ML20099D130

Forwards Responses to 841012 Questions Re 840807 Application for Dismantlement & Termination of CX-10 Facility

ML20099D130
Person / Time
Site:	Lynchburg Research Center
Issue date:	11/15/1984
From:	Olsen A BABCOCK & WILCOX CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), Office of Nuclear Reactor Regulation
References
NUDOCS 8411200216
Download: ML20099D130 (15)

Text

_ , . - - - .

4 F i

- e. Babcock & Wilcox - E,*.*.*n*.'*".e'n *n c "., *"

! a McD.rmott company P.O. Box 230

' Lynchburg, Virginia 24605 (804) 304-5111 November 15, 1984 i

Director . .

Nuclear Reactor Regulation i

~U.S. Nuclear Regulatory Commission-Washington, DC .20555 Attn: Document Control Desk

' License: CX-10 Docket 50-13

Subject:

Answers to questions on decommissioning Gentlemen:

Questions in regard to B&W's application, dated August 7, 1984, for dismantlement and termination of the CX-10 facility were forwarded by letter dated October 12, 1984. Your questions and B&W's responses are attached.

In addition to the fourteen questions presented in the letter one more was added during a visit to the Lynchburg Research Center by Mr. Harold Bernard. Our response to that question is attached as Number 15.

If you require additional information please don't hesitate to call me.

Very truly yours, BABC0CK & WILC0X COMPANY Lynchburg Research Center

%nu rne F. Olsen Senior License Administrator ccm Subscribed and sworn to before me this / day of 1984 City of Lynchburg, Virginia Notary Public

/

My commission expires w -M Ja,/f 8 4 0

kDMA

-P obb!3 PDR 4 l

i

{6

% %,y 7 Jpg $b(@b{

g A[ '

(" N %% "[' Up QV 3^ " L ya :; gJ gge _7 . %g , g? r m l_

i, ti M; ,L'  :

L i,:, '. w

' .> v>

j, ;p..

$ 2 m~ , -

W *

^

u

' ' Sy -

3 A de '*

'[

^

l v 4-[ , ..,

,- b '

lhl le, c

~

9,,,* '

' *

• r

. f <

x w [ Questions /andLResponsesi 0 W

+

y ,  ; . i; -

3r ,

m

,' h; - ;[ . _

, s

, _ h ^

(w [ ll.:  % t Describe the; operating' experiencejf the CX-10 readtor.with respect ltoh y 9 ,1 M)I Contamination.eventiduring reactor operation, including spills,: radio '

, tactive leaks that:could penetrate. concrete:and/or soil,= and' airborne >

iradioactivty thaticould contaminate ventilation. ductworkFpip.ing etc...

that may be of particular concern during dismantling and decontamination.7 <

% y ~

L' , RESPONSE:: ,

? s s . .

.. m. .c ..

o ,

• Except for Bay 2,Lthe CX-10 Control Room.and'the radioactive. liquid

^

'+W ' waste holding tank (RLWHT), ~all'former use ar'easiin _ Building A' addressed 4 i . in the:CX-10 Decommissioning. Plan have~already,beenLdecontaminated Jand-

=put'to general use. No _ major! contamination events or effluent releases are known to have occurred in these areas: or:inLBay 2 that would warranti -

^

3special attention during dismantling.; Minor contamination incidents

included spilling small. quantities (e.g., onelpellet) of fuel from cut." '

or broken fuel: pins. - Such spills were infrequent and were cleaned lup <

1. immediately; they should pose little residual, hazard. -(Irradiation ^ofy .

.CX-10 fuel was so. low thatithe radioactive hazard-associated with any

. residual-fue1~ contamination is essentially the same.as that associated '

lwith the same quantity _ of fresh fuel)L : 0ther incidents: include over-f1_owing the Bay 2 sump when the ~ automatic sump pump failed while mod-erator.was bein s :before, during,gand drained-after thefrom the CX-10 cleanup of these dump tank.i Surveys infrequent performed _

spills failed to-detect any contamination in the moderator or on the basement floor.;

One area which does warrent special' consideration during the decommissioning _

operation is the RLWHT, which the CX-10 facility shared with three other; critical facilities'(CX-1 CX-12, and CX-19) and a pool reactor (R-47)l . ,,

' that were also housed in Building A. This holdin

' underground and outdoors (Figure 2-l'of the Plan)g ,

tank, which has overflowed onis located -

several occasions, flooding the surrounding soil. Routine checks of. the. ,

radioactive contents made each time the RLWHT was emptied, however,-

typically revealed .little or no radioactivity.. The planned survey of the RLWHT, its ~ associated drainlines and the soll basin :in which it is . '

located -is discussed in the LRC's response to question No. _12.

1

'(b) Existence of any high radiation areas due to radioactivity in systems.-

RESPONSE

i

.There are no.high radiation areas associated with CX-10 equipment.

l' (c) Determination of the integrity of the liquid radwaste disposal system 6 l

to verify the absence of leakage to the contiguous soil system.

?

RESPONSE:- ,

L . There is no operating experience to indicate failure of the CX-10 hot

' drains.or resultant contamination. The survey plan for the hot drain system is discussed in the LRC response to Question'No. 12.-

m -

i , A p

. l

^L

- , c

}. ,

l

,- a:

'L ,

d I -..

gypy y '

y, +

,-y; -

y g L gy , g ' p j3, , Q %n j XX

.yL m: N~ M' c

y" QWL%  % hw ' ly ,

w k (; & m% '

% %x&;hg&,f *

,}"q%

v 3

p 3 g... a s? My ,g 4$; .:K

b w%' ' ' ; @6 '

cc -~ ,+ .n M ~, ; . 77 , . gy--

Q} , }. ;;Nc;@&'f[*p p f]f:VW Y LQh f, L

j Q y c_s' [";

,x g, ,m e ,7 y _ we .

+

w 4

+ ]4%seGjg w

.W,: q;p ,

7

- zgp g .y s ,

q' y , gg 7

, . , , _g -

mg,q:}Ly n 2 y ' %f f.; > .

,  ; . , , :F '

'M , .

4 & %i i $. 5.. . .

~ . , +:,_f . ~ . . , s -- , . - - .

p

, b W :,(d)fLArealand airborne dg.adioactivity that may have been cause:for,grosslyf 9 s-A* 2 ' T : exceeding monitoff 6gtsystem alarm set-point levels.; >

m ~

.. ># ~

p  : 1 4

^Y

'2 R-

@s Jj xRESPONSE:l - w@s[n m .-

4v T>. , $0

, .I ee response't.oiQue5 tion No'. 1(a);2 S

p >,; a

' >g 4 ^W t g 1-T ;"

,. , de) Other/radwesteleffluent" releases tha't miyihavef exceededTtechnicalf ' ;

s, specification; limits.;

.. .. , f< r y .

