ML20212L141

Amend 1 to License SNM-7,authorizing Operation of Vol Reduction Demonstration Facility

ML20212L141
Person / Time
Site:	07000008
Issue date:	03/03/1987
From:	Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20212L140	List: ML20212L134 ML20212L141 ML20212L147 ML20212L152
References
NUDOCS 8703100254
Download: ML20212L141 (9)

Text

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NRC Form 3M

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3 AC PAGES ts.ed)

U.S. NUCLEAR RE!ULATERY COMMISSION MATERIALS LICENSE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10 Code of Federal Regulations, Chapter 1, Parts 30,31,32,33,34,35,40 and 70, and in reliance on statements and representations j

heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below;to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.

I Ucensee

1. Battelle Columbus Laboratories

3. Ucense number SNM-7, Amendment No. I MAR 3 1987 h 2. 505 King Avenue 3p

]'4. Eipkr7tionifate

[~ ~,

Columbus, Ohio 43201

/

, April 30, 1988

5. Docket or

"/ 'D 70 8 Reference No.

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6. Byproduct, source,and/or 32

7. Chemical and/or physical V8. Maximum amount that licensee N

special nuclear material form d,'may possess at any one time gl Special Nuclear Material

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(u'rl er thislicense d

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/ jf C

E West Jefferson Site g

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A.

Uranium enriched in A.? Any.'

d) I'i I A.

12Fkilograms of I

the U-235 isotope p

Nr-contained U-235 plus

%'T.h!

[TplN the4 associated and

--irradiated Qc l

M.

l' Vi M

J unseparated plutonium c

J: sj!; p b

c v

N B.

Uranium enriched.in' '

B.

My{ d j ' lk*---*f[d ~B.

,1900 grams of f

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tcontained U-235 E

N the U-235 isotope e

D k

,od 4fh h

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--unirradiated V u jl

// gC)\\

g s,v f

l C.

Plutonium (Pu-238 C.

Sea b b o~urce 13 grams g

principalisotope)

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N t

N _A LM

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f D.

Plutonium (Pu-239 D.' 0xjdept ~g D.

17 grams I(

4 principalisotope) l t

l King Avenue Laboratories f

t E.

Uranium enriched in E.

Any E.

500 grams of r

the U-235 isotope contained U-235 p

--unirradiated N

N I

Source Material West Jefferson and King Avenue Sites W

F.

Uranium (natural F.

Any F.

500 kilograms 9

and depleted) and l

?

thorium l

t i

l (Note: Licensee is also authorized to possess any source material that g

may be contained in the irradiated uranium of Item A above.)

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8703100254 B70303 i

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NRC Form 374A U.S. NUCLEAR CEGULATORY COMMISSION l

PAGE OF PAGES License number I

SNM-7 I

MATERIALS LICENSE SUPPLEMENTARY SHEET l

70-8 1

MAR 3 1987 i

I l

B.yproduct Material I

I West Jefferson Site l

G.

Any byproduct material G.

Irradiated fuel G.

22,000,000 Ci total, l

material, activated not more than i

reactor materials 100,000 Ci of any I

and components one radioisotope I

(excluding Items H I

through Q below)

I H.

Hydrogen-3

\\lj y

/

H.

500 C1 g*D(j NQ s I.

Any

'I/' 500 Ci l

I.

Polonium-210 Q

l J.

Californium-252

.~

J.

Any J... <500 Ci I

l Q?

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'f iflK'> Gas dicjK.

15!000 Ci l

K.

Sulfur-35 L/j L.

Chlorine-36 N

L.

1.000 Ci as R

li i ( f\\

$2 G) 3h/ M, 10002Ci M

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1. • ^

M.

Iodine-131 p i

j @ ri/

h N.

Iodine-129

[ N.M IIv g g',j'{N,3 60 i

0.

Cobalt-60 C

Sk.

kh 3,15,000 Ci k.

J kG L/)

l p# P. 'An '/ }g's

,( g P. C250,000 Ci j

g P.

Cesium-137 l

l Q.

Strontium-90 h

Q. Any 250,000 Ci

,I h

I

(

R.

