ML20151W287
| ML20151W287 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/31/1987 |
| From: | Huebner L TELEDYNE ISOTOPES MIDWEST LABORATORY |
| To: | |
| Shared Package | |
| ML20151W290 | List: |
| References | |
| NUDOCS 8805030348 | |
| Download: ML20151W287 (60) | |
Text
{{#Wiki_filter:- 7 , I
'/PTF1 FrVNE ISOTOPES MIDWEST LABORATOAY 1508 FRONTAGE RD.
NORTHBROOK, IL 60062 4197 om 56m00 NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNES0TA l l I PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-42 i 50-306 DPR-60 ! ANNUAL REPORT to the UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1, 1987 to December 31, 1987 Prepared Under Contract by TELEDYNE IS0 TOPES MIDWEST L/,BORNiORY Project No. 8010 Approved by: hlG. Huebner General Manager 12 February 1988 7 0805030348 880429 ADOCK 05000282 (!l PDR R DCD
9 I e 8 i PREFACE l The staff of Teledyne Isotopes ' Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by members of the staff of the Environmental & Regulatory Activities Department. l The report was prepared by L. G. Huebner, General Manager, Teledyne Isotopes Midwest Laboratory. He was assisted in the report preparation by other staff members of this laboratory. 4 11
l' l' i -. .. , TABLE OF CONTENTS Section Page Preface ........................... 11 Li s t o f Tabl e s . . . . . . . . . . . . . . . . . . . . . . . . iv
1.0 INTRODUCTION
. . . . . . . . . . . . . . . . . . . . . . . . . 1 2.0
SUMMARY
........................... 2 3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) ...... 3 3.1 Program Design and Data Interpretetion ......... 3 3.2 Program Descri ption . . . . . . . . . . . . . . . . . . . 4 3.3 Prog ram Executi on . . . . . . . . . . . . . . . . . . . . 6 3.4 Laboratory Procedures . . . . . . . . . . . . . . . . . . 6 3.5 Program Modifications . . . . . . . . . . . . . . . . . . 7 3.6 Land Use Census . . . . . . . . . . . . . . . . . . . . . 7 4.0 RESULTS AND DISCUSSION . . . . ... . . . . . . . . . . . . . . 8 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents . . . . . . . . . . . . . . . . . . . F 4.2 Program Findings .................... 8 5.0 TABLES . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12
6.0 REFERENCES
CITED . . . . . . . . . . . . . . . . . . . . . . . 25 APPENDICES A Interlaboratory Comparison Program Results . . . . . . . . . . A-1 B Data Reporting Conventions . . . . . . . . . . . . . . . . . . B-1 C Maximum Permissible Concentrations of Radio-activity in Air and dater Above Natural Background in Unre:tricted Areas . . . . . . . . . . . . . . C-1 fii l
o l l LIST OF TABLES No. Title Page 5.1 Sample Col'lection and Analysis Program,1987 . . . . . . . . . 13 5.2 Sampling Locations . . . . . . . . . . . . . . . . . . . . . . 15 5.3 Missed Collections and Analyses,1987 ............ 17 5.4 Environmental Radiological Monitoring Program Summary .... 18 In addition, the following tables are in the Appendices: Appendix A A-1 Interlaboratory Comparison Program Results, 1984-1987 .... A-3 A-2 Interlaboratory Comparison Program Results (TLDs) ...... A-14 A-3 In-house Spiked Samples ................... A-17 A-3 In-house "Bl ank" Sampl es . . . . . . . . . . . . . . . . . . . A-20 Attachment B: Acceptance criteria for spiked samples .... A-23 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Un restri c ted Areas . . . . . . . . . . . . . . . . . . . . . C-2 1 iv
1.0 INTRODUCTION
This report summarizes and interprets results of the Radiation Environmental Monitoring Program (REMP) conducted by Teledyne Isotopes Midwest Laboratory at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December,1987. This program monitors the levels of radioactivity in the air, terrestrial, 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 in this report. These data are included in a reference document (Teledyne Isotopes Midwest Laboratory,1987) 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 achiaved initial criticality on 17 December 1974. Commercial operation at full power began on 21 December 1974. 1
4 . . 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 1987 are sumarized and discussed. Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant. No effect on the environment due to the operation of the plant is indicated. 2 L
. . ~ _ - - - -
L4 . , 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 gama 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; (4) Industrial and medical radioactive waste; and (5) Fallout from nuclear accidents. 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 (distent, 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 ft,m other sources. An additional interpretive technique involver analyses for specific radionuclides present in the environmental sait. oles collected from the plant site. The plant's monitoring progran 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, 3
cesium-137, cerium-144, beryllium-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 pro-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 af ter 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-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, 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 bec.'me operational . Results of the plant's monitoring program can be relawd 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 sumarized 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 (Teledyne Isotopes Midwest 1.aboratory,1987). 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 4
weekly. Particulate filters are analyzed for gross beta activity and charcoal filters for iodine-131. A monthly composite of all particulate filters is gama-scanned on an HP 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 D/Q residence). As a "Lessons Learned" commitment, ambient gama radiation is monitored at thirty-two (32) locations, using CaSo4:Dy dosimeter with four sensi-tive areas at 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 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). If the milch animals are on pasture, the milk is collected biweekly during the growing season (May - November) . All samples are analyzed for iodine-131 and gamma-emitting isotopes. For additional monitoring of the terrestrial environment, leafy green vegetables (cabbage) are collected annually from the highest D/Q garden and a control location (P-25) and analyzed for iodine-131. Corn is collected annually only from fields irrigated with river water and a control location (P-25) and analyzed for gama-emitting isotopes. Al so , well water is collected quarterly from four locations ano analyzed for tritium and gamma-emitting isotopes. River water is collected weekly at two locations, one upstream of the plant (P-5) and one downstream (P-6, Lock and Dam No. 3). Monthly composites are analyzed for gamma-emitting isotopes. Quarterly compo-sites are analyzed for tritium. Drinking water is collected weekly from the City of Red Wing well. Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes. Quarterly composites are analyzed for tritium. The aquatic eavironment is al so monitored by semi-annual upstream and downstream collections of fish, periphyton or invertebrates, and bottom sediments. Shoreline sediment is collected semi-annually from one location. All samples are analyzed for gama-emitting isotopes. 5
4 . . 3.3 Program Execution The Program was executed as described in the preceding section with the following exceptions:
- 1. The TLD data for the first quarter of 1987 for Locations P-04A, P-05A, and P-06A were not available because TLDs were lost in the field.
- 2. The TLD data for the fourth quarter of 1987 for Locations ,
P-03S and P-0SS were not available because the TLDs were lost in the field. Deviations from the program are sumarized in Table 5.3. The cases of TLDs lost in the field over the last three years were reviewed to determine whether action was necessary to prevent future recurrences. Two locations showed multipie occurrences during that time period - P10B and P5S. Relocation to less obvious or less accessible locations is being considered as a corrective measure. 3.4 Laboratory Procedures All iodine-131 analyses in milk and drinking water were made by using a sensitive radiochemical procedure which involves separation of the element by use of an ion-exchange resin and subsequent beta counting. All gama-spectroscopic analyses were performed with an HP Ge or Ge(Li) detector. Levels of iodine-131 in cabbage were determined by HP Ge or Ge(Li) spectrometry. Levels of airborne iodine-131 in charcoal samples were measured by HP 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 (Teledyne Isotopes Midwest Laboratory, 1985). 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 Comission (U. S. Atomic Energy Comission, 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 Quality Assurance Program are presented 6
elsewhere (Teledyne Isotopes Midwest Laboratory,1985). The TIML Quality Assurance Program includes participation in Interlaboratory Comparison (Crosscheck) Programs. Results obtained in crosscheck programs are presented in Appendix A. 3.5 Program Modifications During the growing season, milk producers were monitored to determine when the dairy animals were on pasture or fresh cut feed. The frequency of milk samples was increased to semimonthly at one indice. tor location (Gustafson) during the period because animals were on pasture or fresh cut feed. 3.6 Land Use Census In accordance with Technical Specification 4.10, parcgraph B1, a land use census is conducted in order to identify the location of the nearest milk animal the nearest residence, and the nearest garden of greater than 500 ft b producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of 5 miles. This census is conducted at least once per 12 months between the dates of May 1 and October 31. New locations are added to the radiological environmental 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.
- The 1987 Land Use Census was completed on June 9,1987. This census did not identify any locations of exposure pathways different from those used in the program during the first six months of the year. Milk anc garden sample locations did not change due to the requirements of the land use census.
t { l l l l l 7
l 4.0 RESULTS AND DISCUSSION All of the scheduled collections and : analyses were made except those listed in Table 5.3. All results are summarized in Table 5.4 in a format recommended by the Nuclear Regulatory Commission in Regulator.y 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 and Nuclear Accidents There were no reported atmospheric nuclear tests in 1987. The last reported test was conducted on October 16, 1980 by the People's Republic ' of China. The reported yield was in the 200 kiloton to 1 megaton range. There was an accident at Reactor No. 4 of the Chernobyl Nuclear Plant complex in the U.S.S.R. The accident occurred on April 26, 1986. The releases of radioactive isotopes continued for ten days. On May 6, 1986, the reactor was sealed and releases to the atmosphere were reduced to negligible amounts. There were no reported accidents at nuclear reactor facilities in 1987. 4.2 Program Findings Results obtained show background levels of radioactivity in the environ-mental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant in 1987. Ambient Radiation (TLDs) Ambient radiation was measured in the general area of site boundary, at outer ring 4 - 5 mi distant frcm the Plant, at special interest areas, and at one control location. The means ranged from 16.5 mR/91 days at inner ring locations to 17.2 mR/91 days at outer ring locations. The mean at special locations was 15.9 mR/91 days and 17.0 mR/91 days at the control location. The differences are not statistically significant. The dose rates measured at all indicator and control locations were similar to those observed in 1978 (12.1 and 15.1 mR/91 days, respec-tively; in 1979 (12.6 and 15.3 mR/91 days, respectively); in 1980 (11.2 8
and 13.5 mR/91 days, respectively),; in 1981 (13.0 and 14.5 mR/91 days, respectively); in 1982 (12.0 and 13.0 mR/91 days , respectively),; in 1983 (13.0 and 14.9 mR/91 days, respectively); in 1984 (13.9 and 15.3 mR/91 days, respectively); in 1985 (13.9 and 15.3 mR/91 days, respec-tively); and in 1986 (16.6 and 17.0 mR/91 days, respectively). No plant effect on ambient gama radiation was indicated. Airborne Particulates The average annual gross beta concentration in airborne particulates measured 0.024 pCi/m3 at indicator locations and 0.023 pCi/m3 at control d locations and was imilar to the levels ogserved in 1982 (0.026 gCi/m ), 1983 (0.023 pCi/ ), 1984 (0.024 pCi/m ), 1985 pCi/mo ), and 1986 (0.025 pCf/m ). The average of 0.025 pCi/m{0.025 for 1986 does not include the results from May 19 to June 9,1986, which were influenced by the accident at Chernobyl. A spring peak in beta activity had been observed almost annually for many years (Wilson et al., 1969). It had been attributed to fallout of nuclides from the stratosphere (Gold et al .,1964). It was pronounced in 1981, occurred to a lesser degreTfn 1982, and did not occur in 1983, 1984, 1985, or 1987. In 1 '6, the spring peak could not be identi-fied because it was oversnadowea oy the releases of radioactivity from Chernobyl. The highest averages for gross beta were for the month of December and the fourth quarter, as in 1983, 1984, 1985, and 1986 (exclusive of the period between May 19, 1986 and June 9, 1986. Two pieces of evidence indicate conclusively that the elevated activity observed during the fourth quarter was not attributable to the Plant op-eration. In the first place, elevated activity of similar size occurred simultaneously at both indicator and control locations. Secondly, an i 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, 1988). Gamma spectroscopic analysis of quarterly composites of air particulate l filters yielded similar results for indicator and control locations. Beryllium-7, which is produced continously in the upper atmosphere by cosmic radiation (Arnold and Al-Salth, 1955), was detected in all samples. All other gama-emitting isotopes were below their respective LLD limits. Airborne Iodine keekly l evel s of airborn i dine-131 were below the lower limit of detection (LLD) of 0.07 pC1/m 3 in all samples. f r 9 l i
O
& e a Milk Iodine-131 results were below the detection limit of 1.0 pCi/1 in all sampl es .
