ML20009G361

Annual Rept for Period Jul 1980 - June 1981.

ML20009G361
Person / Time
Site:	University of California - Irvine
Issue date:	07/29/1981
From:	Geoffrey Miller CALIFORNIA, UNIV. OF, IRVINE, CA
To:
Shared Package
ML20009G359	List: ML20009G361
References
NUDOCS 8108040174
Download: ML20009G361 (12)

Text

. _ _ _ _ _ _ _ _. _ . . _ . _ . _ _ _ . _ . _ _ . . . . _ _ ___.. ___ __

' ' 80d ,

92COOOGOM30GvuGN

.624018 #4TOF080Y8 l

J C 5 i t.JGe ng JC3oUEM Jeilip 3 D JC

/4

• s uoT a tioTJ;oad s /.2;IT ocJ ct;;

Jo JL*9 ;JEd (:2 T M GOUUpdooOE, in iOJedCJd I i

92E-CS O C';ocC 9LL-E :csucoll ^4 TIT 0ed Lt:6L 'OE c unt co 036 L ';tt XIDT l

.'o T J e d JCJ GJcdc

j Tencuy E OJ.D 'J3 'd YEIFJ, 3 f:I A% I

• D

• n 8 e

- 9

C'! AP fik 1 OPGl.TIJ"3 0,;aration of this facility is in support of the Department of Ca e.ai s t r y ac o ;r am in r esearen and eauc ation in the use and aoplicatian of r adioca a:rlic al t ecnniquas a nd radioisotope utilization in chelical studies.

daactor utilization, apart fr o n oper ator tr ain in t; and maintenance, is taas e n t ir e ly for saaple irradiation. Samples c or:e fr o.1 liversa orl;1as r elate d ta forensic science, fossil fuels, Teoch e::i s tr y , art and I

arenacio;y st; dies, oneAical syntnasis, industrial quality control, enz/ae studies, :,r ace cleaie nt po llu tion ,e tc .

1 Ina reactar was also utilized in class occk by un jer ;r aduates l a ar a in;; tracer and activation analysis tecnniques u sin ; Taall

> quantities of snart-lived activated materials.

13 graauate students and 7 co st-doctor al associates h ave used tne

+

facility under t .12 .;u id an c e of three faculty in Ch e nistr y . These incluae visitars f r c:a Israel, Norway, Mizerlu, Thailand, P2 coles

, napsulic of China a: d I r elan:1.

earrently tne facility has 4 licensed sentar operators aaJ 1

, licensed aparator ( includin ; the reactor suaa visor).

..o aajor chan;es have been ::t a d e in this ocriod. The annual insgs: Lion of core coaconents indicated that all core ite.ms are in 2001 canaitlan.

l a laintenance oraalra was f ailure of a ballraca in tha drive syste, far e, ne " at u ti n .; s p e c i..a e n r a c '< . A #cpair has not ye 5een accomolished and rotation is acu limited to laadin; and unloadin" so as not to creata

! unaue .ie a r on tae enain drive.

l Jaarations this ye ar have been maintained at about the level of last year. A list of r ecent oublications is tiven in Accendix I.

l

\

Cli AP T ER 2 L A'f A TASULATIO!!S Foti TliE PERIOD (JU' Y 1,19 30 -J 3i!E 30,19ill ) .

TA3LE I.

7 Experiment approvals on file Experinents performed ( includia;; r epe ats) 302 3 a... pl e s i r r r d i a t e 1 4439 Sner;;y gener ated , :1u hour s 56.8 iotal, 69 elaaent core: 127.0

> '/ 4 ele:nent c or e: 6fd.3 Total since initial criticality: 825 3 Mwh Pulse operation (this period) 13 of whien greater t,han $2.00 in s er t ion : 8 Total pulses to 6-30-31 649 uoura critical (tuis 'pur iod) 331 j

Total to 6-30-3'1 42S4 hours 1C hours Operator training and r equal'i fi.c ation , t nis per iod 26 inudvertent scrams . ,

1 Visitors to r eactor (admitted) 690 l

Max dose r ecor led (all witnin instrument errors) 1 mr l

V i s i t in g r ese ar c her s( d os i:'ic ter issues) 79 Max i:aua d ose r ecor ded 4 mr Visitin;; r esear ch ar s ( bad ged) 6 l

l i

T ASULA~IIOi!S FOR T.lE l'SitIOD (JULY 1,19 30 -J 'J:lE 30,19 91 ) . Pa:te 2-2 ,

D.A r:1 Table II.

