ML20198G774

Rev 2 to Decommissioning Plan for License SNM-1168

ML20198G774
Person / Time
Site:	07001201, 07000364
Issue date:	02/15/1978
From:	BABCOCK & WILCOX CO.
To:
References
08670, 8670, NUDOCS 8601110077
Download: ML20198G774 (9)

Text

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l SNM 1168 DECOMMISSIONING PLAN j

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Babcock & Wilcox Company l

Nuclear Materials Division l,

Commercial Nuclear Fuel Plant l

Lynchburg, Virginia j

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Revision 2 february 15, 19/d U,

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i 8601110077 790215 PDR ADOCK 07000364 i

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SNW1'63 i

Table of Contents J

1.0 Introduction 2.0 Perfamance Objective 3.0 Decommissioning Plan 3.1 General Considerations 3.2 Procedure r

3.3 Final Report and Release

. 4.0 Financial Assurance j

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SNM-1168 7]

1.0 INTRODUCTION

The Babcock & Wilcox Cc pany (B&W) holds f4RC License SNM-1168 to conduct operations at its facilities in Lynchburg, Virginia involving source and special nuclear caterials. Although there is no regulation or license condition currently in effect which would require the decontamination '

and decommissioning of its facilities. Babcock & Wilcox will, after cessation of the licensed activities, comply with a valid license require-ment to provide for decontamination cf these facilities to protect the environment and the general public from exposure to levels of radioactivity in excess of those permissible, This Plan sets forth the manner in which we believe'this can be accomplished. Methods and techniques different from those described herein may be employed to achieve the Performance Objective.

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2.0 PERFORMANCE OBJECTIVE The Performance Objective is to assure that the health and safety of the general public are protected by decontaminating the facilities to levels which do not exceed those specified in Table I so as to enable release of the property for unrestricted use.

j 3.0 DECOMMISSIOlING PLAff By the nature of its manufacturing operations, UO2 pellet fabrication.

fuel rod loading and fuel assembly fabrication, storaDe and shipping, tho l

l CNFP site and facilities are, for the most part, not currently contaminated by licensed material.

Many operations ere conducted which involve either l

no licensed material or dnly material Mndled a sealed :curces sr.h as l

fuel rods.

The UF t UO c nversi n facility and increased pelletizing 6

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crea are being designed.

Operation uricg radioactive materials will not i

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SM-1168 begin before 1981. The conversion facility will include several buildings

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and installaticns, the principal ones being the main conversion building, effluent treatment facility, mechanical equipment building and the ware-house. All areas, including those in which no contamination is anticipated, will be surveyed to verify that Table I levels are not exceeded.

3.1 General Consideratio_ns_

3.1.1 Decontamination will be to levels not to exceed those specified in Table I.

In addition, a reasonable effort will be made (and documented) to further reduce contamination levels to as low as reasonably achievable.

3.1.2 No covering will be applied to radioactive surfaces (e.g.,

paint, plating, etc.) until it is known that contamination levels are below those of Table I, and until it is known (h

that reasonable efforts have been made to further reduce contamination below said levels.

3.1.3 The radioactivity of interior surfaces of pipes, ductwork, etc., will be determined by taking measurements at all traps and other appropriate access points, provided contami-nation 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 in-accessible, then such interior surfaces shall be assumed to be contaminated in excess of levels specified in Table I.

3.2 Procedure 3.2.1 This procedure shell apply a f ter cil readily removal source 6nd spect al nuclear r:ateria) has bcen recoved from the site.

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Stim-ll68 3.2.2 A radiological presurvey will be made of contaminated areas I

in order to assess the extent of decontamination involved.

this prasur'.cy will be reviewed with NRC and will include:

a) floor core samples b) core sa ples of earth beneath the floor c) smears of ceramic or metallic or other non-porous wall surfaces, both on and below paint d) roof smear samples "e) samples of concrete or block walls to a depth of'l/8 inch l

t or more f) smears of roof trusses and supports core samples of earth adj' cent to contaminated under-g) a grcund sewer lines.

Records and drawings of sample locations and results will be prepared and maintained.