Cs-137 results were below the LLD level of 15 pCi/l in all samples. No other gama-emitting isotopes, except potassium-40, were detected in any 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 the 1987 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 pC1/1 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 7.9 pCi/1 and was similar to the levels observed in 1979 (10.5 pCi/1), 1980 (11.8 pCi/1), 1981 (10.7 pCi/1),1982 (8.9 pCi/1), 1983 (8.0 pCi/1),1984 (7.9 pCi/1), 1985 (7.1 pCi/1), and 1986 (6.8 pCi/1). River Water At the upstream and downstream collection sites, quarterly composite tritium levels were below the LLD level of 330 pC1/1 in all samples. River water was also analyzed for gama-emitting isotopes. All gama-emitting isotopes were below their respective detection limits. There was no indication of a plant effect. Well Water l At the control well P-25, Kinneman Farm and three indicator wells (P-8, l i Comunity Center; P-10, Lock and Daa No. 3; and P-9, Plant Well No. 2) no tritium was detected above LLD level of 330 pCi/l in all samples. I l Gama-emitting isotopes were below the detection limits in all samples. 10
Crops Two samples of cabbage were collected in August and analyzed for I-131. The I-131 leel was below 0.014 pCi/g wet weight in both samples. There was no indication of a plant effect. Fish Fish samples were collected in July and September, 1987. The only isotope detected was naturally-occuring potassium-40 and there was no significant difference between upstream and downstream resul ts . There was no inoication of a plant effect. Aquatic Insects or Periphyton Aquatic insects (invertebrates) or periphyton were collected in June, July, and September, 1987. The samples were analyzed for gama-emitting isotopes. All gamma-emitting isotopes, except for naturally-occuring potassium-40, were below their respective LLDs. No plant effect was indicated. Bottom and Shoreline sediments Sediment collections were made in May and October, 1987. The samples were analyzed for gamma-emitting isotopes. Cs-137 was detected in two bottom sediment upstream samples and averaged 0.088 pCi/g dry weight. All other gama-emitting isotopes, except naturally-occurring potassium-40, were below their respective LLDs. No plant effect was indicated. 11 l
gg - - - - - O 4 e e E 5.0 TABLES i a ) 12
.. -. - - - . - . - . - - . - . _ - _ _ _ _ . - . - _ - . _ - - . - _ - - _ , . - - _ - - . - ~ . - - - -
Table 5.1 Sample collection and analysis program,1987. Prairie Island Collection Analysis Locations Type and Type and Medium No. Codes (and Typela Frequency b Frequency c , Ambient radiation 32 P-01A - P-10A C/Q Ambient gamma (TLDs) P-01B - P-15B
> P-01S - P-06S P-01C j 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 1 ,, P-4, P-6 ! u> Milk 5 P-16 to P-18, G/Md I-131, GS f P-25(C), P-14 a River water 2 P-5(C), P-6 G/W GS(MC), H-3(QC) Drinking water 1 P-11 G/W GB(MC), I-131(MC) i GS(MC), H-3(QC) Well water 4 P-25(C), P-6, U/Q H-3, GS
! P-8, P-9 i Edible cultivated 2 P-25(C),P-24 G/A I-131 l crops - leafy green vegetables j
., - ~
Table 5.1. Sample collection and analysis program, 1987 (continued) Prairie Island . Collection Analysis Locations Type and Type and Medium No. Codes (and Typela Frequencyb Frequencyc l Edible cultivated 2 P-25(C),P-20 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 l invertebrates Bottom sediment 2 P-5(C), P-6 G/SA GS Shoreline sediment 1 P-12 G/SA GS
- Location codes are defined in Table 5.2. Control stations are indicated by (C). All other b
stations are indicators. Collection type is coded as follows: C/ = continuous, G/ = grab. Collection frequency is coded as f 11 ws: W = weekly, M = monthly, Q = quarterly, SA = semi-annually, A = annuully. c Analysis type is coded as follows: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium, I-131 = i dine 131. Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly composite. d Milk is collected biweekly during the grazing season (May - November) if milch animals are on pasture. I l
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 P-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 Community Center 1.0 mi 0 304'/NW 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 2.6 mi 0 60*/ENE P-17 Place Farm 3.5 mi 0 25'/NNE P-18 Christensen Farm 3.7 mi 0 88'/E P-20 River Irrigated Corn Field
- P-24 Highest D/Q Garden **
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 O.7 mi 0 317*/NW P-10A Property Line 0.5 mi 0 333*/NNW P-01B Thomas Killian Residence 4.7 mi 0 355'/N P-02B Roy Kinneman Farm 4.8 mi 0 17'/NNE P-03B Wayne Anderson Farm 4.9 mt 0 46*/NE P-04B Nelson Drive (Road) 4.2 mi 0 61*/ENE P-05B County Road E and Coulee 4.1 mi 0 97'/E P-068 William Houschildt Residence 4.4 mi 0 112*/ESE P-07B Red Wing Service Center 4.7 mi 0 140*/SE P-08B David Wnuk Residence 4.1 mi 0 165'/SSE P-09B Highway 19 South 4.2 mi 0 187'/S P-10B Cannondale Farm 4.9 mi 0 200*/SSW a
"C" denotes control location. All other locations are indicators.
- Collected only if river water is used to irrigate the cornfields (Tachnical Specification Revision No. 80, effective 11-14-86).
** This location is not determined until after the Land Use Census is completed.
15
Table 5.2. Sampling locations (continued) Prairie Island Code Typea Name Location P-118 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-ISB 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 0.6 mi 0 158'/SSE P-03S Carl Gustafson Farm 2.2 mi 0 168'/SSE P-04S Richard Burt Residence 2.0 mi 0 228'/SW P-0SS 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.
s 16
Table 5.3. Missed collections and analyses, ~1987. Prairie Island Nuclear Generating Plant. All required samples were collected and analyzed as scheduled except the following. Collecti.a Date Sample Analysis Location or Period Comments Thermoluminescent Ambient P-04A ist Qtr. 1987 Lost in the Oosimeters (TLDs) Radiation fiel d. P-05A ist Qtr. 1987 Lost in the fiel d. P-06A ist Qtr. 1987 Lost in the field. P-03S 4th Qtr. 1987 Lost in the fiel d. P-05S 4th Qtr. 1987 Lost in the fiel d. 17
. .m. o . l. :_. ac . C
.\
l
.- - ,,.=.. ;, _ , O_.'s. ...v .- s i,..-._.-
w w .".,= ." Q O.10.h . . . ...
. y . , ... . . ._ ,s y
RAC! ""ON E.'M MC N M EN ~~A l M C.'u 7C.:! N G .: : 0 G .: a .'.' ucE l> - - _
\"'. 12)
N .v i.--. ,, . m % ./
,m w a .
- e. 'c -
I
- 11 I
Nx N4 : t u) *
*. . y I
l e
\
u w s
/..,'.
m' .e s.t w .-
\ . -
E'
.: g w :t 1% w
.\. I
' 1, t c\ /.- - w ,.
% m i N ,
*/, -. # .~/ L
"? a ~p+' 3 bi :l (7 s- , :\ :
-y- - ~
i i c ._ j r Olt MC.' u i- O 5.- i! N 4
= e r == - g 4 C' ' l s E-
- M q
(
~
ym 0
\
.f
's /(. <-
-{
I 3 Q,$ . .i , g3 .s
~
'.s q f.GE?.
il s . M :TY J\%)4 Qb 2 - -. Vs \Mh,' i li fsnC ll. #.g f4 c.. , . 35.C WINGk
.; W l
f, Y- / C, 'iu { (s.e :
-~
1: . , n .
/ -
t)
=
l g Noce: Ifap nu:nbers correspond to l W.--VI S/~# [ -- code numbers without the prefix ? -
\
o i. e
- 4 .=
e
- e. e., 1,0 i,
S C/.LE IN MILZ5 , l 17a
i 3C2- 't 5_a__ ?c.I?. c Je u, t 7'"" ~3* *JC litC" U. G "".: .'s.O! , ?L,u;- Si:s 2cu.ds: - : 'as e - ,3 . l Wrsc Nsc,y i _M W ja l.9 N w$ W '
i::::: :;
i1 l. ' i #!
;,,,,. L. *
%,,.8' . -. . . 9, J, me'.g l'g h 's.' ;. . <.: ,, ; ,
. 4 .'..,W f 4 ,
a j./
.I
*.\* vs( g )-s y r
.}>
4 g.3., 8 %
*r
~, ~
~. n t .-~ s - . ..
'm'== g. .v%.. %.. %,,,.%.
~ ~j a
I r,- . .,j,, . 1, mbh
- 3
!.i ii ." %. . T $
a ; . : ; .
- r. I ! '%#b %l ~
s i t21.,._ 'v' N_,~ . .' ' -, e- . ,'. l
! L,
~ , .
j i H .-
' s %.
i N;k,*s. lQ;i : H g i[' i *- V . ~
.S i o.a.E '
-\j" r
-:: , >'N-Gr -
Q .N !;/..; i;
.t, , :.
~ -
.w* 2 t 6 .m. .
4 ,- g -
-e 9.N;j S ) 1i
=
, 4-
- .A
- r. .
,m. mii s. w '\ .
s i ,, n 1 't 4.,e.
,c./-:.
v=sT'-
, #-/ :. i
- s. r(._
N
- .; . i I
'""D'i.yk.g k. ". s.,t,4% f.. W f.o.i xf ec.". ii 'i .
I
, ,o.
1,.s , ;. .. K ..,.N*...,.# ,
- j. -
-.S.,/ ms w ;,,l
- d. %. m,,,% A- ni a A. U !
u I l.... .. . d
.K-- .-Y eG -gh,d 8
--c -[ ,. 'di . ? #l' 9
(.,
- , = .
L '.i
,tk-L ,:.~.5>- p _ ,,\
.. . mi . W. . r
.h.. . .
'45" ^ .m.m .,
.s ht 5 I f..I.?'I[ g,
- v. /
hb y w 5.. ]s<j.,,,.
=w - -
4 -;
- g. l i. ~, .4 .
v .\ l' 1 r~.!
