ML20033C588

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Notice of Proposed Issuance of Facility OL for Ucla.Proposed License & Hazards Analysis Encl
ML20033C588
Person / Time
Site: 05000142
Issue date: 09/09/1960
From: Price E
US ATOMIC ENERGY COMMISSION (AEC)
To:
Shared Package
ML19283A221 List:
References
FOIA-81-339 NUDOCS 8112030465
Download: ML20033C588 (9)
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i UNITED STATES ATOMIC ENERGY COMMISSION 1.% ;

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DOCKEf NO. 60-lh2 Al.?

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THE REGE! TIS OF THE UNIVERSITY OF CALIFORNIA w,, :.;

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D N0fiCE OF PROPOSED' ISSUANCE OF FACILITY LIC'ENSE

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. Plia'se' takd' notice thdt, unleas wit'hin' ' ifteen days after the' fili $1g of

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hearing is filed with the United States Atomic Energy Comission by the

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. Practice (Title 10, Chapter 1, Part 2), the Commission proposes to issue 1..

to The Regents of The University of California a facility license sub-stantially as set forth below authorizing the possessi8n and operation on w

the University of California campus at Los Angeles of an Argonaut-type

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E nuclear reactor which may. be operated at power levels up to 10 watts (thermal). Prior to issuance of the license the reactor will be inspected I

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'CPRR-h3, as amended. P4titions for leave 'to intervene shall be file'd by

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mailing a copy to the Office of the Sesretary, ltomic.. mEnergy Comission, 2,7 7.'

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yy.i Washin'gton 2$,'D.- C/,i.:v::,or by delivery of a' copy in person to the Office of,CW w

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n the Secretary,' Germantown, Mary 1nna, or the AEC's Public Document Room,

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For further details see,(i) ~ths application submitted by the University lJ

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.r at the AEC's I51blic Document Room. A copy of item (2) above may be obtained at the AEC's Public Document Room or upcn request addressed to the Atomic 8112030465 810909 PDR FOIA POLLOCK81-339 PDR e.

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Director, Division of.

Energy Connaission, NashingUn 26,...D. C., Attention:

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.FOR THE ATOMIC E.NERGY COMMISS u

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.6*l Dated at ceimantoin, Maryland i".

this day of c, 1960.

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THE RHIENTS OF THE UNIVERSITI 0F CAT.TFORNIA

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DOCKET N0'. 50-lh2 4

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PROPOSED LICENSE ' ~'

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1.,'This license applies to the Argonaut-type; nuclear reactor (hereinafter

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referied to as "the reactor") design' d ifor 30 kilowatt (thermal) operation', f.h,1.~

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which is. owned by The Regent's of.The University of California and located ((.7 on the University of California campus in Los Angeles, California, and' y;21

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2 Pursuant to the Atomic Energy Act of 19hh, a.s amended, (hereinafter referred w

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to as "the Act") and having considered.the r' cord in this matter, the Atomic

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The reactor has been constructed in conformity with Construction I

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. California and will opera'te in ' conformity with the application and N'

in conformity with the Act hnd with the ' rules and.begulations of the Y

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University of California is technically and financially qualified to p-Q.;

operate the reactor, to assume financial responsibility for payment y;.

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of Commission charges for special nuclear material and to undertake w.

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and carry out the proposed use of such material for a reasonable

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The possession and operation of the reactor aisi tha recelpt, possession c 42.e s

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University of California is a nonprofit educational institution and will y-i,.4,

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use the reactor for the conduct of educational activities.

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MT of California is therefore exempt from the financial protection require 4:

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Subject to the conditions and requirements incorporated herein, the Commission

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Pursuant to Section 10hc of the Act and Title 10,, CFR, Chapter 1,

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q Part 50, " Licensing.of Production and Utilization Facilities", to

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. possess and operate ~ the reactor as a utilization facility at the

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Pursuant to the Act an'd Title 10, CFR, Chapter 1, Part 70, "Special

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Nuclear Materila18, to receive, possess and use up to h.000 kilograms EST

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s for use in connection with operation of the reactor; and.*- '

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. Pursuant to the Act and Title 10, CFR, Chapter 1, Part 30, ". Licensing ofr..r,+cc C.

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Byproduct Material $ to possess but not to selia2Ete such byproiluct materials"

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..as may be produced by operation of the reactor.

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h. This license shall be d'eemed to contain and be subject to the conditions speci-
8 fied in Section 60.$h of 'Part 50 and Section 70.32 of Part 70, Titl'e 10, Chap-

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Jy; ter 1, CFR, and to be subject to all applicable provisions of the Act,'and to the rules and regulations and orders of. the Commission, now or hereafter in

<'..2h; effect, and to the additional conditions specified below:

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Operating Restrictions i

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University of Califorrila shall not operate the reactor at power

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2.. University of California shall not conduct any experiments other

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than those outlined in Section III

" Reactor Checkout and

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Cperation' of the' final hazards report, without prior written 2llS autho'rization from the Commission.

