Guidelines 3.1.1 Decontamination will be to the levels noted below.
In addition, every effort will be made to further reduce contamination levels to as low as reasonably achievable.
Average (l)(2)
Maximum (l)(3)
TaraetII)
Removable Alpha 1,000dpm/100Cm2 1,000dpm/100cm2 200dpm/100cm2 Fixed Alpha 5,000dpm/100Cm2 15,000dpm/100cm2 1,000dpm/100cm2 Notes:
(1) Reference Annex C, dated November,1976, to Combustion Engineering, inc. Hematite Site Special Nuclear Material License, SN!1-33:
" Guidelines for Decontamination of Faciliti:;
and Equipment Prior to Release for Unrestr.icted Use or Termination of Licenses for Byproduct, or Special Nuclear Material".
(2) Measurement of average contamination shall not be averaged over an area of more than one square meter.
(3) The maximum contamination level applies to an area of not more than 100cm2, 3.1. 2 Radioactive surfaces will not be painted until it is demonstrated that contamination does not exceed the above noted levels.,
3.1. 3 The radioactivity of the interior surfaces of ducts, pipes, etc. will be determined by taking measurements at all access points, prov.i.ded contamination at these locations is likely to be representative of interior contamination.
If such access locations are not likely to be representative, or if interior surfaces are inaccessible, then such interior surfaces shall be assumed to be contaminated in excess of the above noted levels.
3.1.4 All routine health physics and environmental monitoring programs will continue to be conducted in such a manner as to minimize both personnel exposure and release of radio-active material to the site environs. A comprehensive survey will be conducted upon completion of the project. All required records will be maintained for the period specified by applicable regulations.
3.1.5 Disposal of uranium inventory will proceed simultaneously with the plant decommissioning and decontamination. Scrap Recovery areas will be the last areas to be dismantled in order to reclaim,
any uranium generated from cleanup. Security consistent with the requirements of 10CFR73 will be maintained until all radio-active materials licensed under SNM-33 have been removed from the Hematite site.
3.2 Decontamination Procedure 3.2.1 Bulk Removal of Radioactive Material A physical inventory of the facilities will be conducted for all SNM materials covered under License SNM-33.
Inventoried materials will be packaged and disposed of in accordance with DOT and NRC regulations in existence at the time that the facility deccanissioning takes place.,
3.2.2 Disposal of Equipment Contaminated ~ equipment will be disposed of by burial or sale.
a) Equipment disposed of by burial will not be decantaminated.
Instead, this equipment will be cleaned to remove all bulk radioactive materials. The equipment will be vacuum cleaned and then wiped with' damp cloths to remove all remaining radioactive particulate matter. The equipment will then be packaged and transported in accordance with applicable DOT and NRC regulations. All equipment exposed to both high temperatures and radioactive materials (chemical reactors and furnaces) will require burial.
b) Contaminated equipment may be sold for use at another fuel cycle facility.
In such instances, all exterior surfaces will be cleaned to levels pemissible for restricted areas.
The equipment will then be packaged and transported in accordance with applicable 00T and NRC regulations, c)
Equipment may be sold for use at non-nuclear facilities.
In such instances, all surfaces, interor and exterior,shall be decontaminated so as not to exceed levels given in Paragraph 3.1.1.
3.2.3 Precleaning of Facilities Upon removal of inventory covered under SNM-33 and disposal of equipment,the facilities will be precleaned in the following manner:
a)
Floors will be vacuum cleaned and wet scrubbed.
b) Walls will be vacuum cleaned and final wiped with damp cloths.,
3.2.3 Precleaning of Facilities (continued) c) All roof trusses, overhead steel, ceilings, overhead ductwork", piping, etc. will be vacuum cleaned and final wiped with damp cloths...
d) All underground drain lines will be flushed repeatedly with clean water.
3.2.4 Presurvey After completion of the physical inventory, disposal of equipment, and precleaning of the facilities covered under SNM-33, a radiological survey will be made of contaminated areas to assess the extent of contrmination involved. This presurvey will be reviewed by NRC anc will include:
a) Floor samples b) Core samples of earth beneath the floor -
c) Roof smear samples d) Smears of ceramic or metallic or other non-porous wall surfaces, both on and below paint.
e) Samples of block or concrete walls to a depth of 1/8 inch or more, f) Smears of roof trusses and supports.
g) Smears of overhead piping, ductwork, lighting, etc.
h) Core samples of 2arth adjacent to contaminated underground effluent lines.
i) Records and drawings of sample locations will be prepared and maintained.
