ML19305C614
| ML19305C614 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 02/12/1980 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML19305C608 | List: |
| References | |
| NUDOCS 8003310149 | |
| Download: ML19305C614 (46) | |
Text
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$ HAZLETCON ENVIRONMENTAL SCIENCES CORPORATION 1500 F f40N T AGE 510 A0 NOn1 HE35400K. 8LLINCIS 600G2. U ri A e
NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NO.
50-282 LICENSE NO. DPR-42 50-306 DPR-60 ANNUAL REPORT to the UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1, 1979 to December 31, 1979 a
Prepared Under Contract by HAZLETON ENVIRONMENTAL SCIENCES CORPORATION Project No. 08902 Approved by:
Wu B.
G. Johpson, Ph.D.
Vice President and Technical Director 4
12 February 1980 PHONE. (3121564-0 700 o
T E L E x 20-04H3 (H A2t.5 N054kl N9' 8008810 af
HAZLETON ENVIZONMENTAL CCI~NCOO PREFACE
~
This report was prepared by Leonid G.
Huebner, Director, Nuclear Sciences Department, Hazleton Environmental Sciences
=
Corporation.
The members of the Nuclear Sciences Department staff were responsible for the acquisition of the data presented in this report.
The staff includes C. A. Galloto, C. Marucut, L.
- Nicia, J.
Salmorin, and D.
Rieter.
Environmental samples were collected by personnel of Northern States Power Company.
Distribution of this report is made by Northern States Power 4
Company.
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HAZLETON ENVIRONMENTAL CCCNCOO TABLE OF CONTENTS Page Preface............................................
11 List of Tables.....................................
iv I.
Introduction.......................................
1 II.
Summary............................................
2 III.
Program............................................
3 A.
Program Design and Data Interpretation........
3 B.
Program Description...........................
5 C.
Program Execution.............................
7 D.
Laboratory Procedures.........................
7 E.
Program Modifications.........................
8 F.
Census of Milch Animals.......................
8 IV.
Results and Discussion.............................
10 a
A.
Effects of Chinese Atmospheric Nuclear Detonation..................................
10 B.
Program Findings..............................
11 l
V.
Tables.............................................
18 1
VI.
References Cited...................................
27 Appendix A.
Crosscheck Program Results...............
A-1 B.
Data Reporting Ccnventions...............
B-1 C.
Maximum Parmissible Concentrations of Radioactivity in Air and Water......
C-1 e
lii
HAZLETON CNVIRONMENTAL. SCENC30 LIST OF TABLES No.
Title Page 1
Sample collection and analysis program, 1979.......
19 2
Sampling locations.................................
21 3
Missed collections and analyses, 1979..............
22 4
Environmental radiological monitoring program summary........................................
23 In addition, the following tables are in the Appendix:
Appendix A A-1 Crosscheck program results, milk and water
- samples, 1975-1979............................
A-4 A-2 Crosscheck program results, thermoluminescent dosimeters (TLD's)............................
A-9 Appendix C C-1 Maximum permissible concentrations of radioactivity in air and water................
C-2 i
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HA2LETON ENVIRONMZNTAL. CCf!NCHO I.
Introduction This report summarizes and interprets results of the Operational Radiation Environmental Monitoring Program conducted by Hazleton Environmental Sciences Corporation at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January -
December, 1979.
This program monitors the levels of radioactivity the air, terrestrial, and aquatic environments in order to assess the impact of the plant on its surroundings.
Tabulation of the 1".dividual analyses made during the year are not included in this report.
These data are included in a reference document (Hazleton Environmental Sciences Corporation, 1979) available at Northern States Power Company, Nuclear Support Services Department.
Prairie Island Nuclear Generating Plant is located on the Mississippi River in Goodhue County, Minntsata, and operated by Northern States Power Company.
The plant has two 550 MWe pressurized water reactors.
Unit 1 achieved initial criticality on 1 December 1973.
Commercial operation at full power began on 16 December 1973.
Unit 2 achieved initial criticality on 17 December 1974.
- Commercial operation at full power began on 21 December 1974.
e 1
H AZLETON CNVIRONMENTAL CCIZNC'23 II.
Summary The Operational Radiation Environmental Monitoring Program required by the U.S.
Nuclear Regulatory Commission (NRC) Technical Specifications for the Prairie Island Nuclear Generating Plant is described.
Results for 1979 are summarized and discussed.
No effect on the environment due to the operation of the Prairie Island Plant is indicated.
There was, however, a slight ef fect of the fallout from the atmospheric nuclear detonation of a less than 20 kiloton device on 14 December 1978 which resulted in an elevated gross beta activity in airborne particulates during the first quarter of 1979.
The presence of the long-lived fission products, strontium-90 and cesium-137, in several sampling media indicated a long range fallout effect from previous atmospheric nuclear detonations.
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HA2LETON ENVIRONMENTAL SCCNC]O III. Program A.
Program Design and Data Interpretation The purpose of the Operational Radiation Environmental Monitoring Program at the Prairie Island Nuclear Generating Plant is to assess the impact of the Plant on its environment.
For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content.
In addition, ambient gamma radiation levels are monitored by thermo-luminescent dosimeters (TLD's).
Sources of environmental radiation include the followings (1) natural background rsdiation arising from cosmic rays and primordial radionuclides; (2) fallout from atmospheric nuclear detonations; (3) releases from nuclear power plants.
In interpreting the data, effects due to the Plant must be distin-guished from those due to other sources.
A major interpretive aid in assessment of these effects is the design of the monitoring program at Prairie Island which is based on the indicator-control concept.
Most types of samples are collected both at indicator locations (nearby, downwind, or down-stream) and at control locations (distant, upwind, or upstream).
A plant effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location.
The difference would have to be greater than
~
could-be accounted for by typical fluctuations in radiation levels arising from other sources.
3
HAZLETON ENVIRONMZNTAL. SCCNCT3 An additional interpretive technique involves analyses for specific radionuclides present in the environmental samples collected from the Plant site.
The Plant's monitoring program includes analyses for tritium, strontium-89, strontium-90, and iodine-131.
Most samples are also analyzed for gamma-emitting isotopes with results for the following quantified:
zirconium-95, cesium-137, cerium-144, and potassium-40.
The first three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and in the mix produced by a nuclear detonation.
Each of the three isotopes is produced in roughly equivalent amounts by a reactor:
each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown.
On the other hand, 10 s
days after a nuclear explosion, the contributions of zirconium-95, cesium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963).
Potassium-40 is a naturally-occurring isotope.
It was chosen as a calibration monitor and should not be considered a radiological impact indicator.
Other means of distinguishing sources of environmental radiation can be employed in interpreting the data.
Current radiation levels can be compared with previous levels, including those measured before the Plant became operational.
Results of the Plant's Monitoring Program can be related to those obtained in
~
l other parts of the world.
