ML19206A630

Response to Motion by Citizens for Safe Environ & York Committee for Safe Environ for Stay of Initial Decision. Affidavits & Certificate of Svc Encl

ML19206A630
Person / Time
Site:	Crane
Issue date:	01/25/1978
From:	Mcgurren H NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD)
To:
References
NUDOCS 7904200306
Download: ML19206A630 (77)

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4-01/25' UtiITED STATES CF 4 T ICA NUCLEAR 9 CUL/. TORY CC: ' 7 3 S IC ';

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In the :'atter of

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Occket No. 50-320

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FOR STAY OF THE INITIAL DECISION W.fiC p

N INTRODUCTION t' i a t:"

On December 29, 1977, the Joint Intervencrs, Citizens for a Safe Envircn-ment and the York Ccmmittee for a Safe Environment, filed a Moticn for Stay of Initial Decision rendered on December 19,1977 (Motion), which authorized the Director of Nuclear Reacter Regulaticn to continue in effect the constructicn permit of Metropolitan Edisen Cemcany, Jersey Central Power and Light Company, and Pennsylvania Electric Ccmpany for Three Mile Island, Unit No. 2 ("TMI-2"), and to make any fir. dings :n uncontested issues necessary to the issuance of a full-term cperating license for TMI-2, consistent with the terms of the Initial Cecisicn.

By Order dated January 3,1978, the Appeal Board alicwed the Jcint Intervenors until January 13, 1978 to file a Jupplemental memorandum in

_sucpert of their mction.

In accordance with the Acpeal 3 card's ruling, the Joint Intervenors filed "Intervences' Supolemental Memorandu.7 in Support o,f Motion for Stay of Initial Cecisicn" (" Supplemental Memoran-du.m") en January 13, 1975.

This Supplemental Memorandum addressed each 7B04200GBC fr 38-242

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_2 of the fcur criteria of 10 C.:R i 2.783(e) for g-anting a stay of the Initial Decisicn.

These criteria are:

(1) Whetner tne moving party has mace a strcng showing that it is likely to prevail cn the merits; (2) Whether tne party will be irreparably injured unless a stay is granted; -

(3) Whether the granting of a stay would harm other parties; and (4) Where the public interest lies.

The NRC Staff (Staff) believes tnat the Joint Intervenors have failed to satisfy the requisite criteria for granting a stay for the reasons set forth below, and therefore, the Staff c; poses the issugace of a stay of the Initial Decision.

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Whether the Moving Party has made a Strong Shcwing That it is Likely to Pravail en the Merits The sole thrust of the Joint Intervenors' argument that they are likely to prevail cn the merits is that the Initial Decision relies on Table S-3 and that Table S-3 dces not consider the Raden-222 that eminates frcm uranium mill tailings piles after the active life of the mill for an indefinite time into the future.1/ Joint Intervenors put forth these same arguments during the evidentiary hearing in the pecceeding and in

--1/ Supplemental Memorandum, page 2.

(38-243

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their proposed findings. :7/ The Licensing Board's Inicial Decisicn clearly shows that the Joint Intervenors' argument was considerec. E As the Decisicn notes, Jcint Intervenors' witness, Dr. Kepford, testi-fied under cross-examination that even with the significantly larger relcases of Rn-222 that he postulates, one is still oea 'ing with re'aases that are small compared with the natural background. 4/ Further, the Decision notes that the corresponding TMI'-2 related Mealth effects would sunt to an increased mortality rate of one additional death per billicn

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deaths from other causes over the time span of several billion years required (by Dr. Kepford's reckoning) to account for the decay of the c

parents of RN-222.1; Based on this analysis, the Licensing Scard found the relative impact of the Rn-222 censideration to be of negligible materiality. 6/ The record fully supports the Licensing Scard's determi-nation 7/ and Joint Intervenors have failed to assert any new arguments or evidence which would u dicate that the Licensing Scard determination is in error and that Joint Intervenors would succeed on the merits of their pending appeal of the Initial Decisicn.

-2/ Testimony of Dr. Chauncey R. Kepford folicwing Tr.2835; Findings numbered 96 and 97 of Joint Intervenors' Findings of Fact and Conclusions of Law, dated August 15, 1977.

V Initial Decision, paragraph 125.

1 S/ r.2866.

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-5/ Initial Decision, paragraph 125.

-6/ Id.

II See Tr.2864-2366 and Tr.2867-2875.

i 38~244

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The Licensing Scard notad that it was advised by the Staff that an ASL3 Panel member, Dr. Walter Jcrdan, alleged that an errcr exi;ted in Table S-3, that the testimony of the Staff's witness, Dr. Gotchy, ccmcaring ne

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health effects of the nuclear and coal fuel cycles might be affected by Dr. Jordan's claim and that the Staff cccmitted itself to a later assess-ment of the matter. 8/ The Staff has comoleted its assessment and the assessment is attached hereto as an appendix.

It consists of Affidavits by Jack E. Rothfleisch (dated January 18,1978); Hemer Lowenberg (dated January 20, 1978); Paul J. Magno (dated January 16, 1978); R. M. Wilde (dated January 20, 1978); and R. L. Gotchy (dated January 20,1978).

The attached affidavits demcnstrate that the value for Rn-222 in Table S-3 did not include releases fr.cm mining or frcm mill tailings after the active life of the mill. :/ The Gotchy affidavit demonstrates that the o

wide gap between the projected health effects of the uranium and ccal fuel cycles (in the testimeny of Dr. R. L. Gotchy, folicwing Tr. ISS3, the Staff estimated, at p.ll that the ccal fuel cycle would be more hannful to man than the nuclear fuel cycle by factors of 3 to 22) 10/-- i s not significantly narrowed by the addition of the increment frca the

-8/ Initial Decision, paragraph 124.

4:/ Affidavit of Jack E. Rothfleisch, p.3; Affidavit of Mcmer Lcwenberg.

--10/ These values were based en an assumptien that all of the electricity consumed by the uranium fuel cycle is produced by coal-fired piants.

If nuclear plants, instead, sucplied this energy, the health effects associated with the uranium fuel cycle would be significantly lower.

(Dr. R. L. Gotchy Testimony, following Tr.1883, Tabies 1 and 2).

58~24S

aspects of uranium nilling not previously considered.11/ Since the Licensing 2 ard assumed the correctness of Dr. Kepford's analysis, tr.e impact of additional releases cf Rn-222 frca mining or frca mill tail-ings after the active life of the mill was factored into the Licensing Board's decision. 12/ Thus, the Licensing Scard's conclusicn that

"...the nuclear fuel cycle is environmentally an acceptable alternative to coal..." 13/ is not affected by the revisions to the Staff's assess-ment.

For the reasons set forth above, Joint Intervenors, the moving party requesting the stay in this proceeding, have no'. made a strong showing that they are likely to prevail on the merits.

Whether the Party will be Irrecarably injured unless a stav is cranted The Joint Intervenors cite two instances of irreparable harm in support of their motion:

(1) the health effects attributable to the uranium mining, milling and separating activities conducted for the fuel that is planned to be leaded at TMI-2 and (2) the contanination and decem-missioning costs resulting from the fir:t fission reaction. la/

31I Compare paragraph (c) on p.18 of the Gotchy affidavit with Tables 1 and 2 in the Testimony of Dr. Gotchy, folicwing Tr.1883.

Table 8 in the Gotchy affidavit demonstrates that the estinated peculaticn doses and he31th effects attribucable to mining and milling wculd represent only a very small increase in doses and health effects from raden in the natural background.

--12/ Initial Cecision, paragraphs 125 and 129 k.

13/ Initial Cecisien, paragraph 127.

-14/ Supplemental Perorandum, p.7.

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With regard to a motion for stay the consideration of irreparable injary to a party involves ' hether there.till be irreversibic harm during *.h2 timo pericd that the acpeal of the Initial Cecision is being resolved, and not any alleged harm due to activities that precede cr follcw resolution of the appeal.15/ The irreparable harm alleged by Joint Intervenors concerns the future health effects resulting frca the mining, milling and separating activities related to the fuel to be loaded in the faciiity. This fuel already exists.

Granting a stay of the initial decisi.cn pending apceal will have no effect on the amount of releases of Rn-222 which will result from activities related to this fuel.

Further, th'e alleged irreparable harm is not to the Joint Inter-venors but to the general public at scme distant time.

Joint Intervenors' second allegation of irreparable harm relatas to their claim that the ccmmencement of operation of TMI-2 will result in radioactive contamination of the facility and to the ultimate need for decommissioning and decantamination.

The Staff does not believe that Joint Intervenors have stated a irreversible harm.

While it is true that cc=mencement of operation of the facility would result in scme radioactive contamination, that contamination..culd present no particular injury.to Joint Intervenors.

Moreover, there are known methcds of

.deccamissioning, decontamination and removal of waste materials.

15/ ublic Service Co. of New Hamtshire (Seabrcok Station, Units 1 & 2)

P ALAB-338, 4 NRC 10, 15 (1975); Northern Indiana Public Service Ccmoany (Sailly Generating Staticn), ALAS-i92, 7 AEC 020, 021 (1374),

d8-247

Whether the Grenting of a Stay Wculd Harm Othcr Parties The granting cf a stay would harm tne Applicants and their censume s ir that they would incur t!1e added c;erating costs of having to generate from other sources the electricity that would be generated by TMI-2.16/

This additional cost was estimated in the Staff's Final Supplement to the Final Envircnmental Statement to be approximately $7 to 8 million a month. 17/

Joint Intervenors assert that any costs the Applicants may attribute to delay in operation caused by the granting of a stay should be discounted since such delay Jas caused by the Applicant voluntarily. 18/ The reasons for the delays set forth in the NRC " Construction Status Recert",

NUREG-0030-77/7, the document cited by Joint Intervenors, dces not support this assertion. Whatever the reasons for the past delay, ence the plant has been ccmpleted, substantial ec.mcmic penalties to the Applicants and their custcmcrs would result f cm a delay in plant operations.

Joint Intervencrs have nct addressed these ecencaic penalties.

For these reasons, this factor weighs against granting the stay.

Where the Public Interest lies The Joint ir.tarvenors da not assert any public interest warranting the

. requested stay.

Their Supplemental Memorandum dces not support their 15/ Staff Ccunsel has been advised that the Ccemission Office cf Inspection,& Enforcement estimates that DiI-2 will be physically ready to Icad fuel between January 26 and February 1, 1973.