Reactor Status 6-30-31 Fual elements in core (incl 2 fuel followers): 79 fuel.cle1ents in storage (reactor tank) - used 23 1

Fuel elenants unused ( in s t r uin e n t ed )

Gr apait.e r eflector ele:::e n ts in core 29 Eipebniental f acilities in . fuel ele:1cnt positions ,

"4 Jaber filled positions 13 Coca excess (cold, n'a Xenon)

~

22.93 Contrul Had worths ( 6-8-51 )

REG G 3'. $ 0 i

Silici f.4.00 ATR $1.99 FTn $0.72 TOTAL $10.31 Maxinu.1 possiole pulse insertion (ATR + FTR) 32.71 ita x i:c un peak power attained (6-23-81) 900 :4u U

riax inu:a peak temperature coserved ( S-r i n ?,) 328 C 1

1 9

,. .- , , _m- ,- --

- - . CilAPTTR 3 IllADVddTE:!T CCH A:1S AUD U:!PLA!i'iED S!!UTDOWil5 I

l TAJLE III~

DATE T DIE P0iER _T.Y P E _A u _i CAUS E 1)JJ 7/9 10:12 250kw Linez:r nower seram on suitchina, to auto mode.

7/16 10: 42 <10a Per iod se r a a .0;)ce ator crror during criticality approach. I 7/13 13: 49 <3w Period seran. operator error during  :

criticality appecach. I U/30 14: 27 <1.5w Period ser a:n.oper ator error dur in; l criticality aaprcach. l 9/2 15: 20 2 50:< w i, Power sc r am .Op er a tor er or on :lamna build-up fr om samples.

9/6 14: 00 250kw 9 Power sc r am.Same a s 9 /2.

10/24 15:5d 2 50:< w Seismic scram. !!o scis nic activity.

10/29 11: 30 <3w Linear oower heran operator ran<1e switch er r or on .i ner easi ng, pouer .

10/31 06:25 <1u Period scram. Operator error durin; criticalitf approach.

11/6 03: 07 100a Period s c r' aq . Operator error durin, criticality approach.

11/15 14: 05 <3w Period scram. Tr ainee operator error dur ing criticality approach.

11/20 14:29 ~300w Period scram. Sur ',e in LOG circuit caused by c orynect or at r'c ac to r brid;e becouing, immersed in pool water.

11/21 01: 35 250ku Period scrca. Connector still not dry enough after s'rvice! e 01:43,01:45 Same as above!

12/11 10:20 <1u ' Period seram. Trainee operator error dur in;; cr i c icality a;)pr oach.

1931 1/6 10:26 2 50k w 1 Power scram. Sa:ne error as 3/3/30 2/17 17: 03 250ku Period scr am on suitchin", to auto Mo':e.

3/12 14: 37 253:u Scismic scram. No seismic activity 4/24 14:18 10Xw Linear scram on suitch to auta mone.

$/12 1 :i: 52 250ku Linear scram on switch to auto mode.

o/3 00:14 250kw Linear scram on suitch to auto mode.

6/3 00:19 250%u Linear seran on suitch to auto mode.

6/4 11:44 10kw Linear scran on switch to auto oodt .

6/19 06:15 10Rw Linear scram on switch to auto mode.

6/19 10:10 1ku Linear sc r a:n on switch to aut.> mode.

l C!! APT 2 R 4 M AINTEl:A :CE OPIR ATIO:lS

.All major i te:n s (fuel elements, control r ods , c onsolo systens) continua no be found in good condition dur in3 routine mainter.ance inspecticos. There arc a few recurring and new items t;iven s pec i al attention this ye ar .

(a) Continuous Air Monitor (CAM) and Area Blonitor (RA".). Both units experienced low DC volta;c supply f ailure this period owing to r es!stor and capacitor failure.

(b) LOG and PERIOD channel circuit. Pr oblems were encoun tered when the signal lead from ths compensated ion chamber feedinq these chcnnels o c c a::ic socaer3ed in the pool uator at a connection point by the r eactor briu ;e . Eventually both connection ends had to be taken apart a n .1 the cable ends trimand, before the problea of sudden ' signal su a,es uss completely elimincred. Each major sur ge caused a period scra1.

(c )Ph ys ic al Sa csur ity Sc usar Sy ste.n . 'dith changes and auTmentation

, of the pnysical secur ity sensor systen, quite a number of falso alar.;s

~

.dc r e tur n ed in in tais period. Sone units werc adjuste.1 or relocated to c ir cu:.; v e n t these diffici21 ties.

