ML20153D735
| ML20153D735 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 06/30/1988 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20153D725 | List: |
| References | |
| 4410-88-L-0142, 4410-88-L-142, NUDOCS 8809060024 | |
| Download: ML20153D735 (9) | |
Text
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' ATTACHMENT 1 ag h o f 2 EXECUTIVE
SUMMARY
Three Mile Island Nuclear Station Unit 2 Effluent and Offsite Dose Report for the Period of April 1,1988 to June 30, 1988 This re (effluents) portfrom summarizes Three Mile the radioactive Island liquid Unit 2 and and gaseous the calculated releases maximum hypothetical radiation exposure to the public resulting from these releases.
This report covers the period of operation from April 1 to June 30, 1988.
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 provide a means for accurate determination of the type and quantities of radioactive materials being released to 1.he 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 individuG1 and the population downstream of THI 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 ir 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 Exposure to the public from consumption of water and fish withdrawn from the Susquehanna River downstream of the plant is also calculated.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 overestimatet 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.
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, . ATTACHMENT 1 -
4 4410-88-L-0142 Page 2 of 2 Liquid discharges made during the reporting period April 1 to June 30, 1988 consisted of 0.004 curies of tritium, 0.0002 curies of strontium-90 and unidentified beta activity, 0.0000009 curies of cesium-134 and 0.0002 curies of cesium-137. Unidentified beta activity is treated cs strontium-90 for the purpose of dose calculations. These release rates and quantities 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 'vPat flowed past the plant during the same time period.
During the reporting period April 1 to June 30 of 1988, the maximum hypothetical calculated whole body dose to an individual due to liquid effluents from Three Mile Island Unit 2 was about 0.003 millirem. The maximum hypothetical calculated dose to any organ of an individual was 0.007 millirem to '
the bone.
) Airborne discharges made during this same time period consisted of 2 curies of tritium, and 0.000004 curies of unidentified beta activity. Unidentified i beta activity is, as with liquid effluents, conservatively assumed to bo ;
entirely 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 0.003 millirem to the bone of a child. !
l The maximum hypothetical whole body dose received by any individual from ,
effluents from the Three Mile Island Nuclear Station Unit 2 for the latest I reporting period is 6400 times lower than the dose the average individual in the :
Three Mile Island area receives from natural background during the same time i period. Natural background averages about 25 millirem whole body per quarter in t the Three Mile Island area. In addition, average equivalent dose from natural ,
radon is about 50 millirem per quarter. '
The doses which could be received by the maximum hypothetical individual are at most 0.1 percent of the guides estabiished by the Nuclear Regulatory Commission.
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Attachment 2 P;ge 1 cf 4 . .
EFFLUENT
SUMMARY
4410-88-L-0142 ,
THREE MILE ISLAND UNIT 2 LIQUID AND GASEOUS EFFLUENTS (Summary of All Releases) .
TYPE EFFLUEN1 2ND QUARTER 1968 I. Liquid Effluent: APRIL MAY JUNE A. Fission and activation products TOTAL 2ND OUARTER-(not including H-3, gases & alpha) '
- 1. Total Release (C1) (Note 2) 2.63E-5 1. 21 E-4 3.19 E -4 4. 66E-4
- 2. Concentration (pC1/cc)(Note 2) 5.d1E-12 2.64 E-11 6.54E-11 3.26E-11 B. 1ritium -
- 1. lotal release (C1) 3.33E-3 8.46E-5 7.00E-4 4.12E-3
- 2. Concentration (pCi/cc) 6.85E-10 1.84E-11 1.43E-10 2.87E-10 C. Dissolved and entrained gases
- 1. Total release (C1) <LLD <LLD <LLD <LLD
- 2. Concentration (pC1/cc) N/A N/A N/A N/A D. Gross alpha radioactivity
- 1. Total release (C1) (Note 2) <LLD < LLD <tLD -cLLD E. Volume of waste released prior to dilution (liters) (Note 1) 7.46Et4 5.31E&4 5.27Et4 1.80Et5 F. Volume of dilution water (flow to river in liters from NPDES Report) 4.86Et9 4.59E+9 4.89E+9 1.43E+10 G. Number of batch releases: 16 18 17 51
- The concentration of radioactive material other than dissolved or entrained noble gases in liquid effluent released to the unrestricted area shall not exceed the values specified in 10CFR 20, Appendix B, Table II.