17/

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--- Staff Exhibi t 1, Secticn 8. 3. 3.

This estimate is based en the Applicants' estimated overall system c;eratien cost savings of c.ar

$55 million assuming T 11-2 cn line operaticn in May 1973.

---18/ Supplemental "emcrandum, p.7.

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claim that irreparable damage.:culd cccur to Joint Intervenors in the absence of a stay of :he Initial Cecisicn.

Cn the c:her hanc, :ne granting of a stay preventing fuel 10ading and cpernicn of :na ccm-pleted facility would have the effect of causing the Acplicants' cen-sumers to incur more costly producticn of power.

Accordingly, the public interest lies in denying the Motion.

Respectfully sucmitted, 7

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Henry $ McGurren '

Counsei for NRC Staff Dated at Bethesda,- Maryland this 25th day of January, 1978 38 249

UNITED ST?.TES OF AMERICA N C C L L c.a ' 2 C L L A J C h'. C u.. : 'SatCN

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CERTIFICATE OF SERVICE

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I hereby certify that copies cf "NRC STAF RESPONSE TO P.0TIO:! FOR STAY OF THE INITIAL CECISICN" in tne above-cactioned ;:roceeding have been served on the folicwing by de;:osit in the United States mail, first class or air mail,-or, as indicated by an asterisk, through dc;csit in the Nuclear Regulatory Ccm. mission's internal mail system, this 25th day of January, 1978:

Alan S. Rosenthal, Esq., Chairman

• Mr. Gustave A. Linenberger*

Atcmic Safety and Licensing Appeal Atomic Safety.and Licensing Ecard Panel U.S. Nuclear Regulater; Cc:r. mission U.S. Nuclear Regulatory Ccamission Was nin gic a, D. C. 20555 Washingten. D. C.

20555 George F. Trowbrir. ige, Esq.

Dr. W. Reed Johnsen, Member =

Shaw, Pittman, Pctts !. Trowbridge Atomic Safety and Licensing Appeal 1800 M Street, N. W.

Panel Washington, D. C. 2003o U.S. Nuclear Regulatory Commission Washington, D. C.

20555 Dr. Ernest O. Salo Professcr Fisheries Research Jerome E. Sharfman, Esq., Member" Institute, WH-10 Atomic Safety and Lice-ing Appeal College of Fisheries Panel University of W:.shington U.S. Nuclear Regulatory Ccemission Seattle, Washington 95195

' Washington, D. C. 20555 Dr. Chauncey R. Kepford Edward Lutca, Esq., Chairman

• Citicens for a Safe En.ironmen:

Atomic Safety and Licensing Scard 433 Orlando Avenue U.S. Nuclear Regulatory Commission State College, Pennsylvania 16E.

Washington, D. C.

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Karin W Carter Assistr.n e t k..: c '.

Atomic Sa t-/ 2 n'! Li: :'.-..:

General Appeal Panel

• Office of Enicrccment U.S. Nuclear Rgulate r. Con.n,.s ai::-

Department of Environmental Washington, D. C. 20555 Resources 709 Health and Welfare Building Decketing and Service Section Harrisburg, Pennsy1vania 17120 Office of the Secretar/

U.S. Nuclear Regularcry Commissica Ms. Judith H. Johnsrud Washington, D. C. 20555 433 Orlando Avenue State College, Pennsyleania 16801 Atomic Safety and Licensing Board Panel" U.S. Nuclear Regulaterv Cemnission Washingten D. C.

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Henry J./ U23urren Counsel for t'RC Staff a8~251

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AFFICAVIT OF 't.L. GOTCHY

/ i~_, l s c, Reginald L. Gotchy, being duly swcrn, states as felicws:

1.

I am a Senice Radiebiologist with the Radialegical Assessment Branch, Office of Nuclear Reacter Regulatien. A statecent of my professienal cualificaticns is attached.

2.

I have prepared estimatas of the raciclogical i=cact associatad with current staff estimates of raden releases frcm the uranium fual cycle. Tnese are set forth in the attached recort "Radic-Icgical I :act Frca Racen Releases". The statsments contained therein are true and correct to the best of :y S.newledce and belief.

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Aw Egiyag L. Gotcny Subscribed and s,,crn to before me this e day of 'h,1978.

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to-o My Cc=missica E.tcires 0Q G8~253

RACICLCGICAL IMP 2CT CF RACCit-222 ?ELEASES In a Septemcer 21, 1977 memorancum to James Ycre, Chair:an, A :mic Safety and Licensing 2 card Panel ( ASLSP), Dr. Walter H. Jordan, ASL3P, pointed out that the value in Table S-3 of 74.5 curies per RRY* cf Racen-222 release to the at=csphere dces not accurately represent all scurces of racen releases frca the uranium fuel cycle.

A number of other affidavits have been prepared which identify the basis for the value of 74.5 curies per RRY set forta in Table S-3 and whicn provide current staff assesr:ents of racen release, inclucing releases frcm mining and frcn stabilized mill tailings piles, two sources not covered by the 74.5 curies per RRY entry set forth in Tacle S-3.

I have estimated the radiolcgical impact asscciated with tne current staff raden scurce estimates shcwn in Table 1.

Table 1.

ESTIMATES OF RACCH-222 RCM ' TIMING AND MILLING CFERATICNS O? i.-i URANIUM FUEL CYCLE Estimata cf Raden-222 Scurce Operatiens Releases Document Incluced 74.5 (Ci/RRY).

WASH-1248 Milling Only 4'C60 (Ci/RRY)

R. Wilde Affidavit Mining 780 (Cf/RRY)

P. Magno Afficavit Milling and active tailings pile 350 (Ci/RRY)

P. Magno Afficavit Interim tailings Oile (inactive mills; cryi g prior c stacili:stien)

'RRY -- Rererence Aeac:cr Year (a 10C0 MWe lign: water reac:ce :ceratinc

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at SC% capacity facter f:r cne year).

Syncnymcus wi:n :ne annual fuel recuiremen: ( AFR) wi:5 the same cacacity fac:cr.58-254

9 2

Table 1. --Cent' d Esticate of Racen-222 Scurce Cperaticns Releases Cccumen:

Inclucee 1-10 (Ci/yr/RRY)

P. Magne Affidavit Stabili:ec tailings pile (for several huncred years) 110 (Ci/yr/RRY)

F. Magno A-fidavit Stabili:ed tailings pile (beyond several hundred years)

Thus, cur current estimates of projected populati n deses attricutable to Rn-222 releases asscciated with the uranium fuel cycle to suppcrt the operation of enc RRY censiders the 4,1CO.Ci/RRY frca mining, the 1,100 Ci/RRY frcm =fil cperations at an active pile and sucsepuent drying of the pile prior to stacili:stien, and the 1-110 C1/yr/RRY frca the stabili:ed pile.

1.

g iculatien of Projected Peculatien Ucse canni cents Using the RNCdD c::mcuter ccde develcced fer the GESMO prcceeding,I the staff has reevaluated population ecse cc:=nitnents for these scurces of Rn-222. The calculations have been ccrrected for the fellcwing:

(a) An error in ICRP-Publicstien 2 which resu!;ed in accut a facter cf 10 cverestimate cf the tctal bcdy dcse canni'=ent fran the ingestien cf the icng-lived Rn-222 daughtcrs (Pb-210,31-210, Po-210).2 (b) Conversion of the Rn-222 *s= eared lung" dose frca the shcrt-lived En-222 daughters (Pc-218, Pb-214,31-214, Pc-214) to a Orcncnial epithelium dcse (atcut a facter of 20 increase cver the GEIMO *stearec lung

• ccse fran the sacrt-lived c;..:ghtars).

1 GESMO, Nt; REG-CCC2,Section IV.J, Apcencix A (1975).

2 Letter to GES40 Hearing Scard, Cccket "c.

R'l 50-5, Acril 3,1977.

US 255

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3 (c) A ccnservative revision ucwarcs of the GESMC pc;ulaticn censities to reflect tne assu=ction that a stacle U.S. ;cculatien of 2C0 :illi:n afil be reacned in :ne year 2C20 (a: cut a SC% increase ever the pcpulati:n assumed in GESMO).

This was done by increasing the pcpulation density assu=ptiens in GESPC 2

2 (7.5 persens/mi in the west, rising exponentially tc 150 persens/mi 9

in the east aleng a 2000 mile path 1eng'h) to 11 persens/mi-and 235 2

persons /mi in the west and east, respectively.

The calcula*.icns indicate that the 1cng-liyed raden dauchters acccunt fcr abcut 40% cf the smeared lung dese. Thus, the dese ccanitment tc the brcnchial epithelium wculd be apprcximately 10 times the tctal (short-lived plus 1cng-lived daughterd GESMO " smeared lung" dese. The results are summartied belcw fer the est;. rated releases and release rates in the preceding table.

Table 2.

EST EATES CF RACCN-222 PCPULATICN CCSES AND COSE RATES FRCM MINING AND MI'_LD!G CPERATI:NS Envi rcrmental Case C=mi ments*

Estimate of (Man-rem)

Rn-222 Releases Total Ecdy Lunc Bene 74.5 Ci/RRY 3,9 42 5)

Mining (4,100 Cf /RRY) 110 2,300 2,800 Most Recent Milline Estimate (11C0 Ci/5RY) 29 620 750 Current Mining 1 Milling Sut ccalt:

14 2,900 3,500 1 Ci/RRY 0.025 0.56 0.58

• ine envirc=entai ccsa cermicent (ECC) is the sta of the 50 year integra ac peculation cases for each year of tne envirencental perice :eing censicerec.

I-this affidavit 100 year ECC's are used, altncugn as sncwn later, nert is litt!i difference etween @ year anc 100 year ECC's.

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4 Frco this table, the staff's current best estimate of mining and milling deses (prior :: stabili:aticn) wculd be accut ic0 man-rem (:::a1 becy),

2,900 man-lung-rem, and 3,600 man-bene-rem per RRY.

The 1-110 C1/yr per RRY release rate from stacilized piles reflects the curren uncertainty of long-term ;tability cf mill tailings: Current stabili:stien require ents for new mill applicants (for NRC licenses) would result in about 1-10 curies cf Rn-222/yr per RRY fer cericds of pernaps several hundred years.

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In crder :: respcnd quantitatively :: Cr. Jcrdan's ccncerns, it was assumed thac the stabilized tailings pile wculd emit 1 Cf/yr/RRY for ICO years,10 Ci/yr/RRY for tne next 4C0 ye'a s, then 100 curies /yr/RRY for perices beyond SCO years.

corrected for radicactive decay. This is consistent with P. Magnc's affidavit.

