ML20059C885

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TMI-1 Effluent & Offsite Dose Rept for Jan-June 1990
ML20059C885
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 06/30/1990
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20059C883 List:
References
NUDOCS 9009050402
Download: ML20059C885 (12)
v • d • e


Text

i 1

, D:DCUTIVE SLMGRY Three Mile Islar; tauclear Statim Unit 1  ;

Effluent aM Off Site Dose Report I for the Period of January 1,1990 through June 30, 1990 ]

1 This report sumarizes the radioactive liquid a M gaseous releases l (effluents) frm Three Mile Island Unit 1 and the calculated navimm hypothetical radiation R & re to the public resulting frun these releases. This report covers the period of operation frun January 1 '

through June 30, 1990.

Radiological releases frm the plant are monitored by installed plant l radiation monitors which survey the plant stack for gaseous relaaaaa l and liquid dis &arges to the Susquehanna River for liquid releases. i These monitors ard associated sanple analyses provide a means to- '

accurately determine the type and quantitles of radioactive materials being released to the envirunment.

Calculations of the maxinum hypothetical dose to an irdividual and the ,

total population arouM Three Mile Island due to radioactive releases fran the plant are made utilizing environmental corditions existing at the time of the release. Sur:.quehanna River flow data are used to calculate the maxinum hypothetical doses to an irdividual and the {

population downstream of 7MI due to liquid releases. Actual vr "real-tine" meteorological data frun an onsite- tower is used to i determine the doses resultire from gaseous releases frun the plant.

7he use of real-time meteorological information permits the determination of both the direction in which the release traveled ard t 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 effluent data are used to calculate a maximum hypothetical dose to an individual and a population dose fran liquid effluents for any shoreline exposure down to the Chesapeake Bay. Exposure to the public frun consunption of water and fish withdrawn frun the Susquehanna River downstream of the plant is also calculated.

Dose calculations for liquid ard gaseous effluents are performed usirq a mathematical nodel which is based on the methods defined by the U.S.

Nuclear Regulatory Ctr1 mission.

The maximum hypothetical doses are conservative overestimates of the actual off site doses which are likely to occur. For exanple, the dose does not take into consideration the removal of radioactive material frun the river water by precipitation of insoluble salts, absorption onto river sediment, biological removal, or removal durirg processing by water car:panies prior to distribution and consumption.

9009050402 9006<29 PDR R ADOCK 05000289 PDC

i Liquid discharges made during the reporting period Jarwxy 1 thrtugh June 30, 1990 consisted of 57.8 curies of tritium, 0.00205 curies of noble gases, predeminately Kr-85, ard 0.0216 curies of other beta ard gama emitters, predominately C&S8. m e quantities of effluents are .

similar to average semiannual releases frun Unit 1 operations. 1 During the reporting period January 1 throgh June 30 of 1990, the i maxinn hypothetical calculated whole body dose to an individual due to l liquid effluents frun tree Mile Island Unit 1 was about 0.11 millirem. We wavh= hypothetical calculated dose to any organ of an individual was 0.15 millir m to the liver. i hirtorne discharges made during this same time pericd consisted of 10.16 curies of tritium, 661.31 curies of noble gascs, ard 0.00149 l curies of iodines ard particulates. These quantities of effluents are also similar to semiannual releases from previous Unit 1 operaticn, j since 1985 restart.

%e maxian hypothetical calculated dose to any irdividual from noble gases was 0.042 mram to the skin and 0.016 mrem to the W ole body.

Airtorne iodine and particulates are calculated to produos 0.003 mrun >

to the thyroid of the maximum hypothetical individual.

2e total maximum hypothetical whole body dose of 0.126 mrem, received by any individual frun effluents frun the tree Mile Island Nuclear Station Unit 1 during the reporting period is 400 times lower than the dose the average individual in the tree Mile Islard area receives frun natural background during the same time period. Natural backgrund averages about 50 millirem whole body semiannually in the t ree Mile Island area. In addition, the average equivalent dose to the total body frun natural radon is about 100 millirem.

