ML20043C859

Rev 0 to United Nuclear Corp Naval Products Decommissioning Plan

ML20043C859
Person / Time
Site:	07000371
Issue date:	06/01/1990
From:	UNITED NUCLEAR CORP. (SUBS. OF UNC, INC.)
To:
Shared Package
ML20043C857	List: ML20043C856 ML20043C859
References
NUDOCS 9006060266
Download: ML20043C859 (24)

Text

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i INC NAVAL PRODUCIS IE03MISSICNING PIAN t

L Page 1 Rev. - 0 Date:

6/01/90'

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0 GENERAL INIGMATICN!

Licensee's name:

UNC Irwprated.

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67 Sandy namart Rd.

l Uncasrville, CT 06M2 Licenses to be ternf:h%4:

I Special Nuclear Matei.tals License:

StM-368, Docket 70-371 By-Products Materials License:

06-06884-1 l

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2.0 DESCRIPTICE OF PIANNED IIXIM4ISSICNING ACTIVITIES:

2.1 nanr-nimaionincr Obiectives, Activitiaa. Tasks, and Scbarbles 2.1.1 name=nimmianincs Obiective. Activities, and Tasks nanr-nimaioning activities will 1) remove alt accountable quantities of nuclear material from the sitei 2) reduce contamination of building structures, fixturw, and relanneble equipnent to levels beloW those prescribed by condition 11 of StN-368; 3) verify that site soil, and building contamination levels are below those determined on the basis of NUREG/CR-5512, assuring that calculated-awanares will remain below the EPA guide line-of 10 '

Q mRenVyear; arx14) transfer all by-product and accelerator produced sources to licensed facilities.- Performance and i

ocupletion of these activities will:

a.

Permit " unrestricted" use of the site and facilities; b.

Maintain exposures As IoW As Reasonably Achievable (AIARA).

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c.

Accanplish the work in a safe and envimmeitally acceptable manner in accordance with all applicable federal and state laws arri regulations; d.

Minimize the volume of waste' shipments; 3

i e.

Meet these objectives while performing the work in the most oost effective manner practicable.

The Montville facility prnmaaaai a form of fully enriched unirradiated uranium into ennamallated ca p s fa. The-startmg material had physical characteristics which j

l minimized the potential for dusting and was prc-wi in glove boxes when unencapsulated. Fuel processing utilized i

mechanical operations.

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O 9006060266 900601 8

PDR ADOCK 07000371 i

C PDC s

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' UNC NAVAL PRODUCIS IEOGNISSIONING PIAN Pege,2 Rev. O Date:

6/01/90 rswRIPPION OF PIANNED rsmenMIONING ACTIVITULS:

(Cont'd)

- 2.1 h=laalonirn abiectives. Activities. Tanks, and SMles (Cont'd)

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2.1.1 h,r==4maicnirn Obiective. Activities and Tasks (Cont'd)

Some of these encapsulated wue.=ta were sanpled by I

x cutting through the cladding material to expose fuel sections for metallographic examination or chemical l

analysis. With few exceptions, the sanple preparation operations (e.g. cutting and grinding) were mechanical in-ll nature, resulting in sludge and dusted contamination.-

Process generated dusts and sitx5ges were cleaned and collected on an ongoing basis.-

several small scale chenical and analytical operations were performed in the chem Imb and sectioning area. In addition to the fully enriched fuel bearing materials, sczne of these operations also involved small quantities of U-233, or natural uranium standards.- Finally, a small number of w w.mits containing source material have been fabricated i

for verification of production parameters. However, these have not been cut for destructive inspection.

1 Altogether, unene== Hated fuel prmaning occupied j

appruximately 15% of the total plant area.

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1 Aeoord'no" dacon activities for equipnent and structures to b,- s.J myd will utilize normal cleaning techniques.

Itere tc. c4 burjr3 will be cleaned to remove accountable quaizhf es of e Jum, and then' prepared for shipnent to bur.'a1 ' -

!ct.yw'. burial site.

Fut.a. a r - Uw structure and site have not been c

detat.ined. W ser, the entire site is zoned for conmu/ t>w Listed below are the major activities and tasks related to h

iaaioning for the areas in which unclad fuel was swW. All work will be performed in accordance with the requirements of NRC License SNM-368.