For pericds significantly beycnd a few hundred years, there are questiens concerning whether ene can rely cn maincenance of everburden :: Timit raden release to the a ncsphere, hcw soil meisture er other scil charac-teristics may change, etc., as well as very sericus cuesciens as to the ability to project health effects ever very leng' time perieds, wnich are discussed in the fellcwing secticn.

b b8 257

O Using the time varyir.g release rates assc=ec abcve, the cc ulative release and asscaiated peculaticn dcse cunnitmen s wculd be as shcwn in Table 3.

(Fcr discussion cf icng-term releases, see p.12.)

Table 3.

ESTIMATE CF RACCN-222 PCPULATICN CCSES FRCM

~ ~~ STABILIZED PILES PER RRY Envir 5r.mentai Ucse ccranit:en:s

~~ ~

Curies Time f yrs)

Releasec*

Total Scdy Lunc'*

2ene 1

1 0.025 0.56 0.68 10 10 0.25 5.6 6.8 50 50 1.3 28 24 100 ICO 2.5 56 58 500 4,090 110 2,200 2,5CO

__ 1.,000

.. 53,8C0 1, ?CO 30,C00 37,000 "Basec cn ne cecay of Thorium-220 and Ra-225 to Rn-222.

• • All lung deses here refer to :ne cecnchial epithelium.38-258

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6 It shculd be noted that because most of the raden lung cose is given almost immediately by the shcrt-lived raden daugntars (Pc-213, Pb-21;,31-214, Pc-214), the enviremmental dcse esmnitment (ECC) per curie release is essentially the same for a year,1CO-year, cr 1,CCO-year integraticn time.

The total-body and bone dose cccmitments frca long-lived raden daugnters

-(Pb-210, Si-210, Pc-210) are scmewhat more sensitive to the time selected for the EDC; however, there is only abcut a 12-14% difference between 10 year and 100 year EDCs.

2.

Calculations of Potential Health Effects The question of estimating health effects cver icng pericds'of time into the future is subject te very large uncertainties cue to several facters which, so far, arm uncentrclied by can. Risks estimates of health effects are based en past and present demographic and envircnmental statistics which are likely to change within the next few centuries. Scme important facters affecting health effects estimates are:

(a) Li'e expectancies whicn are depencent en other environmental pollutants, both natural and man-cace, stancard of living, and other social and tachnical facters.

(b) Age distributions Of pcpulatiens at risk are certain to change which will cause shifts in risk estimators with time.

(c)

Impacts cf can-made and natural events (e.g., wars, plagues, wide-spread starvatien due to crcp failures, ice ages, etc.) will aimest certainly cause significant variations in (a).and (b), therecy effecting the estimates of risks.

(d)

Unpacts of techncicgical changss (e.g., preventien of and cures fcr i

cancers, and genetic mcdificaticns in peccle carrying sericus genetic defects) can te expected to cause significant cnanges in :ne level of risk per Ci of raden released.

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Mcwever, if cne igncres these uncertainties, and assumes that the risk of health effects per Ci cf Rn-222 releasec to the at:cscnere remains as it is tcday, it is possible to calculate cetential health effects into the future.

It must be understccd, hewever, that such exercises are philoscphical in nature and may have no real meaning.

a.

Calculacien of Potential Cance.- Risks The cancer risk estimators used were taken feca WA5H-11C0 anc GESFC anc are so-called absolute risk estimators that are basec cn estimated latent pericds follcwed by periods of increased risk (plateaus).

These risk esti=atcrs cf cancer acrtality for total-bcdy excesure, lung expcsure, and bene exposure are 135,22.2, and 6.9 deaths per millicn man-rem, respectively. Current E?A risk estimatcrs for total-ccdy and lung excesure (brenchial ecithelium) are.

abcut 140 and 23-280 cases of cancer per millien =an-rem, rescectively.

depending en certain assumptiens. Fcr illustrative purpose s, I have prepared estimates of cancers per RRY based en ite cumulative releases and dcse cc=mitments shcwn in Table 3.

These are set cut in Tacle 4.

l' Personal ccc unicaticn, Dr. W. H. Ellett, U.S. Enviren= ental Protecticn Agency, Decemcer 21, 1977 and January 5,1978.

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S Table 4.

EST! MATES CF FOTENTIAL RI5X CF CA!:CER MCRTALITY.:RCM MINING AND LtILLI:G PER RRY Activity Lune Cancers

• Sene Cancers All Others Mininc:

0.C51

0. 01 9

0. 01 5 Active Milline &

Interim P1les:

0. 01 4 0.CC52 0.0029 Stabilized Piles:

(a) 100 yrs 0.0012 0.00047 0.00025

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(b) 500 yrs 0.C51 0.01 9

0. 01 5 (c) 1,000 yrs 0.67 0.26 0.19 Milline Totals:

(a) 100 yrs

0. 01 5 0.0C57 0.0043 (b) 500 yrs 0.065 0.024

0. 01 9 (c) 1,0C0 yrs 0.C68 0.27 0.19 Mining & Milling Totals for All Cancers:

Millina Minine Totals (a) 100 yrs 0.025 0.C85 0.11 (b) 500 yrs 0.11 0.C85 0.19 (c) 1,000 yrs 1.1

0. C85 1.2

=As notec in ne text, use of EPA estimates wcule increase tne risk of lung cancer sncwn ty facters of accu: 1.3 to 10 cecenci.ng on tee assu=cticns usac. E?A lung cancer esticates are 3.'sec on use of a relative risk ccel witn an assumed lifetime plat;au, witn allcwances for ccepeting causes cf death.

~

13f3 ' E?(51.

- --. k 9

b.

Calculation of Pctential Genetically Cetermined Health Effects Similar calculations can be carried cut for potential genetic ef+ects using the GESMO risk estimators. These ' risk esti=ators represent a mixture of fatal and nra-fatal but damaging genetic effects expressed in future generations when the mutations have been dis-tributed thrcughout the gene pool and are cccurring.at a nearly constant rate (i.e., equilibrium). The numerical values assu=ed are the gecmetric means of the ranges listed in the Naticnal Academy of Sciences report by the Ccmmittee en the Biclegical Effects of Ioni:ing Raciation (BEIR Report-1972). The Envircnmental Protection Agency has contracted with the National Acacemy of Sciences to update its 1972 report. Mcwever, until that report is ccmpleted, the staff feels the 1,972 SEIR Report is tne test reference to. empity for genetic risk assessments.

The numerical values of the risk of dominant and complex genetic diseases are 153 and ICO per millien man-rem, res:ectively. The

tal of 253 health effects per million man-rem can be apolied to cne tctal-tedy EDC's listed in Tables 2 and 3 :: previde estimates of potential genetic health effects as shcwn in Table 5.

o8-262

10 Table 5.

ESTIMATES CF POTENTIAL HEALTH EF:ECTS OF GENETIC CRIGIN RCM MINING JND MILLING PER RRY Activi ty Potential Health Effects of Genetic Oric1n cer Aaf Minino:

0.02P Active Milline &

Inter,m Piles:

0.0075 Stabilized Pfles:

(a) 100 yrs 0.00C67 (b) 500 yrs 0.02S (c) 1,000 yrs 0.36 Millino Totals:

Minine & Milline Totals (a) 100 yrs 0.0082 0.036 (b) 500 yrs 0.036 0.C64 (c) 1,000 yrs 0.37

0. 40 e

G

=

11 3.

Conclusiens Examination of Tacles 4 and 5 incicatas that:

(a) The risk of cancer mortality is abcut 3 times greater than the risk of all genetically related health effects.

(b) Over the short-term (e.g.,100 years), the risk' of potential health effects fran raden-222 results princi-pally fran releases frca Tining and. active milling c::eraticns.

(c) At times of abcut 1,0C0 years and beycnd the risk of pcten-tial health effects fran raden-222 is daninated by releases frca tailings piles which were stabili:sd at the end cf milling cperaticns.

A11cwing for the possibility that the relative risk method with a lifetime plateau is more correct than the absolute risk method with a 30 year plateau, we believe that the estimates of pc*.sntial health effects over the next 100 years are accurate to within abcut one orde:sc f-magni tude.

On the other hand, we agree,wi n :te 3EIR Report's conclusion that the possibility of health effects frcm acci'icnal radiation exposures which represent a small fraction of bacxgrcund radiation exposures may indeed be zero.

If the latter case is cctrect,we have everestimated the health effects.

In any event, if the fer er is true, cur estimate wculd still be within an crder-of magnitude, and wcuid not result in a measurable increase in health effects ever these due to backgrcund radiaticn.

i US 264

6 t

12 For time pericds in excess of accut 500 to 1,CCO years, there may be 2 or mere orders-of-magnituce uncertainty in estimates of health effects. ' The uncartainty bcunds balleen when the possible differences in relative vs. absol.uta risk assessments are added to the larger uncertainties regarding

• demographic variables ef future populations such as pcpulation density (cculd vary by factors of I to 2 crders-of-magnitude) and years at risk per person (cculo easily vary by factcrs cf 2 to

~

5 dependi..g en pepulation age distributions, life expectancies, and medical treatments for prevention and cure of scnatic anc geneticq11y related diseases).

In addition, doses cculd change y one or more orders-of-magnitude since the stability of tai'ings. pile ~

and transport pathways cculd be ccnliderably altered by natural and man-made events over geologic time periods. So large is this uncertainty that the staff feels such speculaticn is meaningless, anc obscures the important fact (as will be :newn) that the potential health effects in any pu;ulation living new or in the distant ana uncertain future as a result of raden-222 emissiens frca the uranium fuel cycle will always represent an immeasurably s=all increase in those health effects ccrurring as a result of backgrcund radiaticn and other naturally eccurring and man-made envirer. mental polutants.

In addition, decisions made by man cculd altar raden release rates in the future (i.e., cec';sions made tcday with respect to staDilic2ticn

~

b8-265

13 cf tailings wculd not be irreversible, either frem tne stancpcin: of technology or costs in the foreseeable future). As a result, it is the Staff's position that health effect estimates should be limited to those pe'iccs of time for shich reasonably credible estimates can r

be made. For purposes of this assessment, the Staff believes that the 100 to 1,CCO year pericd consicered in Tabl'es 3, 4, and 5 is appre-priate.

