ML20198A548

Responds to 860826 Request for Urfo Review of Info from State of Arizona Re Release of Matls from Decommissioning of Secondary Uranium Recovery Operations.Recommendation on Project Submitted

ML20198A548
Person / Time
Issue date:	09/23/1986
From:	Rich Smith NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	Nussbaumer D NRC OFFICE OF STATE PROGRAMS (OSP)
References
REF-WM-189, TASK-TF, TASK-URFO NUDOCS 9801060015
Download: ML20198A548 (4)

Text

,-

DISTRIBUTION URF0 s/f' WM.18i URF0 r/f DBangart, RIV WM-189/NMS/86/09/12/0 NHShopenn LLW Branch, WMLU HPettengill SEP 2 31986 1

i URF0:NHS Docket No. WM-189 l

040WM189100E MEMORANDUM FOR:

Donald A. Nussbaumer Assistant Director for State Agreement Programs Office of State Programs FROM-R. Dale Smith, Director Uranium Recovery Field Office, Region IV

SUBJECT:

TECHNICAL ASSISTANCE This is in response to your request dated August 26, 1986, for URF0 review of information from the State of Arizona related to release of materials from the decommissioning of a secondary uranium recovery I

operation.

The URF0 staff, as part of its review, contacted the Arizona Radiation Regulatory Agency (ARRA) for additional information.

Mr. William Wright, Program Manager of ARRA, supplied the information.

He stated that ANAMAX had sold the land surrounding the facility, but they still owned the facility and the land on which it resides.

In addition to this, the licensee is reexamining the unspecified low-level radioactive waste.

All other information stated in the correspondence remains the same.

O

- our reca adatiaas aa the aroJect toi'aw:

1.

Disposal of Radioactive Waste A.

Disposal stripped resins (1) If the material meets the standards for unrestricted use it can be disposed of in a normal fashion.

However, each barrel of stripped resins should be sampled and analyzed for activity to assure that the activity levels are as low as results indicated on the spot check.-

OFC :

. f........m

... l............ l.0E C 1. l E (ET. C02Y....... l............ l...........

DATE :86/09/22.

9901060015 860923

~

PDR WASTE WPt-189 P_DR

i t

WM-189/NHS/86/09/10/0 2. SEP 2 31936 (2) Should the spent resins be above unrestricted release limits, it could be shipped to a low level waste burial site.

The material must meet the requirements of 10 CFR 61 and be shipped in accordance with applicable DOT l

regulations.

B.

Disposal of Unspecified Radioactive Waste The staff determined om conversations with-ARRA personnel that the company is reexamining the unspecified barreled radioactively contaminated waste.. Should any of the material be-found below unrestricted use linits it may be disposed of as normal waste.

The waste that has been determined to be radioactively contaralnated above the unrestricted use limits

-O will be properly repackaged and shipped to a low level waste disposal site provided it meets the. requirements of 10 CFR 61 and the packaging meets 00T regulations.

C.

Disposal of Contaminated Organic Composite From the limited data presented, it appears that this material is not suitable for release for unrestricted use because of high concentrations of uranium.

Therefore, the following options seem to be available:

(1) The material could be transferred to a licensed uranium processing facility (e.g., Anaconda's Bluewater Mill) provided the facility can and will accept it.

(2) Since the material is a flammable liquid it will not be

~

- (]}.

acceptable for burial at a radioactive waste disposal site.

The only recourse the staff can see for this materiti is to store it until a method of disposal has been dawised.

2.

Decommissioning of a Uranium Concentrator Side Circuit i

A.

The circuit decommissioning plan should have a step-by-step plan for the decontamination and dismantling of each piece of equipment in-the circuit.

Specificity in this phase is most-important.

OFC- :.

i NAME :

- DATE':86/09/23' y

W-'Tw--My g

g g we ryreiy wy4-r1--wy wv'gy p y-y

-gr 9p' t4-:rrwae-- g. m i w rw W-at p Tyv w

• t P

-Cv-z'r1-W-e-+m+pW r14t 4$fr

P9 d

--ere

-T$TTeT-""'-f

^#'

'b 4"

y---

-g-----

WM-189/NHS/86/09/12/0

- SEP 23 DBS B.