50 Ci total i

Rplo -level rp(dig l(

l R.

Any byproduct material

'a ivehaste f

n r

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l King Avenue Laboratories S.

Any byproduct material S.

Any S.

500 Ci total, not more than 35 Ci of i

any one radioisotope I

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_______________________________________________J

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l N:C Form 374A U.S. NUCLEAR R E: ULATORY COMMISSION PAGE OF PAGES License number l

,, -7 SNM l

MATERIALS LICENSE SUPPLEMENTARY SHEET 70-8 MAR 9 1007 9.

Authorized Use:

a.

For use in accordance with statements, representations and conditions contained in the following portions of the licensee's application for renewal (BCL Document 1081) submitted by letter dated October 23, 1981, except as may be modified by the conditions of this license:

1.

Pages vi through x1, Introduction 2.

Part I, License Conditions 3.

Appendix A, Radiologic S

t mmittee Charter The effective paggsgobt se portions of/ lie application shall be those t

l J

identified in nnex A that is attached to'this iicense.

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L b.

Operation o Ct Volume Reduction Demonstration (Fdcility in r

accordance with_ Condition 26 of this license.

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10. Authorized Placep of U5,e

,J The licensee'best Jeffersoft Site]andj ir{g enue Laboratories located r

as described % pages vi;1{th Q6gh p'ene' ia pa 2.1 through 2.5, Part II, L

bs. &. it'ted by letter dated of the licenseg's appljcatio forir o

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5 E

October 23, 1981, f\\ M i~

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.h"?$

d onsof/AnnexBf(attached),

l Thelicenseesha<11c'omp1'y) wit 11.

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" License Condif.ibn fo6 L ak S

y roffuct Mater,ial Sources,"

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for byproduct sedled s'9' d

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' These deak test g

procedures shalT plso b us f

.PlN238/,

ledso0rce(Item 6.Cabove) p b

L at such time as s removed fr

\\dar'lg packadedntheJN-2 Vault l

for use or transf Q

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12. Notwithstanding Table II and T ble IV presertted Part I, Sections 3.4 and 3.5, for the release ofGateriaA gipihnt and facilities for g

unrestricted use the licensee shillP&dhlre to the provisions of Annex C attached to this license, " Guidelines for Decontamination of Facilities i

and Equipment Prior to Release for Unrestricted Use" dated July 1982.

l 13.

Item 9 above incorporates Appendix A (Radiological Safety Committee Charter) of the licensee's renewal application (BCL-1081) as a condition of the pl license to clarify and define more fully administrative procedures for i

review, approval and audit of activities covered by the license, as I

described in Section 1.3 and Section 2.0 of Part I.

The licensee may 1

I make revisions to the provisions of Appendix A, based upon written evaluation of the changes, without NRC approval if it is determined that l

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l N C Form 314A U.S. NUCLEAR REGULATORY COMMISSION 4

8

,,gr y

PAGES License number l

3[, -7 l

MATERIALS LICENSE 1 aererence number I

SUPPLEMENTARY SHEET l

70-8 l

MAR 3 1987 l

l l

l l

l

13. continued i

I I

l such changes will not decrease the effectiveness of the Committee in I

I i

carrying out its functions. Revisions to the Charter and supporting i

evaluations shall be submitted to the Director, Division of Fuel Cycle and l

l Material Safety, NRC, with a copy to the Administrator, Region III Office, i

i NRC, within 60 days following such changes.

l I

I l

14.

In addition to the subjects identified in Section 5.1.1, Appendix A, the I

h I

aci1M ites A all include an assessment of annual review and appraisal of i

q occupational radiation expos ndWTeese of radioactive material I

over the past year with"tefar' to maintainln~y/stich exposures and releases l g

1 as low as is reasonably; achievable, as stated iii-Secyon 20.1(c),10 CFR i

i Part 20.