~. .

^ RESPONSE:D .

+

'* - s

. . See response .to Question.,No'.11(a).s y.

, .x ,

[-

(f) . .. Fuel' handling'and' storage..

y

"( ,

RESPONSE:~  ? ' '

O 3

x a, .m 1

- x "

- Fueliwaslhindled, ~used and . stored iin sealed :formfin:Say"2 except on a few occasionsiwhen fan'alytical quantit'fes'of' fuel were:dissolvediinial .

fume hood.i wereicutLor.n the chemistry

brokeniin. Bay;21aboratory

(room as: mentioned inil(a)iabove. H;of the1P_1an)"a'nd(when)pinsi

- r N- L cy ,m '

As mentioned in' the LRC's fesponses ;to Question?No} 12L theipowidtlevel,;

? duration, and frequency of CX-10' reactor operation war such thatithe- ,

. fission product ~ inventory in;the'fuet has' been keptiex1remely low. . Except; just after operation, the fission ~ product-inventory hai bean-low'enough' to' allow the fuel ^to be ' manually handled.during transfe'r and loading. -

. . . . . - C'"

When.the CX-10 dismantling order takes effect, all fuel will have been?

removed from the facility. :The shipping operation , involved loading inta'ct fuel pins 'and fuel pin segments irito.NRC and DOT approved l shipping containers.and returning the fuel to DOE-0RNL for additional critical ~

experiments or to National Lead Co. 'for reprocessing.- Not all. of the-fuel . pins can be -loaded as 'ist about 190 fuel pins will be cut in two in order to fit inside the DOT-6M containers. This cutting operation-will be performed-in a specially designed cutting ~ hood provided with'a HEPA filtered off gas system. The hood will be; located inside a specially built cutting booth to provide additioral confinement for controlling the -

spread'of unexpected contamination. A step off pad and personn'l e monitor-will be placed at the cutting booth exit. The cutting ~ booth .is located-in Bay 2.

The entire cutting operation has been reviewed and approved by the LRC

. Safety Review Comittee, and will= be ' performed 'in accordance with approved written: procedures. t y  ;(g) Any excessive activation of areas of'the biologicab snield.

9 4.

9

<a '

, , n+l s _

2, ,

+

• W

( g["i  ? f

' ~

E 1* ,

m q

m .m -

g m , .

m.

R

~

( (C ,

+

4 r ,

,x ,+ ' .

4

~

~

RESPONSEi-

- As1 evidenced;by. the: low fuel' radioactivity, the' total ineutron exposure .

, , of ' nearby l equipment will; be'quiteismall . ' Activation of'the nearest :

• ' concrete wall,' which .is: several ' feet from' the.' core ~.tankLedge, is : expected -

+ x to,be negligible. >

2.- ?Section'4.4 of the' plan states that pipes, drainlines:and.ductwork 'shall-

be' surveyed for contamination provided;that

any contamination found at -

appropriate-access points is 'likely to be representative of. contamination

~

in:the; interior of theseisystems.f _ Is this the only alternative forf such .

~

s' urveys?. What will _ be the; survey 1 plan, if no appropriate access point-.is-found.1which could be~used to be representative of: contamination on thei

" interior of; pipes,. etc.1

RESPONSEi <

sSee1 response to Question No.L12.

3.- . The soil = contamination limit proposed .in 'your_' plan sis 30 picocuries/ gram -

for ' enriched uranium and 10 picocuries/ gram for natural thorium and .

Th-232. Verify that the: dose rate ' derived from the soil: contamination m meets SuR/hr above natural background, as measured Lat' one meter from the

' surface, or why_ the B&W level-of 10uR/hris appropriate.

~

RESPONSE

These criteria ~were taken from Enclosure 4, tolSECY 81-576, and are-based' on limiting the dose ~'to bones and lungs that might result _from any con-ceivable use of the. property, rather than direct Lradiation levels.

4. The staff position' for release for unrestricted use or.anrestricted access is Regulatory Guide 1.86 or SuR/hr above natural background at 1 meter.

However, if it can be demonstrated that'the maximum exposure to an indi-vidual from the ' radiation would be less than the staff's annual exposure limit of 10uR/yr because of potential occupancy in the vicinity of.the radiation, than 10uR/hr may be acceptable alternative. Do you intend to make this analysis or:do you intend to. change your release or accesss criteria, as addressed in Section '4.2 from 10uR/hr to SuR/hr to be con-sistent with the staff criteria?

RESPONSE:.

It is the intent of the LRC to prepare the CX-10 facility;in a' manner

- that will permi_t the NRC to release the facility for unrestricted use and unrestricted access. This release shall not carry with it.any re-Jstriction on the time of occupancy or to the future use of the facility.

Therefor all references to the release criteria of 10uR/hr 01 meter-g shall be superseded by the staff position limit of SuR/hr 91 meter.

I:

]. ,

t d

h$

y 3.NMh , g 7 ggf kN  ;. dYY

f. M g 'p- ,

Nc w Z, , ,

CA wC gh@ mr-a- , , ' ,, -

m. h e ,an.:w b* , ., i

+ , , L s -m , .

.Dr c'  ? TIE s I ' > ,. '[ / (O M ([ ' ) .(

,}g ' Qnj t

g' g W % Q[y Qj f. iW '

}, ,,

wy -

, f ,- s

,pk

~ , .e . we 5 _ %m& ~ , y y ,

%g7n b %uf+> . WK s

.u =-

a --

% > c;' v':

^w~ w* n ,' .w -( - Gy' 3e ~,>2 m . u

+ ' r. o e

,n.

z - -

e gc a, o >

9L L y; t .

r#ggy b  ; ; .L [ c L n.; a _. , . .y ,g y R4

, e5W j Section;4;7;1istates that fixed contamination, shall;be measuredNith a A FM # Gb APAC-4G.EiLDis~

3 c ussitheisethodologyJto befused Lto convert;the 7count

• rate.

' Tof?the11nstrumentiinto theEsurface contaminationilimitstof4 Reg."Guidef "

~

('c-'-

@4 M MAdM 11i861which;gives thesellimits'jiniunitsjofid/m perjl00;cm2L i (' ,Jm y $' 7 o u g" " ~wm < - m R&w

'p 3@> i RESPONSEi w; j uz. ~s~' p :hFEr[C;' . XL AC 4 2, . 6 -E, g :n -. .w.

, , z .

.3 "w .

