ML20102C108
| ML20102C108 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/31/1981 |
| From: | Huebner HAZLETON LABORATORIES AMERICA, INC. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 8503050247 | |
| Download: ML20102C108 (55) | |
Text
.
4 MY PRAIRIEISLAND NUCLEAR GENERATING PLANT Red Wing, Minnesota UNITS 1 AND 2 I
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MIMMEAPoLISe
- 57. PAUL
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ANNUAL REPORT to the UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1, 1981 to December 31, 1981 i
NORTHERN STATES POWER COMPANY MINNEAPOLIS. MINNESOTA
!!8 988 8 !ss! L a R
f.6 HAZLETCON ENVIRONMENTAL SCIENCES A CMSION CF HAZLETON LABCAATCAIES AME AlCA. INC.
15C0 FACNTAGE ACAC. NCATHBACCK. ILLINCIS SCCS2, U.S A.
NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNES0TA PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NO. 50-282 LICENSE NO. DPR-42 50-306 DPR-60 ANNUAL REFORT to the UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environaental Monitoring Program January 1, 1981 to December 31, 1981 i
Prepared Under Contract by HAZLETON ENVIRONMENTAL SCIENCES Project No. 9079 Approved by:
/
llh L.G.H/ ebner,M.S..
Director, Nuclear Sciences 24 February 1982 PHONE L3121584 0700 o TELE x 28-9483 (HAZE S NBAkI
HAZLETON ENVIRONMENTAL SCIENCES PREFACE The staff members of the Nuclear Sciences Department of Hazleton Environmental Sciences (HES), a Division of Hazleton Laboratories America, Inc., were respon-sible for the acquisition of data presented in this report.
Samples were collected by personnel of Northern States Power Company.
The report was prepared by C.R. Marucut, Section Supervisor.
She was assisted in the report preparation L. Nicia, Group Leader, and E. Petray, Technical Writer, under the Direction of L.
G. Huebner, Director, Nuclear Sciences.
=
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HAZLETON ENVIRONM2NTAL. CCCNC3'J TABLE OF CONTENTS No Page PREFACE 11 List of Tables iv
1.0 INTRODUCTION
1 2.0
SUMMARY
2 3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) 3 3.1 Program Design and Data Interpretation 3
3.2 Program Description 4
3.3 Program Execution 6
3.4 Laboratory Procedures 6
3.5 Program Modifications 6
3.6 Census of Milch Animals 7
4.0 RESULTS AND DISCUSSION 8
i 4.1 Effect of Chinese Atmospheric Nuclear Detonation 8
4.2 Program Findings 8
S.0 TABLES 13
6.0 REFERENCES
CITED 31 l
l APPENDICES A.
Crosscheck Program Results A-1 B.
Data Reporting Conventions B-1 C.
Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas C-1 I'
l 111 l
HAZLETON GNVIRONM2NTAL CICl2NC23 LIST OF TABLES No.
Title Page 5.1 Sample collection and alalysis program,1981 14 5.2 Sampling locations 16 5.3 Missed collections and analyses, 1981 21 5.4 Environmental radiological monitoring program summary 22 In addition, the following tables are in the Appendices:
Appendix A A-1 Crosscheck program results, milk and water samples, 1975-1981 A-3 A-2 Crosscheck program results, thermoluminescent dosimeters (TLD's)
A-11 Appendix C C-1 Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas C-2 l
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f IV L
4 HAZLETON ENVIRONMENTAL SCIENCES
1.0 INTRODUCTION
This report summarizes and inteprets results of the Radiation Environmental Monitoring Program (REMP) conducted by Hazleton Environmental Sciences at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December,1981. This program monitors the levels of radioacti-vity in the air, terrestrial, and aquatic environments in order to assess the impact of the plant on its surroundings.
Tabulation of the individual analyses made during the year are not included in this report.
These data are included in a ' reference document (Hazleton Environmental Sciences, 1982) available at Northern States Power Company, Nuclear Support Services Department.
Prairie Island Nuclear Generating Plant is located on the Mississippi River in Goodhue County, Minnesota, 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.
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HAZLETON ENVIRONMENTAL SCIENCES 2.0
SUMMARY
The Radiation Environmental Monitoring Program (REMP) required by the U.S.
Nuclear Regulatory Commission '(NRC) Technical Specifications for the Prairie Island Nuclear Generating Plant is described.
Results for 1981 are summarized and discussed.
No effect on the environment due to the operation of the Prairie Island Nuclear Generating Plant is indicated.
Results obtained for gross beta in airborne particulates collected during the first three quarters of 1981 and presence of relatively short-lived fission products, such as noibium-95, zirconium-95, ruthenium-103, cerium-141, and cerium-144 in some of the airborne partiuclates, natural vegetation, and shoreline sediments samples show a moderate effect of fallout from atmospheric nuclear detonation of a 200 kiloton to 1 megaton range device on 16 October, 1980.
Presence of other fission products, mostly strontium-90 and cesium-137 in some of the sampling media indicates a long range effect on the environment from fallout resulting from previous atmospheric nuclear tests.
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HAZLETON ENVIRONM3NTAL. CCCNC3D 3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Des _1gn and Data Interpretation The purpose of the Radiation Environmental Monitoring Program (REMP) 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 thermoluminescent dosimeters (TLD's).
Sources of environmental radiation include the following:
(1) natural background radiation 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 distinguished from those due to other sources.
A major interpretive aid in assessment of these effects is the design of the monitoring program at the Prairie Island Plant which is based on the indicator-control concept.
Most types of samples are collected both at indicator locations (nearby, downwind, or downstream) and at control locations (distant, upwind, or upstream).
A plant effect would be indicated if the radiation level at an indicator location was signifi-cantly 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.
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 groups quantified:
zi rconium-95, cesium-137, cerium-144, bery111um-7, 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 that 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 3
HA2LETON ENVIRONM3NTAL ECCNC2D f
J days after reactor shutdown.
On the other hand, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963).
Bery111um-7 is of cosmogenic origin and 4
potassium-40 is a naturally-occurring isotope.
They were chosen as calibration monitors and should not be considered radiological impact indicators.
The other group quantified consists of niobium-95, ruthenium-103, and
-106, cesium-134, barium-lanthanum-140, and cerium-141.
These isotopes are. released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing.
Nuclides of the final group, manganese-54, cobalt-58, and -60, and zinc-65, are activation products and arise from activation of corrosion products.
They are typical components of nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.
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 other parts of the world.
Finally, results can be related to events known to cause elevated levels of radiation in the environment, e.g., atmospheric nuclear detonations.
I i
3.2 Program Description The sampling and analysis schedule for the environmental radiation monitoring program at Prairie Island is summarized in Table 5.1 and briefly reviewed below.
Table 5.2 defines the sampling location codes used in Table 5.1 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,1981).
l To monitor the air environment, iirborne particulates are collected on membrane filters by continuous pump 1m at four locations.
Also, airborne iodine is collected by continuous pu..oing through charcoal filters at three of these locations.
Filters are changed and counted weekiy.
Particulate filters are analyzed for gros; beta activity and charcoal
' ~
filters for iodine-131.
A monthly composite v 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 located near the residence expected to be most susceptible to any atmospheric emissions from the Plant (highest X/Q residence).
(
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HAZLETON GNVIRONMZNTAL. ECCNC33 Ambient gamma radiation is monitored at the same four air sampling locations using CaFg:Mn thermoluminescent dosimeters (TLD's).
The sensors are placed in pairs at each location and are collected and
~
measured quarterly.
In addition, as a " Lessons Learned" commitment, ambient gamma radiation is monitored at thirty-two (32) special locations, using three (3) LiF2 chips for each location:
ten (10) in an inner ring in the general area of the site boundary, fifteen (15) in the outer ring within 4-5 mi radius, six (6) at special interest locations and one control location, 11.1 mi distant from the plant. They are replaced and measured quarterly.
Also, a complete emergency set of TLD's for all locations, including four air sampling locations, is placed in the field at the same time as regular sets.
The emergency set is returned to the HES laboratory quarterly for annealing and repackaging.
Milk samples are collected monthly from five farms (four indicator and one control).
All samples are aralyzed for iodine-131.
In addition, samples from the control location '(P-25, Kinneman Fann) and the highest X/Q location (P-14, Gustafson Farm) are analyzed for strontium-89, strontium-90, and for gamma-emitting isotopes.
For additional monitoring of the terrestrial environment, natural vegeta-tion (such as grass) is collected semi-annually from three ' locations (including the highest X/Q milk location P-14 and the milk control location P-25).
Samples are analyzed for gamma-emitting isotopes inclu-ding iodine-131.
Cabbage is collected annually from a garden nearest the Plant and a control location (P-25) and analyzed for iodine-131.
Corn is collected annually from the highest X/Q 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 i
-90 and gamma-emitting isotopes.
The latest collection of soil was made in 1979.
River water is collected weekly at two locations, one upstream of the Plant (P-5) and one downstream (P-6, Lock and Dam a3). Monthly composites i
are analyzed for gamma-emitting isotopes.
Quarterly composites are i
analyzed for tritium, strontium-89, and strontium-90.
Drinking water is collected weekly from the City of Red Wing well.
Monthly composites are analyzed for gross beta activity and gamma-emitting I
isotopes. Quarterly composites are analyzed for tritium.
l The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, periphyton or macroinvertebrates, aquatic I
vegetation, and bottom sediments.
