ML20087P245
| ML20087P245 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/31/1983 |
| From: | Huebner L TELEDYNE ISOTOPES |
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PRAIRIEISLAND NUCLEAR GENERATING PLANT Red Wing, Minnesota UNITS 1 AND 2 1
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ANN'JAL REPORT to the-UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environ. mental Monitoring Program January 1, 1981 to December 31,-1983 l
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NORTelERN STATES POWER COMPANY MINNEAPOUS. MINNESOTA -
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NORTH BROOK, IL 60062 (312) $644700 NCRTHERN 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 1,1983 to December 31, 1983 Prepared Under Contract by TELEDYNE ISOTOPES MIDWEST LABORATORY Project No. 8010
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Approved by: .
L."G. # ebner General Manager
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6 February 1984
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PREFACE
. The staff of Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environ-
- mental Sciences), was responsible for the acquisition of data presented in this report. Samples were collected by members of the staff of the Prairie Island Nuclear Generating Plant.
- .1 The report was prepared by L. G. Huebner, General Manager. He was assisMd in the report preparation by L. Nicia, Group Leader, and D. Cohen, Scientist.
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TABLE OF CONTENTS Page PREFACE 11 List of Tables iv
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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 7 3.6 Land Use Census 7 4.0 RESULTS AND DISCUSSION 9 4.1 Atmospheric Nuclear Detonatior.s 9 4.2 Program Findings 9
- 5.0 TABLES 13
6.0 REFERENCES
CITED 25 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
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List of Tables
. No. Title Page 5.1 Sample collection and analysis program,1983 14
_; 5.2 Sampling locations 16 5.3 Missed collections and analyses,1983 17 5.4 Environmental Radiological Monitoring Program Summary 18 In addition, the following tabics are in the Appendix:
Appendix A A-l' Crosscheck program results, milk and water samples, 1980-1983 A-3 A-2 Crosscheck program results, thermoluminescent dosimeters
. (TLDs) A-9 Appendix C C Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas C -2 W
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1.0 INTRODUCTION
This report sussiarizes and interprets results of the Radiation Environmental
- Monitoring Program (REMP) _ conducted by Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environmental Sciences) at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December, 1983. This program monitors the levels of radioactivity in the air, terres-
. trial, and aquatic environments in order to assess the impact of the plant on its surroundings.
Tabulations of the individual analyses made during the year are not included 3 in this report. These data are included in a reference document (Teledyne
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Isotopes Midwest Laboratory,1984) available at Northern States Power Company, Nuclear Generation 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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2.0
SUMMARY
The Radiation Environmental Monitoring Program (REMP) required by the U.S.
Nuclear Regulatory Comission (NRC) Technical Specifications for the Prairie Island Nuclear Generating Plant is described. Results for 1983 are summarized and discussed.
Program findings show background levels of radioactivity in the environmental samples collected in the vicintty of the Prairie Island Nuclear Generating Plant. No effect on the environment due to the operation of the Plant is indicated.
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3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Design 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 (TLDs).
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 1ccations (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.
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I 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 and iodine-131. Most samples are also analyzed for gamma-emitting ,
isotopes with results for the following_ groups quantified: zirconium-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 l in the fission product mix produced by a nuclear reacter and that pro-e duced 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 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).
Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occur-ring 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,
, iron-59, cobalt-58, and -60, and zinc-65, are activation products and arise from activation of corrosion products. They are typical components of a 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.
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, 1983).
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. l To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations. Also, airborne iodine is collected by continuous pumping through charcoal filters at all of these locations. Filters are changed and counted weekly. Parti-culate filters are analyzed for gross beta activity and charcoal filters for iodine-131. A monthly composite of ali particulate filters is gamma-scanned on a Ge or Ge(Li) detector.
, One of the five locations is a control (P-1), and four are indicator (P-2, P-3, P-4, and P-6). 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).
As a " Lessons Learned" commitment, ambient gamma radiation is monitored at thirty-two (32) locations, using three (3) LiF2 chips at ea h loca-tion: ten (10) in an inner ring in the general area of the site boun-dary, fifteen (15) in the outer ring within 4-5 mile radius, six (6) at special interest locations and one control location,11.1 miles distant from the Plant. They are replaced and measured quarterly. Also, a complete emergency set of TLDs for all locations is placed in the field at the same time as regular sets. The emergency set is returned to TIML quarterly for annealing and repackaging.
Milk samples are collected monthly from five farms (four indicator and one control). All samples are analyzed fnr iodine-131 and gamma-emitting isotopes.
In addition, goat's milk is collected in the vicinity of the Plant, when available, and analyzed for iodine-131.
For additional monitoring of the terrestrial environment, leafy green vegetables (cabbage) are 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 loca-l tion (P-25) and analyzed for gamma-emitting isotopes. Also, well water 1s collected quarterly and analyzed for tritium and gamma-emitting isotopes.
I River water is collected weekly at two locations, one upstream of the Plant (P-5) and one downstream (P-6, Lock and Dam No. 3). Monthly l composites are analyzed for gamma-emitting isotopes. Quarterly compo-l sites are analyzed for tritium.
' Drinking water is collected weekly from the City of Red Wing well.
Monthly composites are analyzed for gross beta, fodine-131, and gamma-emitting isotopes. Quarterly composites are analyzed for tritium.
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r The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, periphyton or invertebrates, and bottom sediments. Shoreline sediment it collected semi-annually from one location.
3.3 Program Execution The Program was executed as described in the preceding section with the following exceptions: The- TLD data for the third quarter of 1983 for location P-13B and for the fourth quarter of 1983 for location P-03S were not available because they were lost in the field.
3.4 Laboratory Procedures All iodine-131 analyses in milk were made by using a sensitive radio-chemical procedure which 1.ivolves separation of the element by use of an ion-exchange resin and subsequent beta counting.
All gamma-spectroscopic analyses were performed with a Ge or Ge(L1) detector. Levels of iodine-131 in cabbage were determined by Ge or Ge(L1) spectrometry. Levels of airborne iodine-131 in charcoal samples were measured by Ge or Ge(Li) spectrometry.
Tritium levels were determined by liquid scintillation technique.
Analytical procedures used by the Teledyne Isotopes Midwest Laboratory are specified in detail elsewhere (Hazleton Environmental Sciences,1981, presently under revision). 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) .
Teledyne Isotopes Midwest Laboratory has a comprehensive quality control /
quality assurance program designed to assure the reliability of data obtained. Details of TIML's QA Program are presented elsewhere (Hazleton Environmental Sciences, 1982, presently under revision). The TIML QA Program includes participation in laboratory intercomparison (cross-check) programs. Results obtained in crosscheck programs are presented in Appendix A.