Finally, results can be related to l
l 4
HAZLETON ENVIRONMENTAL SCENCZG 1
events known to cause elevated levels of radiation in the environ-J
- ment, e.g., atmospheric nuclear detonations.
B.
Program Description The sampling and analysis schedule for the environmental radiation monitoring program at Prairie Island is summarized in Table 1 and briefly reviewed below.
Table 2 defines the sampling location codes used in Table 1 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the reactor site.
To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Hazleton Environmental Sciences Corporation, 1978c).
To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at four A
locations. Also, airborne iodine is collected by continuous pumping through charcoal filters at three of these locations.
Filters are changed and counted weekly.
Particulate filters.are analyzed for gross beta activity and charcoal filters for iodine-131.
A monthly composite of all particulate filters is gamma-scanned on a Ge(Li) detector.
Two of the four locations are indicators, and two are controls (P-1 and P-2).
One of the indicators (P-3) is locatad near the residence expected to be most susceptible to any atmospheric emissions from the Plant (highest X/O residence).
Ambient gamma radiation is monitored at the same four locations using CaF2:Mn thermoluminescent dosimeters (TLD's).
5
HAZLETON ENVIRONMENTAL. SCCNCZO The sensors are placed in pairs at each location and are collected and measured quarterly.
Milk samples are collected monthly from five farms (four indicator and one control).
All samples are analyzed for iodine-131.
In addition, samples from the control location (P-25, Kinneman) and the highest X/O location (P-14, Gustafson) are analyzed for strontium-89, strontium-90 and for gamma-emitting isotopes.
For additional monitoring of the terrestrial environment, natural vegetation (such as grass) is collected semi-annually from three locations (including the highest X/O milk location P-14 and the milk control location P-25).
Eamples are analyzed for gamma-emitting isotopes including iodine-131.
Cabbage is collected annually from a garden nearest the P.. ant and a control location (P-25) and analyzed for iodine-131.
Corn is collected annually from the highest X/O farm (P-14) and a control location (P-25) and analyzed for gamma-emitting isotopes.
Also, well water is collected quarterly and analyzed for tritium and gamma-emitting isotopes.
Finally, topsoil is collected every three years and analyzed for strontium-90 and gamma-emitting isotopes.
River water is collected weekly at two locations, one upstream of the Plant (P-5) and one downstream (P-6, Lock and Dam
- 3).
Monthly composites are analyzed for gamma-emitting isotopes.
Quarterly composites are analyzed for tritium, strontium-89, and i
Drinking water is collected weekly from the City of Red Wing well.
Monthly composites are analyzed for gross beta 6
HAZLETON ENVIRONMENTAL CCCNCEJ activity and gamma-emitting isotopes.
Quarterly composites are analyzed for tritium.
The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, periphyton or macro-invertebrates, aquatic vegetation, and bottom sediments.
Shoreline sediment is collected semi-annually.
C.
Program Execution The Program was executed as described in the preceding section with the following exceptions :
(1)
TLD data are not available for the first quarter of 1979 because of thef t of the dosimeters.
(2)
Airborne particulate data and airborne iodine-131 data from location P-4 for the period 5-22 to 5-30-79 are not available due to a power outage during the rebuilding of this substations.
These deviations from the Program are summarized in Table 3.
I D.
Laboratory Procedures All strontium-89, strontium-90, and iodine-131 enalyses l
in milk were made by using a sensitive radiochemical procedure which involves separaton of the element by use of an ion-exchange resin and subsequent beta counting.
Gamma-spectroscopic analyses of milk and water were performed with a NaI detector.
All other gamma-spectroscopic analyses were performed with a Ge(Li) detector.
Levels of iodine-131 in cabbage and natural vegetation were determined by Ge(Li) 7
HAZLETON ENVIRONMENTAL CCIENC:23 spectrometry.
Levels of airborne iodine-131 in charcoal samples were measured by Ge(Li) spectrometry.
+
Tritium levels were determined by liquid scintillation counting.
Analytical procedures used by the Nuclear Sciences Department of Hazleton Environmental Sciences Corporation are specified in detail elsewhere (NALCO Environmental Sciences, 1977a).
Procedures are based on those prescribed by the National Center for Radiological Health of the U.
S. Public Health Service (U.
S.
Public Health Service, 1967) and by the Health and Safety Laboratory of the U.
S.
Atomic Energy Commission (U.
S.
Atomic Energy Commission, 1972).
Hazleton Environmental Sciences Corporation has a com-prehensive quality control / quality assurance program designed to assure the reliability of data obtained.
Details of Hazleton's QA Program are presented elsewhere (NALCO Environmental Sciences, 1971a, 1971b, 1975). The HES QA Program includes participation in laboratory intercomparison (crosscheck) programs.
Results obtained in crosscheck programs are presented in Appendix A.
E.
Program Modifications No modifications of the program involving changes in the Technical Specifications were made during 1979.
F.
Census of Milch Animals During 1979 several surveys of milch animals were con-ducted in the area of the Plant.
On 15 June 1979 an extensive survey was conducted within a one mile radius of the Plant (or 15 mrem / year distance).
-Mo s t I
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HAZLETON CNVIRONMENTAL CCl!NCOZ3 cattle observed were used for beef rather than milk production.
No new milk producing herds were found.
On 22 June 1979 a census for milk cows within a five mile radius was completed.
With the assistance of the Agricultural Agent of Goodhue and Pierce Counties, it was determined that several milk herds had changed ownership.
Current raw milk sampling locations were not affected.
No new herds were identified.
On 22 June 1979 a census of goat herds within a 15 mile radius of the Plant was completed.
Af ter visits with three county agricultural agents, a county 4-H Agent, and several members of the Wisconsin Dairy Goat Association, it was determined there were no reliable suppliers of goat milk in the area.
Most herds in the area are kept as hobbies or as part of youth education programs conducted by 4-H organizations.
Although goat milk sampling is not a part of the routine program certain goat milk samples, when available, were collected and analyzed.
On 21 August 1979 the mid-season census of milch pro-ducing animals was completed.
No new herds were identified.
None of the surveys resulted in changes of milk sampling locations.
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9
MA2LETON ENVIRONMENTAL CCl~NC2']
i IV.
Results and Discussion All of the scheduled collections and analyses were made except those listed in Table 3.
All results are summarized in Table 4 in a format recommended by the U.S. Nuclear Regulatory Commission in Regulatory Guide 4.8.
For each type of analysis of each sampled medium, this table lists the mean and range for all indicator locations and for all control locations.
The location with the highest mean and range are also shown.
A.
Effects of Chinese Atmospheric Nuclear Detonation There were no reported atmospheric nuclear detonations during 1979.
Only one of two atmospheric nuclear detonations conducted by the People's Republic of China in 1978 had limited impact on program results in 1979.
The first detonation was conducted on 14 March 1978.
This test had no short term effect on the level of radioactivity in 1979.
A second detonation conducted by China on 14 December 1978 resulted in an increase in gross beta activity in air particulates collected during the first quarter of 1979.
