ML19246B039

Reg Guide 2.2, Development of Tech Specs for Experiments in Research Reactors

ML19246B039
Person / Time
Issue date:	11/30/1973
From:	NRC OFFICE OF STANDARDS DEVELOPMENT
To:
References
REGGD-02.002, REGGD-2.002, NUDOCS 7907110193
Download: ML19246B039 (6)

Text

@ N[Ma5 E ki5 1 f b R Y G Uim E Novemter 1973 VQg 4

DIRECTORATE OF REGULATORY STANDARD 3 REGULATORY GUIDE 2.2 e

DEVELOPMENT OF TECHNICAL SPECIFIC ATIONS FOR EXPERIMENTS IN RESEARCH REACTORS A. ?NTRODUCTION trays, hasets, or oti,er pudmg e r pw aang :cmes u or adjauent to the reacter wre. M eg

.nw,.e, :o Par 2.~a[h M 34/M 4) of 10 GR Par t 50, special modes of reacter syst s, or compmcu uxe to "I wen an c of Production and Uti!uatmn Fa cih tiesJ accommodate m J m dual, re pc t it n e.

o:

muit:pv requires t ra t each arnheatwn for an operatmg beense experiments should also be prm Jed. These en ma de

wv+ a Gn21 analysn md emavn m the design and such categones as reactor puNng, use of reutei s mm, performance of structe

es <ystems, and companents cf or fuel as gamnu radution sars es. or use < t uet m the f auhty mth the cb:emve of mesung the risk to subcritual arrays separated from t he wre.

pubhc heahh and.atety resitmg from operation of the

-taaha. section M A of 10 OR Part Mi requaes that The design, construction. and plasement ot e& t.

each such appharion also melude prepesed techrucal expenmental f acihty should be analy/ed f or mhereu s;rcimitions derived from the analyses ano evaluation safety q uestions that exist apait from expenmeu s pertmmed for the safety analysis report (S AR).

accommodated ther em.

In addit:on. tor ca d expenrnental f acihty and mode of reactor system or Ihn guide desenbes mformat on that :hould be compone nt use, the descriptior.s and safety analyse' pro posed t echnica! specnic ations for shou!d address the types and copes of expentnents ua.luded m in research reactors. It ident:fies mtended to be performed.

9,~ experiments conederat ons that should be addressed m the evaluation of expenmental. gams as well as :or suerations that '

The purposes of p~sentmg such utety ar h es n should be addressed to defse hnuts and other (1) to demonstrate that the expenmental po c.nn n r e q ui r e ments to be ecluded m the rechmc.d ensisioned at the time of presentation of the M R c m be e xpected t !u t 'he gm M nes carned out without undue nsk ta the pubhc h eahh ad geeincations. It is delmened here will be adapted, as regt.: red, to speci!L safety,(2) to demonstrate the techmcal abihty to arry features and characterist:cs of mdmdual research out the kind of safety arulpes v.hich is expmed to be react ors done on a continumg baus throughout the ciolution of the expertmental program,(3) to estabhsh b n a g;o nst B. OlSCUSSION whah unreviewed safety quest:ons can N easured pursuant to paragraph (c) of 150.59, and 0) selop Lich sa fety analysis report (S A R ) contains subject matter appropriate for mclusion m techn; cal desaipnon of the proposed experm.cntal program an d specificatior,s.

utely arulyses for each type of expenmental facility propowd. It includes descr ptions 3f and safety analyses Safety kJresearch reactor expenmentahon requ:ro for permanently instal!ed facihties such as beam tubes, that consideration be given to ary feature ut the Jeugn thernul columns, hydraube or pneumatic tube systems, or conduct of an expenment, meluJmg miended and other types of capsule irradiation facdities, and functions and possible malfunctions, which can. reate.

movable experimental facilities fin so me types of directly or mdirectly, a radiological exposure hazard.

e reactors) which accommodate placement of shells, tubes, Safety analyses for expenments should corp 142 l

e USAEC REGUt ATORY GUtDE5 Cop.e os puenri y ws

, t oese,r.d er. = wen.re-,..ig r, d..-

demerums na t he

85. A tonec E rwryv Correvuseon, emmere capt e IE M.C Reguteeory G uertes are emuod to dew to end cre w e Nierne to the put*c A ttent.ea Dwector of Respdetory 5tenrhetas Corewnents earl suuw ms Ew t

crwthods erruptetue to tre A EC Reperory steH of vecaemeatq apecif.c pa'ts of 6- - -

