ML20034A376

From kanterella
Jump to navigation Jump to search
Responds to J Mccrery 900206 & 08 Ltrs Re Proposed Gas Centrifuge U Enrichment Plant
ML20034A376
Person / Time
Issue date: 02/08/1990
From: Carr K
NRC COMMISSION (OCM)
To: Mccrery J
HOUSE OF REP.
Shared Package
ML20033G548 List:
References
CCS, MCCRERY-900208, NUDOCS 9004230145
Download: ML20034A376 (10)
v • d • e


Text

._-

f ENCLOSURE /1 RESPONSES TO QUESTIONS ON PROPOSED URANIUM ENRICHMENT' FACILITY-OUESTION 1.

Is uranium hexafluoride highly toxic ~ as has been suggested?-

What precisely are the effects of human exposure to uranium 1 hexafluoride and in what concentrations would such exposure endanger life, health and property including-livestock?

O ANSWER.

In general terms, uranium hexafluoride is considered mildly. radioactive and toxic. However, when gaseous uranium hexafluoride is released into air, it rapidly-y reacts with moisture forming hydrogen fluoride (HF), a corrosive chemical compound which can cause irritation, burns, pulmonary edema, and, with sufficient exposure, death. The other product formed by the reaction between-uranium hexafluoride and moisture is uranyl. fluoride', which is also mildly i

radioactive and chemically toxic, but not as immediately hazardous as hydrogen fluoride. Due to the prompt reaction between uranium hexafluoride and moisture in most situations, any effects of human exposure resulting from loss of containment of uranium hexafluoride would not. occur from the uranium hexa--

- i fluoride itself, but from the products of the reaction, hydrogen. fluoride and.

l uranyl fluoride. The Connission considered the chemical effects of these i

reaction products in proposing the attached design guidance standards for uranium enrichment facilities (53 FR 13276).

In the event LES submits an application for the proposed plant, the NRC would address these concerns in its l

review and ensure that the risks of such exposure are sufficiently low before issuing a license to construct the plant.

9004230145 900328 PDR COMMS NRCC CORRESPONDENCE PDC

l-

)

QUESTION 1. (Continued)-

- l The NRC is presently preparing a comprehensive report on the chemical toxicityj

-I of uranium he'xafluoride. The report will cover the effec'ts of' exposure to.

hydrogen fluoride and uranyl fluoride. and the concentrations:at which. the-effects' occur. We will. provide you a copy of this' report when it becomes -

available.

j I

1 t

'Y L

l' T

i

d A

?

UNITED STATES NUCLEAR REGULATORY COMMISSION RULES and REGULATIONS-

m.. C,tms..

.g.,,s.g

,0

_ g.t REGULATION OF URANIUM ENRICHMENT FACILITIES -

76 PROPOSED RULE MAKING

$3 Pa 13 rte

  • w asms atra/se Pea PueTMen IsepomaTteel Ma4Tt C**a== ewee esseen 7/81/91 A. Thomas Clark.lt Offles of Nusisar detage a the y,epenedq i

> Commem peces estended to 1o/as/se.

Matenal Safety and Safeguards. U.S.

Deprincipalesapementof the Nuclear Regulatory Comsussion.

$[ red

""8

]

to CFR part 73 Wag'on.DC 305s5. telephone (act) which might be emblest to regulation bg Megulation of Uranium Eartshment Fm suppteaseerrany esopoessaftest the U.S. Nuclear Reguistory Commission. The NRCstaffhas aise been muung wie som prWete -

Backyound asency: Nuclear Regulatory Comaussion..

A uteruurn enrichment facultyis e compames. all of which are empreestas an mierest in engaging an armarum actioet Advance notice of proposed

,g$",,,'hd'fl"'d bY enn t underNRCheemse and.

rulerrielung.

, Ad se amended.The regulabons which j

svensaav:The Nuclear Regulatory currently govem the Commission's -

is advance notice of proposed Commission (NRC)is considerms the review and evaluation of an applicah.oa rulemaking to being published to provide eddition of new regulabons Title to

. for a production facility are contained la Se public, th Depwusent and he r

(Part Fe) foruromum anneluneet to CFR Part so.Part 80 provides as prospechve reguised heatry n facuities.The construction and speanc guidance for bcenaang ureatum oppwtmity 2 provide dwies and -

opersuon of such facilities currently ennchment facilities. De NRC staff has -

reconuruneHons 2 h P6 u -

wculd be licensed pursuant to the never received an a licanon fora Se subket d wensam earmheem Commission's regulations in 10 CFR Part uraniuso ennchmeni scility.De staff.

licensing.no NRCsteRhas developed 50 for other production and utilization however has licensed faculties which dance.provided below.which weeld facihtles. such as nuclear power plants, process wenium hexafluoride, which is

' orei to fondeuse fw e new rde,if I

In this nonce the Commission presents the pnnetpal chesucal form of urentum initiated. Because rulemaking may take.

its current analysis of the appbcability used in the gaseous dihalon procese sevwal yure,ud appheaume for '

i of the existmg regulations.in to CFR and the centnfuse process. the summ pgy,,,,gg g g Part 50. to areruns ennchment facilities methods used to produce ennched the NRC staff will proceed with the coNenaw

- mvkw d appuuhme ud hW u

ever,other metbods for serialdag e

separate set of regulations for uranium uranium can be and am being be h10 ennchmentlicensmsis deelreble.

developed. For example, for seven.al CFR Pan 80 and he gudeHase ne GeneralDesign Crt16ns presented years the Department of Energy hoe contained la &is advance nouse sablest in this nonce may be proposed for fostered the development of an Atende to any M* ions which migh he codificauen in the new regulation. These Vapor Laser footope Separation (AVLIS).