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University of California shall not make any changes in the facility design, performance characteristics, and operating procellures speci-j y, fied in'the application without prior written huthorization from the

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In addition to those otherwise required under this license and applicable regulations, University of California shall keep 'the following records:

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Reactor operating ccords, including power levels.

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Records of in-pile irradiations.

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Records showing radioactivity released or discharged into the" air i Q.G

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or water beyond the effective control of University of California i

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writing Eny indicition oi occurrence of a possible unsafe condition relating to the operation of f.ha reactor.

$. Pursuant to.Section $0.60 of the regulations in Title 10, CFR, Chapter 1,

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Part 50, the Comission has allocated to University of California for use

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in connection with opeiation of the reactor, 3.350 Ic'ilograma of uranium 236

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-p and 32 grams oi' o....ncapsulated plut' onium. This allocation supers'edes that

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' previously. granted in Special Nuclear Material License No.'...SNM-392 issue.d R.,...,. w.'. m

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,,,j August $,1960. Estimated schedules of special nuclear material transfers 1.

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to University of California and. returns t o the Commission are contained in ~

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Appendix'"Ah which is attached' hereto. Transfers from'the Cemmission to University of California in accordance with column (2) of Appendix "A" will.

be conditioned upon return to 'the Commission of special niclear material substantially in accordance with column (3) of Appendix ".A".

i This license is effective as of the date of issuance a$d shall expire at 6.

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FOR THE ATOMIC ENERGI COMMISSION

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_.Date of Issuances

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g-UNIVERSITY UF CALIFORNIA

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FACILITY LICENSE N. R-1.^.y p.

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$.:.k;c Estimated Schedule of Transfers 'of 3pEcial 'Nuhleir" Mate'rfal from the Connission to," f'..c..

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the University and to the Commission fr'ontlhe'Univerafty f.'..

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Transfer to the to' AEC Kgs. U-235 Cumulative Cumulative (Fiscal University Recoverable Spent Losses Losses Year)

,Kgs. U-235 Cold Scrap Hot Fuel Kgs. U-235 Kgs. U-235

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HAZARDS ANALYSIS

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" DIVISION OF LICENSING AND RFEULATION

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General Descripti'on~

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y dh The pr'oposed reactor is located on the Campus of the University. of California,

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  1. at Los Angeles, in the Beverly Hills area, approximately 15 miles from the f

California. -It will be housed in a special bui,1 ding center of Los Angeles, ' construction which will be attached. to a future engi-of' reinforced concrete 7-neering building. This building is located near the center of the campus, lQ which has facilities for more than 10,000 students.

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The reactor is a light water-modarated and - cooled Argonaut-type designed AN to operate 'at 10 Kv, utilizing a graphite' reflector and highly enriched Q.

uranium fuel. contained in aluminum-clad MTR-type plates.. These plates will, g ig'd y

b.e'. arrange 1 in groups of i2, with h such groups placed in each of the 6- ~

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vertical aluminum fuel boxes or channels. These will be arranged in 2 rows

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of-3 each, with a foot of graphite between the rows, and additional graphite 4.

rollector will surround them. The graphite will be penetrated by various

, ::j beam ports and test holes to facilitate the irradiation of foils and experi-ments. The reactor will be controlled by h semaphore type control rods which will opeiate in enclosures between the fuel boxes. Three rods worth about

.g-1.5% delta k/k each will be used for shim control, and the fourth, worth about

.,R 0.6% ~ delta k/k, will.,be used for regulating the reactor at a steady power 1cvel.

The reactor will be cooled by water circulating upward through the fuel boxes and out'an overfl~cw pipe at a rate"of 10 gpm. In an emergency, a dump valve' ~ '

j4 will; drain tlie fuel, boxes quickly, and the control blades will be released t6[,

fall by' gravity in'to the ~ reactor to shut down the reactor. The reactor willc: %.;'t

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" be shielded by large blocks of concrete,1some of whi~ch will be removable forf.". 'Jjc

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experimental access. The' reactor room will have'an independent ventilation

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, system ' circ'ulating 5000 cfm of' air witl filters on both the inlet and outlet','^ 'IN

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7 The excess reactivity o'f 'this reactor dill be limited to 0.6% delta k/k above-

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l cold, clean critical, which will not result in a damaging transient even if it t

were all inserted at. one time as a step input. Normally, reactivity insertion

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.W rod drive motors; only one of which may actuate at a time. The mechanical

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drive' connections inirolve, magnetic clutches which will automatically disengage g{j.;q and allow the blad,es to drop into the reactor on receipt of a scram signal.

Duplicate channels of neutron sensitive instrumentation will be provided for all levels of operations. The reactor will be protected by a number of scram f -

and alarm inte'rlocks including neutron level, period, and radiation level, a

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9 C, d./ N~f

.eactor also' has an automatic con' troller which may be connecfed only to W8g[9o eintion monitor which switches the control Mck to manual whenever there i regulating rod to maintain constant power levels. It is protected ~ by a i,

'$.at

. deviation of more than' 10% between the demanded power level and the actual.

