ML19220A376

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Applicants Responses to Questions Raised in Limited Appearance Statements
ML19220A376
Person / Time
Site: Crane Constellation icon.png
Issue date: 09/09/1977
From: Blake E
SHAW, PITTMAN, POTTS & TROWBRIDGE
To:
Shared Package
ML19220A373 List:
References
NUDOCS 7904170501
Download: ML19220A376 (49)
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{{#Wiki_filter:, September 9, 1977 UNI'"ED STATES OF AMERICA NUCLEAR REGULATORY CC?O!!SSION 3efore the Atenne Safety and Licensine Scard In the Matter of ) ) METROPOLITAN EDISCN COMPANY, ) Occhet No. 50-320 et al. ) ) (Three Mile Island Nuclear ) Generating Station, Unit 2) ) APPLICANTS' EESPONSES TO QUESTICNS RAISED IN LIMITED APPEARA' ICE STATEMENTS so, rv*,*. d 3 /.. ...a 7904170 -

_s a e -n. _ Name: Leavitt Transcript: 223 Question: Can it be guaranteed that there will never he an accident which releases extreme radiation? Answer: Studies have been done (the = cst notable one by Dr. Norman Rasmussen, Professor of Nuclear Engi-neerinc. at Massachusetts Institute of Technolce_v_) which evaluate the crebability of havinc. an acciden: at a light water nuclear reactor which could release large arounts of radioactive materials. These kinds of accidents are collectively referred Oc as Loss of Coolant Accidents (LCCAs). Dr. Rasmussen's stucy has found that the probability of fatality caused by a Loss of Ccolant Accident (LCCA) which wculd release large a: cunts of radiation is signi- _# _4 c a n *- ' v, A' ass " " ar. "..". e c -- " a ~'^ _4 _' _d

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_# -=~---__v_ d"e e to other natural and man-caused disasters. The f ollowine. cccc. arisen _s taken frca cac.e 3 of the executive summary of the Rasmussen heport, WASE-1400 (NUREG-7 5/014 ) : Reactor Safety 5tudy an Assessment of Accident Risks in U.S. Cc=mercial Nuclear ?cwer Plants: .c c~ s a LJ r 4 ..... J

U... ~ AVERAGE RISK OF FATALITY SY VARICUS CAUSES ACCrDe.v.u-

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c_ r u, v_ r_.AR v s Motor Vehicle 1 in 4,000 Drowning 1 in 30,000 Air Travel 1 in 100,000 Tornados 1 in 2,500,000 Nuclear Reactor Accidents 1 in 5,000,000,000 As this chart indicates, the probability of fatality due to a Nuclear Reactor Accident is highly remote. In facr, Dr. Rasmussen's report indicates that 'his --bakd'4".v_ s a _w. w.c-... = "-- v "w.". a s a r.e a s "-.".e a'_ d

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"'"e#a ..w;7o 4" ?1 S u; .c. -7,, nr.--- will never be an accident which releases extreme rndiation, it has been determined char the proba-k 4 7 4 " v, C. s "w C.b. a.". a C - 4 d S.".'w s va-" - -. ~. ~ ~ - -. "S " o

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999 _g-. Question: Can it be guaranteed that people can return to hcces after such an accident? Answer: This cuestion is closely related to the preceding one, and the answers are also closely related. Acain, absolute guarantees cannot be made, and it is theoretically possible albeit inconceivable, .,a. a.. 4am_n .act,_,2. oc-,m_. .w,. ..c t,_,. ._sL,_, _ - 4 ... - - a extended evacuaticn of sc=e areas. The reccgniticn c _# e ", e.". '..b.' s "_ c s o _4 _" _4 _' _# '_ v, b.a o~ " e s "m _' "_ a d_ _. ". s *_

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4 safeguards employed to assure that no such event 'd _ _) 1 o c -,1_. 9 [ Y %' *{ %I r/ L _ = _

Name: I.ea'zitt Transcript: 223 Question: Can it be cuaranteed that there will never be a _ d.i a' _4 c n _i....o. a.' cye '+._4 ^.'. ..a_' ease o# vi Answer: Durinc the coeration of any nuclear o.cwer clant small amounts of radicactivity are released to the e.nv4_o =..' a..d "."."s "..".a e

