ML20214Q879
| ML20214Q879 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 03/31/1987 |
| From: | Standerfer F GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 0080P, 4410-87-L-0087, 4410-87-L-87, 80P, NUDOCS 8706050236 | |
| Download: ML20214Q879 (10) | |
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- ATTACHMENT 1 Page 1 of 2 EXECUTIVE SlM4ARY Three Mile Island Nuclear Station Unit 2 Effluent and Offsite Dose Report for the Period of January 1,1987 to March 31, 1987 This re (effluents) from port Three summarizes theUnit Mile Island radioactive liquid andmaximum 2 and the calculated gaseous releases hypothetical radiation exposure to the pubite resulting from these releases.
This report covers the period of operation from January 1 to March 31, 1987.
Radiological releases from the plant are measured by installed plant monitors sampling the plant stack for gaseous releases and ifquid monitors for discharges to the Susquehanna River. These monitors provide a means for accurato detemination 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 infomation pemits the detemination 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 Day. Exposure to the public from consumption of water and fish withdrawn from the Susquehanna River downstream of the plant is also calculated.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 perfomed using a mathematical model which is based on the methods defined by the U.S. Nuclear Regulatory Commission.
The maximum hysothetical doses are conservative overestimates of the actual offsite dosos whic1 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, b b Obonn $gf b d\
ATTACHMENT 1 Page 2 of 2 Liquid discharges made during the reporting period January 1 to March 31, 1987 consisted of 0.000004 curies of tritium, 0.00003 curies of strontium-90 and unidentified beta activity, and 0.000009 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 January 1 to March 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 hypothetical calculated dose to any organ of an individual was 0.0006 millirem to the bone.
Airborne discharges made during this same time period consisted of 11 curies of tritium, 0.000008 curies of cesium 137, 0.000000002 curies of gross alpha activity, and 0.00005 curies 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 0.0009 millf rem to the lung and total body.
The maximum hypothetical whole body dose received by any individual from effluents from the Three Mlle Island Nuclear Station Unit 2 for the latest reporting period is 22000 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 Mlle 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 0.008 percent of the guides estabitshed by the Nuclear Regulatory Comi ssion.
ENE 2
- EFFLUENT SUIWEARY Page I of 4 THREE t~ILE ISLAND UNIT 2 LIQUID ANO GASEOUS EFFLUECTS (Summary of All Releases) .
TYPE EFFLUENT IST QUARTER 1987 JANUARY FEBRUARY MARCH TOTAL 1ST 00ARTER l
I. Liguid Effluent:
A. Fission and activation products (not including H-3 gases & alpha)
- 1. Total Release (Cl) (Note 1) 2.81E-5 3.07E-6 3.35E-6 3.45E-5 l
- 2. Concentration ( ,C1/cc) 6.78E-12 8.62E-13 8.23E-13 2.93E-12 l
l S. Tritium
- 1. Total release (C1) 3.69E-6 <tLD <tLD 3.69E-6
- 2. Concentration (pti/cc) 8.91 E-13 N/A N/A 3.13E-13 C. Dissolved and entrained gases
, 1. Total release (C1) N/A N/A N/A N/A
- 2. Concentration (,C1/cc) N/A N/A N/A N/A l
- 0. Gross alpha radioactivity
- 1. Total release (C1) Note 2 Note 2 Note 2 Note 2 E. Volume cf waste released prior to dilution (liters) (Note 1) 6.76E4 2.14E4 2.50E4 1.14E5 F. Volume of dilution water (flow to river in liters 3.56E9 4.07E9 1.18E10 free NPDES Report) 4.14E9 G. Numt:er of batch releases: 11 7 7 25
- 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 effluent release limits are normally 101 of the concentration values specified in 10CFR 20. Appendix B. 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 aren to any organ per year.
Note 1) Includes only those releases which were found to contain radioisotopic concentration >LLO from the Industrial Maste Stream.
Note 2)* These activities are to be verified by composite sampling.