- Present liquid ef fluent release limits are 10% of the concentration values specified in 10CFR 20, Appendix 8 Table II.
- Liquid effluent releases are also limited to 10CFR 50, Appendix I, not to exceed a dose of 3 mrem total body and 10 mrem to any organ per year.
Note 1) Includes only those releases which were found to contain radioisotopic concentration >LLD from the Industrial Waste Stream..
Note 2) These activities are to be verified by composite sampling.
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Attachment 2 '
- P ge 2 if 4 .
EFFLULNI
SUMMARY
4410-88-L-0142 IllRLL MILL ISI.AND UNil 21.1Q010 AND GASIOUS LI FI ULNIS *
(Summary of Ai! Releases)
B Yl't ti l LULNI 2ND QUAR 1LR 1988 APRIL MAY JUNE TOTAL 2ND 00ARTER .
II. Gaseous Effluent A. Fission & act ivation gases <LLD <LLD <LLD <LLD
- 1. lotal release (Ci) N/A N/A N/A N/A B. Iodine-131 released (C1): <tLD <LLD <LLD <LLD .
C. Particulates with half-lives
>8 days:
- 1. Total releases (not including alpha)(C1) 1.79E-6 1.38E-6 9.35E-7 4.11E-6
- 2. Release rate (pC1/sec) 6.91E-7 5.15E-7 3.61E-7 5.23E-7
- 3. Gross alpha radio-activity (C1) <LLD 8.41E-8 5.49E-B 1.39E-7 D. Tritium
- 1. Total release (Cl) 9.40E-1 5.18E-1 4.34E-1 1.89E0
- 2. Release rate (pC1/sec) 3.63E-1 1.93E-1 1.67E-1 2.41E-1 E. Seconds in period reported 2.5920E*6 2.6784E+6 2.5920E+6 7.8624Et6 F. Number of batch releases 0 0 0 0
- 1he concentration of radioactive material in gaseous ef fluents released to the unrestricted area shall not exceed the values specified in 10CFR 20. Appendix B, Table II.
- 10CFR 50 dose to individual for: a) 10 mrad /yr, gamma radiation; b) 20 mrad /yr, beta radiation; and c) 15 mrem /yr to any organ.
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Attachment 2
- PLge 3 cf 4 .
19.'8 UNIT 2 LIQUID RADIONUCLIDE RELEASES BY IS010PE (C1) 4410-88-L-0142 -
RADIONUCLI9E APRIL MAY JUNE 2ND QUARTER 1988
- Fission and activation products j (not including alpha, H-3 & gases) <LLD <LLD <LLD <LLD ,
Ag -110m <LLD <LLD <LLD <LLD Cc -144 <LLD <LLD <LLD <LLD Co-58 <LLD <LLD <LLD <LLD l
Co -60 <LLD <LLD <LLD <LLD .
j Cs-134 <LLD <LLD 9.17E-7 9.17E-7 Cs -137 1.02E-5 5.61E-5 1. 59 E-4 2.25E-4 I-131 <LLD <LLD <LLD <LLD i
Sr-93* 1.61E-5 __6.47E-5 1. 59 E-4 2.40E-4
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101AL '2.63E-5 1.21E-4 3.19E-4 4.66E-4 1
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- H -3 3.33E-3 8.46E-5 7. 00E-4 4.12E-3 i
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- The values reported include Sr-90 activity and any activity not specifically identified. Thus, the
- reported Sr-90 value represents a conservative estimate (i.e. overestimate) and contains activity j from other beta-gamma emitters which were not positively identified during conduct of analytical orocedures.