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A O

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15. Parti,Section221ofthelicensee'sapplicationspecifieswhen g

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mandatory criti6a,11tysreviews for new operations-are' req"uired by the ubcommittie'.x The reviews byf 'y& Nuclear 5 fety Subcom-l th I

Nuclear Safet ude(1)?a;iyntial-an,alysisbta'nindividualqualified i

1 mittee shall,1 i

in accordance th provision f Se'ction f.282Fand SectioiQ.2, Part I; i

I (2)anindepe nt reviep by af sec6nd (j'ual'fjf,1e'd;individuaLto determine l

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y'sliicare-appfopriate and;that the thatthemethodsusedin7thresults are cogecttdan'd (3)*(

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agop

,9physicp1' inspection by the g

g individual pe'rformin'gf(he,ori_g

' a 3to ass'ute tha,tzthe physical i

environment an arameters'hs f

analysistare val.id.

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16. Parti,SectionM4o t ITca F-reiIe'w1prov s for use of I

l KEN 0 as an acceptiable efitic itf jggth'd.

Pnfor to use of this i

analytical methot.fjy nuclear saf(aiff o

gg uatiofisundeMhisrenewed I

Part II or a new Appen4fx) of its use to NRC for*a(l g

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p i

17. Notwithstanding the formul nh ' n M.

)(c) of the Radiation Safety Committee Charter (Appendix A of th application for renewal), the 1

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licensee shall use the formula:

l l

q l

l l

1 Grams U-235 Grams Pu 1

i I

L

+

220 grams A i

235 i

where L is the mass limit from Table 1, Appendix A of the application, I

forthehproriateU-235 enrichment.

2 I

i

18. The licensee is hereby exempted from the provisions of Section 70.24, I

10 CFR Part 70, insofar as this section applies to special nuclear i

I material authorized under this license for possession and use at the u

l licensee's King Avenue Laboratories.

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i NHC Form 37:A U.S. NUCLEAR E EGULATORY COMMISSION PAGE OF PAGES I

License number l

SNM-7 MATERIALS LICENSE Docket SUPPLEMENTARY SHEET yg_B l

MAR 3 1987 l

I I

19. The licensee shall provide three copies each year of its annual I

environmental report to the Director, Division of Fuel Cycle and Material l

Safety, NRC, and a copy to the Administrator, Region III Office, NRC.

I I

20. Sections 2.1 and 3.10, Part I refer to provisions for training and I

periodic retraining of employees, as appropriate and related to employee I

work assignments with radioactive and fissionable materials. Such I

training shall be conducted, as appropriate, for new employees and prior I

to initiating new operations approved by the Radiological Safety Consnittee 1

I and retraining shall be conducted, org-topfgg appropriate to employee work i

I assignments at least annuallyAI,Documentatiop p/<Q_

f such training and i

l

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retraining shall be maintaine'd.

v l

I Section 4.0, Part Q f'j '

(

l the licensee's renewal app 1'ic tion incorporates I

21.

l the text of previdus amendments issued by the NRC to @p'ecial Nuclear R

Material License No._SNM-7 and Byproduct Material License No. 34-6854-5.

P For clarificati' g, the licensee's authority to l

radioactivity d.nj the Hot 4C(11 Laboratory poolj,pennit 16 crease o

g ater to leYels above the

~

q i

limits for routine operationshas ypecified'ingSection 4.0;is hereby y

affirmed, sub'je[ct to thesfollosing?' pro'visionsMT p

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a.

t pool sha,1A nottex'ceed 450fa before; he~yfare reduced to routine W

l 1evels or below;fA, K 4ll[; y J$

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k W!Oy) j c

1 b.

Work requests, as rapproyedE the; Laboyapry Operajiions Manager and p

4 the resideritiHeallhpPhys'icis shall?be-utilized dur,ing the non-routine p:

operations to>assuFe thtt p6rsbnehar,efaiTare of dye specific radiolo-

)

l l

n gical safetf.c6nsiderationsifgthe opef&tions l

l l

c.

The pool lid co r)shallbeinp ceduringhntimeandafterhours; f

4 d.

Radiation monitoring l'be pe'r.forIngd least twice weekly around h

l the perimeter of the pool and fadia'tlon levels with the cover in b

P place and the cover removed will be posted; q

i Pool water samples will be collected and analyzed at least weekly; and 4

e.

N P

f.