Attcchment 2 P ge 2 cf 4 .
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EFFLUENT
SUMMARY
THREE MILE ISLAND UNIT 2 LIQUID AND EASEOUS EFFLUENTS (Continued)
(Sumary of All Releases)
TYFE EFFLUENT IST GUARTER 1987 JANUARY FEBRUARY MARCH TOTAL IST 00ARTER II. Gaseous Effluent A. Fission & activation gases <tLD <tLD <LLD <tLD
- 1. Total release (C1) N/A N/A N/A N/A
- 8. Iodine-131 released (C1): <LLD <tLD <tLD <tLD C. Particulates with half-lives
>B days:
- 1. Total releases (not including alpha)(C1) 1.54E-5 2.71E-5 1.17E-5 5.42E-5
- 2. Release rate (pC1/sec) 5.75E-6 1.12E-5 4.37E-6 6.97E-6
- 3. Gross alpha radio-activity (Ci) 2.83E-10 <LLD 1.53C-9 1.81E-9 D. Tritium
- 1. Total release (C1) 5.27E0 2.88E0 2.59E0 1.07El
- 2. Release rate (pC1/sec) 1.97E0 1.19E0 9.67E-1 1.38E0 E. Seconds in period reported 2.6784E6 2.4192E6 2.6784E6 7.7760E6 F. Number of batch releases 0 0 0 0 l
The concentration of radioactive material in gaseous ef fluents released to the unrestricted area I shall not exceed the values specified in 10CFR 20, Appendix B. Table II.
10CFR 50 dose to individual for: a) 10 mrad /yr, ganna radiation; b) 20 mrad /yr, beta radiation; and c) 15 mrem /yr to any organ.
Gaseous effluents reported are monitored at the following release points: Unit 2 Station Vent, EPICOR II Vent, Respirator Laundry and Maintenance Building, the B&W Trailer Vent Stack, and the Waste Handling and Packaging Facility.
ATTACHMENT 2 Page 3 of 4 1987 UNIT 2 LIQUID RADIONUCLIDE RELEASES BY ISOTOPE (C1)
JANUARY FEBRUARY MARCH IST OUARTER 1987 RADIDNUCLIDE Fission and activation products
<LLD <tLD <LLD <LLD (not including alpha, H-3 & gases)
<LLD <tLD <LLD <tLD Ag-110m
<LLD <LLD <LLD <LLD Ce-144
<tLD <tLD <tLD <tLD Co-58
<LLD <LLD <tLD <LLD Co -60
<tLD <LLD <LLD <LLD Cs-134 8.75E-6 <LLD <LLD 8.75E-6 Cs-137
<LLD <LLD <LLD <LLD 1-131 1.93E-5 3.07E-6 3.35E-6 2.57E-5 S r-90*
2.81E-5 3.07E-6 3.35E-6 3.45E-5 TOTAL 3.69E-6 <LLD <LLD 3.69E-6 H-3
- 1he 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 from other beta-gamma emitters which were not positively identified during conduct of analytical procedures.
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ATTACHMENT 2 UNIT 2 GASEOUS RADIONUCLIDE RELEASES BY ISOTOPE (Ci) ,
RADIONUCLIDE JANUARY FE8RUARY MARCH IST 00ARTER 1987 Fission and activation cases Kr-85 <LLD <tLD <tLD <tLD Total Particulates (half lives >B dayn Unidentified beta / gamma 1.54E-5 2.71E-5 3.56E-6 4.61E-5 Cs-137 <tLD <LLD 8.11E-6 8.11E-6 Cs-134 <LLD <LLD <LLD <LLD Gross alpha 2.83E-10 <tLD 1.53E-9 1.81E-9 -
TOTAL (including alpha) 1.54E-5 2.71E-5 1.17E-5 5.42E-5 TOTAL (minus alpha) 1.54E-5 2.71E-5 1.17E-5 5.42E-5 Tritium (3H) 5.27E0 2.88E0 2.59E0 1.07El 4
e e y
UNIT 2 ATTACHMENT 3 First Quarter Dosa Rrport Page 1 of 3 .