Althcugh estimates cf potential health effects cver very 1:ng perieds of time are meaningless fer the reasons given abcVe, for perspective, I have provided projectad deses frc= raden releases fran mining and milling (fcr the c:nditiens assumed en p. 4 cf t.51s testimeny) to pernit c;=parisons with d0ses attributable to raden in natural back-grcund. These are set cut in Table 6.

Perieds beycnd 10,000 years were not censidered since current evidence indicates perfedic glacial perieds will. cause significant resha:ing cf the surface alcng tne continental di9fde where mest.cf t.Se tailings piles would be 1ccated. Thus, Rn-222 releases wcuid be ex ected to decrease to zero when c:vered with an ice sheet then resume at an unpredict-able rate when the ice sheet recedes (i.e., the piles cculd be scread cut en the surface or c vered by additicnal overturden).

Using the time varying release rates assumed above, the cunulative release and asscciated peculaticn dose c==nitments wculd be as shewn in Tacle 5.

N 3g-ggg

L 14 Table 6.

ESTI.'9TE CF LC '3-TEF ! R.:CC 1-222 FCPULATIC:1 CCSES FRCM ST'3 LI I2 :?LES :E: ::Y inv1rcr. men:ai ;csa Ccal ments (Man Ren)

Curies Time tyrs)

Releasec' Total Body Lune **

5ene 1

1 0.026 0.56 O.68 10 10 0.25 5.6 6.3 50 50 1.3 28 34 100 100 2.6 56 68 500 4,090 110 2,300 2,300 1,000 53,8C0 1,200 30,000 37,0C0 5,000 443,0C0 12,CCO 250,000 2CC,CCO 10,000 912,0C0 24, CCO 510,CCO 620,CC0

'Sasec en :ne cecay of Thoriu=-220 and Ra-226 :: Rn-222.

• • All lung doses nere refer to t.9e arcncnial epit.ieliu=.

6 e

b k

08-267

15 l' 2 cf raden emanatien frcm scil incicace At the present time, estimates that accut 1 to 2.4 x 10 Cf of raden-222 are released cer year in tne cen-tigucus U.S.

NCRP also states that the averace Rn-222 cencentraticn in the U.S. is abcut 150 pCi/c2, which they estimate will result in a dose e,f 450 mrem / year to the brcnchial epithelium of tne average persen.

If one makes the same assumptions with regard to future populations

&s was made for the mining and milling releases, it is possible to calculata potential future icng-tern peculaticn deses frcm Lackgrcund raden-222 as shevn in Table 7.

These calculaticns use the same dose per Ci released as used in Tatles 2 and 3 (i.e.,

O.025, 0.56 and 0.53 man-rem per Ci for total-bcdy, lung and bene, respectively). The estimated maximum percentace increasr; in icng-ter r pe,culation doses and health effects per RRY are shcw.t in Table 8.

Table 8 demonstrates that regardless of the period selected, Or. Jcrdan was correct when he concluded (p. 7 cf his memcrand:m) that "the number is insignificant ccmcared to these due to raden cantaminatien in natural backgrcund," and that the authors of 'JASH-124 were carrect in their belief that " population desas frcm t' tis source cannot be distinguished frca backgrcunc".4 1

Publication 45, National Ccuncil en Rcr;iation Protecticn and Measurements, (NCRP) p. 80, (1975).

2

' Natural Envircnmental Racicactivity frcm Racen-222", U.S. Department of G, PHS Puc. No. 999-RH-25 (May,1967).

3

[

NCRP-45, p. 87.

4 ASH-12'd, Envircr. mental Surve;y of the Nuclear Fuel Cycle, p. 3-23 (April,1974).

. - ~.

,i

..TAplE7, ES,TIMATED LONG-TERT 1 POPULATION DOSES FROM PACKGROUND.

RA00H-222 C0HPARED TO HilllHG AND HILLlHG ONE RRY Environmental Dose Consnitmentjman-rem {

g Backgrnund Rn-222.*

Time (yns.1 Hining & Hilling

.TB 1.ung Bone T_B Lung Done 100 1.4E2 3.0E3 3.7E3 2.6E8 S.6E9 6.0E9 I

~

S00

2. E2 S.2E3 6.4E3 1.3E9 2.0E10 3.4E10 1,000 1.SE3 3.3E4 4.lE4 2.6E9 5.6E10 6.0E10 5,000 1.2E4 2.SES 3.0ES 1.3E10 2.0 Ell

^ C.1 4

10,000 2.4E4 5.lES 6.2ES 2.6E10 S.6F'.i 6.0 Ell m

e IAssumes ili:23:Fis always in secular equfTilirlum with U-2.TG in n5Tiire.

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- iw 4tD MILLI?:G C'IE RRY Time (vrs)

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la In summary, the staff has reevaluatec ne Rn-222 releases and subscquent pc;ulaticn dose ccmmicments, and potential health effects questiened by. Dr. Jordan in his Septamter 21,1977 memo-randum, and concludea the follcwing:

(a) The mining and milling releases for a 100 to l',000 year perice per RRY are:

Mining:

4,100 C1 Milling:

(1) Active milling and drying of tailings pile prior to stabili:ation:

1,100 C f.

(2) Releases frcm stabili:ed tailings piles for 1C0 to 1,000 years: 100 to 53,0C0 Cf.

Total: C,3C0 to 58,C00 Ci (b) The population dose ccmmit=ents (man-rem) for a 100 to 1,C00 year period per RRY are:

Tctal Body Lune Sone Mining:

110 2,300 2,cC0 Active milling & drying:

29 600 750 Stabili:ed tailings pile:

2.5-1.4C0 55-30.CC0 58-37,CCC Total s:

140-1,500 3,000-33,0C0 3,5CC 21,0C0 (c) The potential health effects for a 100 to 1,000 year perice per RRY are:

Cancers Genetic Effects Mining:

0.C35 0.023 Active milling & crying:

0.023 0.0075 Stabili:ed tailings pile:

0.CC2C-1.1 0.CCC57-0.25 Total s:

0.11-1.2 0.025-0.20 38-271

p

v..

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? f ass 10:a1 Qualifi:stiens My cz=a is Reginald L. Gotchy. I as a Senic: Radi:biol gist en assign =en:

with the Radi=legical Assess =ent 3 :ch in :he Office of !!uclear Resc:::

Regulacien. In this espaci:y, I as responsible f=: cecedi: sting :he technical review and e::' a:1:n of the envir::= ental radi:1 gical i= pact of nuclear fac111:7 epers:1:ss.

4 received a 3.5. ir...cology frem the University of'Washi=g::

in 1958, an II.S. in Radia:ica Eealth from :he Colorado Sta:e University in 1966, a Ph.D. in Radia:1:n 31 l=gy frem the Col::ad: S:a:e Universitf in 1968, and attended the Universi:7 ef Washing::n G:sdus:e Scheel 1953-1959 as an AIC Radi:1 gical ?hysics'Fellev.

~

I have 16 years of pr:f assicesi e=perience in Haal;h Physics, Industrial Hygiene, Radiati:n Physics, Radia:1:n 31 elegy, Invi:: _en:al Sciences, F: jec: Cecrdinati:= cf resesr:h and devel:p=ent p = grams, and devel:pren:

of AIC and :KC s:sddards. This e=: erie :e has included operatic al and safety respensibill:1es, and review and c:ordinati=c of facili:7 opera:i s u= der centrac: := he AIC.

I have been e::10 fed bv. the Lam esce ladiation Labors:: 7, the U.S. Public Eealth Service, laynolds and Ile :rical E=gineering C =pany, the AIC Tevada Opersticus Office, and the NRC Office i

of Sta=dards Development prior to =y assign =ent in :he Cffice of ~ucle.ar Reac::: Regulation is 1975. I was an adjunc: professer of Radiscica Esalth,Technol:gy a: the University of lievada, Las Vegas (1969-1972).

I as a =e:ber of Sig=a II (2asearch Society of !?ce:h Ameri:a), :he A=erican Nuclear Society, :he Heal:a Physics Society, sud the In:er:stic:al Radta:icn Pr :e::10: Assoc 12 1:=.

I z:s certifiad by the A=arican Zeard of Heal:h ?hysics, and se: red as a

= ember of :he Panel of T-r

'ners (1972-1975).

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@\\l1c /? ' s, qs UNITED STATES CF AMERICA . ss

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\\ NUCLEAR REGULATCRY CC:'li!SSICN il/ ',el

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AFFID AV'T CF R.M. '.iILDE DA

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• Ralph M. Wilde, being duly sworn, states as follows:

1. I am Program Assistant to the Director, Divisic, of Fuel Cycle and Material Safety, Office of Nuclear Material Safety and Safeguards. A statement of my professional qualifications is attached. 2. I have pre::ared estimates' cf the radon released as a result of mining of uranium as par: of the uranium fuel cycle. These are set forth in the at,tached decr.ent "Raden-222 Release Frem Uranium Mines". The statements contained therein are true and correct to the best of my kncwledge and belief. aa w. /s/J ~ Ralph M. '.4ilce Subscribed and swcrn to before :e this ac* day of 1973. O - S 0 %%2 Nctary Pubiici My Cc=aission Expires O J' 'c'9 s 0Q b8~287