Shoreline sedment is collected semi-annually.
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HA2LETON ENVIRENMINTAL ECl2NC2]
3.3 Program Execution The Program was executed as described in the preceding section.
There were no deviations from the program (See Table 5.3).
3.4 Laboratory Procedures All str'ontium-89, strontium-90, and iodine-131 analyses in milk were made by using a sensitive radiochemical procedure which involves separation of l
the element of interest by use of an ion-exchange resin and subsequent beta counting.
All gamma-spectroscopic analyses were performed with a Ge(Li) detector.
Levels of iodine-131 in cabbage and natural vegetation were determined by Ge(L1) spectrometry.
Levels of airborne iodine-131 in charcoal samples were measured by Ge(L1) spectrometry.
Tritium levels were determined by liquid scintillation technique.
Analytical procedures used by the Nuclear Sciences Department of Hazleton Environmental Sciences are specified in detail elsewhere (Hazleton Environmental Sciences,1981).
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 i
Laboratory of the U.
S. Atomic Energy Commission (U. S. Atomic Energy Commission,1972).
Hazleton Environmental Sciences has a comprehensive quality control /
quality assurance program designed to assure the reliability of data l
obtained.
Details of Hazleton's QA Program are presented,elsewhere l
(Hazleton Environmental Sciences,1982).
The HES QA Program includes participation in laboratory intercomparison (crosscheck) programs.
Results obtained in crosscheck programs are presented in Appendix A.
3.5 Program Modifications Beginning 1 January 1980, thirty-two (32) new TLD locations were added l
to the program as a " Lessons Learned" commitment. Ten (10) of these locations were selected in an inner ring in the general area of the site boundary, fifteen (15) in the outer ring within 4-5 mi radius of the plant, six (6) at special areas of interest, and one (1) at a control location,11.1 mi distant from the plant.
Three LIF2 chips were placed j
at each location and were exchanged and read quarterly.
l 6
e
HAZLETON ENVIRONMENTAL SCIENCES In addition, a complete emergancy set of TLDs is placed at all locations, including four air sampling locations.
The TLDs are returned to the HES laboratory quarterly for annealing and repackaging.
Several additional sample collections which are not a part of the program were perfor.ned in 1981. Three (3) goat's milk samples were collected from mid September through the mid October 1981 from two fams and analyzed for iodine-131.
3.6 Census of Milch Animals In accordance with Technical Specification 4.10, paragraph B, several surveys of milch animals were conducted in the area of the Plant during 1981. On 11 June 1981 an extensive survey was conducted within a one mile radius of the Plant (or 15 mrem / year distance).
Most cattle observed were used for beef rather than milk production.
No new milk producing herds were found.
On 16 June 1981 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 there were no changes in the milk herds in Minnesota and only location changes on the map of milk herds in Wisconsin. Current raw milk sampling locations were not affected. No new herds were identified.
On 16 June and 19 June 1981 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 that there were no i
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 l
program, certain goat milk samples, when available, were collected and analyzed.
On 16 September,17 September, and 18 September 1981 the mid-season census of milch producing animals was completed.
No new herds were identified.
None of the surveys resulted in changes of milk sampling locations.
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MAZLETON GNVIRONMHNTAL CCl2NCJD
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4.0 RESULTS AND DISCUSSION All collections and analyses were made as scheduled (see Table 5.3).
All results are summarized in Table 5.4 in a format recommended by the 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 locations with the highest mean and range are also shown.
4.1 The Effect of Chinese Atmospheric Nuclear Detonation There were no reported atmospher-ic nuclea.r tests in 1981.
The last reported test was conducted by,the People's Republic of China on 16 i
October 1980.
The reported yield was in the 200 kiloton to 1 megaton i
Il range.
The most pronounced effect of this test was on the gross beta levels in airborne particulates.
The annual mean. gross beta activity was about three and one-half times higher than in 1980.
The highest activity was reached in the month of May and in the second quarter and then by the end of 1981 declined steadily to the level observed in 1980.
Also, the pres-ence of fission products such as niobium-95, zirr: onium-95, ruthenium-103, cerium-141, cerium-144, and cesium-137 in some of the sampled media is attributable to the most recent (16 October 1980) and previous tests in the atmosphere.
4.2 Program Findings A number of program findings reflect effects of the latest Chinese and previous worldwide atmospheric nuclear tests.
The chief environmental indicators of a recent test effects were airborne particulates, and to a limited extent, natural vegetation, aquatic vegetation and shoreline sediments.
Ambient Radiation (TLD's) 4 At four regular air sampling locations, indicator TLD's averaged 12.9 t
mrem /91 days and control TLD's averaged 16.6 mrem /91 days.
The doses measured by control TLD's were about 30% higher than indicator TLD's.
Higher readings at control locations are due to higher readings at location P-2, which historically yielded about 40% higher readings than the second control location, P-1.
The means at special locations were similar to those measured at regular air sampling locations and ranged 3
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HAZLETON GNVIRONM~ INTAL GCCNC33 i
1 from 13.0 mrem /91 days at inner ring locations to 14.5 mrem /91 days at outer ring locations. The differences are not statistically significant.
The dose rates measured were similar to those observed in 1978 (12.1 and 15.1 mrem /91 days, respectively; in 1979 (12.6 and 15.3 mrem /91 days, respectively), and in 1980 (11.2 and ^13.5 mrem /91 days, respectively).
No Plant effect on ambient gamma radiation was indicated.
Air Particulates I
The average annual gross beta activity in airp)orne particulates was similar at bqth indicator locations (0.108 pCi/m and control locations l
(0.115 pCi/m*) and was about three and one-half times higher than in 1980 (0.032 pC1/m ).
The increase in the activity is attributable to 4
the fallout from the test conducted 16 October 1980. The highest averages for gross beta were for the month of May and the second quarter, then decreased gradually to the 1980 level by the end of the year.
The elevated activity in May and the second quarter was due to a spring peak, which has been observed almost annually (1976,1979 and 1980 were
- exceptions) for many years (Wilson et al.,1969).
The spring peak has been attributed to fallout of nuclides from the stratosphere (Gold et al.,
1964).
It was more pronounced in 1981 because of the addition of the l
radioactive debris from the latest nuclear test.
Two pieces of evidence indicate conclusively that the elevated observed activity during the second 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 Nuclear Generating Plant, about 100 miles distant from the Prairie Island Nuclear Generating Plant (Northern States Power Company,1982).
4 Trace amounts of niobium-95, zirconium-95, ruthenium-103, cerium-141, and cerium-144 were detected in some of the composite samples.
Presence of these isotopes in airborne particulates is also attributable to the i
fallout from the recent nuclear test.
Except for beryllium-7,which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih, 1955), all other gamma-emitting isotopes were below their respective LLD levels.
None of the activities detected were attributable to the Plant operation.
Airborne Iodine Airbofne iodine-131 results were below the detection limit of 0.07 L
pCi/m in all samples.
Thus, there was no indication of a Plant effect.
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MA2LETON ENVIRONMENTAL SCIENCES Milk Iodine-131 results were below the detection limit of 0.25 pCi/l in all samples.
Strontium-90 results were nearly identical at both indicator and control locations (3.6 and 3.7 pCi/1, respectively) and were in the range of 2.3-5.4 pCi/1, a range consistent with 1976,1977,1978,1979, and 1980 observations at Prairie Island.
Strontium-90 levels in this range are attributable to worldwide fallout from previous atmospheric nuclear tests and reflect the long half-life (28.6 yrs) of this isotcpe.
Cesium-137 results were below the LLD level of 15 pCi/1 in all samples.
Cesium-137 is also a long-lived component (with a half-life of 30.24 years) of worldwide fallout and is found in the environment in trace quantities.
Finally, all strontium-89 results in 1981 were <5.0 pCi/1, in agreement with 1976, 1977, 1978, 1979, and 1980 measurements.
No significant changes were seen in strontium-90 levels in milk and were similar to those observed in 1980.
This absence of an effect is consis-tent with the low initial production of this isotope in nuclear explo-sions (Eisenbud, 1963).
Also no other gamma-emitting isotopes, except potassium -40, were detected in any of the milk samples.
This is consis-tent 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 metaoolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center for l
Radiological Health,1968).
In sumary, the milk data for 1981 show no radiological, effects of the l
Plant operation, but the presence of strontium-90 in milk samples does exhibit a long range residual effect of previous atmospheric nuclear tests.
l Drinking Water l
In drinking water from the City of Red Wing well, no tritium was detected.
Results ranged from <240 to <360 pCi/1.
As with the other well water samples, all analyses for gamma-emitting isotopes yielded results below detection limits.
Gross beta averaged 10.7 pCi/l and was similar to the l
levels observed in 1979 (10.5 pCi/1), and 1980 (11.8 pCi/1).
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HAZLETON CNVIRONMZNTAL CCCNC"lO i
River Water At the upstream collection site, quarterly composite ' tritium levels ranged from <240 to 790 pCi/1.
i At the downstream site (Lock and Dam #3), quarterly composite tritium levels ranged from 200 to 660 pCi/1.
The differences in levels between upstream and downstream samples were not significant.
Analyses of river water were also made for gamma-emitting isotopes, strontium-89, and strontium-90.