Process Area Activity Unit 3 Vault Rocan 1.

Clean all glove boxes and contained equipment items to remove visible quantities of' fuel. Itens to be rela mad will meet the limits of Condition 11 of SNM-368. 'Ihese items will be dinaammbled to the extent re==ary to assure O

canpliance with the limits.

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1 INC NAVAL PRODUCTS 0000lMISSIONING PIAN Pege 3 Rev. O Date: 6/01/90 fMCRIPPICBi OF PIANNED rsrngTMIONING ACTIVITTE:

(Cont 8d) 2.1 hinaionirn Obiectives. Activities. Tanks. ard Scbasiles (Cont'd) 2.1.1 DecammissigtliDg Objective. Activities ard Tanks! (Cant'd) j i

B:g(yf)y @

Activity 2.

Parwe contaminated ventilation eqcdpent. 'Ibese activities are identical to periodic maintenance operations perfomed when the plant was in operation.

1 3.

Final parvey all structural and i

building surfaces to C w tuate ocupliance with License condition 11.

Unit 1, Unit 2, Chan.

Cleanup activities are as described i

lab., Met Lab., Pack for the Unit 3 Vault Rocan.

-j Assy.,and Raw Fuel Vault Sectionirg Area and Initial cleanup activities will Met Lab Sanple Prep consist of dismantling the machine Area, Decontamination tools and cutting wir=arit to and Drum Storage Area renove accountable quantities of -

fuel. h balance of the i

activities are as hibed for the i

Unit 3 Vault Room.

Rad Waste Da w nt Cleanup activities will consist of disassembling stardpipes, plumbing, ard tanks, cleanirg the above, and packagirg these materials for burial. Floor cleanup may entail some removal of u a..Le, requirirg appropriate safety controls. h balance of.the cleanup is as described for the Unit 3 Vault Roam.

Septic System and A detailed sanpling plan outside Storage Areas (Attachment A) will assure that uranium cus wd rations are below levels determined on the basis of NURB:i/CR-5512. Soil exceedirq these levels will be evaluated to determine contribution to the 10 mr/ year dose limit.

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tNC NAVAL PROCUC'IS IE03MISSIONING PIAN

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Page 4 Rev. O Date:- 6/01/90 IIBCRIPPICE OF PIANNED IE03MISSICEING ACTIVITIES:

(Oant'd)-

2.1 himalmim Obiectives. Activities. Tasks, and S&arkdes (Cont'd) 2.1.2-

==

Description:==

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'Ihis section provides a description of the basic methods whi& will be utilized for performirg the major clearmp activities. With the possible exception of the potential need for vuiu=Le removal from portions of the Rad Waste basement, the steps listed in 2.1.1 above have all been performed at sone 'cima during the life of the plant, have been psvuoduralized, and do not p e.uit any potential-hazards not previously dealt with. nac - issioning and Decontamination operations will'be performed in accordance with Special Work Permits, as specified in Section 4.6.3, Part I, SM4-368.

'Ihe major devviiuunirEtion projects are listed together with a reference to similar work whid has been performed durirq the life of the facility. 'Ihese activities have all been performed to the limits'of Task Instruction 2.1 whi & are considerably more restrictive than the Candition 11 limits.

Glove box. hood, and amirmarrt cleanuo l

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'Ihese cleanups are performed to contract standards in accordance with Manufacturing Procedure MOP-X-048. When the plant was operating, same of these decutunninated items have been released for rework by outside vendors.

Floor and area cleanuo

'Ihese cleanups have been performed -following spills, which-although infrequent, have occurred in the Unit I, Unit II, Sectioniry, Iab, and Rad. Waste areas.

Sectionina roan cleanout, includhrr machine dinanaarnhly and ventilation duct removal

'Ihe sectioning equipnent has been cleaned in accordance with Shop Procedure SP-105. Sectioning ventilation ducts have been cleaned in accordance with Special Work Ibrmits several times through the life of the facility.