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that any radioactive materials released from SIINS are at levels considered safe to the public. It should be noted that based on three years actual data the radiological impact on the public due to the operation of SiINS Unit 1 is much less than that due to a single dental X-Ray. 9F# D [ ' *#) Qs, n ..s M M

3 i Name: Leavitt Transcript. 223 Question: Will realistic evacuation plans be worked up and tested? Answer: Evacuation plans which Met Ed considers realistic and workable have been developed and are available for i==ediate imolecentation if necessarv.. These c.lans, which were the s W ect of dav.s of testimenv. J d u _4.. c. '.'.a_ b.a_a__4..gs _i. = _= _- _ i s " u _-, u'.-=_ _=_. _4 - d _i a.' _' ", 3 e tested, as also was discussed du-ing -he hearings.

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witness at the hearings, were some of the tcst comprehensive and best he had ever observed. o < o r c) "D" b 4-g 6s 4,V

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Cuestion: W4 'CCal authorities receive notificatiCn of an accident in less than the 24 hours experienced at i r 3 w-w n s.,_ _ _,,., Answer: Initially it should be nCCed that the accident at BrCwn's Ferrv. affected no CersCns Cff-site and that no radiCaCtivity was released to the Off-site enV'ronment. '"he timell.nes s C C CCt'C1CatiCn to C I.c _ s _4 u e a,, u.u.r._4._. _4e c. 4 u.k.e C,se O_e u.w. n_ 3 wn s w. .a w 1:' e.".*. ';'.'.". C.i d e.". ' s '". ^ C.' # e i"dc,ed C " C " # 4.". C.'. V. A

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s Fire Department, and the Dauphin County Civil Defense Unit. They nay be contacted by telephone (all necessary phone nn=bers are listed in the Emergency Plan) or bv radic. To ass'..e that the notification systems and personnel who use t'.en are in constant readiness a: Met Ed c.ersonnel on the clant crerating staff have re,eived ex: naive raining and indoc-trination and also receive pericdic rer-~ining based on the e=ercency. clan. Additionally, annual s drills, =cnitored of state and federal authorities, are held, in which the notificatica systam is preven. Many such drills have been held and in all instances the notification systen was satis f actc ry. .er

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g. Similarly, while the principal =cde of transportation in an evacuation is by crivate vehicle, there are i = = e c i a t e _, y a v a l _, a n _, t a nu=cer c:_ a_,ternative =cces such as school buses, vans, military transport vehicles and ambulances. Thare exist spe cial means, as we_,_,,

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,'-4as such as s c.,.c o ls and nursing hcmes, as well as isolated individuals who need special attentien such as the handicapped. These plans assure the public will get the ecrd and be given whatever assistance is necessary to effect crotective measures including an evacuacion. r E Of ,'y s g.<

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Swann ~_ _ a.,. o m-, 4 6~e8 e .e.. ~ Cuestion: Will those of us on the cuter perimeter cf the reads clear? ..b. e ac-ide..*. "e

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7.6o*.' Cuestion: Ecw much radiation was released from two radio-a c *.i ve g a s l e.=..'~. a e.v. e _ _i a..c. e d ' "..'. - a a..v._d.' e 7 s ' '..d .a_4 g .w...e s e .3

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.'I_' _' a. 7 s _i a..d " e .e#e_--ad .o _4.. ..". e c," e s. d .n. U. _d..' a. *. " _- a e.' i_d _' a. Island has experienced unplanned releases, all cf i wb.4 c". hava. " a. a... '..'.e s "u m" 'a ec* o# a ec--_.-a.:c-.a. - "o

iRC simply because they were not planned.

