4 0 flONAL FOaM N~O. 10

UNITED STATES GOVERNMENT

Iem o randumTO : Y. M. Mann, Assistant Director - CoMDI.DATE: May 6, 1960

Division of Inspection - 1q.

FROM Robert W. Kirkman, Director Insnection Division - NYOO

SUBJECT: REPORT OF RADIATTON INCIDENT AT TFE WESTINGO-OUSE

TESTING REACTOR AT WALTZ MILL; PENNSYLVANI. ON APRIL 3, 1960

Transmitted herewith is the subject investigation

re-nort of a Tyne "A" .11 idento It is to be noted

th-.t !ok of time has nermitted the inclusion of on1v one cony of the exhibits.

4 c. ] o l

Information in this record was deleted in accordance with the Freedom of Information Act, exemptions , , FOFA-

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1 I

xkV'ST~rQA'?ION OF kbATiON O 41',"Ck

TNTROD1CTION

The incident at the Westinghouse Testing Reactor, which occurred. on April 3, 196O, was initially reported to the New York Operations Office Inspection Division by Westinghouse on April 4, 1960, by telephone and by a teletype. A written report of the incident was transmitted by Westinghouse to the Director, Division of Licensing and Regulation, on April 4, 1960. On April

13 and 14, Jack R. Roeder and John R. Sears of the NYOO Inspection Division, conducted R preliminary investigation of the incident. On the basis of this preliminary investigation, the incident was classified as a Class "A" incident, because of the estimated reactor down time, and the estimated cost of cleanup operations.

,-An investirating committee was then established, consisting of the following:

Dr. MN•vin M. MNnn, Assistant Director for Compliance Division of Inspection, Hq. Chairm=n

John 2. Sers, Cf00 Inspection Division "Mersbn Booth, Division of Lice.sing & Regulztion, Sq. tTincont A. ?.l'j•er, Tiv'sann of In-rectinn, qj.

Scnnmitteýo ret Pt 1-ho r-rcctor site ?t 14lt7, Mill, Pnennsylvas'us

6n A""ril 2", 1060•, Mr. omr A funn41 A, th" Division of T4,-or -r- 1-ml)tinn, >q•--o.n•.o• n+ to'in" the committoe'S

r tM4)n'., 'Thoý Qi 71trt7oI CP

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the- nearest ste boundary. The ptV opulation 4t 4tu " ý6fore msile fromt e st~e I± 'S 'htea to e Po

The core structure of the reactor consists of two 6-inch

thick aluminum tube sheets between which are welded closely

spaced aluminum shroud tubes. These tubes hold fuel elements

and direct the coolant water through the elements.

Each fuel element consists of three concentric aluminum clad

cylinders held together at each end by locking pins and a spider-shaped aluminum fitting. Each cylinder is made of an

MTR-type plate. The cylinder consists of 13 weight percent

hibhlv enriched uranium-aluminum alloy meat section, which

is 0.052" thick. The claddinp is aluminum, 0.O365" thick. There is space inside the innermost cylinder for installation

of a central aluminum-hollow mandrel in which small canned -specimens may be irradieted. A diagram of the core is included 'as Exhibit Do

Reactor coolant water nasses down through the core, reverses in flow direction, and passes un through annular snaces between the thermal shield. It is then nired outside the containment she.l to P seal rund surge tank, numn, heat exchanger, a head tank located 250' obove grade, and finally back to the reactor. The ýihirsr tank vents to the hend tank which in turn vents to atnos'htro.

Thp rije eOn' no1 , rod cnonni-t of aluminum clq.d on.dmium cy4

inMerS conneCt,, to the drive q-haft byr underwater namotSo. 9cram - ao cnn'onl ished by -rfvlt.- di'n unon d•-enn"'i"in' th'

-recet-. * od drivec a-re of rack and Dini on t-re, two-nlbs.o

rotor ritr-, to- -ninte(i. 'The tIInte center rodc a.rc P nfeti"s.

Theb no the Fi outer rodý cnn be nult or cutomatJ.c control.

robs reactor i. ePuinne, wi..> -onrvectio-r j.1 q+.it u meYtctinr

"o~tctc -F 'r o5-Tan n'rae' qter of 7 neuitron des

tector which 'ontrol o cutbeok ar or ar-, anT)-onriato nrocens

i.nqtrunectct4ion, a rprliction -ofli+ori,ý s~ystem, an( a 'n "m-nr

ci -tor.

