ML20247R715
| ML20247R715 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/31/1989 |
| From: | Roche M GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8906070294 | |
| Download: ML20247R715 (10) | |
Text
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GPU Nuclear Corporation g
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Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057-0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
(717) 948-8400 May 30,1989 4410-89-L-0063/0080P 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 Update - First Quarter 1989 Per Section 5.6.1.C of Appendix B to the Recovery Technical Specifications, the ouarterly report of radiological releases and estimated doses is submitted. is an executive summary of THI-2 effluents and doses reported in Attachments 2 and 3. presents a summary of releases including estimates of total activity and the time rate of release of each nuclide. 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 through March 31, 1989.
Sincerely, hb M. B. Roche Director, TMI-2 EDS/ emf cc:
F. I. Young - Senior Resident Inspector, TMI W. T. Russell - Regional Administrator, Region I i
l-J. F. Stolz - Director, Plant Directorate I-4 I
L. H. Thonus - Project Manager, TMI Site B906070294 890331 ADOCK0500gO g
DR I
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
U, ATTACHMENT 1
)
4410-89-L-0063
)
j-2; Page 1 of 2 EXECUTIVE
SUMMARY
Three Mile Island Nuclear Station Unit 2 Effluent and Offsite Dose Report
.)
for the period of January 1, 1989 through March 31, 1989 l
l This report summarizes 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 January 1 through March 31, 1989.
Radiological releases from the' plant are measured by installed plant monitors L
sampling the plant stack for gaseous releases and liquid monitors for discharges to the Susquehanna River. These monitors and sample results 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 maximmn 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 maximmm 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 removal, or removal during processing by water ecmpanies prior to distribution and consumption.
ATTACHMENT 1 4410-89-L-0063
~
Page 2 of 2 Liquid discharges made during the reporting period January 1 through March 31, 1989 consisted of 0.000001 curies of tritium, 0.00001 curies of strontium-90 and 0.00005 curies of cesium-137. 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.
During the reporting period January 1 through March 31 of 1989, the maximum hypothetical calculated whole body dose to an individual due to liquid effluents from Three Mile Island Unit 2 was about 0.0006 millirem. The maximum hypothetical calculated dose to any organ of an individual was 0.0009 millirem to the bone.
Airborne discharges made during this same time period consisted of 3 curies of tritium, and 0.00000007 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 0.0002 millirem to the bone of a teenager.
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 110,000 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 mrem per year.
The doses which could be received by the maximum hypothetical individual are each less than 0.02 percent of the guides established by the Nuclear Regulatory Commission.
ATTACHMENT 2 4410-89-L-0063 Page 1 of 4 EFFLUENT
SUMMARY
THREE MILE ISLAND UNIT 2 LIQUID AND GASEOUS EFFLUENTS (SUPMARY OF ALL RELEASES)
TYPE EFFLUENT IST QUARTER 1989 TOTAL I. L10UID EFFLUENTS:
JANUARY FEBRUARY MARCH IST QUARTER A. FISSION AND ACTIVATION PRODUCTS.
=
(N7f INCLUDING H-3, GASES, & ALPHA) 1.TOTALRELEASE(C1) 2.25E-05 5.68E-%
2.94E-05 5.76E-05
- 2. CONCENTRATION (uC1/cc) 5.19E-12 1.29E-12 6.45E-12 4.33E-12 B. TRITIUM
- 1. T7fAL RELEASE (C1) 1.45E-06
<LLD G
1.45E-06
- 2. CONCENTRATION (uci/cc) 3.35E-13 N/A N/A 1.09E-13 C. DISSOLVED AND ENTRAINED GASES 1.TOTALRELEASE(C1)
<LLD
<LLD
<LLD G
- 2. CONCENTRATION (uC1/cc)
N/A N/A N/A N/A D. GROSS ALPHA ACTIVITY
- 1. TOTAL?,ELEASE(Ci)
<LLD G
<LLD
<LLD E. VOLUME OF WASTE RELEASED PRIOR TO DILUTION (LITERS) 3.91E+04 2.64E+04 3.87E+04 1.04E+05 F. VOLUME OF DILUTION WATER 4.34E+09 4.42E+09 4.56E+09 1.33E+10 (FLOW TO RIVER IN LITERS FROM NPDES REPORT)
G. NUMBER OF BATCH RELEASES 17 12 16 45
(.
e-ATTACHMENT 2-a
- s 4410-89-L-0063 Page 2 of 4 1989 UNIT 2 LIQUID RADIONUCLIDES RELEASES BY ISOTOPE (C1)
RAD 10NUCLTDE
- JANUARY FEBRUARY MARCH IST QUARTER 1989 FISSION AND ACTIVATION PRODUCTS (NOT INCLUDING ALPHA, H-3 & GASES)
G-GLD GLD GLD i
AG-110M G
G GLD GLD CE-144 G
GLD GLD GLD CO-38 GLD G
GLD CLD CD-60 GLD GLD GLD GLD I,
CS-134 GLD -
GLD CLD GLD CS-137 1.78E-05 2.51E-06 2.48E-05 4.51E-05 I-131 G-
<LLD GLD GLD SR-90 4.69E-%
3.17E-06 4.64E-06 1,25E-05 TOTAL.
