ML19259B280

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Forwards Rept SAND77-1927,Transport of Radionuclides in Urban Environs:Work Draft Assessment. Also Forwards SECY- 78-311 & Unclassified Portions of SECY-78-311A
ML19259B280
Person / Time
Site: Mcguire, McGuire, 07002623, 07701927  Duke Energy icon.png
Issue date: 01/03/1979
From: Hoefling R
NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD)
To: Hand C, Lazo R, Luebke E
Atomic Safety and Licensing Board Panel
Shared Package
ML19259B281 List:
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NUDOCS 7901240305
Download: ML19259B280 (44)
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{{#Wiki_filter:- / THis DOCUMENT CONTAINS ]bb POOR QUAUTY PAGES January 3, 1979 Robert M. Lazo, Esq., Chairman Dr. Cadet H. Hand, Jr., Director Atomic Safety and Licensing Board Bodeca Marine Laboratory U.S. ::uclear Regulatory Coaatssion University of California P.O. Box 247 Washington, D. C. 20S55 Bodega Bay, California 94923 Dr. Enneth A. Luebke Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D. C. 20555 In the Matter of DUKE POWER COMPANY (Amendment to t'aterials License SNM-1773 for Oconeq Nucletreatf0h? pSpeqh Ruel[T,ransportation: andi Scto rage i 7 y, Jat {4cGili e Nuclear StationM~jj L f j @ajaccket.Ad 76-2523 and 3m the Matter of DUKE POWER COMPANY (ililliam B. McGuire Nuclear Station, Units 1 & 2) Docket Nos. 50-369 & 50-370

Dear Members c,

f the Board:. copy qf. f f' C - Enclosed for the informatio'n of the pirfGDsentitled, " Transport of Radi SAND 77-1927 Draft Assessment" (WDA). This is a preliminary report in the development by the NRC of a Generic Environcental Impact Statement (GEIS) on trans-portation of radionuclides in urban environs. The general objectives of the GEIS are (1) to identify any unacceptable risk or hazard to public health and safety and (2) to identify promising alternatives whereby current levels of safety may be impuaved further. The study is not intended, by itself, to support any specific rulemaking action or ather regulatory activity. 4 Among the topics aiscussed in the WDA are: (1) sabotage of spent fuel casks, discussed in Chapter 6. resulting in severe consequences (thousands of deaths, billions of dollars in damages) and (2) consequences of severe accidents in urban areas resulting in costs exceeding $560 millicn. I Also enclosed for the information of the fa~rt eCafe~ccpids'.1 ~ T D ~ of Commission Infomation Reports, SECY-78-31i, dated June 14, 1978 ~~ ~ and SECY-78-311 A */ dated November 9,1978. These Infomation Reports indicate to the Comission the Staff's view of the impact of the WDA on --*/ Only the unclassified portions of SECY-78-311A have been forwarded. In addition, SECY-78-311 A has been supplemented by a " Correction Notice" of November 27, 1978. A copy of this notice is also enclosed. ^ 7 9 012 4 OToM ~

_2_ current regulatory policy. As can be seen from these Comission papers, the !;RC Staff has recomended that no immediate regulatory action is necessary to protect spent fuel shipment at this time. Copies of the enclosed documents have been furnished separately to all Licensing and Appeal Board Panel Members for their use. Sincerely, Richard K. Hoefling Counsel for NRC Staff ~

  1. -~,_.a cc (w/encls.):

cc (w/oencls.):. J. Michael McGarry, III, Esq. Atomic Safety and Licensing Board Panel William Larry Porter, Esq.- Atomic Safety and Licensing Appeal Panel Shelley Blum, Esq. Docketing and Service Section Mr. Jesse L. Riley DISTRIBUTION Ms. Brenda Best Anthony Z. Roisman, Esq. JTourtellotte Mr. Jeremy Bloch ; RHoefling, EKetchen Richard P. Wilson, Esq. FF (2)'

  • Mr. Charles Gaddy Reg. Cent., LPDR

, Shapar/Engelhardt/Scinto S.Kebiusek, R.Birkel B.Spitalny S 1 I g ~. Y, 2A t OELD R9aeT1'ibo ~.o.....* J,4MI wcnouu.,m wcvam m..~.......-----...-...---....

8 9<^. UNITic 57 Arts --u. vuna 1,. le/g

y-e t-v N UC:.EA~t REGUU CRY CO.*.*MisclCr4 INFORMATION REPORT

=c r: The C:missi'eners Fr :m: Rccer-3. Minegue, Cirec :r, CSC Cli fford V. Smi th, Direc::r,.1 MSS / Thru: Executive Direct:r f r Ocera:icns / Suciect: STATUS CF URSAff TUtiSFCRTAT Cit SAFE 3UARDS 5 JOY OISCUSSION: Eariy in June, Sancia Laccrateries (under ::n:rac: Oc 050) cei:verec :: 9RC, anc simultanecusly releasac :ublicly, a Wcrking Craf.a.ssassman: Or ..w. e n,/... .n. 2..t .r _, %..,.,,, e. ..,.. s..... - e. 3.., - <.... _ t. I C e s.......,.....,/ a. _... 4 o 4

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....a. Chac:er 5 en Urcan Transacr: Safeguards : resents :ne :echnical view Of ". n a. (a nd i a --O]' a.r.. *=> .W.2. fil '.a* s.". i..- a.q. a.".--a....1,v=.>#.=.:"..'.'..=., t,.. ur:an fac:ces do not affect significantly :he level cf :r::ec-icn :f'erac by current or prc:csed safeguarding recuirements and (2) hy c netical sabotage events using certain shi:=ents currently exem;; fr:m NRC :nysicai cretecti:n recuirements, such as s:ent fuei, may Osa a su:s :::. :nri.:

c :he public health anc safety (see Enclosure A).

Althcugn success"n' . alevelent attacks are :cr: rayed as extraceiy dif'icuit -*e

+
ei af con-secuences calcula:ec for sucn a :acks :s suf': iently ci;n tra: i t mas be aecessary :: ::nsider acciti:na' safeguarci. ; Oy :nysica! pre:ec:'en measures, further package harcening, ce routing restrictions.

The general cojectives Of :ne urcan trans:Or:a:icn s:ucy are (1) :: ':enti'y ~.'4..*.