There should be strong documentation on the evaluation of the level of radioactive contamination on and within each piece of equipment cleared for unconditional release from the site.

C.

There should be a clean, segregated area on the plant site l=

where cleared equipment and material may be stored prior to shipment offsite.

D.-

Radioactively contaminated equipment and material may be transferred to a licensed facility authorized to receive it.

E.

Radioactively contaminated equipment and material that is not salvageable may be shipped to a licensed facility for disposal-as waste in a low level waste disposal site or a tailings-A impoundment.

The facility shall have received permission in U

the form of a license amendment to dispose of such material.

The aforementioned methods of disposal of radioactively contaminated materials were listed in descending order of preference.

Regulatory Guide 1.86, " Termination of Operating Licenses for Nuclear Reactors,"

does not address this specific decommission effort, however these two references can help the State in their efforts:

1.

" Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for 1

Byproduct or Source Materials," USNRC, Uranium Recovery Field Office, Region IV, Denver, Colorado, September, 1984, 2.

Monitoring for Compliance with Decommissioning Survey Criteria, NUREG/CR-2082 (ORNL/HASRD-95), published June, 1981.

Q-The URF0 staff discussed the methods of. final-verification surveys with the ARRA to'use for final unrestricted clearance by the licensee and the State. ;The staff was able to determine that the State's requirements for

_the licensee and their own verification procedures are very similar to_

that which has been used by URFO.

However, this can only be ascertained by reviewing the ARRA procedures-for this activity.

0FC _

'

HAME 1 DATE :86/09/23'

WM-189/NMS/86/09/12/0 SEP 2 319BG Should you have any additional questions regarding this matter, please contact Messrs. Harry J. Pettengill, Chief, Licensing Branch 2 or Noah M. Shopenn, Program Manager, Licensing Branch 2.

S R. Dale Smith, Director Uranium Recovery Field Office Region IV cc:

Jack Horner, Region V State Agreement Representative Case Closed:

040M189100E Attachments:(1) NUREG/CR-2802 (2) Guidelines for Decontamination of Facilities & Equipment (O'

m i.

fT

.f'

- --l-.4REQb-- 4REQg y--l4 REQ--[-

-l------------l------------l------------!-----------

f NAME :NMS.hopenn/r.s.:.H.Pett.e.igil.l :RDSmith DATE$86/09/23

'7f23ffl, 9 Q3

Attachment No. 1 NUREG/CR-2082

"""^S""

,...,,c,,,,. mi.-

'#r M TL rdN Monitoring for Compliance

With Decommissioning Termination Survey Criteria o

4 Prepared by C. F. Holoway, J. P. Witherspoon, H. W. Dickson, P. M. Lantz, T. Wright 0:k Ridge National Laboratory Mrepared for M.S. Nuclear Regulatory Crmmission e

4 e

{

Attachment No. 2 ll GU10ELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT 1

PRIOR TO RELEASE FOR UNRESTRICTED USE Q

OR TERMINATION OF LICENSES FOR 8VPR000CT OR SOURCE MATER!ALS u

U. 5. Nuclear Regulatory Commission Uranium Recovery Field Office Region IV O

"' c'*d'

' 225 a

SEPTDBER "'M k

e

r

)

)

The instructions in this guide in conjunction with Table I specify the radioactivity and radiation exposure rate limits which should be used in accomplishing the decontamination and survey of surfaces or premises and equipment prior to abandonment or release for unrestricted use.

1.

The licensee shall nake a reasonable effort to eliminate residual contamination.

2.

Radioactivity on equiment or surfaces shall not be covered by paint, plating, or otter covering material unless contamination levels, as detemined by a survey and documented, are below the limits specified in Table 1 prior to applying the covering. A reasonable effort must be made to minimite the contamination prior to use of any covering.

O 3.

