ML19309B919
| ML19309B919 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/30/1980 |
| From: | Metropolitan Edison Co |
| To: | |
| Shared Package | |
| ML19309B916 | List: |
| References | |
| NUDOCS 8004070339 | |
| Download: ML19309B919 (98) | |
Text
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't, THREE MILE ISLAND NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNilAL REPORT FOR 1979 Metropolitan Edison Company APRIL 1980 4
PREFACE This annual report of the 1979 Radiological Environmental Monitoring Program for Three Mile Island Nuclear Station Units 1 and 2 satisfies the reporting requirements of both Unit 1 and Unit 2 as shown in their respec-tive Environmental Technical Specifications.
e i
SUMMARY
This report contains the results of the operational Radiological Environ-mental Monitoring Program (REMP) conducted by Metropolitan Edison Company at Three Mile Island Nuclear Station (TMINS) during the period January 1 through December 31, 1979.
On March 28, 1979, there was an accident at Unit 2 resulting in a release of radioactivity to the environment. The operational program was immediately intensified.
This intensified program required, in addition to all normal operational procedures, an increased sampling and analysis frequency and the addition of new sampling locations. This was done to facilitate an orderly and timely acquisition of radiological data so as to evaluate, in the most efficient manner, the environmental consequences of the incident.
Environmental samples were collected and delivered to commercial radiation laboratories for analysis. There were over 5500 samples collected and over 9700 analyses performed on these samples.
A careful review of the monitoring data in accordance w'ith the Environ-mental Technical Specifications (ETS) for Unit 1 and Unit 2 led to the following conclusions:
1.
The requirements of the radiological portions of the Environ-mental Technical Specifications (ETS) for TMINS were met and exceeded.l.2 2.
Prior to the March 28, 1979 accident at Unit 2, there was no detectable radiological impact due to the normal operation of TMINS.
3.
From March 28, 1979 on, there were some transient, low level increases in the immediate radioenvironment. The increases were limited to iodine-131 in air and milk, and the gamma immersion dose.
4.
The average incremental radiological doses associatec with radioactivity increases along critical pathways were:
11
J Pathway Dose Organ Inhalation of airborne iodine-131 Approximately 1.38 mrem Adult thyroid i
Ingestion of iodine-131 in cows' milk Approximately 0.67 mrem Infant thyroid Gamma immersion dose Approximately 2.4 mrem Whole body 5.
There were no detectable increases found in the local off-site 4
radioenvironment after April 12, 1979, for gamma immersion dose, May 19, 1979, for iodine-131 in cows' milk, and May 3, 1979, for iodine-131 in air.
f I
t f
1 iii L
1 TABLE OF CONTENTS fage PREFACE i
SUMMARY
11 LIST OF TABLES AND FIGURES Vi 4
INTRODUCTION vii PROGRAM 1
I Obj ectives 1
2 Design Exceptions 3
Investigation and Non-Routine Reporting Levels 4
RESULTS AND DISCUSSION 11 Surface / Drinking Water 11 Effluent Water 16 Precipitation 18 Milk 19 Air Iodine 20 Air Particulates 20 Gamma Immersion Dose 22 Fishes 24 Aquatic Sediment 24 Aquatic Plants 25 Soil-Grass Vegetation 25 Edible Foodstuffs 25 _
Miscellaneous Sample 26 ASSESSMENT OF IMPACT 27 Methodology of Dose Assessment 27 Dose Calculations 29 CONCLUSIONS 35 REFERENCES 36 APPENDIX A:
Sampling Locations, Frequency & Methods 38 APPENDIX B:
Chronology of Changes in the Radiological 48 Environmental Monitoring Program f
iv s
r--
Paga APPENDIX C:
Dairy Census 57 APPENDIX D:
Results of Licensee Participation in the En-67 vironmental Protection Agency's Environmental Radioactivity Laboratory Intercomparison Stu-dies (Cross-Check Program) e e
e V
LIST OF TABLES Page
- 1. Summary of Deviations in the Radiological Environmental 3
Monitoring Program Based on Unit 1 Environmental Technical Specifications
- 2. Summary of Deviations in the Radiological Environmental 4
Monitoring Program Based on Unit 2 Environmental Technical Specifications
- 3. Periods During Which Investigative Levels Were Exceeded 5
for Unit 1 During the 1979 Radiological Environmental Monitoring Program
- 4. Periods During Which Nonroutine Reporting Levels Were 7
Exceeded for Unit 1 and Unit 2 During the 1979 Radio-logical Environmental Monitoring Program
- 5. Synopsis of the Operational Radiological Environmental 8
Monitoring Program for Three Mile Island Nuclear Station
- 6. Summary of Radionuclide Concentrations in Environmental 12 Samples From Three Mile Island Nuclear Station for 1979
- 7. Summary of Incremental Gamma Immersion Doses During 1979 22
- 8. Dose Summary - Potential Total Incremental Doses Due to 34 Three Mile Island Nuclear Station Unit 2 Accident LIST OF FIGURES
~
- 1. Average Tritium Concentrations in the Susquehanna River in 17 the Vicinity of TMINS.
1974-1979.
- 2. Average Gross Beta Concentrations in Airborne Particulates 21 in the Vicinity of TMINS.
1974-1979.
- 3. Average Gamma Dose Rates in the Vicinity of TM:iS.
1974-1979.
24 vi
INTRODUCTION l
Metropolitan Edison Company has been conducting a REMP for TMINS since 1969. This program involves sampling and analyzing the aquatic, terrestrial, l
and atmospheric environments along established critical pathways in order to establish the radiological quality of the environment and to determine and evaluate any radiological impact caused by TMINS operation. This program j
'is designed and implemented to meet the ETS for each unit, both individually and collectively.1,2 On March 28, 1979, there was an accident at TMINS Unit 2 which caused the accidental and short-term intermittent release of radioactivity to the environment in excess of that released during normal operations. The normal environmental monitoring program was expanded to include additional sampling and analysis frequency and to include the addition of new analyses and sampling locations, a
j i
e 9
vii
. PROGRAM The REMP includes both a preoperational and an operational phase.
June 5, 1974, the date on which TMINS Unit 1 achieved initial criticality, marked the beginning of the operational phase of the program. The operational phase for Unit 2 began on March 28, 1978, when this unit achieved initial criticality.
In the operational phase for both units, radioanalytical data are collected for comparison with that generated in the preoperational phase and for comparison of indicator and control station results. A n indicator station is one where any reactor-caused increases would be expected to be seen; a control station is one that would likely be unaffected. Differences were then compared to determine whether any station effects existed based on the magnitude and fluctuations of radioactivity levels measured in the preoperational phase and at the control locations.
Objectives The objectives of the REMP are:
1.
To fulfill the obligations of the radiological surveillance sections of the ETS for both TMINS Unit 1 and Unit 2.1,2 2.
To determine and quantify any increase in the radioenvironment due to normal operations of Units 1 and 2, and to the accident of March 28, 1979 in Unit 2.
3.
To detect any buildup of long-lived radionuclides in the environment.
4.
To detect any change in ambient gamma radiation levels.
4 This report provides information for the Metropolitan Edison Company, General Public Utilities, regulatory agencies, and the public record, to support these objectives.
s
'. Design Sampling locations and media were based on (1) established critical pathways for the transmission of radionuclides through the environment to man, and (2) the experience gained during the course of the rogram.
Sampling i
locations were determined by site meteorology, Susquehanna River hydrology, local demography, and differential land useage.
l To examine the effects of TMINS operations on the environment, sampling i
locations were designated either as indicator or control.
Indicator stations are those which are expected to manifest effects, if any exist, of I
plant operations; control locations are those believed to be unaffected by I
plant operations. Fluctaations in the levels of radionuclides and direct i
I radiation at indicator stations were compared with those recorded for control stations to evaluate the contributions of normal'TMINS operations and the March 28, 1979 accident.
Indicator stations' data were also evaluated relative to background characteristics established prior to station operation.3 i
The analytical data gene, rated during the program was reviewed initially by the commercial laboratories and sent to Metropolitan Edison Company (Met-Ed) i where it was further reviewed for reasonableness, accuracy, and tompliance with the ETS.I.2 Table 5 (p. 8 ) presents a summary of t'he TMINS REMP. Appendix A explains i
the sample coding system which specifies sample type and location at a glance.
Table A-1 gives the pertinent information on individual sampling locations, while maps A-1, A-2, and A-3, show their geographical locations. Table A-2 provides a summary of the REMP sampling and analysis procedures. Appendix B i
provides a chronology of the changes that occurred in the sampling program due to the Unit 2 March 28, 1979 accident. Table B-1 presents a complete listing, by sample type, of all changes in the program that occurred in l
sampling location and frequency, and analysis type and frequency.
l
_ =_-
Exceptions The 1979 operational REMP for TMINS was conducted in accordance with the ETS for TMINS.1,2 Deviations from the sampling Program, as described in Table 3 of the Unit 1 ETS and in Table 3.2-2 of the Unit 2 ETS, occurred during this period and are reported below as required.1,2 The loss of these few samples did not hinder the effectiveness of the Program.
Unit 1: Pump outages resulted in the loss of four air particulate and four air iodine samples at various stations. One air particulate filter was lost in transit to the laboratory.
Fourteen surface water samples were not collected due to frozen' river conditions. High river flow conditions prevented the collection of two surface water samples.
I Table 1 i
SUMMARY
OF DEVIATIONS IN THE RADIOLOGICAL ' ENVIRONMENTAL MONITORING PROGRAM BASED ON UNIT 1 ENVIRONMENTAL TECHNICAL SPECIFICATIONS Media Location Date Reason Air Particulates IS2 1/24 lost in transit 7F1 9/15, 9/22, 9/29 pump out IS2 10/27 pump out Air Iodine 7F1 9/15, 9/22, 9/29 pump out IS2 10/27 pump out Surface Water 9A2 1/4, 1/17, 1/24, river frozen 9A2 2/7, 2/14, 2/22 river frozen 9A2 3/8 river high 9B1 1/4, 1/17, 1/24, river frozen 9B1 2/7, 2/14, 2/22 river frozen 9B1 3/8 river high 7G1 1/4, 2/22 river frozen
% 1 Unit 2: A pump outage resulted in the loss of one air particulate and one air iodine sample. One air particulate sample was lost in transit to the laboratory.
Two surface water samples were not collected due to frozen river con-ditions. One sample was not collected as a result of a malfunction of the automatic compositing sampler.
Table 2
SUMMARY
OF DEVIATIONS IN THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM BASED ON UNIT 2 ENVIRONMENTAL TECHNICAL SPECIFICATIONS Media Location Dates Reason l
Air Particulates IS2 1/24 lost in transit IS2 10/27 pump out j
Air Iodine' IS2 10/27 pump out Surface Water 7G1 1/4, 2/22 river frozen 8C2 2/14 compositor malfunction Investigation and Nonroutine Reporting Levels Unit 1 and Unit 2 ETSs require that values exceeding those levels generated from section 5.6.2.2 of the Unit 1 ETS and Table 1 of the Unit 2 ETS warrant an initial investigation and, if the situation requires, a non-routine report to the United States Nuclear Regulatory Commission (NRC) within a specified time period.l.2 Necessarily, if samples exceeded Unit I reporting levels, by definition, they also exceeded Unit 1 investigation levels.
The reporting levels for Unit I are based on specified limits set in the Unit 1 ETS; those values exceeding reporting levels for Unit 2 are aver-aged over any calendar quarter which was interpreted as "any consecutive 91-day period".1,2
The determination of values which exceeded reporting and investigative 1
levels for Unit 1 are assessed in a straightforward manner; i.e., by comparison of those values with specified levels of activity applicable tu any given sampling period. Due to changes in sampling frequency made in response to the March 28, 1979 accident, those levels for Unit 2 must be based on a weighted average which is calculated as follows:
E = f IXi n
where, x = weighted average of analytical values.
f = number of days over which each measurement applies, Xi = analytical value, n = total number of days under consideration (i.e., 91 days).
The following is a summary of those dates during which investigative and reporting levels were reached. Many more samples were taken, due to the March 28, 1979 accident, than were required by both Unit 1 and Unit 2 ETS.1,2 The resulting tables therefore include more values that exceeded ETSs' levels than would be exhibited had only ETSs' required samples and sampling periods have been included.
Table 3 PERIODS DURING WHICH INVESTIGATIVE LEVELS WERE EXCEEDdD FOR UNIT 1 DURING THE 1979 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Medium Station Analysis Time Periods AI IS2 I-131 3/22-3/29, 3/29-3/31, 4/8-4/21, 4/21-4/24 8C1 I-131 3/29-3/31 SA1 I-131 3/29-3/31, 4/6-4/9, 4/9-4/12, 4/15-4/18 15G1 I-131 3/29-3/31 12B1 I-131 3/29-3/31, 4/6-4/9, 4/9-4/12 1C1 I-131 3/29-3/31, 3/31-4/3 Milk 4B1 I-131 3/31 7B3 I-131 3/31, 4/18, 4/19
. Medium Station Analysis Time Periods TLD IS2 y
12/27-3/29, 3/29-4/3, 4/6-4/9, 4/18-4/21 2S2 y
12/27-3/29, 3/29-4/3 4S2 y
12/27-3/29, 3/29-4/9 11S1 y
12/27-3/29, 3/29-4/12, 11/17-12/1 16S1 y
12/27-3/29, 3/29, 4/9 14S2 y
12/27-3/29, 3/29-4/6, 4/1-6/30 16Al y
12/27-3/29, 3/29-4/3 8C1 y
3/29-4/9 4A1 y
3/29-4/6, 11/17-12/1 1C1 y
3/29-4/3 10B1 y
3/29-3/31, 4/3-4/6, 4/18-4/21 12B1 y
3/29-3/31, 4/3-4/9 7F1 y
3/29-3/31, 4/6-4/9, *11/17-12/1 4G1 y
3/29-3/31, 4/21-4/24 9G1 y
3/29-3/31, *11/17-12/1 15G1 y
3/29-3/31
- Although TLD stations 7F1 and 9G1, which are control locations, have exceeded investigation levels for Unit I during the period 11/17-12/1, section 5.6.2.2(b)(1)(2) of the Unit 1 ETS allows for an optional com-parison of data in which results for control stations for that specified time period can be compared with the values in question. When the mean 3
and standard deviation of the other control location data for the period 11/17-12/1 are compared with the values for 7F1 and 9G1, it is evident there is no significant difference between the other control values and the results in question; therefore, such values should be attributed to natural random variations in background levels.
e e
I
. Table 4 PERIODS DURING WHICH NONROUTINE REPORTING LEVELS WERE EXCEEDED FOR UNIT 1 AND UNIT 2 DURING THE 1979 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Time Period Above Medium Station Analysis Reporting Level Unit AI SA1 I-131 1/17-6/2 2*
Milk 7B3 I-131 3/31 1
7B3 1-131 1/3 -4/4 2*
IB1 I-131 1/3 -8/4 2*
TLD 11S1 y
12/27-3/29, 1
3/29-4/12 16S1 y
12/27-3/29, 1
3/29-4/3 16Al y
12/27-3/29, 1
3/29-3/31 IS2 y
3/29-4/3 1
2S2 y
3/29-3/31 1
4S2 y
3/29-4/6 1
8c1 y
3/29-3/31 1
14S2 y
3/29-4/3 1
4A1 y
3/29-4/3 1
1
- Any consecutive 91 days in this period exceeding reporting levels.