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. l o l 3.5 Program Modifications e Effective January 1,1983, the following modifications were made in the REMP.
- a. Number of air sampling locations were increased from four to five;
- b. Number of charcoal sampling locations were increased from three to five;
- c. . Gamma-isotopic analysis of air particulates was changed from monthly composites from all locations to quarterly composites from each location;
- d. Number of TLD locations was reduced from 36 to 32;
- e. Collection and analysis of natural vegetation, soil, and aquatic vegetation was dropped from the program;
- f. Analysis for strontium-89 and strontium-90 was dropped from the program (all samples);
- g. Lower limit of detection (LLD) for iodine-131 in milk was changed from 0.25 to 1.0 pC1/1;
- h. Analysis for iodine-131 in drinking water was added to the program.
3.6 Land Use Census In accordance with Technical Specification 4.10, paragraph B1, a land use census shall be conducted and shall identify the location of the nearest milk animal the nearest residence, and the nearest garden of greater than 500 ftI producing fresh leafy vegetables in each of the 16 meteo-rological sectors within a distance of 5 miles. Tnis census shall be conducted at least once per 12 months between the dates of May 1 and October 31. New locations shall be added to the radiological environ-mental monitoring program within 30 days, and sampling locations having lower calculated doses or a lower dose commitment may be deleted from this monitoring program after October 31 of the year in which the land use census was conducted.
This land use census insures the updating of the radiation environmental monitoring program should sampling locations change within the 5 mile radius from the plant.
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t f e The 1983 land use census was conducted July 27, 1983 and resulted in changing a dairy farm location from 3.5 miles at 181*/S to another dairy farm located 3.7 miles at 88*/E from the plant. This change occurred October 17, 1983, and is reflected in changes to the map and table identifying the locations of sampling presented in the Offsite Dose Calculation Manual (ODCM). These changes are found in the~ Semi Annual Radioactive Effluent Release Report submitted to the NRC within 60 days after the end of each 6 month period.
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4.0 RESULTS AND DISCUSSION All collections and analyses were made as scheduled except as listed in 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 Atmospheric Nuclear Detonations There were no reported atmospheric nuclear tests in 1983. The last repor-ted test was conducted by the People's Republic. of China on 16 October 1980. The reported yield . was in the 200 kiloton to 1 megaton range.-
4.2 ~ Program Findings Program findings show background levels of radioactivity in the environ-mental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant. No plant effect on the environment was indicated.
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[ Ambient Radiation (TLDs)
Ambient radiation was measured in the general area of site boundary, at outer ring 4 . 5.mi distant from the plant, .at special interest areas, and at one control location, The means ranged from 12.4 mR/91 days at inner ring locations to 13.4 mR/91 days at outer ring locations.
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mean ' at ~ special locations was 12.7 mR/91 days and 14.9 mR/91 days at
. control location. The differences are not statistically significant.
The: dose. rates measured were similar to those observed in 1978 (12.1 and .
p 15.1 mR/91 days, respectively; in 1979 (12.6: and 15.3 mR/91' days, res- '
l pectively), in 1980 (11.2 and 13.5 mR/91 days, respectively), in 1981 l - (13.0 and 14.5 mR/91 days, respectively), and in 1982. (12.0 and 13.0 l ' mR/91 days, respectively). No Plant effect on ambient gamma radiation
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1 Air Particulates The average annual gross beta activity in airborne particulatts was identical at both indicator and control (0.024 pCi/ma ) and was about the same as in 1982 (0.025 pC1/m}ocations
). The highest averages for gross beta were for the month of December and the fourth quarter.
The reason for the elevated activity in December and the fourth quarter is not clear. It ,nrobably is attributable to the increased use of wood burning stoves. The spring peak, which usually is observed in April - May (2nd quarter) was not observed in 1983. This peak has been observed
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almost annually (1976, 1979, and 1980 were also 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).
Two pieces of evidence indicate conclusively that the elevated activity observed during the fourth 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,1984).
Except for bery111um-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 Airborne iodine-131 results were below the detection limit of 0.07 pct /m3 in all samples. Thus, there was no indication of a l'lant effect.
Milk Iodine-131 results were below the detection limit of 1.0 pC1/1 in all samples.
Cesium-137 results were below the LLD level of 15 pC1/1 in all samples.
Cesium-137 is a long-lived component (with a half-life of 30.24 years) of worldwide fallout and is found in the environment in trace quantities.
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i No other gama-emitting isotopes, except potassium-40, were 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 metabolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium and iodine (National Center for Radiological Health, 1968).
In sumary, the milk data for 1983 show no radiological effects of the Plant operation.
Drinking Water In drinking water from the City of Red Wing well, tritium activity was below the LLD level of 330 pCi/1 in all samples. Iodine-131 activity was also below the LLD level at 1.0 pCi/1 in all samples. As with the other well water samples, all analyses for gamma-emitting isotopes yielded results below detection limits. Gross beta averaged 8.0 pCi/1 and was similar to the levels observed in 1979 (10.5 pCi/1),1980 (11.8 pCi/1),
1981 (10.7 pC1/1), and 1982 (8.9 pC1/1).
River Water o At the upstream and downstream collection si tes, quarterly composite tritium levels were below the LLD level of 330 pCi/1 in all samples.
River water was also analyzed for gamma-emitting isotopes. All gamma-emitting isotopes were below their respective detection limits. There was no indication of a Plant effect.
Well Water At the control well P-25, Kinneman Farm and two indicator wells (P-8,
! Kinney Store, and P-10, Lock and Dam #3) no tritium was detected above LLD level of 330 pCi/1 in any of the analyses. At the remaining indicator well (P-9, Plant Well #2), tritium was detected in one quarterly sample and was 590 pC1/1. The activity was similar to that observed in 1982
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Gamma-emitting isotope . levels were below detection limits in all cases.
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J Crops Cabbage samples were collected on August 23 and August 29, 1983, and analyzed for iodine-131. Corn samples were also collected on August 23, l 1983, and analyzed for gamma-emitting isotopes. All results, except for potassium -40, were below detection limits. There was no indication of a Plant effect.
Fish Fish samples were collected in May and September,1983. The only isotope detected was naturally-occuring potassium-40 and there was no significant difference between upstream and' downstream results. There was no indica-tion of a Plant effect.
Aquatic Insects and Periphyton Aquatic insects (invertebrates) and periphyton were collected on June 6 and September 28, 1983. The samples were analyzed for gamma-emitting isotopes. All gamma-emitting isotopes, except for naturally-occuring potassium-40, were below their respective LLD's. No Plant effect
, was. indicated.
