ML20153G143

Effluent & Offsite Dose Rept,Jan-June 1988

ML20153G143
Person / Time
Site:	Three Mile Island
Issue date:	06/30/1988
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20153G141	List: ML20153G137 ML20153G143 ML20154C719
References
NUDOCS 8809080051
Download: ML20153G143 (11)

Text

--

EXECUTIVE

SUMMARY

Three Mile Island Nuclear Station Unit 1

. Effluent and Offsite Dose Report for the Period of January 1,1988 to June 30, 1988 This report sumarizes the radioactive liquid and gaseous releases (effluents) from Three Mile Island Unit 1 and the calculated maximum hypothetical radiation exposure to the public resulting from these releases. This report covers the period of operation from January 1 to June 30, 1988.

Radiological releases from the plant are monitored by installed plant monitors sampling the plant stack for gaseous releases and liquid monitors for discharges to the Susquehanna River. These monitors and sample analyses provide a means for accurate determination of the type and quantities of radioactive materials being released to the environment.

Calculations of the maximum hypothetical dase to an individual and the total population around Three Mile Island due to radioactive releases from the plant are made utilizing environmental conditions that existed at the time of the release. Susquehanna River flow data are used to calculate the maximum hypothetical doses to an individual and the population dawnstream of TMI due to liquid releases. Actual or "real-time" meteorological data from an onsite

• tower is used to detemine the doses resulting from gaseous releases from the plant. The use of real-time meteorological infomation permits the determination of both the direction in which the release traveled and the dispersion of radioactive material in the environment.

Utilizing gaseous effluent data and real-time meteorology the maximum hypothetical dose to any individual and to the total population within 50 miles of the plant is calculated. Similarly, Susquehanna River flow and liquid affluent data are used to calculate a maximum hypothetical dose to an individual and a population dose from liquid effluents for any shoreline exposure down to the Chesapeake Bay. Exposure to the public from consumption of water and fish withdrawn from the Susquehanna River downstream of the plant is also calculated. ,

Oose calculations for liquid and gaseous effluents are performed using a mathematical model which is based on the methods defined by the U. S. Nuclear Regulatory Commission.

The maximum hypothetical doses are conservative overestimates of the actual offsite doses which are likely to occur. For example, the dose does not take into consideration the removal of radioactive material from the river water by precipitation of insoluble salts, absorption onto river sediment, biological removal, or removal during processing by water companies prior to distribution and consumption.

8009000051 000329 PDR R

ADOCK 050 g9

Liquid discharges made during the reporting period January 1 to June 30, 1988 consisted of 211 curies of tritium, 0.060. curies of noble gases (predominantly Xe-133), and 0.012 curies of other beta and gamma emitters, predominantly l Co-58. The quantities of effluents are similar to average semiannual releases from previous Unit 1 operations.

During the reporting period January 1 to June 30, 1988, the maximum hypothetical calculated whole body dose to an individual due to itquid effluents from Three Mile Island Unit 1 was 0.052 mrem. The maximum i hypothetical calculated dose to any organ of an individual was 0.075 mrem to the liver. 1 Airborne discharges made during this same time period consisted of 4.2 curies of tritium, 927 curies of noble gases, and 0.00031 curies of iodines and no ,

particulates. These releases are less than average semiannual releases from previous Unit 1 operation.

The maximum hypothetical calculated dose to any individual from noble gases was 0.047 mrem to the skin and 0.017 mrem to the whole body. Airborne iodine is calculated to produce 0.034 mrom to the thyroid of the maximum hypothetical '

individual .