%e calculated whole body population dose frun all plant releases is O.62 person-rem, his is 177,000 times lower than the dose attributed to natural background radiation for the reporting period. S e doses which could have been received by the maximum hypothetical individual are each less than 4.00 percent of the annual limits established by the Nuclear Regulatory Ccxamission in Apperdix I of 10 CFR 50.

1 i

1 i ,, ,  ;

'I' M. 'EFFLUENTE& WA8TE' DISPOSAL SEMIANNUAL REPORT l

,8UPPLEMENTAL INFORMATION .i FACILITY:~ TMIjUNIT 1 LICENSE DPR 50-289  !

,. c '1'. REGULATORY LIMIT 8t-' - --REFER TO'TMI UNIT 1 TECHNICAL SPECIFICATION 8 f A. FI8SION-AND ACTIVATION GA8ES

B. IODINE 8t:

C. PARTICULATE 8, HALF-LIVE 8 > 8 DAYSt p

D. LIQUID EFFLUENT 8 m 2.; MAXIMUM PERMIS8IBLE CONCENTRATION 82- - - 10'CFR 20, APPENDIX B TABLE II-PROVIDE THE MPCS USED IN DETERMINING ALLOWABLE RELEASE AATES OR CONCENTRATIONS.

A.' FISSION AND. ACTIVATION GASES:

B. IODINES:

C. PARTICULATES, HALF-LIVES > 8 DAYSt D. LIQUID EFFLUENT 8 l

3. AVERAGE ENERGY:

PROVIDE THE AVERAGE ENERGY (E-BAR) OF THE RADIONUCLIDE q MIXTURE IN RELEASES OF FISSION AND ACTIVATION GASE8, IF APPLICABLE' E-BAR BETA =3.53E-01/E-BAR GAMMA =8'.97E-01 E-BAR BETA AND GAMMA = 1.25E+00.

I

4. MEASUREMENTS-AND APPROXIMATIONS OF TOTAL RADIOACTIVITY: .

1

. PROVIDE:THE METHODS USED TO MEASURE OR APPROXIMATE THE TOTAL RADIOACTIVITY l IN EFFLUENTS AND THE METHODS USED TO DETERMINE RADIONUCLIDE COMPOSITIONS, J

'A.- FISSION AND ACTIVATION' GASES: HpGe SPECTROMETRY, LIQUID SCINTILLATION.

B. IODINES: EpGe SPECTROMETRY. l C.EPARTICULATES MpGe SPECTROMETRY, GAS FLOW PROPORTIONAL, l BETA SPECTROMETRY. l

'D. LIQUID EFFLUENTS: HpGe SPECTROMETRY, LIQUID SCINTILLATION.

5. BATCH RELEASES:

PROVIDE THE~FOLLOWING INFORMATION RELATING TL ESTCH RELEASES OF RADIOACTIVITY MATERIALS IN LIQUID AND GASE 78 LJFLUENTS. R QUARTER QUARTER 'I 1 2 a A. LIQUID

1. NUMBER OF' BATCH RELEASES: 44 17
2. TOTAL TIME PERIOD FOR BATCH RELEAST , t h '!b 17943. 4798.
3. MAXIMUM TIME PERIOD FOR A BATCH RE1L: (dIh 950. 332.

4.' AVERAGE TIME PERIOD FOR BATCH ~RELEA5Lt tb/N , 408. 282.

5. MINIMUM TIME PERIOD FOR A BATCH RELL?... "' >.) 145. 245.  ;
6. AVERAGE STREAM FLOW DURING PERIODS OF RELEASE OF EFFLUENT INTO A FLOWING STREAM: (CFM) 2.9JE+06 2.41E+06 -

l B. GASEOUS

1. NUMBER OF BATCH RELEASES: 33 10 2.LTOTAL TIME PERIOD FOR BATCH RELEASES: thin.) 23745. 7123.
3. MAXIMUM TIME' PERIOD FOR A BATCH RELEASE (MIN.) 1140. 900.
4. AVERAGE TIME PERIOD FOR BATCH RELEASEst (MIN.) 720. 712.
5. MINIMUM TIME PERIOD FOR A BATCH RELEASE (MIN.) 1. 10.

a

6. ABNORMAL RELEASES

-A. LIQUID

1. NUMBER OF RELEASES: ,
2. TOTAL ACTIVITY RELEASED: (CURIES) N/A N/A l B. GABEOUS L 1. NUMBER OF RELEASES: L 2. TOTAL ACTIVITY RELEASED: (CURIES) N/A N/A 1

-. . ... =- . ~ . - - - .. .-.

