ML20033E325

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TMI-2 Effluent & Offsite Dose Rept for Oct-Dec 1989
ML20033E325
Person / Time
Site: Crane Constellation icon.png
Issue date: 12/31/1989
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20033E324 List:
References
4410-90-L-0016, 4410-90-L-16, NUDOCS 9003120330
Download: ML20033E325 (10)
v • d • e


Text

'.

TMI-2 QUARTERLY DOSE ASSESSMENT REPORT ATTACHMENT 1 FOURTH QUARTER 1989 4410 90-L-0016 l

Page 1 of 2 i

EXECUTIVE

SUMMARY

i Three Mile Island Nuclear Station Unit 2 i

Effluent and Offsite Dose Report for the Period of October 1,1989 through December 31, 1989 This report summarizes the radioactive liquid and gaseous releases (effluents) i from Three Mile Island Unit 2 and the calculated maximum hypothetical radiation i

exposure to the public resulting from these releases.

This report covers the 1

period of operation frcm October 1 through December 31, 1989.

Radiological releases from the plant are measured 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 dose 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 downstream of TMI due to liquid releases.

Actual or "real-time" meteorological data from an onsite tower is used to determine the doses resulting from gaseous releases from the plant.

The use of real-time meteorological information permits the determination of both the direction in which the release traveled and the dispersion of radioactive material i

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 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, j

Dose calculations for liquid and gaseous effluents are perfonned 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 l

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 j

consumption, i

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TMio2 QUARTERLY DOSE ASSESSMENT REPORT ATTACHMENT 1 FOURTH QUARTER 1989 4410- 90-t- 0016 Page 2 of 2 Liquid discharges made during the reporting period October 1 through December 31, 1989 consisted of 0.00009 curies of tritium, 0.000008 curies of strontium-90 and 0.00001 curies of cesium-137. The quantities of effluents are consistent with results of previous quarters. The quantities of each radionuclide released are actually up to 1 million times smaller than the normally existing environmental quantities that flowed past the plant during the same time period.

During the reporting period October 1 through December 31 of 1989, the maximum hypothetical calculated whole body dose to an individual due to liquid effluents from Three Mile Island Unit 2 was about 0.0002 millirem. The maximum hypothetical calculated dose to any organ of an individual was 0.0004 millirem to the bone.

Airborne discharges made during this same time period consisted of 4.0 curies of tritium and 0.000001 curies of strontium-90. These quantities are also consistent with the results from previous reporting periods. The maximum hypothetical calculated dose to any individual due to gaseous effluents was about 0.0008 millirem to the bone of a child.

The total maximum hypothetical whole body dose received by any individual i

from effluents from the Three Mile Island Nuclear Station Unit 2 for the l

reporting period is 27,000 times lower than the dose the average individual in the Three Mile Island area receives fr,a natural background during the same time period, Natural background ave.agus about 25 millirem whole body per quarter in the Three Mile Island area.

In addition, average equivalent dose to the total body from natural radon is about 50 millirem per quarter.

l The doses which could be received by the maximum hypothetical individual are each less than 0.01 percent of the guidelines established by the Nuclear Reigualtory Commission, r

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TMI.2 QUARTERLY DOSE ASSESSMENT REPORT-ATTACHMENT 2 FOURTH QUARTER 1989 4410 90.L.0016 1,

Page 1 of 4

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LITLUENT SINNERY.

i THRFI KILE ISLAC UNIT 2 LIQUID AND G&SEOUS EFFLUENTS i

(SUINERT OF ALL RemES)

. TYPE Ef7LUENT 4TH QUARTER 1989

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.e M &L l

I. LIQUID EITLUENTS:

OC10BER N3VDBER DECDEER 4TH QUARTER.

i

n. rISS10N AND ACTIVhTION PRapoCTS

= = = =

= = =

- = = = = =

= = = =

(NOTINCLUDINGH-3,GLSES,& ALPHA)

1. M kL RELEASE (C1)

.1.80E-05 2.41E-06 1.77E-06 2.22E-05

2. CONCENTRATION (uci/cc) 4.80E-12 6.35E-13 4.12E-13 1.87E-12 B. TRITIlm
1. TOT &LRELEASE(C1) 7.99E-05~

8.49E-06 G-8.83E 2.CONCEMATION(uCi/cc)