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LNC NAVAL IHODUCTS IECOMISSICtGNG PIAN Page 5 Rev. 0-Date:

6/01/90 9.0 DESCRIPI' ION OF PIANNED DEIDMISSIGNING ACTIVITIES:

(Cont'd) 2.1 hinnionim Obiectives, Activities. Tasks, and ScMles (Cbnt'd) 2.1.2

==

Description:==

Rad waste tank cleanout l

'Ihe RP tanks have been cleaned several times. 'Ihis entailed removal of all rasct11g rings fmn the tanks. Poison rings-i have also been cleaned fmn time to time. Task Instruction i

TI-4-9 applies.

Rotoclone and Colaa cleanout

'Ihe hydrostatic precipator units use for fume scrubbing have been cleaned several times during the life.of the facility, and one unit has been replaced. Cleanout is in accordance with Task Instructions TI 5-14 and 5-15, and dismantling will be under a detailed set of instructions.

i Standoine cleanout

'Ibe starx3 pipes have been cleaned numerals times in accordance with Task Instructions TI 5-2 and will be j

dismantled under a detailed set of instructions.

Sectic field l

'Ibe Septic field is not expected to require cleanup.

However, soil exceeding the cannitted criteria will be.

I evaluated to determine its contribution to the 10 mr/ year limit. 'Ihe poi per gram quantities of uranium in the field afford a minimal opportunity for body uptake and are-expected to meet release limits, Maai on prior scheduled sanpling. 'Ibe Septic Tank was cleaned out when use of the system was discontinued.

Attachment A details the plan for sanpling the Septic Field.

l Review of air sanple and bio-assay data confirms that average m =d4ation levels within and outside the facility were well within the respective regulatory limits. All planned decontamination' steps will be evaluated in accordance with the l

provisions of Smi-368. 'Ihese include an AI. ARA prvpam, requirements for monitoring, for protective clothing, and for limiting exposures.

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IMC NAVAL P5000CFS IE00PMISSIGNING PIAN Page 6 Rev. O Date: 6/01/90 h

IESCRIPTIM OF PLANNED IECGMISSICNING ACTIVITIES:

'(Omt'd) 2.1 narv==ianicnim OtHactives, Activities. Tasks, ard Sobaades (Cont'd) 2.1.3 Procedures namn activities ard tasks will be performed in accordance with w -% as required by SIM-368.

2.1.4 S&edules Figure 2.1'.4 shows the current s&edule for C uiamination operations.

2.2 harv==1=mionim Omanintion and Paarvwaibilitima:

'Ihe organization structure, function, and job'related qualifications will remain as specified in Section 2 of SIM-368. Consistent with all licensed operations, NIS perforns safety evaluations for all tasks involvirg radioactive and hazardous materials, and assures that all tools and materials leaving the site meet release limits.

2.3 Training

Section 2 of SIM-368 specifies training requirunents. In addition, the annual reindoctrination training will a@hasize the qvv=ing decontamination effort and the HP SWP psupam will provide job -

specific training prior to the work being performed as radad.

Training will cover the need for assuring that tools, trucks, etc. are verified for release before leaving the site.

2.4 Contractor Assistance:

Contractors may be used to provide the septic systan drilling and sanple acquisition. Other contractors may also be used to assist in the dismantling of ventilation and other a'ytir= ant whim requires riggirg. 'Ihese contractors, their qualifications and training requirements will be identified before they start work.

3.0 NMRIPTION OF MEMODS USED FOR Fivm;n0N OF OCCUPATIONAL AND IUBLIC HEAIDI AND SAFETY:

3.1 Facility History:

Figure 3.1 shows the location of operations involving unclad fuel.

'Ihis section describes theso operations in terms of fuel form, typical contamination levels, and any unusual corditions leading to the potertial of levels av',aading expectations.

All Montville process operations involved unirradiated fully enriched uranium. 'Ihis material was received in a form whid has very low dusting potential, and after limited processing was ermm=11ated in a l

metal cladding. Sanples of the encapsulated cum mds were sectioned i

cc for inspection using cuttirg equipnent, machined, and polished for metallographic inspection and d emical analysis. As part of the inspection preparation process, scxne sanples were acid etched.