4 Although the above TLD readings, which exceeded the investigation levels for Unit 1, encompassed the sampling period 12/27-3/29, it is our opinion that these values were a direct result of the Unit 2, March 28, 1979 accident.
Indeed, all of the above values which exceeded investigation or reporting levels, except where noted, could be attributed to the accident. For a detailed discussion of the significance of these values refer to the Results and Discussion and Impact sections of this report;
TAB 3
SYNOPSIS OF Tile OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FOR Ti!REE MILE ISLAND NUCLEAR STATION Number of Number of Number of Sample Sampling Collection Samples Type Analysis Samples Type Locations Frequency Collected Analysis Frequency Analyzed
- Surface Water /
15 Daily 2715 Gr-Beta Daily 509 Drinking Water Weekly 117 Gamma Daily 508 Monthly 24 11 - 3 Daily 508 I-131 Daily 2715 Gr-Beta Weekly Composite 311 Gamma Weekly Composite 311 11 - 3 Weekly Composite 309 Gr-Beta Monthly Composite 84 1-131 Monthly Composite 31 Gamma Monthly Composite 84 11 - 3 Monthly Composite 83 11 - 3 Quarterly Composite 25 Sr-89 Quarterly Composite 16 Sr-90 Quarterly Composite 16 Effluent Water 1
Daily 306 Gr-Beta Daily 276 Monthly 3
Camma
. Daily 275 11 - 3 Daily 274 I-131 Daily 282 Camma Monthly 12 11 - 3 Monthly 12 I-131 Monthly 1
Sr-89 As Required (5) 1 Sr-90 As Required (5) 1 Air Particulates 8
every 3 days 176 Gr-Beta
%every 3 days 174 Weekly 339 Gr-Beta Weekly
- 338 24 Gamma Monthly Composite 24 8
Gamma Quarterly Composite 24 Sr-90 Quarterly Composite 8
Gr-a Quarterly Composite 8
- Number of Samples Analyzed does not include duplicate analyses.
5 EW:
Sr-89 and Sr-90 analyses performed only when liigh iodine levels were detected.
TAB 5 (cont'd)
SYNOPSIS OF Tile OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FOR TilREE MILE ISLAND NUCLEAR STATION Number of Number of Number of Sample Sampling Collection Samples Type Analysis Samples Type Locations Frequency Collected Analysis Frequency Analyzed
- Air Iodine 8
s every 3 days 176 I-131 s every 3 days 174 Weekly 292 I-131 Weekly 292 Quarterly 2
I-131 Quarterly composite 2
Precipitation 5
Monthly 48 Gr-Beta BI-Monthly 8
Bi-Monthly 8
Gamma Bi-Monthly 8
11 - 3 Bi-Monthly 8
I-131 Bi-Monthly 4
Gr-Beta Monthly 44 Gamma Monthly 38 11 - 3 Monthly 32 I-131 Monthly 12 Gamma Quarterly Composite 12 11 - 3 Quarterly Composite 12 Sr-89 Semiannually 8
Sr-90 Semiannually 8
Milktt 5
Daily 307 I-131 Daily 306 Weekly 150 Gamma Daily 129 Monthly 20 I-131 Weekly 150 Gamma Weekly 130 Camma Bi-Monthly 9
I-131 Monthly 20 Gamma Monthly 20 Sr-89 Quarterly Composite 47 Sr-90 Quarterly Composite 47 Fish 00 2
- Weekly, 47 Gamma Weekly, Semiannually 47 Semiannually Sr-89 Weekly, Semiannually 47 Sr-90 Weekly, Semiannually 47 O Number of Samples Analyzed does not include duplicate analyses.
tt Milk - The Quarterly Composite Sr-89 and Sr-90 analyses were performed routinely; other Sr-89 and Sr-90 analyses were performed only when high iodine levels were detected.
Fish & Aquatic Sediment collection & analysis frequencies normally semiannually, however, immediately post-T AA incident samples were collected weekly for 2 months.
TAL 5 (cont'd)
SYNOPSIS OF Tile OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FOR TliREE MILE ISLAND NUCLEAR STATION
[
Number of Number of Number of Sample Sampling Collection Samples Type Analysis Samples Type Locations Frequency Collected Analysis Frequency Analyzed
- Aquatic SedimentAA 5
- Weekly, 60 Gamma Weekly, Semiannually 60 Semiannually Sr-89 Weekly, Semiannually 60 Sr-90 Weekly, Semiannually 60 Aquatic Plants 1
Semiannually 2
Gamma Semiannually 2
Green Leafy 9
Annually 7
Gamma Annually 7
Vegetables Fruit 2
Annually 4
Gamma Annually 4
Misc. Foodstuffst 11 Non-routine 236 Gamma Non-routine 230 Misc. Sample **
1 Non-routine 1
Gamma Non-routine 1
(goat foetus)
Soil-Grass **
3 Non-routine 6
I-131 Non-routine 3
Vegetation Gamma Non-routine 3
Dosimeters (TLD) 55
% every 3 days 211 Gamma Immersion Dose
% every 3 days 211 Weekly 100 Gamma Immersion Dose Weekly 100 Monthly 206 Gamma Immersion Dose Monthly 206 Quarterly 145 Gamma Immersion Dose
. Quarterly 145 Semiannually 6
Gamma Immersion Dose Semiannually 6
0 Number of Samples Analyzed does not include duplicate analyses.
t Misc. Foodstuffs includes all edible foodstuffs, excluding green leafy vegetables and fruit.
- Analyses performed by Radiation Management Corporation.
A 7 of the 23 samples collected were analyzed by Radiation banagement Corporation.
AA Fish & Aquatic Sediment collection & analysis frequencies normally semiannually, however, immediately post-incident camples were collected weekly for 2 months.
/
RESULTS AND DISCUSSION The averages and ranges of analytical results are summarized in Table 6.
Results for each type of sample were grouped according to the analyses per-formed. The standard deviations of these results were calculated when applicable.
It should be noted that these standard deviations represent sample population variability and not analytical variability.
Prior to the March 28, 1979 accident at Unit 2, the REMP was identical to that performed in 1978.3 However, because of the accident, the Program was immediately and markedly expanded as can be seen in the Program Section and Appendix A of this report. This expanded Program was specifically geared to evaluate, in the shortest time possible, the accident's radio-environmental consequences. The discussion which follows centers on the environmental implications of these analytical results while the Impact Section of this report evaluates the radiological impact of these results.
Surface / Drinking Water Surface and drinking water samples were analyzed for iodine-131, tritium, gamma emitting radionuclides, gross beta activity, and strontium-89 and 90.
The results of these analyses indicate that the radiological quality of these environmental media were not affected by TMINS. The reasons for this con-clusion are discussed below.
o TA8tt 6 50mAAf 0F RA010NuctiftE CONCEWTkATI0h5'IN tavlR0hMEnTAL 5AMPLES FROM DIREE MILE ISLAND NUCLEAA stall 0N 1979 i
tower ladicator tocations Control locations location With Htehest Annual Mean Numter Of Linit Of f AEN'
- EoW W DWtance &
- At.ove LLD/
Reportable Non-Rottine so-nie Tree Aaalotts Cetection Pean Ran*:e_ f Of Analyses Mean Range
- Of Analg name ofrection
_ Pean 8ance
- Cf Analyses.
Units Peasureacets Surface /
3 131
$s10-1 0.5
<0.1-2.4 64/2329 0.5
<0.1-3.2 16/677 7G1 Columbia 15 at SE O.5
<0.1 2.4 43/534 pCl/1 Crt; king M-3 330 215
<100-3500 686/739 220
<100 3900 213/231 981 Above fork Haven Dase 1.5 at SE 620 100-2500 14/14 pct /l Water Cr e.
2.0 2.9
<t.0-11.0 667/121 3.1
<l.0-14.0 218/224 9A2 Below Otsclarge 0.5 at 5 4.8 2.0-8.8 14/14 pct /l 1r-89 1.0
<t.0 <5.0 0/12
<l.0-<4.0 0/4 Sr-90 1.0 0.5
<0.3-<0.8 2/12 pCf/I
<0.3-<0.6 0/4 BC2 York Hwen 2.3 at 55E 0.5
<0.4-<0.8 1/4 pel/l K 40 80.C
<30-970 10/702
<33-<400 0/215 7G2 Ertghtsville 13.6 al SE Cs.137 6.0
<30-970 3/120 pCl/l al.0-<80.0 1/702
<2.0-<20.0 1/215 BE1 Sruoner Island 4.1 al SSE 84-276 80.0 41.0-15.0 1/196 pC1/l 5.0-<200.0 9/702 31.0-<200.0 1/215 9G2 York Water Company 14.7 at 5 Th,-228 8.0
<10-<300 1/93 pC1/3
<0.6-53.0 12/102
<2.0-28.0 1/215 8El Brunner Island 4.1 al 55E
<2.0-33.0 3/196 pC /I Iffluent 1-131 5:30-4 1.20
<1.0 62.0 74/308 Wa t' r M-3 330 659.68 100-19.300 291/310 pct /l Cr-s 2.0 4.73
<l.0-20.0 297/300
-~
~
pct /I Jr.8%
3.0 10 1/1 pCl/l Sr-90 1.0 1.7 1/1 pC1/3 pct /l l
Air Cr-s 1:10-3 51.0 3.9-4100.0 343/346 75.0 9.4-1700.0
- 213/213 TF1 Orager fars 9.8 al SE 152.0 15.0-3700.0 72/12 pct /m's10-3 Partic312tes Sr-9J 1:10 4 0.22 0.35-0.82 2/4 0.29 0.14-0.43 2/4 Cr-e 2:1D*3
- 1. 6 - 0.98 2.6 4/4 3.2 0.41-5.9 4/4 3
pct /m alo-3 8e 7 5.0 0.034
<0.01-0.0671 19/21 0.051 0.028-0.096 12/12 7F1 Dra'er Fare 9.8 at SE 0.069 0.0412-0.0959 4/4 pct /m 3 3,
3 pct /m alo-s R.40 10.0
<0.006-<0.02 2/21
<0.006-40.06 0/I2 1281 Go14sboro I.6 at kSW 0.0002 0.0102-4.02 1/5 pct /m3 i
Cs 137 0.3
<0.0004 0.0016 4/21 0.0006
<0.003-0.0023 4/12
/f t Drager Fars 9.8 at SE 0.0014
<0.001 0.0023 2/4 pct /ma Ce 144 1.0
- 0.001-<0.008 2/21
<0.001-<0.007 0/12 BC1 Falmouth Collins Sulb. 2.3 at 55E 0.006
<0.001-<0.003 t/4 pct /m3 4
Air lodine 1 131 Falo-a 0.4
<0.002-23.9 47/317 0.07
<0.003-1.83 13/184 5Al Ob:ervation Center 0.4 at E 0.6
<0.003-20.3 11/66 pCl/m3 N
l'rectettitlen 1-131 5:30-8 0.675
<0.2-2.1 2/8
<0.2-<0.4 0/8 8Cl Falmouth Collfas Sulb. 2.3 al 55E 0.75
<0.2-2.1 1/4 pct /1 H1 330 134.5
<100 220 15/22 125.5
<100-170 14/20 8CI f aircuth Collins Sulb. 2.3 mt SSE 140
<100-220 8/11 pCf/1 Cr-a 2.0 5.0
<0.5 19.0 27/29
- 7.9 el.0-93.0 26/27 15G1 W fairview Sub.
15 at W 11.1 1.9 93.0 14/14 pCl/l Sr.89 5.0
< 3. 0 0/2
<3.0-<4.0 0/2 Sr 90 1.0
<0.7.<0.9 0/2 pct /1
=0.6.<0.8 0/2
~
Th-728 8.0
<8.0 <30.0 7/31 pct /1
<7.0-<30.0 1/24
~
Se-7 50.0
<50.0-<2000.0 1/24
< 10.0- < 1000.0 0/31 pCl/l pct /1 Milk t-131 5 30-8 7.07
<0.1 110.0 134/407 3.50
<0.1-<0.5 0/101 181 Hardison Coat farm 1.2 at N 11.04
<0.2 110.0 44/87 pC1/1 i
Sr 83 5.0
<1.0-<5.0 0/44
<2.0-<4.0 0/4 5r-90 1.0 5.03 0.82-12.0 44/44 3.6 2.8-4.5 4/4 181 Hardtson Goat fara 1.2 at M 6.14 0.82-12.0 28/28 pCl/l oct/l
~
M 40 83.0 1314 689 2030 235/235 1885 621-2960 60/60 181 Hardtson Coat Fars 1.2 at N ggsy 940-2030 64/64 pct /1 Cs-137 15.0 9.56
<3.0-36.6 52/235 10.75
<2.0-<24.1 24/60 181 Hardtson Coat farm 1.2 at N 12.67 < 6.0-36.6 30/64 pCl/l e
in-228 8.0
< 6. 0- < 30 A I/235
<7.0-75.9 t/60
- 3e.133
~
241.0 1/235 oCl/l
- se 135 56.0 1/235 PCl/l 4 1 131
<7.0-=20.000 22/235
-~
pC1/1
<3.0-<30.000 0/60 pct /l f
4 MOTE:
Means were not.ilculated if less than 25% of the results were above the lower Itatt of detection.wlth the enaception of 1131 where the assigned limit was 25-
'For en explanation and a listing of non-routine reportable measurements, please refer to subsection *lavestigation.and hon-Routine Reoorttag Levels" to the Program Section of this report.
- The LLO for this nucifdc is not calculateel however. If activf ty is detected. It is se quantified.
4 I 131 - portion of gasuna scan.
TA8tt6(cor.t.)