44TheEdetectorisiefficiency wi1Ube based on calibration 'with 'an;; alpha %m -

x

~f^

w .,

m I(egDPu-239)lor1b6ta i(Tc-99)Jsource whose strength (dpm)?isitriceable m 7 , ' %; T , to NBSMThis c'alibration =willf be performed'and thelinstrument;settingsc YW '_ :ny w establishediin accordance withian approved. written ;technica1' procedure.v MN i ;7

>A . label /will? beiattached;tof theLinstrument' describing the calibration C

%2 %f C .h*

m n ,1 -Y #statusiandJthe 71s? to':be' used.J radiatiorEtypeJ(alphalorEbeta)ifor Thel activity;per unit'arealwillf be~ determined: which thefinstrumenti'by, nor. - .%

), -# . 1malizingithemeasured/dpmi(efficiencytcorrected: cpm)ibyithe'sensitivec X <*~ -

- W' .

i surface areasoftthefparticulariprobe being/used.GThis. area is/provided * . , ,

E27 - '1

~

# orf f each, type of probe by;the Linstrument manufacturer.s ' ,,

• p . I,

6. - Sect'ionI4j.2) specifies;that standard smeaningit eshnihesjs'hallfbe usedJ - i c

g' ,3: - &jPleas'e: describe;thesetechniques.pThecounting:systemtobe;usedjtoby +

count 1these_smearsfis a. gas proportional: counter.- cIs this counter apa ' D z s U ~ (E ,-

plaboratoryjcounting systemforOa hand-held < type survey. meter?t 'Ifithe P - W

, f" , tlatterJtypefinstrument, .describelthe instrument:(comercial11dentifi 4 l -

a

.q* .

Tc'ationCif:a'ppropriate)R and(the counting procedure torbe:usiedito? ' '

identifyLalpha,.vsf beta ~ contamination. . - *

- .m . . m, x *

. -- .p4 y s

.- RESPONSE:1 a

.' w 3

. 6 "

There.are two typesioftsmears that.will be taken;fone is a "large~ area i *

' smear", and. the other is ' a "small area - smear. '.' -

~

m y

, m. "

. p -

E , The'purposefof;the'largeareasmearis'toindicatsthepresenceor Y B absence of, removable contamination. No attempttwill be made .to-icorrelate the -smear readings' with dpm/100cm2.; This type of smear is

.< f taken by lightly? wiping the: entire surface (floor, pipes, drum, etc.) '

w 'with the smear' media.. -The smear is then taken to'an; area;of suitably I ilow! background and tsu;rveyed with a PAC-4G for the presence of alpha.or, To . beta contamination,-~or both'. The PAC-4G hi

(established during instrument calibration)gh voltagethatsetting (s)

^

ensure the radiation

[p  : types (alpha l beta);can be distinguished.

O; ~ ,

Fi _

The3 purpose of f thefsmall' area smear is to determine the amount of remov-b , < able contamination per unit area (dpm/100cm2)- on the surface being sur-E* ",

veyedt The; smear is taken by rubbing:the smear media (e.g., 3 cm diameter b' qfilteripaper)(across the area to be surveyed, making an 5, X, or Z pass,

't' ,

~

' applying moderate; pressure. Usually, a 100cm2 area is wiped with a single ipass.C Alternatively, areas that are~ multiples ofc100cm2 may be wiped.

_,j' >

s , 3he smear 'is then packaged,' labeled, and taken .tofa' laboratory counting y & f system--(such;as an NMC model PC-5 proportional counter or'an ORT-S-1 gas

4. , y _ >

1 proportional < smear counter) for analysis. A cs 2 4 "

y 5

I ~#

,.y v

-*- 3  !

• y ~. - [I , s g: 8 . c. c x

N y, ' j 79-p .4:

'# . m ih }3 : - ... q

• a 7 h -

,.gc

, p y n- '- ~

. ..gbt

- sn g= -- J_7Q

~

• .~,_n_

, ,e

. ~ ...+w--. . --- a - -& - - - - ---- - ~ ~ * - ' * ,

All instrumentation used in surveying large and small area smears will be calibrated in accordance with written and approved technical pro-

, cedures. All smears that are part'of the final termination survey will be taken, tagged, identified, and analyzed in accordance with written

and approved technical procedures.

7.. . Section 4.7.3 states that an Eberline Model PRM-7_ may be used to measure

' intrinsic activity. Please state how you will correct your instrument read-out for energy dependence, since a PRM-7 incorporates a scintillation detector which is factory calibrated to 137-Cs.

RESPONSE:-

.e - .

The PRM-7 rea' dings will be supplemented by a GM survey meter and a' Reuter-Stokes RSS-lll pressurized ion chamber. The RSS-111 has a sufficiently uniform response over the entire gama energy range of interest to ensure.

that its exposure readings are independent of the gamma spectrum being-measured. 'As appropriate (i.e., when a significant' fraction of total

. exposure is due to photons whose energy-is much different from 662 key) the PRM-7 readings will be corrected for spectral effects by empirically developed correlations determined in one of two ways p

1) Making a paired observation with the RSS-lll.

2) Measuring the PRM-7 response in a gamma field of known strength and whose spectrum simulates the survey area. l

8. WilltheHhghResolutionGammaSpectroscopysystemaddressed_inSection 4.7.4 be used to identify radioactive nuclides found in swipes, core samples, etc. that may be taken during dismantling? If not, why not?

RESPONSE

The High Resolution bamma Spectroscopy system will be used to identify radioactive nuclides, primarily in core samples. If nuclide identity is desired for other samples or .for smears it will be so used.

8

9. Section 9.0 alludes to decontamination to components to meet criteria specified in a plan for transfer to another licensed facility. Describe the decontamination procedure, packaging and shipping to be used for equipment listed in section 6.3.1 to be transferred to DOE, or the equip-ment listed in Section 6.3.2 to be transferred to other licensed facilities.

To what levels of radiation will this equipment be decontaminated? What are the provisions of the other (receiving) licenses?

RESPONSE

Transfers of equipment from the LRC to the Department of Energy or to another licensee of the NRC will pe in compliance with the license of the receiving facility. Preparation, packaging, and tran,sportation of the equipment shall be performed in compliance with the Department of Transportation regulations or 10 CFR Part 71.

g g ~1

~

g 3 ',  : qg p

fa((wey* 7 m~ s m > .

-r ,

l lh[;[ p ~ b - M=W sr -

[Wk

^ '

Q~

4 . [ <

1' s

+, ,

- y "

wmL,'

'DN I<_ _

[~. . _ , g 3 s ([, ) 7 ,

i

\ g [ h ' i.."

