ML20199L660
| ML20199L660 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 03/17/1986 |
| From: | Huebner L TELEDYNE ISOTOPES |
| To: | |
| Shared Package | |
| ML20199L594 | List: |
| References | |
| NUDOCS 8604100416 | |
| Download: ML20199L660 (52) | |
Text
. __ . . ._ __ _
1 i .
f PRAIRIEISLAND NUCLE'AR GENERATING PLANT Red Wing, Minnesota UNITS 1 AND 2 f
aslMME APOLil e 17. PAUL
"'A'i ..!" * *. ,
AN!4UAL REPORT I
to the UNITED STATES NUCLEAR REGULATORY C0 m!SS!0N Radiation Environmental Monitoring Program January 1, 1985 thru December 31, 1985 ;
, NORTHERN STATES POWER COMPANY MINNE APOLIS. MINNESOTA Nb0 So$ck 0$000f>an 14 P Dl4
TTELEDfNE ISOTOPES WlOWEST LASOAATORY 1500 FRONTAGE RD.
NORTHBROOK, IL 800624191 Q12) $644700 NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA
. PRAIRIE ISL AND NUCLEAR GENERATING PLANT 00cket 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 1,1985 to December 31, 1985 Prepared Under Contract by TELEDYNE ISOTOPES MIDWEST LABORATORY Project No. 8010 4
Approved by: I.
" f L. General G. Huebner Manager 17 March 1986
t i o
b PREFACE 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 Prairie Island Nuclear Generating Plant.
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.
O t
11
i >
TABLE OF CONTENTS Section. Pajpe Preface ........................... 11 List of Tables . . . . . . . . . . . . . . . . . . . . . . . . iv
1.0 INTRODUCTION
. . . . . . . . . . . . . . . . . . . . . . . . . 1 2.0
SUMMARY
........................... 2 3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) ...... 3 3.1 Program Design and Data Interpretation ......... 3 3.2 Program Description . . . . . . . . . . . . . . . . . . . 4
- 3. 3 Program Execution . . . . . . . . . . . . . . . . . . . . 6 3.4 Laboratory Procedures . . . . . . . . . . . . . . . . . .
. 6-3.5 Program Modifications . . . . . . . . . . . . . . . . . . 7 3.6 Land Use Census . . . . .. . . . . . . . . . . . . . . . . 7 4.0 RESULTS AND DISCUSSION . . . . . . . . . . . . . . . . . . . . .
8 4.1 Atmospheric Nuclear Detonations . . . . . . . . . . . . . 8 4.2 Program Findings .................... 8 5.0 TABLES . . . . . . . . . . . . . . . . . . . . . . . . .-. . . 12
6.0 REFERENCES
CITED . . . . . . . . . . . . . . . . . . . . . . . ~ 24 APPEN' DICES A- Interlaboratory Comparison Program Results . . . . . . . . . . A-1 B Data Reporting Conventions . . . . . . . . . . . . . . . . . . B-1 C Maximum Permissible Concentrations of Radio-activity in Air and Water Above Natural Background in Unrestricted Areas . . . . . . . . . . . . . . C-1 iii
- s ,
LIST OF TABLES
- g. Title .
M 5.1 Sample Collection and Analysis Program,1985 . . . . . . . . . 13
- 5. 2 Samp l i n g Loca ti o n s . . . . . . . . . . . . . . . . . . . . . .
15
- 5. 3 Missed Collections and Analyses,1985 ............ 16
- 5. 4 Environmental Radiological Monitoring Program Summary .... 17 In addition, the following tables are in the Appendices:
Appendix A A-1 Interlaboratory Comparison Program Results, 1982-1985,. . . . A-3 A-2 Interlaboratory Comparison Program Results (TLDs) ...... A-9 <
Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural ~ Background in unrestricted Areas . . . . . . . . . . . . . . . . . . . . . C-2 iv i: - _ __
, 3 l.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, 1985. This program raonitors 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,1986) 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.
e 1
+ -,e -- -
i i l I
- 2. 0 SLNMARY l
l 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 1985 are summarized and discussed.
' Program findings show background levels of radioactivity in the environmental sanples collected in the vicinity of the Prairie Island Nuclear Generating Plant.
No eff'act on the environment due to the operation of the plant is indicated.
e O
2
{ y e 3.0 RADIATION ENVIR0 MENTAL 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, sanples 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; i
(2) Fallout from atmospheric nuclear detonations; (3) Releases from nuclear power plants; and (4) Industrial and medical radioactive waste.