10Pt1AAT OF RA010nUCLl0C CONCENTRATIONS IN ENVIROWtENTAL 1ANPLES FROM THAEE MILE ISLAhD NUCLEAR STATION 1979 Number Of tower Indicator locations Control locations location With Highest Anaval Mean Non-Routine Limit of e Alove LLD/
- A5Fve RT/
Distance a a aseve tto/
Reportatile Syy_le Tree Analysts Octection Mean Range
- Of Analyses Mean panne d of Analyses Name
_0trection_ Mean Range f Of Analyses Units Peasure ents Fish 5r-90 5.0a10-8 0.0139 0.0007-0.014 15/21 0.0217 0.0004-0.075 15/22
Background
North 0.0217 0.0004-0.075 15/22 pct /g (wet'l K-40 4:10-1 2.93 2.37-3.93 24/24 3.17 2.17-9.21 21/28 Background.
North 3.17 2.17 9.21 24/24 pct /ge(weti It 228 2:10 a 1/28 Bactorcund 0.4 al NNW
... 0.01-0.29 t/ 21 pCl/gm met
Cs.134 2:10-8 0.0566-0.723 2/24
'0.n!.0.*29
...7/dl Indicator South 0.136 0.0451-0.143 14/24 pct /gm met Indicator South
--- 80.01- 0.07 3/24 pct /qm met
Cs-131 2a 10-3 0.07.0.01 -0.14 b 14/24 0.us4 0.ul. 0.2 Agaa tt s Sr 90 5.0 0.009 0.012 2/48 0.001 0.0011-0.0063 3/11 1A2 0.7 al N 0.0032 0.0011-0.0096 4/12 pct /gm(dry?
5edime;t E.40 410-1 9.41 4.88-15.8 48/48 7.94 5.07 11.2 12/12 981 1.5 at 5 11.163 1.47-15.80 12/12 pct /9-(dry' '
Th-228 2alo-a 3,147 0.2-l.78 41/48 1 037 0.612 1.53 12/]2 981 1.5 al 5 1.298 0.2-1.78 11/12 pct / gal' dry Cs-134 1.5 10-8
..vo.u.1 u/ed 991 1.5 at 5 0.129 0.09-0.303 3/12 pct / gal Cs-137 1.5a10-3
<.05. 303 3/4s 0.1 0.852
' dry 0.328 0.5-0.965 46/48 o,np
.3/]i211/ 2 901 1.5 al 5 0.496 0.122-0.965 11/12 pct / gal' dry'-
84-226 1:10-3 1.573 0.6-3.03 28/43 1.369 0.977-2.33 983 1.5 al 5 l.uW 0.00-2.60 E/32 pct /gmidry Mn-54.
2a10-3 0.04..) 0 6/48 h.bt.40.10 0/12 IIAI 0.5 ml SW e0.555ab.k7-0722 Ig/g pct /gm' dry '
/
try 0.187 Co-58 2a10-3 0.t37*0.04-1.i9 20/43
. 5.o.IU 0/12 IIAI 0.5 at SW
. -1.19 pct / gal 0.04-. 0.2 5/48
.3.05-.0.10 0/12 18Al 0.5 at SW Co-60 2a10 4
- 0.08 40 20 2/12 pC t/om' dry
.56 4/48 1.94
.0.05-3.70 5/12 1A2 0.7 at M 1.44 *0.5-3.76 5/12 pct /gs? ryl 8e-7 1:10-8
.0.04 1.0.2 1/44
.0.G4-.0.10 0/12 IIA 1 0.5 at $d
- 0.07 *0.20 0/12 pct /gmLdryl d
I Zr-95 410-3
.0.04 ta Aquatic K-40 talJ-l 2.95 2.90-3.0 2/2 IA2 0.7 at il 2.95 2.9-3.0 2/2 pct /ge(dry)
I Pla ts f.reen L;afy K-40 4:10-8 1.87 0.4-2.10 3/4 1.72 1.67-1.77 2/2 481 1.1 al ENE 2.1 1/1 pct /ge(dry)
NOTE: Means were not calculated if less than 255 of the results were above the lower Itatt of detection, with the exception of I-131 where the assigned limit was 25.
- for en esplanation and a listing of non-routine recortable measurements, please refer to subsection *Investigatles and Non-Routine Deporting Levels
- to the Program Section of this report.
TA8tt 6 (cont.)
$U41 arf 0F RADIONUCLICE CONCENTRATIONS IN ENylR0fmE1TAL 5AMPLt$ fROM THREE MILE ISLAND NUCLEAR STATION 1973 Nunter Of tower Indicator locations Control Locations location With Hfghest Annual Mean Non-Soutine Limit of
- Above LLD/
l~Above LLD/
Direiciton a s Above LLD/
Reportable
$arple Type Analysts Detection Mean Range f Of Analyses Mean Range
- Of Analysas Meee
__ Dis ta nc e Mean Range
- Of Analyses Units Measure
- nts 1/1 2Gla0ellig Fara 10 $ aj NNE 19.9 Soll 5-40 '8 4:10-8 10.3 6.52-14.3 10/10 19.9 1/1 pCtfgm(dryi Th 232f 3:10-1 1.0 0.92-1.1 3/3 7s30t eccher rara 1.6 mt SE 1.1 t/1 pCl/9m ory i
.Cs ll1'e 2sto-a 0.59 0.248-1.38 10/10 0.46 t/1 14Claconley Fars 2.7 at wat 1,38 1/1 pct /gm dryl R4-226'8 1:10-1 1.43 0.72-1.95 7/10 2.49 1/1 2 Glace 11tg Farm 10.5 at imE 2.49 1/1 pC /om dry' i
+
1h-22S' 2s10-a 1,31 0.719 1.57,
7/7 1.59 1/1 ZG*acellig Fars 10.5 at NNE 1.59 1/1 pCl/gm dry ll E.40{ta l-13 talo-a 0.079 0.033-<0.14 2/6 0.01 0/1 14C1 Conley fars 2.7 atnni 0.%3 1/1 pC1/gm dryl Grass /
4s10-8 3.33 2.9-3.6 3/6 181QtHardison Fars, 1.1 at ENE 3.6 481Qt Almine Fara V:getation t/l pCl/om dry t
Cs '
2:10-a 0.25 0.18 0.32 2/6 1.2 mi N 0.32 1/1 pcg/gm dryl 8e.
2:10-8 3.23 2.3-4.0 3/6 383Qi Bec&er Fars 1.4 at SE 4.0 1/1 pct /ge(dry,i 1/ 7, pct /gm wet'i Edible K-40 W I:10-4 2.46 0.89-7.75 15/17 2.23
<0.085 3.40 5/6 181shardtson Fars 1.2 mi N 7.75 e
Foodsty'ffs Th-2284 tal0-a
<0.02-<0.1 1/17
<0.1-<10.0 2/6 18taHardison Fars 1.2 at N 0.14
=0.08-0.247 1/3 pC1/gm weti en.03-.n.n8 0/6 181aHardison Farm, 1.2 ml N 0.04
<0.02-0.03 1/3 pct /gm wet i
8e-7 '
2:10-8 1.6
<0.07-<2.00 4/17 2.3 Cs-1374 2:10-a n.n51 en.een n.3A 4/17 0.068
.0.02-0.093 2/6 881& Falmouth 1.9 at SSE 0.36 1/1 pCl/ge wet,i I
Goat foetus K-408 4:10-8 1.50 181Qt 1.2 at N 1.50 t/1 1/1 pct /ge(wet) g leersion y
as per 0.296 0.004-2.58 444/448 0.006 0.004-0.040 140/144 1651 Cate la fence 0.2 at NNid 1.95 0.008-0.047 23/23 area / hour Dose USNRC on THI Reg.
Guide 4.13 NOTE: Means were not calculated if less than of the results were above the lower llatt of deteCtton.
- For an esplanation and a itsting of non-routine reportable measurements. please refer to subsection *Investigatten and Non-Routine Reporting Levels
- In the Program Section of this report.
t only RMC data used in calculation of range and mean.
4 Only Teledyne Isotopes data used in calculation of range and mean.
te Both RMC and Teledyne isotopes data used in calculation of range and mean.
e o
e a
e
Iodine-131 There were 3006 samples analyzed for iodine-131 with only 80 results above the limit of detection. These positive results ranged from 0.29 0.12 to 3.2 0.2 pCi/l with 20 of these results being above 1.0 pCi/1. A review of the temporal and spatial occurrence of these results showed no pattern that could be related to TMINS effluents. That is, positive results sporadically occurred upstream, in the plant intake, and dowastream.
For example, positive results were found at control b u t not indicator locations, or positive results were found 15 miles downstream but not in the plant effluent. Thus sources other than TMINS were considered.
When positive iodine results occurred, they generally were in evidence at TM-SW-1C3 (Swatara Creek, approximately 2.3 miles upstream), TM-SW-7G1 (Columbia Water Plant, approximately 15 miles downstream), and TM-SW-7C3 (Lancaster Water Company, approximately 15.5 miles downstream). Consideration was given to Hershey Medical Center as a possible source for the positive values in Swatara Creek. Lancaster General Hospital was considered as a potential source for the Columbia Water Plant and for Lancaster Water Company positive iodine results via Chickies Creek, a tributary flowing into the Susquehanna River just above the respective intakes for these water companies.'
Both hospitals were contacted; and, in many instances, it was learned that positive iodine-131 results found in the sampling program were associated with iodine-131 administered to patients for diagnostic or therapeutic purposes at both institutions.4,5 A study by the Environmental Protection Agency and the Food and Drug Administration in the Ohio River also found similar associative results for iodine-131 and medical uses.6 Also,
. the Department of Health, Education, and Welfare has estimated that medical used of iodine-131 could cause riverine concentrations of between 0.5 and 2.7 pCi/l of iodine-131 around TMINS.7 Tritium The tritium levels detected were within the ranges found preoperationally and operationally prior to 1979; no trends or spatial differences were apparent in 1979 (See Figure 1).3,8,9,10,11 Gross Beta Activity The levels of gross beta activity were similar to those found in 1978, and no trends or spatial differences were apparent for 1979.3 Gamma Spectroscopy The only radionuclides found were naturally occurring radium-226, potassium-40, and thorium-228.
Strontium-89 and 90 Of the 16 samples analyzed, only 2 results for strontium-90 and no results for strontium 89 were above the limit of detection.
These few positive results are similar to those found preoperationally and prior to 1979.3,8,9,10,11 Effluent Water Prior to March 28, 1979, effluent water samples (combined Unit 1 and Unit 2 effluents) were analyzed monthly for tritium and gamma emitting radionuclides. However, beginning on March 29, 1979, effluent water samples were taken and analyzed on a daily basis for iodine-131, tritium, gross beta activity, gamma emitting radionuclides, and, on one occasion (June 25), for strontium-89 and 90.
Figure 1
~
.WEP. AGE TRITItDI CONCENTRATIONS IN SL'sQUEllANNA RIVER IN Tile VICINITY OF TLIINS 1974 - 1979 10000,
Indicator Control 9
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4-TMI-2 ACCIDENT TF11 -1 "n!I -2 INITIAL CRITICALITY INITIAL CRITICALITY i
10 1974 1975 1976 1977 1978 1979
The results of these post-incident analyses showed high levels of iodine-131 in two instances (62 and 43 pCi/l on April 1 and 2 respectively) and occasional low levels of iodine-131 throughout 1979. The low levels of iodine found may have been due to sources other than TMINS; and, in any event, these positive results did not correlate with positive results found in surface or drinking water (refer to Iodine-131 in Surface and Drinking Water Section).
Tritium levels in effluent water generally reflected typical ambient environmental concentrations, but occasional high values were noted. Gamma spectroscopy found very occasional low levels of:
cobalt-58, cesium-137, and naturally occurring thorium-228 and potassium-40.
Strontium analyses noted one low level positive strontium-89 and two low level positive strontium-90 results.
It should be noted, however, that these results for effluent water did not have an impact on surface or drinking water quality.
Precinitation Rainwater samples were typically collected monthly with the exception of April, during which samples were collected twice (for the period March 31 to April 5, and April 5 to April 27).
Samples were analyzed for gross beta activity, tritium, gamma emitting radionuclides, strontium-89 and 90; and, for those samples immediately post-accident, iodine-131 analyses were also performed.
All results for all samples, with the following exceptions, were well within normal environmental ranges. The only unusual results encountered were two low level positive iodine-131 values at TM-RW-8C1 (Falmouth) and TM-RW-5A1 (Observation Center) for the period March 31 to April 5, 1979.
l
Milk Prior to March 28, cow and goat milk samples were collected monthly, and each sample was analyzed for iodine-131 and gamma emitting radionuclides.
Beginning on March 29 and continuing to May 31, samples were collected and analyzed daily; from June 2 on, samples were collected and analyzed weekly for iodine-131 and gamma emitting radionuclides.
Strontium analyses were also performed on quarterly composites and on individual samples with iodine-131 concentrations greater than 10 pCi/1.
The iodine levels in milk were elevated temporarily due to the accident.
This elevation was most noticeable at TM-MG-1B1, a goat farm (on Route 441, 1.2 miles north of the site), where the values ranged from 1.1 0.2 to 110 10 pCi/1.from March 29 to May 23, 1979, and averaged 18.6 pCi/l for this same time period. No iodine was found after May 23, 1979.
Iodine-131 levels in cows' milk were elevated from March 29 to May 19, 1979.
No iodine was found after May 19, 1979. The highest levels were found at TM-M-7B3 (1.6 miles southeast of the site) which averaged 2.13 pCi/1, and ranged from <0.2 to 21 pCi/1 during this time period. When all milk samples from all sampled farms are considered, the average iodine-131 level in cows' milk du' ring this same time period was 0.93 pCi/1. The highest levels found were well below the 439 pCi/l found in milk in North York County in Pennsylvania as a result of the Chinese bomb testing in September 1976 and well below the proposed FDA limit of 12,000 pCi/1.12 Gamma spectroscopy of milk samples found, in addition to iodine-131, i
only naturally occurring potassium-40, normal background levels of fallout cesium-137, and, in two samples, very low levels of radioxenon. Radioxenon has no recognized dose implications in this pathway, thus there is no impact due to these findings.13 No detectable strontium-89. Only normal background levels of fallout strontium'-90 were found in the milk.
W 20-Air Iodine Continuous air iodine samples were taken weekly at four locations prior to March 28; from March 28 to June 1 this program segment was expanded to eight locations with samples taken every three or four days; and from June 2 t h e s e ei gh t locations were sampled weekly.
An increase in the airborne iodine-131 levels were evident from March 28 to May 3, 1979.
The air sampler at TMINS Observation Center (station TM-AI-5A1) had the highest levels during this time period, ranging from <0.02 to 20.3 2.0 3
pCi/m3 and averaging 2.94 pCi/m. The iodine-131 levels in Middletown (station TM-AI-1C1), a proximal population center, averaged 1.12 pCi/m3 and ranged f rom <0.04 to 12.7 1.3 pCi/m3 for this same time period.