.2.13E-11 2.24E-12 G

7.46E-12 l

l C. DISSOLVED kND ErfRAINED G&SES 1.TOTALRELEASE(C1)

.<LLD-G G

G 2.CONCEmATIONuC1/cc)

N/A N/A N/A N/A l

1 D. GROSS ALPHh ACTIVITY 1.T0r&LRELEASE(C1)

G G

G G

r E. VOLIME OF WhSTE RELEASED PRIORTODILUTION(LITERS) 4.24E+04 2.80E+03 1.28E+04 5.79E+04-F. VOLIME OF DILUTION WATER

~3.75E+09 3.79E+09 4.30E+09 1.'18E+10 (FLOW 10 RIVER IN LITERS FROM NPDES REPORT) i G. NIMBER OF BATCH REllASES 14

-2 4

20 s

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~TMI.2 QUARTERLY DOSE ASSESSMENT REPORT' ATTACHMENT 2.

FOURTH QUARTER -1989 -

4410 90.L.0016 Page 2 of 4 l

[.

1989 UNIT 2 LIQUID RADIONUCLIDE RUME BY ISOTOPE (C1) i 1

1 RADIONUCLIDE OCTOBER NOVDEER DECDIBER

-4TH QUARTER 1989 l

~. FISEI(M kND ACTIVnTION PRODUCTS i

(NOT INCLUDING ALPHA, H-3 & GnSES CLD CLD:

4LD G

AG-110M G

GLD

' GLD

'G

.j 1

,CE-144 GLD

. GLD CLD -

GLD.

CO-5B GLD GLD G ~

i G

e CO G GLD.

GLD GLD -

CS 134 GLD GLD 4LD '

GLD.

CS-137 1.21E-05

'2.02E-06 GLD 1.41E I 131 GLD GLD CLD --

GLD C2-90 5.89E-06 3.89E 1.77E-06

_8.05E............................

TurnL 1.80E-05 2.41E 1.77E-06 2.22E-05 H-3 7.99E-05 8.49E-06 GLD 8.83E-05 i'

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I-i r

C1

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TMI-2. QUARTERLY DOSE ASSESSMENT REPORT ATTACHMENT ~2-FOURTH QUARTER 1989 4410-90.L-0016 Page 3 of 4 EFFLUDrf StBIERY

'DIREE MILE ISLhWD UNIT 21.IQUID AND GhSE005 EITLUEllTS (SUIglhRY OF ALL PnmES)

TfPE EITLUt317 4MIQUhRTER 1989 M hL OCTOBER NOVDIBER DECDIBER 431QUhRTER kE222323333 Estaantratt ttttttstatt E3E2233t233 II. CASEOUS EITLUDrrS

h. FISSION kND ACTIVATION ChSES
1. M AL RELEhSE (C1)

G G

G G

2. RELEASE Rh17, (uC1/mec)

N/A N/A R/h N/A B. IODINE 131 RELEASED (C1)

G G

G G

C. PARTICULhTES WITH HkLF-LIVES

>8 DhYS

1. M AL RELEASES (IKft 1.40E 5.62E-08 G

1.4LE-06 INCLUDINGt.LPHk)(C1)

-2.RELEASERATE(uci/sec) 5.22E-07' 2.17E-08 N/A 1.83E-07

3. GROSS htPHk RADIO-ACTIVITY (Cl)

G G

G G

D. TRITIUM

1. M AL RELEASE (Cl) 1.LBE+00 1.27E+00 6.74E-01 3.53E+00 2.RELEASERhTE(uC1/sec) 5.90E-01 4.91E-01 2.52E-01 4.44E-01 E. SECONDS IN PERIOD REPORTED 2.6784E+06 2.5920E+06 2.6784E+06 7.9488E+06 F. NUMBER OF BATCH RELEASES 0

0 0

0

' *f TMI-2 QUARTERLY OOSE ASSESSMENT REPORT:

ATTACHMENT 2 FOURTH QUARTER R989 4410- 90-L-0016 -

Page 4 of 4 UNIT 2GhSEOUSRADIONUCLIDERELEASESBYIS0f0PE(C1)'

RADIONUCLIDE OCTOBER IEWEMBER DECDBER 4TH QUkkTER 1989

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====,an=====,..um

.ma,a,umon.a FISS10N kND ACTIVnTION GASES KR-85 e

e 4tp 4to 1UrhL PARTICULATES(HALF-LIVES >8DhYS)

CS-137-G GLD "G

GLD cS-134 m

e sto.

e-SR/Y-90 1.40E-06 5.62E-08 GLD 1.45E oR0sS nLPHa eto eLo

-e

.. e 70fkL(INCLUDINGALPHA) 1.40E-06 5.62E-08 CLD 1.45E-06 1Uf&L(MINUSALPHA) 1.40E-06 5.62E-08 GLD 1.45E-06 TRITIUM (H-3) 1.58E+00 1.27E+00 6.74E-01 3.53E+00 i

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TRI-2 QUARTERLY DOSE ASSESSMENT REPORT ATTACHMENT 3 FOURTH QUARTER 1989 4410-90-L-0016 Page 1 of 2 TABLE 1 UNIT 2 Fourth Quarter Dose Report

SUMMARY

OF MAXIMUM Ii4DIVIDUAL DOSES FOR UNIT 2 FROM Octo*oer 1,1989 through December 31, 1989 l'

l I

Estimated i

I Location i

% of l

I I

l Applicable Dose Age i Dist Dir i

Applicable I

Limits (mrem) i

! Effluent i

Organ I

(mrem) l Group I

(m)

(toward)

I Limit i 10 CFR 50 Appendix I l 1

l l

l l

l Quarterly l Annual l Quarterly l Annual l

I I

I I

I I

i I

i i

l 3.0 l

l(1) Liquid l Total Body i

2.3E-4 l

Adult i Receptor 1 1

1 7.6E-3 l

l 10.0 i

l 4.1E-3 1

l(2) Liquid 1 Bone 1

4.1E-4 l

Child l Receptor 1 1

i I

I I

I I

I I

i i

i i

1 I

i i

i i

i I

l 10.0 l

1 0

1 1

l(3) Noble Gas l Air Dose 1

0 1

I I (gamma-mrad) I i

l i

i i

i I

l 20.0 i

1 1

0 l

1 l(4) Noble Gas l Air Dose l

0 1

l I (beta-mrad) l l

l l

l l

l l

l 5.0 l

1 1

0 1

l(5) Noble Gas l Total Body i

0 l

All 1

l 15.0 l

l 0

l 1

l(6) Noble Gas i Skin 1

0 l

All 1

l l

l l

1 I

I I

I I

l l

1 I

I I

I I

I i

l 15.0 i

1 5.2E-3 l l(7) Iodine &

I Bone 1

7.8E-4 i

Child I

580 WNW l

l Particulatesi l

l I

I I

l l

l SUPNARY OF MAXIMUM POPULATION DOSES FOR UNIT 2 FROM October 1,1989 through December 31, 1989 Estinated Applicable Population Dose Ef fluent Organ (person-rem)

(8) Liquid Total Body 1.7E-3 (9) Liquid Bone 6.8E-3 (10) Gaseous Total Body 0.0 21 (11) Gaseous GI, Lung, Liver, 0.020 Kidney, Thyroid

_._.______m_

TMI-2 QUARTERLY DOSE ASSESSMENT REPORT ATTACitMENT 3 FOURTH QUARTER 1989 4410-90-L-0016 TABLE 2 Page 2 of 2 UNIT'2 Annual Dose Report

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES FOR UNIT 2 FROM January 1,1989 through December 31, 1989 l

l l

Estimated l

l Location l

% of l

I I

I Applicable 1

Dose l

Age i Dist Dir i

Applicable I_

Limits (mrem) l I

Effluent i

Organ 1

(mrem) i Group I

(m)

(toward)