The resin bags of ion columns will be replaced when readings of s

300mR/ hour at one foot are reached.

P P

l The above provisions, extracted from the licensee's letter to the NRC of l

l October 31, 1980 eliminate the need for reference in this license to this i

letter, which requested the non-routine operational levels to accommodate I

such activities as pool cleaning and maintenance, examination and maintenance p

l of storage racks, and the handling of additional fuel assemblies.

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I b = = = = = = = = = mmmm = = rammmwmm ww2.usu= = = %'Emm%mmme = = = = r= 'm = = = >d

A ltMWMMMMMMMMMmmmmmmmmmeumm nummeemmm3ggmageem-emee NRC Form 37fA U.S. NUCLEAL r.EGULATORY COMMISSION PAGE OF PAGES License number MATERIALS LICENSE SUPPLEMENTARY SHEET 70-8 MAR 3 1987.

22. The licensee shall implement, maintain, and execute the response measures of his Radiological Contingency Plan submitted to the Commission on March 5, 1982. The licensee shall also maintain implementing procedures for his Radiological Contingency Plan as necessary to implement Plan.

This Radiological Contingency Plan and associated implementing p(rocedures incorporate the emergency planning requirements of 10 CFR 70.22 1) as they refer to onsite planning and notification procedures. The licensee shall make no change in his Radiological Contingency Plan that would decrease the response effectiveness of the Plan without prior Commission approval as evidenced by a license gt The licensee may make changestohisRadiologicagCBnj(ngen

.lan without prior Comission approval if the changed'dotnot decrease th's sponseeffectivenessofthe

~

Plan. The license shsi1 Viaintain records of changss hat are made to the Plan withcut prior approval for a period of two years (rom the date of the change and shdll furnish the Chief, Advanced Fue and Spent Fuel Licensing Branch,' Division of Fuel Cycle and Material. Safety, NHSS, U.S. Nuclear Regulatory Commission, Washington,4DC'20555,/and the Region III NRClegionals0f(ice at the address %egified *iii Appendix 0 of 10 CFR Part 20,,a report.containing-a description' of eac(change within z/

six months af r the chariges i ma ei f

Section 5.0,1Part I,f'of the,ligense'e's renewallapplj 23.

thetextofpreviousamendmentsjissue

'NRC5toS License No. SNM'-7 an'djByproduct Mater; 34-6854-5 covering decontamination.and'decommissioj lp* *

' pplicab}e to the Battelle Hot Cell Laborator% It'isthefebyp tmed,tatthsprovisjbnsofthesedecon-A ncTG'diipfinanciaDarrangements, tamination and decommiss'16rtinig11 s

continue in effect nden thik rg

'e' J1 en Cg At such time that fahi14 ties covere y this licensbre decontaminated for l

24.

/

proposedunrestrictedrelease(inaccordancewitRAnnexC),thelicensee shall submit a report that fdentiifies th fgtlitieswhereradioactivemate-rials were used and stored},for7dfspo'se the site. The report shall briefly I

describe used and stored, or disposed on' he site. The report shall briefly describe operations conducted and radioactive materials used in the facili-ties and shall assess the results of the decontamination activities. The report shall provide the basis for unrestricted release of the facilities end the site, including a description of sampling and survey methods and instrumentation used, and shall include final contamination survey data for the facilities and grounds. The licensee may segment the report to obtain release of certain areas of facilities of individual structures if it is demonstrated that ongoing activities in other areas will not lead to recontamination of the area or structure proposed for release.

l

25. The licensee is

• authorized to backfill the retired filter bed area on the West Jefferson site where contaminated soil was removed as described in l

the licensee's letter of May 13, 1981. The homogenized bed containing low levels of residual contamination shall be covered with approximately three feet of soil as stated in the letter of May 13, 1981.

5 I

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I m m m m m -M Mm m mmHmii m m a m_ f-~l.-~ K]~7 ;] Q ~ s ' T TT W tmi simiFudM WWm w ww w w w m m m m m m m.

l NRC Form 374A U.S. NUCLEA3 REGULATORY COMMISSION 7

8 j

pm l

License number l

b I

MATERIALS LICENSE SUPPLEMENTARY SHEET 6

I I

I MAR 3 1987 i

26.