I-131 levels in Goldsboro (station TM-AI-12B1), another proximal population center, averaged 1
2.09 pCi/m3 and ranged from <0.05 to 23.9 2.4 pCi/m3 for this same time period. The overall airborne iodine-131 concentration within 13 miles of the site averaged 1.20 pCi/m3 from March 28 to May 3, 1979. No airborne iodine-131 wac detected after May 3, 1979.
Air Particulates Continuous air particulate samples were collected at eight locations following the same sampling schedule as air iodine samples.
Each air particulate sample was analyzed for its gross beta activity, and composite samples were analyzed for gamma emitting radionuclides and strontium-89 and 90.
All analytical results for all air particulate samples were at normal ambient background levels with no spatial, temporal, or trend differences apparent (See Figure 2).
Figure 2 AVERAGE GROSS BETA CONCF'" RATIONS IN AIRBORNE PARTICULATES IN.
VICINITY OF D11NS 1974 - 1979 1000
..... INDICATOR
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" <-TMI-2 ACCIDENT ntI-1 TMI-2 Initial Criticality Initial Criticality I
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1974 197S-1976 1977 1978 1979 es e
.~.- -._ _
. Gamma Immersion Dose Prior to March 28, thermoluminescent dosimeters (TLDs), used to measure the gamma immersion dose, were collected quarterly at twenty locations.
On March 29, 1979, TLDs were collected and analyzed for the first quarter of 1979, and again on March 31, 1979, and then collected every three or four days in April, weekly in May, and monthly and quarterly from June through December.
In the beginning of September, 35 new TLD locations were added to the monitoring program; TLDs from these new locations were analyzed for the month of September and quarterly thereafter.
In order to evaluate the results of the gamma immersion dose monitoring program, the 1978 observed backgrounds, which are unique for each location, were subtracted from the 1979 observed values to arrive at the incremental immersion dose attributable to TMINS.3 These values, which are in units of milli-Roentgens, were convertad to milli-rem for evaluation purposes by assuming 0.955 milli-rads per milli-Roentgen and a quality factor of unity.
1 Based on this methodology it,was determined that the off-site environmental dose rate was elevated from March 28 to April 12, 1979. No dose increments were observed after April 12, 1979. The table below and Figure 3 summarizes these increases.
Table 7
SUMMARY
OF INCREMENTAL CAMMA IMMERSION DOSES DURING 1979 Incremental Location Gamma Immersion Dose in mrem TM-ID-4A1 (0.5 miles east northeast of the site) 76.3 TM-ID-1C1 (Middletown) 6.8 TM-ID-12B1 (Coldsboro) 12.8 Average from sitit boundary to one mile 8.2 l
I
Table 7 (cont'd)
SUMMARY
OF INCREMENTAL GAMMA IMMERSION DOSES DURING 1979 Incremental Location Gamma Immersion Dose in mrem Average from one to two miles 2.5 Average from two to three miles 1.7 Average from five to ten miles 0.8 Average from site boundary to ten miles 3.6 i
Average from ten miles to twenty miles 0.2 Average from site boundary to twenty miles 2.4 i
l Fishes i
Fish samples were collected weekly from April 11 to May 30, 1979, and once in July and October upstream (control) and downstream (indicator).
These samples were filleted, separated into classes of bottom feeder versus predator-game species, and analyzed for gamma emitting radionuclides and strontium-89 and 90.
Strontium-89 was not detected in any sample, while low levels of fallout strontium-90 were, detected in some samples. Gamma spectroscopy found naturally occurring potassium-40 and thorium-228, low levels of fallout cesium-137, and, on two occasions, low levels of cesium-134.
Aquatic Sediment Aquatic Sediment samples were collected weekly from April 5 through May 29, 1979, and once in July and October at a variety of control and indicator locations. These samples were analyzed for strontium-89 and 90 and for gamma emitting radionuclides.
Strontium-89 was not found in any sample while low levels of fallout strontium-90 were found in some samples. Gamma
figure 3 AVERAGE GA>DIA DOSE RATES IN 111E VICINITY OF TMINS 1974 - 1979
.-------- INDI CATOR
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t 1974 1975 1976 1977 1978 1979
__, spectroscopy noted the presence of naturally occurring potassium-40, thorium-228, radium-226, and beryllium-7, low levels of fallout cesium-137 and strontium-90, and low levels of reactor produced cobalt-58, cobalt-60, manganese-54, and cesium-134.
Aquatic Plants Two aquatic plant samples upstream were taken in July 1979.
Both samples showed the presence of naturally occurring potassium-40.
Soil-Grass Vegetation One week after the accident, soil and grass and/or inedible vegetation samples were taken at each milk sampling location. These samples were analyzed by gamma spectroscopy. Soil samples generally showed the presence of naturally occurring potassium-40, radium-226, and thorium-232 or thorium-228, and fallout-cesium-137. Grass and vegetation samples had, in some instances, detectable levels of naturally occurring beryllium-7, potassium-40, fallout cesium-137, and, in four samples, barely detectable levels of iodine-131.
Edible Foodstuffs A wide variety of edible foodstuf(c was sampled at various times and locations throughout 1979. These samples consisted of:
apples, asparagus, beets, cabbage, cauliflower, corn, green beans, peaches, potatoes, spinach, beef, deer, eggs, mallard, poultry, and pork.
Each sample was analyzed by gamma spectroscopy. The only detected radionuclides were: naturally occurring potassium-40 in most samples, naturally occurring beryllium-7 and thorium-228 in one spinach sample, and fallout cesium-137 in one deer meat sample.
Miscellaneous Sample One miscellaneous sample, a goat foe.tus, whose mother had died due to pregnancy complications, was taken on April 5, 1979. Gamma spectral analysis of this sample found only naturally occurring potassium-40.
9 e
O-
. ASSESSMENT OF IMPACT The March 28, 1979 accid.t resulted in cransient increases of radio-activity in the of f-site envit. nment.
In order to quantitatively evaluate t h i s impact, it is first necessary to calculate the potential radiological doses to individuals in the popu-lation at large that could have been exposed and to then estimate the health effects represented by these potential doses.
Methodology of Dose Assessment 13 The fundamental equation for calculation of radiation dose to man from measured concentratf.ons of various radionuclides in environmental media is:
U DF T
2.
D
=C ipr ip p ipr
- where, ipr = the dose to organ r from nuclide i via pathway p, D
ip
= the concentration of nuclide i in the media of pathway p, C
U
= the exposure rate or intake rate associated with pathway p, p
DFipr = the dose factor specific to a given nuclide, pathway, and organ which can be used to calculate radiation dose from exposure rate to a given concentration of a radionuclide or the intake rate of a radionuclide, and, T
= the duration of the exposure or intake.
The terms used in the fundamental dose equation, and specifically their use in this report, are discussed below.
C ip The concentration of the i,th nuclide in the pth pathway are determined by averaging the observed values over those time periods during which such values were above normal background levels.
For purposes of calculating
. these averages, values below the analytical limit of detection are con-sidered to be at that level; this results in slightly higher averages and consequently slightly higher dose estimates than actually existed.
Up All exposure rates and intake rates used in this report were taken from United States Nuclear Regulatory Commission Regulatory Guide 1.109.13 DFipr All dose factors used in this report were taken from United States Nuclear Regulatory Commission Regulatory Guide 1.109.13 T
The exposure times used in this report correspond to the time periods of increased radioactivity for the discrete media type.
The incremental off-site gamma immersion dose was calculated directly from the thermoluminescent dosimeter (TLD) readings by subtracting the 1978 observed background from the 1979 observed values and summing these results over the time period of increased dose rate.3 These results were then con-verted to mrem by assuming 0.955 mrad per mRoentgen and a quality factor of 1.
The total population dose, expressed as person-rems, was, arrived at using the projected 1980 population.14 The equations used are:
DmR = DmR -DmR 1979-1978 3.
D
= 0.955D mrea mR 4.
D
=D x 1980 Population x 1000 person-rem mrem 5.
- where, I
l i
L.
. DmR = the incremental off-site gamma immersion dose rate in mRoentgens for the time period of interest; DmR = the total observed dose rate for the time period of interest; 1979 DmR = the average observed dose rate for 1978 for the time period of 1978 interest; D
= the incremental of f-site gamma immersion dose in mrem for the mrem time period of interest; and, D
= the incremental person rem dose for the time period of person-rem interest.
Dose Calculations The doses calculated here are very conservative and necessarily represent upper limit estimations. This is attributed to the method of averaging radionuclide concentrations and not taking into account radio-active decay, occupancy factors, or shielding factors which would lower these calculated doses.
Air Iodine The concentrations of airborne iodine-131 were elevated for the period March 28 to May 3, 1979. To evaluate this increase, doses to the th'yroid gland are calculated for the potentially maximum adult at location TM-AI-5A1 (Observation Center which had the highest concentration), the average adult and child in Middletown (TM-AI-lC1) and Goldsboro (TM-AI-12B1),
and for the average adult and child in the general population.
Maximum Adult: This calculation assumes an individual was outside at the Observation Center (TM-AI-5A1) for the entire exposure period - an unlikely event.
D = (2.94 pCi/m3) (22m3 of air inhaled / day) (1.49 x 10-3 mrem /pci inhaled) (35 days) = 3.37 mrem
- 7. -..
. D = (1.12 pCi/m )(22 m3 of air inha' led / day) 3 Average Adult in Middletown:
(1.49 x 10-3 mrem /pCi inhaled)(35 days) =
1.28 mrem Average Child in Middletown: D = (1.12 pCi/m3)(10 m3 of air inhaled / day)
(4.39 x 10-3 mrem /pCi inhaled)(35 days) =
1.72 mrem 3
Average Adult in Goldsboro:
D = (2.09 pCi/m )(22 m3 of air inhaled / day)
(1.49 x 10-3 mrem /pCi inhaled)(35 days) =
2.40 mrem Average Child in Goldsboro:
D = (2.09 pCi/m3)(10 m3 of air inhaled / day)
(4.39 x 10-3 mrem /pCi inhaled)(35 days) =
3.21 mrem Average Adult in the General Population: This and the following calculation for the average child utilized the average air iodine-131 concentration based on all off-site results.
3 D = (1.20 pCi/m )(22 m3 of air inhaled / day)(1.49 x 10-3 mrem /pci inhaled)(35 days) = 1.38 mrem 3
Average Child in the General Population: D = (1.20 pCi/m )(10 m3 of air inhaled / day)(4.39 x 10-3 mrem /pC1 inhaled)(35 days) = 1.84 mrem Iodine in Milk The concentrations of iodine-131 in cows' milk were elevated from l
March 29 to May 19, 1979, while those in goats' milk were elevated from March 29 to May 23, 1979.
To evaluate these increases, doses to the thyroid gland are calculated for the potentially maximum infant drinking only goats' l
milk from farm TM-MG-1B1, the potentially maximum infant drinking cows' milk i
from farm TM-M-7B3 (that farm with the highest concentration), and for the average infant in the general population.
1
. Maximum Infant Drinking Coats' Mi]ki This pathway truly did not exist in March and April as virtually all of the goat milk production was used either to suckle newborn goats or for environmental samples.15 Thus, the calculated dose is necessarily an overestimate of the potential maximum dose.
L = (18.6 pCi/1)(1 1/ day)(1.39 x 10-2 mrem /pCi ingested)(56 days) = 14.5 mrem The more likely potential maximum dose, which considers the twenty-three days of elevated concentrations in May, i s shown below.
D = (14.4 pCi/1)(1 1/ day)(1.39 x 10-2 mrem /pCi ingested)(23 days) = 4.60 mrem Maximum Infant Drinking Cows' Milk: D = (2.13 pCi/1) (1 1/ day)(1.39 x 10-2 mrem /
pCi ingested)(52 days) = 1.54 mrem Average Infant Drinking Cows' Milk: This calculation utilized the average milk iodine-Is1 concentration based on all results.
D = (0.93 pCi/1)(1 1/ day)(1.39 x 10-2 mrem /pci ingested)(52 days) =
0.67 mrem Gamma Immersion Dose The off-site gamma immersion dose was elevated for the period March 28 to April 12, 1979. To evaluate this increase, whole body immersion doses are calculated for the potentially maximum individual'at location TM-ID-4A1 (half mile ease northeast of site which had the highest dose rate where people likely would be), the average resident of Middletown (TM-ID-1Cl) and Goldsboro (TM-ID-12B1), and to the general population as a function of distance from TMINS.
i l
. Maximum Individual: This calculation assumes an individual was outside at this location for the entire exposure period - an unlikely event.
D = (79.9 mR)(0.955 mrad /mR)(1) = 76.3 mrem Average Individual in Middletown: 0 = (7.2 mR)(0.955 mrad /mR)(1) = 6.8 mrem Average Individual in Goldsboro:
D = (13.4 mR)(0.955 mrad /mR)(1) = 12.8 mrem Average Individual at Discrete Distances From Three Mile Island: For these calculations, all results, from locations where people likely v.ould be, were averaged together for the appropriate distances:
D (site boundary to 1 mile) = (8.53 mR)(0.955 mrad /mR)(1) = (8.15 mrem)
(658 people)(1/1000) = 5.4 person-rems D (1 mile to 2 miles)
= (2.62 mR)(0.955 mrad /mR)(1) = (2.50 mrem)
(2017 people)(1/1000) = 5.0 person-rems D (2 miles to 3 miles)
= (1.74 mR)(0.955 mrad /mR)(1) = (1.66 mrem)
(7579 people)(1/1000) = 12.6 person-rems D (site boundary to 3 miles) = (4.30 mR)(0.955 mrad /mR)(1) = (4.11 mrem)
(10,254 people)(1/1000) = 42.1 person-rems D (5 miles to 10 miles)
= (0.8 mR)(0.955 mrad /mR)(1) = (0.76 mrem)
(137,454 people)(1/1000) = 104 person-rems D (site boundary to 10 miles)= (3.8 mR)(0.955 mrad /mR)(1) = (3.63 mrem)
(166.295 people)(1/1000) = 604 person-rems D (10 miles to 20 miles)
= (0.21 mR)(0.955 mrad /mR)(1) = (0.20 mrem)
(577,288 people)(1,1000) = 115 person-rems D (site boundary to 20 miles)= (2.51 mR)(0.955 mrad /mR)(1) = (2.40 mrem)
(743,583 people)(1/1000) = 1785 person-rems
. As can be seen from th'e summary table (Table 8), the average individual living near TMINS could have received an incremental dose for 1979 of less than 4 mrem. This dose level is less than the incremental whole body dose received on a transcontinental airplane flight and approximately 2% of the average annual radiological dose received by an individual due to medical exposures, fallout radioactivity, and natural background.