SUMARY OF MAXIMUM INDIVIDUAL DOSES FOR UNIT 2 FROM January 1,1987 through March 31,1987 l l Estimated l l Location I % of I Limits (arem) l l 1 10 CFR 50 Appendix I l l Applicable l Dose l Age l Dist Dir l Applicable l
Effluent l Organ I (mrem) i Group I (m) (toward) I Limit i Limits (arem) l l
l l I I I I Quarterly i Annual l Quarterly l Annual l I I I I l l i I I I l Total Body 2.3E-4 Adult l Receptor 1 ---
l 7.6E-3 l ---
l 3.0 l 1(1) Liquid 1 1 l 10.0 l(2) Liquid l Bone 1 6.2E-4 l Adult i Receptor 1 1 l 6.2E-3 1 ---
l l I I I I I I 1 I I I I I l l l l l l I I 0 ---- --- I ---
l 0 1 ---
l 10.0 l l(3) Noble Gas ! Air Dose 1 l --- I l l l l (gamma-mrad) I i l l i l 20.0 0 ---
l ---
l 0 l ---
l l l(4) Noble Gas l Air Dose 1 1 ---
I ----
l l l l l l l (beta-mrad l l l 0 l ---
l 5.0 l l Total Body 0 1 --- 1 ---- ---
1 ---
l l(5) Noble Gas l l 0 1 ---
l 15.0 l l(6) Noble Gas l Skin 1 0 l ---
1 ---- ---
1 i l i i l i l l 1 I I I I I I l l I I I 9.0E-4 Teen 630 ESE ---
l 6.0E-3 l ---
l 15.0 l l(7) Iodine & l Lung l i 1 l l l l l l Particulatesi l l I l SUMARY OF MAXIMUM POPULATION DOSES FOR UNIT 2 FROM January 1,1987 through March 31,1987 Estimated l
Applicable Population Dose Effluent Organ (person-rem)
(8) Liquid Total Body 3.1E-3 (9) Liquid Bone 0.01 3 (10) Gaseous Total Body 0.01 7 (11) Gaseous Lung 0.01 8
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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 first 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 ef fluents. 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 i maximum whole body dose and affected age group along with the organ and
- associated age group that received the largest dose.
For the first 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 6.2E-4 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 i 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 l (compass point) where the theoretical maximum plume exposure occurred. It i 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 l
and 6. For the first quarter of 1987 there were no releases of noble gases j from Unit 2. The doses reported on lines 3, 4, 5 and 6 are therefore zero.
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' ATTACHMENT 3 Page 3 of 3 The lodines and Particulates section described in line 7 represents the maximum exposed organ due to iodine and particulates. 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 first quarter 1987 iodines and particulates would have resulted in a maximum dose of 9.0E-4 mrem to the lung of a teen residing 630 meters from the site in the ESE sector. No other organ of any age group would have received a greater dose, i
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 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 first quarter, liquid effluents resulted in a whole body population dose of 3.1E-3 person-rem.
The maximum critical organ population dose to the bone was 1.3E-2 person rem. Gaseous effluents resulted in a whole body population dose of 1.7E-2 person-rem. Maximum organ population dose to the lung was 1.8E-2 person-rem.
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o GPU Nuclear Corporation NggIg7 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-0087 Document ID 0080P May 29, 1987 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 - First Quarter 1987 Per 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 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, j 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 resulting from TMI-2 activities. Doses were extracted from calculational models and represent the bounding dose for all cases. The reporting period includes January 1, 1987, through March 31, 1987.
Sincerely, l'
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F. R. Standerf r Director, TMI-2 FRS/CJD/eml Attachments /b l
cc: Regional Administrator, Region 1 - W. T. Russell I
Director, TMI-2 Cleanup Project Directorate - Dr. W. D. Travers i l
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation