ML19220C197

Responds to 770719.Forwards Utils Comments on Effluent Radiological Tech Specs,Nrc Radiological Environ Monitoring Position & Fes

ML19220C197
Person / Time
Site:	Crane
Issue date:	09/16/1977
From:	Herbein J Metropolitan Edison Co
To:	Regan W Office of Nuclear Reactor Regulation
References
GQL 1194, GQL-1194, NUDOCS 7904300051
Download: ML19220C197 (38)

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METHOPOLII AN EDISON COMPANY PCsT CFFICE BCX 542 REACtNG. PENNSYLVANI A 196c3 TELEN CNE 215 - 909 6c1 Septe:ber 16, 19~7 uw.. 9.

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Division of Site Safety and hvircnnental Analysis

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s Occiet :ic. 50-320 Sciesed please find Met-Ed's respense to you-letter of July 19. 1977.

Scicsure 1 is cur respense to the Radiclegical Assese-a"+ '-e--h pcsition en radiclegical envircnnental =cnitoring.

Encicsure 2 prcviles explanatica for those instances in which Met-Ed disagrees with the staff's cc=ents expressed in the Final Environ-cental Statement (FES).

5:1csure 3 provides Met-Ed's respctse to the proposed inte '- a"ent

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mental Technical Specificaticns, we present cur cc==ents as isciated specifications and allev the Oc==issien to supply the e.ppropriate fo' mat.

~4e request that a "Frcof s=d Review" copy of these CC-2 Envircncental Technical Specificaticns (E"'S), including both the radiclegical and ncn-radiclogical sections be fc-varded to us as scen as pcssible.

Althcugh references a-a

-e to CC-1 in this submittal, it is cur in-tentien that *het.e specification iters not beccre effective for 2C-1, until ve r pecifica.ly request that they becct. 3ffective thrcugh tha specificat'.cn change request process applicable tc 2C " nit 1.

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tief September ;6,1977 b-,.,, n,y4

'4e trust this sut=ittal tc be satisfs ctc:/, hcvever shculd you have any additicnal questions, please ecntact me.

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'. G. Eerhein

<J Vice President

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.n o Encicsures:

1.

Response to the Radiclogical Azess=ents 3 ranch positica and Enviren= ental Mcnitoring.

2.

Justifica. ice for.v t-Ed's disagreement with staff's e

ec==ents expressed in the Final Enviren= ental St atement (FES).

3 Met-Ed's respense to interi effluent radic1cgical Technical Specifications.

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Attachnent #1 Met-Id C0: any September 16,1977 G4L 119h Attach =ent #1 Met-Id's Respense to the Radiological Assessments 3 ranch Position en Invironmental M:nitoring n ^)

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Attach =ent #1 RADICLOGICAL Er/IRC:TME'!'AL :CIITCRU3 PROG?XI 32 Scecification An enviren= ental radiological =cnitoring progras shall be ccnducted in the vicinity of the Three Mile Island :iuclear power Statien.

hviren= ental sa=ples shall te collected and analyced according to Table 3.2-2 at lccatiens shown in Figures 3.2-1,2,3,k.

Analytical techniques used shall be such that the detectica capabilities in Table 3.2-3 are achieved.

The laborateries of the licensee and licensee's centracters which perfor=

c:al7aes requird by the=e cpecificatices sha.11 participate in the Environ-

_ ental Prctection Agency's (IPA's) hviren= ental Radioactivity Laboratcry

.Intercenparisons Studies (Cross-check) Progrs= or equivalent program. This participatics shall include all of the deter =inaticas (sa=ple mediu=-radic~

nuclide ec=bination) that are offered by IPA and that also are included in these specifications. A s"-a y of the results of analysis of these cross-check sa=ples shall te included in the annual report.

A census shall be cenducted annua'iy during the g-cving seasen to deter =ine the locatica of the nearest = ilk an4"' in each of the 16 metecrolegical secters within a distance of 5 miles. 3rcad leaf vegetation sa-pling vill be perfor=ed at the site boundary, annually at ha-est time.

w, c,i MV a A J.r Deviations are per=itted frc= the required sampling schedule if speed = ens are unobtainable due to hacaricus cenditiens, seascnal unavailability, =al-functica of autc=atic sanpling equip =ent and other legitimate reasons.

If specimens are unobtainable due to sa=pling equipner.t nalfunction, every effort shall be =ade to ec=plete correceive action prior to the end of the next sampling peried. All deviations frc= the sa=pling schedule shall be documented in the annual repcrt.

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-c If the results of a deter =inatien in the IPA crewheck pregram (cr equi-valent pr gra=) are outside the specified centrol li=its, the laborater/

shall investigate the cause of the pr ble= and take steps to correct it.

The results of this inves*1gatien and ccrrective actica shall be included in the annual repert.

If it is lee =ed frc= this census that = ilk ani=als are present at a loca-tien which yields a calculated thyrcid dose greater than these previcusly sa= pled, or if the census results in changes in the locatica used in the radicactive effluent Technical Specificatiens fer dose calculaticns, a v-itten repcrt shall be sub=itted to the Director cf Operating Eeacters,

'IEC (with a ecpy to the Directer of the :!EC Eegicnal Office) within 30 dir/s identiffing the nev 10catica (f.istenes :.nd directien).

'm > ani=al locatiens resulting in higher esiculated deses shall be added to the surveillance pr:grs= as scen as practicable.

Se sa= cling 1ccatica having the icvest calculated dcse =ay then te drcpped frc= the surveillance pregrs= at the end of the g acing sessen during which the census was cceducted. Also, any locatien frc= vhich = ilk er bread les' vegetatien can no lenger be cbtained =cy be dr pped frc= the surveillance p=grs= afte nctif/ing the :iEC in v-iting that they are no lenger eb:ainable at the location. Se results of the =112 animal census sW ? te repcrted in the annual report.

a Ae_ _c The results of the radiclogical enviren= ental =cnitoring pr grc= are intended te supple =ent the result of the radiclegical effluent =cnitcring by veriffing that the =easurable cencentrations of radicactive =aterials and levels cf radiatien are not higher than expected en the basis of the effluent =easur-=ents and =cdeling of the enviren= ental expcsure pathways. Thus, the specified en-n=n= ental =cnitcring progra= provides =easure=ents of radiation and of radie-active =aterials in these expcsure pathways and for these radienuclides, which lead to the highest pctential radiation exposures of individuals resulting frc= the s+.atien cperation. The initial radioicgical enviror._ ental nonitoring pregra= shculd be conducted for the first three years of ec=nercial operatien (cr other period corresponding to a -* u= burnup in the init:.a2 core cycle).

Folleving this period, progra= changes =ay be preposed based en operaticnal experience.

The specified detecticn capabilities are state-of-the-art for reutine enviren-

= ental ceasure=ents in industrial laboratories. The L1D'S fer I-131 in vater,

=11% and cther feed products cor espend to ene-quarter of the appendix I (10 CFE Part 50) design objective dcse-equivalent of 15 =re:/yr.