2... c 2 * '. =.. v $ - '.. '. "... '

r.i..e k c c ".. a..=.-.. *..*. a. '.+'i.. i n.v ".a a...= a...=.b 't s. a2 - icentify :remising al:e-ratives, wnerecy cur-an levels :f safety ray :e 'ecr:vec further. 'he urcan trans:cr:aticn stucy is nc: intencec, :y i::ai#,

su::cr any s:ecific rulemaking ac:icn :r ::her reguia: ry activi y.
he study incicates :na acciti:nal requia: ry ac:f cns may :e a :re:r:a:e, s:ecific studies of those ac:f ons wil' be uncertaken.

In accercance uitn these general cojectives, the staf' may rec::menc in the Scrting Craft En-vironmental I :act S:atement, that the NRC uncertake a =cre ce 2iled icves-igation Of: (1) potential maiavelen; at:ack scenaries anc c:nsecuences fer scent fuel, (2) ;cssible ;re:ectice strategies, their feasibility, arc effectiveness, (3) ;cssible rulenaking acticn. he NRC staf# is skecticai e..,. a e... Verman A. Eise cerg, 50 d=..4-C;lO

The Ccemissioners acout the Sandia assessrent of the rescense characteristics of scent fuel to explosive assauit and has already taken stecs to cbtain an evaluaticn of fuel releases and discersien frcm fuel experts at the Cak pidge National Lab - oratory (CRNL). In additicn, a research crcject has been under develocment for some time to identify the need for an actual test crogram to verify the calculations contained in this and etner studies re: Stive to fuel fracture anc release fractions resulting frc= explosive rupture. The CENL will provide excert assistance to the NRC staff to judge on an interim basis whether action is necessary prior to ccmpletion of the research prcgram. The results of the research program cculd provide the final basis for deter-mining whether or not there is a need for adcitional safeguarding. When Sandia submitted the Workino Draft ?ssessment to "RC in early June, Sandia also sent their recort to each of the twenty members of the Task Grouc that has been assisting Sandia in this study, ano Sandia will make their report available to other members of the public en recuest. (CCA has recuested a number of copies to transmit informally to interested members of Ccngress). Scme members of the Task Grcup or general cublic may call for immediate regulatcry action, because of the censecuences of spent fuel cr other sabeti ge events as stated in the recert. In fact, Cr. Lecnard Solen, Cirecter, Sureau of Radiation Control, "ew York City Cecartment of Fealth, Mas called for such inrediate regulatory action en the basis of less refined calculations; both the reculatory actices ard the calculations succerting Cr. Scien's position were discussed in a secuence of corresponcence (het<.een Cr. Scien and the Sandia Lahcratories Staff), which the NRC staff has placed in the record (and the PCR) at briefings of the.1CRS Working Group en Transcortation (Enc 1csure 2). In rescoase to cublic and "CC staff ccmments,-Sandia Labs is excected tc revise, as they deem acpropriate, the '.lcrkirc Draft Assessrent tr=.nsmittec in June. The resulting Craft assessment,, which Sandia plans to issue in Secte.cer. will fcrm a basis 'cr the Pra't Envircrmental Imcact Statement, whics the staff plans to issue later this year. The results statec in the Wer'<ing Critt Assessment accear generally reascnable, reccgnicing the excressed skecticism of the staf# accut the assessment's estimates of release, aerosoli:ec, arc rescirabie fracticns basec en fuel behavice sucject Oc therrai anc mecnanicai assaults. "evertneless, uravcicacle uncertainties in the analysis (nue, ir part, :: lack of excerimentai data) may cause the calculated cnnsecuerces a te greater er lesser than the values realiced, if the hycethetical events were to occur. The.RC staf', in evaluating Sandia's indecencent assessmen:, will interpret the results within the entire framewcrk of regulatory ;clicy I I I l u es as..... l l l l i l w asaur.......___ =........ l l

rs.-

l

~ The Ccemissiccers 3'- L., (Enclosure C), including the likelibced of a successful :alevolent attacx, the consecuences of such attacks, and the ecsts recuired to orevent or reduce such attacks. Therefera, we believe imediate reculatory action, en the tasis of this preliminary reccrt, is premature. Origi:n1 sis::ed by RCm! 3. I':::r"E Robert B. Finecue, Director Office of Standards Cevelopment a %3 + ) Clifford Y. Smith, Cirector Office of ifuclear "aterial Safety and Safeguards

Enclosures:

A. Sun:ary of Public Consecuences P. Correspencence bet,ieen Dr. Leccard Solon and Sandia Labs on Safecuards C. Issues to be consicered in the Staff Evaluation DISTRIBUTION gcc

t. antra i

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ENCLOSURE A Summary of Public Consecuences' Early Early Latent Cancer .atalities Meroidities Fatalities Scurce Spent Fuel-Truck 10's 100's - 1000's 100's Rail 100's 100's - 1000's 10CO's Ncn-fissile Isotoces l's 10's 10's (Large Scurces) SNM l's 10's 1CO's I's L:w Level Waste " Based ucen the larges release fraction Oostulated for each category: Scent Fuel: 100% ncoie gases,1.5" cesium,1.0% solids other nan est'.m. 1/2% of ::tal sciics in resciracle form. Ncn-fissile Isc : es: Uc Oc 100% release, 2% in respiracle fcrm. SNM: Up to ICC% release, 2C% in respirable form. Low Level Wasta: Uc to 5C% release,1.C% in res:f racle f:rm. These casualty estimates are for radiclogical effects only; casualties resulting frcm exc10sions used :: release and to dis;erse radicactive material are not incluced, even though several hundrec immediate ceatns may result frca exolosions in certain scenarics. The econcmic costs which are extremely df ##icul :: estimate f:r :ne hy:er-ur an environment, c:uld excesc several bil'f 0ns Of collars.

e t }3 ..'s -;ittu vn: s UNI Sc S* e I ~g g j,. n Nuc:.2;.a ascutA cay c Atalls ;CN i ded wAsmuc :N;. O. :0!!5 .~. =, M:,'u I H. ) 2 n, a =>,<< .e,i a3 MEMCRANCUM FCR: Raymene F. Fraley, Executive Direct:r, Acvisory Cc=mittae en Reac: r Safecuar s FRCM: Re er: 3. Minccue, Direc:Or, Offica :f 3:ancares Deveicemen: ...a su eu, - LT: -,n u Rx-2 e..,4C n.1C - u,.,i.e. - a-...n. nS..x- -,. Le r.R t u.- re u-i so. e RAD:CNCCL:CES *H UR3AN E.Yl RCNS In May 1975 :ne Office of Standards Develcement centractad wi-h Sandia Laccratories :: :recare an envi :nmental assessment :n :te Trans:crt :f Radionuclides in Ur an Environs.