All inadvertent (unplanned) releases as well as c.lanned gasecus releases have been wichin the .-o_' ease =*- __..-..e

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sm Routine en'Iiren=encal nenitoring is per:.cr ec in the vicinity of the site and would detect any sig-nificant un=cni:cred release should one ever occur. ( b,,. ., <,e i^ s - s.Iame : acnes Transcript: 2685 Cuestion: Ecw =any degrees will the river be heated by discharge

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748o' -e. Question: What has efficiency (capacity facecr) been for TMI 1 a -. _e .e

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,an,. .a4l, 4 w Answer: The capacity facecr for TMI 1 through June 30, 1977, has been 71.9%. This n" "er is considerably higher than the 1976 average of 53% for Pressurized Water Reacecrs. As we discussed in testimony at the c' ac4*v. -^- bea i..,s 4.. C'- 'a-"u-,, .b. e *..v. ~ ' --- +- is anticic.ated to be 65%. This accears to be a reasonable assumption due to the fact that TMI 1 has exceeded this value since it 'cegan ccamercial cpera-

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~ g.-, Mc.=e : Jones A Trans c ri-)t : 2636 Question: What was the initial estimaced ccst of TM: 2 and what are the costs now? Ar.s w e - '. "..". e..i.. 4. 4, ' c,s e.c,d e- - 4 c. . sc. i - June of 1969,and based cn a May 1, 1973, corrercial operating date was 3190,000,000. The current cost projection based on a May 30, 1978, commercial oceratine. date is $642,000,000. m

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, i,. 3 -..v Question: Why, if Rasmussen discusses accidents which can affect area the size o" Pennsylvania, cannot TMI 2 accidents result in whole body doses creater than 5 Rem beyond 4.3 miles? Answer: This resc.ense does not address the c.uestioner's _4.. ~. e _,.2..- a. a + n.. a: .. a. en..aeq"e..cas c# _- a_.". o _- s c v accidents as described in the Reacecr Safe v. Studv. (WAS u. ' '* 0 0 ). 4 a.".c u.' C. '~e ..u-d, h.e w n v a_ _,.. ". ' ~. ..".a ~n .w U.e ' C *_ ^w -_ .C.~' # a. *.v, S "Av,

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g-The accident analyzed for purposes of the refer-enced testimony is the worst consec.uence accident .e.- w." 4 c". u'.a.a.' v s _i s.ds ec,u_d ad--4.. '.'<o.~" ca..a_d..g prcceedings. The consequences calculated are aasec4. d .s_4., a c ..o c..u,.,. _4 s. 4 - .m, w e w - _ _ o_ s e _ c ...o c: .w C C n. a.4......e.,. u. s t.c...,.e c ...e ._r.-- u-,- cc*a 4..v e.". *. c. v, c' d.icac*4ve..' a - ' '. # ' _' c w e d 'w-v, .' e a.'<. c, e - - -.a ~... e .. - - _4. ..e.. . c '.". e a. ~, _' - .. =-.. -.

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~ A v 9 2 Name: Arnold m_ a.a.sc _i -+ - ' '/ ' ' yw. Question: Applicants always refer to danger area as tcward . c.. 1 c,. c _4 e.. he s.w.e no e.,s-, s.4..ce w4s,. - u u _o .v _;..d c _4 _-a,. _4 -. __ w,,,n. . -..d o a.u. _. _A u,. w. Answer: Presumably the c.uestion refers to testi=cnv. on e va c " a 4 c.. c,, 1.=.". s, a _' '. '. c " ~3.". _d ' s _# _5 " *. ". a.'.' "; _d.a. a c " "- * '

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evacuated, if necessary, to avoid receivine the ' 4.. 4 - 4.. c. ---*ac*-'"<e =c-4 c"-i A a-- ave- ' '." _ ^- 4 4d^se i of 25 Res. Doses received by emeruency c.ersennel would be essentially the same as =erters of the = c - -. '.. a i.

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ubl.i sd..ce ^n.ca.. - ~ e c - 4 ". a_ ~ been taken, such as evacuation, there would be no c ^ n '- i.. u' i. c...ead "r--- e..e c,e.cv, - a_ _ s v-.. a_ '

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_~--e11-ws ". a ". a_...a _- e. c "; -...a a = =. _ c a d n - =_ _=. c.ersonnel surelv. would not be exe.csed to their limitinc. thyroid dose level of 125 Rem. L16 ? ... 1)) O ff ' ~ = ~ v