She renerqtjatre cefficin+ of the clean reactor Pt 90 merr

watts in 5 5 A "o p -. PxlO- /,/r/'. -he vonIi nopff'iiet oV<i- A a cr1- "cio n-nri'et ''a" -¾.Z6x10-6 nV/•'/nc'

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........... eteh'eat- thes.ý &srescribed,,' 'Aand that the reactor power le~vel should be d6oersWpM by WO1,W.

However, the investigating committee determined that these re, .

strictions spelled out in test specification Yo. 5-1( were g never translated into operating procedures for the reactor

operator at the console. uring tho in-idc-nt, ;.uuudlns to "

4. For the nq:rticular experiment being performed on the evening

of the incident, test specification No. 5-2 had been prepared. Cbig - ~ d u ..... il o ... ..... t hid ,, a oul •r - . A co py

is included as-Exhibit C. Since in this experiment the flow

was to be cut back to 5000 gpm, Wýat~t ejZte ýM"to

44 megawatts, the scram and cutback settings bad to be re

. adjusted. This specification did not snell out any anticipated

--abnormal conditions which mioht prevail in the reactor as a

result of the ex ýri e t A 'i J -45

.445 -.-, ation of WFestinrhoiise 5s l.op book indicat•d that there

had. been t b- fif'ilty in nrocurini acceptable fuel

c I inflnts. A !'in.re narernooarn o-P element! had boon re-jcted o" -nrno i7-nerftia. '. 0Chultz anid that the

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went off, and BDianchi was ihstruot'ed by Poltono to cut back' manually at about 8:4O p.m. The indicated reactor power was

then approximately 38 megawatts. The reactor power was cut

back to about 15 megawatts, and then as still more radiation

monitors alarmed, Pollono instructed Bianchi to scram the

reactor at 8:44 p.m.

HE ALTH PHYSICS

Mr. Donald Willhoit was the Health Physicist on duty on the

night of the incident. Fe seaid that cnnroximately 12 neonle

were working in the WTR facility. Willhoit was in the health

"nhysirs office at bhut 8:36 p.m. when he heard the first '*'' 'oarzr,,whi.ch subsenun.1tly turned out to be (tann on the

reactor too. He vnrv soon _fter heorA another qhlarm -o off 7

San,' immediately c.iled tf e control room to

determinn what bed hannenodo &t this noint,, ell of the

alarms sounded rrn+ioelThlly simultranouohy. Willhoit then

tool- P Oi.ti n Pie ojr'pýerr rýrtory -a. -ro-nedpA to the control

o ..... r.ront reedins wcr obtoinnA from

Y!-. Onorrr Oni i pter* 'Tp nnj the t thpl- ijoodi-n-s had 1)e0n , _ '___•_... .. __.. ___- ___- ___-_-_- _ nt''.• ".u.• •z4 "4 - t•4W .,t'.c-,• -.....

or ~ ~ ~ ~ ~ ~ ~ -t¾ -g-tto4~f~~Ir~

Ohenne_ MTn 0 orirtion Deedi-or J~ 7 e

1 fliZ l Tpt

qt,"t on Inc00

2 OW'O ? QR-iet'o" St-0 ,tton :.0 Onro• 0 n.nr '.r'- 100

"W!qt'! Th'snosol Vpal4it5r 700 P Prto Pn�, 1000

10) Pobbi.t l,•c4 iti" 5"

!.1 "'.o7 . '5 - r't• h too 1 )4,p7 T1'l n~ I n - rooh'

lit Tho nrnlrnA •T 0 70n

17 qton DPrtio-I'lolte 1000

"Tn•, an- iot+ l ofo -q ! -'"o n'O-0 rIllr•!• nit-1 0" ;'• h-" onntrs' ro e '",

sneor It t-• "roners -" 1 r, nn] rr o r'ot >nr tn•n rs,

or-os~nnl '4 ' 'rr r-pnV -'V.--to ,Ab

18 2

n1 -- T n i " " ' - r o ri - - no ' " 4 1 *s T .