RACCN-222 RELE*SE FRCM URANIUM MINSS Hi5:crical Backercund The release of radicactive material to the at=cspnere during mining cperations is briefly discussed in two doc =ents issued by the Nuclear Regulatory Cc= mission prior ta the publicatien of NUREG-CCO2, Final ~ Generic Enviren= ental Statement en the Use of Recyc1'ed Plutonium in Mixed Oxide Fuel in Light Watar Ccoled Reactors (GESMO)I Both of these documents discuss: (1) The release of uranium bearing dusts, as well as Raden and its daughters, during mining cperations; (2) the unavailability of data on the a= cunt of radicactivity released durinc 2 mining; (3) the unsuccessful attamc+.s by the Eureau cf Mines to measure significant cancentraticns of airborne alpha radicactivity in cpen-pit mines; (A) and the insignificant concentraticns of airterne alpha radicactivity in areas adjacent to these mines.3 The final GEST 0 was developed as a =cre ccmprehensive generic assessment than either of its predecassers, WASH-1248 and WASH-1327. Thus the enviren=encal impacts were addressed more cc= letely and accurately. It was my cpinica, b sed en my experience in the urEnium mining and milling industry, despite the unavailability of confirming cata, that mines 'Enviren= ental Survey of the Uranium Fuel Cycle, WASH-1248, USAEC, (April 1974). Craft GESMO, WASH-1327, USNRC, (August 1972) U.S. Cecart en: of the Intericr, Sureau cf Mines, District E, Memerandta File 137.2 (1968) 3XIerent, A.W., Jr. et. al., "Esti=ates of Ionizing Radiation Ocses in the Unitec States 1960-2CCO*, CR?/CSD 72-1, USEFA, (Augus: T972). ., 6. g b d ,,. v

p- +.. 2 centributed the major partion of the raden released to the envircreen: during the c erating life of a mine-mill c:= plex. Thus, in late 1972, ,the scaff decided that we should attempt to provide a quantitative esti=ste of the scurce term fer raden released frem mining cperaticns for the Final GESMO. DE'lELCpMENLCF THE GESMO SCURCE TE.M ICR MINI.% E. :LUEMTS The data which provided the basis for the scurce t en were cbtained by personal telephcne :::munications fecm T a scurces: James Clevel nd,- Kerr-McGee Nuclear Ccrpcration, Grants, New Mexica (January 30, 1975); anc Edward Kauf=an,,New Mexico Enviren= ental I:;revement Agency, Santa.:e, New Mexico (Fecruary,3,1975). I had been asscciated professicnally with 'coth of these men for several years while I was emolcyed with Anaconda in New Mexico and I knew that they were both kncwledgeable of c:nditiens which existed in uranium mining cperations. Ecth of these individuals supplied me with their estimates of raden c ncentraticns in the ventilation air discharged fr:m underground uranium mines (basec cn limited sa=: ling data) together with additional pertinent infermaticn. This informaticn included data :n: cre production rates, ventilation ficw ratas, number cf ventilation shafts, etc., such as was necessary to calculate the a: cunt of raden discharged per ten of cre mined'. A smanary of the data supplied fc11cws. A. Cata Socalied bv E. Kaufman These data represent Mr. Kaufman's estimatas of the tycical characteristics ( of all of the underground uranium mines which were cperating in New Mexica b8-2S9

3 (Ambrcsia Lake area) in late 1974 2nd early 1975. At that time, under-grcund mines in New Mexico pecduced accrcx mately 753 cf the total U.S. production of uranium cre frca undergrcund uranium mines. Estimated radon concentration in ventilation air 1,200-1,5C0 pCi/ Ore production (Actresia Lake) 7,500 ST/ day Nu=ber of ventilation shafts (Ambrcsta Lake) 60 Shafts Air volume per ventilatien shaft 40,000-50,CCC CF' Mines cperate in an cre production mcde apprcximately 2C0 days / year Cre grade apprcxi=ately 0.2% U,0-

• C B.

Data Sucolied by J. Cleveland These data represent Mr. Cleveland's estimates of the typical characteris- . tics of,the undergrcund mine operated by Kerr-McGee in New Mexico in late 1974 and early 1975 and are thus a subset of the Kaufman data'. ~ Estimated raden concentratien in ventilation air 1,0C0-1,'5C0 ;Cif-Cre production (Kerr-McGee) 5,0C0 ST/ day Number of ventilaticn shafts (Xerr-McGee) 35-40 Shafts Air volu=e per ventilatien shaft 45,0C0 CFM Ventilatien shaft fans cperate 2? hcurs per day 265 days per year Frem my experienca in the industry the data supplied appeared to be re'ascnable and, therefore, was used as the data base frcm which the scuece term for raden release frca uranium mining was calculated. Frem the preceding data, the release cf Raden-222 per me:ric ten cf cre mined may be estimated. a8-290

4 , annual Cre pr: duction (0.2% U 0 :re) 33 c (75CO _ST) (2CC Cav) (0.907 MT) 2.04 x 10' MT = Day 'f r i si fr a Annual Radon Discharged frc= Mines prcducing 2.04 x 10" MT/ year (60 vents) -(45,CCC CF?i/ vent) (23.32 1/C") (5.256 x 10 =in/ year) (1.5 x 10r9C1222Rn/1) = 6.03 x 10 Ci"99Rn/ year 4 Release per =etric ten of 0.2% U 0 Ore 38 6.03 x 10 C f "99Rn/vear = 2.96 x 10-2C1 En/MT Gre ~ 2 2.04 x IU*.% / year In GE90 it was assumed the average cre grade pr: cessed during the pericd 1975-2000 would be 0.2% U,0.,, not 0.2% as a:cve. ine rnicnale for this .e assumption is that the cre reserves and rescurces which c:ntain the required 6 a==unt of uranium (1.6 x 10 short : ns of U 0 ) are projectad to have an 33 , average of appr xi=ately 0.1% U 0. Tne additional assumption was =ade 33 taat the a= cunt of raden released wculd be directed preperticnal t: the grade (uranium content) of the cre. Tne rationale f r this assu=: tion is that raden wculd be in secular equilibrium with the parent uranium and, therefore, directly prepcrtional to the uranium c:ntant cf the cre. The corrected value of raden release for the icwer grade are used in the GE2C =cdd =ay be calculated as follcws. Release per =etric t:n of 0.1% U 0 Cre (Gum 0) 33 0.1% U 0-(2.96 x 10 1C i "o,Rn/MT) = 1.48x10 2Ci 7n/MT Cre ~ zon 0.2%ujaj This calculation gave =e what I censidered Oc be a re?.senable estimate fer the raden release fr:= undergr und =ines.

4 -~ ,.. ~. _ -. l 5 In the printing of GESMO, due to a typographical errer, this value 299 appeared as 1.5 Ci - Rn per metric ton of cre mined (seccnd fcctncte to Table IV F-5, page IV F-22). A correction was made in the GEIMO errata. The raden release frca mining per AFR (Annual Fuel Requirement) was calculated frca this release rate (1.5 x 10 Ci 22'Rn/MT) and the amcunc 7 a cf c~re required to supply the uranium for cne AFR (2.71 x 10' MT). Raden release per AFR 2 299 e 999 (1.5 x 10 Ci - Rn/itT) (2.71 x 10 MT/;'.') = 4060 Ci-- Rn/AFR INDE3ENDENT CCNFIFl%TICN CF GESMO SCURCE TI:li As a result of the errenecus v.lue (typc) which a;; eared in GESMO, representatives of the uranium mining industry quescicned tha validity cf the scurce term for raden release frcm mining. Subsecuencly, in October 1976, Kerr-McGee ccnducted an inde:endent invescigaticn cf raden released from their undergrcund uranium mine vencilation syscems in the Ar.brcsia Lake area cf New Mexico. The results of this iavestigaticn were sen cc ce by a ietter dated December 9,1976, frcm W. J. Shelley, Director, Regulation and Centrol, Kerr-McGee Nuclear Cer;craticn. The unit release vaIus cbtained by Kerr-McGee in their indecendent investicacion was 222 1.5 x 10-2Ci Rn/Mt cf cre mined. This value is ne erically equal to the l t)bh

• A-

6 y t GESMO value. Mcwever, the agreement between the two values is not quite as gced as it a;; pears en the surface, since the grade of cre prcduced by Kerr4tcGee during the sampling ;:eriod was prc:: ably closer c 0.2P. U 03 3 :.9an to the 0.1% U rJ cre grade assumed for GES"O. 33 e e O G 4 h P h e 9 e D 9 e O O at3 na,a

i i . St" MARY The source tern ia GEIMO fcr radan frem uranium m.ining c:eraticns was ' calculated frem estima:es provided by ex:erts wnc were kncwiedgea:le cf the c:nditions which existed in uranium mining ccerations. The indecenden investigation made by Kerr-McGee, which was based on actual measurements, c:nfir=ed the GESMO scurce term within a facter cr' about 2. It is of interest to note that the mines which were sampled by Kerr-McGee in their investigation produce accreximately a third of the U.S. production of uranium cre frem underground uranium mines and thus shculd provide an adequate sampling base. I censider the agreement between the scurce tenn estimated fer GESMO and from Kerr-McGee's investigaticn to be gecd. We new have underway a study to determine actual raden releases from undergrcund and cpen pit uranium mines. The early results cf this study, which shculd be available in mid-1978, will provide a better basis for review of this matter and a mcre accurate estimate of this scur:e tarm. I believe that such additicnal data will shcw that the estimates c:ntained nerei,n for raden releases frem undergrcund mines are reascnable. Fcr caen pit mines, until sucn study is completed, there is just no reliable infermatien available ucen which-to base estimates cf raden release. (,3t3 e id -

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- c,- -, t ! __ia ?.:.; ', PROFESSICNAL C.UALIFICATICMS '+ [' v 'N" R. M. Wilde s 4 U. S. Nuclear Regulatory Ccmmission - y, s e ~ I received my Bacheict of Science Cegree in Chemistry frca Brigham Ycung University in 1955. In March 1955, I startad to werk as an analycical chemist at the uranium cre prccessing pilot plant which was cperated by Nacicnal Lead Cc=cany in Grand Junceic., s Frca Colorado under contract with the Atcaic Energy Ccanissicn. March 1956 to December 1956 I was empicyed as assistant chief ch'emist at the Rare Metals Ccrporaticn uranium cre processing mill in Tuba City,' Arizona. In January 1957, I accepted the pcsition of Assistant Metallurgist in The Anaconda Cemeany's uranium cre precessinc mill in Grancs, In this position I performed metallurgical research ar.d New Mexico. testing for both an acid-leach and an alkaline leach mill circuit. My primary duties included develep=ene, testing and evaluacica of I was aisc ian-exchange prccesses for the acid leach curcuit. involved with testing and evaluatien cf varicus leaching methcds fer sandstene and limestene uranium cres. The cbjectives of these investigations were to reduce prccess Icsses and to deteroine the mest ectncmical me*.ncds of cceration of the r,ill. In Decemcer 1953, I became Radiatien Safety Directer for Anacenda's New Mexico In this pcsitica I was rescensible for surveillance Operations. c8 e 05 9~ ,3 a

_2 and centr:1 of occupational and envircnmental radiation hazards in Anacenda'i uranium mines and mill. I was employed by Anacenda for T6 years. I came to the 'luclear Regulatcry Cc. mission in January of 1973, and currently I am Prcgram Assistant to the Directcr, Divisien of Fuel Cycie and Material Safety, Office of.'fuclear Material Safe:y and Safesuards. S e O e e g O I e 9 mum e e + k o )