, Bottom and Shoreline Sediments Sediment collections were made on -May 23 and November 7,1983. The samples'were analyzed for, gamma-emitting isotopes. Cesium-137 was detected in two bottom sediment samples and was 0.067 pCi/g dry weight in indicator sample and 0.117, pCi/g dry weight in upstream (control) sample.
The only other gamma-emitting isotope detected was naturally-occuring potassium-40. No Plant effect was indicated.
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5.0 TABLES 4
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Table 5.1 ' Sample collection and analysis program,1983. Prairie Island Collection _ Analysis Locations Type and Type and Medium' No. Codes (and Typela Frequencyb FrequencyC Ambient radiation 32 P-01 A - P-10A C/Q Ambient gamma.
(TLDs) P-01B - P-15B P-01S - P-06S P-01C Airborne particulates 5 P-1(C), P-2, C/W GB, GS (QC of P-3, P -4, P-6 each location)
Airborne iodine 5 P-1(C), P-2, P-3 C/W I-131 P -4, P-6 :
Milk 5 P-16 to P-18, G/M I-131, GS P-25(C), P-14 i 7: River water 2 P-5(C), P-6 G/W GS(MC) H-3(QC)
Drinking water 1 P-11 G/W GB(MC), 1-131(MC)
GS(MC), H-3(QC) 1 Well water 4 P-25(C), P-6, G/Q H-3, GS P-8, P-9 Edible cultivated 2 P-25(C), P-24 G/A I-131 I crops - leafy green vegetables
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Table 5.1-(continued) Prairie Island Collection Analysis Locations Type and Type and Medium No. Codes (and TypFFF Frequency b Frequencyc Edible cultivated 2 P -25 (C ) , - P-14 G/A GS crops - corn Fish (one species 2 P-5(C), P-6 G/SA GS edible portion)
Periphyton or 2 P-5(C), P-6 G/SA GS invertebrates Bottom sediment 2 P-5(C),P-6 G/SA GS Shoreline sediment 1 P -12 G/SA GS
- U" aLocation codes are defined in Table 5.2. Control stations are indicated by (C). All other stations are indicators.
bC ollection type is coded as follows: C/ = continuous, G/ = grab. Collection frequency is coded as follows: W = weekly, M = monthly, Q = quarterly, SA = semi-annually, A = annually.
cAnalysis type is coded as follows: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium, I-131 =
iodine 131. Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly composite.
4 Table 5.2 Sampling locations. Prairie Island Code Typea Name Location P-1 C Air Station P-1 16.5 mi 0 348'/NNW P -2 Air Station F-2 0.5 mi 0 294*/WNW P-3 Air Station P-3 0.8 mi 0 313*/NW P -4 Air Station P-4 0.4 mi 0 359'/N P-5 C Upstream of Plant 0.6 mi 0 60*/ENE P-6 Lock & Dam #3 & Air Station P-6 1.6 mi 0 129'/SE P-8 Kinney Store 2.0 mi 0 280*/W P-9 Plant Well #2 0.3 mi 0 306'/NW P-11 City of Red Wing 7.1 mi 0 135'/SE P-12 Recreational Area 3.4 mi 0 116*/ESE P-14 Gustafson Farm 2.2 mi 0 168'/SSE P-16 Johnson Farm 2.5 mi 0 39'/NE P-17 Place Farm 3.5 mi 0 25'/NNE P-18 Birk Farm 3.5 mi 0 181*/S P-24 H. Larson Residence 1.6 mi 0 287'/WNW P-25 C Kinneman Farm 11.1 mi 0 331*/NNW P -01A Property Line 0.4 mi 0 359'/N P-02A Property Line 0.3 mi 0 19'/NNE P-03A Property Line 0.5 mi 0 183*/S P -04A Property Line 0.4 mi 0 204*/SSW
. P -05A Property Line 0.4 mi 0 225'/SW P-06A Property Line 0.4 mi 0 249'/WSW P -07A Property Line 0.4 mi 0 268'/W P -08A Property Line 0.4 mi 0 291'/NNW P-09A Property Line 0.7 mi 0 317*/NW P-10A Property Line 0.5 mi 0 333*/NNW P-01B Thomas Killian Residence 4.7 mt 0 355'/N P -02B Roy Kinneman Farm 4.8 mi 0 17*/NNE P-03B Wayne Anderson Farm 4.9 mi 0 46*/NE P-04B Nelson Drive (Road) 4.2 mi 0 61*/ENE P-05B County Road E a'nd Coulee 4.1 mi 0 97'/E P -06B William Houschildt Residence 4.4 mi 0 112*/ESE P -07B Red Wing Service Center 4.7 mi 0 140*/SE P dBB David Wnuk Residence 4.1 mi 0 165*/SSE P -098 Highway 19 South 4.2 mi 0 187*/S P-10B Cannondale Farm 4.9 mi 0 200*/SSW P-11B Wallace Weberg Farm 4.5 mi 0 221*/SW P-128 Roy Gergen Farm 4.5 mi 0 247*/WSW P-13B Thomas O'Rourke Farm 4.4 mi 0 270*/W P-14B David J. Anderson Farm 4.9 mi 0 306*/NW P-15B Holst Farms 4.2 mi 0 347'/NNW P -01S Federal Lock & Dam #3 1.6 mi 0 129'/SE P -02S Charles Suter Residence 0.5 mi 0 155'/SSE P-03S Carl Gustafson Farm 2.2 mi 0168'/SSE P-04S Richard Burt Residence 2.0 mi 0 228'/SW P-05S Kenney Store 2.0 mi 0 270*/W P -06S Earl Flynn Farm 2.5 mi 0 299'/WNW P -01C Robert Kinnemen Farm 11.1 mi 0 331*/NNW a
"C" denotes control location. All other locations are' indicators.
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Table 5.3 Missed collections and analyses,1983. Prairie Island NGP.
All required samples were collected and analyzed as scheduled except the following:
Coll. Date
- Sample Analysis Location or Period Comments Thermoluminescent Dosimeters (TLDs) Ambient Radiation P-138 3rd Qtr. 1983 Lost in the field Thermoluminescent Dosimeters (TLDs) Ambient Radiation P-03S 4th Qtr. 1983 Lost in the field e
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Table 5.4 : Environmental Radiological Monitoring Program Susanary.