V'%, :c

. t.U.E TABLE 1A' .

EFFLUENT AND: WASTE DISPOSAL SEMIANNUAL REPORT! (1990) " .

.GA8EOUS' EFFLUENTS-SUMMATION.0F ALL RELEASES

, o 1

..........__............___............... 1 UNIT QUARTER 1. -QUARTER 2L EST. TOTAL

ERROR,'%'

........................w............_....

7 L

, ' A. FISSION AND ACTIVATION GASES

................................ .___.......s..es . ....... __

.i 1.. TOTAL RELEASE l CI l 6.60E+02 l.1.32%-100 e.............j 2.50E+01' .i s

2. AVG. RELEASE RATE FOR

...._ PERIOD- uCi/s 8.49E+01 1.67E-01.

3. PERCENT OF TECH, .

M S SPECIFICATION LIMIT  %' *

  • a u s.

1B . . IODINES

, 1.; TOTAL, IODINE ';

.I-131 CI 1.48E-03 6.77E-06 2.50E+01-H 2. AVG.-RELEASE: RATE

.FOR PERIOD uCi/s 1.90E-04 8.61E-07 "

l

3. PERCENT OF TECH. y 8PECIFICATION LIMIT  % *
  • q 1

C. 'PARTICULATES

~1 1.,PART. WITH: HALF-  ;

LIVES > 8= DAYS 1

CI 1.27E-07 <1.00E-04 2.50E+01 '

........____.....___........._.......__...~.............._-__.. ,

2.! AVG'. RELEASE RATE 1 FOR PERIOD- uci/s 1.64E-08 NA

3. PERCENT OF TECH.

18PECIFICATION LIMIT  %

  • NA 4.' GROS 8 ALPHA-RADIOACTIVITY CI <1.00E-11 <1.00E-11 'l 1

1 1

D.-' TRITIUM 1., TOTAL RELEASE CI l 5.01E+00 l

l 5.15E+00 l 2.50E+01 j 1

2. AVG. RELEASE RATE FOR~ PERIOD uCi/s 6.45E-01 6.55E-01 l: 3.' PERCENT OF TECH.

SPECIFICATION LIMIT  % *

  • NOTEt- ALL LESS THAN VALUES (<) ARE IN uCi/cc. l
  • %-TECH. SPEC. LIMITS: LISTED ON DOSE

SUMMARY

TABLE.

l l

a _-- a 1

1

' TABLE 10 EFFLUENT- AND WASTE DISPOSAL SEMIANNUAL REPORT ' (1990)

GACEOUS EFFLUENTS-GROUND-LEVEL RELEASE 8 CONTINUOUS MODE BATCH MO

____................. _............................... __.........DE ..__....

NUCLIDES RELEASED- UNIT QUARTER 1 QUARTER 2 QUARTER l' QUARTER 2

1. FISSION GASES

!. AR 41- l CI' l 5.79E-02 5.65E-02 2.85E 2 36E-01

..............................._____ ..l..........._l_...........l... .._____

KR ~ 85 l- CI l <8.00E-06 <8.00E-06 8.69E-01

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .l . _ _ _ . . . . . . . .l . . ........ . . . . . . . . . .l .

ER 85M CI 3.12E-02

. . . . . . . . . _ _ . . . . . . . . .l . . . . _ _l . . . . _ _ _ . . . . . l _1.92E-03

_ . , _ . . . . . . .l6.97E-01

. . . . . . . . . . .l _........

_ .4 . 4 5 E - 0 4  ;

KR 87 l CI l 2.98E-02 1.16E 5.88E-02 <

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .l . _ _ . . . . . . . .l . . . . . . . . . . .l . . 8 __......

KR 88 l CI 5.79E-02 2.7DE-04 l

..._...l ___ ..

