ML20246J251
| ML20246J251 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 06/30/1989 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20246J088 | List: |
| References | |
| NUDOCS 8909050082 | |
| Download: ML20246J251 (9) | |
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- ATTACHMENT 1 TMI-2 QUARTERLY DOSE ASSESSMENT REPORT
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SECOND QUARTER 1989 4410-89-L-0096-Page 1 of 2 EXECUTIVE
SUMMARY
Three Mile Island Nuclear Station Unit 2 Effluent and Offsite Dose Report for the Period of April 1,1989 through June 30, 1989 This report summarizes the radioactive liquid and gaseous releases (effluents) from Three Mile Island Unit 2 and the calculated maximum hypothetical radiation exposure to the public resulting from these releases. This report covers the period of operation from April 1 through June 30, 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 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 Exposure to the public from consumption of water and fish withdrawn from the Susquehanna River downstream of the plant is also calculated.
Dose 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 riv:r water by precipitation of insoluble salts, absorption onto river sediment, biological removal, or removal during processing by water companies prior to distribution and consumption.
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7 TMI-2 QUARTERLY DOSE ASSESSMENT REPORT ATTACHMENT 1 i' .- SECOND QUARTER 1989 4410-89-L-0096 Page 2 of 2 Liquid discharges made during the reporting period April 1 through
~ June 30,1989 consisted of 0.0001 curies of tritium, 0.000036 curies of strontium-90 and 0.00009 curies of cesium-137. These release rates and quantities are consistent with results of previous quarters. The quantities of each radionuclides released are actually up to 1 million times smaller than the normally existing environmental quantities that flowe:i past the plant during the same time period.
During the reporting period April 1 through June 30 of 1989, the maximum hypothetical calculated whole body dose to an individual due to liquid effluents from Three Mile Island Unit 2 was about 0.0013 millirem. The maximum hypothetical calculated dose to any organ of an individual was 0.0022 millirem to the bone.
Airborne discharges made during this same time period consisted of 4 curies of tritium, and 0.0000001 curies of strontium-90. These release rates and quantities are also consistent with the results from previous reporting periods. The maximum hypothetical dose to an individual due to gaseous effluents was about 0.00082 millirem to the total body of a child.
The maximum hypothetical whole body dose received by any individual from effluents from the Three Mile Island Nuclear Station Unit 2 for the latest reporting period is 11,000 times lower than the dose the average individual in the Three Mile Island area receives from natural background during the same time period. Natural background averages about 25 millirem whole body per quarter in the Three Mile Island area and average equivalent dose from natural radon is about 50 millirem per quarter for a total of about 300 mrem per year.
The doses which could be received by the maximum hypothetical individual are each less than 0.04 percent o' the guides established by the Nuclear Regulatory Commission.
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I d "1- ' -SECOND QUARTER 1989 4410-89-L-0096
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ErrLUENr summRY u . ..
THREE MILE ISLAND UNIT 2 LIQUID AND GASEODS EFFLUENTS h (SUWERY OF ALL annRES) .
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9 TYPE EFFLUENT 2ND QUARTER 1989
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- I. LIQUID EFFLUENTS: ' APRIL MAY JUNE 2ND QUARTER J 4. FISSION AND ACTIVATION PRODUCTS ======= ======== ======= ===========
(NOT INCLULING H-3, GASES, E ALPHA)
- 1. M AL RELEASE (C1)- 3.06E-05 2.29E 7.56E-05 1.29E-04
- 2. CON"ENHLATION(uci/ce) 9.27E-12 6.14E-12 2.14E-11 1.22E-11 i
B. TRITIUM
-.1. M AL RELEASE (C1) G 4.71E-06 1.21E-04 1.26E-04
- 2. CONCENTRATION (uC1/cc) N/A 1.26E-12 3.43E-11' 1.19E-11 F
C. DISSOLVED AND ENTRAINED GASES-LC 1. TOTAL pnnKE (C1) G G e e
[ 2. CONCENTRATION (uC1/cc) N/A N/A N/A N/A D. GROSS ALPHA L TIVITY
- 1. M AL RELEASE (Ci) @ G G 'm L E. v0 LUNE Or m STE RELEASED PRIORTODILUTION(LITERS). 2.98E+04 3."3E+04 4.01E+04 1.03E+05 L
i F. VOLUME OF DILUTION WATER 3.31E+09- 3.73E+09 3.52E+09 1.06E+10
-(rLOWTORIVERINLITERS FROM NPDES REPORT)
G. NUMBER OF BATCH pnnRES - 12 16 11 39
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ATTACHMENT 2 TM12 QUARTERLY DOSE ASSESS 4ENT REPORT -
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SECOND QUARTER 1989 4420-89-L-0096 Page 2 of 4 {
1989 UNIT 2 LIQUID EADIONDCLIDE RELEASES BY ISOTOPE (C1)
RADIONUCLIDES APRIL MAY JUNE 2ND QUARTER 1989 FISSION AND ACTIVATION PRODUCTS.