They are based on the assu=ptions given 10 Regulatory Guide 1.109, except the change for an infant eensu=ing 3301/y cf drinking vater instead cf 5101/yr.

The census of = ilk ed Ws and gardens producing bread lea' vegetntion is based en the require =ent in Appendix I of 10 CFE Part 50 to " Identify change in the use of unrestricted areas (e.g., for ag-icultural purposes ) to pcr=it =cdifi-cations in =cnitoring progra=s fer evaluating deses te individuals f== principal pathways of exposure. " The censu=ption of =11% f c= ani=als grazing en cen-ta=inate:1 pasture and of leaff vegetatica centa=inated by airborne radicicdine is a =ajor pctential scurce of expcsure. Samples frc= = ilk an -u s are con-d sidered a better indicater of radioicdine in the enviren=ent than vegetation.

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3 If the census reveals = ilk and-s are not present er are unavailable for sa=pling, then vegetation =ust be sa pled.

The 500 sq. ft. garden, censidering 20% used fer g-cving bread leaf vegeta-tien (i.e., si=ilar to lettuce and cabbage), and a vegetation yield of 2 kg/ 2, vill produce the 26 kg/yr assumed in Regulator / Guide 1.109 for child censu=pticn of leafy vegetation. The cptic to censider the garden to te bread leaf vegetation at the site boundarf in a secter with the highest X/q should be censervative and that 1ccr.tien ra'/ be used to calculate deses due te radioactive effluent releases in place of the actual 1ccatiens which vculd be deter =ined by the census. This cption does not apply to plants with elevated releases as defined in Regulatory Guide 1.111.

7:e pe. issica of deviaticas frc= the sa=pling schedule is based on the re-

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cognitien of unavoidable practical difficulties which in the absence of the pe=itted deviations would result in violation of the specificaticts.

The requirement for the participatica in the E?A cross-check pregrs=, or similar progra=, is based on the need for independent checks on the precision and accuracy of the reasurements of radicactive =aterial in environ = ental sa=ple matrices as part of the quality assurance program for environ = ental nenitoring in order to de=cnstrate that the results are reasonably valid.

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Eerc-tine Fecuirenent A.

Annual hviron= ental Operating Eeport, Part 3, Ealiclegical.

A report en the raEclogical environmental surveillance pregrc for the previous calendar year shall be sub=itted to the Director of the :iEC Regional Office (with a ecpy tc the Director, Office of :iuc'e* D~ter Regulation} as a separate docu=ent by M.sy 1 of each year. The period of the first reper. shall begin with the date o' ' d a' criticality.

The reports shall include a st-arf (f:rmat of Table 1), interpretations, and statistical evaluation (as deemed appropriate bf the licensee) of the results of the radiological envirennental surveillance activd_ ties for the reper: period, including a e0=parison with Operational centrols,

precperaticnal studies (as appropriate), and previous envirennental surv=4a = reports and an assessment of the observed i= pacts of the station cperatics c the envirennent.

E the event that sete results are not available, the report shall be sub=1tted noting and explaining the reasons for the missing results.

The missing data shall be sub=itted as scen as possible in a supplementarf,

repo rt.

Che reports shall also include the fc11tving: a s'-,ry description of the radielegical envir:n= ental =enitoring program including sa:pling metheds for each sa ple type, size and physical characteristics of each sa=ple type, a map of all sa:pling locations keyed to a table giving dis-tances and directicns frc= cce reactor; the results of milk n-4-n' census required by the Specificatien 3 2; and a s-,rf of the results of licensee participation in the hvironmental Protectica Agency's hviren= ental Fadioactivity Laboratorf Eter:0=pariscus Studies (Crescheck) Progran, vill als: te included.

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Nen-rcutine Eadiclegical Environmental Cperating Reports "If a confirmed (2) =easured radiccuclide concentratien in an enviren-cental sa=pling =edium averaged over any quarter sanpling pericd exceeds the reperting level given in Table 3 2 h a written repcrt shall be subnitted to the Director of the NRC Eegional Office (with a ecpy to the Directer, Office of Nuclear Reactor Regulatien) within 30 days frc: the end of the quarter.

If it can be dencnstrated that the level is not a result of plant effluents (e.g., by ec=parisen with centrcl static: cr preeperatienal data) a repcrt need not be sub=itted, but shall be discussed in the annual repert. When =cre than ene of the railenuclides in Table h which are attributed to stati0n effluents are detected in the =ediu=, the reperting level shall have been exceeded if:

eencentrstienfl) concentratien (2)

...> 1 reperting level (1)+ reperting level (2) +

If radienuclides other than those in Table 3.2 h are detected and are due free station effluents, a reperting level is exceeded if the potential annual dose to an individual is equal to or greater than the design objective doses of 10 CFR Part 50, Appendix I.

This report shall include an evaluatica cf any release cceditiens, envirennental factorc, or other aspects necessary to explain the anc=alcus result.

9 (2) A ccnfirratcry reanalysis of the criginal, duplicate, er a new sa ple may be desirable, as appropriate. The results of the cen-fir:atory analysis s% be ec=pleted at the earliest time con-sistent with the analysis, but in any case within 30 days.

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T AD11 3.2-1 f.MYllMbHHtJfTAL hAbliifDlICAL H)MIR4t!NG I1#0GNM4 AMMU Al.1R49tAhi IDFMAT 13AMIE Name o f Fac t i t ty LM ket NO.

I tucation of Fas;llity Repor tir.g I'er tuJ l

(Cussity, State) l T'pe and

44. wor I.lat t N.mter of y

Medium or l'ellaway Tot al W.=ber of All indientor lascatione

!><at t on wi t h H f,, hest Aa.nual Mesa Control lascetione N.orta. tine faam i.l ed of Assely.cs Imtestion" Nan (f)b g,,,

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Perfurned (IJ L)

Hange Distance & Direction fiange htmp e n as cceents Air Particulates (pC1/m )

Grose B 416 0.003 0.0$(200/ 312 )

Midatetown 0.10(S/52) 0/08 (8/30%)

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(3.05-1.40)

Y-Spec. 32 IN Ce 0.003 0.05 (%/24) f=sithullie 0.08 (2/4)

< tJD 4

(0.03-0.13) 2.5 miles (0.03-0.13)

I0 8 0.001 0.03 (2/24)

Iww.h 0.05 (2/h) 0.02 (2/h) 3 (0.01-0.08) 4.0 sites (0.01-0.08) 3r b0

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leh 90Sr 40 0.0003

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• See Table 3.2-3, note b.

Mean and range bened ugen all meeriu ements with IJD treateJ as poet tive valve. Fractica of detectabl e oceeuremente at et'ec t rieJ locatloce is Indicated la parer. theses. (f)

• Note The esemple, data are provideJ for litustrative purposes only.