Name of facility Prairie Island Nuclear Generating Plant Docitet No. 50-282, 50-306 _
Location of facility Goodhue, Minnesota Reporting period January-December 1983 (County, state)
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 Resalts' TLD Gasuna 40 3.0 12.4 (40/40) P-094, Property Line 13.2 (4/4) (See control 0 (mR/91 days) (9.1-15.0) 0.'7 of 9 317*/NW (10.9-15.0) below) *
(Inner Ring, General Area at Site Boundary)
TLD Gasuna 59 3.0 13.4 (59/59) P-15. Holst Farm 15.0 (4/4) (See control 0 (mR/91 days) (9.8-17.8) 4.2 mi 9 347*/NNW (13.3-17.8) below)
(Outer ring, 4-5 miles distant)
TLD Gasuna 23 3.0 12.7 (23/23) P-045, Near Richard 14.6 (3/3) (See control 0 (mR/91 days) ( 8.9-18.1) Burt Residence (12.3-18.1) below)
(Special 2.0 mi 9 228*/SW Interest Arcss) y TLD Gasuna 4 3.0 None P-01C-R, Kinneman 14.9 (4/4) 14.9 (4/4) 0 (nR/31 days) Farm (12.0-17.0) (12.0-17.0)
(control) 11.1 mi 9 331*/NNW Airborne GB 260 0.002 0.024 (208/208) P-4, Statian P-4 0.025 (52/52) 0.024 (52/52) O Particylates 0.4 mi 9 359*/N (0.009-0.078) (0.002-0.070)
(pCi/mJ) P-6, Station P-6 0.025 (52/52) 1.6 mi 9 129*/SE (0.007-0.070)
G5 20
, Be-7 0.010 0.120 (16/16) P-4, Station P-4 0.129 (4/4) 'O.113 (4/4) 0 (0.064-0.174) 0.4 uf 9 359*/N (0.077-0.174) (0.089-0.137) l Mn-54 0.0020 (LLD - - <LLD 0 Co-58 0.0034 <tLD - - (LLD 0 Co-60 0.0023 (LLD - - <LLD 0 l
Zn-65 0.0057 <tLD - - <LLD 0 Nb-95 0.0043 <LLD - - <LLD 0 A
.' .- [ . . .: ,
Table 5.4 (Continued)
Name of.lacility 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(FI Mean(F) Non-routine (Units) Analysesa Ltob Rangec -Locationd Range Range Results' Airborne Ir-95 0.0065 (LLD - -
<LLD 0
.Particulates (pC1/mJ) Ru-133 0.0064 <LLO - - <LLD 0 (copt'd)
Ru-106 0.019 <tLD - - (LLD 0 Cs-134 0.0017 (LLD - -
(LLD. O Cs-137 0.0019 <LLD - ,- <LLD 0 Ba-140 0.0050 (LLD - - <LLD 0 La-140 0.0074. <tLD - - <LLD 0 Ce-141 0.0012' O.013 (1/4) P-4. Station P-4 0.013 (1/4) <LLD 0 0.4 mi 9 359*/N -
re-144 0.0098 0.016 (1/4) P-3, Station P-3 0.016 (1/4) (LLD 0 0.8 mi 9 313*/ Nil -
so Airporne 1-131 260 0.07 <LLD - -
<tLD 0
-lodine (pC1/m3 )
Hilk 1-131 64 1.0 . (LLD - - <LLD 0 (pC1/1)
Gs 60 K -40 100 1330 (48/48) P-16. Johnson Fars 1350 (12/12) 1290 (12/12) 0
- (1110-1660) 2.5 mi 9 39*/NE (1140-1560) (1150-1510)
Cs-134 15 <t LD - - <LLD 0 Cs-137 15 <LLD - -
(LLD 0 Ba-La-140 15 <tLD - - (LLD 0 1
=e: m .g e- ~ e ,
. Table 5.4 - (Cutinued)
Name of facility Prairie Island Nuclear Generating Plant Indicator Location with Highest Ctetrol Sample Type and Locationg Annual Mean Locations Number of
. Type humber of Mean[F) MeanlF) Mean(F) Non-routine (Units) Analysesa LLDb RangeC Locationd Range Range Results*_
Drinking Water GB 12 1.0 8.0 (12/12) P-11 City of Red Wing 8.0 (12/12) None 0 (pC1/1) .(6.1-10.0) 7.1 al 9 135*/SE (6.1-10.0) 1-131 12 1.0 <tLD- - - None 0 H-3 4 330 (LLD - - None 0 4
GS 12 .
Mn-54 15 <LLD - - None 0 Fe-59 34 <LLD - - None O Co-58 15 <LLD - - None O Co-60 15 <LLD - -
Dine 0 Zn-65 30 (LL D - -
None 0 g Nb-95 21 <tLD - - None 0 o
Zr-95 33 <tLD - - None O Cs-134 10 <LLD - - None- 0 Cs-137 10, <LLD - -
None 0
' Ba-La-140 16 <tLD - -
None O Ce-144 109 <LLD - - None O Riwer Water H-3 8 330 <LLD - - <LLD 0
- p:1/1)
GS 24 Mn-54 15 (LLD - - <LLD 0 Fe-59 49 <LLD - - (LLD 0 Co-58 15 (LLD - - (LLD 0 Co-60 15 <LLD - - <LLD 0 2n-65 30 <LLD - - (LLD 0 Nb-95 28 (LLD - - <LLD 0 i
N '
.- r s . . . ,
~
Table 5.4 (Continued) .
l_ 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) MeaniF1 Mean(F) Non-routine (Units) Analysesa Ltob RangeC Locationd Range Range Results' River Water . 2r-95 30 (LLD .- -
<tLD 0 (PC 1/1)
(Cont'd) Cs-134 15 <LLD - - - <LLD 0 Cs-137 18 <LLD - - <LLD 0 Ba-La-140 15 <LLD - - <LLD 0 Ce-144 99 <LLD - - <LLD 0 Well Water- H-3 16 330 590 (1/12) P-9 Plant Well #2 590 (1/4) (LLD 0 (pci/1) - 0.3 at 9 306* NW (350-520) -
GS 16 Mn-54 15 <LLD - - <LLD 0 Fe 30 <LLD - - <LLD 0 g Co-58 15 <LLD - -
<LLD 0 m
Co-60 15 i <LLD - - (LLD 0 2n-65 30 <1LD - -
<LLD 0 Nb-95 15 <LLD - - <LLD 0 2r-95 25 i <LLD - - <LLD 0 Cs-134 10 <tLD - - <LLD 0 Cs-137 10 (LLD - - sLLD 0 Ba-La-140 15 <LLD - - (LLD 0 Ce-144 108 <tLD - - <LLD 0 Crops-Cabbage I-131 3 0.025 (LLD - -
(LLD 0 (pC1/g wet)
Crops-Corn GS 2 (pC1/1)
Be-7 0.31 (LLD - <LLD 0 K-40 0.5 2.14 (1/1) P-14, Gustafson Fars 2 + _ 2.08 (1/1) 0 2.2 at 9 168'/SSE -
a_
et . e o .