The radioactivity on the interior,urface, of,,,e,, d,ain une,, or ductwork shall be detemined by making measurements at all traps, and other appropriate access toints, provided that contamination at these locations is likely to >e representative of contamination on, the interior of the pipes, drain lines, or ductwork. Surfaces of' premises, equiment, or scrap which are likely to be contaminated 4 e

but are of suci size, construction, or location as to make the surface inacce(sible for puntoses of measurement shall be presumed to be contaminated in excess of the limits.

Upon request, the Connission may authorize a licensee to relinquish' 4.

possession or control of premises, equipment, or scrap having -

surfaces contaminated with materials in excess of the limits specified. This may include, but would not be limited to, special circumstances such as rating of buildings, transfer of premises to another organization continuing work with radioactive materials, o'r conversion of facilities to a=1ong-term storage or standby status.

Such requests must:

Provide detailed, specific information describing the premises, a.

equipment or scrap, radioactive contaminants, and the nature extent, and degree of residual surface contamination.

b.

Provide a detailed health and safety analysis which reflects that the residual amounts of materials on surface areas, together with other considerations such as prospective use of the premises, equipment or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.

i

.)

)

2 I

5.

Prior to release of premises for unrestricted use, the licensee shall make a comprehensive radiation survey which establishes that contamination is within the limits s acified in Table 1.

A copy of the survey report shall be filed witi the Uratiium Recovery Field Office, Region IV, P.O. Box 25325 Denver, CO 80225. The survey report shall a.

Identify the premises, b.

Show that reasonable effort has been made to eliminate residual contamination.

c.

Desc/ibethescopeofthesurveyandgeneralprocedures followed.

O d.

state the findinis of the surv y in units specified <n the instruction.

Following review of the report, the NRC will consider visiting the facilities to confirm the survey. The licensee shall not release the premises for unrestricted use without the written approval of the USNRC4 staff.

t 0

O e

k

TABLE I O

O ACCEPTABLE SURFACE CONTAMINATION LEVELS bef bcf ggggy d f REMOVA8LE NUCLIDES" AVERAGE

=_

1,000 dpma/106 car r

15,000 dpa s/100 ca r

U-nat,U-235,U-238,and 5,000 dpm a/100 ca associated decay products r

20 dpe/100 cm*

r 300 dpm/100 ca Transuranics, Ra-226, Ra-228, 100 dpe/100 ca Th-230 Th-118, Pa-231, Ac-227, 1-125, I-129 v

r r

200 dpm/100 ca r

3,000 dpm/100 ca Th. net, Th-232, Sr-90, 1,000 dpm/100 ca Ra-223 Ra-224, U-232. I-126 I-131. I-133 r

1,000 dpm87 /100 ca r

Beta-gasens emitters (huclides 5,000 dpmBy /100 cm2 15,000 dpm87/100 ca with decay modes other than, alpha emission or spontaneous fission) except SR-90 and cthers noted above.

.-..=-

Where surface contamination by both alpha-and beta-gasuna-emitting nuclides exists, the limits established for aloha--

8 and beta-gamme-emitting nuclides should apply independently.

v As used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive meterial as b

determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentation.

~

Measurements of average contaminant should not be averaged over more than I square meter. For objects of less surface C

~

area, the average should be derived for each such object.

dThe maximum contamination level applies to an area of not more than 100 cm2

~

4 e

G A

a k_

~

~

TABLE I O.

O

_2 l

I

'The amount of removable radioactive material per 100 cm* of surface area should be determined by wiping tha dry filter or soft absortpent paper, applying rederate pressure, and assessing the amount of radioac Iv l

ihen removable contamination on objects of less surface area wipe with an appropriate instrument of known efficiency.is determined, the pertinent levels should b The average and mexisus radiation levels associated with schace contamination resulting from beta-gesas l i

should not exceed 0.2 mrad /hr at I cm and 1.0 wad /hr at I cm, respectively, measured through not more than 7 mil per square centimeter of total absoriser.

Ul I

l 1

i 1

e

~

e e

J

~

O mf' O

w foem1r fen Steerfts m'!W'I4 W 1

1-Statt 5ssetts

,o,e.,,os.e,e e.e,,,*d..e t t,e <* -,infe - t' ~

sete es ele wee ce11octed e,

tecetto.,f e wie collects e ggCI y

Stock f1w rete (e8/sec) 1 (sC1hD c.