This section briefly reviews information about the tests, as reported by the EPA (U.S. Environmental Protection Agency, 1978).
The 14 March 1978 test had an estimated yield of less than 20 kilotons.
The National Oceanic and Atmospheric Administration predicted that the fallout cloud would reach the United States on l
March 18.
EPA gross beta results for air particulates indicated that the main body of the cloud had reached the central United States by 23 March 1978.
10
Havn NTON CNVIRONMENTAL SCCNC~D The 14 December 1978 test had an estimated yield of less than 20 kilotons.
This test had a limited effect on gross beta e
activity in particulates collected during the first quarter of 1979.
The usual spring peak, a phenomenon that is observed worldwide almost annually (Wilson et al., 1969) was not evident in 1979 (1976 was also an exception).
These spring peaks have been attributed to fallout of nuclides from the stratosphere (Gold et al., 1964).
B.
Program Findings A number of program findings reflect effects of the latest Chinese and previous worldwide atmospheric nuclear tests.
The chief environmental indicators of test effects were airborne particulates.
1.
Ambient Radiation (TLD's)
Indicator TLD's averaged 12.6 mrem /91 days and control TLD's averaged 15.3 mrem /91 days.
The doses measured by control TLD's were about 20% higher than indicator TLD's.
The dose rates measured were similar to those observed in 1978 (12.1 and 15.1 mrem /91 days, respectively).
2.
Air Particulates The average annual gross beta activity in airborne particulates was 0.037 pCi/m3 at indicator locations and 0.038 pCi/m3 at control locations and was 60% lower than in 1978 (0.093 pCi/m3).
In the first quarter of 1979 weekly gross beta activity averaged 0.053 pCi/m3 At the end of the first quarter gross beta 11
HAZLETEN ENVIRONM2NTAL CCCNCOO activity dropped to about 0.030 pCi/m3 and remained relatively constant throughout the rest of the year.
4 Elevated gross beta activity during the first quarter was due to fallout from the 14 December 1978 weapons test.
Two pieces of evidence indicate conclusively that the elevated activity observed during the first quarter was_not attributable to the Plant.
In the first place, elevated activity of similar size occurred simultaneously at both the indicator and control locations.
Secondly, an identical pattern was observed at the Monticello Generating Plant, some 100 miles distant from the Prairie Island Generating Plant (Northern States Power Company, 1980).
All gamma-emitting radionuclides in airborne particulates were below their respective LLD's.
Thus, there was no indication of a Plant effect.
3.
Airborne Iodine Airborne iodine-131 results were below the detection limit of 0.02 pCi/m3 in all samples.
Thus, there was no indica-tion of a Plant effect.
4.
Milk All-results for Iodine-131 were below the LLD of 0.25 pC1/1 including five goat's milk samples.
Zirconium-95 and cerium-144 were not detected.
Strontium-90 results averaged higher at the control location (P-25, Kinneman-Farm), and all detectable results were in the 12
Matt ETON ENVIRINMENTAL CCCNCCJ range 2.1 - 5.1 pCi/1, a range consistent with 1976, 1977, and 1978 observations at Prairie Island.
Strontium-90 levels in this e
range are attributable to worldwide fallout from previous atmospheric
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nuclear tests and reflect the long half-life (28.6 yrs) of this isotope.
All of the cesium-137 results were within the 1978 range of <1.0 to 10.2 pCi/l and were in general slightly higher at the control location.
Cesium-137 is also a long-lived component (with a half-life of 30.2 yrs) of worldwide fallout.
Finally, all
]
strontium-89 results in 1979 were <l.3 pCi/1, in agreement with 1976, and 1977, and 1978 measurements.
No significant changes were seen in strontium-90 and cesium-137 levels in milk.
This absence of an effect is consistent with the low initial production of these isotopes in nuclear explosions (Eisenbud, 1963).
Also no zirconium-92 or cerium-144 was detected in any of the milk samples.
This is consistent with the finding of the National Center for Radiological Health that most radiocontaminants in feed do not find their way into milk due to the selective metab-olism of the cow.
The common exceptions are radioisntopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health, 1968).
In summary, the milk data for 1979 show no radiological effects of the Plant operation, but the presence of strontium-90 and cesium-137 in milk samples do exhibit a long range residual effect of previous atmospheric nuclear tests.
13
HaTt NTON ENVIRONMENTAL. SCENCCO 5.
Natural Vegetation Natural vegetation was collected on 7 May and 28 August 4
1979.
No iodine-131, zirconium-95, cesium-137, or cerium-144 were observed in either collection.
The only gamma-emitting isotone detected was naturally occuring potassium-40.
6.
Crops Cabbage samples were collected on 4 September and analyzed for iodine-131.
Corn samples were collected on 19 September and analyzed for gamma-emitting isoptopes.
All results except for potassium-40 were below detection limits.
There was no indication of a plant effect.
7.
Well Water At the control well P-25, Kinneman Farm, tritium levels averaged 260 pCi/1.
For two of the indicator wells (P-8, Kinney Store, and P-10, Lock and Dam #3) no tritium was detected above LLD level of 200 pCi/l in any of the analyses.
The results ranged from <170 to
<200 pCi/1.
At the remaining indicator well (P-9, Plant Well #2),
tritium was detected in all quarterly samples and ranged from 220 to 490 pCi/1, averaging 420 pCi/1.
This is about 160 pCi/l above the control level of 260 pCi/1.
1*
The difference between the Plant well and the control well was not statistically significant; since uncertainty in the measurement is about at the same magnitude as the difference.
The l-highest tritium activity detected in the well (490 pCi/1) was more than fourty times lower than the annual average concentration allowed by the EPA Naticnal Interim Primary Drinking Water Regulation 14
HA2LETON ENVIRONMENTAL. SCCNCED (40 CFR 141) and was less than 0.004% of maximum permissible concentration for tritium in unrestricted areas (3,000,000 pCi/1).
A Gamma-emitting isoptopes were in all cases below detection limits.
An investigation was begun in May 1978 to determine ground water flow patterns in the affected area.
This investigation showed a general slope from the Mississippi River to the Vermillion River past the immediate area of Plant Well #2.
This would indicate that surface water recharge from the Mississippi River may be intercepted by Well #2.
Several plant water system sampling locations have been established in order to monitor possible migration of activity to Well #2.
So far this investigative effort is inconclusive.
Tritium is released by the Plant to the river; however, tritium is also produced by nuclear weapon tests and by cosmic radia-tion and brought to the ground by precipitation.
At this point in time, it is not at all evident which source or sources may be contributing to th_ slightly elevated tritium levels in Well #2.
8 Drinking Water In drinking water from the City of Red Wing well, no tritium was detected.
Results ranged from <l50 to <180 pCi/1.
As with the other well water samples, all analyses for gamma-emitting isotopes yielded results below detection limits.
Gross beta averaged 10.5 pCi/l and was slightly lower than the average levels in 1977 and 1978 (12.2 and 12.1 pCi/1, respectively).
9.
River Water ll^'
At the upstream collection site, quarterly composite
)
tritium levels ranged from <l50 to 340 pCi/l and averaged 260 pCi/1, l
l 15
HAZLETON CNVIRENMENTAL. CCIINCCO and was identical to the 1978 average of 260 pCi/1.
=ede At the downstream site (Lock and Dam #3), quarterly composite tritium levels rar.ged from 170 to 250 pCi/1.
The differences in levels between upstream and downstream were not significant.
Analyses of river water were also made for gamma-emitting isotopes, strontium-89, and strontium-90.
All gamma-emitting isotopes and strontium-89 were below detection limits.
Strontium-90 levels were slightly lower at the indicator location (Lock and Dam 03).
There was no indication of a Plant effect.
10.
Fish Fish samples were collected in June, October, and November 1979.
There was no significant difference between upstream and downstreaic results.
There was no indication of a Plant effect.
11.
Aquatic Insects and Periphyton Aquatic insects (macroinvertebrates) and periphyton were collected on 13 June and 24 September 1979.
The samples were analyzed for strontium,-89, strontium-90 and gamma-emitting isotopes.
There were no significant differences between upstream and downstream data.
No Plant effect was indicated.
12.
Aquatic Vegetation Aquatic vegetation was collected on 4 June and 24 September 1979 and analyzed for gamma-emitting isotopes.
All results except for potassium-40 and one cesium-137 were below detection limits.
No Plant effect was indicated.
13.
Bottom and Shoreline Sediments Sediment collections were made on 6 June and 24 September 1979.
The samples were analyzed for strontium-90 and 16 i
1
HAZLETON ENVIR2NMENTAL. CCCNC]O gamma-emitting isotopes.
There were no significant differences between control and indicator samples.
No plant effect was indicated.
14.
Topsoil Topsoil samples were collected in October 1979.
Strontium-90, cesium-137 and potassium-40 were detected in all samples. Naturally-occurring potassium-40 levels were nearly identical at indicator and control locations.
Strontium-90 and cesium-137 levels were slightly higher at the control locations.
Presence of strontium-90 and cesium-137 in topsoil is attributable to the long range fallout effect from previous atmosphe. : nuclear tests.
No Plant effect was indicated.
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HA?t MON CNVl~ONMZNTAL CCl2NCCO V.
Tables O
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s Table 1.
Sample collection and analysis program, 1979.
Prairie Island Collection Analysis Locations Type and Type (and Medium No.
Codes (and Type)a Frequencyb Frequency)c Ambient radiation 4
P-1(C), P-2(C)
C/O Ambient gamd.a y
(TLD's)
P-3, P-4 Airborne particulates 4
P-1(C), P-2(C)
C/W GB, GS (MC of P-3, P-4 all locations)
O Z
Airborne iodine 3
P-1(C),
5 Milk 3
P-16 to P-18 G/M I-131 30 I
5 2
P-13(C) or P-25(C),
G/M I-131, Sr-89, P-14 Sr-90, GS River water 2
P-5(C), P-6 G/W GS (MC ), H-3 (OC)
Sr-89(OC),
r Sr-90(OC) u 9
Drinking Water 1
P-ll G/ W GB, GS(MC),
j H-3(OC) na E
Well water 4
P-25 (C), P-8 to P-lO G/O H-3, GS Edible cultivated 2
P-25(C), P-24 G/A I-131 crops - leafy green vegetables Edible cultivated 2
P-25(C). P-14 G/A GS crops - corn Natural vegetation 3
P-25(C), P-14, P-15 G/SA I-131, GS
Table 1.
(continued)
Prairie Island
- ~ ~
Collection Analysis Locations Type and Type (and b
Frequency)c Medium No.
Codes (and Type)a Frequency Fish (two species, 2
P-5(C), P-6 G/SA GS flesh and bones)
I Periphyton or 2
P-5(C), P-6 G/SA Sr-89, Sr-90, macroinvertebrates GS 2
Aquatic Vegetation 2
P-5(C). P-6 G/SA GS m
Bottom Sediment 2
P-5(C), P-6 G/SA GS, Sr-90 Shoreline Sediment 1
P-12 G/SA GS, Sr-90 o
l Topsoil 9
P-1(C), P-2(C),
G/ETY GS, Sr-90 P-3, P-4, P-19 to P-23 a Location codes are defined in Table 2.
Control stations are indicated by (C).
g All other stations are indicators.
g b Collection type is coded as follows :
C/ = continuous, G/ = grab.
Collection frequency 3
is coded as follows:
W = weekly, M = monthly.
O = quarterly, SA = semi-annually, ETY =
{
every three years.
g c Analysis type is coded as follows: GB = gross beta, GS = gamma spectroscopy, W
H-3 = tritium Er-89 = strontium-89, Sr-90 = strontium-90, I-131 = iodine-131.
Analysis frequency is coded as follows:
MC = monthly composite, QC = quarterly composite.
HAZLETON CNVIRONMENTAL SC8ENCD Table 2.
Sampling locations Prairie Island Code Typea Name Location 0
P-1 C
Station P-1 (Control-Air) 16.5 mi 9 348 /NNW P-2 C
Station P-2 (Control-Air) 10.9mi@47fNE P-3 Station P-3 (X/0, Res,Comm-Air) 0.8 mi @ 313 /NE 0
P-4 Station P-4 ( X/Q-Air )
1.6 mi @ 129 /SE 0
P-5 C
Upstream of Plant 0.19 mi @ 60 /ENE (1,000 ft.)
0 P-6 Lock & Dam #3 1.6 mi @ 129 /SE 0
P-7 C
Most Farm Well 11.4 mi @ 320 /Ed 0
P-8 Kinney Store 1.0 mi @ 280 /W 0
P-9 Plant Well #2 0.3 mi @ 306 /NW (on-site) 0 P-10 Lock & Dam'#3 Well 1.6 mi @ 129 /SE 0
P-ll City of Red Wing (Drinking Water) 7.1 mi @ 135 /SE 0
P-12 Recreational Area 3.4 mi @ 116 /ESS b
P-13 C
Most Farm (Prescott) 11.4 mi 9 320 /NW 0
P-14 Gustafson Farm (X/Q-Milk) 2.2 mi @ 168 /SSE P-15 Downwind Field 0.6 mi @ 162 /SSE 0
P-16 A.
