ML20195J897
| ML20195J897 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 09/30/1988 |
| From: | Roche M GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| References | |
| NUDOCS 8812050087 | |
| Download: ML20195J897 (12) | |
Text
a ATTACHMENT 1 4410-88-L-0184 go 1 f2 EXECUTIVE
SUMMARY
Three Mile Island Nuclear Station Unit 2 i Effluent and Offsite Dose Report for the Period of July 1,1988 to September 30, 1988 This report summarizes the radioactive 117 4 and gaseous releases .
(effluents) from Three Mile Island Unit 2 ar.1 th calculated maximum ;
hypothetical radiation exposure to the public resulting from these releases.
This report covers the period of operation from July 1 to September 30, 1988.
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 l released to the environment. i i
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 l 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withdrawn from the Susquehanna River downstream of the plant is also calculated.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 t 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 likoly 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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DR ADOCK0500fg2O
'. ATTACHMENT 1 4410-88-L-0184 Page 2 of 2 Liquid discharges made during the reporting period July 1 to September 30, 1988 consisted of 0.001 curies of tritium, 0.0001 curies of strontium-90 and unidentified beta activity, and 0.00009 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 July 1 to September 30 of 1988, 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 0.003 millirem to the bone. 1 Airborne discharges made during this same time period consisted of 3 curies of tritium, 0.00000003 curies of cesium-137, 0.4 curies of krypton-85, and 0.00002 curies of unidentified beta activity. Unidentified beta activity is, as ,
with liquid effluents, conservatively assumod to be entirely strontium-90 . ;
These release rates and quantities are also consistent with the results from l previous reporting periods. The maximum hypothetical dose to an individual due to gaseous effluents was about 0.009 millirem to the bone of a child. i 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 7800 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 i about 50 millirem per quarter for a total of about 300 mrem per year, i The roses which could be received by the maximum hypothetical individual are at most 0.1 percent of the guides established by the Nuclear Regulatory Commission.
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Attacnment i ATTACHMENT 2 4410-88-L-018.4' EFFLUECT
SUMMARY
Page 1 of 4 THREE MILE ISLAND UNIT 2 LIQUID AND GASEOUS EFFLUENTS ,
(Summary of All Releases) .
TYPE EFFLUENT JULY AUGUST SEPTEMBER 3rd QUARTER 1988 I. Liquid Effluent:
A. Fission and activation products (not including H-3, gases & alpha)
- 1. Total Release (C1) (Note 1) 9.47E-5 8.78E-05 2.75E-05 2.10E-4
- 2. Concentration (pC1/cc)(Note 1) 1.81E-11 1.63E-11 6.20E-12 1.39E-11
- 8. Tritium
- 1. Total release (C1) 5.33E-04 4.50E-04 1.15E-04 1.10E-3
- 2. Concentration (pC1/cc) 1.02E-10 8.35E-11 2.60E-11 7.29E-11 C. Dissolved and entrained gases
- 1. Total release (C1) <LLD <tLD <LLD <LLD
[
- 2. Concentration (pCi/cc) N/A N/A N/A N/A D. Gross alpha activity
- 1. Total release (C1) (Note 2) <LLD <tLD <LLD <LLD E. Volume of waste released prior to dilution ('t~crs) (Note 1) 9.75E+04 1.12E+05 5.11E+04 2.61E+5 F. Volume of dilution water (flow to river in liters from NPDES Report) 5.23E+9 5.39E+9 4.44E+09 1.51E+10 G. Number of batch releases: 3.40E+01 3.70E+01 1.90E+01 9.00E+1
- The concentration of radioactive materia? Other than dissolved or entrained noble gases in liquid ef fluent released to l the unrestricted area shall not exceed the values specified in 10CFR 20. Appendix 8. Table II.
- Present liquid ef fluent release limits are 10% of the concentration values specified in 10CFR 20, Apper. dix 8. Table II.
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- Liquid ef fluent releases are also limited to 10CFR 50, Appendix I, net to exceed a dose of 3 mrem total body and 10 !
mrem to any organ per year.
Note 1) Includes only those releases which were found to contain radioisotopic concentration >LLD from the industrial waste stream.
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Note 2) lhese activities are to be verified by composite sampling.
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' ATTACHMENT 2' 4410-83-L-0184
. 1988 EFFLUEDT
SUMMARY
Page 2 of 4 .
THREE MILE ISL'.NO UNIT 2 LIQUID AND GASEOUS EFFLUENTS (Continued) *
(Summary of Alt Releases) .