% ,f p" a .h' =we ,,Jr . Q% * :o

~

x

- s 3

+.

4

. ,~

~

4 % --

g,- s

.4. w r g~ ,

3.e; ,

~.

x ipa W , , +_ > n 1 . .

1 . . , _

x e'

~w ,. , , a.; w c

y &,;6; - - Y ,

/

'a,

'; i >:

l E'i ? , #

a-., .. ~ *%y* ,

,, n r v ...i. . lY ,-

r ( , _ c \ * .. ., r < 'i

,/ ' v,110e ' lWhat release :11mitsvarecinferredlin'Sec$ ion 6.3.3LthatLmay'cause? 1_

~

~ f 4m" n afacility; equipment'to 'be disposed of:as; radioactive waste?DDescribeL * .

y y'_Jthe. measurement" procedures?torbeusedito-determine'when:theselimits -

M f,

'UK ') s Vareiexceededh ~ m k " . y,

' ~

<l V - M -

fay ' ,Q z(,^ ~

a

, J[ ' a by --

w '

u' h n

~ * '- "

~ RESPONSE: L .c '

, i -

> .. Sm.,. ~' .. .,  ; w

^ "

A'. iRadioactive.-' . waste; generated duringithe decomissioning program:shalli. >

s G

• a J ibe1 transferred to the -

Mm.- *- Q packaging, storage,L and: dis LRC's"miterialsilice'nse;Sl#1-778.

~posaliofathats - LPreparation, ,. waste y A' with the materialsilicense. ~ m i # -

,. s ,

+

w -

i lb;- l Describe Me:trainiN[ program for' tihef i ndiVidual's;involvedNn dismantle-i 2 M 'J ' menth including L trainingL ofi contractor = personnel .- ?The ' description ; ,f '

~

4. M ' ; - 1should ; include thelscope"of trainingiin decontamination and'other decom- n

missioningfactivities, health physics,Tand use and' maintenance of radi- .

~

!W"" ,

m j W

s -

iation surveillance)and monitoring ~equipmentb 1

J

?

a; ^. .

a RESPONSEL -

i <T

' mv '

Personnel , performing itasks ; pursuant tolthis :decomissioning fplan ishall? ,

~

.~ '

.s be ~under:the direction of the' Building: A' Decomissioning Foreman.1The; -

foreman holds aL11 cense as'a SenioriReactorL0perator for the CX-101 facility ' -

and theLis designated as'an' Authorized: User ofJ ' Material?(Authorized User). .

9 This -latter designation is' usednin'ou'r materials license to describe'a-

~

Llevellof training that permits: f individuals, iso de'signatedt tolhandleiradio- ,

z

-active materiali unsupervised :and stoL direct the._ handling of. radioactive '

ma'terial by; personnel .not so designated.

" ~

iCandidatesifc Cth'e Authorized User d'esignation must be nominate'd by-their- _ ,

y1 ~ section' manager. They must become familiar with:' . ,

a l ' '

A'.rHealth Physics Procedures _ _ _

~

, .e 8.~.The- Emergency Plan and Implementing Procedures; C.LThe applicable Area 0perating Procedures.-

,_A 4

& m D. The SNM transfer and accounting precedures.> _ -

+

3 Candidates must also < satisfactorily' complete one of the two training t

w programs described below:- .

1 Vs  :

= ~ , RADIATION SAFETY II:

iv?i

. ..'- N-LThis. program, presented as a series of lectures -and tests, is presented ito new' employees _'who~ will do a significant amount of work with radioactive n

= materials. The content of. the program is modified: periodically to reflect -

~

inew regulations,.etc. Thel effectiveness of the course is evaluated by F . 1 written examination and by observations made during the monthly health. ,

F W ' (physics audit. The general course content is:  ;

p ' "^-~ ' .

[; ;p ; .-

• f;.. s >

N. }c

'n ,

, gs -,, e f - ,

' ~

u ,-

d 4 -

g .yi d i a u .e c '

2

~

+ . l ' u  ;. - 2. ,-,J a - -, -- ++- -.l v ~ ,"- ~ ~+ c A+ Os m

q

;" yy?R .? 9 \

' %y , W? . ;& , , . y,, mf,

,  ?

Og

~g>~ -% "-QW ~

n:

• Qs, [^ f

'%g, .

' ,' K ><, ,

e*d 9hz +-+)J "3' ., s

.yLW. z: , , ?. -Ql- -

+

-n-V f ~~y w' >

, ~ , n, ~ -

8 s ,i' mlla s V ',

^ * ' r

-} s a *h lh

' ~ **

, 4' ' ~', * -

'Wh?

+

?"~ .

Q;:k 'i - ~ i<.m l.: g'^ \

• Or M 'y. _ ' ,^ "s + H :n. -

• ,~r 3;$ q:

~ r s.

'[- } _

?.. E' [g* f i f{ l y ,. '

fMNM < Y >

$ ^

, N~.

] ,

< , yj "[. ,

dM' , *

, , _ ,N M Q@.g(y w ~L

. , / Q> - w

> 0 '?  % Ni? x. ,

y~ f"'*

a , ;

W J ,.

F

%x . _ . .

fi.b ?R,adioactivity[ ' s - ,

$.U 7. _g -

kk e s, 1  : _,) '% * 'Y- _^ . ' - 4 , y J'y

/le' Types'ofhad'iation,i. ,, , ,

7 ?? g J s s: , .,+_

. + .

f[.W,

p. 2

. g 3 ~ 1 ,* ' ~~

' fesRadioactive(decay E f f ~, _ -

' ~

~

,t'@ ,

f c- . e?Radiationidose and{ dose; rates ( m - , ,_

s ,

.v -

gc &

1.n f . ~m 'teiProtection;factorsi '

m. ., ,. -- .

T

- .J,

^

le Radiatio'n# effects"on living^ systems 1 m -

g ^%

% 3l , ~ ~ h * "e' Radiationisickness; ' -

/

- + f "l - {e Effectslof; radiation, exposure lasiconidarsdtwishi

~

"A $" ' ^_'+' ' #

Lo pp , ,

other/ common" hazards 6 T -

f ;g-

+

7 -

,7.a. .., , ,,

- - ~ -

- e

'  : m  ; --.

=p.  : . ~

7 ,

3  ; s

. g~t 54 - _ . ,. ,.

22n . Health PhysicsLInstrumentsl: ^ ' ' '

< < _ m. # '

. - .. n. .

." ' ' ^a.

.,;Q a r

+~y[' _j) , _

[ c ); jj. , , ..  ?

, ;a  ;.jt, N ~ ~

$ elloriization" chamber 1 _

pg n-

y .

m*~w , , s

u.e,GM. counter 0 N - - m

• z

- H.