. en etwee pe0e= are encouraged and troukt be sect vi e== Se retar v t he Coeve ans.Xs repetioas. te oesc>aste toer waves veed by the stoft m of the Cmwnmuon. U S. Atomac E nergy Comtress.on. Weseqvc. D r. 70h48 3

evaduetmg apoof >c proo eme or postuanted amonents or *o proveos gudence to Attenteon: chast, Putd c Proceedags St.e+f ers> hants Peqpdator y G series are nos outstitutes f or regu st orse and coptpinence a tm them t.s not <*)uwed beethode end eWut ore differ erst hom thces set Out.n he pedme are issued m tte fodicerg tse tiroad ev,sens ete pedes eeH be seceptabee if they prowse o tosse for the hedg requisite to the assuews or cont.nusace of a garm41 or hcene* by the Cornmess.on

f. Power Reactort 6

P. orkets

2. Reneere eruf Te,t R eectorn 7 Y erso.wteece 1 F user and 64eteres r ocast.se R G rweteormi hee 9h Peterms p,. des w1 t.e rewned perioAen v. es oppropr,ete to eccommodate 4 E nvvoamentes arm 15atq 9 A ntitrust Revow comtruents and to ref ser1 row sefar trution ur espertence.

5 Meteriese erus Pteat Protect.on 10 Gener ei 7907110/ M '

n tciasnan oi an expenmer.t w ah the.castar 3ystem buddup of te mpera t ure or pressure,

e. g., pr es sur e that ha, the potental foi breashing any pnmary barner buddup tn special beam port plugs.

b.

Irradiation of finely dmded sohds, hqwds or t u nsuon produst release from fuel,(2) any mteraction m egnment with the reactor sptem that could gases which are readily aubor ne if inadequ at ely

,a sely ;H es t any ergmeered sa fet y f eat ures or confined.

i o s t o.1 n acm features desuned to protea the pubhc c.

Degradation or failure of naenah mtended to,

lisuon pmduct release, t 3) any mherent feature confine expenments, e.g., by radution decompounm at im o a e x pe r im er i t h.i t could create beams, radiation nonmetalhe ca psules, w eld fa d ur es. gaaet !aiha es.

un onfired radioase materuls, and N) any ncessive mternal heat generation, or inadequate coo ng

n. l d s.

m poi *ntiAly

,J s er se m t er ut wn w it h concurrent d.

Degradation or fadure of ser.t systems or fdiei c get i nenta! and cperationM astmties.

tnstallations or uudequate sluddmg thneut.

or fadure d utety-relied e.

De gr a d a tion spe c a is teJumJ !acton, unadered mstruments cr control devices on exx. neno A un:

i ap >t the torgomg cnteru, san give nse to safety 1.

h}a.u;a; instabdity resultmg m

.N*

nWe na as tollow s movement of an expenment relative h its sLc!Jmc c,

by faulty stackmg of lead bask, by exceedug ti.ior -

i iui> m expenn ents wlu;h cooid cause a breach loadmg capabutties, or by capsujes bewmmg buoy ant m

. any of t he tuon product barners.

wat er.

h eas ovity eifects a rnuit a placemet.t er g.

Use of inadequate dn acs 'or stueldmg mJ e

a.

1 ; at monon of maten.d handhng experiment comporents or capsules fouow mg

enn Tal m exyrunait won tL c y me:a 1 - a example. to terced or irr adiatio ns.

nat ural cosa ecoun of Guids, phase danges. wemical or radwly t a amctation,, : met hamcal umab0ty.

4 F a c t ors relatmg to mteracnou w ith oth.

ts T hernul ettests on f uel w tuch alter i ical heat experunents or with operational actmtics.

e n. r u io n e: ten nanuer rates as a result u neutron a.

R e act mt y ettects of coi c une nt mm n,n das mt w ha% a. p r mu heant:g eleu ncJ neat mg, or occuning m two or more expenn enD aman,

of s want temperature or tiow by expenmert b.