  • n keec13 w1:3 the Cc=missicn's keec the ACRS inf:rmed of :r: cress en this stucy, On Augus-L,

request : 1977 mem ers of my staff and their censaitants fr:m Sancia Oriefed :ne ACRS Warting Grouc cn Trans:Or:2:icn en :ne In:arim Raccc: issued by Sanci a i n a, cr11,i rr e. At this briefing in A.pgust, Dr. Lecnard Sci:n, Direc r, Sureau f:r Radia-tion Ccntrol, Oecar: rent of Heaitn, The City cf New York, was :ermi :ad by Dr. Siess, Chairman of the Working Greu:, :: reac a sta: amen int: tte briefing record and to res:cnd :: cuesticas fran ACRS mem:ers and c:nsultants. Mes: of Dr. Scicn's sta: amen: *as. :m rised Of his Ie::ar of Acril II,1977 c: Petar McGrath (incicsure A). Dr. Scien aisc f licwed uo wi-h a le :ar :: Mr. Gary Cuit:schreiber en Augus: 25, 1977 (Enciosure 3). Or Mcvem er 7,1977, Fetar McGra:n res: ended (Enciosure C) :: Dr. Solen's let:ar of A:ril,1977. My s aff en arec McGra:n's is :ar in: the rec:r: at a briefine of : e ACRS Werti g Gr:u: On Ncvem:er 13, 1977. Rinally, Dr. Solen res:cncac :n Cecameer 20, 1977, :: McGra:n's Never:er le::ar (Enclosure 0). 'ie are transmi ting :ne en f re ::rrescencence secuence :: y:u (1) si ce

ne ACRS na :een invcived 1n en ar ng s me :- ne : r es:cncenca 1n :

ne recorc, (2) so is '<aec :ne ACKS acreas; Of curren: cevei: men:s in ac: reance *ita ;ne C:mmission's cirectica, (2) s: na: Or. Scicn's mes recent c:rres:cncence may :e mace avaiia:Te f:r ne ACRS, its s:sff, anc ::nsui an s. A i lG., /A-A / /' ~l.1, -=y .s Rccer: 3. Min.cque, Gir?c r Offica Of 5:ancarts :evel:: men: Enciosures: 50!:n is::ar : McGra a, *:rii 11, 1977 . e. - e i n 3,.... ., c c u 4..a

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1 Raymcad...:raley JAll 3157T OISTRI3UTION Can:ral. 1'es 50 Alsna/R0 TPS8 rc/Suci bce: R. 3. Minogue C. V. Smi:n, NMSS R. G. Smi th C. E. MacDonald, NMSS G. A. Arict:n V. Hodge, NMSS R. M. Bernera

0. Xasun, NMSS R. F. Sar iar D. A. Nussbaumer, NMSS N. A. Eisancereg D. R. Heckins
0. Nellis N. Landau A. N. Tse R. J. Jcnes, MPSD 9

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magni de. As we all recogni:e, certain attenuatica techanisms wculd be operative in a hyperurban envirencent articularly *he presence of tail buildings - which may tend c c:ntain the dis:ersi:n Of the releasa fission pr: ducts and cwever, it is no: at all evident that '.".e presumably reduce casualties. 'a micremetacrolcc.ical wind c.atterns asscciated with h.vc.erurbia will be less effectivs in pr:ducing T ethal biciegicli deses than the metacreicgy assured s ....*w... e. r, . o cn1 y, ht...2,. w 4. u,1 c g e. r.s. 't a.s. e. a.r.*.a. .sgs..sse 3.a

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New Yor'< City with the potential for hundreds cf tucusan'ds of deads and c her scmatic and genetic casual:ies. I believe the task force must realistically ccnfront Me ineiuctable censequences of the data presented in NUREG-0194 - megacurie shipments of scett fuel and high level wasta are simpiy not acceptable in highly peculatad ur%n cantars such as New York City. Alternative rcu:as or methcds musc be used or established, if not already available, especialiy with increased rellance en ecmercial nuclear pcwer in the ccming decades. May I suggest with the acpreval of you and Art Cucharme, that this lettar be distributed to members of de task force and other interestad individuals? I au taking the liberty of furnishing the authers of NUREG-0194 ccpf es directly. Best perscnal regards. Sincerely yours,e sf/ / w 'M. ~ Cr. Lecnard R }. Scien fp w Directcr LAS.fp cc. C. Vernen Hodge, Nuclear Reguiaccry Cc. missicn James E. Cam: bell, Sandia Lateraccries jArthur Cuchar a, Sandia Laboratcries e e

,,.P* *%s g l.,r%%. ~y@s .v SUR5AU FCR RADCATiCN CCNTRCL Mg g ~M !,TQ? CEPARTMENT OF HE/d.TH r +Q~m]p 325 3rcadway.xzw vonx N f T M r ICC07 vh c ro.w...: = co -77:.-u gly - u Tl8!rT.I011 August 25, 1977 Cffice of the 5xecutive Director Advisorf Cemittee on Reactor Safeguards t!nited States Nuclear Regulatory Cca:nissicn kashington, O.C. 20555 Attention: Mr. Gary R. Quittschreiber L' ear Mr. Quittschreiber: Curing the meeting of the Adviscr/ Ccmittee en Reactor Safecuards '/crkine Greuc on Trans crtaticn of Radioactive Macer 1ais at t1e Snera n-IaGuardia hetai in New forx Ct y August 7.2, 1977, One Cnairnan, Dr. Chester if ess, requested that I forward to you a copy of my letter of Acril 11, 1977 to Dr. J. Peter McGrath of Sandia Laboratories for distribution = 5e 'lorking Grcup. I am glad to do this and a c:py is enciesed. During the questien period which ensued aftar the reading Of my iattar, One of the 'dcrking Grcup consultants expressed dcub: Or surprise at my e ssertion that shi; men 3 of spent react:r fuel and high-level waste Srcugn the City of "ew Y:rk wculd aspecach cr exceed acproxicataly One-cer working d.ay if the three L:ng Island Lighting Cemcany (L:LCO) :cwer reacnr shi: ents were added t: :ne 3reckhaven Nat.icnal Labcrat:ry spent fuel shipments from the SNL High Rux Seam Reactor. The 319 M'Je Shareham react:r 56 miles east Of de New York City line 'which is somewhat cre than fifty percene c:colete) was planned, when it bec:mes ccerational, to add between 35 and 70 megacurie-levei truck shi;:ents through New York City. The twin (each 1150.vue) James; ort reacnes abcut 8 miles east of Shcreham wculd adt an additicnal 150-150 shi:cenu if te James:crt nuclear c:mpiex bec::es cperaticnal. Between Januar/1975 and Octber 1975, the last ;ericd in wnich shi:- tents frem de HF5R at ENL were pe ni-ad by :he Cesar=ent of Heai-$ =r ugn New York City, pri r to the enac=en: Of the Ci ty cf New ^-t Hea':: Code adioactive ta eriais regulatica, recuiring a Certificate :f Emergency Tears:cr: 'or sucn sni: ents, delve scent fuel shipments, each invciving Of t.e Orcer :f 300 kilec'rries of mixed fission ;recucts were :ar-f ed by uck 2r: ugh t.e ci y.