1YPE EFFLUENT JULY AUGUST SEPTEM8ER 3rd QUARTER 1988
- 11. Gaseous Effluent A. Fission & activation gases
- 1. Total release (C1) <tLD 2.34E-01 1.31E-1 3.65E-1 ,-
- 2. Release rate (pC1/sec) N/A 8.74E-2 5.05E-2 4.59E-2
- 8. Iodir.e-131 released (C1): <LLD <tLD <LLD <LLD C. Particulates with half-lives
>8 days:
- 1. Total releases (not including alpha)(C1) 3.2SE-6 6.91E-6 5.48E-6 1.57E-5
- 2. Release rate (pti/sec) 1.21E-6 2.59E-6 2. lie-5 1.97E-6
- 3. Gross alpha radio-activity (C1) 6.72E-9 4. 66E- 9 3.01E-9 1.44E-8 D. Tritium
- 1. Total release (Cl) 7.91E-1 1.64E+0 9.57E-1 3.38E+0
- 2. Release rate (pC1/sec) 2.95E-7 6.11E-7 3.69E-7 4.26E-7 E. Seconds in period reported 2.678E+06 2.6784Et06 2.5920E+06 7.9488E+06 F. Number of batch releases 0 0 0 0 The concentration of radioactive material in gaseous effluents released to the unrestricted area shall no*. exceed the values specified in 10CFR 20, Appendix 8. Table II.
10CFR 50 dose to individual for: a) 10 mrad /yr, gamma radiation; b) 20 mrad /yr, beta radiation; and c) 15 mres/yr to any organ.
. . _. - . . _ , _. - - , _ , . _ . . .._ ___ .- - _ - ~ -
ATTACliMENT 2 4410-88-t-018d Page 3 of 4 1988 UNIT 2 LIQUID RADIONUCLIDE RELEASES SY ISOTOPE (C1) -
s RADIONUCLIDE JblY AUGUST SEPTEMBER 3rd QUARTER 1988 fission and activation products (not including alpha. H-3 & gases) <tLD <LLD <LLD <LLD Ag-110m <LLD <LLD <LLD <LLD Ce-144 <LLD <tLD <LLD <LLD Co-58 <LLD <tLD <LLD <LLD Co-60 <tLD <LLD <tLD <LLD Cs-134 <LLD <LLD <LLD <LLD Cs-137 3.74E-5 4.09E-5 1.47E-5 9.30E-5 I-131 <LLD <LLD <LLD <LLD S r-90* 5.74E-5 4.69E-05 1.28E-05 1.17E-4 TOTAL 9.47E-5 8.78E-05 2.75E-05 2.10E-4 H -3 5.33E-04 4.50E-04 1.15E-04 1.10E-3
- The 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 4410-88,L-0184 Page 4 of 4 ,
1988 UNIT 2 GASEOUS RADIONUCLIDE RELEASES 8Y ISOTOPE (C1) ,
RADIONUCLIDE JULY AUGUST SEPTEM8ER 3rd QUARlER 1988 iission and activation gases K r-85 <LLD 2.34E-1 1.31E-1 3.65E-1 lotal Prrticulates (half lives >8 days)
Unidentified beta / gamma 3.23E-6 6.89E-6 5.48E-6 1.56E-5 Cs-137 1.41E-08 1.35E-8 <LLD 2.76E-8 Cs-134 <LLD <tLD <LLD <LLD I-131(Unit-1 origin) <LLD <tLD <LLD <lLO Gross alpha 6.72E-9 4.66E-9 3.01E-9 1.44E-8 TOTAL (including alpha) 3.26E-6 6.91E-6 5.48E-6 101AL (minus alpha) 1.57E-5 3.25E-6 6.91E-6 5.48E-6 1.57E-5 1ritlum (3H) 7.91E-1 1.64E0 9.57E-1 3.38E+0
ATTACHMENT 3 4410-88-L-0184 Page 1 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 third quarter reporting period of 1988.
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 recomended 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 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 maximum whole body dose and affected age group along with the organ and associated age grcup that received the largest dose.
For the third quarter cf 1988 the calculated maximum whole body dose received by anyone would have been 1.4E-3 mrem to an adult. Similarly, the maximum organ dose would have been 2.9E-3 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) neat, 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 effluents.
Direct noble gas plume dose to the maximum individual is shown on lines 5 and 6. For the third quarter of 1988, the noble gas individual doses are from krypton-85 releases as a result of plasma arc cutting in the reactor vessel. The calculated maximum whole body dose to an individual would ha.'e been 2.2E-7 mrem. The calculated maximum dose to the skin would have been 2.6E-5 meen.