- W -.\
G;. 7, W,,M4 %s?w @ -@h:G i ) 9. lla$ w %n . ( P /p s ~~ l.,.. . c .. e i,
@%rw-f.f.aL.
w s
.r
,u1%g) c n.
r%l5 -
=~.G.) '
W ?w)! ' a ( N. v'" q L:: e. ,., Aw* v/r: ,n. ... .,a ..- l
. F,. -, ; w
~~ , f s e- 1; , F' -
(c ',.ii.-e\ ' N
,g/' '
t, i d'g fg 1~,/s..- .
) ,/ tf g
;g j
( g 'l h'f"gM I I/ p .,r)\ I
~]
['.
- .g r "ls- n
!_ y '* ./
%( ' d D ' j ;' "'-l. /
b Ifo ce: IIap cu::bers correspond to code nu:2bers withou: the sl***I p =f
- C '~ prefix ? -
l c;- %- - = . l l l 0 1 2 3 a 5 6 7 5 C 10 n.-- - . . . - - l h h #%E s .MG'O I 1 17c
l ; e f n' ois tt rul 0 0 0 0 0 0 0 0 0 be ro u, 0 me unR N o N 7
))
7 l 21 ) l l 8 o o ) b5 )8 9 s) o r r )6 /0 40 1 l nF r 2 / r oo( ri eg t n t n t n 4
/8 50 40 D D o D D
- ( L L e tt nn o) o) ol cw 41 (
9
- L L t b n a a t. cwo cw ( - 1 t t i t t 6 m oceR o el o 7 31 20 42 60 CoM el 0
3 e c L el ee ee ee 0. 4 71 0. 0 0. 0
- e Sb Sb Sb D ( ( ( 1( 0( 0(
0 5 2 y )) 8 r 20 i 2 a ) ) 55 )0
- u )
)
)
)5 i
) 4 ) 6 / 0 41 0 n F 1 4 4 4 2 /
5 a Te g 4
/2 /9 /8 50 40 J /0 41 ( - ( - - - - - -
nn 42 42 ( 41
- ' - 6 0 aa ( - (
2 6 7 81 24 t eR 5 20 80 s M 2. 4 0. 4 d e 7. 6 5. 91 6 71 71 0. 0 00 e h 8! 1( 1( 0( 0( t g 1! 1( r in e Ha
'. e
. hM e e W o g t n v n N W W N ni il i W a N N N wau L 5
i r E N 5 m / 6E 6N TJ t t e *1 / / e ro nn y/ D L / on d / t
- n P* P*
k c p iA n o tP r n *1 o r u 8 2 i n 3 3 n2 9 n< 9 o e t a i e8 p1 s 6 B 2 K o1 ol D R o e 9 i i c t l e 9 .c9 . t9 t9 - - - - . o a r9 Rn t a a L c P N t o ,ta t et a tt tt Sa t L , a .d a , Sa n A 8d 5i Cm1 ,6 ,6 a 35 4 a2 4 s0 1 r 6 l 0 0e 0e 0a1 6 R2 1 - 1 P - 0 R4 F1 P y P P P P P r g a m n i ) m t 3 u a r a e
) 0) )
S ) ) ) 24 6) e t t r sC 2) /5 10 m n o a s t on) 7) 31 0) 65 24 30 /1 a e taPC
/ / / 0 6 r G S at( e 29 e 20 10 D D D D D g ct g 70 02 o
r r a t w y
, iann dcaa 32
( - 62 ( - 21 ( - n o ( 7
- (
3
- L L
( L L L L ( L L ( L t e notR 1 8 N 40 83 P M t 1 20 60 n IL*
- 2. 2 2. 0 g
l c , u 5. 2 51 0. 0 0. 0 n u e o 61 71 1( 0( 0( i N u C 1( 1( r h ( o d d t n o 5 i a o 2 2 1 2 2 4 2 n l G 0 2 0 0 0 0 0 o s b 0 0 0 0 0 0 0 0 0 0 0 M I D L 3 3 3 3 0 0 0 0 0 0 0 l e L a i c r i i g a o r y 7 0 2 4 4 0 l P 2 i o
- t dos fa 3 6 2
"! 5 d 1 n e 9 a y t ars ey R t c 4 8 0 5 b t a ebl pma a a a a 7 5 5 6 6 N l i f m m m - - - - - -
t a n t c f a o Ty u.l nA m m a m a m a m a B 5 B e M e C 0 C o 7 n Z r e F G G G G G G m n n f o , o o t ) r it a) y s i v a ma a o c ) sgea
,ar )
sg
, )
s a e r
)
s s e f N L ynrd yn y A y t
) aiAn ais a a) a e s dR u dre) l t dl t as dl o ey l)
. l o l et ppi 1 raB 1 - i n 1t e 1 r ncm ri/
. myn 9er 9ema t 9cr
/ ee 9t
/ n otl aTU / nee / t R pt Ro brC S ( Rnnt Ru5s rap
- DmI et dmo - i DmSn Dmc L((G5 L((4d L((I L(( iP(
T T T T A k 1 M 1 [ill1!
e> Table 5.4. Environmental Radfological Monitoring Pragram Suinary tsstinued) Name of facility Prairia Island Nuclear Generating Plant Docaat 4o. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reperting Period January - December 1987 (County, State) Indicrtor Location with Highest ! Control Sample Type ani Lor.ations Annual Mean Locations Number of Type NumL r of Mean (FIC Heaa (F) Mean (F) kon-routine (Units) Analysesa Ltob RangeC Locationd Range Range Resul ts* Airborne Ra-103 0.002 (LLD - - <tLD 0 Particulates 3 <LLD 0 (pct /m ) Ru-306 0.016 <tLD - - (continued) Cs-134 0.0ul5 <t L D - - CD 0 Cs-137 0.002 (LLD - - <tLD 0 Ba-La -lW 0.012 <t L D - - (LLU U Ce-141 0.0034 <tLD - - <tLD 0 0.0074 <tL D 0 $ Ce-144 <t LD - - Airborne 1-131 26 0.07 <tLD - - <LL D 0 lodine (pCf/m3 ) Milk 1-131 68 1.0 <tLD - - <tLD 0 (pC1/3) GS 68 K-40 100 1330 (56/56) P-25, Kinneman Fars 1380 (13/13) 1380 (13/13) 0 (1130-1580) 11.1 at 9 331*/NNW (1210-1520) (1210-1520) Cs-134 15 (LLD - . <tLD 0 Cs-137 15 (LLD - - <tLD 0 Ba-La-143 15 (LLD - -
<tLD 0
Table 5.4. Environmental Radiological Monitoring Program Summary (coattamed) y
~
Name of Tacti?ty Prairie island Maclear Generettag Pleat Dockes No. 50-282. 50-306 Locatlee of racility Goodhue. Minnesota , Reporting Period January - December 1987 , (County, State)
! Indicator Locatfoe with Highest Control Serple Type and Locations Aanual Mean Locations Number of Type Number of Mean (F)C Mean (F) Mean (F) Non-routine (unsts) Analyses
- upb Rangec Locattoad Range Range _ Resultse Drinking water sa 12 1.0 7.9 (12/12) P-11. City of Red 7.9 (12/12) None 0 (pct /11 (5.6-13.9) Ning (5.0-9.0) 7.1 al 9 135*/SE 1-131 12 1.0 <LLD - - None 0 H-3 *4 330 <tLD - - None O G5 12
, Mn-54 15 <LLD - - None 0 Fe-59 30 (LLD - - None 0 y LS-h4 15 <tLD - - None O co-60 15 < llc - - None 0 Zn-65 30 (LLD - - None 0 Zr-Nb-95 15 qLD - - None O Cs-134 10 <tLD - - None O Cs-137 to <tLD - - None 0 Ba-La-140 15 <LLD - - None O Ce-144 64 <tLD - - None O River Mater H-3 8 730 <tLD - -
<tLD 0 fpC1/1)
G5 24 sNo-54 15 <tLD - - < tid 0 Fe-59 30 <tLD - - <tLD 0 Co-58 15 <tLD - - <LLD 0 Co-60 15 (LLD - - <LLD 0 Zn-65 30 (LLD - - <tLD 0
T
..g-L; 7 ,- ,
i o y "fg a a. o' a o o a a o u a o a a a a g'a M b s=e - s e- 8 eS SS - S eS S S eSeee oe eeevy eeS e S g g g,y ee ee e e A . - 3 7 S ). 5
' sh . . . . . . . . . . . . . . . .
I la I 5
= v-
. at ar3 :-
22 8 , 5 . . . . . . Ijf 3 i 3 " 8 8 j
# I DF
. ~b d % e6 u 5 3 3 SEC
[ : e n I ". SIN 5 S S S ec e S e S S S S S S S S S S ea vv vvv vv v S v
- na a 8
b1a s I %
~~~8 e 2 R $ $ R $ S S $ 3 d
- . =
0 5 5
- n .. 2 2 S
E : ] Ca 3 o T a3g
- : g O ~
3 T . 3 $ $ S $ 4t x ~0 - 3 3 ~ 3%
#1 ~E SS$$ j g l$$$$55SA$ U 13* -
T O 6 U b sr
. . : 3y :
"; y.
~ t:
* $4R '2 e e - -
es u2f. =s es 1 E-- I' a~
~ .
21 l
-- _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _l
l
.o
, Table 5.4. Envire m tal Radiological Monitoring Progran Summary (cont'nued) name of Factitty Prairie Island Nuclear Generating Plant Docket me. 50-282. 50-306 Location of Factitty Goodhue, Minnesota keporting Period January - Decader 1987 - (County,,, State) . Indicator Locatice with Nighest Control Sample Type and Locations Annual Mean Losations Number of - Type Number of Mean {F)C Mean (F) Mean (F) Non-routine (Un!ts) Analysesa LLDb g .g c Locaticp Range. Range Aesults' Fish - Flesh GS 4 K-40 0.1 2.30 (2/2) P-5(C), Upstreaa of 2.76 (2/2) 2.76 (2/2) 0 (2.15-2.46) Plant (2.6s-2.84) (2.66-2.s4) 0.6 mi g 60*/ENE Mn-54 0.025 4LD - - 4LD 0 fe-59 0.12 4LD - - 4LD 0 Co-58 0.038 4LD - - ' 4LD 0 Co-60 0.024 4LD - - <t LD 0 y 2n-65 0.063 (LLC - - (LLD 0 Zr-Mb-95 0.040 4LL - - 4LO O Cs-134 0.n23 4LD - - <tLD 0 Cs-137 0.024 <tLD - - 4LD 0 Ba-La-140 0.29 4tD - - <LLD 0 Invertebrates CS 4 I Be-1 1.47 4LD - -
<LLD D
~
K-40 0.31f 2.14 (2/2) - - 4LD 0 (1.66-2.41) Mn-54 0.17 4LD - - (LLD 0 Co-58 0.18 4LD - - <tLD 0 Co-60 0.16 4LD - - 4Lo 0 2n-65 0.40 4LD - - 4LD 0 Zr-Mb-95 0.20 <tLD - - 4LD o
l'
.9
- 4 . 4 0 we
= = = = = = =
{'jj ..
. o .....
.g-3 .- 4 4-185 o a o o a o o O. 2* S S S S S usef d v
dv dv tv tv v dv -
@ 3,8 g 1 1 1 d1 g99 G Sw
. W S E' h _
?