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UNC NAVAL PRODUCIS DECOMISSIONDG PIAN Page 7 Rev. O Date:

6/01/90 l

.0 IESGIP1'IW OF MPIHXE USED PDR PIDIECTIN OF OOCUPATIONAL AND IUBLIC HEAImi AND SAFETY:

3.1 Facility History: (Otx1t'd) l cantamination is primarily a-lated with cutting aM machinirg equipment in the Sectioning area and in the.Sanple Prep ama of the Met. Iab., with the Rad Waste systen and its answ iated plumbing, and with ventilation aqdr== ant. Figure 3.1 shows these areas.

3.2 Ensurina that Wrational Radiation Exoosures Are As ImW As Reasonably Achievable (ALARA):-

Section 4.8 of SIM-368 specifies UNC's AIARA gwuun. ' ho balance of

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Section 4 specifies the actions, instrumentation, and monitoring to achieve ALARA.

il 3.3 Health Ihysics Pru.aram:

Section 4 of SIN-368 specifies the Health Ihysics Ptwrain. Section 2 specifies staffirg, qualifications, and auditing requirements associated with the program.

nuv=issioning operations fall within the scope of activities conducted during plant operation, and present no new sources of potential exposure to workers or the public.

O 34 o "tr t r '+r= ""e1:

Contractor personnel may be used for septic system sanpling and same i.

of the inside dismantling and rigging work. 'Ibey will be trained, and will operate in accordance with the UNC radiological protection program specified in Soction 4 of SNM-368. Contractor tools, trucks, etc. will be verified to meet release limits before leaving the site.

3.5 Radioactive Waste Manaaement:

Radioactive waste management will be identical to current practices.

All packaging and shipments to burial sites will be carried out in accordance with the UNC " Shipping Guide". 'Ihis h= ant includes all reg 11rments pertaining to waste packaging, shipnent, and disposal; and p= scribes the controls and certifications tw=aary for each such shipment.

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Preliminary projections of waste generation are as follows:

Year Waste Volume 1990 12,000 cu. it.

1991 15,000 cu. ft.

1992 7,400 cu. ft.

'Ibese volumes include contaminated equipnent itans and cleanup

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materials frun which all readily removable quantities of uranium have been remaved. Packages therefore present minimal radaation levels.

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LNC NAVAL PRODUCTS DEXINGSSICNING PIAN l

l Ptge 8 Rev. O Date:

6/01/90 i

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PIANNED FINAL RADIATION SURVEY:

NUREG/CR-2082 will be used as a guide for final radiation surveys.

Section 3.3.1 of that report will be used as guidance for surveying all areas in the Irmilding Vault Room and in all B-South locations.

l outdoor areas,. and indoor areas other than IeBuilding Vault Room and all B-South locations will utilize the'recamandations of Section 3.3.2.

h radiologloal conditions' to be daw.ized on the lower surfaces include alpha contamination levels (removable and direct ruwling), arti external gama radiation levels at 1 meter above the floor. For the alpha surveys, both the average and =av4== levels will be shown.

'Ihe gov =.

.t furnished fully enriched uranium has been well duracterized in terns of isotopic ocuposition and contract specification requirements by both UNC and the supplier of. the fuel.

'Ihese isotopic ratios confirm that canpliance with condition 11 limits for acomptable al@a surface contamination will' insure ocupliance for i

beta /gama as well. Nevertheless, analysis will be performed on a sanpling basis to verify the radiation charactersistics, and assure l

that beta /gama dose rates at the surface arxl removable beta contamination need not be furthur evaluated.

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5.0 IUNDING

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DOE has agreed that decontamination and h-immioning costs are i

allowable costs under existing contracts. Copies of appropriate-h==qtation will be available for review at UNC.

6.0 PHYSICAL SECURITY:

UNC security plans may be modified as fuel quantities are r=+rwl.

h revised plans will be re-sutanitted to the NRC as required.

References:

Please refer to the introduction of Attachment A.

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UNC NAVAL PRODUCTS DECDMISSIONDG PIAN Page 11-Rev. O Date:

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UNC NAVAL PRODUCTS DECOMMISSIONING PLAN ATTACEMENT A

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Page A1.

.Rev. O Dates 6/01/90

&nalysis of Septic Leach Field for Decommissionina Introduction From 1958 to 1987, UNC discharged its sewage to an onsite septic system, cince no municipal sewage system was available.

A new septic field was initiated in 1973 south of Building A.

Beginning in April, 1974,.

discharges to that newer system included licensed discharges of low levels l

Of SNM which.had been processed through our liquid rad waste treatment facility.

In 1978, an addition was added south of the original 1973 field in order' to increase capacity.

This is presented in Exhibit 1.

The combination of these two fields will be identified as "the leach field"-throughout this rcport.

The use of the leach field continued until November, 1987 when UNC initiated discharge of radioactive waste water to the new Montville ocwor system per NRC Condition No. 27 to SNM License 368.

This plan presents the survey methods which will be-used to evaluate the Icach field in order to allow decommissioning of the field.

The following documents were utilised in preparation of this plan.

NUREG/CR-2082

" Monitoring For Compliance With Decommissioning Termination Survey Criteria".

llhNUREG/CR-5512" Residual Radioactive Contamination From Decommissioning" l

Draft Report.

Gcneral Decommissioning Plan referenced in condition No. 19 to Materials License NM-368.

Field Layout Ao stated above, the Leach Field can be divided into two sections.

1.

The original field was fed by a main incoming line to a master distribution box (see Exhibit 2).

The waste stream.was split at this point into a pair of two parallel feed lines which ran the length of the field.

A series of leaching pipes run perpendicular to the feed lines.

These leaching pipes have a series of holes which permits the material to uniformly leach into the ground.

Each leaching pipe is laid in gravel to assist'in the leaching.

The leaching pipes are estimated to lie from 2 to 6 feet below the soil surface with the variance due.to the slope of the land and additional clean fill added during the 1986 building construction.

This field will be called Field 1 throughout this report.

2.

The 1978 field addition was placed immediately south of the original system.

This addition was fed by a feed line which was connected to the master distribution box and led into a secondary distribution point.

Two lines led from this second box, each to yet another box.

Each tertiary box fed six dry wells which were positioned around the O

box.

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l UNC NAVAL PRODUCTS DECOMMISSIONING PLAN ATTACNMENT A

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Page A2 Rev. O Dates 6/01/90 Field Layout continued Exhibit 3 shows these twelve dry wells.

Each dry well is 12e deep and has an inside diameter of 5-1/2'.

The well has a series of holes completely around the periphery which permits the leaching (see Exhibit 4).

Approximately 28 of gravel surrounds each well to aid in the process.

This field will be called Field 2 throughout this report.

Statistical Basis Per NUREG/CR-2082, at least 30 sample points shall be obtained in each field.

A statistical test at its 95% confidence level will be performed on the data to assure that the sample is an adequate approximation of the population.

Failure to obtain an adequate sample will cause additional naasurements to be taken until the criteria is met.

Background 8mmnlina The first step of the survey plan is to determine the radiation background levels of the site.

This will include both beta-gamma measurements-at the curface and gamma measurements at 1 meter.

Thirty background meesurements will be taken from various locations both close to the field and cignificantly away from the field.

Locations will be chosen which are olieved to have relatively the same soil and rock composition (primarily gravel and sand) as the leach field.

The second part of the background sampling consists of soil analysis.

Five holes will be drilled at random locations to the south and west of the leach field.

Three holes will go down 15' while the other two will be drilled to the water table (approximately 20 - 24 feet).

Samples will be taken every three feet for analysis.

As above, locations will be chosen which best reflect the soil located in the leach field.

This data will be added to the two background samples which were taken in 1985 (Report to W.T. Crow from W. F. Kirk dated 10-29-85).

Therefore the soil from a total of seven holus will be included in the data.

Although less than 30 grid sample points are used, the total number of background soil samples for analysis will exceed this value.

Surface Radioactivity Level SamDlina Field 1 A series of 10 meter X 10 meter grids will be marked off to completely encompass Field 1 (See Exhibit 5).

The starting point for the grids will be the main distribution box.

Surface beta-gamma readings will be taken at every grid point and at the approximate center of each grid.

Additionally, gamma readings will be measured at 1 meter from the surface at all locations.

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UNC NAVAL PRODUCTS DECOMMISSIONING PLAN j

ATTACEMENT A llh Page A3 Rev. O Dates 6/01/90 surface Radioactivity Level samnlina continued:-

Field 2

& series of 5 meter X 5 meter grids will be marked off to completely encompass Field 2'(See Exhibit 6).