3.2. 3 Contamination equipment will be disposed of by burial or sale.

a) Equipment disposed of via burial will not be decontami-nated; rather, the equipment will be cleaned in a manner comparable to the cleaning performed in preparation for a physical invent'ory.

b)

Contaminated equipment may be sold for use at another fuel cycle facility.

In sucn instances, all exterior surfaces will be cleaned to levels permissible for rastricted areas.

The equiptent will then be ptckaged and transported in accordance with DOI and fiRC reaulations.

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SNil-1168 c) Equipment may be sold for use at non-nuclear facilities.

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~-~"' In LUch instances, all surfaces, interior and exterior,

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y shall be decontaminated not to exceed levels given in Table I.

'3.2.4 Following disposal of process equipment, roof trusses, walls, pipes. floors, and non-process equipment will be wet-cleaned

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to remove loose surface contamination.

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3.2.5 Surface removal of contaminated walls will then ensue.

Material removal will be repeated as necessary. When the

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contamination levels of Table I have been reached, a final cleaning (wet wipe-down) will be performed.

i 3.2.6 Decontacination of flocrs will follow.

Depending upon the extent of contamination, surface cleaning, surface remoial, or removal of sections of the floor will be dictated.

(Vo) 3.2.7 All contaminated tenks in the liquid efficent system will then be mraaved and disposed of. Underground contaminated piping will be Excavated end removed for burial.

If sampling indicates contaminated soil, removal or burial of soil will also be accomplished.

3.2.8 The contaminated-crea ventilation system will remain intact until all of the above steps have been completed.

It will then be removed and buried.

3.2.9 In the event that it is planned to razo a facility, then one of two courses of action ufil oe taken.

a) The facility may be whnlly decantaminated as outlined above, then leveled.

n this case, the walls and roof ray be dispnsed of via sanitary landfill.

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SNM-1168 b) Surface cleaning, rather than surface removal and/or O(/

decontamination of walls may be pursued, in which case the walls will be disposed via burial.

3.2.10 In general, it is anticipated that the above steps will be followed sequentially.

In certain cases, however, it may be more cost effective, or efficient, to do two or more of l

l the steps simultaneously (for example, presurvey of general plant areas could be undertaken at the same time that general cleanup of licensed material in the contaminated area is underway).

Such modifications shall be approved only after the overall impact on containment of effluents during sub-sequent operations is considered.

3.3 Final Report and Release l

3.3.1 Upon completion of the decontamination of a facility, a A

comprehensive radiological grid survey will be taken.

If necessary, additional decontamination will be performed.

3.3.2 When it has been established that residual contamination is within the limits specified in Table I, a survey report will be sent to the Director, Office of Nuclear Materials Safety and Safeguards, with a copy to the Director of Region II.

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Identify the premises; b) Show that reasonable effort has been made to reduce residual contamination below the levels of Table I; c)

Describe the scope of the survey and the general procedures followed; and d) State the results of.the final survey, in units specified in Table I.,

SNM-1168 3.3.3 Release to unrestricted use is anticipated upon approval by NRC.

4.0 FINANCIAL ASSURANCE O

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. v, SNH-1168 TABLEI '

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ACCEPTADLE SURFACE CONTA.MINATION LEVEI.S

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REMOV.A3LE e~ i.

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U. cut, U 23 5. U.233. md ',

5.000 dpm c/100 cm2 b

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15,000 dpm c/100 ' me2

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1,000 dpm c/100 cm2

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Transurenics. Ra 226,1b 228, 103 dpm/100 cm2 300 dptn/100 cm2

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t..,CAc.227 I.125 1129Th.230, Th 228. Pa.231, 20 dpm/100,cm2 N.,$

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<r.j:,'rg., ' -[; Thist, Th-232 Sr.90, 1000 dpm/105 cmg 200'dp:6)l00crn 5.s.s 3000 dpm/l00 cin2.

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s' i Re.223, Rt 224, U.232,

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5000 dpmky/103 cm2 15,000 dpm,N/100 cm7 105:dptn Pr/100 c.E W'-.

with deer.y modes oth:r fhin alpha

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sverer: should be derived Ice ese:1 cuch obbet.

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should tre redw4 pri,portfo..r,Jz, sted the entire surfsco should be rdpod. inst

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