2.25E-05 5,6BE-06 2.94E-05 5.76E-05 H-3 1.45E-06 GLD GLD 1.45E-06 i
l 1
1 3
i
'l l
l
l ATTACHMENT 2 I
4410-89-L-0063 Page 3 of 4 EFFLUENT SUPEARY
-THREE MILE ISLAND UNIT 2 LIQUID AND GASEOUS EFFLUENTS
(
SUMMARY
OFALLPEEASES)
. TYPE EFFLUENT IST DUARTER 1989 TOTAL JANUARY FEBRUARY MARCH IET QUARTER
====_____
a2 -
r---
__=
_ _ _ _ = - - - -
II. GASEOUS EFFLUENTb:
A. FISSION AND ACTIVATION GASES 1.TOTALRELEASE(C1)
G G
G G
2.RELEASERATE(uci/sec)
N/A N/A N/A N/A B. IODINE 131 RELEASED (C1)
G G
G G
C. PARTICULATE WITH HALF-LIVES
>S DAYS
- 1. TOTAL RELEASES (NOT 7.13E-08 G
G 7.13E-08 INCLUDINGALPHA)(C1) 2.RELEASERATE(uCi/sec) 2.66E-08 N/A N//
9.17r:-09
- 3. GROSS ALPHA RADIO-ACTIVITY (C1) 1.76E-07 G
<LLD 1.76E-07 D. TRITIUM 1.TUTALRELEASE(C1) 9.37E-01 3.57E-01 1.26E+00 2.55E+00 2.RELEASERATE(uC1/sec) 3.50E-01 1.48E-01 4.70E-01 3.28E-01
.E. SECONDS IN PERIOD REPORTED 2.6784E+06 2.41s2E+06 2.6784E+06 7.776Ct G F. NUMBER OF BATCH RELEASES 0
0 0
0
__-__m________________.___m___
__i
'I
ATTACMENT 2 4410-89-L-0063 Page.4 of 4 UNIT 2 CASE 00S RADIONUCLIDES RELEASES BY ISOTOPE (C1)
RADICDCLIDE JANUARY FEBRUARY MARCH IST QUARTER 1989 FISSI C AND ACTIVATION GASES KR-85 GLD G
GLD CLD n
TUI'AL
.PhRTICULATES (HALF-LIVES >B DAYS)
CS-137 GLD
<LLD CLD s
CS-134 GLD CLD GLD GLD SR/Y-90 7.13E-08 GLD
<LLD 7.13E 08 GROSS ALPHA 1.76E-07
<LLD GLD 1.76E-07 TOTAL (INCLUDING ALPHA) 2.48E-07
<LLD
<LLD 2.48E-07 TOTAL (MINUSALPHA) 7.13E-08
<LLD
<LLD 7.13E-08
_=
TEITIUM (H-3)-
9.37E-01 3.57E-01 1.26E+00 2.55E+00 l
l'
l:
I ATTACHMENT 3 4410-89-L-0063 Page 1 of 3 l
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 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 TMI-2 are drinking water, consumption of fish, and standing on the choreline 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 discharT-After calculating the doses to all age groups for all eight organs resulting from the three pathways dercribed above, the Dose Summary Table presents the maximum whole body dose and atfected age group along with the organ and associated age group that received the largest dose.
For the first quarter of 1989 the calculated maximum whole body dose received by anyone would have been 5.6E-4 mrem to an adult. Similarly, the maximum organ dose would have been 9.2E-4 mrem to the bone of a child.
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 maximwm 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 and 6.
Since no noble gases were released in the first quarter, the doses are zero.
ATTACHMENT 3 4410-89-L-0063 Page 2 of 3 The Iodines cnd Particulate section described in line 7 represents the 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 first quarter 1989 iodines and particulate would have resulted in a maximum dese of 2.5E-4 mrem to the bone of a teen residing 70C meters from the site in the E 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 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 l
'1980 population end consider the population out to a distance of 50 miles around TMI.
Population doses are summe6 over all distances and sectors to give an aggregate dose.
Based upon the calculations performed for the first querter, liquid effluents resulted in a whole body population dose of 2.1E-3 person-rem.
The maximum critical organ population dose to the bone was 8.0E-3 person rem. Gaseous effluents resulted in a whole body population dose of 2.7E-3 person-rem. Maximum organ population dose to the liver was 3.GE-3 person rem.
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