Dosdahl Farm 2.5 mi @ 39 /NE 0
P-17 Place Farm 3.5 mi @ 25fMNE P-18 Birk Farm 3.5 mi @ 181 /S 0
P-19 Commissary Point Park 1.0 mi @ 156 /SSE 0
P-20 Meteorology Station 0.4 mi @ 296 /WNW 0
P-21 Sturgeon Lake Access 0.4 mi @ 344 /NNW 0
P-22 Former TLD #14 Location 0.5 mi @ 230 /SW P-23 Farmer TLD #15 Location 0.5 mi @ 184 /S 0
P-24 H. Larson Residence (Nearest Garden) 1.6 mi @ 287 /WNW 0
P-25c C
Kinneman Farm (Control-Milk, etc) 11.1 mi @ 331 /NNW d
P-26 Augustine Farm 5.7 mi @ 24 /NNE d
U P-27 Murphy Farm 2.8 mi @ 42 /NE
^ "C" denotes control location.
All other locations are indicators.
b P-13 discontinued after March 1978.
c P-25 added in April 1978.
d P-26 and P-27 added in July 1978 (Goat's milk).
4 21
e s
O 6
Table 3.
Missed collections and analyses, 1979.
Prairie Island All required samples collected and analyzed except the following:
Coll. Date Sample Analysis Location or Period Comments Ambient radiation Ambient P-2 1st quarter Samples stolen (TLD's) gamma from location.
I Airborne Gross Beta P-4 5-22 to 5-30-79
" Substation being particulate rebuilt," no pow-er available.
7 Airborne I-131 P-4 5-22 to 5-30-79
" Substation being iodine rebuilt," no pow-er available.
30 I
Oe Zna5
Table 4.
Environmental Radiological Monitoring Program Summary.
Name of facility Prairie Island Nuclear Generating Plant Docket No.
50s282, 50-306 Location of facility Goodhue, Minnesota Reporting period January-December 1979 (County, state) indicator j
Location with Nighest Control Sample Type and Locationg Annual Mean Locations Number of Type Number of Mean(F)
Mean(P)
Mean{F)
Non-routine (Units)
Analysema LLDb p,ng.c Locationd
- gang, panq, g,,oggee TLD-quarterly Gamma 15 3.0 12.6 (8/4)
P-2 Station P-2 18.5 (3/3) 15.3 (7/7) 0 (area /98 days)
(9.9-14.3) 10.9 al 0 47* NE (17.9-19.5)
(10.1-19.5) i Air GB 217 0.002 0.037 (107/107)
P-2 Station P-2 0.040 (56/56) 0.038 (110/810)
O Particulates 70.005-0.105) 10.9 at 0 47* NE (0.013-0.100)
(0.013-0.l00) g (pCl/m3) i Airborne 1-131 155 0.02
<LLD
<LIA 0
iaine (pC1/m3)
Air GS 12 Particulates 2
l Monthly K-40 0.01 (LLD None 0
g composite of g
g all locations tr-95 0.002 i(LLD lMone O
f (pC1/m3) i 2
j lMone 0
3 Co-137 0.001 (LLD O
w Ce-144 0.004 (LLD f'Mone 0
g i
I 1 (LLD 0
E Milk 1-131 65 0.25 (LLD (pC1/1)
Sr-89 24 1.3 (LLD (Lla 0
I Sr-90 24 3.5 (12/12)
P-25 Einneman Para 4.1 (12/12) t 4.1 (12/12) 0 j(2.5-4.8)
II.1 mi 0 331* NNN (3.1-5.1)
(3.1-5.Il g
l h
8 GS 24 I
e P-25 Itinneman Fars 1300 (12/12) l1380(12/12) i K-40 60 1380 (12/12) 0 Z
l
,(1220-1520) 18.1 al 0 338' NNN
,(1260-1440) g (1260-1440) l g
8 I
i
[
m i tr-95 10
{<LLD
{ (Lla g
0 3
g i
- 4.8 (4/12) l4.2(5/12) i 0
t Cs-137 P-25 sinneman Para j4.8 (4/12) 2.8 11.1 mi 0 331' NNN ;(3.3-6.3) j (3.3-6.3)
I I(2.9-4.7)
I l30
{<LLD (Lim o
Ce-144
e Table 4.
(Continued)
Name of facility Prairie Island Nuclear Generating Plant
[
Indicator tocation with Highest Control j
f Sample Type and locations
~
Annual Nean tocations Number of j Type Number of Nean(F)#
l Nean(F)
Nean(F)
Non-routine -
Range Range Resulta' i (Units)
Analysema ttob pangec tocationd l 260 (3/4) 260 (3/4) 0 lRiverWater al-3 8
150
- 220 (4/4)
P-5 Upstream 1000*
g
- (pCi/1) i, (170-290) 0.6 mi 9 60* ENE (200-340)
- (200-340) l Sr-89 8
1.2
$ (LLD P-5 Upstream 1000*
1.7 (l.43 1.7 (1.4) 0 0.6 mi 9 60* ENE I
Sr-90 8
0.9 1.2 (1/4)
P-6 tack & Dam $3 1.2 (1/4)
(LLD 0
1.6 at 9 129* SE g
a CS 24 1,
i t
Er-95 to
<LLD (LIA 0
t Cs-137 2.5
<LLD
<LLO O
g l
Ce-144 30 (LLD 1
(LLD 0
g Drinking water ca 12 i
None 0
b i
(PC&/l)
None O
3 ti-3 4
180 (LID O
2 I
None 0
e tr-95 10
<LLD None j
0 0
j t
Ce-144 30 (LLD None 0
i g
2
)
C.
i 420 (4/12) 1 P-9 Plant well 02 420 (4/12) 260 (2/4) 0 E
Well Water H-3 16
'200 I
Z i
I(220-490) i 0.3 mi 9 306* NW (220-430)
(200-120)
(pci/1) j g
t cs 16 N
E-40 60
<LLD
<LLD I
O l
I i
I l
f*
<LLO l
0 i
t Cs-137
' 2. 5 (LLD (Lla 3
0 i
(LLD 0
I Ce-144 30
- <LLD i
t s
I (LLD 0
Crops -
I-131 2
0.008 i <LLD cabbage e
1 (Pci/g wet) 3 3
Table 4.