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i TAllLIC 3.2-2 RADIOLOGICAL ENVIIt0NMENTAL SAMPLING (1)Composite of all unmples for the quarter two (2) groups Background Samples and Indicator Samples.

If Cs-137 levels exceed 20 pC1/m3 for any GS analysis, a Sr-90 analysin vill be performed.

(2)

In the event of icing or dangerous conditions on the Susquehanna River, the campling frequency may be extended tuttil river conditions permit sampling.

(3)

River water sun ples will be collected weekly and composited for monthly and quarterly analyses.

(3 )

8 A Gr-89 analysis vill be performed on each sample analyzed for Sr-90 if the Sr-90 value exceeda the 10 pCi/L.

(5)

One sample of each of two recreationally important species.

(6)

If Cu-137 levels exceed 50 pC1/L for any G3 analyais, a Sr-90 vill be performed.

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TABLE 3.2-2 IlADIOLOGICAL ENVTilONMENTAL SAMPLING I

No. of Sample Stations Collection /Analyaiu Sample Ty g Indicato "l ackground (d)

Type of Analyals Frequency (a)

Collection Site Air 3

1 131 Charcoal Cartridge See Fig. 3.2-1 Iodine and 3.2-2 5

1 GB Particulate Weekly GU(1)

Quarterly (1)

Sr-90 Quarterly if Cs--137

> 20pC1/m3 Radiation TIJ) 10 2

Camma Quarterly See Fig. 3.2-2 and 3.2-3 131 f11]k 3

1 Iodine tlonthly (during See Fig. 3.2 !#

grazing neuson) 131 CS If Iodine > 10 pC1/L Sr-90 If Iodine > 10 pCi/L Green Leary Vegetables (g) 2 1

GS Annually (at harvest)

See Fig. 3.2 1 6 River Water (e)(2)(3) 1 1

GS (6)

!!onthly See Fig. 3.2-1 i

Tritium Quarterly

' CD O Drinking Wut.er (t)(3) 1 90 Strontium (l)

Quarterly See Fig. 3.2-2 i

GS

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Tritium Quarterly L7 Sediment (2) 1 GS Semi-Annually See Fig. 3.2-1 Flah (2)(5) 1 1

GS Semi-Annually See Fic. 3.2-1 1

Giba Groan Beta (b)

G3= Gununa Scan (c)

Table 3.2-2 (continued)

"The number, media, frequency and location of unnpling may very from uite to uite.

It is recognized that, at the time it may not be possible or practical to obtain samples of the uedia of choice at the most desired location or time.

In these instances suitable alternative media and locations may be chosen far the particular pathway in question and submitted for acceptance. Actual locations (distance and direction) from the site shall be provided.

Particulate cample filters should be analyzed for gross beta 21 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or more after sampling to allow fc. radon-thoron daughter decay.

If gross beta activity in air or water is greater than 10 times the mean of centrol stunple for any medium, gamma isotopic analysia should be performed on the individual camples.

1. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluento from the facility.

dThe purpose of this sample is to obtain background information. If it is not practical to establish control loca-tions in accordance with the distance and wind direction criteria, other siten which provide valid t>ackground data may be substituted.

"The " upstream sample" should be taken at a distance beyond significant influence of the discharges. The "down stream" enmple should be taken in an area beyond but near the mixing zone.

"Ilpatream" samples in an estuary t.aken far enough upstream to be beyond the plant, influence.

Composite samples should be collected with equipment (or equivalent) which is capable of collecting an aliquot at time intervals which are very short (e.g., hourly) relative to the compositing period (e.g., monthly).

Elf harvest occura more than once a year, campling should be performed during each diacrete harvest.

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IEGEID SCALE E TAL. :p.T"'.CRI"O ST;

{C' "{'[Qy(,"' GEE CLE AQS - AQUATIC SEDE'E::"' S"'ATIC:s AI - AIR ICDI::E SL :D :iUCLEAR STA~

AQF - AQUATIC FISH (EDI3LE FCETICN)

S'J - SUF5 ACE '4ATER FICURE 3 2 AP - AIR PARTICUL/CE

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EiETABLE STATICN S F FL - FCCO PRoodCT, LE AFY MILK & VEGETASLE S AM? LING STATlc

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Table 3.2-3 Detectiors Capabilities for Dwironmental Stunple f.nalya la Inver Limit of Detection (LLD)b Airborne Particulate Water or Gas Flah

!! ilk Food Products Sediment Anaysic (pci/1)

(pC1/m3)

(pCi/kg, vet)

(pC1/1}

(pC1/kg, wet)

(pC1/kg, dry)

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'!!n 15 130 39Fe 30 260 O

Co 15 130 IS Zn 30 260 ISZr-fib 10 d

d L311 0.8~

7 x 10-2 0.8 25,"

1 L3.,137Cs 15 1 x 10-2 130 15 80 150 IL40Ba-La 15 15 OJ r!.D (a) b

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" Acceptable detectica capabilities for ther=cl=inescent desi=eters used for envirc ectal =easre=ents are given 1: Fogulatcry Guide h.13.

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" Table 3.2-3 indicates acceptable detectics capabilities for radicactive =aterialc in envirce= ental sa=ples. 2.ese detectics capabilities are tabulated in terms of the lever li=its cf detectic ( LL'i) 2e LLD is defined, for purpcses of this guide, as the s est ecccentruit. Of radicactive material in a sa=ple that vill yield a re* ccust (above syste= backgrcund) that will be detected with 95% probability vith cely 5% prtbability of falsely :::cluding that a black cbservatic represents a "real" signal.

For a particular =eas=e=ent syste= (which =ay include radicche=ical separatic=):

h.66 3b LLD = I expl ^J.;)

7 2.22 Y

vhere L1D is the icver li=it c.' detectien as defined above (as pCi per unit

= ass er vel =e) s is the standard deviatics of the backgrcu=d ccusting rate er cf bthe counting rate cf a black ss=ple as apprcpriate (as ecunts per

=1:ute)

I is the ce= ting efficiency (as cc=ts per disintegratic=)

V is the sa=ple si:e (in units of = ass cr vel =e) 2.22 is the nu=ber of disintegratices per =inute per picce rie Y is the fractic:al radicche=ical yield (when applicable)

A is the radicactive decay ec stant for the particula radienuclide (I-131)

At is the elapsed ti=e between sanple collectic: and counting (I-131) 2 e value of S used in the calculatics of the LLD for a particular =easure=ent b

syste= should ce based ce the actual observed variance of the background ccunting rate or of the cc= ting rate of the black sa=ples (as appropriate) rather than c an unverified theoretically predicated variance. In calculating the L1D fer a radiccuclide deter =i=ed by g,-'-ray spectrc=et y, the backgrcund shculd in-clude the typical centributicus of other ra:iicruclides scr-ay present in the s a=ples ( e. g., potas si= ho in =il's sa ples). ?jpical values of I, V, Y, and Lt shculd be use:i in the calculatica.