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3.2.5 Liquid Effluent System Underground. piping that cannot be decontaminated to prnper levels will be excavated and removed for burial.
If sampling indicates contaminated soil, removal and burial of soil will also be accomplished. Contaminated material presently in retention lagoons will have been disposed of prior to implementation of this plan.
The entrance area of the old septic system sand filter will be checked for contamination and excavated for burial to the extent necessary.
3.2.6 Walls Where the presurvey results indicate residual contamination in the wall surface, removal of the contaminated areas will ensue.
Material removal will be repeated as necessary. When the contamination levels of Paragraph 3.1.1 have been reached, a final cleaning (wet wipadown) will be performed.
3.2.7 Floors Decontamination of floors will follow. Depending on the extent of contamination, surface cleaning, surface removal, or removal of sections of the floor will be dictated.
(In the case of the wet scrap recovery facilities, removal of portions of the floor may be required.)
3.2.8 Ventilat on System i
The contaminated area ventilation systems will remain intact until all of the above steps have been completed. The systems will then be removed and buried.
3.2.9 Demolition In the event that it is planned to raze a facility, then one of two courses of action will be taken.
a) The facility may be wholly decontaminated as outlined above, then leveled.
In this case the walls and roof may be disposed of via sanitary landfill.
b) Surface cleaning, rather than surface removal and/or decontamination of walls may be pursued, in which case the walls will be disposed of via burial.
3.2.10 Sequence The above events will not necessarily proceed one upon completion of another. Alternatively, two efforts may proceed simultaneously, such as removal of inventoried materials and the removal of equipment.
In general, decontamination of the facilities will follow the above outline.
3.3 Final Decontamination Report and Release 3.3.1 Upon completion of the decontamination of the facilities, a comprehensive radiological survey will be taken.
If necessary, additional aecontamination will be performed.
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3.3.2 When it has been established that the facilities are within the limits specified in Paragraph 3.1.1, a survey report will be sent to the Director, Office of Nuclear Materials Safety and Safeguards, with a copy to the Director of Region III.
The survey report will:
a)
Identify the facilities.
b) Show that reasonable effort has been made to reduce residual contamination below the levels specified in Paragraph 3.1.1.
c) Describe the scope of the survey and the general procedures followed, d) State the results of the final survey, in units specified in Paragraph 3.1.1.
3.3.3 The facilities covered under SNM-33 on the Hematite site will be staffed for a maximum of two months after decontamination and while waiting a formal release from the NRC for unrestricted use.
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4.0 ESTIMATED COST FOR DECOMMISSIONING The total estimated cost for decontaminating and decommissioning the present Hematite facilities covered under SNM-33 is estimated at $200,000 (in 1978 dollars). The planned plant expansion adds
$150,000 to this amount. A complete breakdown of the cost is shown in Appendix A.
Appendix A also includes an estimate for the total number of cubic feet of contaminated material / equipment to be disposed of at a licensed commercial site.
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APPENDIX A.
DECONTAMINATION COST BREAKDOWN LABOR COSTS Catecory Man-Months Supervisory 30 Technical 34 Labor 105 Total 169 Estimated Cost - $203,600 BURIAL COSTS 3
Area Volume (Ft )
0xide Plant 8,600 Building 240 6,100 Building 255 9,100 Expansion (2 lines) 17,200 Other Areas 2,000 Total 43,000 Estimated Cost - $113,600 OTHER COSTS Supplies / Services Estimated Cost - $ 32,800 Total Estimated Cost - $350,000
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APPENDIX B.
PREVIOUS DECONTAMINATION COSTS All areas involving processing of high enriched uranium were decontaminated prior to C-E's acquisition of the Hematite site in 1974. Areas decontaminated were:
Red Room
- 5600 Ft2 Item Plant - 3200 Ft2 South Vault - Shelving removed Wood Barn Contaminated equipment removed Tile Barn Contaminated equipment removed Actual costs associated with the 1974 decontamination were:
Labor 30,000 Burial 42,605 Supplies / Services -
28,053 Total
$ 100,65S A total volume of 22,084 cubic feet was shipped to licensed burial.
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