S . j - b C b C3
%d ' ' ' '
' .E . . . . . . .
j
- p 5 d
s. 42 3 j 2 -3
- W N SI < <
R' _y .. .,
'3 -
tt 3 -l
- -1 .!A g 5* I. . . . . .
% - . . . . . . . Eli -" s-
"I 3 .1 "
W % %. I 8
- v. - Rd. 3 a'.
e-* av . 3 m2 2t
,F,,
d' L* .. 9 _
~E J
g 3 3 5 3 3 h*8 "C u R* 5 S S S S S gt
.y *4 0-8, ~) S S S SSS S e < eeev v S
v g aeevve
'3
- 532- .d e-y1 .
e
~)
z -- . e o m 3 3 a *S S 2 4 % h A o G $ $0 3 h'* 2 d a a4 d ad i a d d & & d 2 h T' ' : *
- 2 b . . .
E : l'O 3 g
-'t 1 ab3 m - .
2 $ , 0 ~0 3 : : g 3 5 3 $ 9
=
328
- I a hhhhkai a i :. i 6hki 1a
-m , s.
W 9
.: et tre,
- r: e..y :g.
$xs se-I, t=$
t_t_
. $2]t ge s
23
)
Table 5.4. Eevironmental Radiological Monttcring Program Srusmary (continued) Name of Fact 11ty Prairie Island Nuclear Generating Plant Docket No. >J-282, 50-306 , Location o' factitty Goodhue, Minnesota Reporting Period January - December 1987 (County, State) Indicator Location with Highest Control l Sample Type and Locations Annual Mean Locations humber of Type humber of Mean (F)C Mean (F) Mean (F) kon-routine (Units) Analyses 8 LLDb pange c Locationd Range Range Results'
~
Bottom and G5 6 Shoreline <tLD 0 5ediments Ru-103 0.039 <tLD - - ( (pct /g dry) <tLD 0 (continued) Ru-106 0.30 (LLD - - 0.036 <LLO - - <t LD 0 Cs-134 l 0.044 <tLLt F-5(C), Upstream of 0.088 (2/2) 0.088 (2/2) 0 Cs-137 Flant. 0.6 et 6 60*/Lkt (0.066-0.11) (0.066-0.11) 0.078 <tLD - <tLD 0 Ba-La-140 - 0.060 <t LP - - <tt u 0 Ce-141 0.17 <tLD <LLD 0 g 09-144 - - a CB = Gross beta; CS = g.assa scan. b LLD = Nominal lower limit of detection based on 4.66 sigma error for background sample. c Mean and range based upon Jetectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). d Locations are specified (1) by name and code (Table 2) ar? (2) distance, direction, and sector relative to reactor site.
- Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result is considered non-routine if it exceeds ten times the preoperational value for the location.
f One result (<3.70 pCl/g wet weight) was excluded from the determination of LLDs. The elevated LLD resulted from small sample size. J
4 e >e
6.0 REFERENCES
CITED Arnold, J. R. and H. A. Al-Salih. 1955. Beryllium-7 Produced by Cosmic Rays. Scier;ce 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 8. Kahn,1964. Measurement of Natu-rally Occuring Radionuclides in Air, in the Natural Radiation Environ-ment, University of Chicago Press, Chicago, Illinois, 369-382. Hazleton Environmental Sciences Corporation. 1979a. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 19/8.
. 1979b. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January -
December 1978.
. 1980a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January -
December 1979.
. 1980b. Radiation Environmental Monitoring for Prairie Island Nuclur Generating Plant, Complete Analysis Data Tables, January -
December 1979.
. 1981a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant Complete Analysis Data Tabics, January -
December 1980. ,. _ _. 1981b. Radiation Environmental Monitoring for Prarie Island Nuclear Generating Plcnt, 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.
. 1983a. Radiation Environmental Monitoring for Nonticello Nuclear Generating Plant, Complete Analysis Data Tables, January -
December 1982. 25 l
Hohenemser, C.M. Deicher, A. Ernst, H. Hofsass, G. Lindner, E. Racknagel. 1986. "Chernobyl," Chemtech, October 1986, pp. 596-605. National Center for Radiological Health, 1968. Radiological Health and Data RepoMs, 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 Commissicn, 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). Minneapolic, 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). Minneapolie, Minnesota.
. 1983. Prairie Island Nuclear Generating Plant, Annual Rau1ation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1982 to December 31,1982 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.
. 1984. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, lanuary 1,1983 to December 31,1983 (prepared by Teledyne Isotopes Midwest Laboratory). Minneapolis, Minnesota.
. 1985. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1984 to December 31,1984 (prepared by Teledyne Isotopes Midwest i.aboratory). Minneapolis, Minnesota.
. 1986. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Moni') ring Report to the U.S. Nuclear Regulatory Commission, January 1,1985 to December 31,1985 (prepared by Teledyne Isotopes Midwest Laboratory). Minneapolis, Minnesota.
. 1987. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, 1986 to December 31,1986 (prepared by Teledyne Isotopes Midwest Laboratory), Minneapolis, Minnesota.
26
. 1988. Prairie Isl6nd Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Cornission, January 1,1997 to December 31,1987 (prepared by Teledyne Isotopes Midwest Laboratory). Minneapolis, Minnesota.
Teledyne Isotopes Midwest Laboratory. 1971a. Quality Control Program, Revision 7. 20, November 1984.
. 1985. Quality Control Procedures Manual, Revision 6, ,
09 August 1985, t
. 1985. Quality Assurance Program Manual, Revision 1, 15 April 1985.
. 1985. Analytical Procedures Manual, Revision 5, 29 July 1985.
. 1984a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January -
December 1983.
. 1984b. Radiation Environme' ital Monitoring for Prairie Island Nuclear Generating Plant. Complete Analysis Data Tables, January -
December 1983.
. 1985a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analyses Data Tables, January -
December 1984.
. 1985b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analyses Data Tables, January -
December 1984.
. 1986a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete /nalyses Data Tables, January -
December 1985. 1986b. Radiation Environmental Monitoring for Prairie Island Nuclea'r denerating Plant, Complete Analyses Data Tables, January - , December 1985.
. 1987. Sampling Procedures, Prairie Island Nuclear Generating Plant, Revision 16, 18 December 1987.
. 1987a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analyses Data Tables, January -
December 1986. 1987b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analyses Data Tables, January - December 1986. 27
\
. 1988a. Radiation Environuental Monitoring for Monticello Nuciear Generating Plant, Complete Analyses Data Tables, January -
December 1987. 1988b. Radiation Environmental Monitoring for Prairie Island NucleadeneratingPlant, Complete Analyses Data Tables, January - December 1987. c U. S. Atomic Energy Commission. 1972. HASL Procedures .'lanual, Health and Safety Laboratory, New York, NY., 10014. U. S. Public Health Service. 1967. Radioassay Procedures for Environmental Samplos, National Center for Radiological Heal th, Rockville, Maryland (Public Health Service Publication No. 999-RW-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.
28 sv
- - - - _ - - - - - - - - - - - -- 1
- e .. .
Appendix A Interlaboratory Comparison Program Results 1 NOTE: Appendix A is updated twice a year and the complete Appendix is included in January and July monthly reports only. Please refer to January and July Reports for information. January, 1988 A-1