• C ly applicable to I-131 analyses.

oq 4 'J C0 (Us

.- 2 --

Table 3.2-3 : ctes (Cc t. )

It should be recogni:ed that the LLD is defined as an a priori (before that fact) li=it representing the capability of a =easure=ent syste= and net as a ;csteriori (after the fact) li=it for a particuir seasurerent.

C LLD for drinking vater.

171 d.S 's fer

• I in vater, = ilk and other fcod products correspc d to c e.

quarter of the Appeniix I (10 CFE Part 50) desire objective d.cse-equivalent of 15 =re=/ year using the assu=pticas given in Regulatory cuide 1.109 except for an infant ecesu=ing 3301/yr of irinking vater.

e LLD for leafy vegetables.

e f r,

<UU C '0

\\

0

)

t f ne aov 2

3 3

ei 0

0 0

1 1

1 Lt ag dt K x

x x

ae/

ogi 1

1 2

rec BV p

(

2

?

0 1

k/

1 0

0 l1 iC 3

6 7

x Mp 3

(

3n

't f0P

)

)

E a

t I

(

e t

)

w 3

3 G

L b

"0 0

0 0 0

'0 0

h N

lI I

(

s g 1

1 1

1 1

1 1

T iK A

l F/

x x x

x r

x x

t e

i 3x v

c 3 1 3

1 2

1 2

P e

p O

L

(

E g

N n

la I

i T

t 2

0 r

0 o

3 t

p I

e E

N e

l l

L O

t B

N a)

A l3 T

um lIO c/

F

i. 1 d

t 0 o

3 rp i

J I

a(

r E

P e

9 p

V s

E ee L

ns 0

0 0

g ra 1

2 n

G oG i

b l

I rr p

T i o m

A a

l lO s

PE y

l l

l re tra

)

h 3 2 3

2 2

2 u

r1 0

0 0 0

0 0

0 0

q e/

1 1

1 1

1 1

1 1

ti 0

0 y

aC x

x x x

x x

x 2

3 5

x n

W p a

3 1

14 1

3 3

h 2

(

r evo deg a

o r

s 5

h e

i 9

l v

s 4

7 a

y la 9

8 0

5 b

1 3

3 a

l S 5 5

6 6

N 3

1 1

L a

3 1

A 1

t!n e

o o

n r

s s

in a

n 1

F C

C Z

Z I

C C

~

g

Attach =ent #2 Met-Ed Cc pany Septerter 16,1977 C E 119L Attachment #2 Justificatica for Met-Ed's Disa,reement With Staff's e

Cc= ents I ressed in ce Final Enviren= ental Statement (FES)

/O a

c. n

() 's IOV

Attach =ent #2 Met-Ed Cc=pany Septe=ber 16,1977 GGL n9k Ce rents en FES Chao. 6.6.1

?iPC Fece=en tatiens Rec 1rdin SII Radic1ccical Envir---

a ' V *-- -ine pregess Ite: 1.

a) Air Particulate sa=pler added at Fal=cuth, b) SR-09 analysis not performed qua_Merly since SR-59 T 1/2 tcc shcrt for meaningful results.

c) SR-90 analysis vill be dcne en any air particulate sa=ple which has a Cs-137 cencentration in excess of 20 pCi/=3, 2.

An Icdine sa=pler was added at Fa'-^uth.

3 Soil vill net be sa: pled fer the fonoving reascas:

a) The le els of radioactivity fcund in soils is principally cor.r 11ed by rate a=d a= cunt of: rainfall, eresien, til-lage, rect depth, and grevth rate of covering plants and caly to a =inor extent by radicactive fallout whether weap-ens or plant related. Therefore it is extre=ely difficult to extract meaningful te= poral or spatial results frc= the a=alysis of soil. As such soil is not censidered a valid indicator of Icag ter= radienuclide accu =ulatien.

L.

a) A ec=pesite water sa=pler is being installed at locatica 8C.

b) SR-90 analyses vill be perfor=ed en any river vater sa=ple for which the CS-137 concentratica exceeds 50 pCi/L.

c) SR-89 analysis will net be perfor:ed on quarterly river vater cc=posites due to the short T 1/2 of SR-89

.E. a) Mill samples vill be collected at the highest X/Q iccation

=enthly since 3 years of operatienal data, has shown a cal-culated infant thyroid dose of <<1 =re= per year.

b)

G= -a scans and SR-90 analyses vill be performed on any mili sa=ple for which the I-131 concentratica exceeds 10 pCi/L.

c) SR-89 analysis vill not be performed since this is not an important dose contributer via this pathway.

6.

Two recreatienally i=portant fish species vill be ecliected and analyzed frc= each fish sampling iccation.

T.

a) Two different fruits vill be sample' K tach cf two locaticns.

b) Green lea'y vegetables vil be co' h at two locatiens having high X/Q values, and si-

=ples vill bc =cre

.2 indicative of radionuclide au/ me rect vegetable sa=ples vill not be collect

• () G on t

00

Attach =ent #2 Met-Ed Cc= pan'y Septe ber 16,1977 CQL 1194 8.

a) Meat, poultry and eggs will act be sampled because none of these media are in a critical radienuclide pathway as deter-

=ined by air particulate sa ples, air icdine ss=ples, green leafy vegetable sa:ples and water sa=ples; hcvever, should it becc:e apparant that meat, pcultry or eggs would enter a critical pathway as deter =ined by the results of the named indicator media, these vill be sa pled.

b) Gare species have been sa= pled without =eaningful results even though they do not provide an i=portant scurce of dieta / protein (in the TE3 envirens). These vill be left as a discretiona./ sa:ple.

~

9 Lever Limit of I:etectica (LLD) ter=inclogy and a table of LLD's of nuclides have been prepared and included in the ETS.

10.

The sensitivity of the tritium in water analyses has been increased to 330 pCi/L which agrees with R. G. h.8(Oraft Dec. 1975)

h..

q '

Met-Ed Cc pany

~

-I~

p 11%

epte=cer 16,1c77 2.0 LIMITINO CONDITIONS FOR OPEMTION 2.0 MONITORING REQUIROTITS 2.3 Pe.dio. active Discharges 2.3.1 Lieuid Effluents Aeplic:bility Applies to the centrolled relcese of radiosctive liquida fren TM1 Unit Nes. 1 and 2.

Objective Objective To define the limits and conditiens To ensure thac radioactive liquid for the centrolled relesse of liquid releases fren the facility are radicactive effluents to tne envirens within the li=1ts cf Specifica iccs to ensure that thesc releases are as 2.3.1 a, through e.

lov es p seticabic.

These :cleases should net result in radiation exposures to off site areas g:catcr than a few percent of background expesures.

The instantaneous re-leano rate fer all effluent discharges sheuld be within the li=its specified in 10CT?.Part 20.

To assure that the releases of

dicactive liquids to off site areas neat the "as lov as ;;acticable" concept, the felleving objectives apply:

a.