Potentully adserse mieractu:ns re uitn g e vnents or f adute thereof due to heateg, radution the u2e of common electne cucuits and upphes and a

Ge da t. u, or r dio!) tic dnsociation.

cominon portions of Odid systems such as manifolds Wr e

hw al forces on tuel cladd;ng an ag imm coolmg w ater, vent, or drain systerrs.

c.

c.

Physical mierference by xpe nmen t s wd ite maru;da non of expenmenul compontna, : rom um used for suc h rurupulatten, frm t.bc..u su as, patterns of operauonal actmty whic.i could :mped-: m unrat>on, or dock waves, er from misula ansmg from present a safety or emerg ncy function, eg., blockmg ut Iunctonmg os.nalfunctiomr.g expenments.

acuss routes.

d.

Chemaal attack, meludmg conosion, resWteg d.

Creauor. of mdustnal haurds sush e the from the use m or escape of matenals mto the fuel generation or release of toxic or noxious matertah wroch s nuronment or accelerated corrosion due to eleuted could impe u the abihty of opera t ors to per f orm necessary reactor safety functions.

t e m pe r at ure s.

c.

Specui modes of reactor opera n on su l 4,

_. I actors tn expenmer.ts which could adversely affect pulsmg abnormal occunences in reactor operanor.. or enpnecied s.afety features or sontrol system features.

reactor accidents w hich could tngger radores in a.

Neutre fl u s pert urba tta ns a f fect utg experiments.

cahNations at wrety channels and/or rod woiths.

h.

Meduracal forces adversely affeumg slueldmg he proposed techmcal spcctficat ions llu t are or cont mement ansmg from causes as m 1.c. above.

relevant to expenments m research reactors should (!i c.

fLdution Gelds or radioactae releases from hase bases relaim; to safety conaderanons a.s requaec cxperunems wluch can mask the performance of an by j50.36(a), C) address subject areas that ue clear 5 o pe r a tio nal momt onn.,;

system mtended for the under the ducct control of the hcensee, and (3) ta' detection of fission piodact releases at early stages.

under the categones of lumtmg conditions f or operanor.

J.

Physical interference by e x p e n m ent survullance r e q u ir e m e nts, desgn feat w es.

oi mmponents with reactor system components such as a d ministrative c ont roi3, as specried in 550 36.

physical dispiacement of Situations may anse tn whi:n the utely andres o

w ntrol of sa fet y rods or c.ator sy stem stuellmg.

some uruqui expenments establish tl>e need to mnuder the effects of sush experonent> on the safety hnw ami F a, o its m ex penments w hten could create hmitmg safety system settmgs for reactor opeution.

s rJdWlopcal rKks dde to radiation [leids or unConfmed inon t a e mat enal.

Technical specirkations shou!d provide rea,onaNe (Ne af materuls which are or become fle x t b dity to perf or m e xpe nme nt s, mstal! new g

a.

demicahy u:Mahle or highly reactive or are sutgeet to expenmental f acihties, or change or remove trom use 39 7..'.7.

g

., p,.

4.=

i

uancs pre +.orly des nbed. Pr op ned technicA in reaetmty, woa:J cause a viol ion of a saf ety hma m en.dera t ens, as u nnst s pc c i fi c a t i o n s should address s a t e t y -onent ed et the mmmian shutdown marga.

nom functonal or end use (4) The rate of chang ut renta ay

,,t

.m >

1,coptions o: cxpenmentJ programs. On the other unsecured expenment, any mm.a >1e expenmem - any lund, all ufety wnuderanens impoot t ; each mdmdual cumbination of such expenrients mtrod med by armment proposed ;nust be enumerated and evaluated intentionally scumg the expenment(s) m monon rebt ne to Jetermme whether or r.ot thev fall walun the safety to the reactor should not exceed the capac:ty of the analysa f or rentor gerauun pesented m the SAR. In control system to prodde comper.sation.

addamn de proposed exp r: men shou;d be evaluated in (5) The sum of the magmtudes of the stat,<

deuil anJ ns exe,unon wntamed so a, to reduce any reactmty worths of all unsecured expenm;na whu h radunon d.ne to pLnt personre! and the public to the c oaust should net exceed th: rna sirman v iiue

.c low est pacticaHe le.d.

poter.t.al reacLvay worth authonzed for a sme secured remova Ne expenment or the mmunum shu t dow n C. REGULATORY POSITION margm, w hacheser is less.