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II,

c4tO

. . -• . .,

the south door of the reactor building to t.le tr.ocees -nnLaing. 'He recalled thlat he obtained a reading of about 80 mr/hr .b

this area which he erroneously believed was due to Argon

coming from the head tank. In the process building, he found three men working (two in the machine shop, one in the boiler

room), who had not heard the Pemco alarm Aue to the noise of

the machines in the bnilding. He directed them to evacuate

to the control room. Immediately thereafter, the general

evacuation alarm was sounaedi in all of the buildinrs. Willhoit

stated that this could be clearly heard over the no.se of the

machinerly in the Process Building. 7e then proceeded to the

head tank monitor and at two meters away, obtsined a rending

of 5 r/hr. He wert to the -oin oate pt about 9:00 n.m., where

the readinp was about 200 mr/hbr. ie next went back to the

control room wbere -I! nercore! hnd & '1sse'bld urior to 3 erin'

<thoe sitep All nersnrs, with the excentinn nf Wilhboit _.n4 the

Panctn" snperlrisors, evacuated the rite, and e-senhied a.t the

main c:nto, willhoit toolr .7ome m-ore reerdinjis shortly after

9:00 p.m., the results of which follow:

A r• Rereinr in rr/hr

-To P. Officeý 2

F.o.T Lb 5 Tiall'rey outside r-'o P. Office 5

utsi1 de -0p+h 'loor 50

Nt De"cnta"irn~io" fn, " 00

Two ."t .r... fr'. 'ed 'lnr- 1'ri.tnr 5000

Reactor Cont-o t oom 40 Moim flote 200 ,.FD7C 500

ne1a' '-7'uck T nrsio rco r00C

PA-;7 onAi,- . -I*

9+1•. e000

-roioti4

n -fron.....

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4"

"7

'oae~grOunU *.Ln ui ne me~nnu~urn-9 -4-Fnq< -10.ý ;.~v~ eaflng masks,, began 1) takinig~ asit>les th r6ighqut the

t

buildings, 2) taking smear sampl-Bs throughout the buildings,

and 3) assembling instruments for the purpose of setting up

a counting area in the "Fabian House", a second guest house

that is about 1/4 of a mile away, and also owned by Westing

house. At about 9:30 p.m., they were joined by R. J. Catlin, Manager of the Health Physicist Group, who had been informed of the incident by telephone.

In the meantime, presumably between 9:00 and 9:30 p.m., the

security guards set up roadblocks and flares on all roads-

leading to the reactor site. Acting on orders from the

supervisory personnel, the guards re-routed traffic. In

addition, they were instructed to inform all non-essential

personnel, who would be arriving in a few hours to begin the

third shift, to we•ttr-*-- their homes.

At the same time, the first air samples were taken outside the

buildings, as were more direct reading surveys. Portable

inctruments and counting equipment were set up at the Fabian

House. Tn addition, arranpements for the taking of urine

samples of all persons were comoleted. Catlin renorted that

it was decided that all persons who were still at the Seubert

House should oroceed by car to the Fabian House. Upon arrival

at the Fabian Fouse the following steps were taken:- 1) direct

reading surveys were taken of all employees' cars. These in

cluded readings taken on the outside, on the seats, on the

steering wheel, the clutch, the brake, and the gas pedal;

2) spear semnles were taken on the toos, the hoods and the

'runks of all cars; and 1) urine samnles were taken from all

nersons who had been in the buildings at the time of the

incident.

The above surveys were reoortedly conducted by Carl Fritz

and the results of the smear and air sampaes were counted

in the Fabian House. The results of these surveys were

nerative: the direct readinr surveys s'howed no increase in

normal background count, and the smear sanples indicated no

removable contamination.

At some time durinsr the survey, Willhoit stated that he dis

covered a comoan. car that had been oarked near the head tank

and the exhaust stack at the time of the incident, but had

been overl-okVd. He i~nediately checked it for contamination,

but none was found. 0

Unde- the direction of the .P. -ersonnel, various teams, in their own cars, set out ,o conduct direct reading surveys in

outlving ae~ tm~9-inntn

.. It was renorted that one team

went north to Vadison, Penrsylvania, a second went southeast

to '-w Ota'lon, and a third went west to Yukon. The results

of all of these direct rendin' surveys were ne:ative. At the

-ae t47A, air samn"Ts were taken in the downwind direction,

the results oý w~hi'h '1so revealed no detectable airborne ccti'rity. (It ahoulM be roted, at this noint, that at the

-9q-

and' wiiilolt' s*;atea tuna-u-Tne atuauL 'W.LEKu L' vJUýýr~m j w-C£* until the next day inasmuch as the indicating device was not

working. They added that the 3 to 5 mile/hr figure was obtained the next day from the Pittsburgh Airport).

