ML19263C111
| ML19263C111 | |
| Person / Time | |
|---|---|
| Site: | 07001100 |
| Issue date: | 01/15/1979 |
| From: | ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | |
| Shared Package | |
| ML19263C110 | List: |
| References | |
| NUDOCS 7902070061 | |
| Download: ML19263C111 (9) | |
Text
p.
LICENSE SNM-1067 COMBUSTION ENGINEERING, INC.
NUCLEAR FUEL MANUFACTURING WINDSOR SITE DECOMMISSIONING PLAft 790207 006l JAtlUARY 15, 1979
TABLE OF CONTENTS
1.0 INTRODUCTION
2.0 PURPOSE 3.0 DECONTAMINATION PLAN 3.1 Decontamination Guidelines 3.2 Decontamination Procedura
_3.2.1 Bulk Removal of Radioactive Material 3.2.2 Disposal of Equipment 3.2.3 Precleaning of Facilities 3.2.4 Presurvey 3.2.5 Liquid Effluent System 3.2.6 Walls
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Floors 3.2.7 3.2.8 Ventilation System 3.2.9 Demolition 3.2.10 Sequence 3.3 Final Decontamination Report and Release 4.0 ESTIMATED COST FOR DECO'!TAMINATION
1.0 INTRODUCTION
' Combustion Engineering, Inc., is authorized to conduct operations at its Windsor, Connecticut facilities under NRC License SNM-1067. Although there are no federal regulations currently in effect which would require decontamination and decommissioning of these facilities, in May 1978 NRC imposed License Condition No. 24 to SNM-1067 which requires C-E to "sub-mit a plan for the future decontamination of the places of use and sites authorized by this If. cense so they.can be released for unrestricted use."
In a letter dated December 8,1978 (attached) NRC further defined the details required in this plan including the need for financial arrange-ments to insure that the funds will be available and committed to cover the costs of decontamination.
Combustion Engineering, Inc., will, afta tarmination of all licensed activities in the facilities covered by NRC Licer e SNM-1067, comply with License Condition 24 as defined in this plan and decontaminate the facili-ties 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 Windsor Facility licensed under SNM-1067. The oofect of the decommissioning action is to prepare the site and facilities invoived for release for un-restricted use by the company.
3.0 DECONTAMINATION PLAN Under SNM-1067, ali radioactive mat trials are stored, processed, or retained in Buildings 5, 6, and 17 o.n the Windsor site. Accordingly, the procedures noted below will be applied to these buildings to decontaminate them to the levels 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: - - _ - _.
O) (2)
O) (2)
O)
AVERAGE MAXIMUM TARGET 2
2 2
Removable Alpha 1,000 dpm/100cm 1,000 dpm/100cm 200 dpm/100cm 2
2 2
Fixed Alpha 5,000 dpm/100cm 15,000 dpm/lC3cm 1,000 dpm/100cm NOTES:
(1)
Reference Annex C, dated 11/76, to Combustion Engineering, Inc. Hematite Site Special Nuclear Material License, SNM-33"
" Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Lic-enses for Byproduct, or Special Nuclear Material".
(2) Measurements 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 2
more than 100 cm.
.3.1.2 Radioactive surfaces will not be painted until it is demon-strated that contamination does not exceed the above noted i
levels.
3.1.3 The radioactivity of the interior surfaces of ducts, pipas, etc., will be determined by taking rneasurements at all access points, provided 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 peisonnel exposure and release of radioactive material to the site environs. A comprehensive survey will be conducted upon completion of the project.
All required records wil.1 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 tc re-claim any uranium generated from clean-up.
Security consistent with the requirements of 10 CFR 73 will be maintaired until all radioactive materials, licensed under SNM-1067 have been removed frcm Buildir.gs 5, 6, and 17. --
l 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-1067.
Inventoried mat-erials will be packaged and disposed of in accordance with regu-lations in existence at the time that the facility decommissioning 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, 'the 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 radio-active particulate matter. The equipment will then be packaged and transported in accordance with applicable DOT and NRC regu-lations.
b) Con.aminated equipment may be sold for use at another feel cycle facility.
In such instances, all exterior surfaces will be cleaned to levels permissible for restricted areas. The equip-ment will then be packaged and transported in accordance with applicable DOT and NRC regulations.
c) Equipment may be sold for use at non-nuclear facilities.
In such instances, all surfaces, interior 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-1067 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.
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 pressure 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-1067, a radiological survey will be made of contaminated areas to assess the extent of contamination involved and will include, but not be limited to:
a)
Floor samples b) Roof smear samples c) Smears of all interior wall surfaces
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d) Samples of underground piping e) Smears of roof trusses and supports f) Smears of overhead piping, ductwork, lighting, etc.
g) Core samples of earth adjacent to contaminated underground effluent lines h) Records and drawings of sample locations will be prepared and maintained 3.2.5 Liquid Effluent System Underground contaminated piping that cannot be decontaminated to proper levels will be excavated and removed for burial.
If sampling indicates contaminated soil, removal and burial of soil will also be accomplished.
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 con-tamination levels of Paragraph 3.1.1 have been re. ached, a final cleaning (wet wipdown) 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.
..n the case of the pellet faciliti.:s, removal of portions of the floor may be re-quired)....
3.2.8 Ventilation System The contaminated area ventilation systems will remain intact until all of the above steps have been completed. The sys-tems will then be removed and buried.
3.2.9 Demolition In the event that it is planned to raze a facility, then one of the two courses of action will be taken:
a) The facility may be wholly decontaminated as outlined above, then leveled.
In this casa, 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 com-pletion 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
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3.3.1 Upon completion of the decontamination of the facilities, a comprehensive radiological survey will be taken.
If necessary, additional decontamination will be performed.
3.3.2 When it has been established that the facilities are witnin the limits specified in Paragraph 3.1.1, a survey report will be sent to the Director, Office of fluclear Materials Safety and Safe-guards, with a copy to the Director of Region I.
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-1067 on the Windsor site will be staffed for a maximum of two months after decontam-ination ar.d while waiting a formal release from the NRC for unrestricted use.
4.0 ESTIMATED COST FOR DECOMMISSIONING The total estimated cost for decontaminating and decommissioning the present Windsor facilities covered under SNM-1067 is estimated at
$170,000 (in 1978 dollars). A complete breakdown of the cost is shown in Table I.
Table I also includes an estimate for the total number of cubic feet of contaminated material / equipment to be disposed of at a licensed commercial site.
4 e - - -........ -
TABLE I SNM-1067 Waste Material To facilities Covered Be Disposed Of Decontamination Cost Transport / Burial Total Cost Under Snit-1067 in Ft3 in $
Cost in $
in $
Building 5 a)
Facilities 1,000
$10,000
$ 2,000
$ 12,000 b) Equipment 2,000
$10,000
$ 5,000
$ 15,000 Sub-Total 3
3,000 Ft
$ 27,000 I
Building 6 a) Facilities 500
$15,500
$ 1,500
$ 17,000 b) Equipment 4,000
$19,000
$ 9,000
$ 28,000 3-Sub-Total 4,500 Ft
$ 45,000 Building 17
- ) Facilities 1,000
$25,000
$ 3,000
$ 28,000 b)
Equipment 12,000
$40,000
$30,000
$ 70,000 3
Sub-Total 13,000 Ft
$ 98,000 3
TOTALS 20,500 Ft
$170,000