1 1 . . . Appendix A Interiaboratory Comparison Program Results Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of its quality control program in December 1971. These programs are operated by agencies which supply environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems. Participant laboratories measure the concentrations of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant 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 environmental sample crosscheck program for milk, water, air filters, and food samples during the period May 1984 through December 198/. 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, 1984, and 1985-1986 through participation in the Second, Third, Fourth, Fif th, Seventn, and Eighth International Intercompar-ison of Environmental Dosimeters under the sponsorships listed in Table A-2. Table A-3 lists results of the analyses on in-house spiked samples. Table A-4 lists results of the analyses on in-house "blank" samples. Attachment B lists acceptance criteria for "spiked" samples. A-2
7able A-1. U.S. Environmental Protection Agency's crosscheck program, com-parison of EPA and Teledyne Isotopes Midwest Laboratory results for milk, water, air filters, and food samples,1984 through 1987.3 Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collec ted Analysis 200 15, N=1 Control Limits STW-358 Water May 1984 Gr. alpha 3.0 0.6 3t5.0 0.0-11.7 Gr. beta 6.7tl.2 615.0 0.0-14.7 STM-366 Milk June 1984 Sr-89 21t3.1 25 5.0 16.3-33.7 Sr-90 13t2.0 1711.5 14.4-19.6 I-131 46t5.3 43t6.0 32.6-53.4 Cs-137 3814.0 35i5.0 26.3-43.7 K-40 1577*172 1496t75 1336-1626 STW-368 Water July 1984 Gr. alpha 5.111.1 6i5.0 0.0-14.7 Gr. beta 11.9i2.4 13t5.0 4.3-21.7 STW-369 Water August 1984 I-131 34.3'5.0 34.0i6.0 23.6-44.4 STW-370 Water August 1984 H-3 3003t253 2817t356 2200-3434 STr -371 Food July 1984 Sr-89 22.0 5.3 25.Di5.0 14.3-33.7 Sr-90 14.7t3.1 20.011.5 17.4-22.6 I-131 <172 39.0*6.0 28.6-49.4 Cs-137 24.0*5.3 25.0i5.0 14.3-33.7 K-40 2503tl32 2605t130 2379-2831 STAF-372 Air August 1984 Gr. alpha 15.311.2 17t5.0 8.3-25.7 Filter Gr. beta 56.0*0.0 51 5.0 42.3-59.7 Sr-90 14.3tl.2 1Bil.5 15.6-20.4 Cs-137 21.0t2.0 15t5.0 6.3-23.7 STW-375 Water Sept 1984 Ra-226 5.110.4 4.9 0.7 3.6-6.2 Ra-228 2.2i0.1 2.3i0.4 1.7-2.9 STW-377 Water Sept 1984 Gr. alpha 3.3*1.2 5.0*5.0 0.0-13.7 Gr. beta 12.7*2.3 16.0 5.0 7.3-24.7 STW-379 Water Oct 1984 H-3 2360i312 2810t205 2454-3166 STW-380 Water Oct 1984 Cr-51 <36 40i5.0 31.3-48.7 Co-60 20.3tl.2 20t5.0 11.3-28.7 Zn-65 150i8.1 147t5.0 138.3-155.7 Ru-106 <30 47t5.0 36.3-55.7 Cs-134 31.3*7.0 31i5.0 22.3-39.7 Cs-137 26.7tl.2 2415.0 15.3-32.7 : , [ A-3
Table A-1. (continued) Concentration in DCi/lb
. Lab Sample Date TIML Result EPA Resultd Code Type Colle:ted Analysis 22oc 15, N=1 Control Limits STM-382 Milk Oct 1984 Sr-89 15.7 4.2 22t5.0 13.3-30.7 Sr-90 12.?tl.2 1621.5 13.4-18.6 I-131 41. 7t3.1 42i6.0 31.6-42.4 Cs-137 31.3i6.1 32 5.0 23.3-40.7 K-40 1447166 1517*76 1386-1648 STW-384 Water Oct 1984 Gr. alpha 9. 7tl . 2 14t5.0 5.3-22.7 (81ind) Sampie A Ra-226 3.310.2 3.0t0.5 2.2-3.8 Ra-228 3.4tl.6 2.110.3 1.6-2.6 Uranium nae 0.0-15.4 Sample B Gr. beta 48.3t5.0 64c5.0 55.3-72.7 Sr-89 10.7*4.6 11t5.0 2.3-19.7 Sr-90 7.3tl.2 12tl.5 9.4-14.6 Co-60 16.3tl.2 14t5.0 5.3-22.7 Cs-13d <2 2t5.0 0. 0-l'3. 7 Cs-iS7 16.7 1.2 14t5.0 5.3-22.7 STAF-387 Air Nov 1984 Gr. alpha 18.7tl.2 15t5.0 6.3-23.7 Filter Gr. beta 59.0t5.3 52t5.0 43.3-60.7 Sr-90 18.3tl.2 2111.5 18.4-23.6 :
Cs-137 10.3tl.2 10t5.0 1.3-18.7 STW-388 Water Dec 1984 I-131 28.0t2.0 36t6.0 25.6-36.4 STW-389 Water Dec 1984 H-3 3583t110 31822360 2550-3806 STW-391 Water Dec 1984 Ra-226 8.421.7 8.6tl.3 6.4-10.8 Ra-228 3.110.2 4.110.6 3.0-5.2 ; STW-392 Water Jan 1985 Sr-89 <3.0 3.0*5.0 0.0-11.7 Sr-90 27.3t5.2 30.0tl.5 27.4-32.6 i STW-393 Water Jan 1985 Gr. alpha 3.3tl.2 515.0 0.0-13,7 ! Gr. beta 17.3t3.0 15 5.0 6. 3-2.' . 7 STS-395 Food Jan 1985 Gr. alpha 4.712.3 6.0i5.0 0.0 14.7 , Gr. beta 11.3tl.2 15.0*5.0 6.3-23.7 l Sr-89 25.3t6.4 34.015.0 25.3-42.8 i 27.0 8.8 26.011.5 Sr-90 23.4-28.6 I-131 38.0t2.0 35.016.0 24.6-45.4 Cs-137 32.7t2.4 29.015.0 20.3-37.7 K-40 1410*212 1382t120 1174 1590 i L A-4
\
i Table A-1. (continued) Concentration in DCi/10-Lab Sample Date TIML Result EPA Result 0 Code- Type Collec ted Analysis 22cc is, N=1 Control Limits STW-397 Water Feb 1985 Cr-51 <29 48t5.0 39.3-56.7 Co-60 21.323.0 20t5.0 11.3-28.7 Zn-65 53.725.0 55t5.0 46.3-63.7 Ru-106 <23 2525.0 16.3-33.7 Cs-134 32.311.2 35t5.0 26.3-43.7 Cs-137 25.313.0 25t5.0 16.3-33.7 STW-398 Water Feb 1985 H-3 3869 319 37962634 3162-4430 STM-400 Milk March 1985 l-131 7.3 2.4 9.0t0.9 7.4-10.6 STW-402 Water March 1985 Ra-226 4.610.6 5.0 0.8 3.7-6.3 Ra-228 <0.8 9.011.4 6.7-11.3 Reanalysis Ra-228 9.010.4 STW-404 Water March 1985 Gr. alpha 4.7t2.3 6t5.0 0.0-14.7 Gr. beta 11.3*1.2 15t5.0 6.3-23.7 STAF-405 Air March 1985 Gr. alpha 9.1tl.0 10.0t5.0 1.3-18.7 Filter Gr. beta 42.0tl.1 36.0ts.0 27.3-44.7 Sr 90 13.3tl.0 15.0tl.5 12.4-17.6 Cs-137 6.3t1.0 6.0t5.0 0.0-14.7 STW-407 Water April 1985 I-131 8.0t0.0 7.5t0.8 6.2-8.8 STW-408 Water April 1985 H-3 3399 150 3559 630 2929-4189 STW-409 Water April 1985 (81tnd) Gr. alpha 29.711.8 32.0t5.0 23.3-40.7 Sample A Ra-226 4.4iO.2 4.li0.6 3.1-5.1 Ra-228 nae 6.210.9 4.6-7.8 Uranium KAe 7.016.0 0.0-17.4 Sample B Gr. beta 74.3t11.8 72.015.0 63.3-80.7 Sr-89 12.3t7 6 10.015.0 1.3-18.7 Sr-90 14.7t2.4 15.0tl.S 12.4-17.6 Co-60 14.7t2.4 15.015.0 6.3-23.7 Cs-134 12.0t2.0 15. 0t5. 0 6.3-23.7 Cs-137 14.0i2.0 12.015.0 3.3-20.7 A-5 L- _____ ._ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _
Table A-1. (continued) Concentration in pCi/lb Lab Sample Date TIML Result EPA Resulto Code Type Collected Analysis 2ac Is, N=1 Control Limits STW-413 Water May 1985 Sr-89 36.0 12.4 39.0t5.0 30.3-47.7 Sr-90 14.3 4.2 15.0tl.5 12.4-17.6 STW-414 Water May 1985 Gr. alpha 8.3 4.1 12.0t5.0 3.3-20.7 Gr. beta 8.71.2 11.Di5.0 2.3-19.7 STW-416 Water June 1985 Cr-51 44.7t6.0 44.0t5.0 45.3-52.7 Co-60 14.3tl.2 14.0 5.0 5.3-22.7 Zn-65 50.3t7.0 47.0t5.0 38.3-55.7 Ru-106 55.315.8 62.0i5.0 53.3-70.7 Cs-134 32.7tl.2 35.015.0 26.3-43.7 Cs-137 22.7t2.4 20.015.0 11.3-28.7 STW-418 Water June 1985 H-3 2446 132 2416t351 1807-3025 STM-421 Milk June 1985 Sr-89 10.314.6 11.0i5.0 2.3-19.7 Sr-90 9.0i2.0 11.0tl.5 8.4-13.6 1-131 11.711.2 11.0t6.0 0.6-21.4 Cs-137 12.7tl.2 11.Di5.0 2.3-19.7 K-40 1512162 1525*132 1393-1657 STW 423 Water July 1985 Gr. alpha 5.0t0.0 11.0t5.0 2.3-19.1 Gr. beta 5.0t2.0 8.0*5.0 0.0-16.7 STW-425 Water August 1985 1-131 25.713.0 33.0*6.0 22.6-43.4 STW-426 Water August 1985 H-3 4363183 4480t447 3704-5256 STAF-427 Air August 1985 Gr. alpha 11.3 0.6 13.Di5.0 4.3-21.7 Filter Gr. beta 46.0tl.0 44.0t5.0 35.3-52.7 Sr-90 17.7 0.6 18.0tl.5 15.4-20.6 Cs-137 10.3t0.6 8.0*5.0 0.0-16.7 STW-429 Water Sept 1985 Sr-89 15.7t0.6 20.0i5.0 11.3-28.7 Sr-90 7.0i0.0 7.0tl.5 4.4-9.6 STW-430 Water Sept 1985 Ra-226 8.2 0.3 8.9tl.3 6.6-11.1 Ra-228 4.120.3 4.6i0.7 3.4-5.8 STW 431 Water Sept 1995 Gr. alpha 4.7i0.6 8.0*5.0 0.0-16.7 Gr. beta 4.7tl.2 8.0i5.0 0.0-16.7 A-6
Table A-1. (continued) Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collec ted Analysis 2cc Is, N=1 Control Limits STW-433 Water Oct 1985 Cr-51 <13 21.0t5.0 12.3-29.7 Co-60 19.3t0.6 20.0t5.0 11.3-28.7 Zn-65 19.7 0.6 19.0*5.0 10.3-27.7 Ru-106 <19 20.0t5.0 11. 3 t'8. 7 Cs-134 17.0tl.0 20.0t5.0 11.3-28.7 Cs-137 19.3tl.2 20.0t5.0 11.3-28.7 STW-435 Water Oct 1985 H-3 1957t50 1974t345_ 1376-2572 STW-436 Water Oct 1985 437 (Blind) Sample A Gr. alpha 53.0tl.0 52.0t13 29.4-74.6 Ra-226 5.9t0.1 6.3tl.0 4.1-7.9 Ra-228 8.210.1 10.1tl.5 7.5-12.7 Uranium nae 8.0t10.4 0.0-18.4 Sample B Gr. beta 85.7t2.5 75.0t5.0 76.3-83.7 Sr-89 21.3tl.5 27.Di5.0 18.3-35.7 Sr-90 10.310.6 9.0tl.5 6.4-11.6 Co-60 18.3tl.2 18.0t5.0 9.3-26.7 Cs-134 16.3*1.2 18.0t5.0 9.3-26.7 Cs-137 19.0tl.0 18.0*5.0 9.3-26.7 STM-439 Milk Oct 1985 Sr-89 50.310.6 48.0t5.0 39.3-56.7 Sr-90 23.3 0.6 26.0tl.5 23.4-28.6 I-131 45.7 3.2 42.0t6.0 31.6-52.4 Cs-137 60.710.6 56.0*5.0 47.3-64.7 K-40 1547i29 1540t77 1406-1674 STW-441 Water Nov 1985 Gr. alpha 5.3t0.6 10.0t5.0 1.3-18.7 Gr. beta 11.'/11.2 13.0t5.0 4.3-21.7 STW-443 Water Dec 1985 1-131 46. /t 2,,1 45.016.0 34.6-55.4 STW 444 Water Dec 1985 Ra-226 6.5*0.1 7.Itl.1 5.2-9.0 Ra-228 6.110.1 7.3tl.1 5.4-9.2 STW-445 Water Jan 1986 Sr-89 29.7t?.5 31.0t5.0 22.3-39.7 Sr-90 13.7i0.6 15.0tl.5 12.4-17.6 STW-446 Water Jan 1986 Gr. alpha 3.0t0.0 3.015.0 0.0-11.7 Gr. beta 5.3*0.6 7.0t5.0 0.0-15.7 1 A-7