The Jet y-o ns t e d snsideranons frem whnh b.

Thermal-flydraube Effec ts

,a

% Oc

'o evenm ws sr.mJ d be I ekde 31) tL is hd conditions of tne (I) b* "PC U

""I d DC C' "NI u

m

, e n ra n, ( 3 the materuh as a tual and pm enn A GemW et ted s

!mgn anJ condum i

rea tor ora cr t ni e x pe r unent s, and 131 the administrative com peents and ed a nL Norma 4. das c A anon con trols - nployed to nahnte, aatherize, and carry out should be made for the reutor at the extremes of t,

e x pe n m era s.

The

.o terul tlu t itUuw s is orgaruzed oper tmg margm. as defmed by inmtmg saf et s sy stem urWng to the above lla s cer.sideracr.s, but a is not sett mgs.

.J rlut ih.s be the orJy torraat acceptable for use' O bpenments should be destgrvd i pr esera mim foi popm 4 techn;al spes mancns. T he defimnons et the negatim of any Max pea % w reator coi hnt now cert un terms used m th2s section are g:ven in Appendtx cons:derations that have been used to defir.t or are 3'

impheit m the s.cety Imuts for the reactor. ( oi Um f.ow cons;dera tions shuuld melude potent ul blos age or 1.

Physical Condition.s redistribution and potennal phase charges m hqu:d wolant.

a.

Reaethity Effects (3) The surface temptrature ol the materut wtuch. bounds or supports any expenmerit dow.d not I reri a sa fer) sund:vm, toc pancipal concern exceed the lowest of the followirg, where appocable 1

(a) the uturanon temxrature of hquid n ilut csnuted with a net p muve racuuty effect, gg g,

g

,g whether it 's caused by the msert:on 0: an expertment havmg a positive reactaity effect er by the removal of (b) a temperat ure conservative y be:ow h a which the corrosion rate of the boundarv an expenment havmg a neganve reactivay effect. Credit nuy be r Aen for the operation of the reactor safety rnaterial at any su1 face would lead to its facure or, (c) a temperat ure conservat n e:) below system anJ engneered safeguards system ovided (1) they luse been des:gned ta stanJards

...d criteria th t at which the strength of the boundan matcrul estanhslung sery high rehabihty, such as ANSI N42.7 would be reduced to a pomt predictably leadmg to g

(IEEE-27%,(2) adequate quality assurance was provided m their constmetion and is provided danng operation, c.

Mechanical Stress EfTects and D) it ca n be shown that they can function independently of the assumed expenment failure mode.

(1) Every expcoment should be evaluated w ah All proposed transients should be analyzed to assure that respect to the storage and possfale uncontrolled telea>e a utety hma would not be exceeded.

of any mechanical energy.

(1) Every experiment should be evaluated for (2) Experiments invo.vmg potent u! for a

stane reactivay worth and its potential reactivity creating objects wrth substantiJ momentum (nussiles) os worth.

should be oriented in such a way as to minimve the (2) The potentul reactmty worth of each probability of damage to the reas tur sy stem.

secured iemovable expenment should be less than that (3) Matenals of cansuoction and f.tncanor.

salue of reunva which,if introduced as a posinve step and assembly techruques utih/ec m expenments sht uid tiange could re At m a transient tlut would be likely be so specified and used that as:urance is prouded uut to lead to doses m any restocted or unrestneted area in no stress failure can occur a: stresses : wic e tho se excess of the hmits set forth m 10 CI R Part 20.

anticipated m the man:pula no 1 and condutr o! tne

13) The nagnitude of the tutential reactivay experiment or twice those which could oesur. > a r e s u.t worth et each unsecured expenment shculd be less than of unintended but credible changes of, or w :tla the tlut value which, if mtroduced as a positive step change experiment.