All gamma-emitting isotopes and stron-tium-89 were below detection limits.
Strontium-90 was detected in two upstream samples and two downstream samples.
The mean activity was slightly higher in the upstream samples (1.0 pCi/1) than in downstream samples (0.8pC1/1), and was barely above the LLD level of 0.7 pCi/1.
There was no indication of a plant effect.
Well Water At the control well P-25, Kinneman Fam, tritium levels averaged 310 pCi/1, similar to the levels observed in 1979 (260 pC1/1), and 1980 (270 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 270 pCi/1 in any of the analyses.
The results ranged from <210 to <270 pCi/1 and were con-sistent with the results obtained in 1979 and 1980.
At the remaining indicator well (P-9, Plant Well #2), tritium was detected in three quar-terly samples and ranged from <310 to 340 pCi/1, averaging 320 pCi/1, essentially identical to the level at the control well P-25.
Gamma-emitting isotope levels were below detection limits in all cases.
1 Crops Cabbage samples were collected on 31 August 1981, and analyzed for iodine
-131.
Corn samples were also collected on 31 August 1981, and analyzed for gamma-emitting isotopes.
All results, except for potassium-40, were below detection limits.
There was no indication of a Plant effect.
l Natural Vegetation Natural' vegetation was collected on 7 May, 31 August, and 26 October 1981. No iodine-131 was observed in any of the samples collected.
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HA2LETON C"NVIRONM2NTAL CCIENCCQ Topsoil Topsoil was not collected in 1981.
In accordance with Technical Specifi-cations, soil is collected every three years.
The last collection was made in 1979.
Fish Fish samples were collected in May, August, September, and October 1981.
The only isotope detected was naturally-occuring potassium-40 and there was no significant difference between upstream and downstream results.
There was no indication of a Plant effect.
Aquatic Insects and Periphyton Aquatic insects (macroinvertebrates) and periphyton were collected on 22 May and 29 August 1981.
The samples were analyzed for strontium-89, strontium-90 and gamma-emitting isotopes.
Strontium-89 was below the limits of detection in all samples.
Mean strontium-90 levels were very low and averaged 0.062 pCi/g wet weight in the upstream (control) sample and 0.042 pC1/g wet weight in the downstream sample.
The difference between the downstream and upstream samples was not statistically signif-icant since uncertainty in the measurement is about at the same magnitude as the difference.
Trace amounts of niobium-95 and zirconium-95 were detected in some samples.
Presence of these isotopes is attributable to the fallout from the most recent nuclear test.
All other gamma-emitting isotopes, except for naturally-occuring potassium-40, were below their respective LLD's. No Plant effect was indicated.
Aquatic Vegetation Aquatic vegetation was collected on 22 May and 28 August 1981 and analyzed for gamma-emitting isotopes.
All results, except for potassium -40, were below detection limits. No Plant effect was indicated.
Bottom and Shoreline Sediments Sediment collections were made on 22 May and 28 and 31 August 1981.
The samples were analyzed for strontium-90 and gamma-emitting isotopes.
Strontium-90 was below the LLD of 0.016 pCi/g dry weight in all samples.
Cerium-137 was detected in one shoreline sediment sample (0.070 pCf/g dry weight).
Trace amounts of niobium-95 and ruthenium-103 were detected in two sam-ples.
Presence of trace amounts of these gamma-emitting isotopes is attributable to the recent nuclear test.
The only other gamma-emitting isotope detected was naturally-occuring potassium-40. No Plant effect was indicated.
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HAZLETON GNVIRONMENTAL CCGNC2O e
O 5.0 TABLES 1
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Table 5.1 Sample collection and anal,rsis program,1981.
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~ 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/Q Ambient gamma (TLD's)
P-3, P-4 32 P-01A - P10A C/Q Ambient gamma P-OlB - P-ISB z
P-OlS - P-06S P-01(C)
Airborne particulates 4
P-1(C),P-2(C),
C/W GB, GS (MC of P-3, P-4 all locations)
Z m
Airborne iodine 3
P-1(C),P-3, C/W I-131 Z
P-4 53l Milk 3
P-16 to P-18 G/M I-131 7
I 2
P-25(C),P-14 G/M I-131, Sr-89, a
Sr-90, GS River water 2
P-5(C),P-6 G/W GS(MC),H-3(QC) r-Sr-89 (QC)
P-l1 G/W GB,GS(MC),
Drinking Water H-3 (QC) g Well water 4
P-25(C), P-8 to G/Q H-3, GS P-10 Edible cultivated 2
P-25(C),P-24 G/A I-131 crops - green leafy vegetables ename 4
e e-- earm-'
o Table 5.1 (continued)
Prairie Island Collection Analysis Locations Type and Type (and Medium No.
Codes (and Typela Frequencyb Frequency)c 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 Fish (two species, 2
P-5(C), P-6 G/SA GS edible portion)
-4 Periphyton or 2
P-5(C), P-6 G/SA Sr-89, Sr-90 0
Macroinvertebrates GS Z
Aquatic Vegetation 2
P-5(C), P-6 G/SA GS s
80tton Sediment 2
P-5(C),P-6 G/SA GS, Sr-90 0
Ei 2
Shoreline Sediment 1
P-12 G/SA GS, Sr-90 l
d Topsoil 9
P-1(C), P-2(C)
G/ETY GS, Sr-90 P-3, P-4, P-19 to r-P-23 m
D a Location codes are defined in Table D-2.
Control stations are indicated by (C).
l All other stations are indicators.
n b
Collection type is coded as follows: C/ e continuous, G/ = grab. Collection j
frequency is coded as follows: W = weekly, M = monthly, Q = quarterly, SA = semi-annually, A = annually, ETY = every three years.
c Analysis type is coded as follows: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium, Sr-89 = strontium-89, Sr-90 = strontium-90, I-131 = f odine-131.
Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly composite.
d Collected in 1979. Next scheduled collecction is in 1982.
i i
HATt BTON CNVIRINMENTAL CCCNC2O l
l.
Table 5.2 Sampling locations.
Prairie Island Code Typea Name Location P-1 C
Station P-1 (Control-Air) 16.5 mi 9 348*/NNW P-2 C
Station P-2 (Control-Air) 10.9 mi 9 47*/NE 4
i P-3 Station P-3 (X/Q res, Comm-Air) 0.8 mi 9 313*/NW P-4
. Station P-4 (X/Q-Air) 1.6 mi 0 129*/SE
{
P-5 Upstream of Plant (1000')
0.6 mi 9 60*/ENE P-6 Lock & Dam #3 1.6 mi 9 129*/SE i
P-7b C
Most Fam Well 11.4 mi 9 320*/NW i
P-8 Kinney Store 2.0 mi 9 280*/W i
P-9 Plant Well #2 (on-site) 0.3 mi 9 306*/NW
]
P-10 Lock & Dam #3 Well 1.6 mi 9129*/SE 1
P-11 City of Red Wing (Drinking Water) 7.1 mi 0 135*/SE P-12 Recreational Area 3.4 mi 0 116*/ESE P-13b C
Most Farm (Prescott) 11.4 mi 9 320*/NW j
P-14 Gustafson Fam (X/Q-milk) 2.2 mi 0 168*/SSE P-15 Downwind Field 0.6 mi 9 162*/SSE P-16 A. Dosdahl Farm 2.5 mi 9 39*/NE P-17 Place Fam 3.5 mi 9 25*/NNE i
P-18 Birk Fam 3.5 mi 9181*/S P-19 Commissary Point Park 1.0 mi 9 156*/SSE l
P-20 Meteorology Station 0.4 mi 9 296*/WNW j
P-21 Sturgeon Lake Access 0.4 mi 9 344*/NNW i
P-22 Former TLD #14 Location 0.5 mi 9 230*/SW i
P-23 Fomer TLD #15 Location 0.5 mi 9 184*/S P-24 H. Larson Residence (Nearest 1.6 mi 9 287*/WNW Garden)
P-25C C
Kinneman Fam (Control-Milk, etc) 11.1 mi 9 331*/NNW i
P-26d Augustine Farm 5.7 mi 9 24*/NNE i
P-27d Murphy Fam 2.8 mi 9 42*/NE l
P-01A Property Line North Sector. Sampler is on the side of the fence i
adjacent to corps of Engineers public access parking area and facing j
the plant.
P-02A Property Line NNE Sector. Sampler at a i
corner of the property i
line fence near the biology station.
P-03A Property Line South Sector. Sampler is adjacent the SE end of a i
guard rail along the road near a power pole.
16
HAZLETON GNVIRONMZNTAL ECISNC]O Table 5.2 (continued)
Prairie Island l'
Code Typea Name Location i
l P-04A Property Line SSW Sector. Sampler is adjacent ot the NW end of a guard rail along the roadway next to a small access road.
P-05A Property Line SW Sector. Sampler is inside the fence area adjacent to a transmission tower.
P-06A Property Line WSW Sector. Sampler is inside the fenced area adjacert to a telephone junction box and south of an underground cable warning sign..
P-07A Property Line West Sector. Sampler is inside the fenced area about 75 feet North of the railroad entrance gate adjacent to a fence sign.
P-08A Property Line WNW Sector. Sampler is adjacent to the last power pole that serves the Meteorological station along the property fence line.
P-09A NW Sector. Sampler is in north west corner of the property fenced area, just inside the fence and facing the plant.
P-10A Property Line NNW Sector. Sampler is i
inside the fence west of the north entrance gate facing the plant adjacent to a transmission tower.
P-01B Thomas Killian North Sector. Sampler is i
Residence adjacent to a power pole north of the driveway.
P-028 Ray Kinneman Farm NNE Sector. Sampler is south of the driveway adjacent to a telephone junction box.
I 17
t HA2LETON EINVIRONMZNTAL CCl3NCZO 4
~
Table 5.2 (continued)
Prairie Island Code Typea Name Location P-03B Wayne Anderson Farm NE Sector. Sampler is in the front yard adjacent to a power pole facing toward the plant.
P-048
- Nelson Drive (Road)
ENE Sector. Sampler is adjacent to a power pole i
and a telephone junction box, about 15 feet south of the road.
P-05B Country Road E near East Sector. Sampler is Goodwin Coulee Road north of Country Road E and about 300 ft. NW of the Goodwin Coulee Road (near a power pole that has a " Danger High Voltage" sign on it and about 25 ft. NW of the Richard Enberg mail box).
P-06B William Hauschildt ESE Sector. Sampler is Residence between a power pole and telephor.e junction box on the east side of the driveway.
P-07B Red Wing Service Center SE Sector.
(North Highway 61 on Tyler Road)
Sampler is adjacent to a corner transmission pole and the Railroad right-of-way close to a chain link fence.
P-088 David Wnuk Residence SSE Sector. Sampler is on the west edge of property adjacent to a telephone control pole and a road sign "D0 NOT PASS".
P-09B Highway 19, South of 61 South Sector. Sampler is adjacent to a pola support.
ing a telephone junction box and opposite a new bridge on the east side'of highway 19.
O 18
HAZLETON GNVIRONMINTAL ECIXNCCG Table 5.2 (continued)
Prairie Island Code Typea Name Location P-10B Cannodale Farm SSW Sector. Sampler is (Lesson Lane-James Byron) adjacent to a corner fence post and near a " Speed Limit 30" road sign.
P-11B
~ Wallace Weberg Farm SW Sector.
(Fam is on top of the bluff). Sampler is adjacent to a power pole and the telephone junction box facing the plant (ease of driveway).
P-128 Ray Gergen, Jr. Fam WSW Sector. Sampler is north of driveway in the farmyard on the east end of a storage shed facing the plant.
P-13B Thomas O'Rourke Fam West Sector. Sampler is adjacent to a power pole and a telephone junction box outside a stock fence area.
P-14B David J. Anderson Farm NW Sector. Sampler is near the front yard south of a red cedar tree (not located near the main road for protection).
P-15B Holst Farm NNW Sector. Sampler is east of residence near a corner post of a fenced area.
P-01S Federal Lock & Dam #3 SE Sector. Sampler is north of the fenced air l
sampling station (#4) and facing the plant.
P-02S Charles Suter Residence SSE Sector. Sampler on the north side of a power pole in the fam yard and i
facing the plant.
P-03S Carl Gustafson Farm SSE Sector. Sampler is near the north side of the road in the last curve before the farmyard.
(Close to the corner power pole and a fence post).
19 i
MAZLCTrON CNVIRONM2NTAL CCl2NCCD l-Table 5.2 (continued)
Prairie Island Code Typea Name Location P-045 Near Richard Burt SW Sector Sampler is Residence next to a tree about 15 feet away from the curve in the road.
P-05S Kenney Store -
West Sector. Sampler is Trailer Park at the north end of a redwood fence and adjacent to a telephone junction box.
P-06S Earl Flynn Farm WNW Sector. Sampler is on the east side of the house adjacent to a huge stump and facing the plant.
P-01C Robert Kinneman Farm NNW Sector. Sampler is about 250 ft. east of the residence adjacent to a corner fence post and facing the plant.
a"C" denotes control location. All other locations are indicators.
b -13 discontinued after March 1978.
P cP-25 added in April 1978.
d -26 and P-27 added in July 1978 (Goat's Milk).
P e
20
Table 5.3.
Missed collections and analyses,1981; Prairie Island NGP All required samples collected and analyzed except the following:
Coll. Date Sample Analysis Location or Period Comments NO MISSED COLLECTIONS I
aO Z
m Z
5m O
ro Z
Ia c
W G
Eo i
Table 5.4 Environmental Radiological Monitoring Program Summary.
Name of facility Prairie Island Nuclear Generating Plant Docket No. 50-282, 50-33 Locition of facf1Tfy GEdfGieTMinnescta Reporting Period January-December 1981 (CEriti, 5 titer Indicator
. Location with Highest Control Sample Type and Locationg Annual Mean Locations Number of Type Number of Mean[F)
MeantFI Mean[F)
Non-routine (Units)
Analysesa LLDb RangeC Locationd Range Range Result #
TLD Gamma 16 1.0 12.9 (8/8)
P-2, Station P-2 18.6 (4/4) 16.6 (8/8) 0
~-
(ares /91 days)
(11.7-14.6) 10.9 al 9 47*/NE (15.7-20.8)
(14.0-20.8)
TLD Gamma 40 3.0 13.0 (40/40)
P-03A Property Line 13.6 (4/4)
(See control 0
(aren/91 days)
(6.7-17.4)
S Sector (11.5-17.2) below) y (Inner Ring, g
General Area at N
Site Boundary) r TLD Gamma 60 3.0 14.5 (60/60)
P-048 Nelson Drive Road 15.8 (4/4)
(See control 0
(ares /91 days (11.0-21.3)
ENE Sector (11.9-16.2) below) 0 (Outer ring, Z
4-5 miles m
distant)
Z<
y TLD Gamma 24 3.0 13.4 (24/24)
P-045 Wear Richard 14.7 (4/4)
(See control 0
(mres/91 days (9.5-19.2)
Burt Residence (12.3-19.2) below) 3O (Special SW Sector Z
Interest Areas)
TLD Gamma 4
3.0 None P-01C-R. Kinneman Fars 13.9 (4/4) 13.9 (4/4)
O M
(ares /91 days)
NNW Sector (12.3-15.51 (12.3-15.5) 2 (control) g r
Airborne GB 208 0.002 0.108 (104/104)
P-1, Station P-1 0.115 (51/52) 0.115 (102/104) 0 18 Particulates (0.005-0.566)
(Control-Afr)
(0.007-0.367)
(0.007-0.389)
O (pct /m3) 16.5 mi 9 348*/NNW ji Z
P-4, Station P-4 0.115 (52/52)
None 0
g (X/Q-Afr) 1.6 mi 9 (0.005-0.566) m 129*/SE (A
GS 12 Be-7 0.065 0.099 (8/12)
NA None 0
(0.055-0.134)
Mn-54 0.0020
<LLD None O
Co-58 0.0033
<LLD None 0
i Co-60 0.0023
<LLD None 0
l 2n-65 0.0037
<LLD None O
None 0
Nb-95 0.0051 0.065 (7/12)
NA (0.030-0.105)
o Table 5.4 (Continued)
Name of facility Prairie Island Nuclear Generating Plant ___
Indicator Location with Highest Control Sample Type and Locationg Annual Mean Locations Number of Type Number of Mean(F)
Mean(F)
Mean(F)
Non-routine (Units)
Analysesa LLDb RangeC Locationd Range Range Results*
None O
Lirborne 2r-95 0.0014 0.039 (6/12)
Particulates (0.015-0.053)
(pci/m )
3 None 0
(Cont'd)
Ru-103 0.012 0.020 (5/12)
NA (0.0094-0.0260)
None 0
g Ru-106 0.028
<LLD None 0
N Cs-134 0.0019 (LLD None 0
Cs-137 0.014 (LLO None 0
0 Ba-140 0.013 (LLD Z
None O
M La-140 0.0020 (LLD Z
Ce-141 0.015 0.016 (2/12)
NA None 0
m ta (0.016-0.016) g 0
None 0
Ce-144 0.012 0.042 (5/12) 2 (0.029-0.064)
Ea (LLD 0
Z Airborne 1-131 156 0.07
<LLD
-i Iodine (pC1/m3I W
<LLD 0
- LLD 0
Sr-89 24 5.0 (LLD Sr-90 24 2.8 3.6 (6/6)
P-25 Kinneman Fare 3.7 (12/12) 3.7 112/12) 0 g
(3.2-4.3) 11.1 mi e 331*/NNW (2.3-5.4)
(2.3-5.4) g GS 24 K-40 100 1390 (12/12)
P-14 Gustafson Fars 1390 (12/12) 1330 (12/12) 0 (1250-1800) 2.2 mi e 168*/5SE (1250-1800)
(1110-1570)
<LLD 0
Cs-134 15 (L LD
<LLD 0
Cs-137 15
<tLD
<LLD 0
Ba-La-140 21'
<LL D
r Table 5.4 (Continued)
Name of facility Prairie Island Nuclear Generating Plant Indicator Location with Highest Control Sample Type and Locationg Annual Mean Locations Number of Type Number of Mean(F's Mean(F)
Mean(F)
Non-routine tunits)
Analysesa LLDb RangeC Locationd Range Range Results*
D'rinking Water G8 12 1.0 10.7 (12/12)
P-11 City of Red Wing 10.7 (12/12)
None 0
(pct /1)
(7.3-16.9) 7.1 al 9 135*/SE (7.3-16.9)
H-3 4
360 (LLD None O
I Co-58 15
<tLD None O
None 0
r' Co-60 15
<tLD M
None O
Zn-65 30 (LLD None 0
2 Nb-95 20
<LLD 5
None 0
2 Zr-95 26 (LLD N
None 0
g Cs-134 15
<LLD None 0
Ba-La-140 15
<LLD M
None 0
2 Ce-144 108 (LLD I
River Water H-3 8
340 660 (1/4)
P-5. Upstream of Plant 790 (1/4) 790 (1/4) 0 (pct /1)
(1000 ) 0.6 at 9 60*/ENE IO D
(LLD 0
m Sr-89 8
1.9 (LLD Z
Sr-90 8
0.7 0.8 (2/4)
P-5. Upstream of Plant 1.0 (2/4) 1.0 (2/4) 0 O
(0.8-0.9)
(1000 ) 0.6 at 9 60*/ENE (0.8-1.2)
(0.8-1.2)
M IA GS 24
<tLD 0
Mn-54 15
<LLD (LLD 0
Co-58 17
<LLD 0
Nb-95 31
<LLD
<LLD 0
Table 5.4 (Continued)
Name of factitty Prairie Island Nuclear Generating Plant __
Indicator Location wtth Highest Control Annual Mean Locations Number of Sample Type and Locationg Type Number of Mean(F)
Rean(F)
Mean(F)
Non-routine (Units)
Analysesa LLDb Rangec Locationd Range Range Results' (LLD 0
River Water 2r-95 30 (LLD (p/Cf/I)
(LLD 0
(Cont'd)
Cs-134 15 (LLD
<LLD 0
Cs-137 18
<LLD
<LLD 0
Ba-La-140 29 (LLD
<LLD 0
Ce-144 130 (LLD Well Water H-3 16 270 320 (3/12)
P-9 Plant Well No. 2 320 (3/4) 310 (2/4) 0 O
(pci/1)
(310-340) 0.3 at 9 306*/NW (310-340)
(280-340)
Z cs 16 m
Z
<LLD 0
Co-58 25
<LLD
<LLD 0
2 (LLD 0
E Zn-65 30 (LLD Z
g
<LLD 0
Nb-95 15
<LLD I
(LLD 0
Zr-95 36
<lLD N
<LLD 0
0 Cs-134 15
<tLD N
<LLD 0
2 Cs-137 18
<LLD O
<LLD 0
M Ba-La-140 20
<LLD M
<LLD 0
Crops-Cabba9e 1-131 2
0.071
<LLD (pC1/g wet)
5
+
Table 5.4 (Continued)
Name of facility Prairie Island Nuclear Generating Plant Indicator Location with Highest Control Sample Type and Locationg Annual Mean Locations Number of (Units)
Nueer of Mean(F)
Mean[F)
Mean(F)
Non-routine Type Analysesa LLDb RangeC Locationd Range Range Results'
<LLD 0
Crops-Corn I-131 2
4.8
<LLD (pCi/g wet)
GS 2
<LLD 0
Be-7 0.37
<LLD K-40 0.5 1.56 (1/1)
P-25 Kinneman Fars 1.96 (1/1) 1.96 (1/1) 0 3
11.1 mi 9 331*/NNW
)
N
<LLD 0
Mn-54 0.033
<LLD Co-58 0.039
<tLD
<LLD 0
g
<tLD 0
2 Co-60 0.026
<LLD M
<LLD 0
Z Zn-65 0.059 (LLD
<LLD 0
g Nb-95 0.057
<LLD m*
g Ru-103 0.074
<LLD
<LLD 0
$E
<LLD 0
2 Ru-106 0.22 (LLD
<tLD 0
Cs-134 0.022
<LLD 7
<LLD 0
10 Cs-137 0.023
<LLD 0
Ba-140 0.11
<LLD
<LLD 0
m2 (LLD 0
0 La-140 0.055
<tLD E
<tLD 0
18 Ce-141 0.14 (LLD
<LLD 0
Ce-144 0.22
<tLD (LLD 0
Natural I-131 6
0.093
<LLD Vegetation (pci/g wet)
GS 6
Be-7 0.57 1.95 (2/4)
P-14. Gustafson Fars 2.94 (1/2) 2.81 (2/2) 0 (0.95-2.94) 2.2 et 8 168*/55E (0.88-4.74)
K-40 0.5 4.5 (4/4)
P-15, Downwind Field 4.74 (2/2) 4.24 (2/2) 0 (3.43-5.09) 0.6 mi e 162*/55E (4.69-4.78)
(4.06-4.41)
Table 5.4 (Continued)
Name of facility Prairie Island Nuclear Generating Plant Indicator Location with Highest Control Annual Mean Locations Number of Sample Type and Locationg Type Number of Mean(F)
Mean(F)
Mean(F)
Non-routine (units)
Analysesa LLDb RangeC Locationd Range Range Results*
Watural Mn-54 0.045
<LLD
- <LLD 0
vegetation (LI D 0
(pC1/9 wet)
Co-58 0.036
<LLD (Coat d)
(LLD 0
Co-80 0.040
<tLD Zn-65 0.11
<LLD
<LLD 0
g Nb-95 0.085 0.37 (3/4)
P-15, Downwind Fleid 0.38 (1/2) 0.36 (2/2) 0 (0.18-0.55) 0.6 et 9 162*/55E (0.30-0.43)
Zr-95 0.13 0.23 (3/4)
P-25. Kinneman Fara 0.24 (1/2) 0.24 (1/2) 0
-40 (0.13-0.34) 11.1 al 9 331*/NNw Z
Ru-103 0.064 0.11 (2/4)
P-14, Gustafson Fara 0.14 (1/2) 0.074 (1/2)
O M
(0.087-0.140) 2.2 el 9 168*/55E 7
y
<LLD 0
Ru-106 0.40 (LLD 3
0 Z
<LLD 0
{
Z La-140 0.053
<LLD
<LLD 0
>r Ce-141 0.12 0.17 (1/4)
P-14, Gustafson Fars 0.17 (1/4) 0.10 (1/2) 0 3
2.2 at 8 168*/55E Q
Ce-144 0.51 0.48 (1/4)
P-25, Kinneman Fara 0.58 (2/2) 0.58 (2/2) 0 11.1 at # 331*/NNw (0.49-0.66)
(0.49-0.66) g.g IR lA Fish-Flesh GS 8
(PC1/g wet)
K-40 0.1 2.97 (4/4)
P-5.UpstreamofPlant 3.04 (4/4) 3.04 (4/4) 0 (2.39-4.00)
(100010.6 al 9 60*/ENE (2.04-3.55)
(2.04-3.55)
<tLD 0
Mn-54 0.33
<LL D
<tLD 0
Co-58 0.042 (LLD
<LLD 0
Co-60 0.025
<tLD
<LLD 0
Zn-65 0.088
<LLD
Table 5.4 (Continued)
Name of facility Prairie Island Nuclear Generating Plant Indicator Location with Highest Control Sample Type and Locationg Annual Mean Locations Number of Type Number of Mean(F)
Mean(F)
Mean(F)
Non-routine (c its)
Analysesa LLDb RangeC Locationd Range Range Results*
Fish-Flesh Nb-95 0.068 (LLD
<LLD 0
(pCf/9w)et)
(Coat d Zr-95 0.11
<LLD
<LLD 0
Cs-134 0.025
<tLD
<LLD 0
<LLD 0
I
}
Ba-La-140 0.070 (LLD
<LLD 0
E Periphyton Sr-89 4
0.166
<tLD l
<LLD 0
)
(ptt/g wet)
Sr-90 4
0.01 0.042 (2/2)
P-5. Upstream of Plant 0.052 (2/2) 0.062 (2/2) 0 2
(0.011-0.073)
(1000') 0.6 al 9 60*/ENE (0.014-0.109)
(0.014-0.109)
M to GS 4
2g Be-7 0.89
<tLD
<LLD 0
K-40 1.0 3.30 (2/2)
P-6. Lock 8 Dan #3 3.30 (2/2) 2.20 (2/2) 0 2
(3.12-3.47) 1.6 al 9 129'/SE (3.12-3.47)
(1.55-2.85)
Em Mn-54 0.057
<t LD
<tLD 0
Co-58 0.098
<LLD
<LLD 0
Co-60 0.054
<LLD
<tLD 0
a 2n-65 0.16
<t L D
<LLD 0
I2 Nb-95 0.17 0.26 (1/2)
P.S. Upstream of Plant 0.30 (2/2) 0.30 (2/2) 0 O
i 11000*) 0.6 al 9 60*/ENE (0.30-0.31)
(0.30-0.31)
M i
M Zr-95 0.18 0.33 (1/2)
P-6. Lock & Dan #3 0.33 (1/2) 0.26 (1/2) 0 4
1.6 al 9 129'/SE I
Ru-103 0.15
<LLD l
<LLD 0
Ru-306 0.51 (LLD
.4
<LLD 0
Cs-134 0.071
<tLD
<LLD 0
1 Cs-137 0.087
<LLD i
<tLD 0
4 i
0 Table 5.4 (Continued)
Name of facility Prairie Island Nuclear Generating Plant Indicator Location with Highest Control Sample Type and Locationg Annual Mean Locations Number of Type Number of Mean(F)
Mean(F)
Mean(F)
Non-routine RangeC Locationd Range Range Results' i
(Units)
Antlysesa LLDb Periphyton Ba-140 0.19 (LLD
<LLD 0
(pci/9w)et)
(Cont d La-140 0.076 (LLD
<LLD 0
<LLD 0
Ce-141 0.23
<LLD f
<LLD 0
Ce-144 1.01
<LLD N
Aquatic GS 4
g Ve9etation
-1 (pCf/g wet)
Be-7 0.79
<LLD
<LLD 0
0 Z
4 K-40 0.5 1.69 (2/2)
P-6, Lock & Dan #3 1.69 (2/2) 0.98 (2/2) 0 g
)
(0.56-2.82) 1.6 al 9 129'/SE (0.56-2.82)
(0.98-0.99) 7
<LLD 0
Mn-54 0.056
<LLD 2
(LLD 0
0 Co-58 0.074 (LLD Z
<LLD 0
{
Zn-65 0.13 (LLD
<LLD 0
Z
<LLD 0
)
Nb-95 0.14
<LLD e
(LLD 0
(g Zr-95 0.15 (LLD O
Ru-103 0.091
<LLD
<LLD 0
g Ru-106 0.54
<LLD
<LLD 0
}
Cs-134 0.056
<tLD
<LLD 0
<LLD 0
Ba-La-140 0.12 (LLD
<LLD 0
<LLD 0
Ce-141 0.20
<LLD
<LLD 0
Ce-144 0.51
<LLD
Table 5.4 (Continued)
Name of facility Prairie Island Nuclear Generating Plant Indicator Locaffon wilh Highest Control Sample Type and Locationg Annual Mean Locations Number of Type Number of Mean(f)
