ML20236U725
| ML20236U725 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 09/30/1987 |
| From: | Standerfer F GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 4410-87-L-0176, 4410-87-L-176, NUDOCS 8712030321 | |
| Download: ML20236U725 (10) | |
Text
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ATTACHMENT 1 Page 1 of 2 t.XECUTIVE
SUMMARY
Three Mile Island Nuclear Station Unit 2 Effluent and Offsite Dose Report for the Period of July 1,1987 to September 30, 1987 This report summarizes the radioactive l' quid and gaseous releases ;
(effluents) from Three Mile Island Unit 2 and the calculated maximum {
hypothetical radiation exposure to the public resulting from these releases, j This report covers the period of operation from July 1 to September 30, 1987. I 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 j 1
released to the environment.
Calculations of the maximum hypothetical dose tn 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 Exposure to the public from consumption of water and fish withdrawn from the Susquehanna River downstream of the plant is also calculated.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 i 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 f 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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8712030321 870930 \ ('
PDR ADOCK 05000320 R PDR p\(D >
i ATTACHMENT 1 Page 2 of 2 (
Liquid discharges made during the reporting period July 1 to September 30, ,
1987 consisted of 0.0009 curies of tritium, 0.00002 curies of strontium-90 and '
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unidentified beta activity and 0.00001 curies of cesium-137. Unidentified beta activity is treated as strontium-90 for the purpose of dose calculations. 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 flowed past the ,
plant during the same time period. l l
During the reporting period July 1 to September 30 of 1987, the maximum I 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 0.0005 millirem j j
to the bone. j Airborne discharges made during this same time period consisted of 7 curies of tritium, 0.00000004 curies of gross alpha activity, 0.0000008 curies of cesium 137, 0.0000002 curies of strontium 90 and and 0.000003 curies of unidentified beta activity. Unidentified beta activity is, as with liquid effluents, conservatively assumed to be 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.
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 11000 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. In addition, average equivalent dose from natural radon is about 90 millirem per quarter.
The doses which could be received by the maximum hypothetical individual are at most 0.02 percent of the guides established by the Nuclear Regulatory Commission.
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ATTACHMENT 3 Page 2 of 3 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 third quarter reporting period of 1987.
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 TMI are drinking water, 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 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. I For the third quarter of 1987 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 5.3E-4 mrem to the bone of an adult.
i 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 i and 6. For the third quarter of 1987 there were no releases of noble gases l from Unit 2. The doses reported on lines 3, 4, 5 and 6 are therefore zero.
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.. ATTACHMENT 3 .
I
- Page 3 of 3 The Iodines and Particulatts s:ction described in line 7 represents the l 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 third quarter 1987 iodines and particulate would have resulted in a maximum dose of 3.1E-3 mrem to the bone of a child residing 750 meters from the site in the ENE 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 liauid 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 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 distance of 50 miles around TMI. Population doses are summed over all distances and sectors to give an aggregate dose.
Based upon the calculations performed for the third quarter, liquid effluents resulted in a whole body population dose of 9.3E-3 person-rem.
The maximum critical organ population dose to the bone was 3.7E-2 person rem. Gaseous effluents resulted in a whole body population dose of 7.1E-2 person-rem. Maximum organ population dose to the lung, GI, thyroid, liver, and kidney was also 6.7E-2 person-rem.
_ _. ________-___m
l GPU Nuclear Corporation
! Nuclear ::::=s B 480 Middletown, Pennsylvania 17057-0191 717 944 7621 TELEX 84 2386 Wnter's Direct Dial Number:
(717) 948-8461 November 25, 1987 4410-87-L-0176/0080P US Nuclear Regulatory Commission l Attn: Document Control Desk Washington, DC 20555
Dear Sirs:
Three Mile Island Nuclear Station, Unit 2 (TMI-2)
' Operating License No. DPR-73 Docket No. 50-320 Quarterly Dose Assessment Report - Third Quarter 1987 Per Section 5.6.1.C of Appendix B to the Recovery Technical Specification, the cuarterly report of radiological releases and estimated doses is submitted.
Attachment 1 is an executive summary of TMI-2 effluents and doses reported in Attachments 2 and 3. Attachment 2 presents a summary of releases including estimates of total activity and the time rate of release of each nuclide.
Attachment 3 is a dose summary table which provides a summary of the maximum hypothetical and/or real doses to individuals and the general population i resulting from TMI-2 activities. Doses were extracted from calculational I nodels and represent the bounding dose for all cases. The reporting period includes July 1, 1987, through September 30, 1987.
Dose summaries for the previous quarters of the 1987 calendar year were submitted via GPU Nuclear letters 4410-87-L-0087 dated May 29, 1987, and 4410-87-L-0132 dated August 28, 1987. ,
Sincerely, F. R. Standerfer Director, TMI-2 DHW/eml Attachments cc: Regional Administrator, Region 1 - W. T. Russell Direc ar, TMI-2 Cleanup Project Directorate - Dr. W. D. Travers I I GPU Nuclear Corporation is a subsidiary of the General Pubhc Utikties Corporation t I L
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