5.69E-0

..._.l. ._.....1 .....___ l <1.00E-07 XE 131N l CI l <3.00E-07 <3.00E-07 4.49E+00 XE 133'

......___.......l............l.~.._.... ..l..1.52E-03 CI 1.16E+00 6.32E+02 XE 133M l

CI l

....l............l..

7.19E-02

.........l..6.94E-01 ......__

l l 1.64E-02 <2.00E-07 5.11E+00

. . . . . . . _ _ . . . . . . . . . . . . . . . . _ _ . . . . . . . . . . .l . . . . . . . . . _ _ _l _......... __........_

XE 135 CI 3.36E-01 l

_.-_-_-__....._...............l...

l l 9.64E-02 1.37E+0

......l_-_......1 l 3.05E-02 XE 135M CI 7.94E-02

--__........................._-_......_l_...

XE 138 l l 9.70E 02

.__. ..l.....7.65E-08 <

....._l_.5.00E-07 ......,_

)

l CI l 2.12E-02 <3.00E-07 <3.00E 07 <

_ . . . . . _ _ . . . . . . . . . n _ _ . . . . . . . . . . . . . _ - _ _ . .l . . . . _ _ _ . . ...._..._ _ _l _ _ - - . . .

TOTAL FOR PERIOD l CI l 1.79E+00 3.25E-01 6.58E+02 1

.__........__.............. __... .____l....___ ____l______.. ___l_ _9.86E-01 -_......

l I

2. IODINES I 131 l CI l 3.06E-04 6.76E 06 1.17E-03 <1

...__.....__........___..___..____.....l.....____...l____..____l____.00E-08 I 133 j

j l CI l 1.95E-04 8.74E-05 1.15E-06 '

. . . . . . . _ . _ . . . . _ _ _ _ . _ _ _ . . _ _ . . . . . . . . . . . . .l . _ . . . . _ _ ....__ _ _ .. .l . _ _ _ .

l I 135 l CI l 9.99E-06 <1.00E-10 7.65E-08 <

..__ .._..___.. ........ ________ ._. _l_._-_-__.___l __.... .__.l_.1.00E-10 .__._...

TOTAL FOR PERIOD CI 5.11E-04 l l l 9.41E-05 l 1.18E-03 l 3.62E-07 l

3. PARTICULATES 1 CO 58 CI

.... .........__..__._-_ l

\

l l <1.00E-12 <1.00E-12 2.28E-08 <

_ . _ _ . . . . . . . . . . . . _ . _ _ _ _ . . . _ . . . . . . . . . _ _ . .l . . . . . _ _ . __.. .__.. . .l . _ _ . _ _

CB 134 CI L

l

__...___________.................__.___.__. l <1.00E-11 l <1.00E-11 l 4.80E-08

..___ ........_____l__.1.00E-11 C8 137 l CI l <1.00E-11 <1.00E-11 5.66E-08 <

. . . . . . . . . . . - - . . . . _ _ _ _ _ _ . . . . . - . . _ - _ _ _ . _ .l - - _ _ _ _ _ . . . _ -l _ _ - _ - __.__.__

NOTE ALL LESS THAN VALUES (<) ARE IN UCi/cc.

l 1 l

1 l

4 . L' 4

i TABLE 2hi

' EFFLUENT AND WA8TE DISPOSAL' SEMIANNUAL REPORT (19P0)

LIQUID EFFLUENT 8-8UMMATION OF ALL RELEASE 8

, UNIT QUARTER'1 QUARTER 2- EST.' TOTAL ERROR, %

.....___.....___.1.__

I.

L A. - FI8SION AND' ACTIVATION PRODUCT 8-

1. TOTAL' RELEASE-(EE.

H-3,1 GASES, ALPHA) CI- 1.93E-02 2.30E-03 2.50E+01 2.-AVG.-DILUTED-CONC. DURING PERIOD uCi/ml L1.35E-09 1.99E-10 +

3.' PERCENT 0F'

~ APPLICABLE LIMIT'  % *

  • i B. TRITIUM L ........................_.............. ________ ... _.._......
1. TOTALLRELEASE l CI l 4.11E+01 l 1.67E+01'l 2.50E+01
2. AVG. DILUTED o

CONC..DURING~ PERIOD uci/ml 2.87E-06 1.44E-06.

i j

3.' PERCENT OF

' APPLICABLE LIMIT.

.....______ ......................... .__...___.... 1 C. DISSOLVED AND ENTRAINED GASES 1.? TOTAL RELEASE l CI l 2.05E-03 l <1.002-04-l 2.50E+01

2. AVG. DILUTED

~ CONC.LDURING PERIOD uCi/ml 1.43E-10 0.00E+00 3.1 PERCENT OF APPLICABLE LIMIT  % *

  • D.J" GROSS ALPHA RADIOACTIVITY
1. TOTAL; RELEASE l iDt - l <1.00E-07 l <1.00E-07 l 2.50E+01 E.. nVOL. OF WASTE RELEASED (NO DIL.) LITERS 1.64E+07 1.04E+07 1.00E+01 F. VOL. OF DILUTION WATER DURING PERIOD LITERS 1.43E+10 1.16E+10 1.00E+01 NOTE: ALL LESS THAN VALUES (<) ARE IN uCi/ml.

l-

  1. %. TECH. SPEC. LIMITS: LISTED ON DOSE

SUMMARY

TABLE.

H p

p ~V TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1990) r . LIQUID EFFLUENTS CONTINUOUS MODE BATCH NODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 L ............. ___ ..___ _______................ __________ _____.........

CR 51 l CI l <5.00E-07 l <5.00E-07 l 1.23E-04 l <5.00E-07 MN 54 l CI .l <1.00E-06 l <1.00E-06 l 4.32E-05 l <1.00E-06 55 i

FE

..............._____I._CI _ _ I. <5.00E-07

_ _' _ _ . i....______...I..4.95E-04

.<5.00E-07

. . . . ... I 1.09E-03 CO 58 l CI l 3.11E-04 l <5.00E-07 l 7.23E-03 l 7.82E-04 FE 59 l CI l <5.00E-07 l <5.00E-07 l 3.02E-05 l 1.16E-05 CO 60 l CI l <S.00E-07 l <5.00E-07 l 1.83E-04 l 1.19E-05 EN 65 l CI l <5.00E-07 l <5.00E-07 l <5.00E-07 l <5.00E-07

( .._.._______..............____________........___._____....____......_-__.

l SR B9 l CI l <5.00E-07 l <5.00E-07 l 1.91E-05 l <5.00E-07 BR 90 l CI l <1.00E-06 l <1.00E-06 l <1.00E-06 l <1.00E-06 NB 95 l CI l <5.00E-07 l <5.00E-07 l 6.21E-05 l <5.00E-07

_ __ ____..._..___...__.. ..._______._ ._ ____________....._..___......___ \

ZR. 95 l CI l <5.00E-07 l <5.00E-07 l 9.00E-06 l <5.00E-07

....._._________..._________________.... .___________...._______......____ )

AG 110M l CI l <5.00E-07 l <5.00E-07 l 1.99E-04 l- 2.65E __._......_____.._____.__._________._________...___.....__.______.___.____

l l

p SB 125 l CI l <5.00E-07 l <5.00E-07 l 5.51E-04 l <5.00E ______...........___________....___ ________ ___..____..____ __.._____.___

L I 131 l CI l 6.70E-04 l <5.00E-07 l 8.39E-04 l <5.00E-07 CS 134 l CI l 3.02E-03 l <5.00E-07 l 4.56E-04 l 5.92E-05 CS 137 l CI l 4.06E-03 l 2.14E-04 l 1.03E-03 l 1.12E-04 LA 140 l CI l <5.00E-07 l <5.00E-07 l 7.14E-06 l <5.00E-07 TOTAL FOR PERIOD l CI l 8.06E-03 l 2.14E-04 l 1.13E-02 l 2.09E-03 l

KF. 85 l CI l <1.00E-04 l <1.00E-04 l 2.05E-03 l <1.00E-04 NOTEt ALL LESS THAN VALUES (<) ARE IN uCi/ml.