The starting point for the grids i

will be the secondary distribution box.

Identical measurements to i

those stated above will be taken at each grid point.

Measurements will not be taken at the center of each grid due to the smaller grid area.

Both Fields A general walk over survey will also be performed in both fields in order to verify the absence =of any technologically enhanced areas of 1

radiation.

Should this not be verified, the identified areas will be included in the soil sampling discussed below.

4 soil samalina soil samples will consist of split samples for NRC/ORAU and UNC analysis.

Some samples may also be collected for CT. State DEP use as part of a non-nuclear hasardous material characterisation.

llhNeterReadingsAboveBackground All locations-(if any) which demonstrate an above background reading during the surface sampling discussed above, shall-be subject to soil i

sampling.

"Above background" will consist of those measurements which exceed the mean background level at the 95% confidence level.

These samples may be included as part of the random sampling discussed below.

Field 1 systematic samolina Ten locations will be chosen based on technical-knowledge of the field.

Holes will be dug at these locations with care not to hit any pipes.

Every hole will penetrate at least 128 with every fifth hole being dug down to the water table where the ground water shall also be obtained for sampling.

-Soil = samples will be taken every 18".

Random samnlina: Another twenty grid points will be randomly chosen from the grid shown in Exhibit 5.

Additional random grid points will also be selected in case an inaccessible location is initially chosen.

An inaccessible location would be that covered by a very large boulder or by a concrete' slab but would not include soil covered by blacktop.

sampling will occur as stated above.

The combination of the systematic and the random sampling provides for 30 sampling locations.

UNC NAVAL PRODUCTS DECOMMIB8IONING PLAN ATTACHMENT A

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Page A4 Rev. O Dates 6/01/90 Soil Analysis continued - Field la Pine Analysist In addition, following the soil sampling, the pipes will be individually sampled (See Exhibit 7).

The locations designated as L1 through L7 will be excavated and the sludge (if present) will be sampled.

Also, twelve leach pipes will be randomly selected by number for sampling.

Each number chosen shall be sampled at locations near the feed line and out near the and of the pipe.

2 Thus a total of 31 pipe locations will be analysed.

Care will be exercised to prevent any potential contamination from leaving the broken pipe and entering into the adjacent soil.

Field 2 Systematic samolina The soil above and below each well (W1 through W12) shall be sampled.

Moles will be dug at.these locations down to the water table where water samples will be obtained.

Soil samples will be taken every len.

Random samplinct Eighteen grid points will be randomly chosen from the grid shown in Exhibit 6.

Holes will be dug down 20 feet or to the water table.

For any holes which may pass through a well or the gravel around a well, then sampling shall include only the soil above and below the gravel or well.

The combination of the systematic and

()

random sampling makes a total of thirty sample locations.

Well Analysis In addition, all wells and distribution boxes (W1 through W15) will be sampled.

This sampling will consist of sludge collection and subsequent meter analysis at varying depths within the well or box.

Related Eauinment The main discharge pipe, the 5000 gallon septic tank, and any other related equipment not discussed in this report will be evaluated under a caparate project.

These equipment items are still required for the present discharge system.

These will be sampled at the end of the decommissioning effort in accordance with the criteria discussed in the Decommissioning Plan.

Hazardous Materials soil samples will also be analysed for the presence of various hasardous natorials to assure compliance with all applicable regulations.

O

t UNC NAVAL PRODUCTS DECONNISSIONING PLAN ATTACKMENT A

()

Page A5 Rev. O Dates 6/01/90 Analysis And Instrumentation Radiation measurements will be taken with a uR meter.

Soil samples will b3 taken using a split sampler and other standard excavation equipment.

All soil analysis will be performed by a properly certified outside 1cboratory.

Soil samples will be measured for gross alpha, selected camples will be further analysed for total Uranium and in some cases, icotopic analysis shall be performed, several samples will also be checked for additional isotopes including radium 226.

The acceptable alpha radiation release level for soil at UNC will be as ctated in the Decommissioning Plan.

O O

UNC NAVAL PRODUCTS DBOO90tIBSIONING PLAN-ATTACEBtBNT &

Page A6 Rev. 0-Dates 6/01/90 i

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Page A10 Rev. O Dates' 6/01/90 i'

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