(N W INCLUDING ALPHA, H-3 & GASES) G G G G AG-110M G G G G CE-144 G G G G CO-58 G G G G CO-60 G G G G CS-134 <LLD G G G CS-137 2.01E-05 1.12E-05 6.15E-05 9.28E-05 I-131- G G G G SR-90 1.05E-05 1.17E-05 1.41E-05 3.63E-05 TOTAL 3.06E-05 2.29E-05 7.56E-05 1.29E-04 H-3 G 4.71E-06 1.21E-04 1.26E-04 l
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TMI-2 QUARTERLY DOSE ASSESSMENT REPORT . ATTACHMENT-2
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Page 3 of 4-k' EFFLUErf SINDERY THREE MILE ISIAND UNIT 2 LIQUID AND GASE0DS EFFLUElffS ~
(SINNERYOFAU. RELEASES)
- ,TTPE EFFLUElff 2ND QUARTER 1989
... ...._ . . ~ - .. . . .
TOTAL APRIL- MAY JUNE .2ND QUARTER
== === ========c== =========== ======-
2 II. GASEOUS EFFLUENTS:
.A. FISSION AND ACTIVATION GASES 1.TOTALRELEASE(C1). G: -G- <LLD ^ GLD
- 2. RtimE RATE (uci/sec)- N/A N/A N/A N/A-E B. IODINE 131 BrimED (C1) G G G G C. PARTICULATE WITH HALF-LIVES
>8 DAYS.
.1. TOTAL RELEASES (IFJf 1.02E-07 1.02E-07 G 2.03E-07 IllCLUDING ALPHA) (C1)
'2.RELEASERATE(uC1/sec): 3.92E-08 3.79E-08 N/A 2.58E-08
- 3. GROSS ALPHA RADIO -
ACTIVITY (C1) GLD G G G
'D. TRITIUM t
1.TOTALRELEASE(Ci) 2.20E+00 6.39E-01 1.43E+00 4.7/ECs 2.RELEASERATE(uci/sec) ' B.49E-01 2.39E-01 '5.53E-01 5.43E-01' E. SECONDS IN PERIOD REPORTED 2.5920E+% 2.6784E+06 2.5920E+06 7.8624E+06 F. NUMBER OF BATCH RELEASES 0 0 0 0
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TMI-2 QUARTERLY DOSE ASSESSMENT REPORT ATTACHMENT 2 4410-89-L-0096 SECOND QUARTER 1989 Page 4 of 4 UNIT 2 GLSEOUS RADIONUCLIDES RELEASES BY ISO M E (Ci)
RADIONUCLIDES APRIL MAY JUNE 2ND QUARTER 1989
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FISSION LND ACTIVRTION GLSES KR-B5 G G G G TOTAL PARTICULRTES(HALF-LIVES >8 DAYS)
CS-137 GLD G G G CS-134 GLD G G GLD SR/Y-90 GLD 1.02E-07 GLD 1.02E-07 GROSS ALPHA GLD G GLD CLD MAL (INCLUDING ALPHA) GLD 1.02E-07 G 1.02E-07 TOTAL (MINUS ALPHA) GLD 3.02E-07 G 1.02E-07 TRITIUM (H-3) 2.20E+00 6.39E-01 1.43E+00 4.27E+00
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TMI-2 QUARTERLY DOSE ASSESSMENT REPORT ATTACHMENT 4 6
SECOND QUARTER 1989 4410-89-L-0096 Page 1 of 2 J
INTERPRETATION OF DOSE
SUMMARY
TABLE i 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 frem TMI-2 during the second quarter reporting period of 1989.
A. _ Liquid (Individual) <
The first two lines present the maximum hypothetical dose to an individual . Presented are the whole body and critical organ doses.
l Calculations are performed on the four age groups and eight organs recomended in Regulatcry Guide 1.109. The pathways considered for TMI-2 are drinking water, consumption of fish, and standing on the shoreline influenced by TNI effluents. The latter two pathways are considered to be the primary recreational activities ascociated 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.
l 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 second quarter of 1989 the calculated maximum whole body dose received by anyone would have been 1.3E-3 mrem to an adult.
Similarly, the maximum organ dose would have been 2.2E-3 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.
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 ef fluents.
Direct noble gas plume dose to the maximum individual is shown on lines 5 and 6. Since no noble gases were released in the secon.d quarter, the doses are zero.
^ TMI-2 QUARTERLY DOSE ASSESSMENT REPORT ATTACHMENT 4
- - c' SECOND QUARTER 1989- 4410-89-L-0096 Page 2 of 2 The Iodines and Particulate section described in line 7 represents l the maximum exposed organ due to iodine and particulate. 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 second quarter 1989 iodines and particulate would have resulted in a maximum dose of 8.2E-4 mrem to the total body of a child residing 2450 meters from the site in the SSE 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 sumed 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 1980 population and consider the population out to a cistance of 50 miles around TMI. Population lL doses are summed over all distances and sectors to give an aggregate dose.
Based upon the calculations performed for the second quarter, liquid effluents resulted in a whole body population dose of 1.9E-3 '
person-rem. The maximum critical organ population dose to the bone was 7.4E-3 person rem. Gaseous effluents resulted in a whole body population dose of 2.7E-2 person-rem. Maximum organ population dose was 2.7E-2 person rem to the liver, thyroid, GI tract, lung and kidney.
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