~

~v s

. ~ ~1  : e Alpha .. counter ~< s

.m, w%

m - -

'e-Air.-monitorst a- ,.

. ">7

• 2 c J ie"Crilticality;alarmisyst'em[

" '~

t

-Q~ m -

7 ' f e'. Emergency._ equipment 1  %.? '

vi '

~

o,

,+ ;

, e InstructionsLin: field.u'se~ofi. instruments-C-

~

J31 . Regulations! an'd zProceduresE <

. ,. _ 1 .

gun

" o cTitle' 10 : Code Tof Federa1 > Regulations ." '-o e e~ License requirements i "

~

i

_.7 V

. e Shipmentto_f radioactive ~ materials' ,

. . e Waste disposal , -

V

e Internal procedures

~ '

! RADIATION SAFETY II'I' - .

~

IThis-programLis presented t6 technical andi scientific' personne14whofare S c

howledgeable and experienced in work with radioactive' materials.~ 1The course content. consists _ primarily of.' Parts 2iand ,3 offProgramLII,'with -

- extension:of this material into more' advanced areas.,>The effedtiveness >

of_ this course:is evaluated during the monthly health; physics audit by; - *

,r observing workers:following proper procedures and safety ~ practices.

~ '

Personnel assigned to the.CX-10 decommissioning projectishall be desig-N nated as Authorized Users or perform their tasks under the supervision 3

1. : ' 'of an Authorized User.

m 412b ~

' Describe the:terminatiori radiation survey' plan to. demonstrate that the ifacility will meet the criteria for release for unrestricted use. The'__

~ description should include (a) proposed method ;for'assuringfthat sufficient ~

. l. . data andiall< pertinent-structures, systems and components are included T . ~

in.the: survey,-(b)s the type of radiation readings, land (c) the type,_

. .~

4 operating condition and calibration of instruments used.

> - '\.1 fg l }

e

( 1 9 4 Mf d m M , 4 + -

i gn s r-b - , . .y -

h2lg$

w.^  : - - ;p

? -

, ~.

i/ 3 :,  :

3[ ,

h T.

s 4 '"

= ^

ga uu y

.. > - . 1 -

y 4 g _b-k 4

- RESPONSE:. ' -

' ~ '

m . .Thknature of operatiionssat the CX-10[ facility was such'tha' tithe L

-likelihood?of' finding significant. contamination orcactivation is; t

, ~

-extremely low. The'CX-10: facility was licensed.to operate at a' low'~ . >

, maximum power (1kW) and was run' infrequently-(usually at; power levels

=

.below110 watts)( ,The fuel'(uranium and thorium) = was-in sealed' form, ,

gpossessed a low: specific. activity, and did not_ receive enough'ex'posure' ito' accumulate.a significant fission product-inventory.

~

Except for: a' few cases'involv'ing small amounts-of material,: all; radio-active' material was handled in solid (metallic) cr sealed form. More

over, except for Bay.2 and the CX-10 control-room,;all-indoor-areas

covered by this plan- that were ~formerly_ used to handle or store radio-

~

~

' active material have been . decontaminated and puti.to general. laboratory or office use.

The final-termination survey willitake 'the . form of a- stratified random.

sampling: program that takes 'into consideration'the likelihood: of finding-.

contamination-or activation in various areas throughout the . facility, and the typeof contamination _or radiation that may be._found; o

The survey. strata can be divided into 'twol categories,:. indoors .and out'd oors:

~

'These are. described below:

Indoors: ,

1. . Bay 2 and .CX-10 control room _ floors, including walls up to .2 meters above .the floors. "

Bay 2 floors" means all- horizontal walking surfaces (including the fuel storage ledge) remaining:

- after dismantlement.

~.

2 Horizontal walking surfaces'on the~ second floor of' Bldg. A, Phase 2 as defined in the Plan, excluding Bay 2 and the CX-10 control room. (Rooms B, C. D, E, F, G, H,. hallway.and stairs in Figure 3.1 of the Plan).

. 3. ' Horizontal walking surfaces on the first floor of Bldg. A, phase

~

2 as defined.in the Plan, excluding the Bay 2. basement, (Rooms I, J. X, L, M, N, 0,'P, and hallways..in Figure 3.2 of the Plan)'

4. Interior hot drainlines, including the Bay-2 sump.

5. Bay 2 ventilation ductwork -(interior surfaces).

6. Ventilation Lductwork (interior surfaces) in Bldg. A, Phase 2 as defined in the Plan, excluding ductwork in Bay 2.

7 =. Source storage tubes and through-wall instrument cable conduits.

~

r 4 g --

e- .g -w.-- -e- W m- e. q-

p.y ay myw -

,p p.

3 :;; y gue ja m g; p;.'-

.p g;y y.ygg 3 73 ,q +: . - , y ;

hl ~ , 4 , b '?

%,, { cf :Q ' '

Qm W w?;;'3nnw [ j % Y W 'F E' %w b /N t . . h ;g ,~ f '; w ^., Q ' [ jp;"

Nw * - ' I; 4 2p f C:

~ . ' ,.,a J W ' ? H, '

yg

,y Q_ -

^% r

, "3, =

< W;

=

, e <

. ~ - ~ x . , +n -

,s  :

MW! , ') ";& '

. > .l

• _

• ,M ll

f. ?

^

y_l . wk f' , :[ _, A ? ";

,* ?A

. $. ,,an ?f:

p h [ 7 # [ ~{

[0iitsideVStrata: 3

( ' , . f .l. f 7

f 8 r ,y.

_, j , l-,4*

-) l jfg

",M

. , . . . . , . . fS-i

~ , .. a ,.,,,i s -

? M6 m *E~

i1.1'Outsideisurfaceslof? Bldg.JAL. Phase"2 as definedlirf, the Pla'n O P Nj1  ;[(walls &Troof) 4 ',. ' ' ;l & ' 4 eg- ' ' y.d t A .g [ t , f 7 ,9 c

M;, ; V" ' / 71 .g_.  :" - 4 -

• C' />Z w- - .; .. ,

h '" ! %%; 40

. p j,q 4 i21 iSecuritMir' a;behirid e Bay l2 y . y /: tro >

-a. ,

m .

- m- ~

. . .. ~ w,. .

..% . , . . ~ .  :,.,x . , , , _m? e s

4

%4

.  ; 53',c;. Radioactive Liquid Waste Holding -Tank?(RLWHT)(including; , ,

" ' exterior ihot 'dra ins and i contiguou~s ! so.il .

4 4 0 ,

w' ' , J .