W bued en comment enterie may also be modined, depending Process for enriching wenium.no t

on comunents received in respease la sonunercial use of these methods would As nokd above.seneetmgelations 3

this notica and span further staff also be subject to segulaties by the already provide a framework forthe analyste.

Commission, licensing m*w of peducties feeliition.

$y"((esscomewn ter Energy the

~

Ane submaasee thle date wdlbe seasidered ifitle 4bl.ished a n,oose.la the F feview should not held up the '

,reco.i to do.e, b.t es.ur.nos o, rm Ru m,e e.g em-a. m -spaan *-b-ed consideraties taasot be gives exceph as emprmione oflakmetfor pa:Wdan e@h to comments reestved on er before this la the Departnent's eranium enrichme program. In additica, on Febnnery v. nt Uraalum Henafluoride and puhte

date, sooneesem Adedfsoeunene, erne 2ser, he Departeem submited a soport -

Heale and Sdaty W Usamism Secreuryof me wa='-- U.S.

to the Congress on the privatisetten af Enrichment e

Nuclear Regulatory ca=='==aam DOE's emains arishment enterpsies.

M W es @ W weema Weekin D*

D+=gton DC30ssa, Attentient

,,,T,g,y'd,eet,eeim,,sa,,,

g

. -d i *e =m*

,roose ss e,r.e.lossible Ne

,0*imi:"A:"N #!o"chful" sae-ee re,::=3'-',;l:~,e,s,2,na,,dM:1:targ'2ll::" h a

MD. betwees F:30 a.m.and 4:18 p.sa.

gg a me,,

w.

Examme copke of assuments reesives' enrich the uraniuss solising the ehemiset at: the NRC public Docurnent Room.

would be made by he Deparamat at fona of uraniuse hm==dh===tda.The"n 1717 H Street NW. Washington.DC the end of March on the redruchering of principal reason for seing this forn ie < -

the enrichment enterprise. On March 31.

that the compound le a ses at.

1987, the Department provided fureer reasonable temperstures and preneures.

The rolease of uremum hazaGueride-76.PR.1 Septemberso,1ses i

m

.m..

l l

,4 PART76 PROPOSED RULE MAKING from process equipment is a more for chemically fonde eSeets which,if 50.48.80.47.30.48.30.40.34154.

severe chemical (tomicologicall hasard anceeded, coold caese trenesent er 50.80. 80.01. 80.8L 80J4. 40.7150.73.

than a todieuon (redsological) basard as pervoament intery, and 40.100.

discussed below.

De staff consioers that an mtake of Appendices A. C. E. C. H. I. I. K. L. M.

l If utenturn hexafluoride is releasee.sM about 9 mg of uramum is the level at N. O Q. and R.

the atmosphere it wdl roast which slight transient kidney miury is exothermally with moisture in the air to expected to occur and an intake of 1 Sections not applicable for reasons produce hydrogen Duonde (HF) and about 40 ma of uranium is a reasonable othe thas t*a uranyl Duonde (UO.F.). Both esumste of the threshold level et which assese

-messes compounds can be tosus. Hydrogen permanent kidney damage may begin to eats Enemomensast Faserei fluorida is a corrosive acsd vapor which occur (see NUREG-11401.8 Derefers. for essamme t

can severely damage hasus, especally design purposes the staffis considenng som Reneese and the moist tissue of the jungs tf inhaled m the calculated maximum amount that se erwisemmoissa sufficient concentrabons. lf uranyl.

adult at or behond the controlled alte AFD'"d* D Ra'"*8 fluoride is inhaled or ingested, it can boundary could inhale. as a result of Appemen F nesmemmes sesy cause internal injury to the kidneys and credible accidents oflow probebility to Appemem p Ressnes aufficient quantities can be lethal be in the rence of a to 40 mg.Facilihes la order to demonstrate that the desymed such that maximum effects

5. Dose Sections of 2 CPR platt30 chemical, hazard of uranium would not exceed this range should not which Apply Complesely hexafluonde reacuon products ist have a significant adverse effect on the exceeds that ofits radiation hazard one liealth and safety of the public.
1. Sections relsted to administrative might consider the followes example For exposure o MF. levels which procedures: Section 80.1 through SEtt related to lust one of the reaction cause permanent injury are not clearly 50.1150.13. 30.20 through Saat 30Jeb.

products,uranylfluonde.lf a person defmed. Exposure io HF at a 50.37 through 50 40. 80.41. 80.4L 30.45.

inhaled sufficient uranyl Duonde as a concentrauon of 100 mg/m 8 is 50.50 thmuch an&L 80.86. 30.48, stas, result of bems exposed to a plume from esumated to be unbearable for one 50J0. 8038. 50A0 through 50.110 essept released uranium hexafluonde (ennched mmate. HF at 13 mg/m would be 50.109.

a to six percent U-235). such that there detectable by smell and cause possible

2. Appendia B.

was a 50/50 chance of survivm3 (50 trntation. Above 26 mg/m 8. MF would percent lethality) the chemically toxic cause trntation and possible health -

C Those Sections of M CAR PIsrt30 effects. that person would receive only effects.8 Therefore.*the staficonsidere Wh/chApplyportially about 15 rem committed (lifetime) total that 26 mg/m 8 HFis the tria=i==

body dose equivalent or about the concentration that a person at or beyond

1. Paragraphs (3) and (I) of $ 30J3 do maximum amount a radiation worker the controlled site boundary could be not oppIy: all other paragraphs apply, can receive in one calendar quarter (3 '

exposed for ahort penods, as a result of.