I limi t i 10 CFR 50 Appendix I l l

l l

l l

l Qua rterly I Annual l Quarterly I Annual i

i i

l i

i i

i i

l l

l 3.0 l

l(1) Liquid i Total Body 1

3.2E-3 l

Adult l Receptor 1 1

1 0.11 1

l 10.0 i

l 0.055 l l(2) Liquid i Bone 1

5.5E-3 1

Child i Receptor 1 1

i i

i i

i l

i I

I I

I I

I I

I I

I I

I i

1 0

1 1

10.0 l

1 l

l(3) Noble Gas i Air Dose 1

0 1

l I (gamma-mrad) l l

l l

1 l

l l

l 0

1 l

20.0 i

1 l(4) Noble Gas 1 Air Dose 1

0 1

I l

. I (beta-mrad) i l

1 l

I l.

l l

5.0 1

1 1

0 1

l(5) Noble Gas -l Total Body 1

0 l

All 1

1 0

1 1

15.0 I

I 1(6) Noble Gas i Skin 1

0 l

All 1

I I

I I

I I

I I

i i

i i

i i

i I

I I

I i

l 15.0 l

l(7) Iodine &

1 Bone 1

2.2E-3 i

Child 1 2700 WSW 1-1 0.01 5 1 l

Particulatesl l

1 l

I I

i l

l SUPMARY OF MAXIMUM POPULATION DOSES FOR UNIT 2 FROM January 1,1989 through December 31, 1989 Estimated Applicable Population Dose Effluent Organ (person-rem)

(8) Liquid Total Body-0.021 (9)' Ligaid Bone 0.080 (10) Gaseous Total Body 0.077 (11) Gaseous Liver, ridney

-0.076 Annual summations will not equal the sum of each periodic report due to receptor location changes and interpolation

' resul ts.

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TMI-2 QUARTERLY DOSE ASSESSMENT REPORT ATTACHMENT 4 FOURTH QUARTER 1989 4410- 90-L-0016 Page 1 of 2 INTERPRETATION OF DOSE

SUMMARY

TABLE The Dose Summary Table presents the maximum hypothetical doses to an individual and the general population resulting from the release of gaseous 1

and liquid effluents from TMI-2 during the fourth quarter reporting period of j

1989.

i l

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 recommended in Regulatory Guide 1.109.

The pathways considered for THI-2 are drinking water, consumption of fish, and standing on the shoreline influenced by TMI effluents.

The latter two pathways are considered to be t

the primary recreational activities associated with the Susquehanna River in the vicinity of TMI. 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.

Af ter calculating the doses to all age groups for all eight organs resulting from the three pathways described above, the Dose Summary 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 fourth quarter of 1989 the calculated maximum whole body dose received by anyone would have been 2.3E-4 mrem to an adult.

Similarly, the maximum organ dose would have been 4.1E-4 mrem to the bone of a child.

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.

l Lines 3 and 4 present the maximum plume exposure at or beyond the site bounda ry.

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 Summary 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.

Direct noble gas plume dose to the maximum individual is shown on lines 5 and 6.

Since there were no noble gas releases, the values on lines 5 and 6 are zero.

THI-2 QUARTERLY DOSE ASSESSMENT REPORT ATTACHMENT 4 FOURTH QUARTER 1989 4410-90-L-0016 Page 2 of 2 The lodines and Particulates section described in line 7 represents the maximum exposed organ due to iodine and particulates.

This does not include any plume exposure which is 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 fourth quarter-1989 iodines and particulates would have resulted_ in a maximum dose of 7.8E-4 mrem to the bone of a child residing 580 meters from the site in the WNW 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 summed over all pathways and the affected populations.

Liquid person-rem is based upon the population 4

encompassed within the region from the TMI outfall extending down to the i

Chesapeake. Bay.

The person-rem for gaseous effluents are based upon the l

1980 population and consider the population out to a distance of 50 miles around TMI.

Population doses are summed over all distances and sectors to 1

give an-aggregate dose.

i Based upon the calculations performed for the fourth quarter, liquid effluents resulted in a whole body population dose of 1.7E-3 person-rem.

The maximum critical organ population dose to the bone was 6.8E-3 person i

rem.

Gaseous effluents resulted in a whole body population dose of 0.021 person-rem. Maximum organ population dose to the thyroid, lung, kidney, liver and GI was 0.020 person-rem.

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