Table 5.4 (Continued) . .
Name of facility Prairie Island Nuclear Generating Plant i . Indicator Location with Highest Control Sample ! Type and Locationg Annual Mean Locations f Number of Type !' . Number of Mean(F) MeantF) Mean(F) Non-routine (Units) i Analysesa LLDb RangeC Locationd Range Range Results' _
Crops-Corn Mn-54 0.039 <LLD j - - <LLD i 0 (pCf/1) . .. l !
(Cor.t'd) Co-58 0.030, <LLD , <LLD i 0 i
- - <LLD 0 I Zn-65 0.097 <tLD - - (LLD 0
. Nb-95 0.050 (LLD - - <LLD 0 Zr-95 0.073 <LLD - - <LLD 0 i Ru-103 0.040 <LLD j - - <LLD 0 Ru-106 0.23 (LLD - - <LLD 0 1
Cs-134 0.029 <LLD - - <LLD 0 Cs-137 0.030 (LLD - - <LLD 0 Ba-140 0.0 93 (LLD - - <LLD 0 N
N La-140 0.026 <LLD - - <LLD 0 Ce-141 0.048 (LLD - - <LLD 0 Ce-144 0.16 (LLD - - <LLD 0 Fi sh-Flesh G5 4 (pC1/g wet)
K-40 0.1 2.88 (2/2) P-6 Lock & Dam #3 3 23 (4/4) 2.64 (2/2) 0 (2.15-3.60) 1.6 mi 9 129' SE (1.94-3.35) (2.44-2.85)
Mn-54 0.032 <LLD - - <LLD 0 Fe-59 0.12 (LLD - - <LLD 0 Co-58 0.046 <LLD - - <LLD 0 Co-60 0.042 (LLD - - <LLD 0 Zn-65 0.082 <LLD - - <LLD 0 0.097 <LLD 0 Nb-95 <LLD - -
l t
Zr-95 0.097 <LtD - - <LLD 0
{
Cs-134 0.034 <LLD - - <LLD 0
- <LLo o C5-137 0.036 <LLD -
- <LLD 0 0.088 <LLD l
Ba-La-140 t
e ..,
ni. . < >-
. 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 Resultse Invertebrates GS 4 ;
(ptt/c wet) j Be-7 6.5 (LLD - . - (LLD 0 t
K-40 3.4 - 7.24 (1/2) P-5, Upstream of i 10.40 (1/2) 10.40 (1/2) 0
- Plant !
0.6 mi,9 60*/ENE ,
Mn-54 0.50 (LLD - -
(LLD 0 Co-58 0.76. (LLD - - <LLD 0 Co-60 0.49 <tLD - - (LLD 0 Zn-65 1.29 <tLD - -
(LLD 0 Nb-95 1.23 <LLD - -
<LLD D N Zr-M 1.33 . <tLD - -
<LLD 0 Ru-103 0.97 <LLD - -
<LLD 0 Ru-106 3.91 <LLD- - -
<tLD 0
- Cs-134 0.39 (LLD - - (LLD 0 Cs-137 0.44 <LLD - -
<LLD 0 i
Ba-140 1.36 <LLD - -
<LLD 0 Ce-141 1,58' <LLD - -
<tLD 0 Ce-144 2.39 <LLD - -
<LLD 0 l
1
-Table 5.4 (Continued). . . .
Name of facility . Prairie Island Nuclear Generating Plant Indicator Location with Highest Control -l Sample Type and 'l Locationg Annual Mean Locations . Number of I
-Type ; Number of $ Mean(F) Mean[F)
- Mean(F) !'Non-routine f (Units) ~'
.Analysesa j ttob RangeC Locationd Range i Range i Results*
a ,
t Bottom and ~ GS ' 6 ;
}- l Shoreline
- i t
- Sediments l Be-7 0.89 3 <tLD - I - (LLD 0 I !
I (pC1/g dry) t . K-40 1.0 10.48 (2/4) .P-5, Upstream of 11.04 (4/4) 11.04 (4/4) 0
-I (9.86-11.10) Plant (9.01-14.00) (9.01-14.00)
- l. 0.6 mi 9 60*/ENE ,
l i Mn-54 0.062 <LLD ' - - <LLD 0 Co-58 0.074 <LLD - - <LLD 0 Co-60 0.058 <LLD - - <LLD 0 '
Zn-65 0.19 <LLD - - <LLD 0 ]:
Nb-65 0.13 (LLD - - <LLD 0 l Zr-95 0.14 <LLD - - <LLD 0 g
' <LLD 0 g Ru-103
- 0.11 (LLD - -
- l 0 Ru-106 0.59 i (LLD - - <LLD !
I i
C5-134 0.11 t <tLD -
- (LLD 0 j Cs-137 0.056 0.067 (1/2) P-6, Lock & Dam #3 0.117 (1/4) 0.117 (1/4) 0
- 1.6 mi 9 129*/SE - - i I
Ba-La-140 0.11 (LLD - -
l <LLD. O l
Ce-141 0.14 <LLD - - (LLD 0 Ce-144 0.31 <tLD - - <LLD 0
- GB = gross beta; GS = gassia scan.
O LLD = nominal lower limit of. detection based on 4.66 sigma error for background sample.
C . Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).
Locations are specified (1) by name and code (Table 2) and (2) distance, direction, and 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.
-- o
L
6.0 REFERENCES
CITED Arnold, J. R. and H. A. Al-Salih. 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, t ..
University of Chicago Press, Chicago, Illinois, 369-382.
- Hazleton Environmental Sciences Corporation. 1975. Sampling Procedures, Prairie Island Nuclear Generating Plant, Revision 12,1 May 1983.
. 1979a. . Radiation Environmental 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 Analysis Data Tables, January -
.. December 1978.
. 1980a. Radiation Environmental- Monitoring for Monticello
.1 Nuclear Generating Plant, Complete Analysis Data Tables, January -
December 1979.
. 1980b. - Radiation Environmental Monitoring for Prairie i
Island Nuclear Generating Plant, Complete Analysis Data. Tables, Janauary l- - December 1979.
l, . 1981a.. Radiation Environmental Monitoring for Monticello
[- Nuclear Generating Plant, Complete Analysis Data Tables,. January-December >
l 1980.