,f-greer Esthete (

8' (c /r l

w,,gg, (sC1AU e.gg yec11er (WCf/el) _

3 I*eBI.

Tar F3s

%/

Se FF6 st-rse T.

AIS 588FLES For each semple emelytod, esport the feWag IMIW**

]

sete eemple mes collected a, -

e, t,

tecetten of easyte collecties U

IM.

~

g,g f,

r Sedfonsciter (sCfhU -

"*E I

Tb 238 so-rf6 P9-119 en-FF2 7

It Is met a cogfete Ifet of dets te De.a A (See tot of @ end MM IW 2 b/

t Y 8'"IN "-

I*I >1s table 111ostestes fevuot sa1y.

tever cetteste eteeld be esiteleted et 15E entertefety Ivoel, Desed se all Seert** ef 'e'de."e"? 8e 'eN f

See sectlene 6.1,.7.1.4, and 7.3

^ 4 h (W C) shee W te M W W III l

Stentficent systemetic error esse 14 to.._ a esperetely.

All telcolettene of leser lledts of detectfen (f,tt) and,...;;_.. of sesfese M99f910.-.

l I

4 espelement 1 twforsetten.

r j

p.

e e

I~

R r

}

O o

g (CentfaseC ggett feasti fGE BEMff!15 IWWI19EI4 W

2. - MOW 19 SerLU roe each somete snelysed. seeert ik fe11oelag fwferustf m Dete esuele wee collected IM Lacetten of semele coll *Cilen eerface, h. *1 M at. M. " M l

s.

6.-

Type of eagle (for vessefe-LLS

~

c.

Erree totteste (sCfhil conc,.teetten (ect/el) _

(stt/=1) _

v!

nedtonecilde tP-inet (dieselood) 4Heet (;.,- _-f)I N

^

Tb-FM (dfeceleod)

"- f)IO i

Th-F M (..,_

5 Se FIS (diesefood)-

Se-226(e....i")IO FW-219 (dieselevd)

L 1

pt-no (..,

')IO f

t pe ne (dieseleed) i M

c Pe no (.-- c o r

vestvatten. Fear. me rtst sertts i

s.

roe each e k =elysed, sepert tw fe11wlar foreraette Sote esople oss telheted s.

tecetten of sowie coffectfew

~

i b.

Type of essek sai pertlen emetyeed LL8 c.

t w o tetteses (8C'/1El cosco.testsee (sC1/tal _

j sedsenecitee tecitee eet) _

i U-est Tb FM e

se tr6

~

l 7b*nS i

Pe nt l

See factione L t oed 2.1 er this gefer.

- W uet eli esse he eset w onetyeed for essoonsed sodfoneettdee.

i l

i

us 1

O 4

e e

e 98 e

t 8

e

)

O g

j l

}I s1 1

l<.

s.

3 e

}

5.,

.i p:,

i n...

k E

,1

.1 11 h

1 O

k k.

iS

[

.y 3

3 1

{L 18 5

If*gt 3 i-a is

-n1 uil it, 1

i lij!ll i I

i 2

.[2 5 3 a n...li :

l>lt

. on 3

3 a

s 4.14 18

I i

c l

O O

SMWLE FONWLT FOR REPORTIC DETECTION FOitTWtINE DRTA t

Point of Caay11ence Well(s) i l

Background We11(s) i Date (Monr)

Indicster Species j

l Dete-(Monr)

Indicator Species

[

As(agpJ setegn J pntunits)

As(syn J 3egagn ; pngenits) t i

i i

l i

I l

I

%) i i

i i

Sample Population Sample Population i

Sample Mese Sample Mean I

l Sample Standard Sample Standard Deviation Deviation l

Sample Distribution Sample Distribution l

(Norsel, Poisson,other)

(Nomel, Poisson, other) l q

Statistical Significance Test:

Reference:

1 v

I Saaele Statistical Calculation:

1 l

~

• f

+ *

e Results of Statistical Evaluation:

l l

O I

s

_ _ ;a _.