m.ia, u n. uiun rugus. 2:, 1-,,/

/

Thus adding up de totality of spent fuei shi:ments alene frc= Shcreham,, Jamesport, and 3rcokhaven, there were tc have been betaeen abcut 200 and 250 sci:ments of these re:gacurie and high kilccurie spent fuel sni;ments thr ugn New Yo rk Ci ty. I offer without further.cresent cer=en:, these figures for fur-her d1 tailed consideration by de ACRS in its advisory cacacity to the Nucisar Ragula: cry Ccmissicn as part of the latter's iegisiati ecly manda:ac raia of pittacting tne public heal 2 and safety. I appreciated the cpportunity of acpearing before the ACES Workinc Grcuo en Transcertation of Radicactive Materials and the courtesy sacwn me cy re m+mcers anc staff. Needless to say, I am prepared te alify or discuss further any of the mtters treated in the present letter. Sincerely.ycurs( e. p % ~ /:

i. q Dr. Lecnard R. Scien Directer LRS:fp encicsure c::

Cr. Chestar Siess Ncrean A. Eisenberg /rcur CuCharme

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Dr. L. Solco Ncesmhe , 197-Anothat way to lock at the ;c;ulation dose is to pcctulate a reasonable c,c $f,,me.m,, _:cn .u.3u u. , t, w. wo e.---.w -..a e s u t o.. 3 3 4 1 y--u- = -2 --3-- --3-- .--u--- e-~ u., s.a =s -- w,-. 7: .w c"u': i-~ ~=-s a.,,,.,. a o e, ...m s.- - = yu..' -..t.~ w... a - e-s. 1i t ,,n, .a.e n u..w. e s =.,. 4,2 _477-a .a.$., w ~. ' s a-7000 a _- 1-44-w ,t s..&. c..' " a s u-the oan. ulation dose of 1.1 s 10 * =an-ras. Howaver, c e.tn individual-dose of 1000 ren would be lethal to the total pcpulation cf 10 tillic:

v. h.:a a-4 4w ew.<a a a.. _,.,,..

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4-s f might die from'a radiation induced 12:ent cancar. If we postulate conditions to maxi =1:e the fraction of the e::csed.coculation that - would die f:co a radiation induced latant cancer, then we wculd -b-aeb 4-dividua' c= *ha - c : "- ' $ ' i a.. r, a c = i. = s = d - - s a5 c..'aPa .s - au.- .~ of r, diation belev the t.ireshold fc early mortality. For tha puryc353 of cc: calculation we can sssc=e thic dose to ha 300 rs=, which is no t i.n unm en bl^ value.' If we use the esti= ate of 12',-laten t ,1.,.c.. e.. r, s e n a ,no ...__.ea u-..,--4,, ac.e,...,, n , - -.,. 4 - -- - 2.3.,

s-

-s . -- --.s e.- z u----. 2 4% (122 latant cancer fatalities /10 can-: c..., 2 0 0 res : 100) of :he e.~ co =- ^ :~ ~~r 'da' ' '-.i ' n, *.. "= h A' w % =_a l.'.' 4. 7 *4 du4' ' ~ = e =- * = c' u- ^~-=..o=. t- .- 0 ~-, ~ w -va -s wo-b dic c' a ia'=a-c a=c = *-.

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~~oo..,. .t e a,* =----: to cr.m,eting risks and the ccservati=n :nst latent cancara appear with sc:a p chability over 30 or =cre yac:s following a latan: peri:d of C to 15 years af ter exposure to the e.tdiation. The 41 value is -,o c. u' '-.i n.q =ve. :g, ,a-"-4 cu' - c.wu,s i.~. '..'.=,- yt-c;o.. 5 "-5 ,s = ' ~ a 4 4sw. u. s d e,g C.k. _4.~. u s n 1 W.4,1 .aM cV a %. ; 3.u.a.. .s 4 a,.. - e c,_ .%.s. u a.. n w _,,. n,. e ar u A. -w.g

4. 423.

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cau w.:vn: a g fif.q'l..S.. SUREAU FOR PAC *ATICN CNiTECL A ~. vi,f)- w "DM.=[# 325 3rcadway,N?.W YORK..V Y[-]f M N }CCC7 , W+#;m um 5c6-7750 cm {O.r.'Y 7 WW.L0Zk Cecember 20, 1977 Cr. Petar J. McGrath Division 5413 Fuel Cycle Risk Analysis Sa1dia Labora cries Altuguerque, New Mexico 37115 Cear Dr. McGrath: 7 hank you for your lettar of November 7,1977 which addressed itseif tc the matters discussed in my communication tc you of April 11, 1977. [Inciden: ally, score a tie for the Postal Service - the cecy of ycur let:ar sent fr m Albucuerque f'.rst class arrived on my desk at the same time as the cecy sent by Ccurier-?AX Federal Express - i.e. cn the afterncon of November 9,1977. I was surprised to receive the Courier-?AX and. assume the redundancy in mailing redes had scmething tc do with the public hearing by,the Department cf Transportation Matariais Trans;crtatica Scard scheduled in New York beginning the fcilcwing day, Novembec 10,1977]. New tc the issues involved in United States Nuclear Regulatory C:missica Reper' NUREG-Oi9a Ca!:ulations of Radicionicei Consecuences '~m iabeme of piccine Cas;:s f r Scent Fuei and -Men-Level das e by C. 'lernen n::ge QRC), James E. Camp eil (Sancial (Fecruary 1977) anc =e c:ments offered in =e ie: tar by you and David M. Ericscn, Jr. I shculd like to fccus en the real ;ublic health questicas and not taka miner excep:icn :: wha NUREG-019a did and did no: say. Mcwever, f:r tne rec:rd, since your lettar saems te imply that I samencw misread that repcrt: Mcwhere can I find in the retcr the assertion of your lettar that the ccm:u:2 icnal resuits "c:uld be scaled linearly with caution.' As a mattar f fact, in my c:cy the eniy referenca :: linear scaling appears as an ad:anda en an erra=m sneet wnich says in its entirety: ";.6, end cf -hird caracrach Ccnsequences f:r differen: values cf unif:r ;;;u i a ':i = dsns1:y may :e as:1mauc cy linear scaling fr:m :hese results. I: haccens :ha: I wnclly agree with ycur ad enitien of :au:icus ex ra::ia-i= sc I wil' not baiaber tne point. Mcwever =is may be te tes. uni :t Or an-3: :r that we have :: be cauticus 1: cut in using the C.'{C :: dei. An es eciai'y ',cau.i =s sistement, ccmcle ely unsucccriad by the da:a of ne re er i :s ai # (an; ycur su:se-cLent rec:mputations) is =e Abs;rac: cf,*UREG-Ol?2 uni = recr:duca here '1 d :s ef.ti re:7