- ' '/ .74" "'

Collins and 'Jillhoit reported that the time from 12 midnight

on was snent taking various environmental surveys, and analyzing

results. Surveys were also conducted in the buildinps as per

sonnel were beginning to re-enter to beein evaluation and cleanuip

operations. The results of two direct reading surveys conducted durin'ý the morninr of Anril 4, 1960 follow:

3 :15 t. Tr

Are a.er..dinpr in mr/hr

Cate Outside

0outh Door of fiS? Roa d ý'2 Road ..&A Outside ( .Ip1R", Door 0,totide PR-" Of S9O1'_

On =ospd ýdit-,cent to Hedi 'P. nrk Penf

Or. Don4 in nr 5 j'-t~' rn "rd Poiler Poor

ClatRopd "I "Touth Tmnor n PcQf

1nF r T1"r ' 41)P•ro Thn'r

A, l Pr~l I Le-', P Ir s-' T) o'

0n 7)-r 27 c ,.f' I-Tnd monaj

•r T .qad •7 , IlT" gf U - 1 9,..,.

-n'• n, - . lo-r `_rop.

-3d Afn-x l~-

aws ns nrev'iously rIot--, 1]. oi the -ndrn±,ti l*-rreln Prlrr'ted

,..,:•~ ~ t •_(t 6-:

" t" ,en " ', ,4 •h -o m•~~t - t,"•_•.q. 'rn• obru ROOO•

-j

7~S~~~'t 'e(fjl~f+ ''T.. on''

- /

- 4-K�¾I±-'� H� -4--

11 15 ';5

45 170

900

-00-9

17 90

?n

91o 710 700 700

I

*a local representative or' Rohmf & n a&O WAS 8OflDSCz6W in aruar i

have this resin for 'a PC deionizer ready in Philadelphia at about

8:00 a.m. At about 2:00 a.m,, a truck was dispatched to Phila

4.e1~hia in ordet--to. nick up the resin. . ffhe f loy~ is -a chrloica smmay f3 the>2ýtiol "taken uyys~~ose per

Soný_ý tbg ýin-f this wate-11

Nttiday, Akpril 4. 1960

1. Approximately 1:00 a.mn. arran~rnent~s made with local repre

sentative of' Rohm A- Haas to have resin for PC delonizer

reedy in Phila~deinahia. at factory at 8:00 a.qi.

.9. Truprw diSTratched( to Philadelpnhia about 2:00 m.m.

3. 0030 - Attempt made to somnie PC svstem in shutdown. rump.

-roomn. P.O.~ nine read. 10 r at contact -- attemrt oband~oned.

4. 0130 - Val.or c-ntal-er erterer' to nhenlr No. I loop fPor

sa-ti 'sf-torvr nool-donwn o-oratiom.. Padiotton readirn' at

,16 a] evn~tio- al-oort 15 rnr. tabouit s!.ro tin.s boil~er

"'loin ertorsd to <ha1 ' 011 nolert. Ali flIT.

R 030 - D1021r room rhnp.fTJ,

6. 04

2Rc - Tnm oyXnlcrprp nib" P nterod to oeYV-117 miroR.

Thopd"~ ' i'Imnln, 100 mmt-" to "Iottom, ernont PAt nonto't

with) bottim of tan1

' )nI6 fýI~tpr. Topcjjcr hero z.Lt r.

7. ()44;i~ - Poilo " -o-" -"hnec" '-j, ,ooln e in ero-7r nomi-. T-To,

9. oýo0 - llri-,nd "0 o11 of' wotor from hottmý -P Cf 00 n

oyi~~oe-.i~to oniI'qo -poin torlr. "a]ot ' 1on ~tor nP in" oy' pr 007 r

q. 0700 - +partod rormoro] of h -t rnn hoami of ion xhnrc

eo'-r~n ~lto i rtroAýnti on ofP -14.n for nionmnof qVc

tom. 'l'""ýJ1oni'ol Tolto 0770.

10. OFý00 -1600 o~iorrpl r~oP~ n.rorop-'Ol qper

F1711i timep -''i'i i-' o+ A momein"n- coavn

(li,,iTO ac', -i'OI-+.~ '" oonqtif'iU rra oim

r ''4--',1-oi'ior o-f "ewý P7'. ij-1 oyr n,

-cc

i',uo'6n-q 4n'_

- -1 1 -

0- 1 16ed1barl resi.

3 0730 -:tCcsnletsd 1oadinr,, 'cleaned,4taslcet' ~f6rs

4. 1015 - SvrLge tank blower Pt operation.

* 5. 1124 - Flow through ion exchanger started 95 gpm filling surge tank.

6. 1402 - No. 3 PC numn on. one hour total. (Started 1401). Object here was to deconptaminate PC water through PC ion

exchanger.

7. 411 day operation consi-sted( in rapssip' PC water from hlead

tank to io-1 exchanger and surge tank to head tan',.