In addition to other applicable conditions of this license, operation of l

l the Volume Reduction Demonstration Facility (VRDF) shall be in accordance l

I with the following conditions:

l I

I l

l a.

Operation of the VRDF shall not commence without a valid permit or l

l l

permits issued therefor by the State of Ohio Environmental Protection l

Agency and other permits or authorizations required by federal statutes.

l l

l I

b.

Operation of the VRDF shall be conducted by the licensee in accordance l

I with the conditions, statements and representations contained in the l

l application for license ameA me,nt,datgd August 15, 1983, and revisions I

d I

i datedSeptember28,198QJanuarkM,Q985, January 3,1986,and l

March 10, 1986, ezcepEa's m,odified by cheiditions of this license.

l

.1 l

Thelicenseemay%akechangesintheVRDF,Ndescribed in thy appli i

I i

I any proposed' change does not involve (i) a modif,1 cation to the provisions I

l of Conditionb8,,9, or 10 of this license (ii) a significant increase 1

i I

l l

in radiati6tp exposure, of employees; (iii) an'u'nreviewed safety question; An evaluation shallibe(effectiveness of,VRDFreffluent' treatment systems. l or(iv)a(decreas~5;in l

l s

trequiredato validateJa chang to the VRDF not I

i requirinfDmendmentitir;the lidens'el.

shall be reviewed i

and apprt(ed by thelHea{th and Physic (SuWevaluatio d

I s ' Supervisor an the Radiological l

I I

Safety itte and?shal p'rbVide>thelbasis for determining that I

4 I

m the cha will oti'niel modiftcition'to,thepr6visionsof I

l eidal(iinisign}fican$ question, ora l

Oli'c n t-increase in 8, 9 (lofremp r.10"of i

i Conditi f

unreviewed safet radiation (eieffecitivenes Fj tntreatment systems. A change i

xposkre I

i decrease n I

safety quktion if an accident l

I shall be dee'med t571riv'gl re 611s1 i

I the chingeh ($ )yse'sT depfc6hsequeng values exceedin analysis fo e accident ana skr.ibed 1qNitction 6 of the 3

l the values I

i I

licensee's A 3 G, or thilprbb' ability of.p,cshrrence for the types i

l of events there aluatedisjudgedtoincrd(de;or(ii)revealsa l

Records of evaluations vang, of a differpt type than previously ev possibilityforanacagent i

1 pp"uhvagofRhanges shall be maintained 1

l l

by the licensee.

l I

c.

The licensee shall not retain low-level radioactive waste in physical l

inventory in the VRDF, either in the form of incoming waste or end-product.

l 1

on behalf of customers, freight forwarders, carriers, brokers or the i

I licensee, for a period of time in excess of one year from the time of I

l receipt.

j i

d.

The licensee shall limit release of iodine-125 in effluents from the l

l VRDF to not more than 0.010 curies per year. The licensee shall maintain l

I administrative control procedures and records to achieve and demonstrate i

I that such limits >have not been exceeded.

i I

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_ ___ _ _______ _ ____ _ _ __ _ ___m________________a

--w-====- - -------------

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NRC Fwm MA U.S. NUCLEA7 REGULATORY COMMIS$10N PAGE 8

OF 8

PAGES I

I License number l

l I

MATERIALS LICENSE M -7 D

or Rekence numbe SUPPLEMENTARY SHEET gg l

MAR 3 1g87 l

26. continued l

l l

e.

The licensee shall use appropriate methods for the continuous collec-l l

tion of gaseous hydrogen-3, carbon-14 and iodine-125 samples in VRDF airborne effluents and shall analyze such samples on a daily basis when industrial and institutional waste containing these radionuclides i

I is being processed, and on a weekly basis when other waste, including I

waste from nuclear utilities, is being processed.

If only nuclear I

reactor waste is being processed, no sampling or analysis for I-125 l

is required.

9ad hpe7a9 arheal-time continuous m s

f.