Table A-1. (continued) Concentration in oCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collec ted Analysis 2ac 15, N=1 Control Limits STW-447 Food Jan 1986 Sr-89 24.3i2.5 25.0t5.0 16.3-33.7 Sr-90 17.310.6 10.0t1.5 7.4-12.6 I-131 22.7 2.3 20.016.0 9.6-30.4 Cs-137 16.3t0.6 15.0t5.0 6.3-23.7 K-40 927t46 950 144 701-1199 STW-448 Water Feb 1986 Cr-51 45.0t3.6 38.0 5.0 29.3-46.7 - Co-60 19.711.5 18.0t5.0 9.3-26.7 Zn-65 44.0*3.5 40.0t5.0 31.3-48.7 Ru-106 <9.0 0.025.0 0.0-8.7 Cs-134 28.3t2.3 30.0t5.0 21.3-38.7 Cs-137 23.7i0.6 22.0t5.0 13.1-30.7 STW-449 Water Feb 1986 H-3 5176148 5227tS25 4317-6137 STW-450 Water Feb 1986 U total 8.0t0.0 9.016.0 0.0-19.4 STW-451 Mil k Feb 1986 I-131 7.0t0.0 9.016.0 0.0-19.4 STW-452 Water March 1986 Ra-226 3.8t0.1 4.1t0.6 3.0-5.2 Ra-228 11.010.5 12.4tl.8 9.2-15.5 STW-453 Water March 1986 Gr. alpha 6.7t0.6 15.0*5.0 6.3-23.7 Gr. beta 7.3t0.6 8.0t5.0 0.0-16.7 STW-454 Water April 1986 I-131 7.010.0 9.016.0 0.0-19.4 STW-455 Water April 1986 456 (Blind) Sample A Gr. alpha 15.Dil.0 17.0t5.0 8.3-25.7 Ra-226 3.110.1 2.910.4 2.1-3.7 Ra-228 1.5 0.2 2.0*0.3 1.5-2.5 Uranium 4.7t0.6 5.016.0 0.0-15.4 Sample B Gr. beta 28.7tl.2 35.0t5.0 26.3-43.7 i Sr-89 5.7t0.6 7.0 5.0 0.0-15.7 Sr-90 7.0t0.0 7.0tl.5 4.4-9.6 Co-60 10.711.5 10.0t5.0 1.3-18.7 j Cs-134 4.011.7 5.015.0 0.0-13.7 Cs-137 5.310.6 5.0t5.0 0.0-13.7 A-8
Table A-1. (continued) Concentration in oCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collec ted Analysis 2cc Is, N=1 Control Limits STAF-457 Air April 1986 Gr. alpha 13.7!0.6 15.015.0 6.3-23.7 Filter Gr. beta 46.3t0.6 47.0*5.0 38.3-55.7 Sr-90 14.7 0.5 18.0tl.5 15.4-20.6 Cs-137 10.7 0.6 10.0t5.0 1.3-18.7 STU-458 Urine April 1986 Tritium 4313t70 4423t189 4096-4750 STW-459 Water May 1986 Sr-89 4.310.6 5.0t5.0 0.0-13.7 Sr-90 5.010.0 5.0tl.5 2.4-7.6 STW-460 Water May 1986 Gr. alpha 5.310.6 8.0t5.0 0.0-16.7 Gr. beta 11.3tl.2 15.0*5.0 6.3-23.7 STW-461 Water June 1986 Cr-51 <9.0 0.0t5.0 0.0-8.7 Co-60 66.0tl.0 66.0*5.0 57.3-74.7 Zn-65 87.3tl.5 86.0 5.0 77.3-94.7 Ru-106 39.7t2.5 50.0i5.0 41.3-58.7 Cs-134 49.3t2.5 49.0t5.0 40.3-57.7 Cs-137 10.3tl.5 10.0t5.0 1.3-18.7 STW-462 Water June 1986 Tritium 3427t25 3125t361 2499-3751 STM-464 Milk June 1985 Sr-89 <1.0 0.0t5.0 0.0-8.7 Sr-90 15.3t0.6 16.0tl.5 13.4-18.6 I-131 48.3t2.3 41.0t6.0 30.6-51.4 Cs-137 43.7 1.5 31.0t5.0 22.3-39.7 K-40 1567 114 1600t80 1461-1739 STW-465 Water July 1986 Gr. alpha 4.7t0.6 6.0t5.0 0.0-14.7 Gr. beta 18.7tl.2 18.0t5.0 9.3-26.7 STW-467 Water August 1986 I-131 30.3t0.6 45.016.0 34.4-55.4 STW-468 Water August 1986 Pu-239 11.3 0.6 10.1tl.0 8.3-11.9 STW-469 Water August 1986 Uranium 4.0 0.0 4.0t6.0 0.0-14.4 STAF-470 Air Sept 1986 dr. alpha 19.3tl.5 22.015.0 13.3-30.7 471 Filter Gr. beta 64.0t2.6 66.015.0 57.3-74.7 472 Sr-90 22.0tl.0 22.0t5.0 19.4-24.6 Cs-137 25.7tl.5 22.0t5.0 13.3-30.7 STW-473 Water Sept 1986 Ra-226 6.0t0.1 6.lt0.9 4.5-7.7 Ra-228 8.711.1 9.121.4 6.7-11.5 A-9
.o . .
Table A-1. (continued). Concentration in oC1/lb Lab Sample Date TIML Result EPA Resultd Code Type Coll ec ted Analysis 22oc is, N=1 Control Limits STW-474 Water Sept 1986 Gr. alpha 16.3t3.2 15.025.0 6.3-23.7 Gr. Deta -9.0tl.0 8.025.0 0.0-16.7 STW-475 Water Oct 1986 Cr-51 63.3f5.5 59.0t5.0 50.3-67.7 Co-60 31.0t2.0 31.015.0 22.3-39.7 ' Zn-65 87.3t5.9 85.0t5.0 76.3-93.7 Ru-106 74.7f7.4 74.0t5.0 65.3-82.7 Cs-134 25.710.6 28.0 5.0 19.3-36.7 Cs-137 46.3 1.5 44.0 5.0 35.3-52.7 STW-476 Water Oct 1986 H-3 5918160 59731597 4938-7008 SPW-477 Water Oct 1986 478 (811nd) Sample A Gr. alpha 34.0f6.0 40.0t5.0 31. 3-48. 7 Ra-226 5.8*0.2 6.0t0.9 4.4-7.6 Ra-228 2.7tl.0 5.0t0.8 3.7-6.3 Uranium 11.0t0.0 10.0t6.0 0.0-20.4 Sample B Gr. beta 30.7tl.2 51.015.0 42.3-59.7 Sr-89 5.0t0.0 10.015.0 1.3-18.7
- Sr-90 3.0t0.0 4.0i1.5 1.4-6.6 Co-60 24.711.2 24.015.0 15.3-32.7 Cs-134 11.012.0 12.0t5.0 3.3-20.7 Cs-137 9.3tl . 2 8.025.0 0.0-16.7 STM-479 Milk Nov 1986 Sr-89 7.711.2 9.0i5.0 0.3-17.7 -
Sr-90 1.0 0.0 0.0tl.5 0.0-2.6 I-131 52.3t3.1 49.0i6.0 38.6-59.4 Cs-137 45.7*3.1 39.0i5.0 30.3-47.7 K-40 1489i104 1565178 1430-1700 STU-480 Urine Nov 1986 H-3 5540*26 5257*912 4345-6169 STW-481 Water Nov 1986 Gr. alpha 12.014.0 20.0*5.0 11.3-28.7 Gr. beta 20.0 3.5 20.Di5.0 11.3-28.7 STW-482 Water Dec 1986 Ra-226 6.710.2 6.8*1.0 5.0-8.6 Ra-228 5.2i0.2 11.1tl.7 8.2-14.0 STW-483 Water Jan 1987 Sr-89 19.715.0 25.0i5.0 16.3-33.7 Sr-90 21.0t2.0 25.011.5 22.4-27.6 A-10
T Table A-1. (continued). Concentration in oCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collec ted Analysis 2ec 15, N=1 Control Limits STW-484 Water Jan 1987 Pu-239 17.0 2.3 16.7tl.7 13.8-19.6 STF-486 Food Jan 1987 Sr-90 36.0t4.0 49.0t10.0 31.7-66.3 I-131 78.0 3.4 78.0t8.0 64.1-91.9 Cs-137 89.7 3.0 84.0t5.0 75.3-92.7 K-40 942tS6 980 49 895-1065 STF-487 Food Jan 1987 SR-90 2.0t0.0 --- (81anK) 1-131 <3 --- Cs-137 <2 --- K-40 993t102 --- STW-488 Water Feb 1987 Co-60 49.010.0 50.0*5.0 41.3-58.7 Zn-65 96.0*7.2 91.0t5.0 82.3-99.7 Ru-106 92.0t20.2 100.0t5.0 91.3-108.7 Cs-134 53.013.4 59.015.0 50.3-67.7 Cs-137 89.314.6 87.0t5.0 78.3-95.7 STW-489 Water Feb 1987 H-3 4130t140 4209t420 3479-4939 STW-490 Water Feb 1987 Uranium 8.3*1.2 8.016.0 0.0-18.4 STM-491 Milk Feb 1987 I-131 10.0t0.0 9.0 0.9 7.4-10.6 STW-492 Water Mar 1987 Gr. alpha 3.7tl.2 3.015.0 0.0-11.7 Gr. beta 11.3 1.2 13.0 5.0 4.3-21.7 STW-493 Water Mar 1987 Ra-226 7.0t0.1 7.3tl.1 5.4-9.2 Ra-228 7.1*2.3 7.5tl.1 5.5-9.5 I STW-494 Water Apr 1987 I-131 8.0*0.0 7.010.7 5.8-8.2 STAF-495 Air Apr 1987 Gr. alpha 15.010.0 14.0i5.0 5.3-22.7 . Filter Gr. beta 41.0t2.0 43.0t5.0 34.3-51.7 Sr-90 16.3 1.2 17.0tl.5 14.4-19.6 Cs-137 7.010.0 8.015.0 0.0-16.7 STW-496 Water Apr 1987 497 (Blind) Sample A Gr. alpha 30. 7tl . 2 30.0t8.0 16.1-43.9 Ra-226 3. 9t0. 2 3.910.6 2.9-4.9 Ra-228 4.910.9 4.0t0.6 3.0-5.0 Uranium 5.010.0 5.0t6.0 0.0-15.4 A-11
s . . Table A-1. (continued) Concentration in oCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis 12cC 15, N=1 Control Limits STW-496 Water Apr 1987 497 (Blind) Sample B Gr. Beta 69.3 9.4 66.0t5.0 5/.3-74.7 Sr-89 16.3 3.0 19.015.0 10.3-27.7 Sr-90 10.0t0.0 10.0tl.5 7.4-12.6 Co-60 8.3t3.0 8.0t5.0 0.0-16.7 Cs-134 19.0t2.0 20.0t5.0 11.3-28.7 Cs-137 14.7*1.2 15.0*5.0 6.3-23.7 STU-498 Urine Apr 1987 H-3 6017 494 5620t795 4647-6593 STW-499 Water May 1987 Sr-89 38.0i6.0 41.0t5.0 32.3-49.7 Sr-90 21.0*2.0 20.0tl.5 17.4-22.6 STW-500 Water May 1987 Gr. alpha 9.0t3.4 11.015.0 2.3-19.7 Gr. beta 10.311.2 7.0t5.0 0.0-15.7 STW-501 Water June 1987 Cr-51 40.0t8.0 41.0t5.0 32.3-49.7 Co-60 60.3t3.0 64.0t5.0 55.3-72.7 Zn-65 11.3t5.0 10.0t5.0 1.3-18.7 Ru-106 78.3t6.4 75.0t5.0 66.3-83.7 Cs-134 36.7t3.0 40.0t5.0 31.3-48.7 Cs-137 80.3t4.2 80.0t5.0 71.3-88.7 STW-502 Water June 1987 H -3 2906t86 2895t357 2277-3513 STW-503 Water June 1987 Ra-226 6.9*0.1 7.3tl.1 5.4-9.2 Ra-228 13.3tl.0 15.2 2.3 11.2-19.2 STW-504 Milk June 1987 Sr-89 57.014.3 69.0t5.0 60.3-77.7 Sr-90 32.011.0 35.0tl.5 32.4-37.6 1-131 64.0t2.0 59.0t6.0 48.6-69.4 Cs-137 77.7 0.6 74.0t5.0 65.3-82.7 K 1383t17 1525t76 1393-1657 STW-505 Water July 1987 Gr. alpha 2.3i0.7 5.0t5.0 0.0-13.7 Gr. beta 4.011.0 5.0t5.0 0.0-13.7 STF-506 Food July 1987 I-131 82.7t4.6 80. 0:.d . 0 66.1-93. 9 Cs-137 53.713.0 50.015.0 41.3-58.7 K 1548157 1680*84 1534-1826 STW-507 Water Aug 1987 I-131 45.714.2 48.0t6.0 37.6-58.4 STW-508 Water Aug 1987 Pu-239 5.8t0.2 5.310.5 4.4-6.2 A-12
. 1 .