.8. 1To- 3 Dump in oneratior two hiours, total rema-ining rnrew -7nnpnt -. 11 the-ir timpri'p dartgrminatira' and cleaninpr.

J*cot-ti-11'ed "low of wata:r f,"om Ittat; tnn to sur.-n .tn1-" n'ri

thnran ,iý' int- annr'rnt-ninit'~ bncIr to b,39i tapi iridC'llr

2?-Pnm-cl unenenosr~r tep-s from -all oreratiffl areaý and c-elanai! pa;nonnad"n

3. D'31 oirstep bnint- one-rntt;A qt 1owe.-r possibhle flow.

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Von-site and O6ff-site study, and (2) Westingh independent study taken.

;el

rect reading'surveys were conducted between 9:00 a.m. end

1I:30 a.m. on April 4, 1960. The following are the results of

, these surveys:

April 4, 1960

0900

RADIPTITON LEIV•,S

\'achine Shop (No.) Machine Shop (So.) P.S. P.ek •.R. (NiF) Door

3.R. ('i) Door V 9ne

amn Room ( D) Doer w.D. Pact Door

Tor -!c'1 (nit T o n I , ,• .! m u

•T•+Y 0'o'nD

noo- no !i'

"To - --- r-mi

',frnr T,-o r

PW lon

50 mr/hr 40 mrr/hr 55 mr/hr

1SO mr/hr 25 mr/lhw 170 mr/hr at conta •0 mr/b~r

fO Mr'hr 210 mr/hr 40-50 mr 5-1-5 Mr 0oo-4000 r

'70 mr$

L -+-rN...

/5br l 7'

') A,/br

"ýO '-7

Ij52 9_,/hr

AC -- /'

9nO n+ rlcnr(a

r - t 4.

>L: ) -+ .

1I _,.

/ .rc)

- ir (0 , )T,

•Ct

B~eam Hole

-7..

East Railing .; Thermionic Access Port

East Access Port Over Rod Prives

'Step-off pad

16' ~vlrtinm

It -r,!.

65 mrn/hr

42 R/hr

I :5 R/hr

45 mr/hr 1.0 ':"r/hr

Nor~rql r diptior, zone from filter 071 Toon *ýl '9twTeen Loons 2 & 3 _"_100 '1'r/fi" (O11o to PC r'tnt'p' used. fn-' Crml1 mo-.

h�; ��'/Hr

1;0 p,/Wh

40-an mr/hr

vnr-rc- to tP( P-o 0ý10 -/'-

1)0 -N/b

"P'- -.- , T 4 A-,o DI1~ - -f 71

10 -'-/b

)§� ro/l,,'

o---'flir-r3

� -"- & ;'o'rnlll(9

, --'o-N-

7- ,� o"f'

- 17, -

Outside at door Inside at desk

At Guard Hou.se

County Road

1.0 mr/hr 5 mr/hr

10 mr./hr

3 mr/hr

9OITPTT

RompT 1 9

'\TC1 D'1- V

T),? P i ,,

1-7 1 nMr/bh

AI

N

<''~0

SI-I -

4/4/60

1.10

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U@ATS uaeq 4ou pv Saq4 ;vqq. PIVE; OU0110d puv 1 q OuVTa TOR ý-Qxl

*saSuvT4o Idnaqv Su-a jo aavmvun

s q puu 14no pollwo saam jo s2uTpzaa ou 4a;qAa

-1 ;V,

u %ovq qmtlv aq4 pure jaxod uT dip aqq louxana 'GaTdnOO

-o=oqq ps!ýuomna4kju'y aq!t moaj saan!tvýodmaq. !tno* SuT-E-Evo ualaq,

P1914 xosTAjadus aqq. 44uamTjadxa aq!ý SvTaxtp *vq4 pTva TouvTff

There was no evidence, or zale miareria±an. Ulvne PLrIJUtJI - f iX

fuel element- observed in the hot cell.

The specifications for the fuel elements were examined by

the committee. They call for a surface finish free from scratches

more than .003ý" deero, an&* a deviation from straightness of no more

than .015". ýTheyr further suecify that the bond cladding shall be

free of blisters following a. ste~nd.erd 930 0 F, 3-hour blister

anneal.

The shop insrectton rorocedures state that outside diameter

measurements and wall thickness measurements; shell be! tak-en

every six inches. Finally, there sha.31 be a rmeasizrement of

the amonnt of straightness or howin.T of the el~ement.

