ML19353B206
| ML19353B206 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/30/1989 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML19353B121 | List: |
| References | |
| NUDOCS 8912130249 | |
| Download: ML19353B206 (9) | |
Text
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ATTACHMENT 1 4410-89-L- 0121 Page 1 of 2 EXECUTIVE SUW4ARY Three Mile Island Nuclear Station Unit 2 Effluent and Offsite Dose Report for the Period of July 1,1989 through September 30, 1989 This report sunnarizes 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 July 1 through September 30, 1989.
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 and sample analyses 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 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 TNI 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 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 l
l withdrawn from the Susquehanna River downstream of the plant is also calculated.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 Connission.
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.
8912130249 891129 gDR ADOCK 05000320 PNU
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ATTACHitENT 1 4410-89-L- 0121 Page 2 of 2 l
Liquid discharges made during the mporting period July 1 through September 30, 1989 consisted of 0.0008 curies of tritium, 0.00005 curies of strontium-90 and 0.00006 curies of cesium-137.
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 July 1 through September 30 of 1989, the maximum hypothetical calculated whole body dose to an individual due to liquid effluents from Three Mile Island Unit 2 was about 0.001 millirem.
The maximum hypothetical calculated dose to any organ of an individual was 0.002 millirem to the bone.
Airborne discharges made during this same time period consisted of 4 curies of tritium, 0.0000004 curies of cesium-137, and 0.000002 curies of 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 0.0008 millirem to the total body of a child.
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 13,000 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 and average equivalent dose from natural radon is about 50 millirem per quarter for a total of about 300 mrom per year.
The doses which could be received by the maximum hypothetical individual are each less' than 0.04 percent of the guides established by the Nuclear Regulatory Commission.
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ATTACHMENT 2 i
4410- 89-L-0121
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Page 1 of 4
.i EFFLUENT $LM%RY THREE MILE ISLAND UNIT 2 LIQUID M CA$EDUS ETFLUENTS
($U9%RY OF ALL RELEASE $)
l l
'. TYPE EFFLUENT 3RD $JARTER 1999 TOTAL I. Ligul0 EFFLUENTS:'
JULY.
tucusi SEPTEMBER 3 2 gu4RTER-A. Fl&$10N N ACTIVAll0N PRODUCTS
.nsunsee me assess esses....
l -1 (NOTINCLLOINGH-3, CASES,& ALPHA)
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1.TOTALRELEASE(Cl)
$.BE-05 2.59E-05 2.67E-05 1.06E-M l ;'
- 2. CONCENTRATION (uct/cc) 1.46E 11 7.09E 12 7.38E-12 9.6BE 12-F
,L B. TRifIUM 1.TOTALRELEASE(Cl) 3.32E-M 2.91E 04 1.37E-%
7.60E-M
- 2. CONCENTRATION (uC1/cc) 9.07E-11 7.%E 11 3.7BE 11 6.ME 11 l-C. DISSOLVED M ENTRAINED CA$ES 1.TOTALRELEASE(C1)
<LLD
<LLD 2.CONCENTRATIONuti/cc)
N/A N/A N/A N/A D. CROS$ ALPHA ACTIVITY 1.TOTALRELEASE(Cl)
<LLD
<LLD
<LLD
<LLD.
.E. VOLUME 07 NASTE RELEASED PRIORTODlLUTION'(LITERS) 7.30E+%
6.51E+04
$.16E+04 1.90E+05 F. VOLUME OF DlLUTION NATER 3.66E+09 3.66E+09 3.62E+09 1.09E+10
-(FLOWTORIVERINLITERS FROM NPDES REPORT)
C. NUMBER OF BATCH RELEASES 26 20 17 63 k
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ATTACHMENT 2 4410 89.L.0121-i o
Page 2 of 4 -
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< 1999, UNIT 2k.lSJ10RADIONUCLlDERELEASE$BYISOTOPE(CD
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. RADIONUCLlDE-JULY AUGUST SEPTEMBER 311D OuARTER 1989
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Fl5$10N A2 ACTIVAll0N PRODWCTS
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(NOTINCLW2NCALPHA,H-36 CASES.'
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TOTAL.
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ATTACHMENT 2 4410-89.L-0121 Page 3 of 4 L
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EFFLE NT $UMMARY I'
THREE MILE ISLAW UNIT 2 Ll0VID A@ CA&EOUS EFFLUENTS
($lMMARY OF ALL RELEASE $)
i' TYPE EFFLUENT -
32 QUARTER 1989 b
l-TOTAL-JULY AUGUST SEPTEMBER MD QUARTER h
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s 11.' CASE 0V$ EFFLUENT $i F-A. Fl$$10N A2 ACTIVAll0N CA&ES Y
- 1. TOTAL RELEASE (C1)
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N/A N/A N/A N/A
-S.IODINEillRELEASED(C1)
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<LLD C. PARTICULATES WITH HALF. LIVES h
>8 DAY $~
- 1. TOTAL RELEASE $ (NOT 3.59E-07
<LLD 1.$2E-06 1.88E-06 (NCLUDINGALPHA)(C1)
- 2. RELEASE RATE (uci/sec)-
1.34E-07 N/A
$.85E-07 2.36E 3. CRO$$ ALPHA RADIO-ACTIVITY (C1)
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<LLD D. TRITIUM
- 1. TOTAL RELEASE (C1) 1.%E+00 8.36E-01 1.77E+00' 4.04E+00.