Table A-1. (continued) Concentration in DCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collec ted Analysis 22ac 15, N=1 Control Limits STW-509 Water Aug 1987 Uranium 13.310.3 13.0t6.0 2.6-23.4 STAF-510 Air Aug 1987 Gr. alpha 9.7 0.4 10.0t5.0 1.3-18.7 Filter Gr. beta 28.3t0.6 30.0*5.0 21.3-38.7 Sr-90 10.0t0.9 10.0*1.5 7.4-12.6 Cs-137 10.0tl.0 10.0i5.0 1.3-18.7 STW-511 Water Sept 1987 Ra-226 9.9t0.1 9.7tl.5 7.2-12.2 Ra-228 8.1tl.4 6.3tl.0 4.6-8.0 STW-512 Water Sept 1987 Gr. alpha 2.010.6 4.015.0 0.0-12.7 Gr. beta 11.3tl.3 12.0t5.0 3.3-20.7 STW-513 Water Oct 1987 H-3 4473t100 4492*449 3714-5270 STW-514 Water A Oct 1987 Gr. alpha 29.3t2.6 28.Di7.0 15.9-40.1 Ra-226 4.9*0.1 4.8i0.7 3.6-6.1 Ra-228 4.2 1.0 3.6t0.5 2.7-4.5 Uranium 3.0t0.1 3.0*6.0 0.0-13.4 STW-515 Water S Oct 1987 Gr. beta 72.3t2.7 72. 015.0 63.3-80.7 Sr-89 14.3tl.3 16.0*5.0 7.3-24.7 Sr-90 9.7i0.4 10.0*1.5 7.4-12.5 Co-60 16.7t3.0 16.015.0 7.3-24.7 Cs-134 16.7*2.3 16.0t5.0 7.3-24.7 Cs-137 24.3*3.3 24.0i5.0 15.3-32.7 STW-516 Water Oct 1987 Cr-51 80.3t17.5 70.0 5.0 61.3-78.7 Co-60 16.0t2.3 15.Di5.0 6.3-23.7 Zn-65 46.315.6 46.015.0 37.3-54.7 Ru-106 57.3t15.4 61.0*5.0 52.3-69.7 Cs-134 23.7*2.5 25.0*5.0 16.3-33.7 Cs-137 51.7i3.2 51.0t5.0 42.3-59.7 STU-517 Urine Nov 1987 H-3 7267t100 7432i743 6145-8719 STW-519 Water Dec 1987 I-131 26.0t3.0 26.0*6.0 15.6-36.4 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 Vegan, Nevada, b All results are in the pCi/1, except for elemental potassium (K) data, which are in mg/1; air filter samples, which are in pCi/ filter; and food, which is in pCi/kg. C Unless otherwise indicated, the TIML results are given as the mean i2 standard ^ deviations for thres determinations. A-13
, Table A-2. Crosscheck program results, thermoluminescent dosimeters (TLDs). _,
d f Teledyne Average 12'od ' Lab TLD Result Known (all Code Type Measurement 12aa Valuec partic ipants) ] 2nd International Intercomparisonb I 115-2 CaF2 Mn Fleid 17.011.9 17.1 16.417.7 j Bulb Lab 20.814.1 21.3 18.8t7.6 7 )P 3rd International Intercomparisone ]% 115-3 CaF2:Mn Field 30.713.2 34.914.8 31.513.0 j
- Bulb j Lab 89.616.4 91.7114.6 86.2124.0 i
- 4th Inte. national Intercomparisonf 115-4 CaF2
- Mn Field 14.111.1 14.111.4 16.019.0 1 Bulb
! Lab (Low) 9.311.3 12.212.4 12.017.6 I Lab (High) 40.411.4 45.819.2 43.9113.2 l 5th International Intercomparison9 115 'iA CaF2:Mn Field 31.411.8 30.016.0 30.2114.6 4 Bulb Lab at 77.415.8 75.217.6 75.8140.4 l beginning Lab at % .615.8 88.418.8 90.7131.2
- end
? l i
.w
- Table A-2. (Continned) .
mR Teledyne Average 120 d Lab TLD Result Known (all Code Type easurement 12aa Valuec participants) 115-58 LiF-100 Field 30.314.8 30.016.0 30.2114.6 Chips Lab at 81.117.4 75.217.6 75.8t40.4 beginning Lab at 85.4111.7 88.418.8 90.7131.2 y the end 7th International Intercomparisonh l Lir-100 Field 75.412.6 75.816.0
~
l 115-7A 75.1129.8 Chips l Lab (Co-60) 80.013.5 79.914.0 ti.9127.6 l Lab (Cs-137) 66.612.5 75.013.8 73.0122.2 115-78 CaF2:Mn Field 71.512.6 75.816.0 75.1129.8 ! Bulbs l Lab (Co-60) 84.816.4 79.914.0 77.9127.6. l Lab (fs-137) 78.811.6 75.013.3 73.0122.2 l 115-7C CaSO4 :Dy Field 76.812.7 75.816.0 75.1129.8 Cards Lab (Co-60) 82.513.7 79.?i4.0 77.9t27.6 Lab (Cs-137 79.013.2 75.013.8 73.0120 2
a Table A-2. (Continued) . . nR Teledyne Average 120 d
- Lab TLD Result Known (all Type Measurement 12oa valuec participants)
Code 8th International Intercomparison i Field Site 1 29.511.4 29.711.5 28.9112.4 115-8A L1F-100 Chips 11.310.8 10.410.5 10.119.06 Field Site 2 ' 13.710.9 17.210.9 16.216.8 Lab (Cs-137) Field Site 1 32.311.2 29.711.5 28.9112.4 115-8B CaF2:Mn Bulbs Field Site 2 9.011.0 10.410.5 10.119.0 I 15.810.9 17.210.9 16.216.8 Lab (Cs-137) 4 32.310.7 29.711.5 28.9112.4
- 115-8C CaSO4 :Dy Field Site 1 1 Cards Field Site 2 10.610.6 10.410.5 10.119.0 18.110.8 17.210.9 16.216.8 l Lab (Cs-137 a Lab result given is the mean 12 standard deviations of three determinations.
b Second International Intercomparison of Environmental Dosimeters conducted in April of 1976 by the Health and Safety Laboratory (GASL), New York, New York, and the School of Public Health of the University of Texas, Houston, Texas. c Value determined by sponsor of the intercomparison using continuously operated pressurized ion chamber. d Mean 12 standard deviations of results obtained by all laboratories participating in the program. e Third International Intercomparison of Environmental Dosimeters conducted in sunener of 1977 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas, Houston, Texas. f Fourth International Intercomparison of Environmental 00simeters conducted in sunsmer of 1979 by tt.e School of Public Health of the University of Texas, Houston, Texas. 9 Fif th International Intercomparison of Environmental Dosimeter conducted in fall of 1980 at Idaho Falls, 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. h Seventh International Intercomparison of Environmental Dostmeters conducted in the spring and stminer of 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, the U.S. Nuclear Regulatory g Commir.. 'on, and the U.S. Environmental Protection Agency. Eighth International Intercomparison of Environmental Dosimeters conducted in the fall and winter of 1985-1986 at New York, New York, and sponsored by the U.S. Department of Energy.
)
T g . 6 Table A-3. In-house spiked samples. Concentration in pCi/l Lab Sample Date TIML Result r.nown Expec ted Code Type Collec ted Analysis n=3 Ac tivity Precision it, n=3a QC-MI-6 Milk Feb. 19S6 Sr-89 6.0tl.9 6.4t3.0 8.7 Sr-90 14.2*1.7 12.9*2.0 5.2 I-131 34.2t3.8 35.2t3.5 10.4 Cs-134 32.0tl.8 27.3t5.0 8.7 Cs-137 3S.812.1 35.0t5,0 8.7 QC-W-14 Water Mar. 1986 Sr-89 1.6t0.4 1.6*1.0 7.1 Sr-90 2.4t0.2 2.4t2.0 4.2 QC-W-15 Water Apr. 1986 I-131 44.9*2.4 41.St7.0 10.6 Co-60 10.6tl.7 12.li5.0 7.lb Cs-134 30.2*2.4 25.8t8.0 7.lb Cs-137 21.911.9 19. 9t5.0 7.lb QC-MI-7 Milk Apr. 1986 I-131 39.7t3.3 41.5t7.0 10.4 Cs-134 28.7t2.8 25.8*8.0 8.7 Cs-137 21.2*2.8 19. 9t5.0 8.7 SPW-1 Water May 1986 Gross alpha 15.8*1.8 18.0*5.0 SC QC-W-16 Water June 1986 Gross alpha 16.2t0.7 16. 9t2. 5 8.7 Gross beta 38.4*3.5 30.2t5.0 8.7 QC-MI-9 Milk June 1986 Sr-89 <1.0 0.0 7.lb Sr-90 12.621.8 13.3t3.0 4.2b I-131 38. 9t7.0 34.8t7.0 10.4 Cs-134 33.013.4 36.115.0 8.7 Cs-137 38.5t2.8 39.0t5.0 8.7 SPW-2 Water June 1986 Gross alpha 16.8tl.8 18.0t5.0 Sc SPW-3 Water June 1986 Gross alpha 17.7 0.8 18.015.0 SC QC-W-18 Water Sep. 1986 Cs-134 34.715.6 31.3t5.0 8.7 Cs-137 51.117.0 43.318.0 8.7 QC-W-19 Water Sep. 1986 Sr-89 13.6t4.1 15.6t3.5 7.lb Sr-90 6.411.6 6.2*2.0 4.2b A-17
Table A-3. In-house spiked samples (continued) Concentration in pC1/1 Lab Sample Date TIML Result Known Expec ted Code Type Collected Analysis n=3 Ac tiv ity Precision > 1s, n=38 QC-W-21 Water Oct.1986 Co-60 19.222.2 18.St3.0 8.7 Cs-134 31.7 5.2 25.6t8.0 8.7 Cs 137 23.821.0 21.615.0 8.7 QC-MI-11 Milk Oct 1986 Sr-89 12.321.8 14.3t3.0 8.7 QC-W-20 Water Nov.1986 H-3 3855t180 3960t350 5206 QC-W-22 Water Dec. 1986 Gross alpha 9.811.4 11.214.0 8.7 Gross beta 21.7t2.0 23.8t5.0 8.7 QC-W-23 Water Jan. 1987 I-131 29.822.5 27.9t3.0 10.4 QC-MI-12 Milk Jan. 1987 I-131 36.5tl.3 32.6t5.0 10.4 Cs-137 32.6t4.2 27.4t8.0 8.7 SPM-13 Milk Jan 1987 Sr-89 10.4t2.1 12.214.0 8.7 Sr-90 14.6tl.6 12.6t3.0 5.2 1-131 49.5tl.2 54. 9t8.0 10.4 Cs-134 <1.6 0.0 8.7 Cs-137 33.3t0.6 27.418.0 8.7 SPW-24 Water Mar 1987 Sr-89 24.713.6 25.9i5.0 8.7 Sr-90 23.9i3.8 22.8t8.0 5.2 SPW-25 Watcr Apr 1987 I-131 28.0tl.9 29.315.0 10.6 SPM-14 Milk Apr 1987 I-131 25.0t2.2 23.9t5.0 10.4 Cs-134 <2.1 0.0 8.7 Cs-137 34.212.0 27.217.0 8.7 Water Jun 1987 H-3 34221100 33621300 520 SPW-26 Co-60 24.8tl.4 26.St7.0 8.7 Cs-134 <2.0 0.0 8.7 Cs-137 21.210.5 21.6t7.0 8.7 SPW-27 Water Jun 1987 Gr. alpha 8.511.9 10.li4.0 8.7 Gr. beta 22.6tl.9 21.225.0 8.7 SPW-28 Water Jun 1987 Gr. alpha 8.7tl.3 10.114.0 8.7 Gr. beta 12.215.2 9.4t3.0 8.7 A-18
f- O . Table A-3. In-house _ spiked samples (continued) Concentration in pCi/l Lab Sample Date TIML Result Known Expec ted Code Type Collec ted .inalysi s n=3 Ac tiv ity Precision 15, n=3a SPW-29 Water Jun 1987 Gr. alpha 16.4tl.3 18.925.0 8.7 ' Gr. beta 15.9t4.0 11.814.0 8.7 i SPM-15 Milk Jul 1987 Sr-89 19.4 1.6 18.8t3.5 5.2 I-131 43.5t0.7 45.3t7.0 10.4 , Cs-134 17.912.2 16.015.3 8.7 ' Cs-137 25.4tl.8 22.7t5.0 8.7 SPW-30 Water Sep 1987 Sr-89 17.St3.0 14.3i5.0 8.7 Sr-90 18.4t2.2 17.522.2 5.2 SPW-31 Water Oct 1987 -H-3 2053t93 2059t306 520
~
4 n=3 unless noted otherwise. b n=2. c n=1. i r I 5 l N i A-19 l
,4 .. .