TMI-l EFFLUENT & WASTE DISPOSAL SEMIANNUAL REPORT January l',1990 - June 30,1990

~l TABLE' 3A ETTLL'EST AND WASTE DISPOSAL SEMIANSUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIP.12iTS.

L A. .

Solid waste. shipped off-site for b'urial or disposal (not irradiated fuel) l'. Type of vaste

a. spent resins, 111ter sluoges, UNIT f,*$"jh EgS TOTAL p

3 evaeorator bottoms. etc. m 78.25 m l '- Ci 641.7 Ci 5%  !

b. Dry equitment,compressf*1e waste, contaminated m3 et.. 354.6 m3
c. Irractatec components, control e4 5 no r4 5 '*

' rod s , e t c. a#

Ci N/A N/A

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

l- ,

2. Estimate of major nuclide composition (bv type of waste)

_ a. CsAdi Csl3" 47.6 %

Cobe 29.4 3 Nis3 10.34 t

b. I131 4,71g NiW 32.31Y CR 137 13.86Y ensa 12.98%

roS5 12.73%

c. 10.74x i 1

t 4

__ d.

2 I

3. Soli t Waste Disposition Number of Shipments Mode of Transportation l Soo Attached Destination l'

l 1, l ._

I. B.

Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination N/A I ,

j 1

_ g.

1 I

1

4 h' .;

.: q - ;

-1 s

e. TMI-1 EFFLUENT & WASTE DISPOSAL SEMIANNUAL REPORT January 1. 1990 through June 30, 1990- '

l E Table A.3.a No. of Shipments Mode of Transportation i

Destination Four (4) Shipments Tractor - Cask-(HN-100 Series 3) Chem-Nuclear-Barnwell, SC Three (3) Shipments Tractor - Flatbed US Ecology-Richland; WA

  • Two (2) Shipments Tractor - Flatbed Scientific Ecology Group-l l' Oak Ridge. TN I Table A.3.b No. of Shipments Mode of Transportation Destination ,

L One (1) Shipment Tractor-Fla tbed US Ecology-Richland WA l *Nine (9) Shipments Tractor-Flatbed Scientific Ecology Group-Oak Ridge, TN-

)

l l

WASTE SHIPPED AS FOLLOWS:

Table A.1.a: 1 1

u Four (4) Radlok 500 High Integrity containers at 135.8 Ft.* Each :l Three (3) Steel Liners at 170 Ft.*-Each 1 Three (3) Steel Liners at 178 Ft.8 Each - Solidified with Cement  ?

  • Six'(6) Steel Liners at 196 Ft." Each l

l Table A.1.b: '

  • Twelve (12) 8' x 8' x 20' Cargo Containers at 1,040 Ft 8 Each One (1) Steel Box at 44 Ft.'

l l l l

l l

1 l

i

  • Material Sent Of f-Site to a Waste Processor for Volume Reduction l

I

,c -

4 - INTERPRETATION 0F' DOSE

SUMMARY

TABLE ~

~

The Dose ~ Sumary Table presents the maximum hypothetical' doses to an individual and

,the general population resulting from the release of gaseous and . liquid effluents from THI during the' first half . reporting period of 1990.

A. Liquid (Individual)

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

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

Calculations are performed on the four age groups and eight organs recomended in Regulatory Guide 1.109. The pathways considered for TMI are drinking water, irrigated. cow milk, irrigated goat milk, irrigated beef, consumption of fish, and standing on.the shoreline influenced by TMl effluents. The latter two pathways are considered to be the primary recreational- activities associated with the Susquehanna River in the vicinity of TMI. The irrigation pathways apply to the sewage sludge.

The " receptor" would be that individual who consumes water from the Susquehanna River and fish residing in the plant discharge,. while occupying an area of shoreline influenced by the plant discharge and consuming the milk and beef fed irrigated vegetation.

After calculating the -doses to all' age groups for all- eight organs resulting from the three pathways described above, the Dose Sumary Table presents the maximum whole body dose and affected age group along with the organ and. associated age group that received the largest. dose.-

For the first half of 1990 the calculated maximum whole body dose received by anyone would have been 0.11 mrem to an adult. Similarly, the maximum organ dose would have been 0.15 mrem to the liver of a teen.