(Continued)
Name of facility Prairie Island Nuclear Generating Plant i
i Indicator Location with tiighest Control 3
Sample Type and tocationg Annual Nean locations Number of Type Nunber of j
Nean(F)
Nean(F)
Nean(F)
- hon-routine,
(Unital Analysema t
LLob kangeC tocationd Range Range Results* '
I i
. Crops - corn CS 2
g i
l(Pi/9 wet)
C K-40 0.1 2.0 (1/1)
P-14 Gustafson Para 2.0 (1/l) 1.4 (1/1) 4 0
g 2.2 mi e 168* SSE I
i 0.027 (Lla I
2r-95 l
<LLD 0
<LLD 0
Z Ce-144 0.63
<LLD
<LLD 0
! Natural I-131 6
0.03 (Lta I
f i vegetation 0
(Lla 0
(pci/g wet)
CS 6
i j
K-40 0.2 5.0 (4/4)
P-25 Kinneman Farm 5.0 (2/2) 5.8 (2/2) g 0
g (4.1-6.6)
I II.1 mi e 3JI' NNW (5.7-5.9)
(5.7-5.9)
I E
z 3r-95 0.04
<LLD (LLD 0
g
{
Cs-137 0.03
<LLD
, <LLD 0
I 1
0 Ce-144 0.2 (Lla (LLD 0
2 Fish-whole CS 8
i l
E (flesh and l
bones)
K-40 0.1 3.5 (4/4)
P-6 lock & Dem 03 3.5 (4/4) 2.7 (4/4) 0 (pci/g wet)
(2.9-4.2) l 1.6 mi e 129' SE (2.9-4.2)
} (2.0-3.8) i 4
F Er-95 0.05
<LLD (LLD 0
g O
P-5 Upstrema 1000' O.04 (1/4) 0.04 (1/4) g E
0
=
O.6 mi 0 60* ENE Z
Ce-144 0.13
<LFO
<LLD I
O O3 Periphyton Sr-89 4 l 0. 2 (LLD 8
<LLD 0
W (gC1/g wet) l I
Sr-90 4, 0.004 0.13 (2/2)
P-5 Upstrema 1000' O.20 (1/2) 0.20 (1/2) 1 0
s (0.03-0.22) 0.6 mi 9 60* ENE I
l
- cs 4
l t
I K-40 1.0 1.5 (2/2)
P-6 Lock & Das 0 3 1.5 (2/2) 1.4 (1/2) l 0
(0.5-2.5) j 1.6 mi e 129' 58 (0.5-2.5) e 4
0 e
?
Ca-137
- 0.00
< Lla (LLD 0
Ce-144 j 0.4 (Lla (LLD 0
1
e e
Table 4.
(Continued)
Name of facility Prairie Island Nuclear Generating Plant Indicator tocation with Highest g
Control Sample Type and locationg Annual Mean I
tocations Number of
~
Type Number of Mean(P) hean(F)
Mean(F)
Non-roestine (Units)
Analysema LLDb RangeC Locationd Range Sange Resulta'
' Aquatic GS 4
Vegetation (pC1/g wet)
E-40 1 0.7 1.7 (2/2)
P-5 Upstream 1000' 2.0 (2/2) 2.0 (2/2) 0 l
(0.9-2.5) 0.6 mi e 60* ENE (1.9-2.1)
(1.9-2.1) g I
(LLD 0
tr-95 0.02
<LLD I
Das 0 0.067 (1/2)
<LLD 0
I I
j Cs-137 0.08 0.067 (1/2)
P-6 tack & n9 S3 i
i.6.i.
f l
<LLD 0
{
Ce-144 0.08 (LLD l Bottom or Sr-90 6
0.004 0.008 (3/4) l P-5 Upstrema 1000' O.Olt (2/2) 0.018 (2/2)
\\
O shoreline (0.007-0.090) 0.6 at 9 60* ENE (0.010-0.011)
(0.010-0.011)
O sediments
(
Z (pCi/g dry)
GS 6
K-40 0.5 13.7 (4/4)
P-6 tock 6 Dam 83 14.3 (2/2)
II.7 (2/2) 0 l
2y (ll.6-14.5) 1.6 mi 9 129* SE (11.4-11.9) g f
tr-95 0.04
<LLD
<LLD O
M Cs-137 0.02
< Lim P-5 Upstream 1000' O.08 (2/2) 0.08 (2/2) 0 2
0 0.6 mi 9 60* ENE (0.06-0.09)
(0.06-0.09) j
{
n i
a Ce-144 0.12 (LLD i
(Lth i
0 t
Topsoil Sr-90 9
0.10 (7/7)
P-1 Station P-1 0.40 (1/l)
I 0.26 (2/2) 0 (pci/g dry)
(0.07-0.14) 16.5 at 9 348* NNW 1 (0.12-0.40) l a
G 9
f h
a l
7 K-40 0.5 15.1 (7/7) k P-14 Gustafson Fars 21.2 (1/l) g 14.7 (2/2) 0 (13.3-21.2) 2.2 mi e 168* SSE
- (14.5-14.9) g f0.07 (Lla O
i tr-95 (LLD l0.1 0.5 (7/7)
P-l Station P-l I.4 (1/l) 1.1 (2/2) 0 I
Cs-137 (0.3-0.8) i 16.5 al 0 344* aned (0.5-1.4)
Ce-144 0.25 (LLD
<LLD 0
aG8 = gross b stas GS - gamma scan.
bLto. nominal lower limit of detection based on 3 sigma error for background sample.
cMean and range baned upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).
d ocations are specified (1) by name and code (Table 2) and (2) distance, direction, and sector relative to reactor site.
L eNonroutine results are those wLtch escoed ten times the control station value.
If no control station value is available, the result is considered nonrout.
af it esceeds ten times the preoperational value for the location.
HA2LETC 4 CNV*MONMINTAL CCl2NCCO VI.
References Cited
- Eisenbud, M.
1963.
Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275 and 276.
Hazleton Environmental Sciences Corporation.
1978.
Sampling Procedures, Prairie Island Nuclear Generating Plant, Revision 9, 20 October 1978.
1979a.
Radiation Environmental Monitoring for Prdirie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978.
1979b.
Radiation Environmental Monitoring for Monticello Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978.
1980a.
Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1979.
1980b.
Fadiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, Janauary - December 1979.
~
NALCO Environmental Sciences, 1971a.
Quality Control Program, Nuclear Sciences Section, Revision 3, 15 May 1978.
1971b.
Quality Control Procedures Manual, Nuclear Sciences Section, Revision 3, 15 May 1978.
1975.
Quality Assurance Manual, Revision 6, 18 April 1978.
1977.
Analytical Procedures Manual, Nuclear Sciences Section, Revision 1, 23 May 1978.
National Center for Radiological Health, 1968.
Radiological Health and Data Reports, Vol. 9, Number 12, 730-746.
Northern States Power Company.
1977.
Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, 1976 through December 31, 1976 (prepared by NALCO Environmental Sciences) Minneapolis, Minnesota.
1978.
Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S.
)
Nuclear Regulatory Commission, January 1, 1977 through December
~
31, 1977 (prepared by NALCO Environmental Sciences) Minneapolis, Minnesota.
27
Ma7t IFTON CNVIR'INMZNTAI. CCCNCOO r
1979.
Prairie Island Nuclear Generating Plant, Annual Radiation Environnental Monitoring Report to.the U.S.
Nuclear Regulatory Commirssion, January 1, 1978 to December 31, 1978 (prepared by Hazleton Environmental Sciences).
Minneapolis, Minnesota.
U. S. Atomic Energy Commission.
1972.
KASL Procedures Manual, Health and Safety Laboratory, New York, NY.,
10014.
U.
S.
Department of Energy.
1978.
Environmental Quarterly, January 1,
1979.
Environmental Measurements Laboratory, New York, NY 10014.
U.
S.
Environmental Protection Agency, 1978.
Environmental Radi-ation Data, Report 12 (April 1978) and Report 14 (October 1978). Eastern Environmental Radiation Facility, Montgomery, Alabama.