" Radiological con:equences cf a hy::cthetical sabetage event which causes a raiease of esdicactiv2 Ic.:erial fecm a spent fuel cask and a high level waste cask are calculated. Tne release frac:icas of vciatile fissien creducts in the scent fuel and.he solid fissicn prcducts in bc.n the sner.: fuel and high level waste are treated as ;arameters. Assuming a largesc credible solids release fracticn of one percent, -he numbers of heal.n effects are shown to be smali and en te same creer of magni:uce fer ac;h spent fuel and high levei wasta. The numbers recalculatad frcm the CQ4C =cdel and ::resen ed in ycur ie: tar (which inciden. ally amploys a hy;cthe:icai pcpulation densi y distributica grar:er than New Ycek City) clearly do not supper: the inference of :he Abs:rac; 'wnier is the only thing many planners get to read). Fcr the sake of cc=;arison, let us list these varicus numbers decending v;cn the assu=ction of pc;:ulation density. Pcpulaticn Early Latent Censity Dea ths Cancer Cea ds cersens mile-2 Hecge and Camcbell NUREG-0194 1.00 0-2 20 - 250 (February 1977) McGrath and Ericscn 0 d miles 150-1500 5CCO - 11,000 (Letter to Salen; (250,408) (mean) (mean) November 7,1977) 4-12.5 miles (50,080) 12.5 - 30 miles (10,000) 30-55 (ICCO) 55-5C0 (1C0)

aien

,o_,,.C u, ,,CO 10:,u,,, u ',New Ycrk 7i es) (Manhattan Ncveccer 12, 1977 average) Scien ECO,0C0 0 - 1C,000 2x10-i.3xid 'Latter to McGrat) (Manna ttan Acril 11,1977

eak) 4

I succit, that in tarms of pubiic health significance, ycu and Mr. Ericscq care to the essentially identical Ocerational conclusica that I have. I am sure that neither of us will argue ::o strenucusly in behalf of the precise quantitative rebutness of any of the nu ters. It is evident, newever, that the resul ts of a major radicicgical releasa from the deliberata cr accidental ructuring of a spen t fuel cask in a hyperurban envircr. ent could be disastr:us indeed - either =cre or less sericus than most of the numbers tabulatad. Ncw to the assumpticns of the ecnsequence : del (CQt0) itself. Another o# my references here is NUREG-0310 Overvie<< of the Reacter Sa fe ty Studv Consecuen;g Model published in Cct:ber 1977. I ceserve :nat you are listac as One of :ne six autnars. (I.3. Wall, S.S. Yaniv, R.M. 31cnd, P.E. McGrath, d.W. Church, J.R. Wayland) (1) Solids Fraction Release NUREG-0194 used a 1% solids fraction release as a point of reference. NUREG-0210 (and Apoendix VI of the Nash-Ta00 Reac:Or Safe:v Study) treated raiease

  1. ractions up :o unity. There does not a;; ear c :e anything cancnical abcut a ::

release. I sugges: that a carefully planned sabotage event en a fuel cask could release a let cre cr a lot less than 15 so the assu=ctica of 1% shculd be viewed wi th caution. (E) Meteorciocical Cata - The weighted "six-site" weather structure re crted in NUREG-0210 and presumabiy empicyed in NUREG-0191 is inapplicable tc New York City. For Iccking at New Ycrk City. one shculd assume the kind of high veiccity winds and turbulence typical of many days beginning in October and ending in March and cc:asicnally for other days thr: ugh-out the year. (S) Peculation Evacuation It is cbvicus that the. peculation evacuaticn =cdel~ discussed in NUREG-G!;C is deficien wnen apolied to New York City. Cne cannot take sericusly (f:r the satetagac spent fuel cask case) assumptiens -hat (cf. P.15): The ;cpula:icn within 25 miles is assumed to :cve radially cu:aard fr:m the reactor wi th... a 20% ;r:bability of 7.0 m.p.h." "If the evacuating ;cculation is Overtakan by the ciced of radicactive ma:arial, it is assumed that peccle wiii have ecved cu side of the c:ntaminated area within a a-hour pericd." ! cita -hese ;rier items :: indi:2:a recresentative insuffi:f encias in :re CCMC : del as a:clied : 3:ent-fuel cask radiclogical release in Naw Y:rt City. I Lm still of tne ::inien :nat overail it is a helpful firs: ste: in a;;rcacn::q the cr:ciem Of radicactive ma:arials trans:ceta-i:n and, in fact, d:es iaad :: -he

nclusi:n -ha large scent fuei shi: cents thr:c;n censeiy :c:uia:ad ur:13 are.s are act accac:2:le fr:m the ;cin: Of viaw Of publi health.

Dr. Ltcnard R. Scion Cecember 20, ig77 Pemit me to reiterate my accreciati:n f:r the additicnal aff:r: that ycu and Mr. Ericscn have put in furtner analysis of this imccr: ant mat ar. May I imcosa ucen ycu to cir:ulate the present letter to all the ;:eccle who received ccpier. of ycur Mcvember 7,1977 c:=unication :: me, es;ecially members :f the-Task Jecuc en Trans cetation of Radicactive "ateriais in Ur:an Envi crs. I am furn13ning Vern Mcdge anc itcm i:sen:: erg c:c:es cirec:!y. Sest personal regards and bes: wishes for the Season and ali of 1973. Sincerely v~~, ,7 Y \\ n ~ Dr. Lecnari R. Scien Direc:cr LD.S:fp cc: C. '/ernen Mcdge, U.S. Nuclear Regulat:ry C:rcissicn, Washingt:n Normen Eisenberg, U.S. Nuclear Regulat:ry Cer=ission, Washing::n Arthur CuCharme, Sandia Laborat: ries, Albuquerque