2.2-3

(4) Prot ot y pe testin g under ex penment Irradiation of fission.ible materials.

tonditions should be employed to demonstrat: the excludmg the fissior.able material centent of fuel abday to withstand f adure.

element asse mbhes described in the technical specifications, should be deemed an ur.rev ewed ufety 2.

Material Content of Experiments question unless a speci0 cation meeting the abuse entero and its related safety analysis have been approved by the C ertam kmds of matenals which may be used in Commission. With respect to other radioactive materuls e x periment s possess properties with sigmficant safety specifications and safety analyses should be submitted im plica t io n s.

Limita tio ns on the amounts of sush that are representative of expenments a nh either the ma t er uls ca n hmit the consequences of expenment highest inventory of radioactae matenal s or the highest fail ur es. The matenal omtent of esery expenment probabdey for failure that could result m the escape of should be analyzed and bmited accor 6ng to the such matenal nto res:n<ted and unrest'icted areas. In clas,incations given below.

additien, recor ds shou!d be generatec and mamtamed to aUow for review to demonstrate tha t the rad m in.

a.

Radioactive materials matenal content of each mdmduaJ expenment does not exceed that aUowed by the stated entena.

(!) the raJioactne mtenal cor.ter.t. mcludmg fnsion prohts. af any ung!y encapsubted expenment T he se conside rations shauld not be should be : muted so that the complete release of all interpreted (1) to permit or enc ' ge any unnecessary ga seou s. ;w rticulate, or volatde component s from the i nt e n t io nal releases of

..oa c t iv e materuls t,

encapsulanon wdl not result m doses m excess of 105 of unrestncted areas, or (2) to reheve th" cbhption t s the equivalent annual doso stated m 10 CFR Part 20.

mimmue and control radiation doses in restucted areas Tlu s dose hmit applies to persons occupy ig (1) unrestucted areas continuously for two hours startmg at b.

Trace Elements and impurities time of release or (2) restricted areas dunng the length of nme required to evacuate the restucted area.

A reasonable efturt should t>e nude to idennt, (2s Re radioactive matenal content, including in advance of an expenment trace eieraer.ts or impunnes fission products, of any doubly encapsulated or vented whose actaation products may represent the domirunt expenment should be limited so that the complete radiological hazard.

release of au pseous, particulate, or volatde components

, Wi n Matenah c.

g from the encapsulation er confimng boundary of the.

experiment could not result m (1) a dose to any person Nuchdes possessmg high thernul acutro.

occupying an unrestricted area contmuously for a period o: two hours starting at the time of release m excess of.

absorption cross sections should be identified ar.d limited with respect to their quantity or method et 0.5 rem to the whole body or 1.5 rem to the thyroid or inclusion in individual experiments in order to contro!

(2) a dose to any person occupymg a restncted area reactmty or thermal effec's within the bmitations dunng the length of time required to evacuate the specified, restneted area in excess of 5 rem to the whole body or N reri to the thyroid.

d.

Eghly Ructive Chewa (3) For purposes of a ppiyin g the above The inclusion of ex plosive materuls in considerations, a smg!c-mode norniolent failure of the enca psula non boundary that relea ses au radioactive expenments ccnstitutes an urueviewed safety quesnon matenal mto the immedia te environ ment of the unless such usage has been reviewed and approseJ by the expenment or to the reactor build:ng, as appropnate, Commission, except that amounts up to b mdhgrams or should be assumed. The analysis should estabhsh the TNT equivalent may be uradiated or stored inside the reactor.mfinenent system in accorda nce with most probable trajectory of the mater;al, if any, into restucted and unrestncted areas. Credit for natural regulauxy p sition C.I.c.

c o n se q uence-braiting features such as solubility, Corneive Chemk21s e,

absorption, and ddution and for installed features such as filters may be taken provided each such feature is A hst should be prepared idenn'ymg materuls specifically identiSed and conservatively justined by which are chemically incompit ble with the reacio:

specific test or physical data or well<stablished physical system from the viewpoint of corrosian and which mecha msmt in addinon, w ith respect to mstalled should be excluded f rom any experiments or the use o:

gredit taken for their ef feetneness shoald teatures wtuch is subject to special scrutiny and control. Tins hs:

e depend d the adequacy of the related quahty assurance should be provided to all who use the reattor.