\\p1 7N n 4. ~ o c sc c;:a: 5- 'r o gJ Mc g t o ~q3 P r- ! ,4 C~' .... s d-Mi sq ~ c. AFFICA'!IT OF PAUL.J. "AG.1C 0 S, ^- / /.tv i Paul J. Magno, of Reckville, Maryland, being culy swcrn, states as fc11cws: 1. I am a Health Physicist with the Divisicn of Fuel Cycle and Material Safety cf the U.S. Nuclear Regulatcry Ccmmission and my professicnal qualifications are attached hereto. 2. Mr. Ro-hfleisch has indicated the basis fcr the staff's estima a in WASH-1248 of the raden-222 releases from uranium milling during active operations. Since this estimate was made, the staff has carried cut additional assessments of the raden-222 releases frc= uranium mill tailings and has also developed a series of performar.ce objectives for the waste management of tnese tailir.gs. Using this additicnal informaticn, I have estima ad the release rates of raden-222 frem uranium milling operations. These estimates include releases frcm :ne tailings areas folicwing cessaticn cf active milling whicn as indicated by Mr. Rothfleisch were not included in :ne raden-222 release estimatas presented in WASH-1213. 3. These raden-222 release rates are expressed in curies per annua! fuel . equi remer.: (AFR) for a ICCC Mwe reac cr cperating at an 20". cacacity fac:cr. These estimates wnica are presented belcw were develeced taking inte censidera:icn raden-222 releases frca (1) milling cf ne 1 l US 2S7

cre, (b) tailings areas during active milling, (c) tailings areas during the interval between :ne end cf active milling c erations and final stabilistien and (d) stabilized tati1ngs areas. Raden '.22 Releases frem Millin: C erations . Scurce c' Release Curies ter A : '41111ng of Cre 30 Tailings Curing Active Milling 750 Tailings During. Inactive Period 250 ~ Sub:cta1 l120 Tailings Follcwing Stabilization 1 - 10 (curies per year per AFR) The detailed basis and calculations for these raden-222 release estima es are presented in the felicwing secti ns. 4 E-i.v. e i :_ t e : c er.!_ m- ::: :,e_ r_; nL.: n.o.C.

m.. _i...'c a-

..cre_e-2 w. _ a -_2 Raden-222 releases curing cre s:Orage and processing were estima:ec (C assuming :na: the raden-222 is in secular equilibrium witn tne ;ranium-222 in the cre and (b) using an esca;e fraction (emana:ing pcwer) of 0.4 The emanating ocwer (E) is the fraction of raden-222 fer ed wnich escaces one scurce particles. Fce both natural soils and uranium mili ; fiings, E was f und :: be accut 0.2 (I) A value of E = 0.4 has been usec i.c :nis estima:e in order to take into ac:cun: :ne pc en-ial effec: :nat var cus i ( stecs in :ne milling precassas (i.e., grinding anc ieac.,ing) may rau :n One ecanating pcwer of t.* e cre particles. b8'2Ob

. Calcul nicn of A.:R 're Ecutveiev. (*) . 1 AFR = 215 MT U,0 a3 1 MT ore = 0.001 MT U-Ce x 0.9 recovery = 9 x 10-E U?0o MT ore fac:cr MT cre 1 AFR = 245 MT U-02 = 2.72 x 10* MT ore 9 x 10~# MT U,0c MT cre Calculitien of Ecuili'rium Raden-222 Activity in Ore c 9 222,,n, Ci 0.C01 MT U-Oo x 0.348 U x 0.33 Ci = 2.3 x 10~ Ci = A..i ore M. cre U308 d. U ' ' " cre a Calculation of Raden-222 Release cer AFR 2~"~Rn, curies = 2.3 x 10-' Ci x 2.72 x 10~ MT cre x 0.4 = 20 n r..- A.s cre nrn n; F,, -cJ. 7_.33 - -..,n, i : ._e e .c., .t..,ca -n ,.,r. ,,e L.-..Lc t.,,7.,, c.

si t, n u s: :

_..s v n. ..__..e Estimates of the raden-222 releases frca the tailings area during accive milling were made based on a ccm;csite model tailings cile developed e, J3 g requirement for no recycle cc:icn frco GE3F0, Table I'!J'E)-17'C 0 (*) This is tne mcs: conservative cc icn since it recuires ne larges-cuanti y of U;03 cer AFR. I \\ - 900 J ns J

.a_ frcm information presented ir. CRNL-7A 4903, '/cl.1 (Table 4.13). ('l 3 Using this mccel, cne AFR (2.72 x 10 MT tailings) wculd ccver 2.9 acres of tailings area to a desta of 33 ft. For a mill prccessing cre centaining 0.1% U 0 and having a 25 year life, tais wculd result in a release of 33 about 750 curies per AFR. The basis for this estimate is as follcws: Calculatien of Tai 4ines Area car AFR Table I shcws the method used to arrive a ne ccm;csite ecdel tailings 7 pile. This piie contains 1.33 x 10 MT of tailings anc near the end of mill life covers 140 acres (105 acres of pend and wet beacn and 24 acres of dry beach). A conversicn facter of 0.0205 (2.72 x 103 + 1.33 x 10 ) is used to normalice the area of the ccmposice ta.iiings pile into area per AFR. Area of Ccmposite Conversien Area per AFR Tailines Area, Acres Factor Acres Fcnd and Wet Beach 2.17 105 x 0.02C5 = Cry Beach 0.70 x 0.02n.: s Total ltilings Area 2.37 140 X 0*02n5 = ~ Calculation of Raden-222 Release cer AFR Scurce cf Release Acres Release Race Years cf Curies APR curles curies Release ., F A acre-yr .-? R -y r 33 Pond and Wet Beacn 2.17 1.C4 2.25 '25 = i~gi Cry 3each 0.70 32.2 25.7 25 = /:- Total Tailines Area b8 300

5-This calcula:f cn.as ade using ne c:nserve:ive assume-icn tha- -he celease rate during tne 25 year mill life was equivalent to the release rate near :he end of mill life. The release rate per acre-year for the pond and wet beach area was calculatec from data presented in CRNL-E4-4902, Vol. 1 (Table 4.20). The release rate frca the dry beach areas was calculated using the following formula which has been derived frem simple one-dimensional diffusion theory (CRNL-TM-4903, Vol.1, p.146):

li,

7 J =0C A x 4.05 x 10'cm-x 3.15 x IC sec. o ev D /v acre year e where: ~~ ~~~ J = raden flux in Ci/ acre-year 3 O /v = effective diffusion c: efficient = 0.054 c=?/sec (CRNL-e TM-4902, Vol.1, Table 9.29) = decay constant of radbn-222 = 2.1 x 10-6 sec"I A v = void fraction = 0.37 C, = ::ncentra:icn of raden in voids C =EC* v v where: E = emanating pcwer = 0.2 v = voic fraction = 0.37 C, = activity of radium-229 in tailings per unit vclure (2.3 x 10'39 Ci/g x 1.5 ;/

1. = 2.43 x 10-'" Ci /:2 3) i o

'O# e JD "

s. .g --.4

.l...,."

.... -..,/ n,,L m,e03 L,,L.%...-4 --..y.-- n-01 .o a..._ _s Ke vU. t - f.44 MO Q. ," a i 1. n i ; v. ..,_.s . h.., 1.,i,a m. v u v.v t :... u. 4 we s i.- c. u.,.. t. u.- .m t.e: .us ..n t_ The release of raden-222 per AFR frem the tailings area fer the interval between the end of milling and c:mpletion of stabilintien was calculated assuming a five-year pericd to dry cut the uilings and c;mplete the stabili n tion. The release rate of raden-222 fcr :nis pericd was estimated to be 350 curies :er AFR. Table II. shcws tne datails cf these calcula:icns? These calculations aere made assuming :na: ne pond and wet be. acnes cry cut linearly over the #ive year pericd and using the same release ra:es (curies per acre-year) as were used fer calcula:icn of release rates during active milling. O c RA

• C't m_ __ : =.__ c %' e r.

C.'i 5~i r' B 't L I 7:.D m' I' "..'Ge rn,' s.

u i .s. r. - Ie,i_3

2:

/. m The staff of the Division of Fuel Cycle arc Material Safety has recently devel:;:ed a series of perfor.ance cbjectives fcr an acce:::aale tailings management ; cgram fer use in uranium mill licensir.; actions ( To meet these perfor-ance cojectives, ali :GC licensac uranium mills (including license renewal actions) are recuire:. :: develop a tailings stabilintien and reclamation program wnicn. sill reduce the raden-222 release rate (flux) frem the tailings area :a a:cu-twice the release rate from natural soils in the surrouncir.g envicens." Tne n.sC s u ff is working c'.csely.ei:n :ne Agreemen: 5 2:es ic order : ~ have similar ;erf:r ar.ca ::jec:ives inc:r;;ra:ec i :: :ne 5:2:as' licarsi.; acticr.s fcr urinium -iiis. OS 202

The elease ra e of raden-222 fr:m uranium mill tai'ings areas ::abi',':s:

mee these :erf:rmance cbjectives is estima ed :: be '.ess -han :na curie per year per n,e-

-. is value was ca,t cu,.atec as.,,ciscws: in x The raden-222 flux frcm the tailings area is comprised of two c::: nents: the flux fr:m natural scils (cover materials) and the flux frem :ne tailings. Therefore, :: meet the performance objective that the rad:n-222 fTux from the tallings discosal area should not exceed abcut tvice the flux fr:= natural sails in the area, the rad:n-222 flux fr;: th e tailings tnemselves shculd not exceed a value about equal to tne #1ux frem :ne natural scils (i.e., backgrcund flux). Calcula. tion of Backereund Raden-222 Flux 3 1 7 J5=J C x 1.05 x 10 m-x 3.15 x 10 sec o s acre year where: J = backgrcund raden flux in curies / acre-year b o J = raden flux in Ci/m -sec per pCi/g of racium-225 g in scil = 1 x 10-12 (1.0 pCi/m,3gc) 2 C = radium-225 concentration in scil = 2.5 :Ci/c s J = 0.32 curies / acre-year 3 e. 38~303