".2l,Jp level.

s.

Sh Loading proced s,for 'the reactor have been establis'hed, and[the ap'p'licatio'n

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-includes a chart 'sho' wing the configuration of the fuel, at each step in the.g,,,

gyh loading.

The qualifications of, the personnel operating the reactoi aie ade ensure that they will be able to carry out the procedures in a safe manner.

t EM@

Har,ards Tnalysis

?

r 9'

A reactor of' essentially 'this same design has been constructed and 'is being

" ~

operated at the University of Florida. Hazards analyses pertaining to the

-.l Florida reactor can also be generally applied to the UCLA facility, since the reactors are almost identical. These analyses demonstrated that there appeared to be no credible way to release fission products from the reactor, and that it therefore presented no unacceptable hazard to the health and i

safety.of the public. The conclusion, which was supported by theoretical calculations, was also bded partially on the experimental informatio'n s

gbtained in.the relatively sirWie SPERP. reactor, which has demonstrated w3i t n as ability.to. withstand large additions of reactivity without damag

. W.%'

Although it is conceivable that extreme mishandling of the reactor or e.

~

experiments could result in sone hazard to the operators, such hazard can be minimized by proper design and operating procedures, and the possibility of hazani to the general public would be extremely low.

m.

Operating Limitations I

There are certain deficiencies in the application as discussed below which

@l require.the liYeorporation of several special operating limitations in the g

license to assure th,e proper, degree of safet' y in the operation of the facility 2,

L; until these deficiencies are corrected.

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a.

Handling of Gaseoli Ef'fluents

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MiJ?

] %;-U,.

U The proposed method for.handl'ing radioactive gaseous c'ffluent, particularly i

argon-Isl, is not considered to be described in adequate detail to support a

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conclusion that full power operation at 10 kilowatts (themal) can be c'arried -'

out without undue.public hazard.

Preliminary calculations by the applicant, assuming the reactor is at full power operation about 20% of the time and that no decay occurs wighin the reactor, predict an argon concentration of about 8 x 10

.uc pee em at the discharge point to the atmosphere. This predicted

)l' concentration is somewhat above the limit specified by AEC Regulation 10 CFR Part 20 for unrestricted areas.

dicting argon concentrations in the reactor room itself.There are no calculations p t-In addition, the' actual procedures described for safely releasing the activity from the reactor l

where it will accumulate to the atmosphere are incomplete.

Ii For these reasons, we recommend operation of the reactor be limited for the

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H present time to a maximum power level of 10 watts (thermal), a power level i

I

' i_E

-... '.. 9.*. i N

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c.

3 d

';gj sufficiently low to insure 'that' the argon ' activity will not constitute a

.d@

serious hazanis problem. Before full power operation is authorized, a more d 'i :.

complete analysis as'to the quantity of gas expected, methods,of controlling

75p, release,_ points of releas', and concentrations at all points of release must e

( :.

be submitted by the applicant and reviewed by the Commission.

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, ~,, ~,

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b. "Expirimenta1 Probran N..

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There are essenfially no. procedures described in the application for conducting

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experiments,.and proposed experiments other than those in the initial testing

6 program are not specifically described. Before authorization for conducting pp experiment,s.other that those described in Section III

" Reactor Checkout and

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Operation," of the final hazards report can be granted, general procedures and YJ limitations for the conduct of the experimental program must be fonnulated and approved.

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c.

Cha;.gs in Design and Operating Procedures

. g

At a number of points in the Hazards Report, the possibility of making changes in the reactor design and operating procedures is mentiongd. We do not believe that any changes which affect facility design,. performance chsracteristics, or c.

operating procedures should be made without. review and approval by the AEC.

g;

~~

~ ~ '

-, T In viev.of 'the f' regoiAg, ' hie f511owing lic'ense~ provisions are cons'idered o

1, f appropriate 1.

University of California shall not operate the reactor at power levels in excess of 10 watts (thermal) without prior written authorization from the Commission.

.a igif;t 2

Un'iversity of California shall conduct only such experiments as those p-outlined in Section III

" Reactor Checkout and Operation" of the final 7,

hazards report.

$jfy@

- 3.

University of California shall not make any changes in the facility rdMi fb.

h

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, design,; performance., characteristics, and operating procedures specified

@f.g

_-in the, application without prior written authorization from the N

' ' Commission.

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. a.;., ' h t.,?.9,

.SW(, _

.. Conclusions

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Weconclude.thatthereis.a.r$'

igQ' easonabic. assurance that the reactor described in the ' application,' can be constructed 'and operated as proposed in the application,

[4 -

vith the addi,tional operatihg limitations specified above, without an undue risk

.y l-

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r;is to the health and safety of the public.

,p% '. '

14lh;?

P, Chief, Hazanis Evaluation Branch Division of Licensing and Regulation 7'

SEP 9 1960 i

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