procedures undertaken, includmg the extent to which

'suneillance tests 9mulate the conditions to be met in f,

Radiation. Sensitive Materials praettee. If assumpnons regardmg atmosphenc ddution aie involved, they should not be less conservanve than The evaluation of each expernnent shoulu those uwd in the analysis of Design Basis Accidents, melude an assessment cf the consequence, of physwal or

\\42 156 2.2-4

the nmal dur.ge i.i t he mJIerui cor.te:.t a s a r esLlt of its h) Records should be kept of t! e hatety raduhon envuonment, particularly for Review G ro up's reuew and authorvation :o: eash presens e u.

a nonrnetalhc rnatcruh.

expenment or dass of expenments.

1 Hetts to he considered mcluJe the aheration (2) Operations Approval os cc p ada non of :neu tu mcai pro perties Jae to uhanon-induced decompisilmn, e g., of pLstia or (a) b ery expenment should base the pol > n cr s..md radiolytic pneration of excessive gas prior exphat wnnen approval of the litensed Senior pressure or explosne eas mixtures.

Operator in charge of reactor operations.

(b) bery person who is to carry out an g.

Flammable or Toxie Materials expenment shoulJ be certi: icd by the !icensed Senwr Operator m charge of reactor opnanons as to the hocedures co n t rol sh m.d mcer pra te sufficiency of his knowledge and trammg m pro.cdures a.ec ha m sm s for hanfung ar.d h: aung the quantit:gs of required for the sate conduct ot the expenment.

h.ghly llammabie or tox:c outenah used in experimental propams or used m the reacior room.

b.

Procedcres for Aethe Conduct of Experiments h.

Cry ogenic Liquids (1) Detailed wn t te n procedures 4o nd be provided for the use ur operation of each exper.menta!

Ihe uniusion ot cryogerm hquids withm the taahty.

Nolop al stueld of re.carth reac or w ou.d constitute (2) The Licensed Op utor at the onsole a

an um eviewed afety questiun uniess such usage has shou'd be nonfied just poor to movmg an) exper. ment been reuewed and apptmed by the Conannsion.

withm the reactor area and should authorve such movem en t, t

Unknown Materfah (3) Each expenment removed trom tJie.cactor or rea cto r sy st em should be subject to a redunon

% expenments should be pert'orrned urdess the moratonng procedure wh2ch antiapates expnun rates u u t enal tentem, with the excepuon of trace feater than tho se predicted. The results M such wn3nt uent s, is know n.

moratoring should be documented.

1

\\dminntrathe Controh of Expenments c.

Procedures Relating to Personnel Access to Experiments a.

Internal Authortzation (1) There should be a documented pr <edure (1) Evaluation by Safety Renew Group f or the control of usttor access to the reactor area to mmimke the likehhood of unnecessary exposuie to (a) No expenment should be performed radiation as a result of expenmental actinties and to w a bout reuew and approval by a techruca!1y competent mi-inide the possibihty of mtentional or unmientional S. lei)

Reuew Grocp or Com mit t ee.

Repetinve ob trucuon of safety.

e xpen men t s wnh sauty conuderapons m common rnay (2) Th ere shou!d be a wroten ruimag be :o ew cJ and appwed as a class procedure for the purpose of quahiymg expenme:ners in ib) Caterig for review Di an experiment or the reactor and ufety-related aspects of then acuuhes.

J.n s e x pe nmem s should irelude (1) apphcable including theu expected responses to alarmt regulatory untena, mJuding those m 10 CFR Part 20 and the techmcal specifications ar.d (2) in-house safety d.

Quality Assurance Program troen; ard 7u:es which have been estabbshed for facility operanos, mJuJme those which pvern requirements There should be a Quahty Assurante Progra:n to, e:uapwianon, senting, filtration, shieldmg, and cus enng the design, tabocation, and te s t. r 2 of smuLr exner; ment design conude ations, as weh as those expenments, me:ud.ng procedures f or ventunon or which gosern the qua!!ty assurance program required kinds and amounts of theu materu; cont fru s such as undei ; W 4.

those described m regulatory pos:non C.2.

\\A2 \\Si 2.2-5

APPENDIX A DEFINITIONS 1.

E s periment An e gnment, a, used h. em, K any the expenmern in monon rda: e to the reu

r. n, of the toNwme ur.entahun ah :.; eash t rajecto:,.md m une ances a.

An amt nit) ut di/ing the ratur sy stem or its w!%h can coume u.ternal thangt ss hasiier m.gsq s um p ment s ur the ne u t r o ns or radution l'iiimp c: vrod spaces or mohon of meLim al cenerved t!.erem compon en t s ror remov-ible expernaents the An e,,hutm

,r test o: a reactor systern po ter.ha: tutnity w. rth n equal to or greata than i

a ciibnce. or mamtenance the stanc reactnity worth.

o perata nal, s

Its !: hhc,

M.

e s p. r uu.:a tesa utni:3 whuh a n.

flemovable Expenment A r e;no, r

cq-m s

< :J ie ment or an; e x peri n.c n t, e x ; c:.mentai i Ja tonducted w it hm ta nment o. sten of de reactor: or co m po n en t ut ar.

e x per n.

nt.

othe um a i;

..!s ur of a of me!cregarg, permanently at'thed gpurtenans e io tio m t or iala '

su u. t r A s ap zis. scapsulanon a stem, w huh can reamHy be mt < y te, t.,s n meg ho mJ.:nes, ad sor. tamed Cutds mused one or mme tunes d aum de im

,1 t! <

or or se.ds reactor.

E xpentnental I aality A n e xpen r: ' :al laahty is

~' Secured E x pe riment Any x pe r m e ro any st nm me er A, ice w hNr. a inRnded to guide expenmemi t&,,

or

.f n

r rient, pninoa, mampuLte, u otb rwne fasihtae expenment a dec 1.u t o he se.

M cr m 2 -

acJ a nanpA ay or expernrents of smnbr sharacter.

p*ihon, it it is held in a cat, na y p s..n mianw to the reaa by mes h a r, cal mea n IL re a muy I @,iw Material b plosn e Aer i is a ny solid forces must be subuanniily peates than or

. in hqun! w hu h is c a t egor ved as a Severe, wiuch the expen ment mi#it be sub s ted by or (bageroas, er Very Ibngerou, hp;osan Hazard in hydrauhc, pneumahc buoyant, or other n.n es "l)ancereus Properties of Indatru! MatenaN' by which are normal to the operatmg emnonn eni ol l.

Sa x, Thad t d. t l w ),

or is given an the expenment, or by forces which car. an e.is a

!&ntihcanon of Reactivay (StaNhty ) :ndex of 2,3.

result of crediNe ma!funct.ons.

or 4 M the Nanonal Ftre Protecnon Aswaation m as pubhcanon M M,1% "!Jentnanon system h.

Static Reactisity horth L se I herem : h

.t at a ror I ire Hazards of Mate:iah, ' also :.amerated m reactmty wonb of n experanen: is th. nsolute the "Ha nd book f or Lboratory Safety ~ 2nd Ed.

value of the reacavity change which is n ca,urabie t 1971) pubhshed by The Chemical RubSer Co.

by cabbrated control or regubtmg rod mm;unson methods between two detmed termina; pmmon.s or 4

Mosable Experiment A mouble expenment is one con figura hens of the expenment. l or reooraMe which may be nuerted, remmed, er manipuLted ex pen m ent s, the ternunal po si t io ns are tuuy whde the reactor is entical.

removed from the reator and tuhy inseled or inml!ed m the normal f unchomag er ir t ended 5.

Potential Reactisity horth-The pinennal reactivity po srtion.

w orth of an expenmer.t n the maximum absolute ialue of the reactivity change that would occur as a 9 U n sec u re d Experiment Any e x pe r une n t,

result ot mtended or anacipated changes or credible e x pe nment al f aa ht y,

or com p me nt or an malf unstions that alt er experiment posinon a experiment is deemed to be unsecured 4r a n not t o n fig u at i.m.

and when it is not secured as defined in 7. alove.

Monng parts of experiments are deemed to be The culuanon must consider possible trajectories of unsxured when they are in motion.

142 158 2.2-7