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h-Name: Arnold Transcript: 2730 Question: Can we he sure that technical and environmental dangers posed by Unit 2 are minimized by capable people working in a secure and well-ordered installaticn and that all NRC regulations have been adhered to in TMI-2's construction? Answer: TMI Unit 2 was designed and constructed (and will be operated) by qualified, experienced and profes-rional personnel. A multi-level Cuality Assurance / Quality Ccntrol o. roc. ram in effect throughout the life of the planto includinc. desie,n and construction, provides additional assurances that regulations and requirements are strictly adhered to. In addition, the complete review and constant survei_ lance by the NRC provides another independent ascessment as to the adecuacy of organization, design, ccnstruction and operation of the Unit in accordance with NRC regulations. All of these checks and balances mini-mise the potential of any technical and envircamental dangers. p,s' nc .4 OO.

Name: Arnold Transcript: 2731 Question: Can we be abso).utely assured that not one violation of Codes and regulations is to be found at TMI 2? Answer: In reality, absolute assurance that not one violation of codes and regulations has gene undetected is impossible to ascertain. For this reason, a Quality Assurance / Quality Control program is estab-lished and implemented in several levels ;f degree with the highest level of CA/QC devoted ec those areas where the consecuences of an undetected vio-lation could result in the more severe sa f t:_y hazard. To this extent, one can be certain that the Cagree of assurance is cc=mensuratt with the risks involved. Likewise, since that degree of assurance may not be 1003, safeguards are inherent in the design of the plant to protect against the small possibility of a sericas violation of a ccdc of regulation that might affect safety. d'd Cl>

Name: Jarboe Transcript: 2747 Question: What has been the capacity factor for Unit 1 for each year of its operation? What is predicted or Unit 2? Answer: The capacity factors for EMI 1 since it began cc=mer-cial operations in 1974 are as follows: 1974 86.0% 1975 79.9% 1976 62.3% June 30, 1977 65.9% Cumulative to date 71 9% We are predicting a capacity factor for Unit 2 of 65%. 4r;

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f Name: Jarbce Transcript: 2747 Question: Why wasn't a balloon type (as was conducted at Goldsboro) or some analogous experiment done by .a .v.e +. = m,. Answer: Dispercion models used by the Applicant are su.a.corted bv. disc. ersion exe. eriments cerformed at many locations over the entire spectrum of meteorological conditiens. Built-in conservations assure that application of these acdels at almost any site would yield conservative (high) estimates of consequences from radiological release. Met Ed has, in fact, conducted tracer gas dispersion tests at Three Mile Island under very stable, low wind speed conditions -- T.eteorological conditions leading to the highest estimate of consequences from a given release. The results of these exper-iments indicate that the dispersicn models used for our accident analyses are conservative. These results also have been confirmed in experiments at other sites. Bal]oon trajsctory observations such as those made,p.> .n,. 8

p-g at Goldsboro are interesting, but must be inter-preted carefully. The trajectory of a icw density parcel of helium which wot ' be strongly influenced by wind shear (change in wind direction with height) may not accurately simulate the trajectory of a radicactivity release. Furthermore, ballcon obser-vations give no direct estimate of dilution along the trajectory. The estimate of consequences depend strongly on radicactivity dilution along the trajec-tory. - 3 2-d.. s^..4

dlP Name: Jarboe Transcript: 2747 Question: Are there plans to conduct similar or more sophis-ticated studies to demonstrate where routinely released low-level radiation particles will return to earth before a license is granted? If not, why not? Answer: There are no. clans for Metrocolitan Edison to cen-duct special studies to improve <tssessments of the disposition of routine releases of radioactive particulate material. At cspheric dispersion mcdels used in the radiation dose assessment are based on results from a number of experiments performed at several locations under a variety of meteorological conditionc. The data base is considered sufficient for conservatively simulating the deposition phenca-enon. Since 1974, Metropolitan Edison has been conducting an ongoing environmental radiation monitoring program which is sensitive to very low levels of radionuclides which could be present in airborne effluents from Three Mile Island 1 or 2. To date, no measurable activity attributable to Three Mile Island 1 has been detected because dis-charge rates have been very low. Ecwever, results - 3 3- ' ; O ....s ty,