The total maximum hypothetical whole body dose of 0.069 mrom, received by any individual from effluents from the TMI-1 for the reporting period is 720 timet lower than the doses the average individual in the area of TMI-1 receives from natural background during the same time period. Natural background averages e about 50 mrom whole body semiannually in the TMI-1 area. In addition, average equivalent dose to the lung from natural radon for the same period is about 50 mrom per quarter. The calculated total whola body population dose from all plant releases is 1.5 person-rem. Tnis is 73000 times lower than the 6ose attributed to natural background radiation for the reporting period. The doses which could be received by the mcximum hypothetical individual are each ,

less than 25 of the annual limits established by the Nuclear Regulatory  :

Commission in Appendix ! of 10 CFR 50. '

i h

IFRtJEXT & WAflE IISP0JAL SEMIAMMUAL KPORT'

[, IUPftEENTALINFORMT10N FACILITY: TM1 IM!i i LICENIE: DFt 56-289

1. KGULATORY LIMIT! - - - REFER TO IMI UNIT 1 TECHNICAL INCIFICATION!

A 4 AtilVATION GASEf:

g. l ,

h: IW! tdMk ,

2. . MXIMUM FDMl!!!KE CONCENTRAi!0NI - - - 10 CFR 29, APPEDIX B TARE !!

ggigggK MIERMINIK All0 WARE RELEAIE

. ggMD Aci!VATION GAE!:

asww-" -

3. AVERAGE EE RGY RkbAkhWh! A ki AT b F APftlCARE i E4AR SETA = 2.05E41 E4AR GAMM = 2.99E41 E4AR KTA MD GAMM = 4.05E-61

4. MAIUREENT! MD APPt0XIMAT10N! 0F TOTAL RADIDACTIVITY 4

$\blYhbENES Sho FEM Nh RblNEYChkf i: WM ""c"'a"* '" E MME "" '*"a*""

C.PARilCULATE!

HPGE JPECT g TRY g g ft0 PORI!0M L, D. LIWID EIFLluff: HPGE SMCTROMETRT, LIWID SCINTILLATION

5. BATCH RELEAIES I hi kkhYbk) OU1 MMiP

• A.LIWID WARTER i ! WARTER 2

h. f0 AL ifME 0 CH RELEAIES: (MIN.1 21 4. 12b 1:23""i!!!81isi&P"BiP in:) 'q*:!g.  :

1:MMAMslaA%Effiti"#

0F EffLtDi IMiG A FLOWING JiKM (CFM) 2.47t+66 ! l.98E+44 8.GAIE0V!

b'. WifM 0  : (M':N.) 74 . 5 844.

. YIka i M !hs BANkCHRELEA!E[h3 REfhAi N'.

5. MINIMUM i .hE f9100 FOR A PATCH KLEAIE: (M N.)

22'.

6.  !

8.

5.

4. AMORML ELEAft!

1 hmm -,, m;a

..w . .

table 14 h5Y $ hl k N f i....._

1 I e i )

i i QUARTER 1! QUARTER 2iEITTOTE!

l UNIT

!  ! !ER*0R,I l I

A. Fl!!!0N AND ACilVATION GA!El *

,i . . . _ . . _ . . .

!!.T07'1RELEATE  ! CI ! 3.78E+42 ! 5.4 K+62 ! 2.54E+61 ! -

i - .. . . .. . -

.i 32 AVG RELEAIE RATE' /' ' '

3 (R KRIOD i

!UCI/!!4.85E+41 !6.98E+91 ii

!3.KRCENTOFTECH !  !  !  ! s

! IPECIFICA110N LIMIT! !  ! #  ! * '

I IODINE!

i 1931  ! Cl ! .....

5.39E-M ! 1.99E 94 !2.50E+0i !

i . .. .- _ ... _

!2. AVG RELEA!E RATE!  !

' FOR KRIN i

!UC!/3!4.93E-07 i 2.5X-95 *i i3 HKENT OF TECH '  !  !

I 3  ! h CIFICATION LINIT) %  ! e  ! e  !

r C. PARTICIA. ATE!

i .. ... ..... . ....... ..... i

' 8 8 I i11. PART. E.....  !

1.. LIVE! ) 8 DAYSTH HALF ! Cl ! U.99E44 ! (1.60E-64 ! 2.5E+61 !

!2. AVG. E LEAJE RATE!  !  !  !

' FOR KR100 !UCI/!! NA  ! NA '

i i

!3. KRCENT OF TECH ' ' ' i

' IM ClflCAi! W LIMIT! %  ! NA  ! NA i i

.... .. )

i... N M M ITiCii<i.E.iii<i.00E.ii i!

D. IRiflVN e.. = . .. . . _ . . . .

31. TOT E KLEAIE I

! CI ! 3.34E+6) ! 8.87E-61 ! 2.56E+41 !i 32 Ayc KLEAIE RATE' ' '

4 i(ORfiR10Di . ...!UC1/!  ! 4.33E-61

' .13E-ti !

11 ,

!3 K RCENT OF TECH !  !  !  !

' lH CiflCAll W LIMii! !  ! e  ! e

! 'l NOTE: ALL LEJJ THAN VALUE! (O ARE IN UCtht..

elTECW.INC.LIMlif: LlfiED ON 00!E !UMMARY TA KE.

I f

e \

TAILEIC U!EsW M M E E M " .

CONTINU0VJM0K BATCHN00E

i. . . _ - _ . . . .i i i i i i e I i NUCt!KJRELEATED i UNITIQUARTERi i QUARTER 2IQUARTER1 i QUARTER 2 i i

. .i e

. .i e i

i

..)

1.Fl!!! GIGA!El >

s _ .._ .. . ..

I , KR 85  ! l! ! (8.ME-96 ! (8.ME46 ! 5.32E+M ' 3.92E+96 -1 8 l

i KR 85M i ..  ! CI ! 1.18E44 ! (5.6K48

..... . .  ! 2.83E42 ! 4.69E41 !.

I  ! C! ! (8.00E-08  ! (8.99E48 ! (8.99E48  ! (8.9E-98 i) i.. ..KR ._ ..87 ... .. . ...... .. . . _ .

i i _ KR 88 ...  ! Cl ! (l.ME47 ! (1.66E47 ! (1.99E-97 ! 7.5E42.!.

i XE133  ! C1 ! 4,38E+M ' i.55E41 ! 3.54E42 ! 5.00EH2 i l i i Xi135  ! CI ! 5.24E42 ! 5.99E42 ! 4.87E+M ! 1.13E41 ii i

! XE135M  ! C1 ! 6.7E !. (5.00E47 ! (5.4K47

. , -__..i

! (5.0M-67 !

i XE 138  !

i . . _ . Ci ! (3.90E47 ! (3.ME47 ! (3.6E47 ! (3.ME47 !.

XE 1331  ! C1 ! (2.0E47 ! (2.ME-97  ! 1.24E+M ! 3.91E+M  !

.! .- - . . . _ . . _ _ . ... _ i i XE131M  ! CI ! (3.ME 97 !......

(3.ME 97. ! 3.6tE+M ! 3.ME+M-ii i AR 41

! CI ! (3.ME-67 ! (3.6K-67 ! 2.34E-01

._ . _ .. _!.2.15E+M l .

i .... ..... . . .. . ... . _ . ..... ..... _ .. . i i TOTAL FOR FfRIOD ! CI ! 4.43EH9! 1.54E+61 ! 3.71E H 2 ! 5.33E42i 3

2.10 DINES i....... ......... ... . .. .... .. ........ ... ....... ..

3

! CI ! ..............

5.38E-64 ! 7.98E-07  ! (1.0M48 ! 1.99E-64 I l

l ... 1 131 .... ....... ....... ........ ... .. . .i i

'ii.  ! 132  ! Cl ! (l.ME 10 ! (1.0E-10 ! (l.ME48 ! 3.31E46 ii i

i i

1 133  ! CI ! 2.2E44 ! 1.67E47 ! 5.55E-47 ! 8.99E45 ii i  !  ! 135  ! CI ! (1.9K 18 ! (1.MC-16  ! (1.ME-10 ! 1.61E45 i

........ .. . ...... .i t . ..... .. .... .... . . . .. . .

l i TOTAL FOR PERIOD ! C! ! 7.41E46 ! 9.65E-07 ! 5.55E47 ! 3.02E-44 i i  !

3. PARI!CULATEf I

i _ . . - . . . ........ . . _ . . ..

I SR 89  ! Cl ! (1.69E-li. !...(1.09E ..11. ! (1.6M48 !.(1.0E-M .

i. . .. . _ .. .

3  ! CI ! (1.0E 11 ! (i.NE il ! (1,90E-M ! (1.0M-98 !

i i .. IR 96 . ... ... ... ._ .... . . ..

I

! C3134  ! C1 ! (1.6M-il ! (1.ME-fl ! (1.6M-08 ! (1.6K-M i1 i

i l

! CJ 137  ! ..C1  ! (1.tM 11_...  ! (1.0M_-li .-! (l .ME_M ! (1.9K-M....I i  ! CI ! (1.6K il ! (1.ME-il ! (i.tM48 ! (1.0K48 !i l i_ BA le . .. ....... _ . ... .... .... .

! i LA 1H  ! CI ! (1.6K il ! (1.ME-ll ! (1.9M46 ! (1.6E49 !i i i r

( NOTE: ALL LEff THAN WLUES (0 ARE IN UCI/1.

l.

+.

TAKE2A f@ bb bN e _ . . . _ . .

, r i i e n

! UNIT! QUARTER 1 3 QUARTER 21E!TTOTAL i

!  !  ! ERROR, I l

_.._. .. ._ . l A. Fl!!!0N MD ACTIVAi!0N PRODUCif i.. _ . _ .. _ . . .. ..

! I

!1.TOTALRELEAJE(EX.!  !  !

' ' TRIT.,GAIEf, ALPHA)! Cl ! 9.73E-43 ! 2.47E-63 ' 2.56E+61 1 -

I .m .

i .D h b l. _ . _ .!UCl/' .:E ! 7.35E-10 i

! l.73E _10 !

!3.MACEWTOF  !

• APPLICAKELid!T l!  ! a i n i i

, . . . . - .._. . .. . .i I4 TRIT!y4

i. _..= . _ . . . . . .

Cl ! 1.7tEt02! 4.13D 61 ! 2.50E+61  !

11.TOTALRELEA!EI ... ..! ___ .i '

!2. AVG.SILUTD  !  !  !  !

' CONC. DURin PRt. !UCI/E! 1.28E-65!

i i ' 8 2.8K-N)' .,

33 PERCENT OF  !

3 AffilCAKE LIMIT !! ! *  ! s '

.i I.

C. DI!!0LVD 20 ENTRAINED GAIEI

i. . .. .. ... .. .. ,

! Cl ! 3.95E-62 ' 2.68E-62  ! 2.54E+el 1 11.TOTALRELEAIEl _ .... _ . . . . . ...

32 AVG. SILUTED  !

! b C. 00Rin PR). !UC1/E ! 2.98E-99 ! 1.45E-69  !.

i _ .. _ . .. . .....

!3.KRCENTOF  !  !  !  !

!APPLICAKELIMIT  !!  ! *  ! n '

9. GR0ff ALFhA RADIDACilVITT 1

i. .. .. . ..... .......... .. .... . .. ....i

- I  ! Cl ! (l. ME-61 ! (l. ME-67 ! 2.5&E+61 I

!.I.10TR RELEAIE i .. .... ... . .. .._.... . . .

i.. . .

' ' i I i.E YOL O  !

'MLEASEh(FiMJTEi... _....N0 O!L.) ! LITER!I 1.21D67 I' 1.35E+07 ! 1

!T. Y0L. OF DILUTION.'  ! ' ' 8

'W i

I.ATER

.... .. ...DURING

. M ....

... RIOD ......!...........

LITER!! 1.32016 ......!! 1.43E+19 l 1.MD61 I r

e i

l NOTE: RL LE!! THM VALUE! (() AE IN UCI/K.

l I et TECN. JMC. LIM!il: Ll!TD ON !CIE !LinMART TAKE.

I 1

l

9 TABLE 23 EFELVENT 4 0 liAITE g f g f REf1)R7 (1968) '

CONTINV0V! M0K s DATCH M0K i.- . . . - _ . .. a i a e i s. e i i -

i. WVCLIKJ RELEAIED , i  ! (MIT !, QUARTER i i !, QUARTER e. 2i ! QUMTER I ! 9VMTER 2 ! c

..I

i. _. _. . _ . . . . . . - -

i  ! C1  ! (5.06E46  ! (5.66E-66  ! 6.49E46  ! 1.34E-66! -

i . IR 89 .. ._ - . . _ . . . . .

3 i

3R 96  ! C1 ! ..(5.66E48 ! (5.4K48 .

! 3.54E-96!(5.66E-H ....... .... i i

i  !

C!134  ! C1 ! (5.HE47 ! 1.94E44 ! 7.42E44

! 1.5M44 !

i . Cf 137 .

! Cl ! (5.HE-67 ! 7.5E44 ! .2.02E43 ! 5.64E44 !i-i

' i  ! C1  ! (1.66E46 ! (i.HE46 ! 3.92E-64 ! 2.69E-64 !

i . I 131 _. . .. . . ..i i  ! Cl !.(5.HE-67  ! (5.4M47  ! 4.62E43 ! 5.3tE44..II i _ ..CO .. 58 . .. ._.. . _ . . .

i  ! Cl. !_ .(5.HE47  ! (5.6K-47 ! 2.87E44 _! 8.5 E46 i

i. _ .C0 64 .. ....- _. . .. ... ..I

! FE 59 s._................._.i  ! Cl ! (5.66E-67 ! (5.4K47 ! (5.HE-67 ! (5.6K47 i i ZN 65

! Cl ! (5.HE47 ! (5.HE-67 ...:

! (5.6K47 ! (5.NE-67 !

..........._i l

! MN 54  ! C1  ! (5.66E47 ! (5.6E-67  ! 1.42E46  ! (5.66E-67 iI s . ..- .~ .. _ . . .. .. .... . ... r i CR 51  ! C1 ! (5.4E47  ! (5.6K-47 ! (5.6E-67 ! (5.66E-67  !.

, i =- . . .. . .. . .. ..... . ,

j  !

ZR 95  ! CI ! (5.46E47 ! (5.NE47. ! (5.66E-47 ! (5.66E47..i ,

1 . . . . . . . . _ . . . . . _ _ . - - z.

NB 95

! Cl.___! _(5.NE47 ! (5.HE-67

! 9.13E46 ... ...

! (5.HC_-47 __.i !

i MO 99

! CI ! (5.HE47 ! (5.HE-67 ! (5.AE47

! (5.4E47

!e

!, _ _TC _..

99M  ! Cl ! (5.HE47 ! (5.HE47

! (5.NE-67 ! (5.NE47 I  !

i ..

IA146

! C1 ! (5.6M-67 =

! (5.NE-47 ! (5.NE47 ..! (5.4M-67

! I

, i  ! CI ! (5.46E-67 ! (5.6E-67 ! (5.6M47 ! 4.NE46 i 1 .LA 144

.............._._i ,

i CE141  ! Cl ! (5.NE47 ! (5.NE47 ! (5.6W-67 ! (5.NE47 ii I .

t i FE 55  ! Cl ! (i.NE46 ! (1.NE46 ! 6.39E44 ! 1.65E44 ii  !

i i

AG116M

! CI  ! (5.NE47 ! (5.6K47 ! 9.39E44 ! t.73E45..Ii I

! Cl ! (5.6E47 ! (5.NE47 ! 6.6K45 ! (5.6K-47 !

!......Cf134.... . ... ..... . ._

i .

+

i.. ...... .............. _ ... . . _ .

l  !. TOTAL FCR KR!0D ! C! !..6.6M+H

! 9.44E44 ! 9.73E43 ! l.53E43 !

j i. ... ............. _ . ...... ... ...... .. ........... .i i i XE1331 -  ! Cl ! (1.HE44 ! (1.HE44 ! 1.29E44 ! 2.72E44 ii

,i i i

n XE 133  ! C1 ! .... (1.66E44

! (1.6M44 ! 3.9K42 ........! ..... 1.99E -62 ..!

{'

XI135  ! C1 ! (1.6M44 ! (1.HE44 ! 8.67E45 ! 6.3K44

.. ... . . _ . ..... ... . _ i 3

t t

i f b l NOTE: ALL LE!! THAN VALUE! (() Akt IN UCl/ML.

I i

! I i

I a

I ,

y I

h

.a .

TMI-1 January 1, 1988 through June 30, 1988 TABLE 3A ETTLt*ENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED TUXL SHIP.'GNTS A. Solid waste shipped off-site for burial or disposal (not irradiated fuel)

1. Type of waste

4. spent resins, filter sltsges, UNIT f,a Nh ES g TAL evaporator bottoms. etc.

m' k4.005 m3 Ci .ot?2 ci. 5,,

b. Dry co=pressible vaste, contaminated m3 equipment. etc. c.4 N/A N/A

c. Irraciateo co:poneats, ccTerol m' rod s . e t c . Ci N/A N/A mi

d. Other (describe) Ci N/A N/A

2. Estimate of major nuclide  !

composition (by type of vaste)

a. ce5$ 33,53 %

Ce117 04.e09*

C813U 17.95 t Nib 3 7.397*

b.

y

c. q t

d.

t

_ 1

3. Solid Waste Disposition Nurber of Shipreents Mode of Transpor;ation Destination A)'7 Shirnents Tractor - Flatbed Ifanford-Richland, WA

5. Irradiated Tual Shipments (Disposition)

Number of Shipments Mode of Transportation Destination N/A

' Shipped as Follows:

6 Steel Liners 170 Ft.3 each 3 Steel Liners 178 Ft.3 each (Solidified with Cement)

~

All Shi; cents were Exclusive Use - LSA

l INTERPRETATION OF DOSE

SUMMARY

TABLE i The Dose Susenary Table presents the maximum hypothetical doses to an individual and the general population resulting from the release of gaseous 4

and liquid effluents from TMI-1 during the first half reporting period of 1988. l A. Liquid (Individual) '

The first two lines present the maximum hypothetical dose to an t

individual . Presented are the whole body and critical organ doses. .

Calculations are perfonned on the four age groups and eight organs I

! reconsnended in Regulatory Guide 1.109. The pathways considered for TMI-1 are drinking water, irrigated cow milk, irrigated goat milk, irrigated beef, consumption of fish, and standing'on the shoreline influenced by TMI effluents. The latter two pathways are considered to be the primary recreational activities associated with the Susquehanna River in the i

l vicinity of TMI. The irrigation pathways apply to the sewage sludge.

The "receptor" would be that individual wno consumes water from the  !

l Susquehanna River and fish residing in the plant discharge, while  ;

occupying an area of shoreline influenced by the plant discharge and i consuming the milk and beef feit irrigated vegetation.

After calculating the doses to all age groups for all eight organs resultug form the three pathways described above, the Dose Sumary Table presents the maximum whole body doso and affected age group along with

• the organ and associated age group that received the largest dose.

For the first half of 1988 the calculated maximum whole body dose received by anyone would have been 0.052 mrom to an adult. Similarly, the maximum organ dose would have been 0.075 mrem to the liver of a teenager.

B. Gaseous (Individual)

There are seven major pathways considered in the dose calculations for gaseous effluents. These are: (1) plume, (2) inhalation, consumption of (3) cow milk, (4) goat milk, (5) vegetables, (6) meat, and (7) standing on contaminated ground. ,

Lines 3 and 4 present the maximum plume exposure at or beyond the site boundary. The notation of "air dose" is interpreted to rien that these doses are not to an individual, but are considered tc e ,.% 4ximum dose that would have occurred at oa beyond the site bounn 9 TP Dose Sumary Table presents the distance in meters to the loa tu in the affected sector (compass point) where the theoretical max .d plume exposure occurred. It should be noted that real-time meteorology was used in all dose calculations for gaseous effluents. Lines 5 and 6 present the dose which could actually be received by an individual frcm the noble gas effluents for the first half of 1988. The calculated maximum whole body dose received by anyone from noble gases would have been 0.017 mrem. Similarly, the maximura dose to the skin would have been 0.047 mrem.

, 1 The iodines and particulates section described in line 7 represents the maximum exposed organ due to iodine and particulates. This does not I include any whole body plume exposure which would be separated out by '

lines 5 and 6. The doses presented in this section again reflect the

, maximum exposed organ for the appropriate age group.

The first half 1988 iodines and particulates would have resulted in a maximum dose of 0.034 mrem to the thyroid of an infant residing 2700 meters from the Lite in the WSW sector. No other organ of any age group would have received a greater dose.

C. Liquid and , Gaseous (Population)

Lines 8 - 11 present the person-rem doses resulting from the liquid and gaseous effluents. These doses are sununed over all pathways and the affected populations. Liquid person-rem is based upon the population encompassed within the region from the TMI outfall extending down to the Chesapeake Bay. The person-rem for gaseous effluents are based upon the 1930 population and consider the population out to a distance of 50 miles '

around TMI. Population doses are sunened over all discances and sectors to give an aggregata dose.

Based upon the calculations perfonned for the first half of 1988, liquid effluents resulted in a whole body population dose of 1.3 person-rem. .

The maximum critical organ population dose to the thyroid was 1.4 person-rem. Gaseous effluents resulted in a whole body population dose of 0.17 person-rem. Maximum critical organ population dose to the skin was 0.56 person-rem.

l l

l 1

=_. . -

TABLE 1 UNIT 1 First Ha W 1988 Dose Report SLMJWtY OF M.XIRIM INDIVIDUAL DOSES COR U'.v'T 1 FROM J4nuary 1,1988 , thro;gh Jus: 30, 1988 l~ '~ l l Estimated I i Location l 1 of I Technical i l l Applicable i Dose l Age l Dist Dir l Applicable I Specificat19n l l Eff:.ent i Organ _ l (aren) l G.oup l (m) (toward) I Limit l Limits (area)  ?

I I i 1 1 I Quarterly I Annual I Quarterly l Annual l I I I I I I I I l l l(1)

• xid l Total 3ody 1 0.0!i' I Adult l Receptor l l 3.4 l 1.I i 1.5 1 3.0 1 1(?) LivH  ! Liver 1 0.f l Teen l Receptor 1 1 1.5 1 0.75 1 5.0 1 10.0 l I I I I I I I I I 1

1 I I I I I I I I I

'I3) Noble Gas l Air Dose 1 0.10 1 ---

l 395 N I 2.0 1 1.0 1 5.0 1 10.0 l l (gaena-arad) l l 1 l l 1 l l

(4) Neble Gas l Air nose 1 0.36 l ---

l 395 H l 3.0 l 1.5 l 10.0 1 20.0 l l l (beta-arad i I I I I I I I l(5) Noble Gas l Total Body 1 0.01; I All l 1000 N I ---

l 0.33 l ---

l ---

l l(6) Noble Gas l Skin 1 0.047 i All l 1000 N l ---

l 0.31 1 ---

l ---

1 I I I I I I I I I I I I I I I I l l l l

.l(7) Iodine & l Thyroid 1 0.034 l Infant i 2700 WSW l 0.46 1 0.23 1 7.5 l 15.0 l l P rticu~...tesl l l l  ! l l l l SIM ERY OF MAXImlM POPULATIGd DOSES FOR UNIT l FROM January 1,1988 through June 30,1988 Estimated Applicable Population Dose Effluent Organ (person-ren)

(8) Liquid Total Body 1.3 (9) Liquid Thyroid 1.4 (10) Gaseous Total Be@ 0.17 (11) Gaseous Skin ,

0.55