-. 1981b. Radiation Environmental Monitoring for Prarie Island Nuclear Generating _ Plant, Complete Analysis Data Tables, January'-
December 1980.
. 1982a. Radiation Environmental Monitoring for Monticello Nuclear _ Generating Plant, Complete Analysis Data Tables,- January -
~
December 1981..
.. 1982b. -Radiation ~ Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January --
. December 1981. .
L . 1983a._ Radiationi Environmental Monitoring for Monticello j., Nuclear Generating Plant, Complete Analysis Data Tables, January - ,
f = December 1982.
25-
[:
, -, ._ .._.L. . ._.-._....-.._,._..._...L.L....._-..___ . . . , . . , _ - - _ . . _ . _ _ . - . _ . . - . _ - - . _ _ _ _
l . 1983b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -
December 1982.
. 1982. Quality Assurance Program Manual, Revision 0, 1 January 1982. (Under revision)
. 1977. Analytical Procedures Manual, Nuclear Sciences Section, Revision 3, 22 May 1981. (Under revision)
National Center for Radiological Health,1968. Radiological Health and Data Reports, Vol . 9, Number 12, 730-746.
Northern States Power Company. 1979. Prairie Island Nuclear Generating Plant, Annual Radiation 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
, Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1979 to December 31,1979 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.
. 1981. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to.the U.S. Nuclear Regulatory Commission, January 1,1980 to December 31,1980 ~ (prepared by Hazleton
- Environmental Sciences). Minneapolis, Minnesota.
. 1982. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1981 to December 31,1981 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.
. 1983. ~ Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring iteport to the U.S. Nuclear Regulatory i Commission, January 1,1982 to December 31,1982 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.
Teledyne Isotopes Midwest Laboratory. 1971a. Quality Control Program, Revision 6,15 July 1983.
. 1971b. Quality Control Procedures Manual, Revision 5, 15 July 1983.
. 1984a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January -
December 1983.
. 1984b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant. Complete Analysis Data Tables, January -
e December 1983.
4-26
U. S. Atomic Energy Commission. 1972. HASL Procedures Manual, Health and Safety Laboratory, Net York, NY., 10014.
U. S. Public Health Service. 1967. Radioassay Procedures for Environmu tal Samples, National Center for Radiological Heal th , Rockville, Maryland (Public Health Service Publication No. 999-RH-27).
, Wilson, D. W., G. fi. Ward and J. E. Johnson. 1969. In Environmental Contam-ination- by Radioactive Materials, International Atemic Energy Agency.
- p. 125.
G i
10 27
a E .
v" A
Appendix A Crosscheck Program Results L9 5
h' o -
4 .
A-1
i Appendix A Crosscheck Program Results Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory coriparison (crosscheck) programs since the formulation of its quality control program in December 1971. These programs are operated by agencies which supply envircnmental-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 eneck 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 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 1980 through 1983. 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 parti-cipation in the Second, Third, Fourth, and Fif th International Intercomparison of Environmental Dosimeters under the sponsorships listed in Table A-2.
A-2
Table A-1. U.S. Environmental Protection Agency's crosscheck program, com-parison of EPA and Teledyne Isotopes Midwest Laboratory results for milk and water samples,1980 through 1983a, Concentration in DCi/lb Lab ~ Sample Date TIML Result EPA Result Code Type Collected Analysis 2sc t30, n=1d STW-206 Water- Jan. 1980 Gross Alpha 19.0 2.0 30.0i8.0 Gross Beta 48.0 2.0 45.015.0 STW-208 Water Jan. 1980 Sr-89 6.1 1.2 10.0f0.5 Sr-90 23.9 1.1 25.5t1.5 STW-209 Water Feb. 1980 Cr-51 112 14 101 5.0 Co-60 12.7 2.3 11 5.0 Zn-65 29.7 2.3 25 5.0 Ru-106 71.7 1.5 51 5 Cs-134 12.0 2.0 10 5.0 Cs-137 30.0 2.7 30 5.0 STW-210 Water Feb. 1980 H-3 1800 120 1750 340 STW-211 Water March 1980 Ra-226 15.7 0.2 16.0 2.4 Ra-228 3.5 0.3 2.6:0.4 STM-217 Milk May 1980 Sr-89 4.4 2.69 5:5 Sr-90 10.0 1.0 12 1.5 STW-221 Water June 1980 Ra-226 2.0 0.0 1.7 0.8 Ra-228 1.610.1 1.7 0.8 STW-223- Water. July 1980- Gross Alpha 31 3.0 38 5.0 Gross Beta 44 4 35 5.0 STW-224 Water July 1980 Cs-137 33.9 0.4 35 5.'0 Ba-140 <12 0 K-40 1350 60 1550 78 I-131 <5.0 0 STW-225 Water Aug. 1980 H-3. 1280 50 1210 329 STW-226 Water Sept. 1980 Sr-89 22 1.2 24 8.6 Sr-90 12 0.6 15:2.6 STW-228 Water Sept. 1980 Gross Alpha nae 32.0 8.0 Gross Beta 22.5 0.0 21.0 5.0 STW-235 Water Dec . 1980 H-3 2420 30 2240 604 A-3
<4 .
