ML20212F481

Forwards Executive Summary,Dose Assessment Rept for Fourth Quarter 1986, Effluent & Waste Disposal Semiannual Rept, Jul-Dec 1986 & Third Quarter 1986 Joint Frequency Tables

ML20212F481
Person / Time
Site:	Three Mile Island
Issue date:	02/27/1987
From:	Standerfer F GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20212F485	List: ML20212F481 ML20212F521 ML20212F596 ML20212F626
References
RTR-REGGD-01.109, RTR-REGGD-1.109 0080P, 4410-87-L-0031, 4410-87-L-31, 80P, NUDOCS 8703050098
Download: ML20212F481 (4)

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GPU Nuclear Corporation ggIgf Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057-0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:

(717) 948-8461 4410-87-L-0031 Document ID 0080P February 27, 1987 US Nuclear Regulatory Commission 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 1986 Semi-Annual Radioactive Effluent Release Report Per the requirements of Section 5.6.1.C of Appendix B to the Recovery Technical Specifications, the quarterly 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 listing estimates of total activity and the time rate of release of each nuclide. Attachment 3 is the Dose Summary 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 Summary Table. Doses were extracted from calculational models and represent the bounding dose for all casas. The reporting period includes October 1, 1986 through December 31, 196d.

Also enclosed as Attachment 5, in accordance with the requirements of 10 CFR 50.36a(a)(2), is the Radioactive Effluent Release Reports for TMI-2. Table 1B, " 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. Attachment 6 presents the Joint Frequency Tables for TMI-2. These reports cover the period July 1, 1986 through December 31, 1986.

870305g{[5 PDR A PDR 20 R t}D, GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation l Llf

Document Control Desk Feb u ry 27, 1987-4410-87-L-0031-Dose summaries and effluent releases for the previous quarter of the 1986 calendar year were submitted via GPU Nuclear letters 4410-86-L-0088 dated May 30, 1986; 4410-86-L-0148 dated August 26,1986; and 4410-86-L-0199 dated November 26, 1986.

Sincerel ,

i F. R. Standerfer e en rector, NI-2 FRS/CJD/eml Attachments cc: Regional Ad;ninistrator, Region 1 - Dr. T. E. Murley Director - TMI-2 Cleanup Project Directorate, Dr. W. D. Travers l

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. ATTACHMENT 1-

, u: 4410-87-L-0031 '

Page 1 of 2 EXECUTIVE SU M RY Three Mile Island Nuclear Station Unit 2 Effluent and Offsite Dose Report for the Period of October 1,1986 to December 31, 1986 This report sununarizes the radioactive liquid and gaseous releases

.(effluents) from Three Mile Island Jnit 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, 1986.

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.

i Calculations of the maximum hypothetical dose to an individual and the total population around Three !iile 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 pennits the determination of both the direction in which the release traveled and the' dispersion of i 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 i-effluent data are used to calculate a maximum hypothetical dose to an individual l

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 Piver 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 removal, or removal during processing by water companies prior to distribution and consumption.

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ATTACHMENT 1

< - 4410-87-L-0031 Page 2 of 2 Liquid discharges made during the reporting period October 1 to December 31, 1986 consisted of 0.0003 curies of tritium, 0.00004 curies of strontium-90 and unidentified beta activity. 0.0000004 curies of cesium-134, and 0.00003 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 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 to December 31 of 1986, the maximum hypothetical calculated whole body dose to an individual due to liquid effluents from Three Mile Island Unit 2 was about 0.0005 millirem. The maximum hypothetical calculated dose to any organ of an individual was 0.001 millirem to the bone.

Airborne discharges made during this same time period consisted of 0.28 curies of krypton-85,17 curies of tritium, 0.0000001 curies of cesium-137, 0.0000004 curies of gross alpha activity, and 0.00002 curies of strontium 90 and 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 i reporting periods. 0.03 curies of xenon-133 originating in Unit 1 were also released through Unit 2.

Noble gas releases for the period are calculated to produce 0.0000004 mrem to the total body and 0.00005 mrem skin doses to the maximum individual.

Airborne particulates are calculated to produce about 0.003 millirem to the bone of the maximum hypothetical individual.

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 tines 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 j the Three Mile Island area. In addition, average equival.ent 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 i Comission.

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