_a. This calculaticn is based on a radium-225 scii concentratice of 2.5 pCi/g whicn is c value at the upcer range of concentratiens of I5) radium-225 measured in natural sails in the '.lestern States The 2 raden flux value of 1.0 pCi/m -sec per pCi/g of radium-225 in scil was calculated using an effective diffusicn ccefficient (D /*) e 4 2 5.4 x 10 cm /sec which is a value acclicable to sandy soils (CRNL-Di-4903, Vol 1, Table 9.29). Curies per AFR per year = 2.9 acres x 0.32 curies = 0.93 AFR acre-year Although the taii'[ngs disposal area will be designed for a raden-222 release rate not to exceed abcut I curie per year per AFR, the estimated raden-222 release rate frem the taiTings has been excressed as a range frca 1 - 10 curies per year per AFR to take into acccunt uncertainty abcut the integrity of the stabilized tailings areas over long periods of time. Siting and engineering design futures recuired to assure icng-ter-stability are incor; crated into final stabili:sti design. Bere are numerous specific methods for stabilizing the mill tailings. One attractive alternative presently being evaluatec is clacing :.9e tailings beicw grade in mined cut areas tc provide maximum assurance of icng-term stability. ( Tc reduce the caden release rate :: tr.e level s;eci ied in :ne staff's perfor ance cbjectives ai!I recuire be:aeen 5 and 20 fee: a8 304

.g. of csver material Over :na tailings. The am:unt of ::ver recuire: will cepenc u;cn the specific characteristics of :na scil wi-n res;ec: to the rate of diffusion of raden-222 tr-Ough the material. We believe such a stacilized pila will maintain its in:aprity over an ex endec e pericd of time like a-least several hundreds of years anc that any degradation, if it takes place, will be small and not catastrechic. 8. With respect to Dr. Wal.er Jordan's memorandum of Sep emser 21, 1977 Oc James R. Yare, Chairman of the At:mic Safety and Licensing 2carc, concerning errors in the racen-222 release estimates in Table S-3 cf CFR i 51.20, I agree with Cr. Jordan that Table 5-3 does nc: re: resent all sources of raden frca uranium milling activities. Furthermore, I agree with Dr. Jordan that releases of raden-222 fr:m tailings areas curing time pericds folicwing cessessati:n of active milling coerations should be included in estimates of raden-222 . gave ir.ciudec suen releases rem uranium m111:.ng c; era:1cns. t.. releases :n the racen-222 release estimates presented in :nis affidavit. Dr. Jcedan has estimated a radon-222 release rate of 71 curies ;er year per AFR for a tailings area stabili:ed with 2 feet of earth cover. I wculd agree witn :nis escimate for the ::ndi:icns s:eci'iec. The 2 feet of earth cover wculd resul-in abou: a 25 ter enc redue:icn in :ne raden flux frc= the bare tailings. I nave estima ed the f raden-222 release rate frc= stabili:ed ailings areas based cn :ne t) ' f 6 (. b i)

. -.h O - !0 - the staff's new ;erfen ance objectives fer tailings canage enc. These perfer.ance objectives recuire a reducticn of the raden flux ac:ce or about.00 (1.e., to about 1 curies ;er year cer.s,.,-s,. 2 by a r. As suggested by Dr. Jcrdan, I have presented the raden-222 release rates frca stabilized tailings areas in curies per year per AR. 9. In crder to provide additional cerscective, I have also estimated the release ~ rate of raden-222 which wculd c 2r frca a :ailings area if all of its ccver material vere reccved as a resuit of ercsicn processes ever scme long c. ried of time such as a thousand years. This cceplete erosien of cover material (ail cther fac crs remaining the same) wculd result in a release rate of accu: 110 curies per year per AR. This is a factcr cf about 10 - 100 greater than the estimates I have presented for :he covered tailings areas.

10. The Ccemission is new in prccess of preparing a generic envircemer.tal impact statament en uranium milling. The infer-ation cavelcced during pre;aration of this statement and research ;r: gram asscciacec with tna; effer should provide a much in:pecved data base fcr making future estimates of raden-222 release.

C v 6;l $ SE,2C.{? ? x

i..' = = i se-sc.ri':ed a:.d swe= a ' ef:ra

\\

n ci.is 15c. drf c:

=u 21, 1373. Q. m ,'s m \\ .s

s

~e r __ .,s. w SC:J.rf y?uch 68~306 ...... i,,,,.

h_ References (1) Haywccd, F. F., et al, " Assessment of Radiological I::act of the Inactive Uraniu=-+1ill Tailings Pile at Salt Lake City, Utah" CRML /TM-5251, p.14, Oax Ridge Naticnal Labora:Ory, Oak Ric;e, Tennessee (1977) (2) " Final Generic En.Hrcreental Statemen: on the Use of Recycle ?lu :ni : in Mixed Oxide Fuel in Ligh: Water C:cled React:rs (GESMC)," NU:.EG-CC 2, Vol. 3, U.S. Nticlear Regula: ry C::=issicn, Wasning: n, D.C., ( Augus: 1975) (3) Sears, M. B., et al, " Correlation of Radioactive Waste Treaten-C s s and the Envirccmenul Incact of Waste Effluents in the Nuclear Fuel Cycle r.cr Use. n stac.oshing,as Lcw as Practicaole,

a..aes

,i..n. ng u M: of Uranium Ores," CRNL-T'4 4903, Vol.1, Oak Ridge. National La:cra::ry Oak Ridge, Tennessee, (May 1975) (4) 3 ranch.:csiticn - Uranium Mill Tailings Management, Fuel Processing and Fabrica icn Branch, U.S. Nuclear Regulat:ry C:=-ission, Washing::n, D.C. (5) " Phase II-Title 1 Engir.eering Assessments of !"ctive Uranium 'bli Tailings," C:T-i through GJT-125, U.S. Cecar=ent of Energy, Grand Juncti:n, C:icraco. (Issuec ':ril 1976 thr ugn ::cvecter 197 ; ( .M-307

I .~ 1AllLE I CAL C01 Alluti Of Altf A 0F C0ilPOSITE Tall.IllGS IMPaun!!Mfilf Contrtitution Tallings area f or Init viilual fraction of to Composite flill._Tylies b) (Acres)_ contribution . _ Tailings AreajAcres)__ h Ponil ' anal Ponal anti to composite ICI I.ocation IdI Type Itill uet lleach Dry.Heach Tailings Area 'L. Beach Dry _Heach Total llyoniing-Sx lib 12 0.425 ' 61.6 S.] 66.7 llyoming-All 91 37 0.075 6.0 2.0 9.6 Ilew flexico-Sx UU 4 11 0.42S 34.0 20.4 54.4 i flew Mexico-Alt 50 70 0.07S 3.0 S.9 9.7 I Conposite Tallings I..ea 106 34 140 l l ~- ~- l footnotes: I (a) Sx - solvent extraction niill), Alt = alkaline leach mill g (b) Data f roni Olttil-lH-4902 (lable 4.13). Areas are representative of conilitions near enti of mill I 7 Mf of tainings. [ life. lailings areas contain I.33x10 l (c) liasetl on assinoption of 115% of proiluction from sc., cut extract ion inills anal 1b% frotin alkaline Mills (Gl' hila page IV I-25) anil assuuiing 50% L1 0,g proib.dl<ni in New Maico anti 50% in Wyaning. 3 I l

9 TABLE II ' u' n ^ ~ ~,* ~ ~ '4 "c " ', L,..., - S '"e 'x '. '."a' ~~t-'~ I '.' ~i.'.x '..' t. ~ Ce' l'.'"L a* ~i m.. ur n.c u. _. t7,.. r, a. C :. a..,. -... e. LL'.. r.-.u - h,R 40 s-:,.:.rLicsi a.l i tua ur m a Mcds! Tailine Area Acres /AFRtW Curies released er AF? Time after Pena anc Eccc anc Milline Encs(3) Wet Beacn cy Beach Wet Beach Dev Beach ~ 0-1 1.95 0.92 2.01 35.1 1-2 1.52 1.25 1.57 51.5 2-3 l.C3 1.79 1.12 55.a 3-4 0.55 2.22 0.57 Sa.5 4-5 0.22 2.55 0.23 101.2 TOTAL FOR PERICD 5.50 3ai v, w*/ (a) Based on assum: tion that a five-year interval will take, place between end of active m.illing and c:=pleticc of stabili-ration of tailings area. (b) Average area for the time intarval and based on the assuccti:n tna; the ponds dry cut linearly w'th time over a 5-year period. ( ,s M OS~3C8

\\ f' t& )s . a.) y ..p.: rC ,, p - N . n c, ? -: ; a, b ' i 'a p .v' a r- -.o,.* q/ ..p..,.,,.. \\.,, 93ul J. I'acnc

• m s Professional Cualificaticns

, I have been employed as a health physicist by the.'luclear Ragulatcry Cermaission since 1975. I am presently assigned tc the Division of Fuel Cycle and Material Safety where I am invcived in the asassment of :ne raciological impac: of uranium milling cceraticns. I received a S.S. degree in chemistry frce Scsten Callege in 1952 and have over 2a years crafessional excerience in the nuclear field. Pricr to joining the Cc= mission, I was invcivec in -he assessment anc meni:cring cf envircnmental radicactivity serving in varicus cacacities wi-h the U.S. Public Health Service and the Environmental Frc:acticn Agency. Frca 1963-1973, I served as Chief cf tne Field Caeraticns Brancn a-the lortneastern Radiological Health Labcratory. Frc= 1952-1953, I was emolcyed at the AEC's Raw Materials Cevelopment Laboratcry in Winchester.. '4ssachusetts where I worked en metallurgical extraction processes ter the recovery of uranium. Frca 1958-1959, I was asscciated with the Radicchemical Analysis Grcup a 3reckhaven ita-icnal Laccrncry. I then served as a staff heal n physicist a the Massacnusetts Institu a of Technology frcm 1959-1962. I have published over 30 technicai ; apers and reports in the field of envircnmental racicactivi y. I am a memcer af the Health Physics Society, ne American Chemical Society and have served en ASTM C mi::ee C 19.04, and U;SI Cc=ittee 21-46. / ( 08 aes

l! e t r.), q. n. r.. . ; r. c..o..r a,Le = a. v. i. .l.C,. n, d 3. au-. la. ---,[ L....l I S S. ~i l \\\\@ll d .LX . n. L .C t f /q ! ~j sf s/ is Y c.7 Y -33o,.cJ3yo i c. @a A %a*As m s O sr. IDA./ r. i C r e., C,. sC a.a.,...,.c.c-.d n,_. s CN THE UCON VALUE I:t T*SLE S-3 h8 1 6-8 Jack E. Rc nfleisen, being culy sworn. states as folicws: 1. I am a Senice Chemical Engineer witn :ne. uel.orecessing and Fabricatien Erancn, Office of tiuclear :'aterial Safe y and Safeguarcs, U.S. Nuclear ?.egula: cry Cc=ission, and y prcfessicnal qualificc dens are attacned heretc. 2. I participated in the prepara:icn of tne value cf radan release frcm the uranium milling cperaticns set ferin in Appendix 3 cf '.GSM-1228. This afficavi: describes One metnce $y wnica : e vaWe of 72.5 curies per annual fuel recuirement was cerived. 3. . cr tre '. LASH-1223 s udy a ccmcined cpen ci: :ine - acid leacn mill was selected as the acdei depicting the frcnt end of the urani m fuel cycle since this ccncep: representec a significan pcr icn cf 6 b8-310

the :nen existing industry and was c:nsis:er wi n :ne incus ry trend. (NASH-1248, p. A-1 and S-6). The cdei mit.e-mill c::alex was assumed to have *ne cs:acity to pr duce and process 1500 metric . tens of cre per day Oc yield 950 metric : ns of U 03 3 er year or 3.2 =etric ::ns of U 0 cer day based en an assumed average on-33 stream time of 3CC days per year. Ea<ed on a lifetime average an ual fuel requiranent (AFR) of 132 metric ::ns for the medel 1CCO MWe LWR, :ne :ccel nine-niil c: : lex would recuire 182 MT U 0 3 e accut 57 days of operation to produce cne ann'.a! 32" --- fuel recuiremen Of U 3

• 0' 3.2 MT U.0 / day ao 3.