U.
S.
Public Health Service.
1967.
Radioassay Procedures for Environmencal Samples, National Center for Radiological Health, Rockville, Maryland (Public Health Service Publication No.
999-RD-27).
Wilson, D. W.,
G. M. Ward and J.
E. Johnson.
1969.
In Environmen-tal Contamination by Radioactive Materials, International Atomic Energy Agency. p.
125.
I r
e D
28 1
HAZLETON CNVIRZNMENTAL CClZNCH3 Appendix A Crosscheck Program Results I
O
HA2LETON ENVIRONMENTAL CCCNC2O Appendix A Crosscheck Program Results The Nuclear Sciences Department of Hazleton Environmental Sci-ences Corporation has participated in interlaboratory comparison (crosscheck) programs since the formulation of its quality control program in December 1971.
These programs are operated by agencies which supply environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories.
The purpose of such a program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems.
Participant laboratories measure the concentrations of specified radionuclides and report them to the issuing agency.
Several months later, the agency reports the known values to the participant 1aboratories and specifies control limits.
Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.
The results in Table A-1 were obtained through participation in the environmental sample crosscheck program for milk and water 1
samples during the period 1975 through 1979.
This program has been
)
conducted by the U. S.
Environmental Protection Agency Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, Las Vegas, Nevada.
The results in Table A-2 were obtained for thermoluminescent dosi-meters (TLD's) during the period 1976 and 1977 through participation in the Second the Third International Intercomparison of Environmental Dosimeters under the sponsorships listed in Table A-2.
A-2
HAZLETON ENVIR2NMENTAL CCCNC"l3 f
Table A-1.
U.S.
Environmental Protection Agency's crosscheck pro-gram, comparison of EPA and Hazleton ES results for milk and water samples, 1975 through 1979a, Concentration in pCi/lb Lab Sample Date HES Result EPA Result Code Type Coll.
Analysis 12a c 130, n=1d STM-40 Milk Jan. 1975 Sr-89
<2 0+15 Sr-90 73+2.5 75T11.4 I-131 9974.2 101715.3 Cs-137 7670.0 75I15 Ba-140
<377 0T15.0 K(mg/1) 147015.6 1510}228 STW-45 Water Apr. 1975 Cr-51
<14 0
Co-60 421+6 425+63.9 Zn-65 48776 497774.7 Ru-106 50ST16 497774.7 Cs-134 38573 400760.0 Cs-137 46813 450}67.5 STW-47 Water Apr. 1975 H-3 14591144 149911002 STW-48 Water Jun. 1975 H-3 2404134 220411044 STW-49 Water Jun.1975 Cr-51
<14 0
Co-60 344+1 350+53 Zn-65 33075 327T49 Ru-106 31577 325749 Cs-134 291T1 304T46 Cs-137 38712 378}57 OW-53 Water Aug. 1975 H-3 3117164 320011083 STW-54 Water Aug. 1975 Cr-51 223+11 255+38 Co-60 305T1 307T46 Zn-65 28973 281T42 Ru-106 346T5 279757 Cs-134 238T1 256738 Cs-137 29212 307}46 STW-58 Water Oct. 1975_
H-3 1283180 12031988 STM-61 Milk Nov. 1975 Sr-90 68.9+2.1 74.6+11.2
~
I-131 64.6T3.8 75T15 Cs-137 75.6}20 75115 Ba-140
<3.7 0
K(mg/1) 1435157 15491233 A-3
HA2LETON CNVl'ZONMENTAL CCCNC"O Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date HES Result EPA Result c
+3J, n=1d Code Type Collected Analysis 12c STW-63 Water Dec. 1975 H-3 1034139 10021972 STW-64 Water Dec. 1975 Cr-51
<14 0
Co-60 221+1 203+30.5 Zn-65 215T6 201730.2 Ru-106 17179 181I27.2 Cs-134 19872 202I30.3 Cs-137 15214 151122.7 STW-68 Water Feb. 1976 H-3 1124131 10801978 STW-78 Water Jun. 1976 H-3 2500144 250211056 STW-84 Water Aug. 1976 H-3 3097121 310011080 STM-86 Milk Sep. 1975 Sr-89 29+2.0 45+15 Sr-90 30T1.0 30T4.5 I-131 100T8.6 120T18 Ba-140 50T10.1 85I15 Cs-137 1771.5 20I15 K(mg/1) 15401231 STM-91 Milk Nov. 1976 I-131 83+0.6 85+15 Ba-140
<4 3
Cs-137 12+1.7 11+15 K(mg/1) 1443131 15101228 STW-93 Water Dec. 1976 Cr-51 105+15 104+15 Co-60
<T 3
Zn-65 97+4 102+15 Ru-106 8773 99715 Cs-134 8574 93T15 Cs-137 103~+4 101115 STW-94 Water Dec. 1976 H-3 2537115 2300+1049 STM-97 Milk Mar. 1977 I-131 55+2.5 51+15 l
Ba-140
<3 3
l Cs-137 34+1 29+15 K(mg/1) 1520135 15501233
~
STW-101 Water Apr. 1977 H-3 1690162 176011023 A-4
MazLaTON ENVIRONMENTAL faCCNC33 Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date HES Result EPA Result Code Type Collected Analysis 12cc 130, n=1d STM-103 Milk May 1977 Sr-89 3812.6 44115 Sr-90 12+2.1 10+4.5 I-131 5972.1 50715 Ba-140 53T4.4 72T15 Cs-137 1471.2 10T15 K(mg/1) 1533T21 15601234 STW-105 Water Jun. 1977 Cr-51
<14 0
Co-60 29+2 29+15 Zn-65 74T7 74T15 Ru-106 64T8 62715 Cs-134 4171 44T15 Cs-137 3513 33115 STW-107 Water Jun. 1977 Ra-226 4.710.3 5.112.42 STW-113 Water Aug. 1977 Sr-89 13+0e 14+15 Sr-90 1012e 1074.5 STW-116 Water Sep. 1977 Gross Alpha 12+6 10+15 Gross Beta 3216 30715 STW-118 Water Oct. 1977 H-3 1475129 165011017 STW-119 Water Oct. 1977 Cr-51 132+14 153+24 Co-60 3972 38T15 Zn-65 5175 53T15 Ru-106 63T6 74T15 Cs-134 3073 30715 Cs-137 2611 25}15 STW-136 Water Feb. 1978 H-3 16901270 168011020 STW-137 Water Feb. 1978 Cr-51
<21 0
Co-60 36+2 34+15 Zn-65 3274 29715 Ru-106 4172 36T15 Cs-134 47T2 52T15 Cs-137
<2 3
A-5
HA?t NTON CNVIRONMZNTAL. SCENCE]
Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date HES Result EPA Result d
Code Type Collected Analysis
+2ac 13a, n=1 STW-1389 Water Mar. 1978 Ra-226 5.4+0.1 5.5+0.6 Ra-228 NXf 16.712.5 STW-150 Water Apr. 1978 H-3 21501220 222011047 STW-151 Water Apr. 1978 Gross Alpha 2011 20115 Gross Beta 56+4 59+15 Sr-89 1972 21715 Sr-90 871 1074.5 Ra-226 NIf 7
Ra-228 NAf H-3 112+12 0
Co-60 1973 20+15 Cs-134 16T1 15715 Cs-137