Table A-4 In-house "blank" tarples. Concentration in pCi/1 icceptance I.ab Sample- Date Results Criteria Code Type Collec ted Analysis (4.66o) (4.66o) BL-1 0.1. Wa;er Nov. 1985 Gross alpha <0.1 <1 Gross beta <0.4 <4 BL-2 0.1. Water Nov. 1985 Cs-137 (gama) <1.9 <10 BL-3 0.I. Water Nov.1985 Sr-89 <0.5 <5 Sr-90 <0.6 <1 BL-5 0.I . k'ater Nov. 1985 Ra-226 <0.4 <1 Ra-228 <0.4 <1 SPW-2265 0.I. Water Apr. 1985 Gross alpha <0.6 <1 Gross beta <2.2 <4 Sr-89 <0.2 <5 Sr-90 <0.4 <1 1-131 .
<0.2 <1 Cs-137 (gama) <7.4 <10 BL-6 0.I. Water Apr. 1986 Gross alpha <0.4 <1 BL-7 0.I. Water Apr. 1986 Gross alpha <0.4 <1 BL-8 0 I. Water June 1986 Gross alpha <0.4 <1 BL-9 0.I. Water June 1986 Gross alpha <0.3 <1 SPW-3185 0.I. Water Jan 1987 Ra-226 <0.1 <1 ,
Ra-228 <0.9 <1 SPS-3292 Milk Jan 1987 I-131 <0.1 <1 Cs-134 <6.2 <10 Cs-137 <6.4 <10 SPW-3554 D.I., Water Feb 1987 H-3 <180 <300 Gross beta <2.6 <4 SPS-3555 Milk Feb 1987 Sr-89 <0.6 <5 Sr-90 1.910.4a <1 SPS-3731 Milk Mar 1987 Cs-134 <2.2 <10 . Cs-137 <2.5 <10 [ a tow 1,ye) (1 4 pCi/1) of Sr-90 concentration in milk is not unusual. I j A-20 ;
~
4 .. .
-Table A-4. In-house "blank
- samples (continued).
Concentration in pCi/l Acceptance Lab Sample Date Results Criteria Code Type Collec ted Analysis (4.66o ) (4.66a ) SPS-3732 0.I. Water Mar 1987 Sr-69 <0.9 <5 Sr-90 <0.8 <1 1-131 <0.3 <1 Co-60 <2.3 <10 Cs-134(G) <2.2 <10 Cs-137(G) <2.4 <10 Ra-226 <0.) <1 Ra-228 <1.0 <1 Np-237 <0.04 <1 Th-230 <0.05 <0.1 Th-232 <0.02 <0.1 U-234 <0.05 <0.1 U-235 <0.03 <0.1 V-238 <0.03 <0.1 SPS-4023 Milk May 1987 7-131 <0.1 <1 SPS-4203 0.1. Water May 1987 Gross alpha <0.7 <1 4 Gross beta < 1. .' <4 SPS-4204 3 Milk May 1987 Sr-89 <0.5 <S Sr-90 2.410.6a <1 SPS-4390 Milk Jun 1987 Cs-134 <4.7 <10 Cs-137 <5.2 <10 SPS-4391 0.I. Water Jun 1987 Sr-89 <0.4 <5 Sr-90 <0.4 <1 1-121 <0.1 <1 Co-60 <3.8 <10 Cs-137 <5.7 <1's Ra-226 <0.1 'l Ra-228 <0.9 <1 SPW-4627 0.1. Water Aug 1987 Gross alpha <0.6 <1 Gross beta <1.4 <4 Tritium <150 SPS-4628 Milk Aug 1987 Sr-89 <0.6 <5 Sr-90 2.4A0.6 <1 SPS-4847 Milk Sep 1987 Cs-134 <4.4 <10 Cs-137 <5.3 <10 a low level (1 - 4 pCi/1) of Sr-90 concentration in milk is not unusual. A-21
1 . Table A-4 In-house "blank" sa ples (continu;d) . Concentration in pCi/1 tcceptance Lab Sample Date Results Criteria Code Type Collected Analysis (4.66o) (4.66o) SPS-4848 0.I. Water Sep 1987 I-131 <0.2 <1 ; SPW-4849 0.I. Water Sep 1987 Co-60 <4.1 <10 Cs-134 <4.8 <10 Cs-137 <4.0 <10 Sr-89 <0.7 <5 Sr-90 <0.7 <1 SPW-4850 D.I. Water Sep 1987 Th-228 <0.04 <1 Th-232 <0.8 <1 U-234 <0.03 <1 : U-235 <0.03 <1 U-238 <0.02 <1 Am-241 <0.06 <1 Cm-242 <0.04 <1 Ra-226 <0.1 <1 2 Ra-228 <1.0 <2 , SPW-4859 0.I. Water Oct 1987 Fe-55 <0.5 <1 , SPS-5348 Milk Dec 1987 Cs-134 <2.3 <10 Cs-137 <2.5 <10 SPW-5384 Water Dec 1987 Co-60 <2.8 <10 i Cs-134 <2.6 <10 : Cs-137 <2.8 <10 I-131 <0.2 <1 Ra-226 <0.1 <1 ! Ra-228 <1.2 <2 I Sr-89 <0.5 <1 Sr-90 <0.4 <1 SPW-5385 Water Nov 1987 Gr. alpha <0.4 <1 , Gr. beta <2.2 <4 : Fe-55 <0.3 <1 ! SPS 5386 Milk Jan 1988 I-131 <0.1 <1 l SPW-5448 "Dead" Water lan 1988 H-3 <177 <300 i A-22
. -- ___. . . _ _ - _ . __ ._ _ . . _ . = - - _ _ _ - , _ _ _ _ _ - _ _ -
TIML.$ LINO-01 Revision 0, 12 29-86 ATTACHMENT B ACCEPTANCE CRITERIA FOR
- SPIKED" SMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa the Standard Deviation Analysis Level for Single Determination Gama Emitters 5 to 100 pCi/ liter or kg 5 pCi/ liter
>100 pCi/ liter or kg 5% of known value Strontium-89b 5 to 50 pCi/ liter or kg 5 pCi/ liter
>50 pCi/ liter or kg 10% of known value Strontium-90b 2 to 30 pCi/ liter or kg 3.0 pC1/ liter
>30 pCi/ liter of kg 10% of known value Potassium >0.1 g/ liter or kg 5% of known value Gross Alpha <20 pCi/ liter 5 pCi/ liter
>20 pCi/ liter 25% of known value Gross Beta <100 pCi/ liter 5 pCi/ liter
>100 pCi/ liter 5% of known value Tritium <4,000 pCi/ liter is=(pCi/ liter)=
169.85 x (known).0933
>4,000 pCi/ liter 10% of known value Radium-226, <0.1 pC1/ liter 15% of known value Radium-228 Plutonium 0.1 pCi/ liter, gram, 10% of known value or sample Iodine-131, b <55 pCi/ liter 6 pCi/ liter Iodine-129 >55 pCi/ liter 10% of known value Uranium-238, <35 pCi/ liter 6 pCi/ liter Nickel-630, >35 pCi/ liter 15% of known value Technetium-99b ,
Iron-55b 50 to 100 pCi/ liter 10 pCi/ liter 10% of known value a From EPA publication, "Environmental Radioactivity Laboratory Intercompari-son Studies Program, Fiscal Year 1981-1982. EPA-600/4 81-004. b TIML lirait. A-23 I
o B
+
Appendix 8 Data Reporting Conventions B-1
s . -s Data Reporting Conventions 1.0. All activities,except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period. 2.0. Single Measurements Each single measurement is reported as follows: xis where x = value of the measurement; 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 where L = is the lower limit of detection based on 4.66a uncertainty for a background sample, 3.0. Duplicate Analyses 3.1. Individual result,s,: x1 i s1 x2
- 52 Reported result: xis wherex=(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: xis
<L Reported result: x i s if x > L;
<L otherwise 4
B-2 l
4 . . 4.0. Computation of Averages 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 . deviation (s) of a set of n numbers x1, x2, . . . xn are defined as follows: x= hex s=kEI***)2 n-1 4.2 Values below the highest lower 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 LLO, the highest LLO 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 reported. 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, and the retained 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 retained is increased by one if 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. , 8-3 1
3 e' s Appendix C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas C-1
Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas.a Air Water Gross alpha 3 pCi/m3 Strontium-89 3,000 pCi/1 Gross beta 100 pCi/m3 Strontium-90 300 pCi/1 Iodine-131b 0.14 pCi/m3 Cesium-137 20,000 pCi/1 Barium-140 20,000 pCi/1 Iodine-131 300 pC1/1 Potassium-40c 3,000 pCi/1 Gross alpha 30 pCi/1 Gross beta 100 pC1/1 Tritium 3 x 106 pCi/1 a Taken from Code of Federal Regulations Title 10 Part 20. Table II and appro-priate footnotes. Concentrations may be averaged over a period not greater ' than one year. b From 10 CFR 20 but adjusted by a f actor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway. C A natural radionuclide. 1 T i C-2
- _ _ _ _ _ _ _ - _ _ _ _}}