The annual total quantity of radicactive nsterials in liquid vaste, excluding tritium and dis-solved gases, should not exceed 5 curies por :sdioactive vaste-producing cacter, and the annual dose to the whole bcdy or =ny c:can of an individual should not exceed 5 :cs f:c= the : cabined releases of Unit Mos.1 and 2.

b.

The annual average concent:stien of radicactive anterials in the effluent from the Mechanical Draft Ccoling Tcvers prior to dilutien in the Susquehannc F,1ver, excluding tritium and diccolved gases, sheeld not exceed 2 x 10-6 uci/=1.

c.

The annual average concentratica of tritium in liquid vaste prier to dilutica in the envirectent shculd

},\\

not caceed 5 x 10-6 uci/=1.

rO OC i

-. 2-2.0 LIMITI'IG CO'IDITIC'?S 70R OpIRA ION 2.0

!'C:!ITC I'IG PF;UIRZ"I':TC Sre cifi cation Sce ci ficat icn a.

Tne radicactivity release During release of liquid radioactive concentration in liquid effluents vastes f c= the Waste Ivaporatcr frc= Unit 'Ics.1 and 2 to the Cendensate Sterage tank and the enviren=ent shall not exceed the Waste Evaporator Ccndensate Test values specified in 10 CTR 20, Tank, the conditions shall be met.

Appendix 3, for unrestricted areas.

a.

The liquid gress activit/

=cnitors (U+it 1: DI-Lo; Unit 2 b.

The total release of radicactive

..,s. _2.,.n., ),.,.,.,. s,._,.,,, de.g. c., a.

n a..

,,,,,,,2 e.,.,.,.....,,_,r,,4.

.; s.

and r

um.

recorder en the raisaste effluent 2, excluding tritius and ncble gases '

line shall be operable.

shall nc exceed 10 curies per radicactive vaste-producing reactor b.

The liquid gress activity during any calendar quarcer.

--.4.,,,.

( gm.,4

.m g_ Lo'.

Umd* 2-

'@L-3-1311) er sinilar device shall c.

Tne equipment installed in the be set to ala = c.nd autenatically liquid radicactive vaste system clcse vaste discharge valve (Unit 1:

shall be naintained and shall be WDL-V-257; Unit 2: WDL-V-99) cperated to process all radicactive

,..su e et,,re., y 4

,.. o.,, e x...,, 4. -

+s,

.w

-.~e liquid vastes prier to this discharge

,,,. s s n e e,.,.,,. a. 4.,0 Cr. R. ^c0,

when the activity release rate vill

^

Arpend1x 3 for unrestricted areas.

exceed 1.25 curies per radicactive vaste producing reactor, excluding c.

Liquid vaste radicactivity and tritiu= and dissolved gases, during flow rate from the vaste evaporator any calendar quarter.

condensate storage tank (Unit 1) and the vaste evstorator cendensate d.

h. e - M '- -adir a-'. d. d.'.y '.o

• e test tank (Unit 2) shall be d

cent a - a d _a cne liquid ratsaste tank, cent.,nuous,y men., ored anm recera..

a a a

._.x,.,.. a t -.e,,., <,

an

$$ggv,5.e 6 ages, r..

a a

d,,, 4 g,,,.,, as e.

y,

.w,

-- r.

that can be discharged directly, to canno be =e., cen., nue. re., eas e c.,

a the envirens, shall not exceed 10

,, c1.,,. d e.,,, uent s s 3.,.a.,,. sm e r e.-...t e,.

c "~ ~* a s *

~

cnly during the succeeding h8 hours provided that du-ing this h8-hour e.

anen the average release rate ci, radicactive effluents, excluding

• re,eti tvo,nderendent sa=cles c;,,

e aca,,.ank s,a,_, be ana.yced and vo tritium and dissolved. gased, exceeds m

s.,,at.,cn personnel shall.,ndependent,y 2.)_ curies per radicactive vaste-c eck valve 1.,ne-up pr,.':r to the s

producing reactor during any a y,, cha.,._,.

-a e_

calendar quarcer, the licensee shall

.c +o.< iy

+e m e fR C,e4 + u..,.,.

=.0 p.,, s,

s u

f d.

yac.4., 4../

._ - a s s h,,,, s,,,,,,,,, -

identi.^/ing' the causes and e-

. a,,,, e m o., t h e,., a2 4,,, a.,,.

4...,,

a o.-

da a c.' d.b 4 - - 'ka 2-wre s e d. - e-. c." o" a

'"6 y

,,,,,,,CC,.,,..

c, a 7C.,,,,.,,., t e.c,,,,,

~

acticn to reduce such release rates.

a_, ~,,,.,,. n o,. e,.,. c.,

s~,...,

.c..

v a.

e ffluent releas ed, and the average dilutica ficv and length of time over which each discharge cecu rei.

Radioactive liq' id vaste canpling e.

and activitf analfsis shall be performed in accordance with ao,, o..o_.,.

i

]

4

, n

\\

4 L--

_. 2.0 MONITORING FICUIREMDiTS 2.0 1.7?ttitjjlCMDITIONS FOR OPERATION Specification (Cont'd) f.

The liquid effluent radiatica

. m uitors M-L6 and WDL-R-1311 shall be calibrated at least quarterly by means of a kncun radioactive sourec.

RM-L6 and 1:DL-R-1311 shall also have an'instrurent channel test centhly and a source check pric to each discharge to verify that the read-out device is indicating as expected, g.

The ability of WDL-V-257 and WDL-V-99 to clese autc=atically en receipt of a high radiation alar:t signal from RM-L6 and WDL-R-1311 shall be checked annually.

e e

e

\\#

TABLE 2.3 1 Radioactive Liquid '4aste Sa:pling and Analysis (4, 5)

A.

Monitor Tank Releases T1pe of Detectable Sampling Frecuency Activity Analysis Concentration (3)

Each Satch Individual Ca--'

5x10-7 uci/ml (2)

E-3 10-5 uci/=1 Monthly Ce=posite (1)

Gross Alpha 10-7 uci/n1 Sr89 5x10-8 uci/=1 Sr90 5x10-8 uci/=1 Notes (1) A ce=posite sa=ple is one in which the quantity of liquid sa= pled is proportional to the quantity of liquid waste discharged from th,e plant.

(2) For certain =ixtures of gn--n e=itters, it may not be possible to measure radicauclides in concentration near this sensitivity li=its when other nuclides are present in the sacple in =uch greater concentrations. Under these circum-stances, it will be more appropriate to calculate the concentrations of such radionuclides using =easured ratios with those radionuclides which are routinely identified and =easured.

(3) The detectabill:7 li=1ts for radioactivity analysis are based on the technical feasibility and on the potential significance in the environ =ent of the quantities released. For some nuclides, lower detection 14 d ts =ay be readily achievable and when nuclides are measured below the stated limits, they should also be re-ported.

(4) The results of these analyses thould be used as the basis for recording and reporting the quantities of radioactive =aterial released in liquid ef fluents during the sa=pling period. In estienting releases for a period when analyses were not perforced, the average of the two adjacent data points spanning this period should be used. Such esticates should be included in the effluent re-cords and reports; however, they sheuld be clearly identified as esti=stes, and the =ethod used to obtain these data should be described.

(5) Deviations frs, the sa=pling/ analysis regi=e will be noted in the report' spe-cified in 5.6.1.

.b,nO il OD I'

2.0 LIMITINC CONDITIONS FOR OPERATION 2.0 MONITORING FIQt IRErCITS Bases Bases Liquid radicactive vaste release Specificaticas a, b, and c, above levels to unrestricted areas shculd require that suitable equip =ent to be kept "as Icv as practicable" and cenitor the release of radioactive are not to exceed the concentration

=aterials in liquid effluents are li=its specified in 10CTR 20.

The operating during any period these obj ective provides reasonable as-releases are taking place.

surance that the resulting annual exposure to an individual in off The surveillance require =ents g.

en site areas will not enceed 5 =1111-in the re=aining specifications pro-rem per year. At the sa=e ti=s, vide assurance that liquid wastes are these specifications per=lt the properly centrolled and =enitored flexibility of cperatien, cc pati-during any planned release of radio-ble with censiderations of health active materials in liquid effluents.

and safety, to assure that the These surveillance requirecents pro-public is provided a dependable vide the data for the licensee and source of power under unusual the cc==issica to evaluate the sta-operating conditiens, which cay tica's perfor=ance relative to radio-te=porarily result in higher than active liquid wastes released to the nor=al releases, but still within environce.3t.

the concentratien limits specifie'd in 105"'. 20.

It is expected that by using.his operational flexibility under unusual operating conditions, and exerting every effort to keep levels of radioactive =aterial in liquid wastes as lov as practica-ble, the annual releases will not

-e-exceed a s=all fraction of the an-nual average cencentratica 14-* ts specified 'in 10CTR 20.

Specification a. above requires the licensee to 11=1: the concentration of radioactive caterials in liquid effluents from the station to lev-els specified in 10CTR 20, Appendix B, for carestricted areas. This specificatica provides assurance that no me=ber of the general pub-lic can be exposed to liquids con-taining radioactive caterials in excess of licits considered per-missible under the cc--4 esicu's rules and regulations.

Specification b. cbove establishes

- an upper 11=it for the release of radioactive liquid effluents, ex-cluding tritium and dissolved

,c gases, of 10 curies per unit dur-

{ }

,g i 3 ing any calendar quarter. The in-tent of this specification is to per=it the licensee the flenibili-ty of operation to assare that the

-o-

'n.v2. a'G C'vT.D"u ". "as~

Tr o.. O or. m* ". "u"a 2.0 "n. 'P.."O.Q ".. u" c. e" Un. r"a'. o~

T.

m.

a 2.0 public is provided a dependable source of power under unusual c n..a 4 4 -.a,,,u. 4 u-

,.]

n.,..4.,

,..-..~e tenperarily result in releases higher th:n the levels normally d

achievable when the statien an.

the liquid radvaste equipment are functioning as designed.

F.eleases of up to 10 cri'es per radicactive vaste-producing reactor dring any calendar quarter vill result in concentraticns of radicactive raterials in liquid effluents at s-=

percentages of the 1*

'ts specified in 10 CFR 20.

c.,..,,,,4..,. s +. w_a..w.e y.. 4,_4 c. 4 -.,

e.

.~

licensee sha

-=4 ain and cperate

_4,s, t.,4. d e,r,. 4.._..,.. 4

+. a.,,, a

4.,,.

o.

+w

.,. w.

. adicactive vaste syste to reduce tne release of radioactive naterials in liquid effluents to as icv as practicable, censistent with the requirements of 10 C73 50.

2c a.

Ncr:al use and naintenance of installed equipment in the liquid radicactive system is expected to result in releases of not nore than about five cu'-ies per radicactive

..g2+,_-,.~a..4 s-. a-,.,e

/,...,

- ~.,

excluding tritiu: and dissolved gases du-ing nc'nal cperatices. In order to keep releases c' -ad'cactive materials as Icv as practicable, the specificatica requires, as a ninimut, operation of eqriprent whenever the rate of -elease exceeds 1.25 cries per radicactive vaste-prcducinS reactor per quarter, excluding tritiu and dissolved gases.

In addition to the liniting ccnditions for operatica listed under Specificatien

b., the reporting requirements of Specificaticn e., the requirenants cf Sectic: 5.6.2, delineate that the licensee shall identiff the cause whenever the rate of radicactive effluents, excluding tritiu: and ncble gases, exceeds 2.5 cries per radioactive vaste-prcducing reacter during a.y calen.ar qua-ter and na 4 -.

d describe the propcsed prcgra: of C0 j /O action to reduce such release rate.

Sis report =ust be filed within 20 days felleving L

.-mo_~~=

~

~

~

2.0 LIMITING CONDITIONS FOR OPEitATION 2.0 MONITORING REQUIRD13TS Bases (Cont'dl

. the calendar quarter in which the 2 ^1 2.5 curies release occurred.

• 2.3.2 Caseous Effluents Aonlicability Applies to the controlled release of radicactive gases fron TMI Unit Nos. 1 and 2.

Objective Objective To define the li=its and conditions To ensure that radioactive gaseous releasec fre= the facility are for the controlled release of radioactive gaseous effluents to the within the limits of specificacicas.

environs to ensure that th ese releases are as low as practicable.

These releases sheuld not result in radiation exposures in offsite areas greater than a few percent of background exposures. The instantanecus release rate for all effluent discharges should be within the linics specified in 10CFR 20.

To assure that the releases of radio-active gases to offsite areas neet the ca low as practicable concept, the folleving objectives apply-a.

The relecse rate of radionuclides, 2,-

averaged over a yearly interval, ex-cept I-131 and particulate nuclides with half lives greater than 8 days, discharged frem Unit Nos. I and 2, should result in a dese rate at the site boundary of less than 10 =re=/yr to the whole-body or any organ.

b.

The release rate of I-131 and other particulate radionuclides with half-lives longer than 8 days, should result in a dose in the unrestricted area of less than 15 nre=/yr by inhalatien or to the thyroid of a child through the cow-UO l 7 7, milk chain, gn 4

_,. )

2.0 LIMITI?;G CONDITIONS FOR OPERATION 2.0 MONITORING REQUIREFE';TS Specification Specificati3g a.

The instantaneous release rate of grcss During release of radioactive gasecus gasecus activity except for halegens and wastes, the following conditions shall particulates.with half-lives longer than be cet:

eight days 3

' A.

During release of gasecus vaste I(Qi 5m

- l.2 x 10 MFC)1 sec fren the waste gas decay tanks, the follcwing conditions shall be =et:

where Qi is the release rate in 1.