.; p, fi 1,. '; . .. ,. '

, .. , f 17, '

i' ,

Because:fofithe nature-of, operationslin;the'CX-100 ceilings, walls,'b'eams;y C~% * ' !andt iedges;are' generally!not:includedlinisurvey1 strata. . If, howevere l &af'* ,,

'N $ - -

J unexpected L contamination Lis sfound, the need to ;includelthese;iadd_i tiona a

' .J J i f. m is tra ta i n L the J termina tion Jsurvey~ wil l a be1 eval ua ted and li ncl uded di f .  % '

'e g ,Mi 9 i~ appropriate; ~

~'

i 64 ' #E

n. . ,

Ai>.

~

6 Leach Lindoor bdilding surI, f acel.s"tratum will be diddedlintdlunifordly{ , .J

(%

~~

Esized surveysblocks, Teach: block;being 1;to13 meters}on an? edge."Since.-

CE

~

Tall . readings 1are; expected to1be at'or near; background.sa;mi.nimum"off 30 :

t >

_0 survey? blocks will be'used .in .each stratum. Since.we do{ not plan toi . ,

, remove ; permanently L a ttached : equi pment D (such as l abora tory ( benches ) fin" ~

.2 ' areas;outside' of. Bay;2;and the CX-10 control room, .theJnumber of Esurvey M '

2 blocks'into which.the = stratum. 'is1 actually(divided 30), willibewill :be' sufficient to  ?

ensure thatt.theiminimum:

for survey. jlf covering;.(such as-paint or/ tile number of blocks = 5 or 9)i accessible hasjbeen!:a'ppliedj n. to

' ^ the surface of a former use area since~ ~ radioactive materialiwasthandled; ^

' ~ '

[' . there,ithe covering :in;at least'onef spot of that survey.-block willibel ~

g removed:so that a contamination survey can be made on the' originals surface.

g

, >The:resulting paint or tile debris will be, surveyed by gama spectroscopy.

. . . . , _ . y

, , The radiation 1 measurements taken in each survey. block ~offindoor, strata -

N ,

(1) throughf(3) are: >

u b - e Alpha' and beta' activity, dpm/100cm2, fixed and smearable.

E e Gamma and beta-gamma exposure. rate (uR/hr) within 'a few -

y ,m ~

centimeters and at 1 meter from the surface. This measurement F7 willfalso be. performed on the concrete wall nearest the core tank. '

ht '

The -instrumentation used will_ be that described in paragraphs _4.7.1 -

.through.4.7.4 of the Plan, and further detailed in the. responses?to L s jquestions5,3,and7above. 6 r .

Q ,"

'The interior ' hot drsins (indoor stratum 4) will be surveyed by pulling-

.or: pushing a smear through the-drainline and checking the smear for the presence:of ~ alpha and beta activity. This check will be made with instru--

mentationidescribed. in paragraphs 4.7.1 and 427.2'of the Plan, and further g$  ;  ; detail'ed in thel responses to questions 5 and 6- above. If no activity is g*

cr y ifound,Sthe: hot'drainline will be abandoned in place. If activity is found?

n ,i s 4 1 #

s x .

y r .

'g n T >  % ,,

r m flp 9 SYv . k, . r p < .,+- - ~

g _. i

' WYlg ,

! E' NW , ,.

an -

p,-

p s' " g lp gy , m 7

, - qy~

.g -q .

f gg , p yg.

, f*-

a' m ~,n, .-

, ,I.. -

y

• Ky ,

7, (\- , ( ,(

a lP; l'+ a. ,

~

_g ?)gj ,

?-

yi' g? y:+ .D,>

~

J Q1,, rQ'.-' ', - 2 m,q:&. ',_

~

~,

DS n

Js

n > % * %

g *

~ ~ , ~ ,H~

r , -

_- ? . , + 4- ; % e , _t =_,.,

- L -

J Q. +

y

'p e

,,,bc.-

,  ; j p-s s "r 5 4

+-

2 kh! -

Y 3 , of .

&j

[3LJ '" , i'

[_ff _Q . f7

• L ag; ' iD 9,

.f l m ,

>~f l , (( , [

or;measurementUcannot be,made (to establishiwhether contamination; "

_ [ g 5ll ;3 p .  ;

PW ,~

y ]y X1evels:are;below:those D 1will s bei removedi andlei ther specified Ldecontaminated by' Reg.iGu'idell.86L2or' disposed.offas' the'radio drainM line! c ,^ "

- - ~

Lactive waste'.?The: cavity;1 eft'by the drainline's'removaliwillsbe- ," .

$~ ~

~

s isurveyed(for alpha'and beta!cantamination (dpm/100cm2)1 fixed' and; f removabl e R and iforJ gamma ; and t beta-gamma Lradia tion .l evel s) (uR/hr) . ; o 1

, ;A ,

, The Einstrumentation. willibe ithe: same fas ithat descrihed inL paragraphsi ' J s nn' J 4;7.1;through.4.7.3coftthe Plancand further detai.lediin?theiresponses? c

'1 w ,m ~

< tor qu'estions>5,16,iand :7 above. f iIn the Maseiof fdrainlin'es removed- from - ~ -

Psoil ,;the: soil (will; beisamplediand : analyzed: byJgamma1 spectroscopy 1with .

m ithe1 instrumentation _ described in paragraph. :4.7.41ofjthe Plan. 1 P 4 s ,7 .

- -

• LBehiauseofdheinatu of Lop $ritions at i tk CM0ffaM11ty[no contam ~ . .

~ination;isjex'pectedito be: fou'nd!in(interior ductwork-(stratai5'and 6).

7' ' - . .

Neverthel ess p thej interiors surfacesi ofiventil ation' ductwork ' will < bei - -

lsmea red ffor al pha f andi beta l contamination. 1In' addition ,n.where' 'accessi c y g*

~

lbility permits,5andlsmearidata? indicates,7 direct' alpha (and: beta : surveys = , -

x . ,Jwill;be performed) 2The. points.7surve~yed;willibefthose<where contamination d' mightbeexpecteditoconcentrate,Hsuch'a_sla'ngles'orjbends.77Thefchoicelof; is~uchisurveyilocations twill'.bejguided ;by taking large' area. smears ofithe-fductwork. interior inianf attempt tot locateJany possi.b_lel hot. spots.o t c -

Portions ~ off th'e' ductworkithat show fno ;contaminatihn~ on allarge' area usmea_r;

~

- Jwillinotibe1 subjected tolaimorefdetailed'small-' area smear or. direct: survey. ,

fcampaign.:

The: entire insidE s~u'rface of straturm b(Bay 2 ductwork) willi beiwiped

'with one or more:large area smears"in?an'ef. fort tofdetect the'presense*, '

~

'of~ contamination. Because the -likelihood 'of. contamination in stratum J6;(ductwork outside Bay.2) is s'ousmall, cnlyLthe inside area practicably xa  : accessible'through existing duct 0;ienings will- be checked i

.for removeable Econtuinationn !More extensive surveys of less accessible' areas will'be d 6 considered;If unexpected contamination.is-found. - -

The survey instrum5ntation 'used will' he'that -described in paragraphs 4'.7.1

~

[

p and .4.7.2 of the' Plan, and further detailed n the responses f.o questions R 5 and 6 above.