The licensee shall i es in the'VRD ncinerator off-gas discharge I

for particulate I

stack whenever t ineratorisoperating.iT(emonitorshallannunciate mixtures of p,1goom and shall alarm if concentrattons of expected I

in the contro I

rticulate radionuclides should exceed 24 MPC-hours, or l

equivalent using Appendix B. Table II values of 10'CFR Part 20. The g

~

sh'all b(continuously manned _during perjods when the control room)is ope]paKn.

g incineratorf I

f

?;.:

l g

ff

(*

the NRC Regto)nal Administrator

,- n an"disubhiti )ji i I

g.

The licensee shall p' rep r pro'videls ay val 6ation ofiVRDF operations I

semiannusl,1yareport3ta s

l 11'eh'se'e{s,exerengewith;correlatingand managing the rece,udin,g'i e3 performance,ing1 h

c materialasthepp(pt.wpro'&essin,o,p,e,Qipmegt'andrelease>ofradi i

g y

be submitted 6 months 4fttr -in(i tiihlrtions..;Thk'firstreportshall sult'6f/fRD a

t eration and atl6 month intervals I

g%3

[

j thereafte r

Thelicensebshallhavekavajibator vendor h ke\\ i,t,c,r,( tech l

h.

o from the in firsf/six lEs of VRDF incinerator t

i l

operation to a f7 with operat ons, trainin cd trouble-shooting.

I 1.

The licensee shal ins 11 fepce or qther means of access control areas.ffortradiationprotectionof l

around the VRDF or por io hgeof individuals in unrestrict g

l

,j.

The licensee shall test installed HEPA filters used in the VRDF after e

initial installation, at intervals not to exceed six months, and after filter change. Testing shall comply with ANSI N101.1, " Efficiency Testing of Air-Cleaning Systems Containing Devices for Removal of Particles," using a " cold DOP" test with acceptance based on an efficiency of 99.95 percent or better, i

l k.

The licensee shall monitor the environment surrounding the VRDF for l

i l

radionuclides processed therein, including hydrogen-3, carbon-14, i

l l

I and iodine-125 in air, water, soil and vegetation.

I I

I j'

FOR THE U.S. NUCLEAR REGULATORY COMMISSION ate:

' 1987 By:

(brt4 R

I Leland C. Rouse'; Chief i

l Advanced Fuel and Spent Fuel Licensing Branch I

I Division of Fuel Cycle and Material Safety, NMSS l

(***"=V"~=Nyy=yyW%ilmMiimMagpiespiBGsMAlithiMysUndmUmuni~'amiDuUmQm.mUnicsQugiDuii[

l

a ANNEX A LIST OF EFFECTIVE PAGES BATTELLE COLUM8US LABORATORIES APPLICATION AS REFERENCED BY ITEM 9 0F LICENSE NO. SNM-7, DOCKET NO. 70-8 Page No.

Date Page No.

Date Introduction vi 08/15/83*

1.26 10/05/81 vii 08/15/83*

1.27 10/05/81 viii 08/25/83*

1.28 10/05/81 ix 08/15/83*

1.29 10/05/81 x

10/05/81 1.30 10/05/81 xi 10/05/81 1.31 10/05/81 1.32 08/15/83*

1.33 08/15/83*

1.34 08/15/83*

1.35 08/15/83*

Part License 1.36 08/15/83*

Conditions 1.1 08/15/83*

1.2 08/15/83*

1.3 08/15/83*

1.4 08/15/83*

1.5 08/15/83*

Part II, Appendix A, as submitted with 1.6 10/05/81 renewal application by letter dated 1.7 10/05/81 10/23/81.

1.8 10/05/81 1.9 10/05/81 1.10 08/15/83*

1.11 10/05/81 1.12 10/05/81 1.13 10/05/81 1.14 08/15/83*

1.15 10/05/81 1.16 10/05/81 1.17 08/15/83*

1.18 10/05/81 1.19 10/05/81 1.20 08/15/83*

1.21 10/05/81 1.22 08/15/83*

1.23 10/05/81 1.24 08/15/83*

1.25 10/05/81

• Amendment No. I dated MAR 3 1987