<7 i
STM-152 Milk Apr. 1978 Sr-89 85+4 101+15 Sr-90 8T1 9T4.5 I-131 78T1 82T15 Cs-137 2973 23715 Ba-140
<T1 0
K(mg/1) 1503190 15001225 STW-1549 Water May 1978 Gross Alpha 12+1 13+15 Gross Beta 2114 18115 STW-1579 Water Jun. 1978 Ra-226 4.0+1.0 3.7+0.6 Ra-228 NAf 5.610.8 STW-1599 Water Jul. 1978 Gross Alpha 19+3 22+6 Gross Beta 2813 3015 STW-162 Water Aug. 1978 H-3 1167138 12301990 STW-1659 Water Sep. 1978 Gross Alpha 4+1 5+5 Gross Beta 1311 1015 l-i-
I A-6
Haya sTON CNVIRONMENTAL CCIENCCO Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date HES Result EPA Result
,13c, n=1d Code Type Collected Analysis 12cc S'1W-167 Water Oct. 1978 Gross Alpha 19+2 19+15 Gross Beta 3672 34T15 Sr-89 971 10T15 Sr-90 4TO 572.4 Ra-226 5.570.3 5.072.4 Ra-228 NIf 5.472.4 Cs-134 10+1 10T15 Cs-137 1531 13115 STW-170 Water Dec. 1978 Ra-226 115+0.6 9.2+1.4 Ra-228 NAf 8.974.5 STW-172 Water Jan. 1979 Sr-89 11+2 14+15 6~4.5 Sr-90 5}2 1
STW-175 Water Feb. 1979 H-3 13441115 12801993 STW-176 Water Feb. 1979 Cr-51
<22 0
Co-60 10+2 9+15 Zn-65 26+3 21715 Rn-106
<I6 3
Cs-134 8+2 6+15 Cs-137 1512 12115 STW-178 Water Mar. 1979 Gross Alpha 6.3+3 10+15 Gross Beta 15}4 16315 aResults obtained by the Nuclear Sciences Department of Hazleton Environmental Sciences Corporation as a participant in the environmental sample crosscheck program operated by the Inter-comparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S Environ-mental Protection Agency, (EPA)), Las Vegas, Nevada.
ball results are in pCi/1, except for elemental potassium (K) data which are in mg/1.
cUnless otherwise indicated, the HES results given as the mean
+ 2 standard deviations for three determinations.
dDSEPA results are presented as the known values i control limits of 3 for n=1.
eMean + 2 standard deviations of two determinations.
fNA = Not analyzed.
9 Analyzed but not reported to the EPA.
A-7
Table A-2.
Crosscheck program results, thermoluminescent dosimeters (TLD's).
mR HES Average 1 2cd Lab TLD Result Known all Code Type Measurement
+20a Value (participants) 2nd International Intercomparisonb 115-2b cap 2:Mn Gamma-Pield 17.0+1.9 17.1C 16.417.7 y
Bulb Gamma-Lab 20.814.1 21.3c 18.817.6 8
3rd International Intercomparisone Z
115-20 cap 2:Mn Gamma-Pield 30.7+3.2 34.9+4.8f 31.5+3.0 m
Z
~
Bulb f
86.2+24.0 Gamma-Lab 89.616.4 91.7114.6 O2 p
i Lab result given is the mean i 2 standard deviations of three determinations.
a Second International Intercomparison of Environmental Dosimeters conducted in April h
of 1976 by the Health and Safety Laboratory (HASL), New York, New York, and the v
School of Public Health of the University of Texas, Houston, Texas.
f Value determined by sponsor of the intercomparison.
r Mean i 2 standard deviations ot results obtained by all laboratories participating d
e 9
in program.
E
- Third International Intercomparison of Environmental Dosimeters conducted in summer of 1977 by Oak Ridge National Laboratory and the School of Public Health of the
!N University of Texas, Houston, Texas.
EValue + 2 standard deviations as determined by sponsor of the intercomparison l
HA2LETON CNVIRONMZNTAL CCCNCCO Appendix B Data Reporting Conventions er l
e i
HA2LETON ENVIRONMENTAL CCCNCEO Data Reporting Conventions 1.
All activities are corrected to collection time.
2.
Single Measurements
~
Each single measurement is reported as follows:
xis where x = value of the measurement; s=2 counting uncertainty (corresponding to the 954 confidence level).
In cases where the activity is found to be below the lower limit of detection L it is reported as
<L.
Detection limits are based on 3 background counting uncer-tainties.
3.
Duplicate measurements, the average result is reported as follows:
a.
Individual results:
x1 i s1 X2 i s2 Reported result:
x1a where x = (1/2) (x1 + x2) 2+sf s = (1/2) s b.
Individual results:
<L1
<L2 Reported result:
<L where L = lower of L1 and L2 O
l B-2
Hart NTON CNVI~'5NMENTAL CCCNCQ c.
Individual results:
xis
<L Reported result:
x i s if x < L;
<L otherwise 4.
Unless otherwise indica,ted, the " cumulative average" for a location is the average of all measurements from the beginning of the current year through the date of the last entered result.
"Less-than" values are ignored in the computation of the average.
If all results are less-than values, the highest value is reported.
5.
Unless otherwise indicated, the " previous average" for a location is the average obtained during the 1978 program period.
6.
In rounding of f, numbers followed by a 5 or higher digit are s
ro'2nded upwcrds.
t h
B-3
Ma71 WTON ENVIRCNMZNTAL. CCCNCCO Appendix C Maximum Permissible Concentrations of Radioactivity in Air and Water h
t e
d l
r HA2LETON ENVIRONMENTAL. CCCNC30 Table C-1.
Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas.a Air Water 9
Gross alpha 3
pCi/m3 Strontium-89 3,000 pCi/l Gross beta 100 pCi/m3 Strontium-90 300 pCi/l Iodine-131b 0.14 pCi/m3 Cesium-137 20,000 pCi/l Barium-140 20,000 pCi/l Iodine-131 300 pCi/l Potassium-40c 3,000 pCi/l Gross alpha 30 pCi/l Gross beta 100 pCi/1 Tritium 3 x 106 pCi/1 aTaken from Code of Federal Regulations Title 10, Part 20, Table II and appropriate footnotes.
Concentrations may be averaged over a period not greater than one year.
s b rom 10 CFR 20 but adjusted by a factor of 700 to reduce the F
dose resulting from the air-grass-cow-milk-child pathway.
cA natural radionuclide.
S C-2 i
i
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