- 2. RELEASE RATE (uci/sec) 5.38E-01 3.12E-01 6.81E-01 5.09E-01 E. SECO@$ IN PERIOD REPCRTED 2.6784E+06 2.6784E+06 2.5920E+06 7.9488E+06 F. NUMBER OF BATCH RELEASES -
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4410-89.L-0121 Page 4 of 4
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UNIT 2 CASEOUS RADl0WCL10E RELEASES BY 150 TOPE (C1) i p
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RADIDWCLIDE JULY AUGUST SEPTEMBER 3 2 QUARTER 1989 i
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Fl1$10N AND ACTIVAtl0N CASES i
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PARTICULATES (HALF-LIVES >0 DAYS) i t
CS 137 3.59E-07
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. TOTAL (INCLUDINGALPHA) 3.59E-07
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TOTAL (MlWS ALPHA) 3.59E-07
<LLD 1.52E-06 1.88E-06 I
3 TRITIUM (H-3) 1.44E+00 8.36E-01
.1.77E+00 4.04E+00:
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ATTACHMENT 3 4410-89-L-0121 TABLE 1 Page 1 of 3 UNIT 2-Third Quarter Dose Report SIM4ARY OF MAXIMUM INDIVIDUAL 00SES FOR UNIT 2 FROM July 1, 1989 through September 30, 1989 l
l l
l Estimated i
I Location i
1 of I
i I
l Applicable i Dose i
Age l Dist Dir l
Applicable i
Limits (area) l I Effluent i
Organ I
(area) i Group I
(m)
(toward) i Limit i 10 CFR 50 Appendix I i l
l I
I l Quarterly I Annual I Quarterly I Annual i
i i
I I
i I
i i
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I I
'3.0 l
l 0.036 1
l l(1) Liquid l Total Bo#
l 1.1E-3 l
Adult i
Receptor 1 1
l 10.0 I
1 0.020 l
l(2) Liquid i Bone i
2.0E-3 i
Child i Receptor 1 l
i 1
1 I
I l
i I
I I
i I
I I
I I
I i
I 2
1 10.0 1
l 0
1 1
1 l(3) Noble Gas i Air Dose 1
0 1
l I (gamma-arad) i l
i i
i i
l l
l 20.0 i
1 0
1 1
l I(4) Noble Gas l Air Dose 1
0 1
I I (betawared) i I
I I
I I
I i
I 5.0 I
1 0
1 1
1(5) Noble Gas 1 Total Body 1
0 1
All 1
1 15.0 l
1 0
1 1
j l(6) Noble Gas l Skin 1
0 i
All 1
I I
I i
i i
i I
I i
i I
I I
I I
I I
I i
l 15.0 I
1 5.5E-3 1 l(7) Iodine &
I Total Body I
8.2E-4 I
Child i 2300 W
I l
l Particulatesi l
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i i
i i
l l
SINIARY OF MAXIMUM POPULATION DOSES FOR UNIT 2 FR(M i
July 1, 1989 through September 30, 1989 l
Estimated Applicable Population Dose Effluent Organ (person-ren) l (8) Liquid Total Body
- 0. 01 2 (9) Liquid Bone 0.049 (10) Gaseous Tctal Body 0.026 (11) Gaseous Liver, Thyroid, Lung, 0.025 GI-LLI, Kidney l
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s ATTACHMENT 3 4410- 89-t- 0121
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Page 2 of 3 INTERPRETATI0id 0F DOSE
SUMMARY
TABLE The Dose Sumary 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 1989.
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 THI-2 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 I
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 4
resulting from the three pathways described above, the Dose Sumary Table presents the maximum whole body dose and affected age group along with the organ and associated age group that received the 1argest dose.
For the third quarter of 1989 the calculated maximum whole body dose received by anyone would have been 1.1E-3 mrem to an adult.
Similarly, the maximum organ dose would have been 2.0E-3 mrem to the bone of a child.
B.
Gaseous (Individual)
There are seven major pathways considered in the dose calculations l
for gaseous effluentt.
These aret (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 ef fluents.
Direct noble gas pitsne dose to the maximum individual is shown on lines 5 and 6.
Since no noble gases were released in the third quarter, the doses are zero.
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ATTACHMENT 3 4410-89-L-0121 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 i
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 1989 todines and particulates would have resulted in a maximum dose of 8.2E-4 mrem to the total body of a child s
residing 2300 meters from the site in the W sector. No other organ of any age group would have received a greater dose.
j C.
Liquid and Gaseous (Population 1 l
Lines 8 - 11 present the person-rem doses resulting from the liquid l
and gaseous effluents. These doses are sunned over all pathways and the affected populations.
Liquid person-rem is based upon the population encompassed within the region from the TMI outfall 1
i 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 f
effluents resulted in a whole body population dose of 0.012 person-rem. The maximum critical organ population dose to the bone was 0.049 person rem.
Gaseous effluents resulted in a whole body population dose of 0.026 person-rem. Maximum organ population dose was 0.025 person rem to the liver, thyroid, GI tract, lung and kidney.
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