'She fuel element records -indAjated that thq.z eie'-ýort hoeý

"been roýceived on Yý'hver'ber 20, 1%?, a~nd 4-t hi-d hp-en inz~nected

P-rd ýInnrovod by Wsiohue

Mo'~fl~o o~d hetAn~i~'l'r Arthe elements ~rpre by

Ciovit-e, tlkpre hed bheen void- Jn thP h'-'a r as lang, Pa 10"1

10" Mwoxro, hoi- A thit. tu-n T)-nrlo ho1 heraovoi l

P row nrro'-enlo',red. "oý statedi t~hat hoe hod6 eroonai1ly in

7' soeted one~'a1eleneno "I? with i-he ne.w n-rooea- owlthe

t',e-- 1-d 1,aeo ornnroxroA/ .A- W 1>' renort r'ed th'-t heý h'.-d 'nr two

o~~s~on'n-doon rnr-oourc.c-d irsnpotionn in Clor-itnilrq n to

check, on theý fle1

O fnh b-- or Co olotn)r6,bdbe

A '~,-,T- Th~o I~ tl-t, ir theý -f' 4 t ehirront op R plemPntq,ter

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S-T- 40'. UOTIU40,do ayes I twTjý ,a J, ajqTsuods"ýý

0.0

half of the ruptured element to examine the bond between clad

and meat. Further netallurgica studies may then be done on

the remnants of the ruptured olewent. . -_ ( k. 4 --1

5. As of May §, cleanup operations of the primary coolant system

outside the containment shell had progressed to the noin t that

this pert of the system was considered clean. Fowever, it is

reported that some mn.rticles of highly active material have

evidently become lodfed in riping joints in thp primary pmpina

irside the containmert shell, and further flushing will be

necessary to clear un the system. P. "1t- 5-j

mnonth gg'1

~ g}~ ~r~p 'rf' ~cons-'der:.nx rovingý

the lon-atioo of' t',e f4 5 qin0 nrodmnt monitor,-so that it, ae water

'Pl,p-r ..~ _,_• .•,,ee--ht4a r'- .i rir rn, 4hn&' fo,' ... ,c-, :-?...

lro:ýn+ ir on j cant. n' t 1-prý hoýp t vrt n-r-i.-ef qt ahe'qt

C ut4 o

�---rj�

'- - �- �

M: zI,.

"- ° "

Noise Level as a Function of Flow

Constant Power 40 MW

Scale: 1 Large Block = 50 KW

Access. Tubes In

S... .. • 6 • . : ... . ... ql- ..

7-7.. ( "

T -IN

- ..

.. r. ""---'-'-'-'-'-.- .

.--" - -- "

:: - . ! /• l i t . -t r ' , - -,• -- ' : • :. . -.- . - - - .7_ , - - - . , " --- • • - - -/ . -/ - -• - _ . -._ . i - P -t ' ---_- .- ... - : b- . -K• . ' , _ _ ." / -' '* i . ... :-- -', : --- ' -• -: - :d . _t-z - _.t -f - ..-- - .- -- _ -- - .. -I' .I f . . " = .... 1 .•, -- 5- _-:. .--. • • ! . - :I -.: •-e •--f. -- -_ -. •-.-: - :-- .; --- . . . .. :--: --- -.•.. -: '":".t :•N -_ --. :- =, ."- -•",N •

Noise Level as a Function Of Power Output

Constant Flow at '7000 glm Scale: 1 Large Block = 50 KW

Access Tubes In

j ., I . . -- '.. t I' i -, *j

'. \ 'y\ - U the dqt

I/I//I/ /I/ii/ 1 i VTT L /L1

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f~ Ip

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.: 6 At ''

..cc I IU v l 4 ttt (ria

No iseLvl v oe

CosatF low~U Q3M tc~l1 at 800 gp

Scle 1 Lag Blc = 50 KW :I

Access Tubes In

1/

W.- --- - - - - - - - - -. -.- .- . - - -. - -- -. -- - - - - - - -- -

-- - -- - - - - - - - - - - - - --- - - - -i - - - - - -~ - -~

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7- -E- =-i-T .

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Acces Tues t

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I "

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.- - - - -

---

-

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S- - -- - . - - --- - -•

- - --- = ------ .

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1~~ -1- 1-

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I----4 -17 -4-

* -- -. - .: . M

A~ - 1..I

-e -on f t-LEM

Noise Level as a Function of Power

Constant Flow at 9500 gpm

Scale: 1 Large Block = 50 KW

Access Tubes In

�v*

EXHIBIT B

TEST SPECIFICATION - - P

T-Spec No. 5-1

Attached is the copy of the Test Specification for increasing the

reactor power to 60 MW.