1 Section SE334 mfen toinfensation i

rem). Obviously, even further chemical credible incidents oflow probability, requested by the Attorney General for injury could be sustained by the same Enrichment facilities designed to limit antitrust review. Paragraph (cl es i

indMdual from the hydrogen fluonde any release to a value below this reserved. Paragraphs (a). (b). and (d) produced during the same release of reference concentration will not have a apply only to nuclear power reestors, uraruum hemanuonde.

significant adverse effect on the health paragraph (e) applies to a ursaism Design Guidance Staadards Based on and safety of the public, enrichment application.,

Chemical Effects Analysis of the, Applicability of 18 CFR Beeed on the above discussion the Part 30 to Umamm Enrichment Ap a

nical den.

applies in part to a uranium enrichment staff will be guided mainly by the De NRC staff has reviewed each plant. De extent to which paragraphs of chemical effects of rescuen products section of to CFR Part 80'to determine i 50.34 applyis discussed below:

from uranium hexaGuonde in its outlook which sections do not apply, which on design for the protection of the health sections uriu apply,includmg the astere '

A Pl8N8NPhloAPalisulsoryaspery and safety of the public.no Atomic of their applicability. and those which Ar'olveisAaport Enargy Act provides authenty for the will apply la part.This analysis is based Th foHowing regraphs putain Comaussion to considerany on the staff's lodgmentas to techaiaal f*rincipallytonu eiarh wer plaats:(1).

'Wi,5's",an'a's'Edd

Gyl"fm7%',ft"basise,,

E$qE n(

',ge, d

characteristica oflicensed acerce or the NRC staff's approach to licensing of o

para 8r8pha skald be plepared special nuclear materialauch as

  • urannanennchmentfacilities, fr po A~ U M Aart30 m

at w p safe sIl to used or gj,$

the evaluation of altasand designa wsth S. pbmpsph (b). Fino/Sofsfy Ane/peis -

respect to potentialaccidents at

1. Sections and appendices related aspg,g uranium enrichseet facilities. Daae only to ancisar reactorlicensing:

proposed reference values for UO.F.

Sections so.34a.80Jea,snes,gnet.

The following paragraphs pertain and HF. besed on cheedaal toxicity, are yrincipauy to nuclear power plasne:(th intedned to be comparable with the ecosis.ormasc.nes em Ml3)(1),(4).(8)(v) (6)(vilk andl9g,

original intont of the resetor alting to sepaansasem er a --- y be paresses bem Placementparagrapha rela

- us ceasemem crtteria in to CFR Part 100.La a whole.

Pr*"me omma. p.o. asa spear. weemasism oc to the intent of these paragrapha sheeld body radiation dose guideline value

'm"",,"w"7 M

  • d*,',"%,",gg be prepared unless they are saly-3*"* **

fined at the polat where it is believed seres ases.sweene6s. VA anos. A esey es eine.

applicable to nuclear power planes.

ff$c es to e

thus

  • s Doommem mes that O*~s'"w* e (CAPhyel8elSecomifF78pp

%$1c"m'.,,,8'",,,

proposes using quantitles or This paragraph applies la its entirety.

j concentretion values which are at the ca

,..,w w ur..,sur.H r

lower range or aversgethreshold level em*=ne. son asn an.s.3.ny asas. yssee April 29,1988 76.PR.2

1

?

l PART 76 PROPOSED RULE MAKING l

D paraprophidl.Sofspuords T. misting Regulatory Basis for Applying Droff Genero/DesWa Criterio.fer Contsnpency Plan Safeguards to Enrichment FacGiues UnnmaE,nrichment his parepeph opphes in its entirety

1. Section to.34tc) requires that each The staff has preputed draft General f Parapsph Iel apphes in sie entirety. appiscent for a hcense to operate e Design Critens Ior uranium ennchment F. parsgraph (f) does not apply.

producuon or utihtation facahty must which are imended to apply to any C. Paragraph (3) does not app 1y.

include a physical secanty plan se port techmoue used for that purpose. These

4. Section 50.38 applies.escept for of theirappbcauon.

draft General Design Critene have been

3. Secuon 30J8 requien uch bolder drawn from several sources. including fa ue uns en ens. A trucuon sud W

).g mques by g and thosela replacement paragraph related to siting

  • [$" d use in to CFR Pare no formuelear power rmatso on Fo
71. perm planes. ney am intended to pmWde
8. Section 50J6 apphes in part to venfication thereof by the latemahonal general guidance as to topics which Atomic Ene'EY A '"'F. and take such must be considered and the overeu uramum ennchment.De followmg 8

paragraphs related to nuclear power

',b

",h"g Tg*

criterios. De actual implementation ci 8

performance objectives related to each plants will not apply:(c)(1)(1)(A) and gp (c)(1)(ll)(A). Paragraphs (c)(1)(1)(B) and Agreement. in the scanner set forth in the generaldesign critena wtH be (c)(1)(li)(B) apply to fuel reprocessag il 78.6 and 78*11 through 78.14.

Mmat &an in the case of assinar I

plants. but could equally as well apply

3. Section 73.1(h)(1)(1) states that Part power plants and wiH depend upon the to uranium ennchment plants.

73 presenbes requirements for the specmc procosm and dge being Paragraph (c)(2) applies to both nuclear physical protection of productoa and considered and wiU be aamaaa-ste i

l power plants and reprocessing plants.

uuhsstion facihties licensed pursuant to d es salg funcuan of tesped8e This paragraph could apply to uramum Pan 54 strucmres, sysums or P ennchment plants in the same manner

4. The meterial control and related to those designs. As exponenos is gained on the apphastion of the as it opphes to fuel reprocessing plants.

secountability requirements of 8 70J1(bP criteria. maoifications may be deemed l

All other paragraphs apply to uramum (1). (2). (5), and (6). I 70.81(c) and j

ennchment except (c)(7). which is 70.51(d) pertain to enrichment facilities.

appropnate to the cnteria.it is also specific to nuclear power plants.