]
1 l
4 s
i
tat.., 8 DOSE
SUMMARY
POTENTIAL TOTAL INCREMENTAL, DOSES DUE TO TilREE MILE ISLAND NUCLEAR STATION UNIT 2 ACCIDENT Incremental Critical Incremental Dose:
Media / Pathway Affected Populatinn Organ Dose: mrem Person-rem Iodine-131 in Theoretical Maximum Adult Thyroid 3.37 Afr/ Inhalation Average Adult in Middletown Thyroid 1.28 Average Child in Middletown Thyroid 1.72 Average Adult in Goldsboro Thyroid 2.40 Average Child in Goldsboro Thyroid 3.21 Average Adult within 13 miles Thyroid 1.38 of Three Mile Island Nuclear Station Average Child within 13 miles Thyroid 1.84 of Three Mlle Island Nuclear Station Iodine-131 in Theoretical Maximum Infant. drinking Thyroid 4.60 Milk / Ingestion goats' milk Theoretical Maximum Infant drinking Thyroid 1.54 cows' milk di Average Infant drinking cows' milk Thyroid 0.67 7
Gama Imersion Theoretical Maximum Individual Whole Body 76.3 Dose Average Individual in Middletown Whole Body 6.8 Average Individual in Goldsboro Whole Body 12.8 Average Individual within 1 mile Whole Body 8.2 5.4 of Three Mile Island Nuclear Station Average Individual between 1 and 2 Whole Body 2.5 5.0 miles of Three Mlle Island Nuclear Station Average Individual between 2 and Whole Body 1.7 12.6 3 miles of Three Mile Island Nuclear Station Average Individual within 3 miles Whole Body 4.1 42.l of Three Mile Island Nuclear Station Average Individual between 5 to Whole Body 0.8 104.0 10 miles of Three Mile Island Nuclear Station Average Individual within 10 Whole Body 3.6 604.0 miles of Three Mlle Island Nuclear Station Aver' age Individual between 10 Whole Body 0.2 115.0 and 20 miles of Three Mile Island Nuclear Station Average Individual within 20 Whole Body 2.4 17850 miles of Three Mlle Island Nuclear Station
~
4 CONCLUSIONS Based on the information contained in this report, the following conclusions can be drawn concerning the 1979 Radiological Environmental Monitoring Programs and their results for TMINS.
1.
The re.quirement of the radiological portions of the ETS for TMINS Unit 1 and Unit 2 were satisfied.
2.
Prior to the March 28, 1979 accident at Unit 2, there was no detectable radiological impact due to the normal operation of either. unit.
3.
From March 28, 1979 on, there were some transient, low level increases in the immediate radioenvironment. The increases were limited to iodine-131 in air and milk, and the gamma immersion dose.
4.
The average incremental radiological doses associated with radio-activity increases along critical pathways were:
Inhalation of a'irborne iodine-131 resulted in about 1.'38 mrem to the adult thyroid; ingestion of iodine-131 in cows' milk resulted in about 0.67 mrem to the infant thyroid, and the gamma immersion dose resulted in about 2.4 mrem to the adult.
5.
There were no detectable increases found in the local off-site radioenvironment due to the accident ofter April 12, 1979, for gamma immersion dose, May 19, 1979, for iodine-131 in cows' milk, and May 3, 1979, for iodine-131 in air.
l 1
REFERENCES
- 1. Three Mile Island Nuclear Station Unit 1.
License No. DPR-50.
Appendix B, Technical Specifications.
1974.
- 2. Three Mile Island Nuclear Station Unit 2.
Environmental Technical Specifi-cations.
1979.
- 3. Teledyne Isotopes.
" Metropolitan Edison Company Radiological Environmental Monitoring Report, 1978 Annual Report." IWL-5590-443.
1980.
- 4. Personal communication.
Mr. Ken Miller.
Hershey Medical Center.
- 5. Personal communication.
Mr. William Jefferson. Lancaster General Hospital.
- 6. Letter communication.
Mr. Michael A. Terpilak. Department of Health, Education and Welfare. August 20, 1979.
- 7. Internal Memorandum. Department of Health, Education and Welfare.
June 22, 1979.
- 8. Radiation Management Corporation.
"Three Mile Island Nuclear Station Preoperational Radiological Environmental Monitoring Program January 1, 1974 - June 5, 1974." RMC-TR-75-17.
January, 1975. and " Radiological Environmental Monitoring Report For The Three Mile Island Nuclear Station First Operational Period June 5, through December 31, 1974."
RMC-TR-75-2.
February, 1975.
- 9. Radiation Management Corporation.
" Radiological Environmental Monitoring Report For The Three Mile Island Nuclear Station 1975 Semiannual Report."
RMC-TR-75-13.
August, 1975. and " Radiological Environmental Monitoring Report For The Three Mile Island Nuclear Station 1975 Semiannual Report II July 1 through December 31."
RMC-TR-76-01.
February, 1976.
- 10. Radiation Management Corporation.
" Radiological Environmental Monitoring Report For The Three Mile Island Nuclear Station 1976 Annual Report January 1 through December 31."
RMC-TR-77-01.
March, 1977.
- 11. Teledyne Isotopes.
" Metropolitan Edison Company Radiological Environmental Monitoring Report."
IWL-5990-427.
1978.
- 12. Proceedings: Workshop On The October, 1976, Fallout Radiation Incident.
United States Environmental Protection Agency.
Phila., PA.
1976.
- 13. United States Nuclear Regulatory Commission.
Calculation Of Annual Doses To Man From Routine Releases Of Reactor Effluents For The Purpose Of Evaluating Compliance With 10 CFR Part 50, Appendix I."
Revision 1, October 1977.
- 14. Final Safety Analysis Report. Three Mile Island Nuclear Station - Unit 2.
Volume 1.
Docket No. 50-320.
- 15. Personal communication. Mrs. Hardison.
Owner of farm TM-MG-1Bl.
- 16. International Commission on Radiological Protection.
" Recommendations of the International Commission on Radiological Protection." ICRP Publication 26.
Pergamon Press.
New York. January 1977.
- 17. National Council On Radiation Protection and Measurements.
" Review of the Current State of Radiation Protection Philosophy." NCRP Report No. 43.
Washington, DC.
January 1975.
- 18. Report Of The Advisory Committee On The Biological Effects of Ionizing Radiations.
"The Effects on Populations of Exposure to Low Levels of Ionizing Radiation." National Academy of Sciences - National Research Council. Washington, DC.
November, 1972.
- 19. United Nations Scientific Committee on the Effects of Atomic Radiation.
" Sources and Effects Of Ionizing Radiation." United Nations. New York, 1977.
- 20. A Report Of Advisory Committee On The Biological Effects Of Ionizing Radiations.
" Considerations Of Health Benefit-Cost Analysis For Activities Involving Ionizing Radiation Exposure And Alternatives." National Academy of Sciences. Washington, DC.
1977.
- 21. American Cancer Society.
" Cancer Facts and Figures - 1979."
O r
(
l
9 APPENDIX A SAMPLING LOCATIONS, FREQUENCY AND METHODS 9
e i
TABLE A-1 RADIOLOGICAL ENVIRDtatENTAL MONITOR!ttG PROGRAM SAMPLE LOCATIONS SAMPLE LOCATION MAP' DI5fAtlCE MID!uM CODE nut 2ER (MILES)
A2!MUTH DESCRIPTION AP.A!,1D 152 1
0.4 0
N of site, North Weather Station ID 252 2
0.7 28 NNE of site on Itght pole in middle of North Bridge ID 452 3
0.3 71 ENE of site on top of dike. East Fence ID 552 4
0.2 95 E of site on top of dike, East Fence ID 851 5
0.4 167 SSE of site ID 952 6
0.8 184 5 of site at South Beach of Three Mlle Island EW 1051 7
On site, RML-7 10 1052 8
0.4 200 SSW of site 1D 1151 9 -
0.1 221 SW of site, mest of Mechanical Draft Towers on dike 10 1351 10 0.4 270 W of site on Shelley Island SW 1352 11 0.1 270 W of site, intake ID 1452 12 0.4 293 W?N of site on Shelley Island ID 1551 13 0.5 317 NW of site on Shelley Island ID 1651 14 0.2 340 his of site at gate in fence on test side of Three Mile Island. North boat dock ACP 1A1 15 0.7 1
N of site A05 1A2 16 0.7 O
N of site at north tfp of Three Mlle Island ID 3Al 17-0.6 35 NE of site on Route 441 ID 4A1 18 0.5 65 ENE of site on Laurel Road AP,41 RW,1D
, SA1 19 0.4 100 E of site on rorth side of Observation Center Building ID 6Al 20 0.5 117 ESE of site on Ifght pole on Route 441 ACS 7Al 21 0.3 137 SE of site 10 7A3 22 0.6 143 SE di site on Route 441 1
SW,AQP 9A2 23 0.5 188 5 of site below Olscharge Pipe A05 10A1 24 0.8 '
202 SSW of site A05 11A1 25 0.5 225 SW of site i
ID 11A2 26 0.5 221 SW of site on Beech Island 101 16Al 17 0.4 332 NPM of site on Fahr Island MG 181 28 1.2 5
N of site. farm along Route 441 M.FPL 431 29 1.1 65 EW of site, farm best of Grfngrich Road P.f P'.
783 30 1.6 125 SE of site, farn on the cast side of Conewaqo Creek C20 Af;)
1.9 163 5'iE of site. Ialeuth 5.i. Ary, Ag$, Agp 9B1 31 1.5 178 5 of site above York Haven Dam A05,1D 1031 32 1.1 2-0 SSW of site on south tseach of Shelley Island ID 1181 33 1.9 227 SW of site on Route 262 AP.A1.10 1281 34 1.6 253 QSu of site adjacent to Fishing Creek, toldsboro Afr Station ID 1381 35 1.2 261 W of site at *.oldsboro Marina 13 1481 36 1.4 290 W'M of site on Still House Road 10 1581 37 1.8 304 N'l of site on Still House Road ACF 1681 38 1.1 337 NtM of site below Fall Island AP.AI,1D ICI 39 2.6 355 N of site at Middletown Substation SW IC3 40 2.3 347 N of site at Swatara Creek AP AI.RW,ID SCI 41 2.3 159 SSE of site at Falmouth-Collins Substation SW 8C2 42 2.3 165 SSE of site York Haven Hydro M. FPL 1401 43 3.7 283 WM of site, farm 10 IE4 44 4.3 3
N of site on Vine Street exit from Route 283 10 2E1 45 4.8 18 NNE of site, School House Lane and Miller Road 10 3E3 46 4.5 42 NE of site on kennedy Lane ID 4I5 47 4.9 62 EHE of site on Beagle Road 10 SEl 48 4.6 Cl E of site, North Market Street and Zaeger Road ID 6E6 49 4.6 115 ESE of site on Amostte Road 10 7E6 50 4.8 131 SE of site. Sainbridge and Rfsser Roads SW 811 51 4.1 160 55E of site on Brunner Island ID 8E2 52 4.1 155 SSE of site at Guard Shack on Brunner Island ID 9El 53 4.9 182 5 of site on Canal Road, Conewago He19 ts h
- Station GAD-881: 1 sample - road kill
TAB.E A-1 (cont'd)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE LOCATIONS (cont'd)
SA@LE LOCATION MAP DISTANCE MEDIUM CODE NUMBER (MILES)
A21MUTH DESCRIPTION ID 10E3 54 5.0 200 55W of site on conewago Creek Road. Shrinestown ID llE3 55 4.1 228 SW of site. Stevens and Wilson Roads ID 12E4 56 4.3 245 W5W of site. Lewisberry and Roxberry Roads. Newberrytown ID 13El 57 4.9 268 W of site. Yocumtown and Old Trail Feeds ID 14E4 58 4.9 281 WNW of site. Route 262 and Beinhower Road ID 15El 59 5.0 313 NW of site on Lumber Street. Highspire ID 16El 60 4.9 339 NNW of site. Spring Garden Drive and Route 441 10 2F1 61 9.3 18 NNE of site. West Areba Avenue and Mill Street. Hershey ID 3FI 62 7.2 48 NE of site. Shanks Church on School House Road ID 4F1 63 8.5 72 ENE of site on Mt. Gretna Road, Bellatre ID 5F1 64 6.8
'85 E of site on Humeistown Street. Elizabe'htown FPF SF2 65 5.1 100 E of site. orchard ID 6F1 66 9.4 113 ESE of site. Donegal Sprinos Road. Donegal Springs AP.AI.RW.10 7F1 67 9.8 127 SE of site at farm off Engle's Tollgate Road ID 8FI 68 7.4 163 SSE of site on Saginaw Road. Starview ID 9F1 69 6.5 177 5 of site on Maple Street. Manchester ID 10F1 70 7.4 196 SSW of site. Coppenhaffer Road and Route 295. Zion's View 10 llFi 71 8.0 225 SW of site on Andersontown Road. Andersontown ID 12F1 72 8.6 242 WSW of site on Alpine Road. Maytown ID 13F1 73 7.8 260 W of site on Route 382. In mile north of Lewisberry 10 14F1 74 8.0 292 WNW of site on Evergreen Road. Reeser's Sumit i
SW.lD 15F1 75 8.5 308 NW of site across from parking lot of Steelton Water Co.
d ID 16F1 76 8.1 340 NNu of site on Derry Street. Rutherford Heights f
M.FPL 2GI 77 10.5 9
NNE of site, farm on Route 39. Humelstown ID 3GI 78 16.9 47 NE of site on Cumberland Street. Lebanon ID 4G1 79 10.0 63 ENE of site. Route 241 ID 6G2 80 21.1 113 ESE of site. Steel Way and Loop Roads. Lancaster SW 6G3 81 12.6 122 ESE of site. Chickles Creek SW.ID 7GI 82 14.4 124 SE of site at Columbia Water Treatment Plant SW 7G2 83 13.6 128 SE of site. Wrightsville Water Treatment Plant SW 7G3 84 14.8
,124 SE of site. Lancaster Water Treatment Plant ID 8GI 85 13.2 157 SSE of site. Orchard and Stonewood Roads. Wilshire N111s AP.AI ID 9GI 86 12.6 180 5 of site in Met. Ed. York Load Dispatch Station
' SW 9G2 87 14.7 178 5 of site. York ID 10G1 88 12.7 204 55W of site. Alta Vista and Fox Run Roads. Weiglestown ID llG1 89 11.7 225 SW of site on west side of Route 74. Mt. Royal FPF.ID 12G2 90 11.0 239 WSW of site on west side of Route 74. Rossville ID 13G1 91 13.2 276 W of site. Orchard Lane and Hertzler Road Mt. Allen ID 13G2 92 10.4 274 W of site. Lisburn Road and Main Street. Lisburn ID 14G1 93 12.2 300 WNW of site on Ereford Road. Camp Hill AP.AI.RW.ID 15G1 94 15.0 306 NW of site at West Fairview Substation ID 15G2 95 11.5 307 NW of site. Penn and Forster Streets. Harrisburg ID 1
96 11.2 330 NNW of site. Route 22 and Colonial Road, Colonial Park AQF Indicator All locations where fish were caught below the discharge were grouped together and referred to as " indicator" AQF Control All locations where fish were caught above the discharge were grouped together and referred to as " Control".
l
APPENDIX Sampling Locations Sample Identification Metropolitan Edison identifies samples by a three-part code: The first two letters are the power station identification code, in this case TM. The next one-to-three letters are for the media sampled.