9 from this routine monitoring program would provide information on deposition of low-level radiation particles if discharge rates approached significant levels. _,4_ gs r d') aQ 4 <g 2,.,a

Name: Jarboe Transcript: 2748 Qut> tic : Cn December 23, 1976, higher than normal radiation levels were detected in Susquehanna, which were attributed to Chinese bomb fallout. Were any con-trol studies done at several points at TMI 1, s e ve r a:. miles upstream? If not, why not? Answer: It is assumed that the question refers to a report submitted by Met Ed to the U.S. Nuclear Regulatory Cc= mission an December 23, 1976, which described higher than normal concentrations of Zirconium-95, Niobium-95 in a surface water sample collected at a point approximately 0.5 miles downstream of the TMINS. Investigation of these sample results and other samples taken at the same time indicated that these concentrations should not be attribured to the TMINS. The isotopes cbserved are typical indi-cators of weapons testing fallout. As discussed in the subject report this sampling location alone of the six river water locations upstream and downstream had higher than normal concentrations. Hcwever as also indicated in the report these radionuclides were noted as well in air samples, sediment samples and fish samples at both near and distant (indicator and - 3 5-nro g p nat.o.

S: 9 background) sampling locations during this pericd. The control location for the reference sample is the Steelton Municipal Water Works, 8.7 miles NW of TMIMS. During the previous month samplin~v ceriod these radionuclides were noted in the upstream (con-trol) samples and not in the downstream (indicator) locations. We are continuing to monitor analysis results to keep track of environmental perturbations including those due to atmospheric nuclear weapons testing. . '*14 s.... dr ,q

O. Name: Jarboe Transcript: 2748 Question: Are there any plans to routinely test soil samples for radioactivity in the area bounded by Goldsboro, Reading, Lancaster and York? If not, why not? Are there any plans to routinely test soil samples for the area bounded by Millersburg, Newville, and Goldsboro? If not, why not? Answer: Although not required to sample soil, TMINS has sampled and analyzed soil from 12 locations in the area surrounding TMINS in 1974 and again in 1977. The sample locations are in six different sectors and at distances frem 41 to 715 miles from TMINS. Following is a list of sampling locations: 5Al 0.4 miles East of site on north side of Observation Center building 1.1 miles ENE of site, wesr of 431 Gingrich Road 531 1.0 miles East of site on Peck Road 732 1.2 miles SE of site off Engie Road 1.6 miles SE of site east side of 7B3 Conewago Creek 1C2 2.3 miles N of site in Middletown 7C1 2.5 miles SE of site East of Rt. 441 14Cl 2.7 miles NNW of site near intersection of routes 262 & 392 1F2 6 miles North of site on Fiddlers Elbow Road 7F1 9' miles SE of site off Engle's Tollgate Road ISG1 15 miles NW of site at Wert Fairview 2G1 2 miles NNE of Hershey en Route 39 Hummelstown c <1 A t};, , < =

Soil sampling and analysis has several inherent problems which make it an undesirable medium for environmental analysis. Cne of these problems involves the variability of soil types between areas which have varying quantities of natural radioactivity. Normally high naturally occurring radioactivity compounded by long-term accumulations of f allout make soil a very insensitive indicat.>r of any change. Since the focal point of interest in environ-r ntal monitoring is the amount of radioactive material ingested, other sample mediums such as miik or vegetation are much more sensitive and better indicators. For these reasons Met Ed does not intend to rou-tinely sample seil, and specifically not at locations as distant as Reading, Lancaster, '? o r k, Millersburg (Millersville) and Mcwville (Newburg). The dispersion factors at these distances is such that the small amounts of radioactivity released under controlled

cnditions could never be detected.,

or - d 3,<6 4. t.. L) 3

Name: Jarboe Transcript: 2748 Question: Are there plans to routinely test milk samples for radioactivity in Goldsboro, Reading, Lancaster and York? If not, why not? Answer: Milk samples are routinely collected and analyzed conthly during the grazing season at five or more locations. The locations currently sampled are Goldsboro, Marietta, Hummelstown, and two farms approximately one mile east of the TMINS. For reasons similar to those described in the prior response on soil sampling, atmospheric dispersion 'ampling at distances greater than about 10 miles would be ncnproductive, other than as a control or background sample since it is highly unlik'ly to be affected by TMINS controlled releases and could not be recognized frcm background perturbations. - 3 9- ,, o,, , f. ( e e..