~

&~ There are several large metal _ tubes in the Bay 2 walls 'used for storage f of radioactive sources and for instrumentation cable. conduit. These will be-surveyed by; pulling a' smear ~through the tube and checking'the smear

• b ;for?the presence;of-alpha and-beta 1 activity. This check will'be:made 6" with instrum_entation described in paragraphs 4.7.1 and:4.7.2 of the Plan,  :

14 .. 'and further detailed in' the responses to' questions 5 and 6 above.. If no-  !

E*4 . ; activity istfound,;these tubes will be abondoned in: place. If activity p

m lis found orl measurements cannot be made to establish. whether contamination C levels are below those1specified by Reg. Guide 1.86, the~ tube will be re- .

L ~ r ; moved Land either' decontaminated orf. disposed of a's radioactive waste.

,% g lb ).- y o- -

~

( l . ~~'~ > r 1

OA.w t *

,"~

. . '- p 9 l'

' ' ~

, y }y > .

~

. .,Il

? v'

~,N LL r u .- .w s. + - i . A ~, - - ,~c+ i-=== ~ - - - , ~ ~-"' "*~~- ~*~" ~~~* **

% <%gewn w w .7 + tz- 4 " - ' Me;a- eB " 7- Fc 7 lf hi ~

~

suf~n

@ M9 ;f 3 AW% %a mr mw@w Q

c ;J w'<N.y~

n-E a N. v y n

.?

- ~ ~ . .

' y-

, y 31

..-/

,o-

,~

v d

_. ~ w w -- W

^ % :b _^) $

9 n' 2 a g'1 f~

3 ,.,

a

• p C Jk "D *%.N...*' 5 .N_. \ ~ ; is !I a$[ynyg%:. gy.d* v[g , f( F 7 [ Qf+ .W, '%,# ;

x . 3 :[:q;[!0utdoorf g stratum,1?(rooftand! wall's up etoi3

@, __ . yn;x. , yw .y 3 9 m  ;; . '.2  ? . .,

a~"' -V .D s

W D. , "

t willibe f divided into Euniformly sized O surveys iblocks h eachili to43; metersi -

MTF ' 1 'J T * :on anledgeQ Surveys within eadh;blockiwill c6ns~ist:of measurements . -

g %'. . M

~

a

- falphaland' beta contaminationi(dpm/100cm2)',1 fixediand; removable 4 jIn ' ' - >~

y yadditio~nk measurements of[gamafexposure; rate 1(uR/hr)j will .be'madeFInstfu-0 i m#" x i Mmentationiwillibe that; described in. paragraphs 4.7!1,14.7.2,pa'nd =4.7.3E V

1. Tof. the Planiand:further/detailediin the:responsesito questions;5,96,LandP f( x

, 7 %g "

1/p] g " 071above6, ,

, p ,- {g ( 1 4s

, ^? ,

d ~

50Nddor3t$$m 2ksecurity: area {bEhind: Bad 2) wil'llbe'dividAd[intoc h MC a;. ~

(uniformly,sizedisurveytblocks jofflitbymetersion an;edgeN.Each blocki + -

gf

~

will!be2 surveyed foribeta-gammalandigammatexposuretrate (uR/hr)(at?ad N-; < ifew cmia'ndf atilimetesfrom the'soilssurface.-- :The instrumentation =usedt s

%$h ' s dwilllbelthat de' scribed in/ paragraph l4.7:3'ofqthe;plania'ndf furtherIdetailed ' ' g,

' ^

gE ,' J 41nithe.iresponse;to question;7 abovel JA minimum:of(5:soilisamplesiwillibe. ~

4s scollected for. gama~ spectrometricia'nalysisk iThe?instrumentationifoWthe:

' C' N soillanalysis ~ will ? be ithat- descri bed lin ; paragraph 44.7.41 of: the' P.l an.3 EThe t t ,

ji ; ~

myi, Lsoi14samplestwill be from theiS1 survey blocks having' the:highestigamma ' . .l

,e ? 1 3 exposure,ratepSamples willebe'taken fromLthe top f 0Jtoil5 cm ofesoil.s ~ c . .

,s W tMore than[5;samplestwilljbe taken;if warranted by the

gamma!surveyJresults. .

-e' .*

~ .. . ) ;O. L '

wa&: 0utdoor,; stratum 13/(RLWHT; exteriorihot' drain 1'ine9 and1 contiguous ~soi1)f

."  ?;will;be; surveyed as f6110ws:= W

~

m m-

..3 0 '

~

^ ., ~

WCorelsoil"samp1'siwill?be1taken e around the concrete tankland; th'e 1 1;

'm '

, 1 %j hot)drainline.. leading- to it; These:willebe analyzed by;gammai

• spectroscopy with? instrumentation-described in1 paragraph 4.7.4LofS

, t ~ sthe Plani ~These:results' will -belused to definenthe extent of any-pi

~

1. s' oil? contamination.

~ . , . . .

c d

=

.i

• ~e aThe inside surface of the~ exterior hot ' drain willube ' smeared Lin the

[Y '

same mannerJas the -interior drainlines. ~Ifi contaminationiis-found,:

the-hot drainline will be removed and eitheridecontaminated or' dis ' ' '

~+

h. posed of as' radioactive waste. ,

d u .. - . ..

b.

• e tIfathe hot drainLil removed, soil samples will be taken from1the-  ;

9'. excavation areas and -subjected to gamm' spectrometric analysis.

m

!M i

, ef . Sludge will be removed;from the RLWHT and analyzed by gamma spec -

x + trometry!u' sing the instrumentation described in paragraph 4.7'.4- "

.w_ , - w of the. Plan. ,

t

-~ 2 e < The~ interior surface ofithe RLWHT will- be surveyed for alpha andi E- _

abeta contamination :(dpm/100cm2), fixed and removable. In a'ddition, ,

g gamma. exposure rates (uR/hr) 'at 1 meter (or less) from the interior l surfaces wt.11:be' measured. The instrumentation for this survey will~

m. ,

b'e that described:in paragraphs 4.7.1 through 4.7;3 ofa the Plan,.