. ATTACHMENT 3 4410-88-L-0184 Page 2 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, i
The third quarter 1988 fodines and particulates would have resulted in a maximum dose of 8.8E-3 mrem to the bone of a child residing 700 meters from the site in the WNW sector. No other organ of any age group would have received a greater dose.
C. Liquid and Gaseous (Populationi 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 sumed over all distances and sectors to give an aggregate dose.
Based upon the calculations performed for the third quarter, liquid effluents resulted in a whole body population dose of 0.059 person-rem.
The maximum critical organ population dose to the bone was 0.27 person rem. Gaseous effluents resulted in a whole body population dose of 0.037 person-rem. Maximum organ population dose to the bone was 0.053 person rem.
ATTACHMENT 3-
- 4410-88-L-0184.
UNIT 2 Page -3 of 3 Third Quarter Dose Report ..-
SUtMARY OF MAXIMUM INDIVIDUAL DOSES FOR UNIT 2 FROM July 1, 1988 through September 30, 1988 l 1 1 Estimated l l Location l % of I l l l Applicable i Dose 1 Age 1 Dist Dir i Applicable I Limits (arem) .1 1 Effluent i Organ I (mrem) i Group I (m) (toward) l Limit i 10 CFR 50 Appendix I l l 1 1 I I I Quarterly I Annual I Quarterly I Annual l I I I I I I I I I i 1(1) Liquid i Total Body 1 1.4E-3 l Adult 1 Receptor 1 1 ---
1 0.045 l ---
l 3.0 1 '
l(2) Liquid i Bone i 2.9E-3 1 Adult i Receptor 1 ! --
l 0.029 l ---
l 10.0 [
l i I i i i I I i 1 ,
I I I I I I I I I l '
l(3) Noble Gas ! Air Dose 1 1.8E-6 1 ---
l 2413 WNW l ---
l 1.8E-5 l ---
l 10.0 l l 1 (gassa-arad) i I I I I I I i 1(4) Noble Gas i Air Dose 1 2.lE-4 l ---
1 2413 WNW l --
l 1.0E-3 l ---
l 20.0 1 1 I (beta-arad i I I I I I I i 1(5) Noble Gas i Total Body 1 2.2E-7 i All I 1130 NNE l ---
l 4.3E-6 l ---
1 5.0 l l(6) Noble Gas l Skin i 2.6E-5 l All I 1130 NNE l ---
l 1.7E-4 1 ---
l 15.0 I I I I I I I I I I I
I l.- 1 I I I I I I i 1(7) Iodine & lt Bone 1 8.8E-3 1 Child 1 700 WWW I ---
1 0.059 l ---
l 15.0 l Particulates! l l 1 I l l l l l
SUfeARY OF MAXIMUM POPULATION DOSES FOR UNIT 2 FROM July 1,1988 through September 30, 1988 Estimated Applicable Population Dose Effluent Organ (person-rem)
(8) Liquid Total Body 0.069 (9) Liquid Bone 0.27 (10) Gaseous Total Body 0.037 (11) Gaseous Bone 0.053
Page 1 of 2 TABLE 1
, TYPICAL LIOUID EFFLUENT LLO (Lower Limit of Detection) VAL!'11 ASSUMPTIONS: Sample volume = 1 liter = 1000 cc Sample counting time = 1000 see Sample counted with a 25% Ge(L1) for Gamma Emitters IS0 TOPE pCi/cc LLO NOTES Gross Alpha Alpha 4E-9 Counted with proportional counter Gross Beta 0 7E-8 Counted with proportional counter Tritium H-3 4E-6 Counted with liquid scintillation counter Krypton-85 Kr-95 1E-4 Xenon-131m Xe-131m 2E-5 Xenon-133 Xe-133 1E-6 Xenon-135 Xe-135 3E-7 Chromium-51 C r-151 3E-6 Manganese-54 Mn-54 4E-7 Cobalt-58 Co-58 4E-7 Iron-59 Fe-59 9E-7 Cobalt-60 Co-60 6E-7 Z1nc-65 Zn-65 1E-6 Zirconium-95 Zr-95 7E-7 Niobium-95 Nb-95 4E-7 Molybdenum-99 Mo-99 3E-7 Technetium-99m ic-99m 3E-7 Silver-110m Ag-110m 6E-7 Antimony-125 Sb-125 9E-7 Ces ium-134 Cs-134 SE-7 Cesium-136 Cs-136 4E-7 Cesium-137 C s -137 SE-7 Barium-140 Ba-140 1E-6 Lanthanum-140 La-140 7E-7 Cerium-141 Ce-141 SE-7 Cerium-144 Ce-144 3E-6 lodifie-131 1-131 3E-7 lodine-133 1-133 4E-7 Phosphorus-32 P-32 1E-6 These LLO values for liquid Iron-55 Fe-55 SE-8 sample analyses of gross alpha.