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 Praccie Island Plant which -is based on the
- indicator-control concept. Most types of sanples are collected both at L indicator. locations (nearby, downwind, or downstream) and at control
! locations (distant, upwind, .or upstream).. A plant effect would be
- indicated if- the radiation level at an indicator location was signif t-cantly larger than tut at the control location. The difference would have to be greater tnan could be accounted for by typical fluctuations in +
radiation levels arising from other sources.
p p An additional interpretive technique involves analyses for specific radionuclides present in the environmental saneles collected from the i_ plant site. The plant's monitoring program includes analyses for tritium L and iodine-131. Most samples are also analyzed for gamma-emitting ,
j isotopes with results for the following groups quantified: zirconium-95, l
cesium-137, cerium-144, beryllium-7, and potassium-40. The first three j . gamma-emitting isotopes were selected as radiological impact indicators 3
i- .
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 dcys af ter 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 igact indicators.
1 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 atmospharic 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 egloyed 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.
l 3. 2 Program Description The sampling'and analysis schedule for the environmental radiation l monitoring program at Prairie Island is sunrnarized 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, i detailed sag ling procedures have been prescribed (Teledyne Isotopes l Midwest Laboratory, 1985).
l To monitor the air environment, airborne particulates are collected on menbrane filters by continuous puging 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 -
l culate filters are analyzed for gross beta activity and charcoal filters for iodine-131. A monthly cogosite of all particulate filters is gamma-l 4
l -
y ,
4 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 (highes t 0/Q residence).
As a " Lessons Learned" commitment, ambient gama radiation is moni-tored 'at thirty-two (32) locations, using three (3) LiF2 chips at cach location: ten (10) in an inner ring in the general area of the site boundary, fif teen (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 sagles are collected monthly from five farms (four indicator and onecontrol). 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 gama-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 the highest 0/Q garden and a control location (P-25) and analyzed for iodine-131. Corn is collected annually from the highest 0/Q corn field and a control location (P-25) and analyzed for gamma-emitting isotopes. Also, well water is collected quarterly from four locations and analyzed for tritium and gama-emitting isotopes.
l t
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. QJarterly cogo-sites are analyzed for tritium. .
Drinking u ter ir collected weekly from the City of Red Wing well.
Monthly cogosites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes. Quarterly composites are analyzed for tritium.
The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, periphyton or invertebrates, and bottom sediments. Shoreline sediment is collected semi-annually f rom one location. All samles are analyzed for gama-emitting isotopes. ,
5 t
i .
- 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 1985 for Locations P-108 and P-148, the third quarter TLD data for Location P-025, and the fourth quarter TLD data for Location P-108 were not available uecause TLDs were lost in the field.
- 2. No air particulate datum was available from Location P-1 for the collection period ending .
02-11-85 because the sample was lost in the field.
- 3. No air particulate data were available from Locations P-1, P-2, P-3, P-4, and P-6 for the collection period ending 11-18-85 because the sanples were lost in shipment.
Deviations from the program are summarized in Table 5.3.
- 3. 4 Laboratory Procedures All iodine-131 analyses in milk were made by using a sensitive radio-chemical procedure which involves separation of the element by use of an ion-exchange resin and subsequent beta counting.
All ganrna-spectroscopic analyses were performed with a Ge or Ge(L1) detector. Levels of iodine-131 in cabbage were determined by Ge or Ge(Li) spectrometry. Levels cf airborne iodine-131 in charcoal samples were measured by Ge or Ge(Li) spectrometry.
Tritium levels were determined by liquid 3cintillation technique.
Analytical procedures used by the Teledyne Isotopes Midwest Laboratory are specified in detail elsewhere (reledyne 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 Commission (U. S. Atomic Energy Commission,1972).
6
i Teledyne Isotopes Midwes' 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 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 Early in the 1985 growing season a " Pasturing Dairy Animal Survey" revealed. that only one location, the Gustafson Farm (P-14), actually turned these animals into a pasture area for. any length of time. A decision was also made to collect biweekly milk samples from these animals if they were fed " freshly cut hay" taken from a field adjacent to the farm. This process could parallel the grazing concept for concentra-tion of radionuclides in the raw milk.
3.6 Land Use Census In accordance with Technical Specification 4.10, paragraph 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 producing fresh leafy vegetables in each of the 16 meteo-rological 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.
4 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 1985 Land Use Census was completed on July 19, 1985. This census did not identify any locations of exposure pathways different from those used in the program during the first seven months of the year. Milk and garden sample locations did not change due to the requirements of the land use census.
7
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 recomended by the Nuclear Regulatory Commission in Regulatory Guide 4.8. For each type of analysis of sach 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 1985. The last reported 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.
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 loca~ tion. The means ranged from 13.5 mR/91 days at inner ring locations to 14.3 mR/91 days at outer ring locations.
