ML19220B096

Comments on NRCs Draft Suppl to Fes:Discussion Inadequate Re Radiological Dose Assessments,Potential Impact of Gas & Liquid Discharges & State Thermal Stds

ML19220B096
Person / Time
Site:	Crane
Issue date:	10/18/1976
From:	Synder D ENVIRONMENTAL PROTECTION AGENCY
To:	Harold Denton Office of Nuclear Reactor Regulation
References
10736, NUDOCS 7904250333
Download: ML19220B096 (15)

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I gTED STATES ENVIRCNMENTAL PROTECTICN AGE NCY

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Mr. 'darold Cent:n Director j

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Divisi:n of Site Safety and Q,

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,y U.S. Nuclear Regula:ory Cc~ission

'Jashington, D.C.

20555 Cear Mr. Denten:

s 2.e Envir:n= ental ? o tectica Agency has reviewed the U.S. Nuclear Regulatory Cc~ission's Draf t Environ =en:a1 Impact Statement issued July 22,19 76, in conjunction with the application of Metropoli:c.:

Edison Cc=pany for a license for the start up and operation of 2ree Mile Island Nuclear Station. Our de: ailed cc::ents are enclosed.

The Draf: Environmental I pact S:atement did not adequately ciscuss:

1.

radiological dose assess ents including estimates of the expected radiation dose to representa:ive individuals in de surrounding population; 2.

the potential i= pact of the radicactive gaseous and liquid dis charges f ree bo th Uni:s No. 1 and No. 2 ; and,

3.

state ther=al standards and the =anner.nd location the/

will be applied pursuant to Section 97.32 a. and b. o f the Pennsylvania State '4ater 'aw.

E?A is reviewing 1:s positiens en high-level waste =anagement and related aspects of the fuel cycle in light of the recent decisiens of the U.S. Court of Appeals for the District ci Columbia with respect to Vernant, Yankee and Midland nuclear power plants. Therefo ~ - ents on high-level vaste management issues do not appear in this review.

'/3-200 7904'250333

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2 In view of the above and in accordance vi h our procedures, we have classified the project "ER" (Environmental Reservations) and have rated the Draft Envirenzen:al !=cac: Stater:n " Category 2" (Insuf ficient Inf o r=a tien). If you have any questices ccucerning cur classifica:ica or cc =ents, we vill be happy to discuss the vith you.

Sincerely, DanieliJ. Snyder, III

,a Regional Administrator

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Inclosure 73-~201

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Radiological Ef fluents and Dose Assessments 3.

Rea:::: Accidents C.

Radica::ive 'ias te Management D.

Transportation III. NC:I - RjuIOLCGICAL ASPECTS A.

'4ater Quality Impacts 3.

Trans ission 'ines and Their Field Ef f ec:s C.

Metacrologf and Climatologf 1,v,.

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2 will produce up to 2S00 megawatts thermal and will dissipate 1813 M:7 (:) as was:e heat using a natural draf: ::ver in a closed cycle

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the Sus uehanna River. The following are our ma.ior conclusiens.

x The proposed gasecus and liquid treatrent sys tens appear to

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and we believe the f acilir/ can be co. erated with radica: ivity eleases consis tant with '!uclear Regulatory Ce==ission's icw as practical releases - 10 CFR Par: 50.

Ecwever, the draf state ent centains several deficiencies in the dose assesscent analye ts which shculd be

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Radiolo:ical Ef fluents and Dese Asses srents' The draf: supple:ent sec: ten :itled " Radio.cgical Impacts" is deficient in everal respects.

In our cpinion, it is difficult to assess and to place in perspective :he radiological impacts indicated in the draf supple =2nc.

The first of :hese deficiencies a;; ears to be an editorial e rro r. An Appendix C is referred to for descr,iption of the ncdels and censiderations for environmental pathwa;s. The Appendix C la the draf t supplement describes biota collected in the vicini ) of Three Mile Island.

There is no appendix describing radiation e::pesure pathways.

The final state ent should be corrected to include a discussi:n of radiation exposure pathways, a defini:1:n of :er s and of ecdels used.

The rad 10acrive ef fluen:s used in the dose computaticas were these esti=a:ed by the staf f to reasonably charac:eri e the annual release of radioactive esterial.

I: would h:ve been helpful to cc pare these with actual release da:a fr = the cc panion plant, TMI Uni: No. 1.

There is ene ec parisen with reported values (^), ad=1 :edly no:

the bes: da:a, because this was the Uni: No. 1 start up period.

The radioactive releases range fr m a factor 33 grea:er to several orders of :agni:ude less for liquid effluents, and consistently less by f acters of 5 to 10,000 for gastous effluents (when actual releases are cc pared :o calcula:ed releases),

A staff cceparisen wi:h cc parable.cperating da:a would be useful in the final statemen:.

(') Three Mile Island, Uni:

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Several references are available :: this su;fect.

~he A:ccic ~nc gy C mission's (new '2C) concluding s:a:cecn: :

i:s rule-

=aking proceed n;:s en Appendix 1 to 1-0 cr. Par: 50 contains improved esti:eres o.c 3., u *' a '.*,,=. *' a o '.'. a c,v s es.

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which provides a cenpilatien of cperational experience relativc. to these

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.e en analysis of availa' ale inic matica, EPA estimates that the annual off-site hipcant cf " low-level solid wastes" will be ec= prised of approxicately 13,600 fae:3 for a Ptl-',cperated at Unit 2's design power vi:It S0 percent (3) capacity factor We believe the final sta:ecent should provide the rationale for an ecticata based upon present was:e management prac: ices.

We u.derstand that another 3:udy is being c cdu::ed on this subjec: by the Acomic :ndustrial Forum. We enceurage the NRC to update the es:1:stes of lev-lavel solid wasta quantities using the cs t appropriate and curren:

experience.

(3 ) Mann, Caidberg, and cendricks, "'cu-Level Solid Radi: active Waste

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Transecr atica In its earlier raviews of the environmental impacts of transporta:ian of radioactive caterial, EFA agreed viu. AEC that cany aspects of this progrs= could best be treated on a generic basis.

The "RC codifi2d this generic appreach (40 ?.R.1005) by adding a :able : its regula:icns (10 CFR Part 51) which su=nari:es the environmental impac:s resulting frc: the transpor:aticn of radica::1ve ca:erials to and frc= light-water reactors.

This regulatica per its the use of the i: pact values lis:ed in the table, in lieu of assessing the transper:stien impa::

for individual reactor licensing actions, if certain condi: ions are set.

Since Three Mile Island appears to meet these condi:icns, and since EPA agrees that the transportatica impact values in the table are reasonable, the generic approach appears adequa:e for this plant.

The impact value for routine transportation of radioac:ive =aterials has been set at a level which covers 90 percent of the reactors currently operating or under ccnstruction.

(The basis for the impact, or risk, of transportation accidents is not as c? early defined.)

The E?A will make knew: its views on any envir:n=entally unacceptable conditica related to transportation. On the basis of present infor:ation, EPA believes that there is no undue risk of transper:ation accidents associated with operation of the Three Mile Island Nuclear Stati:n, Uni: No. 2.

73 210

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Water Quali:v Iroacts EPA's analysis cf all Water Cuality data and information presented in the Craf: Supple:ent :: the IIS for TMI"S, shows tha: this section of the EIS was well writ:en and very adequate.

However, E?A is concerned with the appr:priate state ther al discharge s:cndards and their applica-tien at Three Mile Island Nuclear S tation.

The draf: supple =ent indicates en page 5-3, tha: the foll wing s: ate ther:al water quali:y s tandard is applicable to TM "S :

Temperature - Sc: nore then a SOF rise a'ceve ambient tenperatures or a =axi=u: of 370F, whichever is les;;

not to be changed by : ora than 2CF during any one-hcur period.

The state thermal reaadard is inadequa:ely defined in the report.

It does not so. ecify how or where this s tandard will be apo. lied o. ursucn:

Oc Section 97.32 a. and b. of the Pennsylvania State L'ater Laws.

The N? DES perni: issued by EPA to T'C"S, ef fective December 30,19 7?.,

imposed an effluent limitation of 870F for the protection of the squati:

ec unity. Pennsylvania later approved Metrcpolitan Edison's request :o discharge at the ambient receiving strea: :e:pera:ure when the tempera:ure is above 870F.

The enspany is trying to negotiate a workable application of the 50F rise li:1:2: ion with the State.

The final supplement shculd report hcw this proposed variance will affe:: the applica:ict of thermal standards a:

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< J 211

The technical specifications for Unit No. I require tha: the tempera:ure cf the discharge fr:: the mechanical draf t eccling

cuer be no cre than 7CF above or less than 3 F bel:w the a bient temperature of the river water.

In additi:n, the discharge tempera:ure cust be main:ained at or belcw the anbient river water temperature when the intake water te=peraturc is 370:- er greater.

The final supple en shculd indicate

• hethar ther:al limitatica imposed en Uni: No. 1 rechanical draf cooling ::wer will be applied to Uni: No. 2.

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. 3 m the final supple:ent should show the lucati:n of the in:ake structure in relation to kncvn spawnin areas in the vicini:~1 of the power b

plant.

3.

Transmission Lines and Their Field Ef fects It is encoura;ing to see a discussion of the possible health hazards due to induced electric field eff ects and to read tha: the applicant is ec=:itted to undertake a series of safety steps in this area.

EPA is concerned, however, with the SCO K7 ::ansmissica line that crosses Pennsylvania Reute 100 east of 3echtelsville, and would like to have this transmission line included in all saf ety imple enta:ica plans regarding induced field eff ects.

has been given notice ('%that it desires to collect the data E?A necessarv :o define cessible heal:h and envir:::en:al eff ec:s of EE7 4

a pcuer transmission.

I: is hoped that the applican: and others will (5)

Federal Register, Vcl. 10, p. 12223, March 13, 1975.

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• 'e concur with the N20 staff Opinion that presen: state-of-the-ar:

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on clinata due to at cspheric fispersion of heat and coisture fro: the p c,=. c s. -..<,.., a.,..u. o a 3 a a, n.... e a

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to resui: f ree the operation of the Three ie Island Nuclear Sta:ica.

d We make the cbservatica that an'; future p roj ects invol-ring large heat releases into :he at:csphere in :he icwer Susquehanna 3asin should utilice the growing body of knowledge on macroscale wea:her codifi:stion.

TS.e environtental impact of the large aggregation of power generation f acilities in :he area should be analyzed on a regicnal basis for future envirennental impact.

Estinatas of relative at:cspheric cencentration (;C/Q ) values at varicus distances and direc:icns fro the site should be recorputed

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Table 2-2 of Section II " Site Analysis" lists all downstrec:

water users. The Hol:wcod Dan and hydroelect-ic pcVer sta:ica uas not

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7.:e final supplement should include the fa:: :ha: an :7053 Permit f:r Tarce l'ile Island :.2: lear Station was issued on De:crie:

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