Waste gas dischar'e conitor pCi/see for isetcpe 1, and MFCi (Unit 1: RM-A7; Unit UD G-R-1480)

(pCi/m ) is the =2ximun per=is-or si=ilar device, sha 1 be operable.

3 sible conce:tration of isotope i and defined in Appendix 3, 2.

Auxiliary and Fuel Handling Table II, Col=== 1, 10CFR 20.

Building and Unit Exhaust Vent exhaust gas, iodine and particulate conitor b.

The instantaneous release (Unit 1: RM-A8; Unit 2: WDG-R-219) or rate of I-131 and particulates s1=114r device, shall be operable, with half-lives greater than eight days, released to the en-3.

The waste gas decay tank discharge virens as part of airborne ef-valves (Unit 1: UDG-V47; Unit 2: WDG-fluents, shal1~not exceed 0.63 V-30A or 303) shall be cperable.

pCi/sec.

4.

The waste gas decay tank discharge c.

The release rate of gress gase-valves (Unit 1: WDG-V47; Unit 1: UDG-cus activity shall not exceed:

V-30A or 30B) shall be closed on re-ceipt of any one of the following conditicus:

4 3

~ ~

7(Qi

< 1.9 x 10 m

a high radiation signal frem the MFC)1 --

see a.

vaste gas discharge conitor (Unit 1:

RM-A7; Unit 2: WDG-R-1480).

when averaged over any calendar guarter.

b.

a high radiation signal frc= the Auxiliary and Fuel Building exhaust d.

Ihe release rate of I-131 and nonitor (Unit 1: RM-A3; Unit 2: HP-particulates with half-lives R-219).

greater than 8 days, shall not 0.05 pC /sec., when aver-c.

a high ficw signal from the Waste exceed:

i aged over any calendar quarter.

Cas Decay Tank discharge flew trans-nitter (Unit 1: FT-123; Unit 2: WDG-e.

Radioactive gaseous wastes

.FT-3923.

collected in the gas decay tanks shall be held up to a nini=us of 45 days, except when the release 3.

During purge o f the Reacter Buil-rate shall not e.tceed:

ding, the folicwing conditicas shall be met:

1.

91

_2.4 x 10 3 3 1.

The Reacter Building Purge Exhaust m

y 7ec lbnitor (Unit 1: RM-A9 ; Unit 2: 'd? - R-

-EPCi 225 and/or HP-R-226 and RP-R-219) or Inoble gases) si=ilar device,shall be operable.

OC ll0 and

. 2.0 LDC"'"TG CCFDITIC::S yCR OPUX'ICH 2.0 "C'!I'URI !O RE;UIRE"E'I"'S Seecifieaticn (Cent ' d) 2.

"he Purge Exhaust Valves (Unit 1.

AE-VIA and AE-VI3 and Da=pers; u i/sec (icdine 131 and Unit 2: D5129 A/D and 05129 3/C) 2.

0.012 C

parciculates shall be Operable.

vith half-lives greater than 8 3

The valves (Unit 1: AE-VIA and days)

AE-V 3 and Dampers; Unit 2: D5129 A/:

and D5129 3/C) shall be interlocked f.

Radicactive gas and particulates to close or recirculate, respectively purgea frc= the reactor building shall en receipt of a high radiatien signal be filtered through the high ef#iciency frc= the Reactor Building Exhast pa" -"'ee air filters and charcoal Menitor (Unit 1: Fl&9; Unit 2: HP-a-absorbers.

225 and EF-a-226) respectively.

g.

Se maai:iu: activity to be cen-c.

The ficv re.te for radicactive tained in ene gas decay tank shall not effluent stres:s and the Auxilliary exceed ccCO curies (equivalent to Xe-and Fuel Handling Suilding and the 133).

Reacter Building, shall be =enitored and recorded. Gasecus effluents h.

When the annual release rate of frc= the Waste Gas recay Tanks and radioactive raterials in gaseous the Reactor Building Purge Exhaust vastes, averaged over a calendar shall be continuously =onitored and quarter excee:is, re :orde d.

d.

Radicactive gasecus vaste samplin; Qi h.8 x 103 3

E and activity analysis shall be per-2 for=ed in accordance with Table 2.3-2.

(MPC)i.

see e.

The vaste gas decay tank effluent (noble 6ases)

=cnitor (Unit 1: PN-A7; Unit 2: WDG-E-1kdo) shall be tested using the C '*

installed check source or equivalent 0.024 uC /sec (.icdine 131 and prior to any release of radicactive t

particulates gas frc= a holdup tank and shall be vith balf-lives calibrated quarterly using a re-greater than 8 ferenced calibration source in a days) centrolled reproducible gec=etry.

f.

During power operation, the cc: -

the licensee shall notify the YRC vithin 30 days, identi^ ring the densor vacuu= pu=p discharge shall be causes and describing the proposed centinucusly =enitored for gress progra= cf actica to reduce such gaseous activity. The accitor shall release rates.

not be inoperable for = ore than a Week.

Whenever this =cnitor is in-cperable, a grab sa=ple shall be taken daily and analyced for gross radic activity. (3,y).

g.

Facility records sha'.1 be rain-tained of radicactive ccncentration, release racic and volu=e of each batch of gasecus effluents released and the leng'.h of tire over which release cccu' red.

n i ~/ O O

\\ii

.. 2. 0' LI?CTEIG C0'IDITIONS K R OPERATION 2.0 m'!!TRING REOUIRD'E':TS Srecification ICont ' d) h.

At least annually, autc atic initiation and closure of the Waste Gas recay Tank Discharge valve en alar = of (Unit 1: F31-AT and RM-A3; Unit 2: WEG-R-lkc0) c:all be verifiel 1.

The Auxilirry and Fuel Handling Suilding and R. 3. Purge Exhaust gen

=cnitors (Unit 1: F31-A3 and F3!-A9 ;

Unit 2: EF-R-219, EF-R-225, and EP-R-226), nspectively, shall be cali-brated at least quarterly by =eans cf a kncvn radicactive scurce. These detectors shall have an instru=ent Bases channel test at least menthly, and a senscr check at least daily, to The specified levels provide rea-veriP/ that the read-cuc device is senable assurance that the resulting indicating as expected annual exposure rate fren ncble gases at any 1ccation at the site Bas es bounda:/ vill nct exceed 10

1. ' ' d --=s per year. At the same time, Specificatiens a. thrcugh 1. abov3, these specificaticas per=it the require that suitable equipment to flexibility of operation, ec=patible

nnitor the radicactive gaseous with consideratien of health and releases are operating during any safety, to assure that the public is period these releases a e taking provided a dependable source of pcVer place.

unusual cperating conditions, which =ay te porarily result in higher than The surveillance requirements given nor al releases, but still within the under the rem'ning Specifications ccncentration limits specified 10Cy2 20.

above, provide assurance that It is expected that using this operaticnal radioactive gaseous effluents frcs flexibility under unusual operating the station are prcperly centrolled conditiens, and by exerting eve:/ effort and =cnitored ever the life of the to keep levels of radicactive =aterisi statien. These surveillance in gasecus vastes as icv as practicable,

requirements provide the data for the the annual releases vill not exceed a licensee and the Cen issicn to s=rli fractica of the annual mrt-evaluate the statien's perfor=ance centration li=its specified in 10CFR 20.

relative to radioactive gasecus These efforts should include consideratica vastes released to the envircr ent.

of =eteorological conditiens during releases.

The annual objectives have been developed taking into account a cerbinatica of systen variables on 1 n GO 10(

1 i

-u-

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"ABLE 2. 3-2 RADICACTIVE GASECUS '4ASTI SA'GII:iG A'ID A'iALYSIS (5)

Sa=nle ?rne Sa= cline Fracuenev

?f*e of Activity An alys is retectable Ccncentration (1 A.

~41ste Gas recav Tsr.k Felease Gas Zach Tank H-3 10-pCi/cc Release Individual G=-a Initters 10- uCi/cc(2) 3.

Peactor Buildine Purre Peleases Gas Zach Purge H1

'0-pCi/cc Individual Ga==a I=itters 10 pCi/cc(2)

C.

Condenser Vacu= Fro Feleases Gas Ltnthly E-3 10- pC1/ec Stn hly(3)

Individual on-, E=itters 10-uCi/ce(2)

D.

Au:cillia: r and Fuel Handling Building Exhaust Vent, Peactor Euilding P=ge Vent a.nd Ur.1t Exhausttc)

Vent Felense Fcints 4 pCi/cc Gas

!buthly E-3 10 pCi/ce(2)

• ndi ridual Ga-a I=itt ers 10 Charec al

~4eekly(h)

I-131, I-133, I-135 10-12 pcife Particulates

'4eekly Individual Ga-n E=itt ers 10-10 Ci/ce(2) 3tnthly Cc=pesite Sr-89, Sr-90 10 " Ci/cc Stnthly Cc=pesite Grcss c 10-11 pCi/cc (1) The above detectability 14 4ts are based en technical feasibility and en the potential significance in the environment of the quantities released.

For sc=e nuclides,1cuer detecticn limits may be readily achievable and when nuclides are reasured belev the stated limits, they should also be reported.

(2) For certain nixtures of g"

' eritters, it may not be pcssible to reasu e radienuclides at levels near their sensitivity limits veen ether nuclides are present in the sa=ple et nuch higher levels. thder these cire= stances, it vill be care apprcpriate to calculate the levels of.euch radienuclides using cbserved ratics in the gasecus cccpenent in the reactor ecolant for those radienuclides which are ressurable.

(3) Analysis shall also be perfor:ed felleving each refueling period, start-up cr s

e-4 cperaticnal cec =rence which eculd alter the =ixture of radienuclides.

r.

4 p (9 i

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. TABLF 2.3-2 (Cont'd)

's)

Sanpled during periods '. ten no vaste gas decay tank release or reactor building purge is in progress.

5)

Deviations fron the sanpling and analysis regine vill be noted in the report specified in 5.6.1.

(6) The Auxilie.:/ and Fuel Handling Builiing Exhaust Vent and Reactor Eui.lding Purge Vent pertain to Unit 1 ("C-1), while the unit exhsust vent pertains to Unit 2 (T'C-2).

t P#1 4 O ')

00 IOm

2.0 LIMITING CONDITIONS FOR OPERATICN 2.0 MONITORING REQUIRE EITS Bases (Cont'd) including fuel failures, pri=ary system leakage, pri=ary to secondary systen Icakage, and the performance of radienuclide re= oval cechanis=s.

Specificatien a. above, requires the licensee to li=it the con-centratien of noble gases fro the station to levels specified in 10 CFR 20, Appendix 3, for unrestric-ted areas.

Based on a X/Q of S x 10-6 sec/=3, this specificatica provides assurance that no me=ber of the general public veuld be exposed to radioactive caterials in excess of linits specified in the Co=nission's rules and regu-lations'.

Specification b. abcve, requires the licensee to 11=1: the concen-tratien of I-131 and particulates with half-lives greater than eight days, released from the station to 1/233 of the levels of 10 CTR 20, Appandix 3 for unrestricted areas.

This reductica facter of 233, and a grazing period of 5 cenths have been arb4trarily applied to radio-nuclides of iodine and to all radionuclides in particulate fer=

with a half-life greater than eight days, to allev for the milk expcsure pathway. The release rate is de-ter=ined by:

3 Qi (z)(700)

< 0 (m )

g (MFC)

(3)

X (sec)

I-131 where Qi and ITC are defined in

a. above. The X/Q of 8.3 x 10-7 sec/m3 is derived from the anoual average reteorological data where the nearest cov granes 1-b miles ESE. The g value accounts for the fraction of tine that the cow grares in the pasture, i.e., 5 months per year.

Specificatien c. above, establishes an upper limit for the release of

{l p-5 IO" gaseous activity at 16 percent of. instantaneous release li=1t of

-1L_

2.0 LI CTI'IG CC:TDI"'IC:!S FCR CpEPATIC:I 2.0

'4C:II?3RI'IG REOUIFj0!E's"'S noble gases and 3 percent of the release rate cf I-131 and particu-lates with half-lives greater than 8 days, averaged over any calendar quart e r.

Tae intent of this speci-fication is to pe 4'

+ka 14 cens et.

the flexibility of cperation to assure that the public is_ provided a dependable source of pcve-

"~3a-unusual cperating ccnditiccs.

Specification e. above, requires a h5 d y holdup ti=e for radicactive gasecus vastes collected in the gas decay tanks to assure decay of

=cs: ra *--"-14'as.

The deses (ma# 'y d

frc Kr-SS) at the site boundary after h5 days of he?. dup is expected c result in less than 10 =re /yr.

Specificatica f. abcve,

'd

'ts the radicactivity that may be released to the envirennent to "as lev as practi cable. "

Specification g. above, limits the ca.xir';: offsite dcse to well below the li=its of 10 CFR 100, postulating that the rupture of a '4aste Gas recay Tank hciding the -* un activity releases all of the contents to the atncsphere.

In addition to 'ba ' d d +'ng ccnditions for cperation listed under a, b, and c love, the reperting requirenents of Specificaticn h. lelineate that the licensee shall identify the cause whenever the radicactive gaseous release rate exceeds k percent of Specificatien a. cr 2 percent of Specification b. above, e.veraged over a calendar quarter, and d escribe the prcpesed progras of actton to reduce such release rate.

"'he repcrt must be filed within 20 days f alleving the calendar quarter in which =cre than twice the design release rate occu red.

er.: m..a-wa

.~

i' (1) Peteoro.'.6i and Ate-ic Energy, pp. 20k i

on 4 n (2) Petecrolog7 and Atcmic Energy, pp.112

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