Distribution List

M. A. A. J. R. B. R. J. G. C. L. F. E. H. W. S. T. Sp: J. W.

Schultz Pressesky Rice (6) Catlin (3) Geisler iardos (3)_ Hemmerle (2)Johnson (6)

ies Sadler

M. Crane A. de St. Maurice

EHASE V

>o-~

.3 February 19, 1960 TEST SPECIFICATION - -PHASE V T-Svec No. 5-1

T.S. V-I Raising Power Level from 20 MW to 60 MW

The reactor power is to be raised from an operating level of 20 mw to 60 mw in incremental step of 5 mw. A set of operating parameters has been established for each power level and will be adjusted during the program, as the need arises. If plant limitations are exceeded, the program will stop until remedial action is taken. In general, the program consists of establishing that the reactor can be operated safely with a given set of conditions and then operating under these conditions for several days.

The criteria for safe operation have been established in the WTR License Application Amendment No. 14 and supplementary information issued to the AEC and in Amendment No. 1 to the WTR Operating License. They areý

1. First fuel ring bulk water outlet temperature. 4 220°F

2. Inlet primary coolant temperature. < 140°F

3. Nuclear power level oscillation controlled with + the automatic control system. < - 5%

4. Radiation level at accessible portions of the face of the biological shield. _- 1 mr/hr

5. Radiation level at accessible points in the primary loop < 1 mr/hr

6. Boiling will be detected by the "bubble experiment" described ir WTR-SS-TA-258

C7. Less than 1% voids will occur in the moderator due to

boiling.

8. Maximum heat flux will not exceed one-half of "urnout heat flux.

Table I lists the pertinent olai.t parameters establishing the safety of oper

ating at a given power level, These conditions are obtained by establishing

the required flow for a given power with the reactor at a Dower level 5 lioN be

low that desired. A reference no__se level should then be established on the

bubble detection equipment 0 o The reac*or -ower should then be raised to the

specified level. During this time particular attention should be given to the

bubble detection equipment. The power should be redued to the starting point .f boiling is detected. If boiling is not detected the reactor should be op

erated with these corditions for 15 minute: or. 'nýtil ciling- i_ noted. At th-e

end of this period e flow should be ýn'nr-eased •o tb value li sted in Tac le H tne soecial nuclear :-nael e! of .he btt- ecui:n e; s'.-cdown aDn •era~ton

tinxe- at t o-,• lel o;r e v e > ood i'e - ie sci:ihedule Table I. Tw_ o

exceptions will occur, The boiling check will be made prior to the twelveday run at 40 mw and a second reduced flow experiment will be carried out "after two*day operation at 60 mw.

Secondary coolant parameters and cooling tower operation are left to the judgement of the reactor operator. Standard records should be maintained of the temperatures and the flow rate but the actual values are not important if the required primary coolant conditions are maintained.

Radiation survey of the entire primary system will be required during the program to insure against excessive radiation levels.

Based on a void coefficient of -0.14% reactivity/% voids in the moderator, the loss of .14% reactivity will indicate that a prescribed limitation has been exceeded. This reactivity is equivalent to 3% motion of the peripherial control rod in its most sensitive position. This motion can also be caused by a core temperature increase of about 15 F. If this rod motion is suddenly required during an increase in power level or subsequently, the reactor power level should be decreased by 10 mw and the incident reported to Scientific Support for appraisal. It is assumed that temperature can be held constant to within t 50 F.

The bulk outlet temperature of the first fuel ring will be measured by installing thermocouples in a 'IV" basket inserted in core position Th,

Boiling will be detected by the tbubble detection" equipment described in WTR-SS-TA-258. A description of this equipment and its operation will be contained in an appendix to this test specification to be written after the installation is made and checked oit.

r ',edby Safeguards Subcommittee

A. JTPressesky, Chairman of Safeguards Comrit tee

TABKE I

Tout R.-V. 0oF

156

156

157

1'7

156

154

158

156

155

SPECIAL RUN

157

/ ýs'-

A T. Alarm 0oF

25

31

38

43

42 40

39

36

35

17

Po'e:!r Level Cut ba,`ý Scram

MW MW

25

28

35

40

45

50

55

60

65

65

30 30

40

45

50

55

65

70

75

75

Low Flow Cutback Scram

GPMI GPM

5650

5650

5650

5650

6650

7750

9050

10500

12000

11000

5000

5000

5000

5000

5850

6850

7950

9200

10600

9750

-3-

P wo V I r' MW

-'(

2'