Table A-1. (continued)
Concentration in DCi/lb Lab Sample Date TIML Result EPA Result
-Code Type Collected Analysis 2cc 20 , n=1d STW-237 Water Jan. 1981 Sr-89 13.0 1.0 1618.7 Sr-90 24.0 0.6 34 2.9 STM-239 Milk Jan. 1981 Sr-89 <210 0 Sr-90 15.7 2.6 20t3.0 I-131 30.914.8 26t10.0 '
Cs-137 46.9 2.9 4119.0 8a-140 <21 0 K-40 1330 53 1550 134 STW-240 Water Jan. 1981 Gross alpha 7.3t2.0 95.0 Gross beta 41.0t3.1 44 5.0 STW-243 Water Mar. 1981- Ra-226 3.5 0.06 3.4 0.5 Ra-228 6.5 2.3 7.3tl.1 STW-245 Water Apr. 1981 H-3 3210 115 2710 355
'STW-249 Water May 1981 Sr-89 51 3.6 36 8.7
, Sr-90 22.7 0.6 22 2.6 STW-251' Water May 1981 Gross alpha 24.0 5.3 21 5.2 Gross beta 16.1 1.9 14 5.0 STW-252 Water Jun. 1981 H-3 2140 95 1950 596 STW-255 Water- Jul. 1981 Gross alpha 20 1.5 22 9.5 Gross beta 13.0 2.0 1518.7 STW-259 Water ^
Sep. 1981 Sr-89 16.1 1.0 23 5 Sr-90 10.3 0.9 11 1.5 STW-265 Water Oct. 1981 Gross alpha- 71.2 19.1 80 20 Gross beta 123.3 16.6 111 5.6 Sr-89 14.9 2.0 21 5 Sr-90 13.1 1.7 14.4 1.5 Ra-226 13.0 2.0 12.7 1.9 STW-269- Water -Dec. 1981 ~H-3 2516 181 2700 355 7
> >- A-4
, , , - r . - - , .- - - , -# ,, , . -, ,~--*r v - + - - - + - m,r.- . - - --- ---
Table A-1. (continued)
Concentration in oCi/lb Date TIML Result EPA Result Lab Sample 3o, n=la Collected Analysis 2ac Code Type Jan. 1982 Sr-89 24.3 2.0 21.0 5.0 STW-270 Water 12. Dil.5 Sr-90 9.4 0.5
- ~
Jan. 1982 I-131 8.6 0.6 8.411.5 STW-273 Water Feb . 1982 H-3 1580 147 1820t342 STW-275 Water Cr-51 <61 0 STW-276 Water Feb. 1982 Co-60 26.0 3.7 20 5
- Zn-65 <13 15 5 Ru-106 <46 20 5 Cs-134 26.8 0.7 22 5 Cs-137 29.7 1.4 23 5 Mar. 1982 -Ra-226 11.9 1.9 11.6!1.7 STW-277- Water Gross alpha 15.6 1.9 19 5 STW-278 Water Mar. 1982 Gross beta 19.2 0.4 19 5 Apr. 1982 H-3 2690:i] 2860 360 STW-280 Water Apr. 1982 Gross alpha 7527.9 85:21 STW-281 Water 106 5.3 Gross beta 114.1 5~. 9 Sr-89 17.4 1.8 24 5 Sr-90 10.5 0.6 12 1.5 Ra-226 11.4 2.0 10. 9 1.5
<4.6 0 Co-60 Gross alpha 31.5 6.5 27.527 STW-284- Water May 1982 29 5 Gross beta 25.9 3.4 H-3 1970 1408 1830 340 STW-285 Water June 1982
.Ra-226 12.6 1.5 13.4 3.5 STW-286 Water June 1982 8.7 2.3 Ra-228 11.1 2.5 I-131 6.5 0.3 4.4 0.7
~STW-287 Water June 1982 H-3 3210 140 2890 619
-STW-290 Water. Aug. 1982 I-131 94.6 2.5 87 15 STW-291- Water Aug. 1982
-4 A-5
= . , . - - - , - - - - w -
k Table A-1. (continued)
Concentration in aci/l b Lab Sample Date TIML Result EPA lesult Code Type Collected Analysis 12aC 30, n=1d STW-292 Water Sept 1982 Sr-89 22.7 3.8 24.5 8.7 Sr-90 10.920.3 14.5t2.6 STW-296 Water Oct. 1982 Co-60 20.0 1.0 20i8.7 Zn-65 32.3 5.1 2428.7 Cs-134 15.3 1.5 19.0 8.7 Cs-137 21.0 1.7 20.018.7 STW-297 Water Oct. 1982 H-3 2470 20 25602612 STW-298 Water Oct. 1982 Gross alpha 32230 55 24 Gross beta 81.726.1 81 8.7 Sr-89 <2 0 Sr-90 14.120.9 17.2 2.6 Cs-134 <2 1.8 8.7
. Cs-137 22.7 0.6 20 8.7 Ra-226 13.6 0.3 12.5 3.2 Ra-228 3.9 1.0 3.6:0.9 STW-301 Water Nov. 1982 Gross alpha 12.0 1.0 19.0 8.7 Gross beta 34.012.7 24.0 8.7
-STW-302- Water Dec.'1982 I-131 40.0 0.0 37.0 10 STW-303 Water Dec. 1982 H-3 1940 20 1990 345 STW-304 Water Dec. 1982 Ra-226 11.7 0.6 11.0 1.7 Ra-228- <3 0 STW-306 Water Jan. 1983 Sr-89 20.0 8.7 29.2 5 Sr-90 21.7 8.4 17.2 1.5 STW-307 Water Jan. 1983 Gross alpha 29.0 4.09 29.0 13 Gross beta 29.3 0.6 31.0 8.7 STM-309 Mil k ' Feb. 1983 Sr-89 35 2.0 37 8.7-Sr-90 13.7 0.6 18 2.6 I-131 55.7 3.2 55 10.4 Cs-137 29 1.0 26 8.7 Ba-140 <27 0 K-40 1637 5.8 1512 131 A-6
Table A-1. (continued)
Concentration in 3Ci/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis 12ac 130, n=1d 4
STW-310 Water Feb. 1983 H-3 2470i80 2560i612 STW-311 Water March 1983 .Ra-226 11.911.3 12.7*3.3 Ra-228 <2.7 0 STW-312 ~ Water March 1983 Gross alpha 31.614.59 31*13.4 Gross beta 27.012.0 28 8.7 STW-313 Water April 1983 H-3 3240180 33301627 STW-316- Water May 1983 Gross alpha 94t7 64 19.9 Gross beta 13315 149t12.4 Sr-89 19 1 24 8.7 Sr-90 12 1 13i2.6 Ra-226 7.9 0.4 8.5 2.25 Co-60 30t2 30t8.7
. Cs-134 2712 3318.7 Cs-137 29 1 2718.7
. . STW-317 Water- May 1983 Sr-89 59.7 2.1 57 8.7 Sr-90 33.7 1.5 38 3.3 STW-318f Water May 1983 Gross alpha 12.811.5 11 8.7
' Gross beta 49.4 3.9 5718.7 STM-320 Milk June 1983 -Sr-89 20 0 25 8.7
.Sr-90 10 1 16 2.6
, I-131 30 1 30 10.4 Cs-137 52 2 47 8.7 K 1553 57 1486 129 STW-321 Water June 1983 H-3 1470 89 15291583 STW-322 Water- June 1983 Ra-226 4.3 0.2 4.8 1.24 Ra-228 <2.5 0 STW-323' Water July 1983 Gross alpha 3t1 7 8.7 Gross beta 21 0 22 8.7 STW-324 Water August 1983 1-131 13.3 0.6 14 10.4 s A-7
c Table A-1. (continued)
Concentration in DCi/lb Lab- Sample Date TIML Result EPA Result Code Type Collected Analysis 27C t3o, n=1d STAF-326 Air August 1983 Gross beta 4212 3618.7 filter Sr-90 14t2 10 2.6 Cs-137 19t1 15t8.7 STW-328- Water Sept. 1983 Gross alpha 2.3t0.6 5 8.7 Gross beta 10.711.2 918.7 STW-329 Water Sept. 1983 Ra-226 3.010.2 3.110.81 Ra-228 3.210.7 2.0 0.52 STW-331 Water Oct. 1983 H-3 1303 32 12101570 a Results obtained by Teledyne Isotopes Midwest Laboratory 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. ~
- b- All results are in pCi/1, except for elemental potassium (K) data which are in mg/1.
c Unless otherwise indicated, the TIML'results given as the mean 2a standard deviations for three determinations.
d USEPA results are presented as the known values control limits of 3o for n=1.
e NA =-Not analyzed. ~
'f' Analyzed but not reported to the EPA."