( d ) R ad iolo;;ic al safety staf f personnel flave been appointed to work at the f acility aproximately 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> per week, starting in March, 1931.

i,fter an initial familiarization period, a complete revicu of the r ad io lo c,i c al safety pr o ;r a:a is being conducted anj t t.e St an.l ar d u p,:r a t i n ; Pr oc edur es ar e beinr, r ewr i t t,e n , section by section, t. s a result.

( e):10DE swi tch. Several unexpected reactor scr a:ns have occur r ed in recent :no n t h s , apparently caused by poor switching contacts in the MODE switch when switched fr o:a M A!!U AL to /,U T O mode. Elecranics personnel

, have not yet ocen available to attend to this problem by cleanin ; or r eplacin;; the swi tch.

( f) The pneumatic transfer capsules (rabbits) continue to fr ac tur e acre free ;ently and easily than expected. *iethodc htvc been developed l for casj sample retrieval when this occur s and no special oroble as have resulted.

l f

~

1AlnTc

!A:!CL OFF.R ATIO::3 P a r, e 4-?

( t;) Fotating Speciten Hack. On 8/20/31 an cuerator saw that the Y o t a t i n.; s peci:aen r ek wa s r o ta tin;; in a very jerky :nanner . P.ather than cantinue *:i t h the reactor run, he unloaded the S r. pl e s ani sau four s.a a i l ball b ear i n.;s in the top cap of one of the sa1ple holders. Tne uear inr,s acr e :aild ly r adioac tive ( Co-6 0, Cc-51 etc). Using a :na s, n e t on a s t r i n:; , a further tnree Bulls and a strip of crumplel r etainer metal uare r ecovered fr oa1 the rack, i.x a:ai nat ion o f tac d r awi n~,s av a il able and consultatian with tha reactor .na nu f ac tur ce led to the conclusion bein'; made that the hearin; s u p po r t i n;; the nain drive shaft within the rack assembly had collanaed.

Tais pernits some l atc r al movemen t. ( t h ou:th not .n uc h vertical) of the gear drivin ; the drive chain for the r ack . Since the rack in a permanently uelded structu e, wi th a hie,h r ad iation level, r e pl ac e.n e n t of the bearin; is not feasible. Consid er a tion is 'bein; given to f abrica tin ; a graphite sleeve, which could be slid down the louer section of the dri '

snaft into the rack assembly to provide lateral stacilization for the drive gear. This manipulation should he able to be done with the rack still'under sono shielJini, water.

Meanuhile, rotation of tae rack is being rys t r i c t e'l to unload in ;

and l oad in;; operations, or very occasional 9'i de;;rce r otation dur in.;

lan3 runs, so as to : m e. the possibility of dannge to the drive chain.

This pr o o l e.a is not con idered to c6nstitute any forn c'f sa fety r elate i pr o ol e:1, except for radiolozical concerns dur ing any attenpted r epair operatlan.

• S a,- -

l

- e t

'I

~~

Cll A PT t'It 5 FACILITY Cl!A!!3E.J A:!D SPECI AL EXPE!il'iE::TS APPnoVED Cit anr,0s to the physical secur ity s yste:n wer e :aade dur in?, this year to- i.c pr e v e tile ability to detect unauthorized i ntrusion or activities Within the facility. Iti all cases, i~tpr ov e ne nt of secur ity was attainea. Coalplete details of the new syste:a have been subsitted t o . ii C in tire for:n of a revised Security Plan. Final appr oval has not yet been diven.

l10 other signific ant chan?,cs were raade dua ina, this period and no Special exper i:nents we re approved.

e e 4 e

e 4

5 6 9

4 S

l l

l r

o

~

9---,...--,v..-,y.w.--, , , . , , , , - .--.--.-y.-,w.--,,-.y.-, v..- . ,-ew.~,, ,,-#w -

- . - . . ~ - - - - - -

C:l A PTE R 6 R ADIC ACT I'!E EFFLUF.'!T R ELE ASi:S (a)J ses. Tne major direct release to tne environs is Argon 41 proouced 3IIr i n e, norma) o;)er a t i o n s . Very small amounts of other unse L-liv e J r,ases ut a y be rcleased f r o.a irradiated materials in e .( p e r 1::i e n t s .

deleases are estimated based on cris,inal e st i:n a t e s at point of a r.1 ;i: witnin *he facility and taki;r; only dilution into account. An integrated Jose estinate is pr ovid ed by an environmental d o s ' "t e t e r

( c a l c i a.:t sulfata-cyaprosiua) h a n ;;i n ', directly in the exhaust at the point of stack d i sc h ar s,e . This is c ha n:;ed quarterly. The r esul t s substantiate the vojection that the submersion dose to an i n d iv i:!u a l stanJinj in taa s t a c',: dischar',e continuously would he less than the reliscility li.1i t o f t he d osime ter, e st i:aa ted at about 20 ..:r ca per year. ,

Tae exact quarterly dose r e ad i n t,s obtained are P,i v e n belaa at Location 5 in S2ction 7.