Mean(FI Mean(F)
Non-routine (Units)
Analysesa LLDb RangeC Locationd Range Range Resultse Bottom aad Sr-90 6
0.016
<LLD
<LLD 0
Shoreline Sediments GS 6
(pCl/g dry)
Be-7 0.74
<LLD (LLD 0
K-40 1.0 13.54 (4/4)
P-12, Recreational 13.42 (2/2) 11.91 (2/2) 0-(12.35-14.48)
Area 3.4 at 9 (12.35-14.48)
(10.61-13.21)
I 116*/ESE (LLD 0
<LLD
<LLD 0
-i0 (LLD 0
Z Co-60 0.050
<LLD
<LLD 0
Zn-65 0.15
<LLD (LLD 0
Nb-95 0.084 0.182 (1/4)
P-6, Lock & Das No. 3 1.6 mi 0 129*/SE 31 O
<LLD 0
2 Zr-95 0.13 (LLD E
Ru-103 0.067 (LLD P-5, Upstream of Plant 0.19 (1/2) 0.19 (1/2) 0 g
0.6 mi 9 60*/ENE g
Ru-106 0.32
<LLD
<tLD 0
)r Cs-134 0.031
<LLD
<LLD 0
g O
Cs-137 0.057 0.070 (1/4)
P-12 Recreational Area
<LLD 0
g 3.4 mi e ll6*/ESE 7
h Ba-140 0.19
<LLD (LLD 0
(LLD 0
La-140 0.042 (LLD Ce-141 0.13'
<LLD
<LLD 0
(LLD 0
Ce-144 0.28 (LLD aGB = gross beta; BS = gamma scan, btLD = nominal lower Ilmit of detection based on 3 sigma error for background sample, cMean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).
dLocations are specified (1) by name and code (Table 2) and (2) distance, direction, a~nd sector relative to reactor site.
'Nonroutine results are those which exceed ten times the control station value. If no control station value is available, the result is considered nonroutine if it exceeds ten times the preoperational value for the location.
f onthly composites from all locations were gamma scanned together. Thus the location with the highest annual mean cannot be Midentified.
HA2LETON CNVIRONMENTA1. CCISNC'lO
6.0 REFERENCES
CITED Arnold, J.
R.
and H.
A. Al-Sal t h.
1955.
Beryllium-7 Produced by Cosmic Rays. Science 121: 451-453.
Eisenbud, M.
1963.
Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275 and 276.
Gold, S., H. W. Barkhau, B. Shlein, and B. Kahn,1964. Measurement of Natural-ly Occuring Radionuclides in Air, in the Natural Radiation Environment, University of Chicago Press, Chicago, Illinois, 369-382.
Hazleton Environmental Sciences Corporation.
1978.
Sampling Procedures, Prairie Island Nuclear Generating Pl ant, Revision 10, 10 March 1981.
1979a.
Radiation Envi ronmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -
December 1978.
1979b.
Radiation Environmental Monitoring for Monticello Island Nuclear Generating Plant, Complete Analisis Data Tables, January -
December 1978.
4 1980a.
Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January -
December 1979.
1980b.
Radiation Envi ronmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, Janauary
- December 1979.
1981a.
Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December 1980.
1981b.
Radiation Environmental Monit.oring for Prarie Island Nuclear Generating Plant, Complete Analysis,D'ata Tables, January -
December 1980.
1982a.
Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January -
December 1981.
1982b.
Radiation Envi ronmental Monitoring for Prairie.
Island Nuclear Generating Plant, Complete Analysis Data Tables, January -
December 1981.
1971a.
Quality Control Program, Nuclear Sciences Section, Revision 5, 6 November 1981.
1971b.
Quality Control Procedures Manual, Nuclear Sciences Section, Revision 4, 4 April 1981.
31 i
~
~
--,,m
-,,-n-ww-w-
-,,_-.,,r-,,-
,,-m
HA2LETON ENVIRONMENTAL CCCNC23 1982.
Quality Assurance Program Manual, Revision 0, 1
January B82.
1977.
Analytical Procedures Manual, Nuclear Sciences Section, Revision 3, 22 May 1981.
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 Environmuotal Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1977 through December 31,1977 (prepared by NALCO Environmental Sciences) Minneapolis, Minnesota.
i 1979.
Prairie Icland Nuclear Generating Plant, Annual Radi-ation Environmental Monitoring Report to the U.S.
Nuclear Regulatory Commission, January 1,1978 to December 31,1978 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.
1980.
Prairie Island Nuclear Generating Plant, Annual Radt-ation Environmental Monitoring Report to the U.S.
Nuclear Regulatory Commission, January 1,1979 to December 31,1979 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.
U. S. Atomic Energy Commission.
1972.
HASL 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 Radiation 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 Environmental Samples, National Center for Radiological Heal th, Rockville, Maryland (Public Health Service Publication No. 999-RH-27).
Wilson, D. W., G. M. Ward and J. E. Johnson.
1969.
In Environmental Contam-ination by Radioactive Materials, International Atomic Energy Agency.
- p. 125.
32 l
l l
L
HAZLETON CNVIRONMZNTAL CCI"iNC~'O Appendix A Crosscheck Program Results O
i e
9 I
i A-1 l
[
HA2LETON CNVIRONMENTAL SCCNC]'3 Appendix A Crosscheck Program Results The Nuclear Sciences Department of Hazleton Environmental Sciences has parti-cipated in interlaboratory comparison (crosscheck) programs since the formula-tion of its quality control program in December 1971.
These p(rograms 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 s'pecified radionuclides and report them to the issuing agency.
Several months later, the agency reports the known values to the participant laboratories 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 environ-mental sample crosscheck program for milk and water samples during the period 1975 through 1981.
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 dosimeters (TLD's) during the period 1976,1977,1979,1980, and 1981 through participation in the Second, Third, Fourth, and Fifth International Intercomparison of Environmental Dosimeters under the sponsorships listed in Table A-2.
E 9
f l
1 6
h 9
i A-2
HA2LETON ENVIRENMINTAL. CCCNCZ3 Table A-1.
U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Hazleton ES results for milk and water samples, 1975 through 1981a, Concentration in 3Ci/lb Lab Sample Date HES Result EPA lesult Code Type Coll.
Analysis 22 a c 3e, n=1d STM-40 Milk Jan. 1975 Sr-89
<2 0215 Sr-90 7322.5 75211.4 I-131 99 4.2 101215.3 Cs-137 7620.0 75215 Ba-140
<3.7 Ot15.0 K(mg/l) 147025.6 15102228 STW-45 Water Apr. 1975 Cr-51
<14 0
Co-60 42126 425263.9 Zn-65 487 6 497274.7 Ru-106 505:16 497t74.7 Cs-134 38523 400260.0 Cs-137 46823 450267.5 STW-47 Water Jun. 1975 H-3 1459:144 149921002 STW-48 Water Jun. 1975 H-3 2404t34 2204:1044' STW-49 Water Jun. 1975 Cr-51
<14 0
Co-60 34421 350253 Zn-65 33025 327249 Ru-106 31527 325249 Cs-134 29121 304246 Cs-137 38722 378257 STW-53 Water Aug. 1975 H-3 3317264 320021083 STW-54 Water Aug. 1975 Cr-51 223211 225238 Co-60 30521 307t46 Zn-65 28923 281242 Ru-106 34625 279257 Cs-134 23821 256238 Cs-137 29222 307246 STW-58 Water Oct. 1975 H-3 1283 80 12032988 STM-61 Milk Nov. 1975 Sr-90 68.922.1 74.6211.2 1-131 64.623.8 75215 Cs-137 75.6220 75215 Ba-140
<3.7 0
K(Mg/1) 1435257 15492233 A-3
HAZLETZN ENVIRINMENTAL. CCI~NC2]
Table A-1.