AI = Air Iodine ID = Imersion Dose (TLD)
AP = Air Particulates M = Milk AQF = Fish RW = Precipitation AQP = Aquatic Plants SW = Surface Water AQS = Sediment V = Vegetation E
= Soil MG = Milk (Goats)
FPF = Fruit EW = Effluent Water FPL = Green Leafy Vegetables The last four symbols are a location code based on direction and distance from the site. Of the last four symbols, the first two represent each of the sixteen angular sectors of 22S degrees centered about the reactor site. Sector one is divided evenly by the north axis and the other sectors are numbered in a clockwise direction; i.e., 2 = NNE, 3 = NE, 4 = ENE, 5 = E, etc.
The next digit is a letter which represe,nts the radial distance from the plant:
S~
On-site location E
4-5 miles off-site
=
=
A 0-1 miles off-site F
5-10 miles off-site
=
=
l B
1-2 miles off-site G
10-20 miles off-site
=
=
l C
2-3 miles off-site H
> 20 miles off-site
=
=
D 3-4 miles off-site
=
This last number is the station's numerical designation within each sector and zone; e.g.,1, 2, -...
The location portions of these codes (i.e.,151, 3A1, etc.) are shown in Table A-1 along with detailed information and map coordinate numbers used to designate the individual samples on maps A 1. A-2, and A-3.
Table A-2 summarizes the Threa Mile Island Nuclear Station Radiological Monitoring Program sampling and analysis procedures.
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1* : APPR loMitES MAP A-3 THREE flILE ISLAND NilCLEAR STATION location of Radiological Environmental 11onitoring greater than 5 miles from the site boundaries O
TABLE A-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OF SAMPLE COLLECTION AND ANALYSIS METHODS Approximate Procedure Sample Samp1tng*
Samole size Manual Procedure Analysis Medtum Method Collected Number Abstract Gross alpha AP quaeterly composite of weekly 13 weeks of filters 032-14 sample is leached with nitric or more frequent samples, con-per samp1tng site acid. filtered. and evaporated tinuous air samp1tnq through (s3600Ca.M.)
onto planchette. Low Level gas filter paper flow proportional counting Cross bets AP continuous weekly or more I filter 032-10 low level gas flow proporttonal frequent air sampilng through
($280Cu.M.).
counting filter paper if weekly RW.5d.EW grab or compostte sample 4 liters 032-1 sample is evaporated, residue according to sampling site, transferred to planchette, and various compositing frequen-activity measured by low level ctes counting Gama AP monthly and quarterly compo.
4 weeks or 13 weeks 042-5
- high resolution Ge(L1) gama spectroscopy sites of weekly or more fre-of filters isotopic analysts quent samples; continuous
( ~1100 or 3600 Cu.M.)
air sampling through filter paper 8
y Al continuous weekly or more I cartridge 042-5 same frequent air sampling through (s280Cu.M.)
e charcoal cartridges M
grab or compostte sample 8 liters 042-5 same RW.5W according to sampilng site, 4 liters 042-5 same various compositing frequen-ctes AQF.AQP.
grab sample 2 kg 042-5 same AQS.FPL.FPF Trittum RW.5W.EW grab or compostte sample 4 liters 052-2 water is converted to hydrogen.
according to sampling site.
methane added, and counted in various compositing fregsan-1-11ter ctes 1-131 RW.M.5W.EW grab or composite sample 8 Itters 032-11 anton-exchange, solvent extrac-according to samp1tng site, tion, palladium todide precipl.
various compositing frequen-tate. Iow level gas flow counting cles Sr-89.90 AP quarterly composite of weekly 13 weeks of filters 032-24 strontiuminsample(withcarrier) or more frequent samples, con-per sampilng site is prectpttated as Srr403 mount.
tinuous air sampling through (s3600 Cu.M.)
Sr-90 taferred from Y-90 on ytt-filter paper rium oxalate mount. Iow level gas flow counting AQF grab sample 2 kg 032-23 stellar
- Refer to Tables 8-1 and B-2 for a more complete description of the sampling wthods used.
TABLE A-2 (Continued)
Approximate Procedure Sample Sampling
- Sample Size Manual Procedure Analysis Medium Hethod Collected Number Abstract Sr-89,90 AQS grab sample 2 kg 032-24 similar (c:ntinued)
RW,5W.fW grab or composite sample 4 liters 032-16 similar according to sampling site, various compositing frequen-cies M
grab sample or quarterly 8 liters 032-18 oxalate precipitation of TCA composite sample flitrate, barium and iron sca-venge, 7 day yttrium ingrowth, Sr-90 on yttrium oxalate mount, low level gas flow counting TLD ID dostmeter exchange over TLD 342-17 thermoluminescent dostmetry various time periods C
I (Refer to Tables B-1 end B-2 for a more complete description of the sampling methods used.
9 9
e APPENDIX B CHRONOLOGY OF CHANGES IN THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM e
l l
\\
h
O
- Table B-1 CHRON0 LOGY OF CHANGES EtiACTED DURING 1979 IN THE THREE MILE ISLAND NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
~
3/28/79 Unit 2 Accident 3/29/79 Surface / Drinking water station 9G2 added; Surface / Drinking water changed to daily collection and analysis for Gr-B, y-emmiters, H-3, and I-131; Effluent Water changed to daily collection and analyils for Gr-8, y-emitters, H-3, and 1-131; Milk changed to daily collection and analysis for I-131 and y-emitters; Air Particulates collected and analyzed for Gr-B severy three days; Air Iodine collected and analyzed for I-131 severy three days (including stations 12B1, 9G2, 7F1 and 1C1);
TLD's collected and analyzed for gama immersion dose severy three days.
4/1/79 Milk station 14Cl deleted; Milk station 1401 added.
4/4/79 Drinking Water station 8 elf
- added 4/5/79 Precipitation special samples collected: 8C1, 5Al, l'jG1 and 7Fl; Aquatic Sediment: additional stations sampled and analyzed for Sr-89, Sr-90, and y-emitters: 1A2, 7A1, 7A2, 981, 1081, and 11Al.
4/10/79 Fish: additional sta.tions sampled and. analyzed for Sr-89,,
Sr-90, and y-emitters: Indicator stations (9A2. 9D2, 10A3) and Control stations (13Al,16A2,16B8).
4/22/79 Surface / Drinking Water stations 7G2r* and 7G2f* added.
4/24/79 Milk stations changed to bi-monthly analysis for y-emitters; (I-131 continues daily).
4/27/79 Precipitation special samples collected: 8Cl, 5'A1, 15G1, and 7Gl.
5/2/79 Fish: additional stations sampled and analyzed for Sr-89, Sr-90 and y-emitters:
Indicator station (982) and Control Station (16A1).
5/7/79 Aquatic Sediment:
additional stations sampled and analyzed for Sr-89, Sr-90, and y-emitters: 7A1, IA2, 981, 1081, 11A1.
l 5/15/79 Green Leafy Vegetables: additional station sampled and analyzed for y-emitters:
181.
j l
6/2/79 Milk stations changed to weekly collection and analysis for I-131 and y-emitters; Surface / Drinking Water stations changed to weekly composite,
- f:
finished - potable water
- r: raw - river water
Tablo B-1 (cont.)
analysis for Gr-B, y-emitters, and H-3; (I-131 continues to be analyzed daily);
Milk changed to weekly collection and analysis for I-131 and y-emitters; Air Particulates changed to weekly collection and analysis for Gr-B; Air Iodine changed to weekly collection and analysis for I-131; TLD's changed to monthly collection and analysis for gamma immersion dose.
6/10/79 Drinking Water station 7GlF* added.
6/13/79 Drinking Water station 7G3F* added:
6/24/79 Green Leafy Vegetables: additional stations sampled and analyzed for y-emitters:
781 and 181.
7/16/79 Green Leafy Vegetables: additional stations sampled and analyzed for y-emitters: 781 and 6Gl.
7/7/79 Surface Water station 7G2r* deleted.
7/19/79 Aquatic Sediment: additional stations sampled and analyzed for y-emitters:
7Al and 1081.
8/14/79 Green Leafy Vegetables: additional stations sampled and and analyzed for y-emitters: 181, 5A4, SAS, 6Gl, and 14D2 8/31/79 TLD's - 35 stations added (to be collected and analyzed monthly in September and quarterly thereafter for gamma imme sion dose): 8S1,1052,13S1,15S1, 3Al, 6Al, 7A3, ll A2,1181, 1381,1481,15B1, lE4, 2El, 3E3, 4ES, S.El, 6E6, 7E6, 8E2, 9El,10E3,11E3,12E4,13E4,14E4,15El, 2F1, SF1, 3G1, 6G2, 14G1, -15G2, 7 6G1, and 16El.
10/11/79 Aquatic Sediment: additional stations sampled and analyzed for Sr-89, Sr-90, y-emitters: 7Al and 10Bl.
10/26/79 Intake Water station 1352 added.
12/22/79 Precipitation station 1C1 added.
12/27/79 TLD's - 18 stations added (to be collected and analyzed quarterly for gamma immersion dose): 3F1, 4F1, 6F1, 8F1, 8G1, 9F1, 10F1, 11F1, 12F1, 13F1, 14F1, 15F1, 16F1, 10G1, 11G1, 12G2, 13G1, 13G2. First analyses due in 1980.
- f:
finished - potable water
- r: raw - river water
Table 0-2 DESCRIPTION OF CHANGES ENACTED IN c'.%PLING AND ANALYSIS DURING 1979 IN THE THREE MILE ISLAND NUCLEAR STATION RADIOLDGICAL ENVIRONMENTAL HONITORING PRDGRAM a
Samp13 Sample Method Typs Location
, & Frequency Collection Analyses Comments Surface Water /
TM-SU-lC3 thnual Grab-D W until 3/28; Gr-8 : MC; D: 3'/29-6/1; WC: 6/2-on Drinking D from 3/29-on y
- FC; D: 3/29-6/1; WC: 6/2-on H-3 : MC; QC; D: 3/29-6/1; WC: 6/2-on Water I-131: D: 3/29-cn TH-SW-SElr Manual Composite-D
'W until 3/28;-
~ Gr-8 : HC; D: 3/29-6/1; WC: 6/2-on TH-59-7Gir Auto-Compositor-D D from 3/29-on y
- 11C; D: 3/29-6/1; WC: 6/2-on TH-SW-1SF1 Auto-Compositor-D H-3 : HC; QC; D: 3/29-6/1; WC: 6/2-on Hand Composite-H I-131: HC; D: 3/29-on e
IC T!1-SW-8C2 Auto-Compositor-D Sr-89: QC I
Sr-90: QC TH-SW-9G2 Grab-D D from 3/29-on Gr-8 : i: 3/29-6/1; WC: 6/2-on Station added: 3/29/79 y
- 3: 3/29-6/1; WC: 6/2-on H-3 : L* 3/29-6/1; WC: 6/2-on 1-131: D: 3/29-on TH-SW-DElf Manual Composite-D D from 4/4-on Gr-8 : D: 4/4-6/1; WC: 6/2-on Station added: 4/4/79 y
- D: 4/4-6/1; WC: 6/2-on Hanual Composite-M H-3 : D: 4/4-6/1; WC: 6/2-on 1-131: D: 4/4-on TM-SW-7G2r Manual Grab-D D from 4/22-7/7 Gr-d : D: 4/22-6/1; WC: 6/2-7/7 Station added: 4/22/19 y
- D: 4/22-6/1; WC: 6/2-7/ 7 Station deleted: 7/7/79 H-3 : D: 4/22-6/1; WC: 6/2-7/7 I-131: D: 4/22-7/7 TM-SW-7G2f Manual Grab-D (4/22-D from 4/22-on Gr-s : D: 4/22-6/1; WC: 6/2-on Station added: 4/22/79 7/7) y
- D: 4/22-6/1; WC: 6/2-on Auto-Compositor-D H-3 : D: 4/22-6/1; WC: 6/2-on (7/7-on) 1-131: D: 4/22-on
o Table B-2 (cont.)
DESCRIPTION OF CHANGES ENACTED IN SAMPLING AND ANALYSIS DURING 1979 IN THE THREE MILE ISLAND NUCLEAR STATION RADIOLOGICAL EHVIRONMENTAL HONITORING PROGRfd1 Sample Sample Method Type Location
& Frequency Collection Analyses Conenents Surface Water /
TM-SW-7Glf Manual Composite-D D from 6/10-on Gr-8 : WC; 6/10-on Station added: 6/10/79 Drinking y
- WC; 6/10-on Water (Cont'd)
H-3 : MC: 6/10-on 1-131: D: 6/10-on TM-SW-7G3 Hanual Composite-D D from 6/13-on Gr-8 : WC: 6/13-on Station added: 6/13/79 y
- WC: 6/13-on H-3 : WC: 6/13-on I-131: D: 6/13-on TH-SW-1352 Hanual Grab-D D from 10/26-on Gr-8 : WC: 10/26-on Station added: 10/26/79 y
- WC: 10/26-on H-3 : WC: 10/26-on 1-131: D: 10/26-on TH-SW-6G3 Hanual Grab-D D from 11/26-on 1-131*
Station added: 11/26/79
- Procedure for enacting analysis of TH-SW-6G3:
when a positive iodine result is detected at 7GI or 7G3, 6G3 is analyzed for lodine on the preceeding day, the day of, and the day following the initial positive value.
No analyses required in 1979.
Effluent Water TH-EW-1051 Hanual Grab: W: HC-1/3-3/28 D from 3/29-on Gr-8 : D: 3/29-on Manual Grab: D-3/29,4/1-5/15 Y
- D: 3/29-on Manual Composite:
ly - 5/15, 3ll
[; ff,, ",
0 Auto Comoositore D-5/22-nn
Table B-2 (cont.)