(1) Operation af tne p n e um a t'i c tr an s f dr s y s t e:' (7/1/30-5/30/31):

Total (250 %a assunedP 4,170 minutes helease ate 6x 10,( - 3 ) mi crocur ies/ al F l a ',, eate 2x 10(5) ml/aec Total r elease 3.0 x 10 ( n. ) nicrocuries (2)R21easa froa pool surface:

To;al operation (:Nn x 4) 227 nou-s helease r ate (assumed) <1 x 10 ( -- 3 ) mi cr acur ies/ml Flow rate (exhaust) 2 x ,10 ( + 6 ) Lil/ se c Total release <2 x 10(a ) nicrocuries rotal of (1) and (2) <5 x 10(+4) microcuries Coacentralian avera;cd over 12 months = <3 x 10(-10) mi c r oc ur ie s /.11 Tais is almost the sa*.e as the level reparted last 'y e a r .

( b.) L i ::u id s and Solids.Liouid and solid uastes fr om utilication af oy-or oduc t aEerlais are dicoosed tnrough a 'Un iversity contr ac t. la .t e is transferred to custody of E,H and S for final p a ck a ;;i n ', and s h i;ra e i t .

30 uastes have been c,ener a t ed this year otner than irrsiieted sa" ole

-aa t e r i a l s .

Sane of the ma ter ials gener ated are t r an s f er r e.1 to other usars operative unacr Scate of California license and tr an s fer r ed by t10se users beyand control of the reactor facility.

Disposals by tne facility were as follous: (activities are deteroined as af time of transfer to fiad i ati an Safety Office control).

Dry wastes: 6 cubic feet - 7 microcuries (mixed activation products)

Liquid wastes: 2 cubic feet -37 microcuries (irradiation vials with liquid mixed activation products )

2 gallons - 5 ni.crocuries (mixed activation products)

. C:! A P ii'i /

E::V I m.," ' E .T AL SL" VM T L', A ':C E Cale tu :-sulpnate:Dv ;n osin a ther toluminencent dosi etern in p W:s 4 o ,2 p 1 i e i ny !'ad i at ion Je teu tion Com a.i t v , 'so n n y v a l e , California are al ee e.!

. t. n in e 1acations a oun1 Campus. 01e ;)a c k is w at of f-c nrus in a- uaod a ic n ,.) u s 2 (second stary) as a conteal. Tne av er aqe o f tne r c..:otal y 2 xa te j uaaxs on ecmnus is in fact used as a " concrete environment" b ac a .;r ou n l fo r comparison pur po se s for evaluation of packs olaced closer t ,s L.te facility.

Loestionu:

1. ..'i n d o u of cactor rooq (inside f acility) .

2. de twe en r eac tor laboratories and r adioche nical lab,in hall.

3. Lo ad in-; d ock , adjacent to west wall of r eactor facility.

4 Classr oo t 152, over reactor facility.

S. In rocf exnaust air flou from rcactor rcom.

6. Scainhaus Hall (Dio. Sci) building: lit h floor.

7. Library buildin;, 5th floor.

6. Co:n put er Sc ien ec fu ildi.n s , 4t h fl oor .

9. Fame Hood Exhaust, Roof Level, fr o.a r eac tor 16b.

IJ. 17941 3piceucod V.'a y , Ir v ine (control'.

fable IV shous tha data as received from RDC r epor ts for the period. All levels are as expected. Those above background reflect the neuscon .;ener ator oper ating schedule (nitro.;en-16 in the cooling uater) and are essentially similar .to those r eported in orior year s. As noted be fo r e , areas 1 and 2 are partly. controlled so that the maximum possible

, annual dosa to a true " o f f- s i t e" individual would be estimated at less thar 4 3 ur ea from tais data (above background).

The uain and fu'ne hood exhaust ducts continue to shou no dose above oacqraund within error limits d elivered to continuous occupancy of the

! exit stack locations.