5.The Material Control and expected that designs to implement the 1

6. Section 50.54. " Conditions of Accountability Reform Rule, as entens willin mostinstances not be comparable with that of nuclear power l

l.icenses." applies in part to uranium contained in il 74A1. 7443,74A5. 7447 plants. In particular. the ranaammana ennchment. Paragraph (a) applies to and 7449, pertains to faculties riuclear power plants and fuel authorised to possess five formula criteria might apply to only lindeed areas reprocessmg plants, but could be kilogramt (or more) of strategic spedal of the plant where significant teleases opphed to a uratuum ennchment plant.

nuclear material except for reprocessing could occur which, in tura, could asuse The following paragraphs apply to a plants and nuclear reactors licensed exposurein excess of the reference uranium ennchrnent plant in their pursuant to Part so.nus, this rule values for toxic effects.

entirety-(b). (c). (d). (e). (f). (3). (h) (1).

would apply to an enrichment facility As discussedin a previous sectionof (ll. (n). (p) (v), x followng pereg(ra). (y). (aa), and (cc). The that handles or produces high enriched this notice, the current t ^ '-

phs apply only to uranium (but not those limited to low using the chemical fortn'utentus riuclest power plants:(J). (m) (o). (q). (r),

{s). (t). (u. (w). (3), and (bb). Paragrephs enriched uranium production).

hexafluoride, would be of more (11) and (k), apply to operator licanstng

8. Sections 70.81. 70.87, and 70.84 (in Immediate concern. In this section we and may or may not be appucable to their entirety) pertain to any fadlity provide these draft criterta as bened ca urentum ennehment, authortsed to possess special nuclear the NRC staff's current considerations
7. Section 80.88. " Conditions of matenal to moderate strategic as to potential hasard to the health and significance, except that nuclear safety of the public.We note.in construction pennits." applies in part to reactors Ucan' sed pursuant to Part so are particular. that the draft cettene uranium enrichment.The following parsgraphs apply in thsir entirety to exempted from Il 7037 and 70.58. Thus, presented for design for effectsof an enrichment fadlity that bandles or natural phenomens are characterised by uranium enrichment:(a) (b). (c), and d).

produces uraniwn enriched abovela return periods. These criteria shooid be t

Paragraph (e) applies only to nuclear cercent butiess than 30 percent (in the by competent authorities relate usedla conjunction with date power plants. Paragreph (f) applies to (Nt38lootope)would be subject to both nuclear power plaats and fuel Ig 70.81.70.57 and 7n88.

design vertables such as ground acceleration and wind speed to return andcoifd pbly oa Emisdag Safeguanie Regulances het de a

ennehment p t.

    • t Apply to Enrichuneet Fedlities but Genese/ Des /gn D/serier
a. Section 50A7."Issuanos of I

b An application fora constraction

^

opereting license." applies is part to uranium enrichment. Paragraphs (a) and yg perinit for a uranium enriebnene facility (b) opply whoHy. Paragraph (c) epphes 1.Section 74J1(i.e the low Enriched criterie for the proposed These must include the principal only Io nuclear powerplants.

Urantura Reforse Rule) contains material GeneralDesign Criterie s.Section soft. 4faintenanen of recortis, making of reports." Paragraphs control and accountability (MC&A) minimuni requirements for the psincipal regulations for facilities authorised to design criteria which are====a-ste (a) through (d) apply wholly. Parsgraph possess special nuclear material oflow with their safety function.These-(e) applies to nuclear power plants, bot could apply to a utsalum enrichment strategic significance, but speMArslly Ceneral Design Criteria may not be plaat.

exempte production sad utilisatica complete. Any omissions de act sollee's faci!! ties licensed pursuant to Part 80.

the applicant from the requirement of

.1 76.PR 3 April 29,1988

e PART76 PROPOSED RULE MAKING l

Primdmg the nuessary safety featurn have safety signinosast shallbe for accessibility to the equips.ent of '

in the dessen of a specific lecility. !n protected spamet dpiamic effects, onsite and available oilsste emergemey,

additson to satisfying the General including effects of missiles and

. facablies and semese such as keepstals.

Design Critena. the applicant must; dischartmg fluida, that may result from fire and police oepartments, ambulemer (1) Design ogsmet me loss of natural phenomena, accidents at nearby semes. and otner emergeasy armaams confmement capabilley or other industnal. military, or transportation

" M.""N N

capability which would jeopardise the facitttits. equipment fauers, and other health and safety of the public where similar events and conditions both Aasdents, on#&sectese Ageanet such loss of capability results from any inside ead outside the facility.

sinal failure a systems having safety p,,,,,,,,'n Against Fires and Emplosions O*'I8'

'%""fie.versity in eysiens Si,u-os. sysiems. and compemens m s-'a==t 'am= =st w commensurtste with their safety which a:= deteramed to have safety detsned a set he sneenwoman of,

funcuen:

sipraticance must be designed and hasareem maiensis at or beyond he ~

(3) Mmimise the possibluty of non.

located so that they can conunne to boundary of te encimien me undw random. concurrent failures of important perform their safety funcuens effectively. nonnal opwoung consuesa, h as elements in protection systems:

under credible fire and emplosien.

Iw as is mesonably achipeble, aW2) i (4) Provide design criteria and design esposure condiuons. Non. combustible.

as the resuk of design basis assideais.

q bases for resistance of parts of the and heat resistance materials mest be iniele&ns how of tw proba

,abau facility to upper limit accidents and for used wherever practical throughout the. am emem any undue nok to to mammur.tprobeble natural phenomena faculty. particulely in locauons vital to ; and safety of the public.

when the conuquences of such events the control of hasardous materials and

. (b)De design of the facihty meet be -

endanger the health and selety of the to the maintenance of safety control adequate to provide protesties public; funcuens. Explosion and fire detection. _ wwm utmalmais est soeuk.

(5) provide adequate protection for alarm and suppression systems shau be in te mium of quanuk and -

employees from hasards which could designed and provided with sufficient concentrauons of hasardous material affect their performance of actions capecity and capability to minimise the - which may be of public health and requimd to protect the public from adverse effeets of fires and explosion on safety sismficance, ne design basse for.

exposure to hasardous matenals.

structures, systems, and components such events shall take into essonet their nere may be some facilities for which are deteramed to have safety historic frequency and severity la the which & General Design Critens are significance, ne design must include mgion of the site sad es poteadalrisk not sufficient and for which additional provisions to protect against advene to public health and safety. includlag the cntene must be satisfied in the interest effects that might result from either the innatory of hasardous meterials in the of public safety. Also some of the operation or the failure of the Are facWty and the site east the preuimity of General Design Criteria may not be suppression system.

the populadon at risk.no typeof swam mots to be considemiwiu vary necessary or opbropnate for a specificSharing of Structures. Systems, and armong sites, however.

I _ " --

(

faculty.For fact ues such as these.

Componente tornasoes.and floods abau be departures from the General Design Criteria must be idenufied and justafled.

Structures. systems, and components - considered in au cases, as desertbed la which are deternused to have safety Paragraphs c.d. and a below..

Cenem/ Requirements significance must not be shared between. (c) Historical informauos commerning Quality Standards and Records an ennchment facility and other _

the regional seismicity interpretod ia fac81 ties unless it is shown that such light of regional structural and.

Structures. systems, and components sharms wiu not impair the capability of site eologicalconditions be used which are determined to have safety b unchnum facWty a pufamis f

umuning h maximumvers significance shall be designal.

safety funcuens, including the ability to =

d motion which reasonably coE fabncated. erected.and tested in return to a safe condition in the event of -

pected to affect the site during te accordance with the quality assurance anacmdsat, opere life of the facility.Seekas l

enteria set forth in Appendix 5 to to

  • 8 wiHhan a

,,.,, g, gdy gsoo' years. Ibsign CFR part 50. Appropnato records of the Proximity of Sites design, fabricauon, erection, and testing An enrichment facilitylocated near earthquakes of shorter retura period of structures, systems. and componeata other nuclear facillues must be designed may beproposed,and shau be justiBed which are determined to have safety to ensure that the cumulative effects of aroughconsidentionsof thee significance must be maintained by or their combined operations wiu het inerenwatal risk to publis healtin and under the control of the licensee

, constitute an unreasonable risk to the safety relative to the eco. year interval.

throughout the life of the faciuty.

beslthandsafetyof theymbila-(d) Historicat informanoa semeerains protection Against Environmaatal Testing and Mainsananen of Systems the agional andlocallacidense and -

l Conditions and Components g of tornadoes shaRbeused to IN deterndnedto de eN't bN tye

'8*'i'*"

  • d* 8" pon at canoa have safety significance shall be must be designed to permit inspection.

(

daigned to withstand the effects of. and maintensane.and tesdag.

puesmen"u

  • men es me et nemmmamess >
    • "" openedehesimniendseemosy i

l be compedble with,the environmental conditions sesociated with operation.

Eawtgency Capability g,,s.SaO*"mese aM'..',.

cs maintenance shutdows, testing,and Structures, systems, and aampananen Asches techaniser CauenL Mc ansk 488-accidents.

which are determined to have safety 89"*=' 88 C"a*"""emessiamuser.

(b) Structures, systems, and significance aust be designed for yY,'n,",n ummeNem 1,

components which are determined to emergencies.De design must provide se es,emed esse April 29, %88 3pg q.,

o, n m.

l I

i

l PART76 PROPOSED RULE MAKING l

i tornodo shall be determaneo consioennt propaystmg failure, or gross rirpturehocea8 Safety both the tomoeo frequency for the retrion m which the facility is located. as cunns the desagt. life of the feelhty.

well es the frecuenew of occurrence for s Compartmentalssataon of prosses Prometwa $ yams 1omaco of a gwen amensity witmn inet inventory, wn' en used as a motbod of (a) Protection systetas shau be NF8onM reoucang the amount of hasardous designed (1) to iniuaw achon that will 4

le)The desism basis Dood as e meienal capable of besng released by assure that specified acceptable minimum shall be the Standard Project any smale orlocal fauure of prunary operettog design hans are not escoeded ylood as dermed and in common use by contamment. shau be consideredin as a neuH of opwouonaloccutunoss the Corps of Engmeers. The Standard destFn as a means to effectively leolate and (3) to sense potentially basardous or 1

i Project Flood is the floor resulung trore and contain the process inventory in occident conditions, and to activate the most severe Good.protecton rainfall module umu mmws fw au systems and components regelred to depth. ares.durstson relationahlp and MmnsW nonnelor ebnormay ensure the safety of operating onnel tsonyetal pattern of any storm that as

    • ""8"'"

and the public or to give audib nd i

considered reasonably charactensuc of Ventaletion Systems in a timely manner to ensure soeb risual alarm ao that action can be taken the region m which the watershed is located. If snow melt may be Ventilation systems required for the safety. Systems and components abau substantial. appropriate amounts abaD coorment of hasaidous matenals be activated autornaticauy where this be included with the Door producing shall be designed and appropriately mode is compatible with the aefety t

rainfall. When floons are pretjommantly tested to ensurlr their opetsbility daring requirements to be satis 6ed.

t caused by snowme the Standard normal or abnormal conditions. To Ib) Protection systems shaB have Project Flood shall.. based on cnucal accomplish this obtective. these systems reliability and in sim testabuity. %e combinations of an +. temperature.and shall be designed to meet the followmg design or prosecuon sysment abau wate: a requirements:

consider altemate methods atleast (f) t _

ystems. and components wmch must withstand the (a) The desired ventflating airflow sulf cient to ensure that (1) no single design basis eenhquake to meet the direcnon shall be maatamed under failure results is loss of the protection l

nquirements of paragraph (al shall t>e operstmg and accident condidoras.

functions and (3) removal troen servsce designed usmg a sunable dynamic (b) The ventilation systern shall of any component does not restdt la loss enslysis or a saatsble quahfication test accor.unodate changes in opereung of the protection system such that it wiu to demonstrate that they can withstand conditions, such as vanetions in operate with acceptable relisbuity.The the seismic snd other concurrent loads, temperature or pressure. and shall be protection systems shall be designed to eacept where se can be demonstrated capable of safely controlling aH off.

ermit the periodic tesung of their ctions while the plant is la operation i

asses that could be associated with to detersune competency to perfona otho p vidas a le numal e accident condiuons.

their intended safety functione, amsenstern.

(s) Conservenve udmates of (c) The contamty of necessary (c) Protection system shanbe atmosphent drepersion of hazardous ventilation shell be assund by means of designed to fall into a safe state or into j

attemate equipment. fail.sefe systems, a stata demonstrated to be seseptable matensi besed on locAi! meteorological or other provisions.

conditions shall be used to evaluate the on some other defined basis if j

impact of normal operations and of (d) Prov6sions shall be made fbr conditions such se disconnection of the design basis accidents to demonstrate testms. during normal operations all sysken. loss of enngy w modw pown.

compliance with the requiretoettts of component functions havmg safety or admse enwonments am paragraph (s).

sigmficance to the extent necessary to experienced.

provide reasonable assurance that they Confmetoent Barriers and Systems pufem their design safety lastrumentation and Control Systems Instrumentation and control systems Confinement systems shall constat of (e y"**

e don syswtas shaB be shall be provided to monitor vertables confinement bemers and eqmpment which controlagamst the release of desW W pennit me cont 2ned and operating systems that are hazardous matenals to the envitorunent. occupancy of any and all areas where significant to safety over anticipated The confinement aystems which are such occaspancy la aquired for sermal ranges for normaloperatiost.for sigmnant to safety shall be designed to plant paratioca.for safe shutdown.and abnormal operelion,for accident protect assmet the effects of accidenu for maintaining the facihty in a safe condidone andforsafeshutdown.

orextemalnetwalp8m and shau shutdows condluon,noirdesign abau These systems shah ensure adequate be fabricated. encted, appropftstely incimle prokedon against he intake safety of process and utdityservice tested.and mentained to ensure and accumulation of basardous operadons in connection with their prsvention of abnormalleakage, rapidly metertala. Tt v design shall also permit safety funedon.The variables and the timely and safe evacuatloa of systems that req. uire constaat

% %,,,,,,,,ay % m personnel from su areas.

surveulance and controlinclude procese royew sus.om.T.na.em emais (f)Ventdauon systema chau be systems heving safety significence, the v in wroscm e.m-samencesse.es te, ow unswd suu.-Asenne end cent or beenaan designed to confine the basardous overall confinement systeen, mesw weid, g*"gs@ "O^^ ***Fg

  • materials during nonnel operstics and confinement barriers and their to ensure that the release of hasardous sesociated systema, and other systects Am s entrein weis,se sweiiknens m,n materials in the affluent gases is as low that affect the overen safety of the plaat.

senawsu est rN1,4m.Opetertem tomiamwmse as reasonably achievable. Such systems Controls shell be provided to maintala w t.v.ne nesaseet.wumaclot-shal] also be designed to retala theie these vertables and systems withis the Pg* "M%"u",,d ",,,",,"g,,*,y, *I confinement and separation capabGity prescribed oper$ ting ranget anddraE normal conditions. InstrumentatNo and meme ep e.re se m **r w r=*e *=estestser wu's to minimise releases resulting from as control systems shall be designed to fdG accident condition.

lato a safe state or to asscene a state 76.PR 5 April 29,1988

e a

PART76 PROPOSED RULE MAKING I

demonstrated to be acceptable on some electnc power source or arcuit rehable (b) the equipment contaming the fasile 1

other basis if condmons such as and timely emergency power wiu be matanolis located behmd su!!smaat disconnection. loss of energy or motive prowded to instrumenta, confeement bamers and stueldang to roouce the power.or adverse environmeets are systems. utility service systems. and probability and extent of accidental s

eApenenced.

process systems in amounts suffacaent to contaramation of the environment and Separation of Protection Systems and aHow oowetions to be shut down safely accidemal redisuon exposure to Control Sysums and to be memteined m a safe shutoown personnelin tne event of a entscahty condition with all safety dewees accident.

nunual safe shutdown WM from ont s sie to i e a a

Ancillary Criteris for Nuclear Criticality change or failure m a control system

&cherCrMcoMofey Safety leaves intact a protection system with Safety Margas (a) Process and storage systems shall acceptable reliability and independence The desip of procen and storspe be designed to ensure that no "9"*****

systema shallinclude demonstrable mecnanisms that could cause Control Areas maryms of safety for the nacisar segregauon of fissile matenals saa be A control rons or controlareas shall enucality parameters that are present in components whose nesleer be designed to peruut occupancy and commensurau wi h the uncertainties in enticality safety is dependent se the -

actions to be taken to operate the plant the process and storage conditions. in homogeneous distribuuos of flesile safely under normal conditions and the data and methods used la d

under abnormal or accident condiuons calculations, and.in the nature of the (b) Components whose naciser to either operate the plant safely or to immediate environment under accident criticality safety is dependent se a -

shut down the plant and mamtsin the conditions. All process and storage limiting concentretion of fissile material plant in a safe condition.nere shall be systems shall be designed to be shall be designed so that either(1) en allemate system designed to allow memtained subentical and to ensure mechanisms that could cause entieel 4he plant to be put into a safe condition that no nuclear criticality accident can concentrations of fissile matenals are if any one control room or control area occur unless at least two unlikely, not present or (g) concentretsoais is removed from sernce.

Independent, and concurrent or controlled by postuve instrumental sequential changes have occurred in the means.

Process Systems as Prunary conditions essennel to nuclear caucality (c) Process and storese systems shall Confmement Barners

safety, be designed to ensure that the treasier Process components and systems are Mebde of Connel
  • I t "il' **II'i f'*" **I' 'I'e' t*

the pnmary conhaement barner.no unsafe systemsis not possbie as a design of each process system shall (a) Favorable geometry.in which consequence of any single failureer provide capability for the system to equipment or systems are subcnocal by operstmg error, memtsin its integnty and operability as virtue of neutron leakage under worst sh(all be designed to ensure thatleakage d) Confinement system components necessary to protect the public health credible conditions. is the preferred and safety. Provisions shall be included method of nuclear criticality control.

from equipment or from oss for the safe handlms of anticipated (b) Where the favorable geometry confinement zone to another nonroutmo process conditions.

method of nuclear criticality controlis confinement none cannot resultla a Utility Serwees not practical, the use of permanently condition that would result in nacisar

+

fixed neutron absorbing materials criticality.

Onsite utility service systems shall be (poisons)is the next preferred method of (e) ne spacing between discrete provided when such onsite service is control accumulations of fissile matenale shall necessary for emergency use to protect (c)Where both the favorable be controlled so as to maintain a i

the health and safety of the public.

geometry and the permanently flued subcntical state.

i Onsite utility services shall meet the neutron absorbing materials (poisons) f) A criticality monitoring system sh(all be maintained in each area wher

(

folicwmg entena:

methods of nuclear criticality control are (a) The WWa of each ut!!!ty service not practical. adannistrative controls of special nuclear materialis handled.

system requm for emergency modersuon, fissile material used.or stored which willenergne conditions shall provide for the meeting concentration. total fissile material, or clearly audible alarm signalsif of safety demands under normal and the use of soluble neutron-absorbing accidental criticality occure.

i abnormal conditions.The design of matertuis (poisons) shall be employed 1

utility services and distribuuon systems when combined with marsme of safety Radiolog/colAvesetdea having safety sigmficance shallinclude measurements or appropriate analysis Exposure Connel attemate systems ta the extent and engineered safety features.

necessary to maintain, with adequate N'ul Absorbers Itadiation protection systems mest be

(.apacity, the ability to perform safety provided for all areas and operations functions assunung a single failure.

Where solld neutron-absorbing where onsite personnel may be exposed

[b) Emergency utility servlees shall be materials (poisons)are used for the to radiation or altborne radioaction designed to permit testing of their prevention of nuclear criticality, the materials. Structures, systems. and funcuonal opershility and capacity, design shall provide for poaluve means - components for which operation, including the full operational sequence to verify their continued ofBcacy.

maintenance, and required inspostless of each system for treaafer between Soluble neutron absorbing materials may involve occupationalexpoeme normal and emergency supply sources.

may be used as a pnmary noclear must be designed. fabricated. located, and the opereues of associated safety criucality control provided(a) two shielded. controlled, and tested se as to systems.

ladependent methods are provided to

. control extemal and internal radiaties (c Provisions shall be made so that. In ensure the presence of the required exposures to personnel.no design meet the e) vent of a loss of the pnmary concentration of neutron absorber and include means to:

April 29,1983 76.PR.6

i

l

.e-1

-y PART76L PROPOSED RULE MMGNG

)

(e) pmvent the steemeisteen of informenon pe6danos set forth to for e basse of design salesleese i

redsonsteve metenalin these eyetems Regulatory Guide 315.*'$tesdard.

comparable to the twenty five see.

resumag sessee Format end Content of Safety Analysis whole body value usedler goedesse la.

-l (b)Doesniaeusste those oyenems to

Reports for Uransum Ennetuneet 10 CFR part 20D?

j which accese 6e required.

Feeihtees.* anel empenense gamedin (c) Control accese es areas of potential : pronous evaluetons of other typse of WS@in pupseed u CFR 1 contammenen er radiates:

fuel cycle feedities a order to determies p,, g.

(d) Meseure and seneet the individual topies for its revow and QaaniGedinforuestsee.Hasanises contasunsuon of areas seguinos seasas evaluation of the safety of a saareIB sabetanees. Penalty. Aedessen (e) Mmimise the tee reemrod to :

{.

perform work in the wenty of ennchment facility.nese tepees em a protecken. Reportans and reenedkeepees follows: esismology. seoisgy, hydrology, regenrenness. Sesenty mesesses. Sewee i

redaoecove componente: for esemple, by ' meteorology, siw 6eestion tseiers.

masoneL S providmp suffloemt spese for esse of structwalanalyes.mechaniemi

' Urannse. penalancientaseenaL operetion and desigmng equipment for equipment analyens.antkahty.

x eeee of mpair and repleeement and prevention. fire /esplosies prevenues De authority citaties for this.

(f) Shield personnel tres pedasues and protectaas.vesulaties typsee.

desamentis:

1 espeews.

analysis. idestificeoon med chanes of,

. (see. tet.as gast.ses, se aseseded ten USC.

Radiological Alarmlysteme.

strucewes.ayesema.and t-asest see. set. se stet. saea, as ameeded les 7

Radiologicalalarm eyesens must be knponm u ndaym6mcow wmW UAC aMHl.

l treatment, packagnap.and

-amiety.

Apnisses.

Daed m AssNGo.MD.this tabday of -

l provided in acesseible work areas as redieuon protocuen.obs appropnate to worn opereung personnel accident analysis and emesgeseF of radieuos and altbome radioecove.planmns.decontamansues and yer $e Noeles Repalsewy Cummasse.

material concentretions above a given '

decoeurusatorung, management g,,,,g p, setpoint and of concentreuena of orgaruzauon and quelaty asserence.

Seemsory radioactive matenalia effluents above techmcal specaficationa, human factors.

controllinuts. Radsauce alorei systems operstot hcensiog safeguardag specaal p gg pg ggggy must be designed with provisions for auchar matenal,and es prossenesof puneesi,eofygjeg calibrauen and tesung their operability.

classified utformanon. it le exposted Commene portes esenses so 10/30/ge.

Emuent and Dimet Radiatson that each of these topics will be M***"*E addressed separately in any safety-10 CFR part F4 evaluation report prepared by fo,s m.oennamentfac.thestaff, Regulation of Urenews: Enneluneet s

t.me,.opriais emum eysieme E"e'2,,*L'1","f2*fC*i.

Uranium M==8 Facmas ty.

oe.uos on*= R**d * *e mes*= or a= =m m.* = Reg

  • arf dunns normal opersuono and under Commission. -

accident conditions must be prowded In light of the pmvious diensessee. Iba senese: Adverse notice of proposed for these systeres. A means of measuttag. U.S. Nuclear Regulatory Cosammenen de. tutamakinst: entestoien of sonuneet r

the flow of the diluting medium. either parucularly interested la receenas pert'ad.

air or water.most also be provided, commeote concerning the icGesnes:.

(b) Ames contatmas radioactrue

1. Are the siting anteria setforthla evasesaav On May 22.1983(33 FR matenals must be prended with the General Design Criteria appropnate 13273). the U.S. Nuclear Regeistory syelems formeasursng the direct and complete for uranium ennelument

. Commission (NRCl pubhshed for public -

radiationlevele in and around these facihuest comment an Advance Notice of areas.

2. Are them factore plated to Pmped Remdhs MNpRIr&md m Effluent Connel prowcumiof b m vira m m a d.e

' the regulation of uranium ennetusent public ether than the chemical toxicity fachu.N comme pened k tie Facihties most be dangned to provide of the reaction products of armaism

[5Yb'n'e'r w ba p

means to limit levels is as, ne'-

mesonswy asevem. low as is henafluonde. that are not tak.a.a into.

um,,in,.of wr yiDOEl,,,,

e mies.e of

.- - maebon.gon.

eae radioscuve materiale in efDuenta dareg the GeneralDesign Cetteriet maiunwd a wesome normel operemons: and assoal the

3. Should the materia of Appendix 5 P

'p teleese of todioscuve materiale under to 10 GR plert 30." Quality Assuremen g,

g',,q,g g accident conddeas.

Criterie for Neeleet perwer plante and me h DOE's avkw h am sempime. '

4 Duomalasienhg 7,,

b ad M&tioal uom was needed u -

pm e ed

%e facGity must be designed so se to faciligest h [O mee Mh feelittate decommissioetas.Provtetens,

4. What estivitise shooldhe the rule,its experience a knowledge t

arest be made to fadtttate perfonned byalicensed and.

of the subject matter, sad the likelihood decontaramation of stroomros and what mquiremente a that the additional comuments wHibe equipment. and feellitate the removal of

3. Should the technical helpful for development of a proposed redioecove westes and contaminated catesones applicable to rule the NRC staff hee decided to -

metertels at the thne the facihtyis entend the comment period forse groesseing plaats.as set forthhang additional ninety days. The entended Permanently d==- -a-a--d Stat be applied to unehm comunant period new empires en October ReviewPlas TopiesSerNRCStaf

'Y# "

[g"'

II.1ges, weCommissis. setane..t.

.oo.e soneer g.e g

,g,g,gg,

= man-ad6-w

e beni. e.ec. co account the information sentained in the persone by the sptake of arenfun what entended and expires on October 38.

ymytous paragraphe la this notion, the value of areases mass ebeeldbe used Conun o

gg m

76.PR 7 September 30,1938

e.

o PART78 PROPOSED RULE MAKING so.but asentenes of consideraties -

cannot be pvos except as to casumente

-1 received on or before this date.

. aeoness: AfollCommense as:The Secrett.ty of the a==*

US r

Nuclear Regulatory Conussessa.

Washington.DC 20685 Attention:

Docketing and Bernae Bronsh.

j Delivercommensada 11883 Rockville Pike. Rochville. heatyland, betereen 7:30 a.a and 4.18 p an. Esamine copies of commente received at: the NRC Pubite Document Room 3120 L Siteet NW.,

Washington. DC.

j POA PUemtea leseenesafices coeffacT!

Leland C. Rouse, Omos of Nuclose htetenal Sofety end sefegeerde.UA Nucleat Regulatory Commise6ea.

Washington.DC20&as telephone (1

,j 201)492-3320..

The authority citetton for this document is: Sec.181 as Stat.o a. as amended (42 U.St 220tk Deted at Aschet!!e. bearyland. this 12th day of 5.vicmeet sees.

For the U S. Nuclear Regulatury ComnussioaL l

same.11. chik.

.$temoryof the Commossion.

1 i

l 1

[.

September 30.1988 76-PR-4 l

l

Retrieved from "https://kanterella.com/w/index.php?title=ML20034A376&oldid=4584759"