The mean at special locations was 13.4 mR/91 days and 15.3 mR/91 days at 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 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), and in 1984 (13.9 and 15.3 mR/91 days, respectively). No plant effect on ambient gama radiation was indicated.
8
Air Particulates The average annual gross beta activity in airborne particulates was nearly - identical at both indicator and control locations (0.024 pCi/m3 and 0.025 pCi/m3, respectively) and was about the same as fa 1982 (0.025 pCi/m3), in 1983 (0.024 pCi/m3), and in 1984 (0.026 pCi/m3). The highest averages for gross beta were for the months of February, July, November, and December and the fourth quarter.
The reason for the elevated activity in February, November, December and the fourth quarter is not clear. It probably is attributable to the increased use of wood burning stoves. The spring peak, which usually is observed in April - May (second quarter) was not observed in 1985. This peak has been observed almost annually (1976,1979,1980,1983, and 1984 were also exceptions) for many years (Wilson et al.,1969). The spring peak has been attributed to f allout 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 simulta-neously 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,1986). -
t Except for beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih, 1955), all other gamma-emitting isotopes were below their respective LLD levels. None of the activities detected were attributable to the Plant operation.
Airborne Iodine Airborne iodine-131 results were below the detection limit of 0.07 pCi/m3 in all samples. Thus, there was no indication of a Plant effect.
Milk Iodine-131 results were below the detection limit of 1.0 pCi/l in all samples.
Cesium-137 results were below the LLD level of 15 pCi/l in all samples.
Cesium-137 is a long-lived component (with a half-life of 30.24 years) of worldwide f allout and is found in the environment in trace quantities.
9
I l
.I i
No other gama-emitting isotopes, except potassium-40, were detected in any of the milk samles. This is consistent with the finding of the National Center for Radiological fiealth 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 1985 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/l in all samples. Iodine-131 activity was also below the LLD level at 1.0 pCi/l in all sagles. As with the other well water samples, all analyses for gama-emitting isotopes yielded results below detection limits. Gross beta averaged 7.1 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/l), 1983 (8.0 pCi/1), and 1984 (7.9 pCi/1).
9 River Water At the upstream and downstream collection sites, quarterly composite tritium levels were below the LLD level of 330 pCi/l in all samles.
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.
I i
l- $11 Water At the control well P-25, Kinneman Farm and three indicator wells (P-8, Kinney Store; P-10, Lock and Dam No. 3; and P-9, Plant Well No. 2) no tritium was detected above LLO level of 330 pCi/l in all samples but one.
The detected concentration was at the LLO level of 330 pCi/l in one sample from P-9, Plant Well No. 2.
I
- Gama-emitting isotope levels were below detection limits in all cases.
l l 10 .
l
.g'- ,
Crops Cabbage sagles were collected on September 9, 1985, and . analyzed for iodine-131. Corn sagles were also collected on September 9 and 23, 1985, 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 sagles were collected in May and September,1985. 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
'F Aquatic insects (invertebrates) and periphyton were collected on May 29, 1985. The samples were analyzed for gamma-emitting isotopes. All gamma-emitting isotopes, except for naturally-occuring potassium-40, were below their respective LLO's. No plant effect was indicated.
Bottom and Shoreline Sediments Sediment collections were made on May 20 and October 28, 1985. The sagles were analyzed for gamma-emitting isotopes. The only gama-
- . emitting isotope detected was naturally-occuring potassium-40. No plant effect was indicated. .
I h
5 e a 1
L
! 11
, e * .,-,__,,,,,,--.y .my,,...,.,-.,.,,,..,--...,,,9- - , - , . -
.e -, ,..-%..- ,,yy,.--p,,,.y7.- ,-.%,.__.,
1
. e e
O
- 5. 0 TABLES 9
12
Table 5.1 Sample Collection and Analysis Program, _1985. Prairie Island '-
Collection Analysis Locations' Type and Type _and Medium No. Codes (and Typeja Frequencyb Frequencyc:
i Ambient radiation 32 P-01A - P-10A C/Q Ambient gamma -
(TLDs) P-018 - P-158 P-015 - P-06S P-01C Airborne particulates 5 P-1(C), P-2, C/W G8, 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/Md I_131, ss E3 P-25(C), P 14 River water 2 P-5(C),P-6 G/W GS(MC), H-3(QC) ~
Drinking water 1 P-ll G/W G8(MC),I-131(MC)
Well water 4 P-25(C),P-6, G/Q H-3, GS 4
P-8, P-9 Edible cultivated 2 P-25(C),P-24 G/A I-131 crops - leafy green vegetables I
.=
Table 5.1. Sample Collection and Analysis Program,1985. Prairie Island Collection Analysis -
Locations Type and Type and Medium No. Codes (and Type)a Frequencyb Frequencyc 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 invertebrates Bottom sediment 2 P-5(C),P-6 G/SA GS
- Shoreline sediment 1 P-12 G/SA GS a
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 C
as follows: W = weekly, M = renthly, Q = quarterly, SA = semi-annually, A = annually.