B. Gaseous (Individual)

- There are seven major pathways considered in the dose calculations =for gaseous effluents. These are: (1) plune, (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 mean that these doses are not to an individual, but are considered to be the maximum dose that would have occurred at or beyond the site boundary. The Dose Sumary Table presents the distance in meters to the location in the affected sector- (compass point) where the theoretical maximum 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 from the noble gas effluents for the first half of 1990. The calculated maximum whole body dose received by anyone from noble gases would have been 0.016 mrem. Similarly, the maximum dose to the skin would have been 0.042 mrem.

O

P

-s y .

The iodines and-particulates section described in line 7; represents the ;

maximum . exposed.: organ due to iodine and; particulates. - This does not' .!

s include any whole body plume exposure which would be separated out by

linesL5 and_6. The-doses presented in this section again reflect.the maximum exposed organ for the appropriate age group.  ;

i

.The first. half 1990 iodines and particulates would have'resulted in:a- .

maximum dose of 3.0E-3 mrem to the thyroid'of an infant' residing' 580

  • meters from the site in the WNW sector. No other organ of any age group. d would have received a greater dose. - ,

~C.~ Liquid aEd Gaseous (Population)

Lines 8 - 11 present .the person-rem doses resulting from the liquid 'and .

gaseous effluents. These doses are summed over all pathways and the affected populations. Liquid person-rem is-based upon the population encompassed within the region from the TM1 outfall extending down to the -

Chesapeake Bay. -The person-rem for gaseous effluents are based upon the p 1980 population and consider the population out to a distance of 50 I

miles around TMI. Population doses are summed over all distances and ,

sectors to give an aggregate dose. i Based upon the calculations performed for the first half of 1990, liquid effluents resulted in a whole body population dose of 0.39 person-rem.

The maximum critical organ population dose to the thyroid was. 0.54 person-rem. Gaseous effluents resulted in a whole body population dose of 0.23 person-rem. Maximum critical organ population dose to the skin was 0.47 person-rem. q i

1 f

L i l

. - - - :g.

. TABLE 1 _

UNIT 1 2 First Half 1990 Dose' Report

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES JuneFOR 30,UNIT 1990I FROM January 1, 1990 through .

Location  % of l Technicai l

Estimated Dir Applicable j ' Specification ; ,

Dose Age Dist l l Applicable Group (m) (toward) l Limit i Limits (Frem) l-Organ (mrem)  ! l Cuarterly Annual. l' l Effluent j l Quarterly l Annual l { .) i 'l I i 'l . I Receptor 1 l

l 7.3 3.7 l 1.5' '3.0. ll.

.(1) Liquid l Total Body l 0.11 L Adult i .

10.0 - l'-

Receptor 1 l 3.0 l 1.5 l 5.0: 1 0.15 Teen

.(2) Liquid [ Liver 1 I

j 0.64 0.32 5.0 l 10.0' l 0.032 2000 NNE  !

i(3) Noble Gas , Air Dose (

l l l l. l l (gamma-mrad) 2000 NNE l 0.87 l 0.44 J. .10.0 i 20.0 l (4) Noble Gas l Air Dose .0.087 l l '

l l l l l-(beta-mrad) 2150 NNE j ---

l l:

(5) Noble Gas Total Body 0.016 All l l ---  !

l .j-Skin 0.042 All 2150 NNE l l

,(6) Noble Gas 1 1 .

WNW 0.040 0.020 l- 7.5- .- l 15.0 l Thyroid 3.0E-3 l Infant l 580 l (7) Iodine & ,

l- l l l l l l Particulates l

SUMMARY

OF MAXIMUM POPULATION DOSES JuneFOR 30,UNIT19901 FROM January 1, 1990 through Estimated Applicable Population Dose Effluent Organ (person-rem)

(8) Liquid Total. Body 0.39 (9) Liquid- Thyroid 0.54 Total Body 0.23 (10) Gaseous -0.47 (11) Gaseous Skin

, ,

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