Strontium-89 Sr-89 SE-8 P-32, Fe-55, Sr-89, and Sr-90 Strontium-90 Sr-90 SE-8 are the same as Unit I which are Gross Alpha Alpha 1E-7 offsite vendor LLO values.
, P&9e 2 of 2 4 TABLE 2 TYPICAL GASEOUS EFFLUENT LLD (Lower Limit of Detection) VALUES ASSUMPTIONS: Sahlevolume(Marinelli) 1640cc Sample volume (Particulate & Charcoal Filters) 5.7E8cc Sampling Rate 2 cfm or 5.66E4cc/ min Sampling Time 1 week or 1E4 min Sample volume (tritium bubbled thru water) 7.56E5cc Sampling Rate 75cc/ min Sampling Time IE4 min Sample Counting Time: Alpha & H-3 = 20 min; 8 eta =10 min; Ganvna =1000see Sample Counters: Gamma emitters 25% Ge(Li)
Alpha or 8 eta Proportional Counter H-3 Liquid Scintillation Counter ISOTOPE 9C1/cc LLO hat!El Gross Alpha Alpha 1 E-15 Particulate Filter Paper Gross Beta 0 1E-14 "
Tritium H-3 1 E-10 Air bubbled thru water by a fritted disc or Fisher Milligan gas washer Krypton-85 Kr-85 SE-6 Marinelli Krypton-85m Kr-85m 2E-8 '
Krypton-87 Kr-87 6E-8
- Krypton-88 Kr-88 SE-8 "
Xenon-133 Xe-133 4E-8
- Xenon-133m Xe-133m 1E-7 '
Xenon-135
l Xenon-138 Xe-138 3E-7 '
! Iodine-131 1-131 2E-8 '
Iodine-133
- 1 l
fodine-131 1-131 3E-14 Charcoal Filter j todine-133 1-133 4E-14 "
todine-135 1-135
- 3E-13 i Manganese-54 Mn-54 3 E-14 Particulate filter Paper i
tron-59 Fe-59 8E-14
- Cobalt-58 Co-58 3E-14
- Zinc-65 Zn-65 9E-14 "
Strontium-89 Sr-89 2 E-14 "
Strontium-90 Sr-90 2 E-14
Si lver-110m Ag-110m 3E-14 '
Cesium-134 C s -134 4E-14 i Ces ium-13 7 C S -137 3E-14 Cerium-141 Ce-141 3E-14 i Cerium-144 Ce-144 9E-14 "
e e
GPU Nuclear Corporation Nuclear :=gweo Middletowet Pennsyivania 17057-0191 717 944 76;;
TELEX 84 2386 Writer's Direct Dial Number:
(717) 948-8461 November 29, 1988 4410-88-L-0184/0080P US Nuclear Regulatory Comission ATTN: Document Control Desk Washington, DC 20555
Dear Sirs:
Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Operating License No. OPR-73 Docket No. 50-320 Quarterly Dose Assessment Report Update - Third Quarter 1988 Per Section 5.6.1.C of Appendix B to the Recovery Technical Specifications, the cuarterly report of radiological releases and estimated doces is submitted.
Attachment 1 is an executive sumary of THI-2 ef fluents and doses reported in Attachments 2 and 3. Attachment 2 presents a summary of releases including estimates of total activity ard the time rate of release of each nuclide.
Attachment 3 is a Dose Sumary Table which provides a surmary of the maximum hypothetical and/or real doses to individuals and the general population resulting f rom TMI-2 activities. Doses were extracted f rom calculational models and represent the bounding dose for all cases. The reporting period includes July 1, 1988, through September 30, 1988.
Dose sumaries for the previous cuarters of the 1988 calendar year were submitted via GPU Nuclear letters 4410-88-L-0089 dated May 27, 1988, and 4410-88-L-0142 dated August 29, 1988.
Sincerely, W6Afe M. B. Roche Director, TMI-2 EDS/ emf cc: R. J. Conte - Senior Resident Inspector, TMI W. T. Russell - Regional Administrator, Region 1 J. F. Stolz - DirectN, Plant Directorate IV
/[d[
'f i L. H. Thonus - Project Manager, TMI Site }
l GPU Nuclear Ccrporationis a subs l diary of the General Pubhc Ut.ht>es Corporation