Name: Jarboe Transcript: 2748 Question: What is projected schedule 'or routine gaseous release of low-level radiati.n for Unit 2? When do you release? How often? Is it a function of atmospheric conditions'. Do you ever release during a southeast rain? What concentrations and what kinds of radionuclides will be released? Answe-There is no projected schedule for routine gasecus release of low-level radiation for Unit 2. However Unit 1 cperating experience over the rast year is as follows: There were 69 gasecus releases or an average of 1 every 5 days. All releases were less than 20% of the Technical Specification limit at the point of release. These releases were not a function of a'.mospheric conditions. As an example during the fourth Quarter of 19~/6 the average release rate for gases was 1.07E02 uCi/sec, or 0.0392 percent of the Technical Specification limit. A total of E44 curies of gases of which 97% were xenen-133 were released during this cuarter. The cniv. source of c.lanned routine gasecas releases 40- 'l *e :- "a t.- 's

9' is from a waste cas decav. tank. Compressed waste gases are sampled shortly after a waste gas decay tank has been filled. The analysis of ' his sample is the basis for determining whether the gas in the gank could be recycled as cover gas or discharged to the e"vironment. If the gas is to be discharged to the environment, the following precautions are

observed, a.

Approval of sample analysis taken from the waste gas decay tank is cbtained prior to release. b. The release can onJy be effected through paths that require positive manual operation in order to effect the release. c. The release follows a path in which the gas is monitored three times; once as ic leaves the decay tanks, once in the discharge header to the unit vent, and finally, after it mixes with other gases in the unit vent. Either of the first two monitors will terminate the gas dis-charge automatically in the event its setpoint is exceeded. g,- m,.. A' g.t..v A g The policy of operation for the 2 nit is (1) to discharge the minimum quantiq adicactive materials to the environment which is consistent with the equipmen; provided in the unit, (2) to meet all the conditions of the operating lic e.n s e and all applicable Federal, State and Local regula-tions and (3) to meet its obligation to the public to provide adequate pcwer on a reliable basis. It is expected that during periods of ncrmal operation, when all equipment is operable and functioning at its design efficiency, the quantities and concen-trations of activity discharged to the environment will be maintained substantially below the limits specified in 10 CFR 20 as indicated herein. How-ever, during periods of operation when some equip-ment has failed or is unavoidably out of service and, if taking the unit cut of service would jeopard-ice the public power supply in 3 served (either directly or indirectly), the unit would continue to operate and the necessary remedial action will be implemented. Such operation, however, will always be in accordance with applicable regulations and eithin NRC-imposed technical specification limita-tions. -4 2 - d,u- ...f n c --

In implementing the abo're stated policy with respecr to disposal of gaseous wastes from the radwaste gas system a combination o f hold-tp for radicactive r decay and filtration through " roughing" and HEPA and charcoal filters prior to release is utilized. For the radioactive waste gases stored in the waste gas system, storage capacity is provided to permit storage of radioactive gases for pericds of cp to 90 days during normal operation prior to release to the environment. However, it i s anticipated that a minimum hold-up time, prior to release, cf - bout 2 weeks miwht be ancicipated during pericds when ecrip-ment has failed, malfunctioned, or is anavoidably out of service. For waste gas releases during normal operation, the minimum hold-up period prior to release of gas from the waste gas system is set at 30 dav,s, with the 90 day time usually bein-uti-3 lined. Further details of isotope types and concen-trations are described in Chapter 11 of the Final Safet"1 Analvsic Recortr a copy of which is available at ate Library of Pennsylvania in Harrisburg. 1,',I n., 3 -4 3 -

Name: Jarboe Transcript: 2748 Question: What is projected schedule for routine release of low-level radiation into the Susquehanna for Unit 2? What kinds and amount?? Answer: There is no projected schedule for routine release of low-level radiation into the Susquehanna. Releases of low-level liquids are made as required by operational experience and in accordance with all applicable limits. Operating experience for Unit 1 over the past year is as follows: There were a total of 128 liquid releases or an average of about one every three days. All releases were less than applicable limits. The average release was less than 1/2 of 13 of the applicable limit. As is typical of pressurized water reactors the major isotope teleased was tritium. The liquid wa te disposal sysrem processes all effluents. All radioactive liquids collected within the liquid waste system normally pasa through an evaporator, and, as condensate, through a mixed bed demineralizei, prior to being collected for re-use in *' a n.:4 L' s.'L.

6lF 9 or disposal to the river. Disposals to the river are on a batch basis with activity analyses. Samples frem the batch are obtained prior to disposal. Based cn the batch analysis and the diluent flow rate from the mechanical draft cooling towers, a maximum flow rate for the disposal of the batch is de te rmined. The flow rate of each such batch dis-po sal of radioa ct.17e 'iquids is controlled to ensure that the activity in the cooling tower effleunt being discharged to the river is within 10 CFR 20 and 50 limits. Set pointo on the flow and activity monitors (providing direct surveillance over the discharge of a batch) are set accordingly before initiating the discharge. After liquid waste enters the effluent from the mechanical draft cooling tower, the mixture travels approximately 275 feet before dischar-inc. w into the west channel of the Susquehanna River -- approximately 600 feet dcunstream of the river water intake structure. Satches of liquid waste are not released to the effluent from the mechanical draft cooling tower if its flow rate is less than 5,000 gpm and dilutica credit is taken only for ccoling tower effluent flow rates up to 38,000 gpm. M '. ^ <l 53

Tb-table on the following page (excerated from the NRC's Final Environmental Statement for TMI 2) shows the calculated releases of radioactive materials in liquid effluents expected from TMI 2 operation. 4 d),, n '., 3 er 1 1

A

r. _

-m-I },*m f ,? d TA3tE 3.2 l CALCULATED RELEASES OF RADICACT:'/E PATERIAL5 !N LICUI EFFLUE'4T5 h FRCM Tr'iREE MILE ISLAND NUCLEM STATICN, RiIT 2 . h-{ .5' Cf /yr/ reactor .d* .g, Nuclide Ci/yr Nuclide Ci/vr Corrosion & Activation Products Fission Products (continued) I3.i Cr-5; 1.4(-4)* 7.-129 7(-5) W %f 'i{s([' Mn-54 1 ( -3 ) - I-130 9(-5) .Wg Fe-55 1.4(-4) Te-131m 5(-5) wW Fe-59 S( 5) I-131 4.6(-2) pi Co-58 5.3(-3 Te-132 1.1(-3) e tJJp Co-50

8. 9(- 3) 1-132 2..(-3)

.e lh Zr-95 1.4(-3) 1-133 2.3(-2) Mjg Nb-95 2(-3) I-134 2(-5) pA N o - 2 3"> 5(-5) Cs-134 2.5(-2) C-s .fm 'ih' Fission Pr ducts I-135 4.7(-3) .y

N Br-23 3(-5)

Cs-135 3(-3) ' i.\\

b-86 2(-5)

Cs-i37 3.4(-2) .wy Sr-89 3(-5) Sa-137m 9.3(-3) y,nd Sr-91 1(-5) 3a-140 1(-5) y 4 f,n Mc-99 3.7(-2) Ce-144 5.2(-3) 4(1 u Tc-99m 2.3(-2) All Others 5(-5) .ig

  • g Ru-103 1.4(-4)

Total (exce; H-3) 2.4(-1) } .c Ru-ICS 2.4(-3) H-3 5.5(+2) I 3 '.M.. Ag-110m 4.4(-4) 3 ,@Y) Te-127m 2(-5) .h Te-127 3(-5) l p ( Te-129m 1.i(-4) E i 'E c crential notation; 1. (-4) = 1.0 x 10 Y U M Nu:lices wncse release. ates are less inan 70 Ci/yr are not listed .4 individually, but are ir.cluced in t*e ca:egory 'All Ct..ers. ' f, p I. Y&i . n., K. Ip 4 'gy 4h L f r.' f - 4 7 -. L D ',- A,Ij 0-ma 2 .1 ( !q. S ?.

e. Name: Jarboe Transcript: 2749 Question: Do you routinely test for radiractivity concentra-tions during or after a rain in the areas cited previously in the soil test questions. Answer: Rain water samples are routinely collected as monthly ccmposites and analyzed for radioactivity. The locations sampled are ?iest Fairview, Falmouth, the Observatior Center, and Marietta. Three of these locations are also coil sampling locations. As noted in the soil te s t" response, sampling at locaticns as distant as those indicated wculd be non-productive in that they are highly unlikely to be affected by controlled releases frcm TMINS. o-3a: A 6 2e s

W Septamber 9, 1977 UNITED STATES OF AMERICA NUCLEAR REGULATORY CCMMISSION Before the Atomic Safety and Licensing Board In the Matter of ) ) METROPOLITAN EDISON COMPANY, ) Docket No. 50-320 et al. ) ) (Three Mile Island Nuclear ) Generating Sbation, Unit 2) ) CERTIFICATE OF SERVICE I hereby certify that copies of the foregiong "Appli-cants' Responses to Questions Raised in Limited Appearance Statements" dated September 9, 1977, have ceen served upon each of the persons listed en the attached service list by mail, postage prepaid, this 9th day of September, 1977. Y" <f // s (su-/ /

  • c t, s).

Ernest L. Blake, Jr. September 9, 1977 r 19e6'

wg g-UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSICN Before the Atomic Sa'fety and Licensing Board In the Matter of ) ) METROPOLITAN EDISON COMPANY, ) Docket No. 50-320 et al. ) ) (Three Mile Island Nuclear ) Ge'erating Station, Unit 2) ) SERVICE LIST Edward Luton, Esq., Chairman Atomic Safety and Licensing Board Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Washington, D.C. 20555 Mr. Gustave A. Linenberger Alan S. Rosenthal, Esq., Chairman Atomic Safety and Licensing Board Atomic Safety and Licensing Appeal U.S. Nuclear Regulatory Cc= mission Board Washington, D.C. 20555 U.S. Nuclear Regulatory Ccmmicsion Washington, D.C. 20555 Henry J. McGurren Esc.. r Cffice of the Executive Legal Dr. W. Reed Johnson, Member Director Atomic Safety and Licensing Appeal U.S. Nuclear Regulatory Ccmmission Board Washing cn, D.C. 20555 U.6. Nuclear Regulatcry Commission Washington, D C. 20555 Dr. Ernest O. Salo Professor, Fisheries Research Jerome S. Sharfman, Esq., Member Institute, WH-10 Atomic Safety and Licensing Appeal University of Washington Board Seattle, WA 98195 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Dr. Chauncey R. Kepford 43'. Orlando Avenue Docketing and Service Section State College, PA 15801 Of2 ice of the Secretary and U.S. Nuclear Regulatory Ccmmission 2585 Broad Stree: Washington, D.C. 20555 York,.PA 17404 Karin W. Carter, Esq., Assistant LIMITED APPEARORS: Attorney General Office of Enforcement Elicabeth Northam Department of Environmental Resource-1125 N. Front Street 705 Health and Welfare 3uilding Harrisburg, PA 17102 Harrisburg, PA 17120 c 2 Marv Swann -,ti s. i. .o R.D. New Park, PA 17352

9 David Leavitt Rte. 2, Box 2743 Spring Grove, PA 17362 Ray Hearne Muddy Creek Forks Airville, PA 17302 John Simon c/o Ms. Virginia Southard 3514 Walnut Street Harrisburg, PA 17120 Robert J. Jenison R.D. 2, Box 148A New Cumberland, PA 17070 Dr. Carl J. Jarboe 9 East Marble Street Mec'Tanicsburg, PA 17055 Dr. Judith Johnsrud 433 Orlando Avenue State College, PA 16801 Abigail Jarboe 9 East Marble Street Mechanicsburg, PA 17055 William V. Whittock Box 234 Etters, PA 17319 Milton Lowenthal 5017 Haverford Road Harrisburg, PA 17120 Jane Donahue R.D. 3 Etters, PA 17319

tary Douglas Mill Road Grantham, PA 17027 a.', '

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