9 Results after calculations corrected (error in calculations when reported to EPA).
a Y
A-8
- +
4..
Table'A-2. Crosscheck program results, thermoluminescent dosimeters (TLDs).
mR
'Teledyne Average 12 d Lab- TLD.. Result Known (all Code Type Measurement 12 a value participants)-
2nd International Intercomparisonb
~
ll5-2b CaF2:Mn Gamma-Field 17.011.9 17.lc 16.417.7
, Bolb
- Gansna-Lab 20.814.1 21.3c 18.817.6 1
3rd International Intercomparisone 115-30 CaFp:Mn Gansna-Field 30.713.2 34.914.8f 31.513.0 Bulb Gansna-Lab 89.616.4 91.7114.6f 86.2124.0 4th International Intercomparison9 115-49 CaFg:Mn Gamma-Field 14.111.1 14.lil.4f 16.09.0 Bulb -
Gausna-Lab (Low) 9.311.3 12.212.4f 12.017.6
, Gausna-Lab (Illgh) 40.411.4 4h.819.2f 43.9113.2 5th International Intercomparisonh 115-5Ah CaF2:Mn Gamma-Field
- 31.411.8 30.016.01 30.2114.6 Bulb Gan.na-Lab 77.415.8 75.217.61 75.8140.4 at begirining i Gamma-Lab 96.615.8 88.418.81 90.7131.2 i at the end i
-' .= > - . .
Table A-2. (Continued) mR
_ Teledyne Average i 20 d (all
. Lab _ TLD Result Known' Code Type- Measurement 12oa Value participants) ll5-5Bh LiF-100 Gamma-Field 30.314.8 30.0161 30.2114.6
.! Gamma-Lab 81.117.4 75.217.61' 75.8140.4 at beginning i s l Gunna-Lab 85.4111.7 88.418.81 90.71131.2 i atLthe end
- aLab result given is the mean 12u standard deviations of three determinations.
3,.
bSecond International Intercomparison of Environmental Dosimeters conducted in April of 1976 by th0 Health y, and Safety Laboratory (GASL), New York, New York, and the School of Public Health of the University of c2 Texas, Houston, Texas.
4 cValue determined by sponsor of the intercanparison using continuously operated pressurized ion chamber.
d Mean las standard deviations of results obtained by'all laboratories participating in the program.
- eThird International Intercomparison of Environmental Dosimeters conducted in summer of 1977 by Oak Ridge 4 National Laboratory and the School of Public Health'of the University of Texas, Houston, Texas.
IValue 13a standard deviations as determined by sponsor of the intercomparison using continuously operated
~
.t' pressurized ion chanber.
9 Fourth International Intercomparison of Environmental Dosimeters conducted in summer of 1979 by the
' School of Public llealth of the University of Texas, Houston, Texas.
.hFif th International Intercomparison of Environmental Dosimeter conducted in f all of 1980 at Idaho Falls, Idaho and sponsored by the' School of Public Health of the University of Texas, Houston, Texas and i Environmental Measurements Laboratory,-New York, New York, U.S. Department of Energy.
i I Value determined by sponsor of the intercomparison using continuously operated pressurized ion chamber.
1 i
,= 2
e ..
3 O
Appendix B Data Reporting Conventions o
'a 5
B-1
r a
JF Data Reportino Conventions 1.0. All activities are decay corrected to collection time.
2.0. Single Measurements Each single measurement is reported as follows:
Xis where x = value of the measurement; s=2 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 .
where L = is the lower limit- of detection based on 4.660 uncertainty for a background sample.
3.0. Duplicate Analyses
, 3.1. Individual results: x1 s1 x2 i 52 Reported result: xis where x = (1/2) (x1 + x2) s = (1/2) s 2+sf 3.2. Individual results: <L1
<L2 Reported result: <L where L =-lower of L1 and L2 3.3. Individual results: x s
<L' Reported result: x s if x < L;
<L otherwise if j' 8-2
- 3 e
4 4.0. Computation of Averaces and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviations of a set of n numbers x1, x2. Xn are defined as follows:
' x = fI x s= E I*-a 2 n-1 4.2 Values- below the-highest ~.ower limit of detection are not included in the average.
4.3 If all of the values in the averaging group are less than the highest LLD, the highest LLD is reported.
. 4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is recorted.
a 4.5. In rounding off, the following rules are followed:
4.5.1. If the figure following those to be retained is less than 5, the figure is dropped, ano the retaineo figures are kept unchanged. As an example,11.443 is rounded off to 11.44 4.5.2 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.
4.5.3. If the figure following those to be retained is 5, and if
~
there are no figures other than zeros beyond the five, the figure 5 is dropped, .and the last-place figure retainea is -
increased by one if it is an odd numoer or it is kept unchanged if an even number. As an example,11.435 is rounded off to 11.44, wnile 11.425 is-rounded off to 11.42.
P
,g B-3
o a
~
e d
Appendix C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas
-O r
C-1
s
" 'd 'able C-1. Max 1' mum pennissible concentrations of radioactivity in air and water above natural background in unrestricted areas.a Air Water
-i
- t Gross alpha 3 pCi/m3 Strontium-83 3,000 pCi/1 Gross beta 100 pCi/m3 Strontium-90 300 pC1/1
- :odine-131b o,14 pCf/m3 Cesi.um-137 20,000 pCi/l Barium-140 20,000 pCi/l Iodine-131 300 pC1/1 Potassium 40c 3,000 pCi/1 j, Gross alpha 30 pCi/1 Gross beta 100 pCi/l .
.... Tritium 3 x 106 pCi/1
, l' a7aken from Code of Federal Regulatf ons Title 10, Part 20, Table
!! and accrocriate footnotes. Concentrations may be averaged over a ceriod not greater.than cre year.
b: rom 10 CFR 20 but acjustec by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.
~
cA natural radionuclide.
e i
C-2
.. _ _ _ _ _ _ _ _ _ _ _ _ _ _-. _