.. ,�

P.C. Flow GPM

; 50

66 j0

() 50

1'. 50

10600

1-2300

142100

13oo000

R.V. AT o F

21

20

32

37

36

34

33

31

30

32

Tin R.V. 0,

1 35

130

12)

126

12,

125

12 '

125

125

/ -ý

K)

(,O yo

-< ./

-70

RoVo AT Tin 11VX 0oFo

18

22

26

30

30

28

27

26

25

140

135

130

130

130

130

130

130

130

TABLE II

Tout R.V. 1 F

158

J-57

156

a.60 160

158

157

156

155

AT Alarm 0oF

21

26

31

35

35

33

32

30

29

Power Level Cutback Scram

MW MW

25

28

35

40

45

50

55

60

65

30

30

40

45,

50

55

65

70

75

Low Flow Cutback Scram GFM GP

6800

6800

6800

6800

8000

9350

10900

12600

i4500

6000

6000

6000

6000

7050

8250

9600

11100

12750

K>

-4-

MWPJ'C, Flow

GPM

8000

8000

',400

1000

1)800

-4800

17000

,0()

7)

-� 4

C>

TABLE III

Schedule for Increase in Power

February 18

February 19-20

February 21-22

February 23-24

February 25 March 1

March 11-23

March 26-27

March 28-29

March 30-31

April 1-2

20

25

30

35

40

40

45

50

55

60

1

2

2

2

MW

MW

MW

MW

MW

MW

MW

MW

MW

MW

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EXHIBIT C

TEST SPECIFICATION NO. 5-2"

POWER ESCAIATION PROGRAM

LOCAL BOILING IN THE CORE

Several changes have been made in the reactor core instrumentation which should aid in the detection of the beginning of local boiling. They are: (a) the removal of the core access tube, (b) insertion of the helium bubble tube into a fuel element V basket for the production of bubble in the P.C. flow, (c) instrumentation of the two (2) fuel element channels in addition to the bulk outlet of the element and (d) direct measurement of control rod position.

The reactor has previously operated at 40MW with !000 GPW P.C. flow and an inlet temperature of 1250 F with exisnce of only mild disturbance on the special nuclear instrumentation. Since then it has been established that there was some boiling in the core access tube installed in the core.

For the Dresent test, the-reactor will be brought to equilibrium at 3CUW with a flow of 5000 GIU and a core inlet temperature (heat exchanuger outlet temperature) of 1I0°F. A reference set of date will be taken. The reactor -ower will be raised successively to 35MWy 38MW, 4",W, 431W and oPQAW, Automatie control will be accomplished by one rod during the en-tire test. Data to be taker. at each power level is: Tin R.V.; Tort R.V; Tout Heat Exchanger; Position of Control Rod on automatic ccntrol, temperature of the six thermocouples in the ins-,ruented f...... element and the compensated power trace wth the sL-ec- cl nr',ýlear i-stsiru.ernta-tLron.

E, H, He-rerle, Supervisor Terffical Assist" •oe

A. hrUessesicv, Chi /ran 'TR - Safecuarcd s Coizntte-

SCON & CUTBACK

Settinz - Low Flow Cutback

Scram

April 3, 1960

4000 GON 3000 GPM

Power - Nuclear

Cutback

Scram

55 60

MW ,MW

Tout R.V. - Keep less than 180°F.

Tin R.V. - Tout of Heat Exchanger 130 0 F

L. P. Thimble - Alarm - Set to 2000F

Temp. cut of fuel element - Less than 250 0 F, Call 240

Reactor 'T

E. H, He.=rerle) Sapervisor Tehchnical Lssistance

©utbaý-ý 76 T0F

- A

'SUNDAY APRIL 3, 1960

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#4 #6it #2 #1 #5 #3

2 Channel Bulk Water Basket Channel Basket Channel Bulk Water 2 Channel

Reduce Power to 30 MAW

J1?:_jV Reduce Flow _T'-?17

P.C. Flow at 5250 (81P.M.)

15 MW

20: 44 S cram Reacto~r

IS~UMNTDFME ELFNNT Tiý ýTUF

... ...........

NEE

PM ELEMEW RATURM

-SUNDAY APRIL 3, 1960

FQel 191emmt Inst. Fuel Element

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2 i,'I I lit,

2 '3,:

#4 #6 #2 #1 #5 #3

2 Channel Bulk Water Basket Channel Basket Channel Bulk Water 2 Channel

Reduce Power to 30 M

Reduce Flow r

P.C. Flow at 5250 (8

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A,B,C.DE & F HOLES ARE

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