(continued)
Concentration in DCf/lb Lab Sample Date HES Result EPA Result 3a, n=1d Code Type Coll.
Analysis t2 oc STW-63 Water Dec. 1975 H-3 1034 39 10022972 STW-64 Water Dec. 1975 Cr-51
<14 0
Co-60 22121 203230.5 Zn-65 215 6 201230.2 Ru-106 171t9 181227.2 Cs-134 19822 202230.3 Cs-137 15224 151222.7 STW-68 Water Feb. 1976 H-3 1124t31 1080 978 STW-78 Water Jun. 1976 H-3 2500244 250221056 STW-84 Water Aug. 1976 H-3 3097221
.310021080 STM-86 Milk Sep. 1975 Sr-89 2922.0 45 15 Sr-90 3021.0 3024.5 I-131 10028.6 120218 Ba-140 50t10.1 85215 Cs-137 17 1.5 20215 K(mg/1) 15402231 STM-91 Milk Nov. 1976 I-131 8320.6 85215 Ba-140
<4 0
Cs-137 12 1.7 11215 K(mg/1) 1443 31 15102228 STW-93 Water Dec. 1976 Cr-51 105215 104215 Co-60
<4 0
Zn-65 9724 102215 Ru-106 8723 99215 Cs-134 85t4 93215 Cs-137 103 4 101215 STW-94 Water Dec. 1976 H-3 2537215 230021049 STM-97 Milk Mar. 1977 I-131 5522.5 51 15 Ba-140
<6 0
Cs-137 3421 29215 K(mg/1) 1520235 15502233 STW-101 Water Apr.' 1977 H-3 1690 62 176021023 A-4
HA2LETON ENVIRINMZNTAL CCCNCZ"3 Table A-1.
(continued)
Concentration in DCi/lb Lab Sample Date HES Result EPA Result Code Type Coll.
Analysis 2oc 3 c, n=1d STM-130 Milk May 1977 Sr-89 3822.6 44215 Sr-90 12 2.1 1024.5 I-131 5922.1 50 15 Ba-140 53 4.4 72215 Cs-137 1421.2 10215 K(mg/l) 1533 21 1560 234 STW-105 Water Ju'n. 1977 Cr-51
<14 0
Co-60 2921 29 15 Zn-65 7427 74215 Ru-106 64 8 62215 Cs-134 41 1 44215 1
Cs-137 3523 35215 STW-107 Water Jun. 1977 Ra-226 4.720.3 5.1 2.42 STW-113 Water Aug. 1977 Sr-89 13208 14 15 Sr-90 1022e 1024.5 t
STW-116 Water Sep.1977 Gross Alpha 1225 10215 Gross Beta 3226 30 15 STW-118 Water Oct. 1977 H-3 1475229 165021017 STW-119 Water Oct. 1977 Cr-51 132 14 153224 Co-60 3922 38215 t
Zn-65 5125 53215 i
Ru-106 6326 74215 Cs-134 30 3 30215 Cs-137 26 1 25215 i
e STW-136 Water Feb. 1978 H-3 16902270 168021020 t
STW-137 Water Feb. 1978 Cr-51
<27 0
Co-60 3622 34215 Zn-65 3224 29215 Ru-106 4122 36215 Cs-134 4722 52215 Cs-137
<2 0
A-5
HAZLETON CNVIRONM3NTAL CCENCQ Table A-1.
(continued)
Concentration in DCi/lb Lab Sample Date HES Result EPA Result Code Type Coll.
Analysis 2a e 3a, n=1d STW-138g Water Mar. 1978 Ra-226 5.4p.1 5.520.6 Ra-228 NA 16.722.5 STW-150 Water Apr. 1978 H-3 12502220 222021047 STW-151 Water Apr. 1978 Gross Alpha 20 1 20 15 Gross Beta 56 4 59 15 Sr-89 1922 21 15 Sr-90 82}
10 4.5 Ra-226 NA Ra-228 NAf H-3 112 12 0
Co-60 19 3 20 15 Cs-134 1621 15 15 Cs-137
<2 0
STM-152 Milk Apr.1978 Sr-89 8524 101215 Sr-90 8t1 924.5 I-131 78t1 82 15 Cs-137 2923 23 15 Ba-140
<11 0
K(mg/1) 1503290 15002225 STW-154g Water May 1978 Gross Alpha 12 1 13 15 Gross Beta 2124 18215 STW-157g Water Jun. 1978 Ra-226 4.02}.0 3.7 0.6 i
Ra-228 NA 5.6 0.8 l
STW-1599 Water Jul. 1978 Gross Alpha 19 3 2226 Gross Beta 2823 30 5 STW-162 Water Aug. 1978 H-3 1167 38 12302990 STW-1659 Water Sep. 1978 Gross Alpha 4t1 525 Gross Beta 1321 1025 i
I e
A-6
HA2LETON ENVIRONMENTAL SCIENCES Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date HES Result EPA Result Code Type Coll.
Analysis 22 e c 3a, n=1d STW-167 Water Oct. 1978 Gross Alpha 19 2 19 15 Gross Beta 36 2 34215 Sr-89 91 10 15 Sr-90 420 522.4 Ra-226 5.52g.3 5.0 2.4 Ra-228 NA 5.422.4 Cs-134 1021 10215 Cs-137 1521 13215 STW-170 Water Dec. 1978 Ra-226 11.520.6 9.2 1.4 Ra-228 NAlefld 8.924.5 STW-172 Water Jan. 1979 Sr-89 1122 14215 Sr-90 522 614.5 STW-175 Water Feb. 1979 H-3 13442115 1280 993 STW-176 Water Feb. 1979 Cr-51
<22 0
Co-60 10 2 9215 Zn-65 2625 21 15 Rn-106
<16 0
Cs-134 822 6215 Cs-137 1522 12 15 STW-178 Water Mar.1979 Gross Alpha 6.3 3 10215 Gross Beta 1524 16215 STW-195g Water Aug. 1979 Gross Alpha 6.3 1.2 525 Gross Beta 42.727.0 4024 STW-193 Water Sep. 1979 Sr-89 5.021.2 3.021.5 Sr-90 25.022.7 28.024.5 STW-196 Water Oct. 1979 Cr-51 13525.0 113218 Co-60 7.021.0 625 Cs-134 7.320.6 7 15 Cs-137 12.721.2 11 15 STW-198 Water Oct. 1979 H-3 1710 140 156021111 A-7
HAZLETON ENVIRINMENTAL CCIZNCZ3 Table 5.3.
(continued)
~
Concentration in pCi/lb Lab Sample Date HES Result EPA Result Code Type Coll.
Analysis 2a c 23 0, n=1d STW-199 Water Oct. 1979 Gross Alpha 16.023.6 21 15
~
Gross Beta 36.321.2 49215 Sr-89 10.720.6 12215 Sr-90 5.7t0.6 7215 Ra-226 11.120.3 1125 Ra-228 1.620.7 0
Co-60 35.0 1.0 33215 Cs-134 50.7 2.3 56215 Cs-137
<3 0
STW-206 Water Jan. 1980 Gross Alpha 19.022.0 30.028.0 Gross Beta 48.022.0 45.025.0 STW-208 Water Jan. 1980 Sr-89 6.1 1.2
'10.020.5 Sr-90 23.921.1 25.521.5 STW-209 Water Feb. 1980 Cr-51 112214 10125.0 Co-60 12.722.3 1125.0 Zn-65 29.7 2.3 2525.0 Ru-106 71.721.5 51 5 Cs-134 12.0 2.0 1025.0 Cs-137 30.0 2.7 3025.0 STW-210 Water Feb. 1980 H-3 18002120 17502340 STW-211 Water March 1980 Ra-226 15.720.2 16.022.4 Ra-228 3.520.3 2.620.4 STW-215 Water April 1980 Gross Alpha NAf 98.0224.5 Gross Beta NAf 100.025.0 Sr-89 3.720.6 425.0 Sr-90
<1.0 0.001 0.1 Ra-226 NAf 16.022.4 Ra-228 NAf 21.323.2 Co-60 10.021.0 625 Cs-134 14.021.0 825 Cs-137 21.721.5 1825 STM-217 Milk May 1980 Sr-89 4.422.69 525 Sr-90 10.021.0 1221.5 STW-221 Water June 1980 Ra-226 2.010.0 1.720.8 Ra-228 1.620.1 1.720.8 A-8
i HazLaTON ENVmONMENTAL SCIENCES Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date HES Result EPA Resylt Code Type Coll.