TABLE IV 1

l E NVIRutD1EUT AL DUSDIEUY REPORT D AT A l T4/9-u Av er age E.x po sur es in nr

~ ~ ~ ~

Location Quarter Total To t a l .l e_s__s_

2 3 4 1 BACKGROUND (127+ 14) 80 30 83 81 --

1 39 40 43 51 178 51 2 53 107 65 48 273 146 3 3d 34 43 34 154 27 4 23 22 32 27 104 0 i a 24 13 36 27 105 0 o 30 29 li l 33 133 (0)

/ 29 28 t6 34 137 (0) 3 20 21 31 3M . 111 (0) l 9 25 24 36 28 113 0 l 10 21 ia 3n 28 103 o Average of locations 6,7,P used for P. AC KGli OU M D .

Ci! APTER 8 R ADI A TIO!! r.X PO SU:< E T O F E R F.3:! iEL T.l e annual e x po s ur es recorded are pr esented in Table V.

Ess~entially all of these exposures are acquired in the cour se of isotopo lia n d li n ; experiuents and in s w.e instances will have been r eceived in 5 tate licensed areas. '40st personnel working within tuo facility also carried neuteon f i l .a .  !:0 non-zero exposures have cver bcen r epor te i for tuese fil as . .

29 c f the ;>er sonnel r epor ted ue r e under.7,r aduate stu.i en ts in a class in Rauloisotope Techniques :nectin'; for one academic quarter (9 weeks of la'aoratory work) only, i!o non-zero readinzst were r epor ted for tais group.

Coats:li n a tion s ur v'eys con sistina, of uipe tests and C:1 sur veys hav e snaun si,;nificant, r emo v a b l e s hor t-liv e.d conta.instion in intope -

handling areas.  ::o o ther cohtaaination areas trave been foun d .

TABLT V.

Personnel Expasu 3 Su:1:acF7 - 17T/30 - 12/31'/93 (in at ri) t i n t e r"H t o ",

Individuals Pen --shole LadyRon-Pen 1 -

6; o 670 1 15 . 0 360 1 0 120 15?O 1 0 50 .70 1 0 .0 . 550 1 0 0 150 t

1 0 0 140 i 1 0 0 90

! 0 1 0 40 1 0 0 30 55+ 0 0 *

• : lot monitored in all cases I + includes 29 students aonitored for only 9 weeks.

l 4

l L

APPENDIX I Publications - (July 1,1980 - June 30, 1931 )

T. Isak-Biran', V. P. Guinn, and M. A. Purcell, " Detailed S,tudy of the Removal of ' Copper Jackets frcm Jacket Bullets",

J. Forensic Sciences, 2_5_ 5 (1980) 374'-379.

V. P. Guinn, " Cyclic Nuclear Activation Analysis", Radio-chem:. cal 'and Radionnalytical Letters , M 41930) 133-138 V.

Geor P. Guinn, "Nuc car Activation Analysis 45 Years after

. Chem:ge .ctry,Hevesy's Discovery",

50 (1980) 309-314 Journal of Radioanalytical

. Th e rmal Cl Reactions wi.th Propyne Journal o f Physical Chemistry, Sj, 1876-1881 (1980) i F.S.C. Lee and F.S. Ro wl and The Abstraction Reactions of Methylene with Deuterated Me thyl

llal ides .

Jo urnal o f Physical Chem is try,. 35,136(1981). .

Peter S.-T. Lee and F.S. Ro wl a nd .

Direct Fo rmation o f RCl from the Ga's Phase Reaction of Thermal

! Atomic Chlorine with 'PbR. (R = CH C ., H d Journal of Physical Chealstry, 8_5,3,M (1931)

Ma ko to Ki kuchi ,. F. S. C. Lee, and F.S. Rawland Gas Phase Reactions of Thermal.

O F with Pr'o~pyne and 3,3,3-

! Tr i fl uo ro proovne 1

i Jo urnal of PEysical Chemistry 8_5,89(19RI)

Colman Concannon and F.S. Ro wland i

l A Microprocessor Based :tonitoring System for a Er.:cil Nuclear , React:r Facility l G.E. Miller and C.F.DeXeyser 1

Proceedings of TRIGA Owners' Conference '/II -

San Diego, California, March 1980 -

Assessments of Accuracy and Precisicn of Multi-Elteent Determinations in Whole Coal by non-destructive Neutron Activation Analysis.

George E. Miller, Don R. Burtner, and Paul A. Jerabek Proceedings of 3rd annual Conference en Nuclear Methods in Environmental and Energy Research Columbia, Missouri, April 1980 l

. ..