DESCRIPTION OF CHANGES ENACTED IN SAMPLING AND ANALYSIS DURING 1979 IN THE THREE MILE ISLAND NUCLEAR STATION RADIOLOGICAL ErIVIR0tiftENTAL HONITORING PROGRAtt Sample Sample tiethod J re Location 8 Frequency Collection Analyses Connents Air TM-AP-IS2 Auto-Cnmposite-s Every 3 days from Gr-s: s every 3 days 3/29-6/1; Particulates
-8C1 s every 3 days 3/29-6/1; W: 6/2-on
-5Al 3/29-6/1; W 6/2-on
-1281 W 6/2-on
-7F1
-9G1
-15G1
-ICI e
Air Iodine TM-Al-12Bl*
Auto-Composite-S Every 3 days from I-131:
- every 3 days 3/29-6/1; y
-9Gl*
s every 3 days 3/29-6/1; W: 6/2-on
- charcoal cartridges had i
-152 3/29-6/1; W 6/2-on been exchanged but not
-8C1 W 6/2-on analyzed at TM-Al-1281
-5Al and -9GI-- analysis for
-15G1 both stations began 3/29/19.
-7F1
-1C1 Pricipitation TM-RW-8C1 Continuous M
Gr-s : M
- special samples were
-5Al composite-M y
- QC; M: 4/5-on enllected and analyzed
-15G1 H-3 : QC; M: 4/5-on for stations TM-RW-8Cl.
-7F1 1-131: M: 10/31-on
-5A1.
15Gl. -7F1 Sr-89: SA for 3/31-4/5 & 4/5-4/27.
Sr-90: SA TM-RW-ICI Continuous H 12/22-on Gr-8 : M Station added: 12/22/79 composite-M y
- QC; M (12/22-on)
H-3 : QC; M I-131: M Sr-89: SA Sr-90: SA Milk TM-M-581 Station not sampled during 1979
0 Table B-2 (cont.)
DESCRIPTI0'N OF CHANGES ENACTED IN SAftPLING AND ANALYSIS DURING 1979 IN THE THREE HILE ISLAND NUCLEAR STATION RADIOLOGICAL ENVIROOtENTAL 110NITORING PROGRAM Sample Sample Method J oe Location
& Frequency Collection Analyses Coments Hilk (Cont'd)
TM-H-481 Hand Grab-D from 3/29-6/2; I-131: D: 3/29-6/1; H: 6/2-on
-783 0(3/29-6/1);
W 6/2-on y
- H; D: 3/29-4/23*; Bi-M: 4/24-6/l*;
-14C1 W(6/2-on)
Sr-39: QC W: 6/2-on
-2G1 Sr-90: QC
- Bl*
- 181 - D 3/29-5/12; Bf-M: 5/13-6/1 TM-M-14Cl Station deleted: 4/1/79 Tit-H-1401
~ Hand Grab-D from 3/29-6/1; l-131: D: 4/1-6/1; W: 6/2-on Station added: 4/1/79 di D(3/29-6/1);
W 6/2-on y
- M; D: 3/29-4/23; Bi-H: 4/24-6/1; y
W(6/2-on)
Sr-89: QC
. W: 6/2-on Sr-90: QC
.a Fish TM-AQF-9A2 Electroffshing SA y
- SA additional stations
-9D2
& Trapnet Sr-89: SA sampled
-13Al Sr-90: SA
-16A2
~
-16BB
-10A3 Ind. Pred.
Ind. Btm. Feed.
Cti. Pred.
Ctl. Btm. Feed.
Aquatic TM-AQS-7Al Ponar Grab SA y
- SA additional stations Sediment
-llAl Sampler Sr-89: SA sampled Sr-90: SA Aquatic TH-AQP-1A3 Hand Grab SA y
- SA only station where Plants aquatic plants could be found 3
9 h
A %fp
///// \\\\\\
/ #
\\\\ +
te+
'+
eE Ev <e 1,e~
TEST TARGET (MT-3)
I l.0 g a gag
!!yjiE I.I
? "' 1M3
\\
1.8 l.25 1.4 1.6 4
4 6"
MICROCOPY RESOLUTION TEST CHART l
l l 4lllll%
+%74 Y'
%f.
3,
- ~. 4 A
i
Table B-2 (cont.)
DESCRIPTIOf1 0F CHANGES ENACTED IN SAMPLING AND A;iALYSIS DURING 1979 IN THE THREE HILE ISLAND NUCLEAR STATION RADIOLOGICAL ENVIR0fiMENTAL tt0NITORING PROGRAH Sample Sample tkthod Type Location
& Frequency Collection Analyses Comments Green Leafy Vegetables TM-FPL-181 Collection:A
.A y
- A additional stations
.-2G1
.-5A4 sampled
.-5A5
-691
-6G1
-781
-14Cl
-14D2 Y
Dostmeters TM-ID-IS2 Q;
Q; (TLD)
-252 Dosimeter exchanged:
S every 3 days: 3/~ 6/1; Gama insnersion dose: S every 3 days: 3/29-6/1;
-452
% every 3 days 3/29-M 6/2-on H: 6/2-on
-552 6/1; QC
-8C1
-952
-1151
-1651
-1452 74A1
-5A1
-16Al
-1001
-1201
-1C1
-7F1
-4G1
-9G1
-15G1
-7G1
r Table B-2 (cont.)
DESCRIPTION OF CHANGES ENACTED IN SAMPLING AND ANALYSIS DURING 1979 IN THE THREE 111LE ISLAND NUCLEAR STATION RADIOLOGICAL EfMIRONftENTAL MONITORING PROGRAM Sample Sample fkthod Typs location
& Frequency Collection Analyses Comments TLD (Cont'd)
Tit-ID-8SI:
Dostmeter Quarterly: 8/31-on Gama imersion dose:
Stations added: 8/31/79
-1052 exchanged:Q Honthly Sept.
8/31-on
-1351 M Sept.
11 Sept.
-1551
-3Al
-6Al
-7A3
-llA2
-11B1
-1301
-1401
-15B1 g
-lE4 i
-2El
-3E3
-4E5
-5El
-6E6
-1E6
-8E2
-9El
-10E3
-11E3
-12E4
-13E4
-14E4
-15El
-2F1
-5F1
-3G1
-6G2
-14G1
-15G2
-16G1
-16El
KEY: D:
Daily Q: Quarterly WC: Weekly Composite W:
Weekly SA: Semi-annually MC: Monthly Composite Bi-M: Bi-flonthly A: Annually QC: Quarterly Composite M:
fionthly
9 4 J B
APPENDIX C DAIRY CENSUS 9
e I
l
6 4
MILK ANIMAL CENSUS The Environmental Technica'l Specifications for Unit I require that a census be conducted, during the midpoint of the grazing season, to determine the location of cows within a five-mile radius of the plant.1 The Environ-mental Technical Specifications for Unit 2 require that an annual census be conducted during the growing season to determine the location of the nearest milk animal in each of the sixteen meteorological sectors within a distance of five miles.2 These requirements were met by the performance of a complete dairy animal census from August 14 to August 29,1979, which is summarized in the following eight pages.
D 4
4 5
6 0
I l
1 O
l
~
Dairy Cow and Goa t Census Polar Direction & Distance of Hace and Address Breed of # Dairy M Cows M Goats
- Goats Coor.
Yarm from Reactors of Farmer Cattic Cows Milked Hilked T"-1S1 1.02 mi i:
Louise Hardison 12 nannies
- 6. milked used RD 1, iiiddletown 5 kids at hone and 944-0712 1 billy neinhbors T"-1Cl*
2.04 ni N PA Holstein Assoc.
They periodically have cows there for a few days to week Howard Weiss l'or.
for nuarantine before shinnino to foreinn countires.
If Reigle Farm, Poyalton nilked, nilk may be shinoed to Reading Dairy or used for 044-1374 hoo feed if animals recently treated.with antibiotics.
T"-101 3.14 ni il paul Lytle Holsteins 117 02 915 Harrisburg Pike (1)**
liiddletown 944-3432
?
' qg Tii-1E3 4.94 ni il Art Lutz
!!o dairy animals now, may have cow in future IEEE0 PD 1,liiddletown 944-3582 G555) p3 T"-1F3 5.32 mi il t'arlin Pickle.
Holsteins 44 40 19n0 Swatara Creek Rd (2)
(jjj)
Hun'elstown cgggg 56f-0322 (gfj)
T"-1F5 5.32 ni il PrucE Zell Holsteins 90 60 r -'
RD 3 Hummelstown (2) 55 sed
'566-0321, 566-0070 N
- indicates new farms U
- number in parentheses refers to code number for dairy milk is beino shipned to.
See last sheet.
Dairy Cow and Goat Census Polar Direction & Distance of I ame and 7.ddress Breed cf NDa2ry N Cows N Goats NGoats Coor.
Farm from Reactors of Farmer Cattle Cows Milked Milked TII-241 10.5 mi fille Robert 0ellia 1/3 Holstein 38 34 90 4 Humnelstown 2/3 Guernsey (1) 566-0027 TI'-3C1 2.28 mi NE Ira Ruhl Polsteins 20 20 RD 1. Piddletown (2) 944-5060 TM-392 3.20 mi flE Sanuel Saul may have..ooats in fui.:tre 2507 E. Harrisburo Pike "iddletown 944-7198 TM-3E1 a.37 mi NE Russel Kennedy Holsteins 125 75
?
RD 1,fliddletown (3) 944-6289 TM-3E2 4.09 ni IIE Howard Kopp Holsteins 130 95 g
1597 Colebrook Rd.
' (3)-
b@
fdiddletown 944-5023 D
Tit-481 1.05 mi Ef1E Richard Alwine Holsteins 7P.
AS g
RD 1, Middletown (4) 944-3062 Ei'50 T- 4 C1 2.47 ni Ef!E Daul Geyer No dairy animals now, may have cow in future RD 1, Middletown y
94a-3040 y
u
i
~
Dairy Cow and Goa c Census h
Polar Direction & Distance of llame and Addrcss Breed of MDairy H Cows E Goats
- Goats Coor.
Farm from Reactors of Farmer Ca t tle Cows Hilked Hilked 1
i Tf'-4 E1 4.37 mi Ef;E Karl flertzler lloisteins 114 74 2623 fi. f!arket St.
(114 includes 25 bred heiffers at farn in 7E sector)
Elizabethtown 367-2461 TM-4F2 4.76 mi EllE John Hertzler lioisteins 90 50 RD 2, Elizabethtown (5) 357-2377 l
T'-t-4 E3 4.40 ni Ef1E "ahlen Lehman Holsteins 55 da RD 2, Elizabethtown (2)
I 367-2361 Tf'-4 E4 4.18 mi EllE John R. Book Holsteins 57 43
-T RD 2, Elizabethtown (1) 367-1686 T!1-581 1.05 mi E flornan, Craiq and Guernseys &
70 53 t'arvin Miller Holsteins (4)
RD 1 Piddletown q
944-5963 O
b T"-5D1 3.47 mi E Parvey L'.
Esnenshade Holsteins 47 40 I
RD 4, Elizabethtown (2) 367-4196 (unable to contact, must be on vacation, cattle pres assume same number) 4 TM-5E1*
4.01 ni E h' alter Halbleib 1 nanny not plannin RD 4, Box 186 milk Elizabethtown
)
367-4535 2E o
l
{E
~
l
~
i 1
1 Dairy Cow and Goat Census Polar Direction & Distance of
- ace and Address Breed of HDairy H Cows M Goats
- Goats Coor.
Farm from Reactors of Farcer Cattle Cows Hilked j!ilked T"-6C1 2.33 mi ESE Jay Swooe Holsteins 42 23 P.D 4, Elizabethtown (a)
}
367-2927 T'l-6D1 3.23 mi ESE David G. Miller Holsteins 65 41 P.D 4. Elizabethtown (2) 3E7-2914 Tft-603 3.80 mi ESE Herman L. Zaeoer Holsteins ~
64 44 Paul Swanoer,' f4or.
(2)
~
P.D 1. Bainbridae 367-2090 l
A T!1-604 3.57 mi ESE Elrer F. Gruber Holsteins 48 32
';3 P.0 1, Bainbridoe (3) 367-3108 Tit-6El 4.23 ni ESE Forrey I'innich Holsteins 7
4 P.D 4, Elizabethtown
- (home use only)
~ c2 367-3145 o
Tit-6E3 5.04 ni ESE Georne Eaun Holsteins 48 40 a
P.D 1. Elizabethtown (5) 367-2577 TI'-6Fa 5.30 mi ESE
. Albert L. Wilson Ayrshires 155 105
!'asonic Homes (1) orocessed at dairy and most Elizabethtown returned to Homes for use 357-3181
Dairy Cow and Goat Census Polar Direction & Distance of Name and Address Dreed of HDairy H Cous M Goats NGoats Coor.
Farm from Reac: ors of Farmer Cattle Cows Milked Hilked Tri-783 1.43 mi SE Christian Becker Holsteins 30 32 RD 4, Elizabethtown (2) 367-2056 Ti'-7 Cl 2.57 mi SE Cathryn fi. Schrall Jerseys 5
cows dry, I wether RD 4, Bainbridae uses to feed doqs f. cats Tit-7El 4.10 mi SE Donald Risser Holsteins 168 112 RD 1, Bainbridoe (a) 367-4626 Ti*-7E2 4.72 ni SE Menno Gruber lloisteins 60 50 E
367-3162
~
(2)
Y RD 1, Bainbridae Tf'-7 E3 4.74 mi SE Daniel Brenneman Holsteins 22 17 RD 1, Bainbridae
'(4) c 367-3157
(
Til-7E4 4.03 mi SE Edward L. or Holsteins 105 64 2 wethers Russell Shocp (2)
RD 1, Bainbridae 367-6292, 367-2025 2
T't-7 E5 4.62 ni SE Georoe Stone c~ $
2 nannies 2 milk used at RD 1, Bainbridge 1 billy home 367-3220
@fD 2 kids Eg p
Dairy Cow and Goat Census Polar Direction & Distance of Name and Address Drecd of NDairy H Cows M Goats NGoats Coor.
Farm from Reactors of Farmcr Cattle Cows Milked Hilked s
l Tit-7F2 5.13 ni SE Lester Hawthorne Holsteins 190 120 RD 1, Elizabethtown (5) 367-3248 TM-8Cl*
2.61 mi SSE Lloyd r,ilder 2 nannies will milk RD I, Box 176 1 billy when fresh Bainbridae 367-5104 T't-901
- 3.60 mi S Stanley E. Druck 2 nannies too young to RD 1,flanchester 2 billies breed 266-4544 Tri-902
- 3.61 mi S Rodney Stoner 1 nanny toooldtoh' RD 1 Panchester milk 266-3224 Tit-903*
3.63 ni S
~
Ronald Laehr 1 nanny pet - not RD 1 P.anchester planning to 266-4682 milk
- TM-904*
3.88 ni S Lester Shamber l nanny will milk RD 1, !!anchester N
1 billy when fresh 266-4954 C
T'4-1091 3.14 mi SSM
- William Ruby 1 billy RD 1, York Haven 266-3555 e
Dairy Cow and Goa t Census Polar Direction & Distance of 1:a=e and Address Breed of MDairy M Cows
- Goats NGoats Coor.