4 ENCLOS*URE c The issues to be considei ed in the staf# evaluation include: 1. Oegree of realfsn in the Sandia consecuence estimates e ncble gas and volatiies release fraction a solids release fraction o solids aerosolized and resoirable fractions 2. Perspective on sabotage consecJenCes sabotage of radioactive shi:ments versus shi:ments of other hazardous e material.1 e radiolog' cal consecuences of a malevolent attack on radioactive shipments versus nonradiological consetuences, e.g. explosion fatalities, injuries, and property damage attrac:4veness of radioactive shipments as a target versus otner e cotentici targets 3. Potential mitigating actions routing around cities - but scme shi;ments can be hijacked and taken e to a high consecuence target hardening packaging - stronger casks e chysical protection communication system on shi: ment or transoort vehicle - alcrm or e locating devices k

. ;- v,. g. !NmMAT[ON N " - - - ~ ' [.[, Oisc:scrs su::fset,g UNITED STATES b NUC1. EAR REGULATORY COMMISSION SECY-78-311 A ' November 9, 1978 INFORMATION REPORT For: The Ccmmissioners N 0.T e\\ From: Robert B. Minogue, Director, 050 Thru: Executive Director for Operations STATUS UPDATE ON URBAN TRANSPORTATION SAFEGUARDS STUDY

Subject:

Discussion: On June 14, 1978, the staff sucmitted an information recort (SECY-78-311) to the Commissioners indicating that: (1) the Working Draft Assessment on Transport of Radionuclides in Urban Environs (SAND 77-1927), issued by Sandia Labs to NRC in May 1978, states that a successful sabotage attack on a spent fuel shipment, although difficult to accomplish, could produce sig-nificant consequences, if performed in an urban area; (2) the staff was skeptical about certain aspects of the Sandia analy-sis, particularly the response of spent fuel to the sabotage attack environment; (3) the staff would evaluate in an accei-erated manner, with help from experts outside NRC, the degrr.e of realism inherent in the Sandia analysis. Because of the NRC staff skepticism regarding the ability o' the spent fuei to respond to the attack environment in the manner assumed in the Sandia analysis, the staff believed the analysis contained a fundamental conservatism and the consequences esti-Discussions mated greatly exceeded what might occur in reality. of this matter were held among Sandia, Oak Ridge National Labora-tory (ORNL), and NRC (SD and NMSS) staff members (see Enclo-sure "A" - Report on Safeguards Coordination Meeting and Fel-lowup). The 050 staff and technical consultants from ORNL and Sandia recognize that great uncertainties exist in the anaiysis, but no longer believe that the properties of the spent fue', will inherently prevent the response behavior postulated in the Sandia analysis. Because of this change and otha.r factors, the OSD staff characterization of the Sandia consequence analysis has changed from " conservative" to "probably realistic but with large uncertainties" (se. Enclosure "B" - Factors Affecting Staff View of the Sandia Analysis).

Contact:

N. A. Eisenberg 443-5946 man q: e tre gr me, ,m, m 7

2

%it Of;;;.- ; ; s*.re. 4 c.n..-,. 3. y

The Commissioners 2 On July 25, 1978, NMSS formally transmitted to RES a "Researc;1 Requirement on Vulnerability of Spent Fuel Shipments to Malevolent Events (NMSS 78-7)" (see Enclosure "C"). The requested research ~ program is generally intended to identify the vulnerability of spent fuel shipments to malevolent attack, quantify the sourre term from such attacks for consequence estimation, and to pr.)- vide information useful in the formulation of protective meat-ures, if they are judged to be necessary. The staff believes the requested research program is a suitable vehicle for resolv-ing the technical questions raised by the Sandia sabotage analy-sis and the subsequent staff evaluations. Several key technical problems have been identified (shaped charges as a significart attack mechanism, the response of the fuel to a shaped charge attack, released, aerosolized, and respirable fractions), and this information can be used to focus the research program oa key problems. NMSS and RES have primary responsibility for this research effort; OSD will provide technical input as required. Chairman Hendrie has received a letter dated August 18, 1978 from L. D. Santman, Acting Director, Materials Transoortatien Bureau, 00T, inviting NRC's views on DOT's advance notice 01 proposed rulemaking on.' outing requirements for nighway carrige of radioactive material. The staff sent a response (letter of September 19, 1978 from L. V. Gossick, NRC to L. D. Santman, 00T), that indicates the interrelation of safeguards and routing considerations. The staff proposed to participate with 00T in a rulemaking. proceeding on this subject. The Division of Safeguards in NMSS is considering what imolications, if any, the information above has on Safeguarfs policy or staff activity. , ~ 'i..,,', /> !.' a Robert B. Minogue, Director Office of Standards Development

Enclosures:

See next page ,!-s s., le 9

Tha Commissioners 3

Enclosures:

"A*' - Report on Safeguards Coordination Meeting and Follevup "B" - Factors Affecting Staff View of the Sandia Analysis "C" - Research Requirement on Vulnerability of Spent Fuel Shipments to Malevolent Events (NMSS 78-7) DISTRIBUTION Commissioners Commission Staff Offices Exec Dir for Operations Secretariat e e "9 G

9 ENCLOSURE A 8 9 4

Further-of gas from the gap, out of the rupture, sweeps out the cesium. more, heating of the fuel pins after rupture would tend to cause the U02 near the rupture point to oxidize and the resulting swelling would tend to occlude the gap near the rupture point, thereby isolating the gap cesium inventory from the external environment. Since the postulated sabotage scenarios cause rupture of the cladding at normal temperature (as opposed to certain accident scenarios), Sandia agreed: (1) that no gap cesium would be released except for that directly in the path of the shaped charge jet, (2) that the cesium release would accompany the solids release, and (3) that the cesium release fraction would equal the solids release fraction. Third, ORNL experiments on shearing of spent fuel and shatteriag of fresh fuel by fast fission heating, indicate that a respirable fraction of 1% or lerc is likely for these processes (see Attachment 2 to Enclo-sure "A"). The Sandia analysis assumes a 50% respirable fraction for those solids released and aerosolized. Hcwever, in a postulated attack using a shaped charge, the molten metal jet from the shaped charge erodes 3 away the target material at a penetration velocity of about 2 x 10 m/sec, 7 by creating pressures of N 10" Pascal (about one megabar or 1.4 x 10 ps ) i and temperatures of 2000 to 3000 C, and thereby causing the target mater:al to flow away from the jet-target interface. Since the environment created by a shaped charge attack is so different, in both energy deposition per unit mass and energy deposition rate, from the ORNL experiments, both the Sandia and ORNL staff memaers agreed that the experimental data could not reasonably be extrapolated to the sabotage scenario. h the absence of directly applicable information, the 50% respirable frac *. ion estimate 2 Enclosure "A' {

appears reasonable. In summary the ORNL and Sandia Staff members agreed that the noble gas and cesium release fraction needed to be revised downward, but that there is at present an insufficient technical basis for revising the 50% respirable fraction for solids. Followup Following up on the coordination meeting, Sandia performed some prelimi-nary calculations to determine the effect of the modifications suggested by ORNL. As expectad, changes in the noble gas release fraction had Reduction of the cesium release frorr. virtually no effect on consequences. 1.6% (1% in solids plus 0.6% in gap) to 1% (no gap cesium released) causec' a small reduction (10% or less) in consequences. Thus, the revised analy-sis provides consequence estimates different from those of the original analysis to a degree that is well within the uncertainty inherent in the analysis. Essentially then, Sandia stands by the original consequence estimates. In following up on the coordination meeting, the ORNL staff members have been unable to discover any data that might provide a better basis for estimating the respirable fraction for solids. In fact, the ORNL fuel behavior experts are not sure if there are any physicochemical phenomena involved in a shaped charge attack that could provide a signifi-cant limitation on the respirable fraction. In a related series of experi-ments (associated with the LMFBR program), ORNL staff will rapidly discharge a capacitor into a fuel pellet heated to a semi-molten state; the particle size distribution from the resulting explosion will then be measured. Although not an exact analog of the shaped charge environment, this experiment 3 Enclosure "A" S g QQi 9 [p y!h J J40M LV

As approaches the rate of energy deposition in a shaped charge attack. the results of this experiment become available in the next few weeks, al? concerned parties will be kept informed and judgments will be made on the applicability of the forthcoming information to this sabotage issue. m 4 Enclosure "A' ,'t.

t ATTAChnENT ' TO ENCLOSURE "A" Attendance At Coordination Meetings On Spent Fuel Sacotage - Albuquerque, NM, August 10, 1978 Morninc NRC: Norman A. Eisenberg, 5;' Carl B. Sawyer, NMSS Sandia Labs: Ronald B. Pope David M. Ericson, Jr. John M. Taylor Bruce Varnado Arthur R. Ducharme Martin Tierney David McCloskey R3bert Reese ORNL: Aathony P. Malinauskas George W. Parker R. A. Lorenz Afterncon: NRC: Norman A. Eisenberg, SD Carl B. Sawyer, NMSS Sandia Laos: Arthur R. Oucharme David M. Ericson, Jr. Paul H. Cooper Robert Reese David E. Bennett, III ORNL: Anthony P. Malinauskas George W. Parker R. A. Lorenz J.': ulna 5klclj

\\lHti.A8hid ATTACHMENT 2 TO ENCLOSURE "A" Particle Size Distributions For Stressed Fuel e = t !' 0 ;.; b;u(. v=; r rh? !\\* Q ' Y 'J ' n s

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I 9 O ENCLOSURE C l A ' 4f-4 t

  • e O

se se M

ENCLOSURE "A" REPORT ON SAFEGUARDS COORDINATION MEETING AND FOLLOWUP Coordination Meeting On August 10, 1978, a meeting was held at Sandia Labs to provide an oppor-tunity for staff members of NRC, Sandia, and ORNL (see Attachment 1 to Enclosure "A" for list of attendees) to discuss the analysis of spent fuel sabotaae discussed in SAND 77-1927. Specifically, fuel behavior experts from ORNL discussed with the sabotage analysts at Sandia the physical environment created by malevolent attack, the response of spent fuel to such an environment, and implications, if any, on the released, aero-solized, and respirable fractions estimated by Sandia. Three technical issues received substantial discussion. First, experiments performed at ORNL on spent fuel reprocessing indicate that even after prolonged heat-oxidizes to U 0, at most 20% of the krypton in ing, during which the UO2 38 the fission product inventory is released; both ORNL and Sandia Staff agreed that in view of this, the assumption in the Sandia analysis of 100*. noble gas release was too conservative. Second, the ORNL staff considered the release of all cesium in the cladding gap (0.6% of the Cs in the fission product inventory) to be highly unlikely, since such releases are believed possible only when the cladding is ruptured at an elevated tempera-ture, so the cesium in the gap is in a volatile form and so the rapid f1]w

UIYblM00lflLU i f 3 2.u0 ... neGULATORY COMMISSION WASHINGTON D. C. 20555 JUL 2 ~ 19N Saul Levine, Director MEMORANCUM FOR: Office of Nuclear Regulatory Research Clifford V. Smith, Jr., Director Office of Nuclear Material Safety and Safeguards FROM: RESEARCH REQUIREMENT ON VULNERABILITY OF SPENT F SU3 JECT: SHIPMENTS TO MALEVOLENT EVENTS (NMSS 78-7) The attached NMSS Research Requirement forr. ally expresses the Division of Safeguards needs for research support in the evaluation of the vulnerability of spent fuel shipments to malevolent events. Procedures for Processino User Office In accordance with SECY-77-1303, Research Recuirements, it is requested that a work scope, schedule, and cost es.imate for tne work needed to satisfy the requ A. C. Giarratana is devaleped and submitted to my office for review.the HMSS ;:cin the stated requirement. / / L/ v // / Clifj0' 'd 'V. Smith, Jr.,p Safety / a rector Off4 of Nuclear Mater and Safeguards ~, Enclosers: ,.d. - 7' s NMSS Research Requirement to d p". > Evaluate the Vulnerability of ,(. Spent Fuel Shipments to g. Malevolent Events g W C., .:g 'a .,q-s M ".. ' ' (' / Enclosure C

s MM55 SA:E3UAE05 RESEARCH REQUIREMENT TO EVALUATE VULNERA3ILITIES OF SPENT FUEL SHIPMENTS TO MALEVOLENT EVENTS SACXGROUND AND STATUS OF PROBLEM At present, there are no specific physical protection requirements for safeguarding snipments of spent nuclear fuel. Transport standards which do exist are concerned primarily with safety, and are based on standards developed by the International Atomic Energy Agency (IAEA). There are four basic requirements for meeting these safety standards. These are: Adequate containment of radioactive material; Adequate control of radioactive emissions; Safe dissipation of decay heat; and, prevention of criticality. In meeting safety standards requirements, the safeguards posture of spent LWR fuel shipments is enhanced, although the degree of inherent safeguards protection afforded by these requirements to some extent remains to be To complete such an assessment, NMSS needs information on the assessed. release source tem.s appropriate to a shipping cask exposed to an explosive attack in which the integrity of the cask is breached. There are, at present, a number r / approved and licensed spent fuel shipping containers suitable for either truck or rail transport. These include legal weight truck packages with a capacity of one PWR or two BWR fuel assemblies; overweight tr.uck packages with a capacity for three FWR or setin BWR fuel assemblies; and rail packages of seven to ten PWR or eighteen to twenty-four SWR assembly capacities. Preliminary, classified investigations of the penetrability o" spent fuel revealed shipping cask exemplars by various kinds of explosive attack ho that shipping cask walls can be breached by a broad spectrum of explosive device configurations. While at this time conservative bounds can be determined, it is not possible to estimate precisely the radioactive release fractions that could result from an act of sabotage involving an explosive attack on a spent fuel shipping cask. Accordingly, it is necessary to refine the estimated effects of a successful attack to cbtain a more exact c U i'nition of consequences. Investigations to date have raised the following questions vis-a-vis the potential vulnerabilities of spent LWR fuel shipping casks to acts of sabotage involving explosives:

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t ilNC ASiJilB . What adversary rescurce requirements need be assembled to, with e a high degree of assurance, explosively breach a loaded spent LWR fuel shipping cask? What quantities of spent LWR fuel could be discharged from spent LWR fuel shipping casks subjected to a variety of explcsive ~~ ) attacks? What portion of the radiation release fractions resulting from explosive breachings of spent LWR fuel shipping casks would be released in respirable aerosol for ns? $n What could the range of potential consequences of such events various environments? / What are the safeguards implications? RESEARCH REGUIREMENTS A. Functional Need_ A requirement exists for invest.igating the vulnerabilities of spent LWR fuel shipping containers to acts of sabotage involving the employment explosives; for the development of potential sourc source terms.. Support is required for: 1. Consecuence Assessment This capability is required to assist in the formulation cf policy concerning safeguarding shipments of spent LWR fuel. 2. Reculatory Design This capability is required to provide a basis fo for the shipment of spent LWR fuel. product Characteristics S. Maximum radioactive release fractions from explosive ruptures o fully loaded spent LWR fuel shipping casks s 1. disintegration of high burnup LWR fuel pellets and of explosive rupture of scale model spent fuel shipoing casks loaded wi,th surrogate fuel.

V UNXASSEED - The data from the controlled laboratory tests s 2. breachings of fully loaded, full-size spent LWR fuel shipping casks. The research products should include the range of volatile (30,00G releases frem explosive disintegrations of high burnup 3. mwd /t) LWR spent fuel pin segments and pellets; the proportions of particulates arising from such disintegrations i i cask structural elements on the dynamics of explosive events, and the resulting interactions with and breakup of spent fuel samples; the estimated degree of plate out of explosively disintegrated LWR fuel; and radioac in the spent LWR fuel explosive disintegration tests. This research requirement product should include a data base describing the combinations of spent LWR fuel shipping containe 4. and attack modes which would likely result in rele with the nature of damage inflicted on a shipping container, as activity. asso-wcil as with the internal cask pressures and temperatures ciated with the attacks. Empl'oying radiological release source terms developed in the course of this research program or other NRC funded research 5. f programs, consequence estimates should be made for a va explosive attack model and associated release five, and ten year-old spent fuel. Although those portiens of the data base which provide details in safeguards vulnerabilities must be classified, the research 6. d product should, to the extent possible, provide an unclass overview and appreciation of the range of p project Schedule C. it a ?reliminary evaluative data concerning results of explosive dis n egr - h ld be available tions of high burnup LUR fuel pellets and pin segments s ouCo by the end of FY79. be available by early FYSO.

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  • af UNC. ASS!fB should be scheduled for early FY80 for NRC staff to evaluate program results and decide whether program results warrant furthe A decision poin research.

IMPLICATIONS FOR SAFEGUARDS FROGRAMS This is a high priority requirement, significantly impacting NRC's policy the develop-concerning the safeguarding of spent LWR fuel shipment ; ment of regulatory upgrades in this area. RESEARCH RECUIREMENT Procedures for Processino User Office. in accordance with SECY-77-1303, Research Recuirerents_, it is requested that a work scope, senedule, and cost estimate for tne work needed to satisfy the requirement, as well as an estimate of the value effectiveness of the proposed research, he deve by the Office of Research and submitted to the Office of Nuclear Mat Safety and Safeguards for review. RELATED ACTIV: TIES IN OWER AJENCIES This research caquirement could by met by a joint program with the Departmen: cf Energy (CGE), whose objectives in a currently funded progra of similar nature appear complamentary to those of NRC. The DOE program to date ha; involved investigating the effects of various kinds of explosive attack on empty, obsolete, fuel casks desig b as on models of these casks. Continuation and cocrdina icn with their centinuing effort is essential. of this program into studies of the effects of explosive attack on casks design containing high burnup LWR fuel, is and cask models of curren:The most recent Sandia Laboratories 189, which is attached, contains estimated costs of the DOE proposed program tests a contemplated by DOE. validation studies. Scurce terms developed from a joint undertaking could be used in cense-l d -quence estimation methodclogies recently developed, or now being dev under an NRC funded research program.

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  • F "ovember 27, 1978 C 0 R R E C T I 0 N N 0 T I C E TO ALL HOLDERS OF SECY-78-311A - STATUS UPDA'S ON URBAN TRANSPORTATION SAFEGUARDS STUDY, DATED NOVEMBER 9, 1978 (INFORMATION REPORT)

PER THE REQUEST OF THE EXECUTI'lE DIRECTOR FOR OPERATIONS, THE LAST PARAGPAPH OF PAGE TWO 0F THE EAS:C PORTION OF THE SUBJECT STAFF PAPER IS REVIS RFAD AS FOLLOWS: "THE OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS MAINTAINS THE POSITION AS STATED IN SECY-78-311 THAT NO IMMEDIATE REG ACTION TO PROTECT SPENT FUEL SHIPMENTS IS NEEDED AT THIS TIME. IN SUPPOR; 0F THIS JUDGMENT, NMSS DOES NOT BELIEVE THAT ANY NEW INFORMATION HAS BEEN P9ESENTED THAT WOULD SIGNIFICANTLY ALTER ITS INITIAL EVALUATION OF S.;NDIA STUDY. SPECIFICALLY, THE LARGE UNCERTAINTIES ASSOCIATED WITH CALCULATION OF CONSEQUENCES STILL REMAIN. A REVIEW OF THIS POS BE MADE AFTER THE FINAL REPORT OF RESEARCH PROJECT NMSS 78-7 IN EARLY FY S0." THE SECRETARIAT e w}}

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