~ 7' . and furtheridetailed in:the responses. to questiohs 5, 6, and 7 aboven s 2 g; ,,

DIf thesetsurveys show that contamination and radiation levels are low' ~

%P ^

enough to meet the criteria for unrestricted use, the RLWHT will be -

abandoned:in place.z

- . m, O s y 1 ,

1 .,'?} , ,

C [.i.. 7 . *

, 1, ~, '

~

, b- *

(

. '. d:S ~~ &

TEQ JJ2 '. ..;; p;R

.M-~; [ $

_l.m - #U s ..'. . & _ _ C.R a. , J .J_. ..- L. .&.-. -

' - ~

.fj s T s

j h '

s _ _

m iThe_ entired' ismantling; effort, including the! termination'. survey, will

be p'erformed41n accordance.with an approved.QA Plan. 1The QA Plan will l prescribe.-requirements forl development of! applicable test, measurement,-

operating, and= calibration proceduresE 'The . termination ~ survey will be s

performed in-accordance with writtenjprocedures,as' required by the'QA-Plan. 4 .

~

All radiation. measurement l instruments willrbe calibrated with' radioactive

' ~

sources tra'ceable to NBS to ensure that instruments readings z(e.g.,: cpm)'

~

can be properly correlated With specified -limits -(eig', dpm/100cm2). These

. calibrations willfbe' performed 11n'accordance-with written and appro'ved-procedures.-

~ '

~

ESamples talien in theMeld;(so'il,'smbars, <etc.)Efor laboratory analysis

~

willThe collected,flabeled, and:preparedcin accordance with written andL

': . approved procedures to ensure:the dependability and! integrity of ~ the sub.-:

.. sequent analysis,'and' to ensure proper identificationiand documentation -

of: archived samples.

~

-Survey criterialtoibe appliedlare asl follows: : Reg? Guide'l' 86 'forcsurface contamination;: response to question 14 above for gamma radiation, levels;.

and paragraph 4.6.of the . Plan for? soil' contamination ~. The: instrumentation-

referred to in the

preceeding paragraphs. has sufficient. range, accuracy .

-and sensitivity to determine that=the facility _ complies with these' criteria.

^

13. : - Discuss. potential; accidents and consequesces that have been considered for z

the' dismantling operation. -

m

RESPONSE

The deccanissioning plan shalI become effective only after;all the fuel

. has been removed from the facility. Therefore, criticality safety-is not  :

an issue for' accider.t consideration. The cnly radioactive material that

. may be present in the facility at the time the deccmmissioning plan bedomes eff ective .is-sealed sources and low level contamination.

t'I

~

Sealed sources are smear checked each 6 months-to determine if they have

' developed leaks. hone of the sources in the facility have indicated leaks.

These. sources will be removed from the facility before. dismantlement begins

-and transfered to the-LRC's materials license for disposal;or storage.

These sources will -be placed in appropriate containers for the transfer c'

from the . facility ;The transfer will be directed by health physics personnel.-

The chances of an accident during container loading or source. transfer are Jvery remote and-because of the presence of trained and - knuwledgeable health physics- personnel,' the consequesces of an accident will! be small .

- Low levels of contamination that may be present in the facility will not present an accident potential because this contamination would have been present during the operational or fuel. shipment phases and the controls

- placed on personnel will remain ' essentially unchanged and the amount of

= surveys to. detect the contamination will, by the nature of the project be Lincreased.

q,- -

m q

g :g; '

, y .. -

3 ,

l L; ,

L y  % _

14. . Provide pre-decomniss'i$ning basbline radiation survey data and? soil contamination levels,- including identification?of. radionuclides.

4~ .

RESPONSE: 4 0

The nature of) opera.tions at the.CX-10 facility were[such that residual.

? contamination and activation'.istexpectedito-be extremely: low.-(However,_

_ .because:of the: enhanced: background in the: facility due to'the remaining'-

fuel and sourcesistored in the . facility, unambiguous radiation levels?

'near.equipmentTand structures-_in Bay 2 cannot be ?made at this ' time.

. Ambient radiation 11evels in Bay '2:are' typically 0.050 to 0.150mR/hr, s with readings up to a' few inR/hr adjacent.to the stored fuel and sources.

The fuel"and sources < willmbe _ removed prior- to thel beginning.of. dismantle =

. g ment, at which time a meaningful baseline survey canLbe. performed.

Ra'diation fields' outiside_' Bay 2 are' essentially at background! levels.

zThe~. extremely --low degree:of: fuel: activation (as evidencsd byLthe direct ~

radiation meas ~urementsLof the fuel pinsland by the infrequency of operation

- asidocumented in the facility logbooks): attests.to the, low neutron fluence to ? which ~ facil_ity components (mainly the. two. core' tanks, grid plates, =and

~

. base plate) were subjected.1Except for the 9-foot . diameter:by 9-foot high~

> ' coreitank, which is:made of carbon steel, all of the components were con--

'structed of aluminum. It is estimated that the carbon steel core' tank may contain altotallof.a 'few uCi's of Co-60 from component activation.

10ther gamma ~ emitting ' activities .(such as Fe-59) are too shortlived to have -

persisted at significant levels ~(the facility _ has not been operated for over a year).

~

'15. .NRC reviewers Lasked: for additional information regarding item No. '4 of Guidence and -Discussion of; Requirements for an applicaticn to Terminate a '

Non-power . Reactor Facility and -0perating license. That- item requests;infor-mation of_ an environmental nature that is in addition to that already sub-mitted'in the Decommissioning Plan. The questions and our responses are listed below in crder in which they appear in the guidance.

-1. The collective dose equivalent or workers for the entire dismantling and decommissioning-project.

RESPONSE

The collective dose equivalent for workers for the entire project will be < 1 person Rem.

2. - Exposure of the general public to radioactive effluents released during the proposed activities.

RESPONSE

Because most areas have already been decontaminated, and little or no residual radioactive material is expected to be found in Bay 2, LRC projects that no identifiable dose will result to the general public from effluents f1 o ,

./ L..

_~- ___ _

1 released during the proposed operation. Any effluents actually released m that contain radioactive substances are expected to have activity concen-

trations at or below the sensitivity of instrumentation used for effluent moni tori ng.

3. Anticipated exposure levels of the general public following license termination.

RESPONSE

I The calculated exposure of the general public before the decommissioning project is the same as the results after the project. That level is < 10

- person millirem for the population within a 10 mile radius.

o 2

=

R Y

b k

?

g g-g -

h t

f

.E s-J b

ls