Analysis 2e c 23o, n=10 STW-223 Water July 1980 Gross Alpha 31t3.0 3825.0 Gross Beta 4424 3525.0 STW-224 Water July 1980 Cs-137 33.9 0.4 3525.0 Ba-140
<12 0
<5.0 0
STW-225 Water Aug. 1980 H-3 1280150 1210 329 i
STW-226 Water Sept. 1980 Sr-89 22tl.2 2428.6 Sr-90 1220.6 1522.6 STW-228 Water Sept. 1980 Gross Alpha NAf 32.028.0 Gross Beta 22.520.0 21.025.0 STW-231 Water Oct. 1980 Sr-89 17.021.7 2328.6 Sr-90 1.6720.6 I-131 18t8.6 Cs-137 2621.0 2128.6 Ba-140
<39 0
K-40 1310 100 1700285 STW-235 Water Dec. 1980 H-3 2420230 22402604 STW-237 Water Jan. 1981 Sr-89 13.021.0 1628.7 Sr-90 24.020.6 3422.9 STM-239 Milk Jan. 1981 Sr-89
<210 0
Sr-90 15.722.6 2023.0 1-131 30.924.8 26210.0 Cs-137 46.922.9 4329.0 Ba-140 (21 0
K-40 1330253 15502134 STW-240 Water Jan. 1981 Gross alpha 7.322.0 915.0 Gross beta 41.0 3.1 4425.0 STW-243 Water Mar. 1981 Ra-226 3.520.06 3.420.5 Ra-228 6.5 2.3 7.321.1 A-9
r HA2LETON ENVIRONMENTAL SCIENCES Table A-1.
(continued)
Concentration in DCi/lb Lab Sample Date HES Result EPA Result Code Type Coll.
Analysis 20 C 30, n=1d STW-245 Water Apr. 1981 H-3 32102115 27102355 STW-249'idater May 1981 Sr-89 5123.6 3628.7 Sr-90 22.720.6 2222.6 STW-251 Water May 1981 Gross alpha 24.025.29 2125.25 Gross beta 16.121.9 1425.0 STW-252 Water Jun. 1981 H-3 2140 95 19502596 STW-255 Water Jul. 1981 Gross alpha 2021.5 2229.5 Gross beta 13.022.0 1528.7 STW-259 Water Sep. 1981 Sr-89 16.121.0 2325 Sr-90 10.320.9 1121.5 STW-265 Water Oct. 1981 Gross alpha 71.2219.1 80220 Gross beta 123.3 16.6 11125.6 Sr-89 14.922.0 2125 Sr-90 13.121.7 14.421.5 Ra-226 13.022.0 12.7 1.9 STW-267 Water Nov. 1981 Gross alpha 15.724.3 Gross beta 7.320.9 STW-269 Water Dec. 1981 H-3 2516:181 2700:355 aResults obtained by the Nuclear Sciences Department of Hazleton Environ-mental Sciences as a participant in the environmental sample crosscheck program operated by the Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S.
Environmental 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.
dVSEPA results are presented as the known values i control limits of 3 for n=1.
'Mean 2 2 standard deviations of two determinations.
fNA = Not analyzed.
9 Analyzed but not reported to the EPA.
A-10 i
~
Table A-2.
Crosscheck program results, thermoluminescent dosimeters (TLD's).
mR Lab TLD Hazleton Average 2od Code Type Measurenent Result Known (all 12 03 Value participants) 2nd International Intercomparisonb 115-2b CaF :Mn Gamma-Field 17.0tl.9 17.lc 16.427.7 Bu b p
Gamma-Lab 20.824.1 21.3c 18.817.6 m
-4 3rd International Intercomparisone 115-3e CaF :Mn Gamma-Field 30.723.2 34.914.8f 31.523.0 E
Bu b Gamma-Lab 89.626.4 91.7214.6f 86.2224.0 I
?
~
=
4th International Intercomparison9 g
115-49 CaF :Mn Gamma-Field 14.121.1 14.ltl.4f 16.09.0 Bu b r
-Lab (Low) 9.321.3 12.222.4f 12.027.6 r-a Gamma-Lab (High) 40.421.4 45.819.2f 43.9213.2 og 5th International Intercomparisonh
!.8 CaF :Mn Gamma-Field 31.421.8 30.026.01 30.2214.6 115-5Ah 2
Bulb Gamma-Lab 77.415.8 75.227.61 75.8240.4 at beginning Gasuma-Lab 96.625.8 88.428.81 90.7231.2 at the end
Table A-f.
(Continued) mR Lab TLD Hazleton Average i 20 d Code Type Measurement Result Known (all 22ba Value participants)
Il5-5Bh Lif-100 Gamma-Field 30.314.8 30.0261 30.2214.6 Chips y
Gamma-Lab 81.127.4 75.217.61 75.8i40.4 at beginning p
Camma-Lab 85.4211.7 88.428.81 90.72131.2 l
at the end Z
alab result given is the mean i 2 standard deviations of three deteminations.
b econd Ir.ternational Intercomparison of Environmental Dosimeters conducted in April of 1976 by the Health 3
S and Safety Laboratory (GASL), New York, New York, and the School of Public Health of the University of l
g CValue determined by sponsor of the intercomparison using continuously operated pressurized ion chamber.
a dMean i 2 standard deviations of results obtained by all laboratories participating in the program.
2 eThird International Intercomparison of Environmental Dosimeters conducted in summer of 1977 by Oak Ridge j
National Laboratory and the School of Public Health of the University of Texas, Houston, Texas.
r-fValue i 2 standard deviations as determined by sponsor of the intercomparison using continuously operated a
pressurized ion chamber.
9a 9 Fourth International Intercomparison of Environmental Dosimeters conducted in summer of 1979 by the School of Public Health of the University of Texas Houston, Texas.
n hfifth International Intercomparison of Environmental Dosimeter conducted in fall of 1980 at Idaho Falls, a8 Idaho and sponsored by the School of Public Health of the University of Texas. Houston, Texas and Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy.
IValue determined by sponsor of the intercomparison using continuously operated pressurized ion chamber.
G
=
6
--p.m=
,pe
HA21.ETCN CNVIRONMENTAL. Sciai!NCO I
i Appendix B Data Reporting Conventions 4
e B-1
MA21.ETON CNVIRINMINTAL. CCCNC23 Data Reporting Conventions 1.
All activities are corrected to collection time.
2.
Single Measuements Each single measurement is reported as follows:
xis where x = value of the measurement; l
s=2a counting uncertainty (corresponding to the' 95%
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 4.66a background counting uncertainties.
~
3.
Duplicate measurements, the average result is reported as follows:
a.
Individual results:
x 2 sg x 2s 2
Reported result:
x2s where x = (1/2) (x1 + x2) s=(1/2)1/s2+s2 V1 2
b.
Individual Results:
(L1 (L2 Reported result:
<L where L = lower of L1 and L2 I
i B-2 l
e
MA71 SiTON CNVI ACNMkiNTAL CCIONCCD c.
Individual results: xis
<L Reported result:
x i s if x.1 L;
<L othemise 4.
Unless otherwide indicated, 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 othemise indicated, the " previous average" for a location is the average obtained during the previous year.
6.
In rounding off, the following rules are followed:
a.
If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an example, 11.443 is rounded off to 11.44.
b.
If the figure following those to be retained is greater than 5, the figure is dropped, and the last retained figure is raised by 1.
As an example,11.446 is rounded off to 11.45.
If the figure following those to be retained is 5, and if there c.
are no figures other than zeros beyond the five, the figure 5 is dropped, and the last-place figure retained is increased by one of it is an odd number or it is kept unchanged if an even number.
As an example,11.435 is rounded off to 11.44, while 11.425 is rounded off to 11.42.
l I
B-3 i
1 9
MA2LETON ENVIRONMENTAL CCl!NCE3
+
4 APPENDIX C MAXIMUM PERMISSIBLE CONCENTRATIONS OF RADI0 ACTIVITY IN AIR AND WATER AB0VE NATURAL BACKGROUND IN UNRESTRICTED AREAS t
h i
+
4 3
C-I l
e HA2LETON ENVIRINMENTAL CCl!NC2O Table C-1.
Maximum pennissible concentrations of radioactivity in air and water above natural background in unrestricted areas.a Air Water 3
Gross alpha 3
pC1/m Strontium-89 3,000 pC1/1 3
Grcss beta ~
100 pCi/m Strontium-90 300 pCi/1 b
3 Iodine-131 0.14 pCi/m Cesium-137 20,000 pCi/1 Barium-140 20,000~pC1/1 Iodine-131 300 pCf/1 Potassium-40c 3,000 pCi/l Gross alpha 30 pC1/1 Gross beta 100 pCi/l l
6 Tritium 3 x 10 pC1/1 aTaken from Code of Federal Regulations 'itle 10, Part 20 Table II and appropriate footnotes. Concentrations may be averaged over a period not bgreater than one year.
From 10 CFR 20 but adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.
cA natural radionuclide.
C-2
i l
Northem States Power Company 414 Ncollet Ma0 Minneapohs. Minnesota 55401 Teephone(612)330 5500 March 29, 1982 RegionalAdm'inistrr$or Region III U S Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License DPR-42 50-306 DPR-60 Annual Radiological Environmental Monitoring report 1981 In accordance with the Prairie Island Technical Specifications, Appendix A to the Operating License DPR-42 and DPR-60, we are submitting the Annual Radiological Environmental Monitoring Report Covering the period January 1, 1981 through December 31, 1981.
Yours very truly, L 0 Mayer, PE Manager of Nuclear Support Services LOM/bd cc: Document Control Desk, NRC (18)
Resident Inspector G Charnoff MPCA
' -- " ^ '"
Attn: J W Ferman Cartifiua Ey_ d h
_d Attachment M
- o w
., -, -