Estima:es by Humble Oil and Refining Cc=pany in their Envir:r.cental Report dated July,1971, covering a 2CCO ST per day ocen pit mine-ecid leacn mill c: ciex (WA5H-1248, p. 3-22; Reference 2) i-dicated an Rn-222 release frc= One ore crusner dust collect:rs of of 3C3 uCi/:ay. Additianal estica:as presentac by Humcie 0i1 in :neir Apolicant's Respense :: Agency C:cments on Draf t Statement Higniand Uraniun Mill Occket No. ?O-8102" dated August,1972 (WASH-1223, p. 3-24, Reference 5), indicated the total Rn-222 generated by tne 125-acre tailing pend :: te 3.d5 uCf/sec wnich is scaled u: to 17.12 ;Ci/sec from the 250-acre tailing pond assumec for the '.J:H-12da :cei mil' r G8 211

-. - - - -. - ~ -... -. + 7 hen, assumir.g releases from ne :ccel mill ce :r: arti:nal :: n;se estima:ec for r.e Mignian: Mill, :ne :::21 racen release fr:= :ne acdel mill during tne pr: duction of cne AFR of U 0 was calculated 3g as tolicws: Total Curies of Rn-222

• 16CC MT/dav x 1.1 ST/MT 57 days AFR (57 cays) 2CLQ 57/ cay 10 uCi/Ci 5

or 5.02 x 10~ times the daily release ir uCi fr m ne Hignl:nd Mill. 4 Therefore, Rn-222 per AFR: (a) Fr:a Cust Ccliect:rs = (308 uCi/ day) (5.02 x 10'~) =.02 Cf / AFR. (b) Frcm Tailings Pcnd = 17.12 uCi/sec. (17.12 uCi/sec) (8.64 x 10' sec/ day) (5.02 x 10- )174.5 Ci/AFR (This corres: ends :: the value of 13 X 10' uCi/ day in Table 3-2 at p. 3-12 of WASH-1248). ta. -an-cc. a,elease =,,.: ri/a. 3r-e9 so t / e 5. In snor:, One value of 74.5 Ci/AFR set forth in Tacia S-3 of '4 ASH-12 3 reflects only releases from :ne tailings conc cf the acdel mill described in '.2 ASH-1213 during crerati:n of :ne mill. It dces not include contributions na may result frca stabili:ed piles after active milling coera:icns cease. It also does not include estimates for radan release from mining. 58~2.12

= 6. Tne 3E:R Recer: U ) ar.d tre USE A reccet, "Esti ates of ::r.i:in; ,3s Radiation Ocses in :ne Uni ac States 1960-2000' " - Oc:n c:nciacec

nat wnile uranium mining activities increase tne amcunt of surface uranium and its decay product's,.nese activities do not cause measurable increases in envircrr. ental radicactivity Outside t;.e immediate vicinity cf tne mines. On tne basis of nese conclusions,-

raden releases respiting from mining activities were nc: included in the BASH-1213 5-3 Table. 7. Similarly, radon releases fr = stabilized tailings piles were nc-included on tne basis of One E A Reper: ( ) wnicn indicated na: studies at active and inactive mill sites witn covgred and unc:vered tailings showed no significant raden exposure to the puolic from these sources ('.iASH-1243, c. 3-22). ,, Y %l.<, jw.' N(.fi,n-^4.{. / I'. Y ? js / / ..s., -% ' -/ /dacx.. sc:nfi e;sca v Subscribed and sworn Oc before e this 'I cay of l.~ '~ 7'1373. i. l .e (,1.> I' \\ ye ,f n, w...... w- .10:ary Pu.'iic My Ccmmi:sicn Expires 'd /r / / 7/ ) i( 58 313

Q-- S-

References:

(1) National Acacemy cf Sciences,.'lational Research Ccun;.il; The Effects en Occulations of E.xcesure to Lcw Letels er, ten 1::r.g Radiation"; Reccet of the Adviscry Cc=mittee on :ne 3;clogical Effects of I nizing Radiaticns (3E:R), Wasnington, D. C. 2CCuG; November,1972; page 15. (2) USEPA Office of Radiation Programs; " Estimates of I ni:it.g Radiation Ocses in ne Unitec States 1960-20C0"; CRF/CSD 72-l', August,1972; page 27. o G e k e e

a 4. e' h ~ dM i rc A 6 o 'f c r Fc -- 22.r c.,m.. L C,e,n. L i c. c.a i.C N e s - sr -. .7 usna-gg. E. ~ n s 6 i3l 9 ~7-s:~ Jack E. R0:nfieisch ~50-c / ** cg~* *-h# [ - U. S.."uclear Regula :ry C:=issica 3 s Educatien: In 1941 I received a Eacheice cf Chemical Enginee. kcH i

• desr:0 frc= the College of the City cf New Ycrk. Curing the pericd 1955-lC60, I at:anded nient classes at tne University cf Tennessee and cc=:leted : s of the c:urse work leading to a Yastars degree in Indus: rial Management.

' Jerk Ex:erience: In 1941-I accepted a positi n.as Chemical Engineer with the Tennessee Valley Authority Cecar:= ant of Chemical Eng'.neering, wcrking en pr:Jects associated with the devale;=ent of. nitrata and :hosphata fertili:er catarials including tne manufacture of watar gas c:nversien and am=:nia synthesis catalys:s and star:up of a synthetic ,---.z... r _... In 19*3 I voluntaer2d for service in the kl. S. "avy where I served as CO:=unications Officar, then Exacutive Officer, and finally, as C:==anding Officar cf USS L5T Eal. In 1946 I re:urnad to a ;;si-ica in chemical engineering wi-h TVA where I designed, felicwed c:nstructicn, and :: era:ad pilot scale ~ facili-ies in su::cr f the pr:ducti n Of phosphatic fertili:ars, a== nia, nitric acid, ar=enium aitrata and elemental phos:horus. I sucervised the de ails of the ex:erimental work, evaluated and c:rre'.a:ad data en projects including control of emissiens fr: ;ncs;ha a and nitric acid plants. In 1950 I was recalled to active duty with the U. S. "avy, assigned as Jcin: C==unicati:ns Center Of#f ter a: ard :..e USS Eld rad (?"C-ll), in Korean waters, where my pr::ary ~e ro e.w.. g. s 5 3 ; ~w,,,. z s ..u. a.c.= e. z..... C C =. s. a r. s e... - :

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/ /_ / 2-f:r all ex ernal cc munications as well as ::,1-i:- a n a a <, n., n.,.. -, c '. '..". a. .......... i.' '. '..n s.v,...... In Oct::er i952 I acceptad a ;csition with Uni:n Carbide Nuclear C: pany at the Oak Ridge Casacus Ciffusien Plan: where I was engaged in engineering devele: ment studies directed t: ward improving varicus processes asscciated 93c with the enrichment of the -- U isatepe by gasacus diffusien, cutlining the cbjecticns, sc:;e and e hed of attack for fluorine gener2tica, gasecus diffusi:n feed P l a n *. n-a..' '.d. e.n s, 'f r.."". *. ra.r.v e.v =. d.. .'.."'.ac.... . r r ~ barrier. In1960 I was transferred t: ;csition as Chief "etallurgis with Unicn Carbide at their Uranium Mill in Rifle, C:lerad. In this positicn, I planned and supervised studies f process c:erations in the pr:duc:ica of uraniu and vanadic fr m ca-::tita cre. Investigati:ns included pr: cess it:reve- .-.n t r.-.ea l s, c..e..c...a 1,. s c. r r. -..e e. C 1.-..J 1.., s..,T1..;..< n z s r r. r cf plant cperaticnal trends, pre: ara-icn of technical re: r:s, and pollutien =cnit: ring and abatament programs. In 1962 I was transferred :: ; sitien of Senicr "evelc: cent Engineer wita Unica Carbide Cor; ration Electr:nics Divisi:n a r.d A, s,... 3 c, a s. i n.. u.. d.a,/ a.1 n,.... ~. +. a. .n. --....a a a. e

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a %7 l ! In 1972 I 20:e ted a ::siticn with the U.'S. AEC as a Senior.Matarials Licansing Engineer pr:ces:ing licen:e applicati:n: f:r uranium niliing and UF E"Od"CIIC' 6 facilities including pre aring envir:nmen:21 im:ac-statement f:r proposed er existing insta11aticns. / assisted in the preparaticn of WASH-1248, "Envirencen 21 / Survey of the Uranium Fuel Cycle" and c:ntributad t: the sect ens en uranium mininc, uranium milling, uranit: hexa- [ fluoride pr:ducticn and uranium enrichment. 4 In 1974 I was pr:motad t: ;csiticn of Senice ?r : ass Licensing Engineer with the primary functicn of acting as pr ject manager and principal technical reviewer f ,/ license applicatiens for the c:nstructicn, mcdifica:icn j and cperatien of ncn-react:r fuel cycle facilities. Subsequen:1y One title of my posi:'cn was cnanged :: i Senice Chemical Engineer. I' 8 I i 8 I a e n. M. 3 8.. a".. $..R. *., O gg-217}}