Farm from Reactors of Farmer Cattle Cows !!ilked
!!ilked f
T"-10E1 4.86 mi SS!-!
Doll Zirkle Holsteins 39 23 RD 2,ttanchester (5) 266-2582 T't-10E2 4.91 mi SSH Josenh Marchione 1 nanny 1 milk used RD 2, Manchester 1 kid at home 2E6-1641 T'It-1101 3.75 mi SW Richard Fox 1 nanny
- just raises RD 1, York llaven 2 billies kids 933-3113 T:*- 11 E'.
4.33 mi SW Dan Sipe 2 nannies 2 doas killed RD 1. York Haven rest of herd T't-129.1
- 1.48 ni MSW Carole Carleton 1 nanny not milking Box 1, RD 2 nresently Etters 933-6273 TI'-12 E1 4.03 mi USl!
Jacob l'ise 5tols teins 1
RD 1. York Haven 93F,-2951 T"-12E2 4.40 mi USt' DelohesLomman 1 nanny
- no plans RD 1, York Haven 1 billy to milk e
t
Dairy Ccw and Goa t Census Polar Direction & Distance of Name and Address Breed of MDairy H Tows N Goats NGoats Coor.
Farm from Reactors of Farmer Ca:tle Cows P ked Milked TP-12E3 4.76 mi USU Preston Mitners 3 nannies 3 feed to other RD 1, York Haven animals' 938-5062 TM-14D1 3.64 mi UNU Jeremiah K. Fisher Holsteins a3 33 1 billy RD 1, Etters (5) 93S-6628 TD-14D2 3.23 ni UNW Vance E. Fisher 4 nannies animals didn't RD 1, Etters 2 kids breed, will 938-2762 milk in future TM-1403 3.08 mi MNk' San Conley Holsteins 2
RD 1, Etters calves nursing, will milk for home use in future TM-14E1 5.04 ni WNH John Beinhower Holsteins 1
1 RD 1, Etters u_qgg TM-14E2 4.23 ni UNW E.S. Whitehill 2 nannies 1
g-)
RD 1, Etters 2 billies R
[3ME9 Totals 2190 1512 37 nannies 15 15 billies O
10 kids pg, gg 3 wethers j
w
- New farms added this census
((})
- Dairies to which farmers sell milk are numerically listed below.
If no indication is aiven in the table as to use of the milk, it is used for hone use only.
!! umber after the dairy name indicates the number of farms
- sred selling to each dairy.
cggg3
- 1. Harrisburn Dairies a
}.
Penn Dairies, Lancaster - 3
- 5. Interstate - Penn Suoreme - 5
- 2. Pershey Foods - 10
- 4. Mt. Joy Farmers Coon-Lehich Valley - 5 6. Vengert's, Lebanon - 1
O m
- 4 M
-- ese
=+ m m
M he e
4 Na-6 M*
Gn&
--6 mehe W
4 APPENDIX D EPA CROSS-CHECK PROGRAM 6
RESULTS OF LICENSEE PARTICIPATION IN THE ENVIRONMENTAL PROTECTION AGENCY'S ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES (CROSS-CHECK) PROGRAM The Environmental Technical Specifications for Three Mile Island Unit 2 require that the results of licensee participation in the Environ-mental Protection Agency's Environmental Radioactivity Laboratory Inter-comparison Studies (Cross-check) Program be presented in the.innual report.2 This section contains those results through September, 1979, the latest date for which the Environmental Protection Agency has reviewed and supplied the results.
-i h
9 0
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QttALITY ASSURANCE P R OG R t.f4
~
INTEF.CC:!?ARISCN tlITII:
USEPA (EMSL-LV)
DATE FI! AL REPORT l'. AILED:
p.qc:;n;at:
Strontium-89 and Strontium-90 in water cross-check COLLECTION DATE:
January 5, 1979 TEl.EDYt:5 NORMAL.IZED ISOTOPES CRAND DEVIATION EPA TI/ EPA TYPE OF NL'CLI DE I
- N CODE rCJ AVERAGE
( KN0'clN)
RESOLUTICN P *,T I O AG EE"E';T Sr-89(pCi/literh 14 1 5 11 2 2
- 0.7
- 1.0 2.8 0.79 AG l 44 participants 13 1 4 l
l Sr-90 (pCi/ liter) 61 1.5 41 1
~
- 1.7
- 1.9 4.0 0.67 AG I
4S narticipants 6! 2
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(AG) AErec=en:
li.O. !:o. 3-2923 (5) Gr nd average : cxperimental signa for participants reporting (P) Possible aErec ent T.I.1;os. 62106-8 (C) Average i experi= ental *.ig:ra (D) Disagreement.
Program 116
~
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USEPA (EISL-LV)
DATE FINAL REPORT MAILED:
P RO~,R/d::
Radionuclides in nilk cross-chetk COLLECTION DATE:
January 26, 1979 TEl.EDYt;E
!;0ll:4ALIZED ISOTOPES CilAND DEVIATICN EPA TI/ EPA TYPE 0.:
NL*CL!CE
' uni CC3E t'CJ AVERT.GE (KNC'c.'N)
RESO LUTIO.'1 P.*,T I O AGREE."E 7 I
lSr-E9 (nci/ liter) 33 2 5 16 2 5
?
- 5.8 r6 0.4S P
- rc.rticirants 29 2 4 t
5r-90 (pCi/ liter) 19 2 1.5 13 t 3
- 4.2
- 6.5
[
12.7 0.68 l
AG i
25 esrticipants 17 2 3 l
I-131 (rCi / l i t er) 105 1 5 117 t 6 3.6 j.
21 1.11 AG 4.0 N
l 43 narticinants 106 2 8 4
- 8 I
I 51 1 9 0.6 I
9.8 1.04 AG Cs-137 (pCi/ liter) 49 1 5
- 0.2 I
43 rarticinants 51 ! 4
]
19.7 0.89 AG K(cic=) (r.c / l i t er) 1560 178 1390 279
- 2. 4
- 3.8 l
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\\l199 113 c r a.-
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Program 118 (C) Aversco 1 experimental sigra E?.TERED:
I:nc 21, ?
4 OUALITY ASSUD.ANCE PROGRAM D;TE?.CCM?ARISON WITil:
USEFA (EMSL-LV)
DATE FI!!AL REPORT MAILED:
? ?.C';7.U:: Ga :.a in water cross-check COLLECTION DATE:
Feburary 2, 1979 TELEDY::E
?;0RMAI.I ZED ISOTO?ES Ci!AND DEVIATION EPA TI/ EPA TYPE OF
';'
- E !.
- E E
- : n ;,
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AVEP. AGE (KNONN)
RESOLUTION RATIO AGsEEMENT Cr-51 (pCi/ liter)
O L.T. 70 l-paticipants l
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I C0-60 (pCi/ liter) 915 13 1 2 1.1 1.4 l
1.8 1.4 AG 1 52 participants l
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1.2 1.2 AG M '5 artici-ants 712 ll oCs-137 (pCi/ liter) 12 2 5 15 1 3 0.5 0.9 l
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(AC) Agreement W.O. } o. 3-30S6 (E) Crand average i experi=ca:21 sig=a for participants reporting (P) Pcssible agreement T.I. !!os. 63237-9 (C) Average i experimental sigma
.D) Disagrec=cnt' Program 119
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QUALITY ASSURANCE PROGRAM INTEflCO.\\lPARISON 1i1111:US EPA ( E.1S L-LV)
DATE FINAL REPORT MAILED:
PROGRMI:
Air Filter Cross-Check COLLECTION DATE:
.\\t\\RCil 30, 1979 TELEDYNE NORMALIZED ISOTOPES GRAND DEVIATION EPA TI/ EPA TYPE OF NUCLIDE
Epi CODE #CJ AVERAGE (FNOWN)
RESOLUTION RATIO AGREEMENT GR-A(pCi /fi ll 14 ! 5 16 ! I n.7 0.8 2.8 1.1 AG h
6 particinants 14 1 3 GR-B(nci / fi ll 63 ? 5 67 ! 2 0.7 1.3 12.6 1.1 AG 64 participants 65 1 6
'ln Sr-90 (pCi/ fill 21 1.5 No data nro vided!
14 No data provided Y
Y 21 entticinants 10 t 3 7
pf Cs-137 (pCi/fil) 21 1 5 19 ! 3
-1.4
-0.6 4.2 0.9 AG
'S participants 23 1 5 28 Ch&
W 55E3 c--,
iJ (A) Expected laboratory precision (1 sigma,1 determination)
(AG) Agreement W.O. No.
3-3425 (B) Grand average i experimental sigma for participants reporting (P) Possible agreement T.I. Nos. 65740-2 (C) Average.1 experimental sigma (D) Disagreement.
PROGRAM 124
)
ENTERED: DEC. 28, 1979
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9 OUALITY ASSURANCE PROGRAM INTERCOMPARISON WIT 11:
USEPA (EMSL)
DATE FINAL' REPORT !%ILED:
PP.C3 RAM:
Laboratory Perfornance Evaluat ion Studv COLLECTION DATE:
APRIL 20, 1%'9 i
TELEDYNE NORMALIZED ISOTOPES GRAND DEVIATION EPA TI/ EPA TYPE OF NUCLIDE
' Epi COJE #CJ AVERAGE (KNOWN)
RESOLUTION RATIO AGREEMENT I
GR-A (pCi/ liter) 22 2 5 28 2 4 0.8 2.0 1 4.4 1.3 AG h
60 nnrticinants!
25 : 8 GP-B (pCi/ liter) 44 2 5 44 1 3 0.1 0.1 8.8 1.0 AG 55 participants 4316 Sr-S9(pCi/ liter) 91 5 72 1
-1.0
-0.7 1.8 0.8 AG f
33 participants 10 1 4 a
l5.3 0.8 AG Y
Sr-90(pCi/ liter) 81 1.5 61 1
-1.7
-1.9
- 0 narticinants 8! 1 Ra-226(pCi/ liter) 5.9 2 0.9 20.1 11.2 22.3 27.3 6.6 3.4 D
42 participants 8.5 1 6.3 g
Ra-22S(pCi/ liter) 6.2 1 0.9 No data prov ided' ll Q
32 participants 8.1 2 4.2 Vio I
cont inued c =a (A) Expected laboratory precision (1 sigma, 1 determination)
(AG) Agreement W.O. No.
3-3599 h
(B) Grand average i experimental sigma for participants reporting (P) Possible agreement T.I. Nos.67163-5 PROGRAM 127 M
(C) Average i experimental sigrra (D) Disagreement.
ENTERED:
DEC.2S, 1979
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USEPA (EMSL-LV1 DATE FINAL REPORT MAILED:
PRCGRAM:
Milk cross-check COLLECTION DATE:
APRIL 27, 1979 TELEDYNE NORMALIZED ISOTOPES GRAND DEVIATION EPA TI/ EPA TYPE OF UUCLIDE
Eod CODE #CJ AVERAGE (KNOWN)
RESOLUTION RATIO AGREEMENT S r-S9 (pCi /11t er) 4215-14 1 0-
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- 9.7 8.4 0.33 D
29 carticipants 34 112 Sr-90(pCi/ liter)'
54 1 3 43 1 4
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1-131 (pCi/ liter) 96 1 5 115 ! 16 5.1 6.6 19 1.20 AG BC participants 100 110
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PROGRAM 126 b
ENTERED: DEC. 28, 1979
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QUALITY ASSURANCE PROGRAM USEPA (DISL-LV)
INTERCOMPARISON IflTil:
DATE FINAL REPORT MAILED:
PROGRMt:
Radium in water cross-check COLLECTION DATE:
JU.'iE 22, 1979 TELEDYNE NORMALIZED ISOTOPES GRAND DEVIATION EPA TI/ EPA TYPE OF I;UCLIDE
Eok CCDE tlCJ AVERAGE (KNONN)
RES0iMTION RATIO AGREEMENT Ra-226fpCi/ liter) 9.4 1 1.4 7.6 1 0.3
-0.9
-2.2 6.7 0.31 AG 20 narticinants 8.3 : 1.2
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PROGRAM 134 1
ENTERED: JAN. 2, 1980
9
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QUALITY ASSURANCE PROGRAM I!TTERC051 PARIS 0ft WIT 11: USEPA (EMSL-LV)
DATE FINAL REPORT MAILED:
COLLECTIOri DATE:
JUNE 29, 1979 0400 PST PROGRAM: ATR FILTER CROSS-OlFCK TELEDYNE NORFIALIZED ISOTOPES
" RAND DEVIATION EPA TI/ EPA TYPE OF NUCLIDE
' poi CODE #CJ
!VERAGE (KNOWN)
RESOLITTI0fl RATIO AGREE!!ENT I
GROSS ALPilA
(;)Ci / fi l t er) 9 5
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GROSS BETA (tiCi / fi l t e r) 30 5
32 i 1
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PROGRAM
_137 EITTERED: Fl\\RCil' 10, 1950
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DATE FINAL REPORT MAILED:
PROGRAM:
RADIUM IN WATER CROSS-CliECK COLLECTION DATE:
SEPTEFEER 14 1979 TELEDYNE NORMALIZED ISOTOPES GRAND DEVIATION EPA TI/ EPA TYPE OF NUCLIDE
- Epi CODE #CJ AVERAGE (KNOWN)
RES0ttITION RATIO AGREEMENT (A)
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ENTERED: 'EnCI! 10. 1999
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[
1.0 L.T.
Sr-89(pCi/ liter) 5iS L.T.5 I0) 26 participants 6
3 Sr-90 (pCi/ liter 11 2
10 2 (C)
-1.3
-0.9 5.5 0.91 AG fA) 31 participants 12 1 2 (B)
IAI 18 1 3 (C) 0.1 0.5 3.4 1.1 AG 1-131 (pCi/ liter-)
17 1 5 IO) 31 particinants IP i4 I^)
13 1 1 (C)
-0.1 0.2 2.4 1.1 AG Cs-137 (pCi/ liter 12 1 5 I
35 participants 13 1 3 Ba-140 (pCi/ liter)
O L.T.
10 6.__3 31 pa rt i ci pant s -
0 9
K f ohm)(mg/ liter) 1630 81 1720 1 265 3.3 1.9 20 1.1 AG g
32 participants 1567 ! 117
{&3 a@
w Wg (A) Expected laboratory precision (1 sigma,1 determination)
(AG) Agreement W.O. No. 3-4376 b
(B) Grand averagc 1 experimental sigma for participants reporting (P) Possible agreement T.I. Nos.72378-So PROGRAM 136 (C) Average i experimental sigma (D) Disagreement.
EhTERED: sjm n! In. 19c7
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