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Attachment 4' P ge 4 Lf 4 UNIT 2 GASE003 RADIONUCLIDE RELEASES 8Y ISOTOPE (Ci) 4410-88-L-0142 RADIONUCLIDL APRIL MAY JUNE 2ND QUARTER 1988
. fission and activation gases Kr-85 <tLD <LLD <tLD <tLD lotal <LLD <LLD <LLD <LLD Particulates (half lives >8 days) j Gross beta / gamma 1.79E-6 1.38E-6 9.35E-7 4.11 E l Cs-137 <tLD <LLD <LLD <LLD Cs-134 <LLD <LLD <LLD <LLD 4 Sr/Y-90 <tLD <LLD <LLD <tLD Gross alpha <tLD 8.41E-8 5.49E-8 1.39E-7 101AL (including alpha) 1.79E-6 1.46E-6 9.90E-7 4.24E-6 I TOTAL (minus alpha) 1.79E-6 1.38E-6 9.35E-7 4.11E-6 Tritium (3H) 9.40E-1 S.18E-1 4.34E-1 1.89E0
i ATTACHMENT'3 .- '
4410-88-L-0142 ,
9' '
UNIT-2 , ,1 Second Quarter Dose Report *
! SUM 1ARY OF MAXIMUM INDIVIDUAL DOSES FOR UNIT 2 FROM June 30,1988
! April 1,1988 tnrough 1
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! l I I Estimated i I Location I % of I l l l 1 Applicable i Dose I Age l Dist Dir i Applicable i Limits (mrem) l
'l Effluent i Organ I (mrem) 1 Group I (m) (toward) l Limit i 10 CFR 50 Appendix I l' l l Quarterly I Annual I Quarterly I Annual l 4
l l l l l l l 1 1 I i l l l l 1 j l(1) Liquid i Total Body l 3.3E-3 l Adult l Receptor 1 l ---
1 0.11 1 ---
l 3.0 "I l(2) Liquid i Bone 1 6.5E-3 1 Adult l Receptor 1 1 ---
1 0.065 l ---
1 10.0 I
) l I i i l I i i i i i i i I I I I I i I i n l(3) Noble Gas l Air Dose 1 0 1 ---
1 ---- ---
I ---
l 0 l ---
l 10.0 l
- 1 I (gamma-arad) l l l l l l 'I I i
l(4) Noble Gas l Air Dose 1 0 1 ---
1 ---- ---
1 ---
l 0 1 ---
l 20.0 I j i I (beta-mrad i I I I I I I I l(5) Noble Gas i Total Body ! O I ---
1 ---- ---
1 ---
1 0 -I ---
1 5.0 l l' l(6) Noble Gas i Skin 1 0 1 ---
l ---- ---
1 ---
l 0 1 ---
l 15.0 l
! I I I I I I I I I I I I I I I I I I I l l(7) Iodine & 1 Bone 1 3.4E-3 i Child l 700 WNW l ---
1 0.023 l ---
l 15.0 l l Particulatesi l l l l 1 l l l SUM 4ARY OF MAXIMUM POPULATION DOSES FOR UNIT 2 FROM April 1,1988 through June 30,1988 Estimated Applicable Population Dose Effluent Organ (person-rem)
(8) Liquid Total Body 0.058 (9) Liquid Bone 0.230 (10) Gaseous Total Body 0.011 (11) Gaseous Boi.e 0.01 6
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ATTACHMENT 4 4410-88-L-0142 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 and liquid effluents from TMI-2 during the second quarter reporting period of 1988.
A. Liquid-(Individual)
The first two lines present the maximum hypothetical dose to an individual.
Presented are the whole body and critical organ do:;es. Calculations are performed on the four age groups and eight organs recomended in Regulatory Guide 1.109. The )athways c~1sidered for THI-2 are drinking water, consumption of fis1, 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 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.
After 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, f
Fcr the second quarter of 1988 the calculated maximum whole body dose i received by anyone would have been 3.3E-3 mrem to an adult. Similarly, the i
maximum organ dose would have been 6.5E-3 mrem to the bone of an adult.
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 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. For the second quarter of 1988 there were no releases of noble gases from Unit 2. The doses reported on lines 3, 4, 5 and 6 are therefore zero.
.. ATTACHMENT 4 4410-88-L-0142 Page 2 of 2 The Iodines and Particulates section described in line 7 represents the maximtm exposed organ due to iodine and particulates. This does not include any plume exposure which is separated out by lines 5 and 6. The I
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doses presented in this section again reflect the maximum exposed organ for the appropriate age group.
The second quarter 1988 iodines and particulates would have resulted in a maximum dose of 3.4E-3 mrem to the bone of a child residing 700 meters ;
from the site in the WNW sector. No other organ of any age group would have received a greater dose. ;
l 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 encompassed within the region from the THI 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 distance of 50 miles around TMI. Population doses are sunned 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 5.8E-2 person-rem.
The maximum critical organ population dose to the bone was 2.3E-1 person rem. Gaseous effluents resulted in a whole body population dose of 1.1E-2 person-rem. Maximum organ population dose to the bone was 1.6E-2 person rem.