ML20147D417
| ML20147D417 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/29/1988 |
| From: | Standerfer F GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20147D425 | List: |
| References | |
| 4410-88-L-0027, 4410-88-L-27, NUDOCS 8803040020 | |
| Download: ML20147D417 (4) | |
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GPU Nuclear Corporation MNuclear m's=!=8o Middletown, Pennsytvania 17057-0191 717 944 7621 TELEX 84 2386 Wnter's Direct Dial Number; (717) 948-8461 February 29, 1988 4410-88-L-0027/0080P US Nuclear Regulatory Commission 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 - Fourth Quarter 1987; Semi-Annual Radioactive Effluent Release Report Per the requirements of Section 5.6.1.C of Appendix B to the Recovery Technical Specification, the quarterly report of radiological releases and estimated doses is submitted. Attachment 1 is an executive summary of TMI-2 erfluents and doses reported in Attachments 2 and 3.
Attactraent 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 Sunmary Table which provides a summary of the maximum hypothetical and/or real doses to individuals and the general population resulting from TMI-2 activities. Attachment 4 is an interpretation of the Dose Sumary Table. Doses were extracted from calculational models and represent the bounding dose for all cases. The reporting period includes October 1,1987, through December 31, 1987.
Also enclosed as Attachment 5, in accordance with the requirements of 10 CFR 50.36a(a)(2), is the Radioactive Effluent Release Report for TMI-2. Table 18, "Effluent and Waste Disposal Semi-Annual Report, Gaseous Effluent-Elevated Releases," is not included as release paths at TMI-2 do not meet Regulatory Guide 1.109 definition of an elevated release. Attachnent 6 presents the Joint Frequency Tables for TMI-2. These effluents reports cover tN period July 1, 1987, through December 31, 1987.
8803040020 880229 PDR ADOCK 05000320 R
DCD GPU Nuclear Corporation is a subsidiary of the General Pubhc Utihties Corporation f/
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- Document-Contt01 Desk _ February 29,' 1988 Z-f '#
-4410-88-L-0027_~
Dose summaries._and effluent releases for the previous quarters of the-1987 calendar year were submitted via PU Nuclear letter 4410-87-L-0087, dated May 29,1987; 4410-87-L-0132, dated August 28, 1987; 4410-87-L-0148 (Update),
dated October 1, -1987; and 4410-87-L-0176, dated November 25, 1987.
Sincerely,-
F. R. Standerfer Director, TMI-2 DHW/ emf Attactinents cc: Regional Administrator, Region 1 --W. T. Russell Director, TMI-2 Cleanup Project Directorate - Dr. W. D. Travers I
'6 ATTACHMENT 1 Page 1 of 2 EXECUTIVE SUM 4ARY Three Mile Island Nuclear Station Unit 2 Effluent and Offsite Dose Report.
for the Period of October 1,1987 to December 31, 1987 Tnis report sumarizes 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 October 1 to December 31,.1987.
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 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 meade 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 river water by precipitation of insoluble salts, absorption onto river sediment, biological remon1, or removal during processing by water companies prior to distribution and consumption.
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ATTACHMENT 1
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Page 2 of 2 Liquid discharges made during the reporting period October 1 to December 31, l
1987 consisted of 0.0003 curies of tritium, 0.00002 curies of strontium-90 and unidentified beta activity and 0.000006 curies of cesium-137. Unidentified beta activity is treated as strontium-90 for the purpose of dose calculations.
These l
release rates and quantities are consistent with results of previous quarters.
The quantities of each radionuclide released are actually up to 1 million times 5
smaller than the nonna11y existing environmental quantities that flowed past the plant during the same time period.
During the reporting period October 1 to December 31 of 1987, 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 l
hypothetical calculated dose to any organ of an indivioual was 0.0005 millirem to the bone.
Airborne discharges made during this same time period consisted of 3 curies of tritium, 0.00000006 curies of gross alpha activity, 0.000007 curies of cesium 137, 0.0000001 curies of cesium 134, and 0.000004 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 l
effluents was about 0.0007 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 40000 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 50 millirem per quarter.
The doses which could be received by the maximum hypothetical individual are at most 0.006 percent of the guides established by the Nuclear Regulatory Commission.
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