Analysis type is coded as follows: G8 = gross beta, GS = gamma spectroscopy, H-3 = tritium, I-131 =
d iodine 131. Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly composite.
Milk is collected biweekly during the grazing season (May - November) if milch animals are on pasture.
e
o--
f, ,
Table 5.2 Sampling locations. Prairie Island Code Typea Name Location P-1 C Air Station P-1 16.5 mi 9 348*/NNW P-2 Air Station P-2 0.5 mi 9 294*/WNW P-3 Air Station P-3 0.8 mi 9 313*/NW P-4 Air Station P-4 0.4 mi 9 359*/N P-5 C Upstream of Plant 0.6 mi 9 60*/ENE P-6 Lock & Dam #3 & Air Station P-6 1.6 mi 9 129*/SE P-8 Kinney Store 2.0 mi 9 280*/W P-9 Plant Well #2 0.3 mi 9 306*/NW P-11 City of Red Wing 7.1 mi 9 135*/SE P-12 Recreational Area 3.4 mi 9 116*/ESE P-14 Gustaftm Farm 2.2 mi 0 168*/SSE P-16 Joh1LM Farm 2.6 mi 9 39*/NE P-17 l' late hm 3.5 mi 9 25*/NNE P-18 Chr:s M a en Farm 3.7 mi 9 181*/S P-20 HQnett D/Q Corn Field
- P-24 HigMn % 4 Garden
- P-25 C Kinneno f crm 11.1 mi 9 331*/NNW P-01A Proparty Line 0.4 mi 9 359*/N P-02A Property Line 0.3 mi @ 19*/NNE P-03A Property Line 0.5 mi 9 183*/S P-04A Property Line 0.4 mi 9 204*/SSW P-05A Property Line 0.4 mi 9 225*/SW P-06A Property Line 0.4 mi 9 249*/WSW P-07A Property Line 0.4 mi 9 268*/W P-08A Property Line 0.4 mi 9 291*/NNW P-09A Property Line 0.7 mi 9 317*/NW P-10A Property Line 0.5 mi 9 333*/NNW P-01B Thomas Killian Residence 4.7 mi 9 355*/N P-028 .Roy Kinneman Farm 4.8 mi 9 17*/NNE P-038 Wayne Anderson Farm 4.9 mi 9 46*/NE P-048 Nelson Drive (Road) 4.2 mi 9 61*/ENE P-058 County Road E and Coulee 4.1 mi 9 97*/E P-068 William Houschildt Residence 4.4 mi 9 112*/ESE P-078 Red Wing Service Center 4.7 mi 9 140*/SE P-088 David Wnuk Residence 4.1 mi 9165*/SSE P-098 Highway 19 South 4.2 mi 0 187*/S P-108 Cannondale Farm 4.9 mi 9 200*/SSW P-118 Wallace Weberg Farm 4.5 mi 9 221*/SW P-128 Roy Gergen Farm 4.5 mi 9 247*/WSW P-138 '
Thomas O'Rourke Farm 4.4 mi 9 270*/W P-148 David J. Anderson Farm 4.9 mi 9 306*/NW P-158 Holst Farms 4.2 mi 9 347*/NNW P-01S Federal Lock & Dam #3 1.6 mi 9 129*/SE P-02S Charles Suter Residence 0.6 mi 9 158*/SSE P-03S Carl Gustafson Farm 2.2 mi 0 168*/SSE P-045 Richard Burt Residence 2.0 mi 9 228*/SW P-05S Kenney Store 2.0 mi 9 270*/W P-06S Earl Flynn Farm 2.5 mi 9 299*/WNW '
P-01C Robert Kinnemen Farm 11.1 mi 9 331*/NNW
- "C" denotes control location. All other locations are indicators.
- These locations are not determined until after the Land Use Census is completed.
15 l
TABLE 5.2 I
i FRAIR!E 15LANO NUCLEAR GENERAT!NG :LANT !
RACIAT!CN ENVIRO N M ENTAL MONITOR!NG FROGRAM g
.vem
( 5_ _ -
L M- '
~
N b
, IPRE3CCTT -
g i .
p *
+
~h s
.' ; no ,
s gn
' ~
- _i
- e. *
. , l, !
\ +,f so f \ s e at / I 4' .N m
- E
( a ,s .
s., m)
_. /a w;
.- .,- il
,, s , m d
\sN kM
- 4 6 E.-tI '
4
$\ h e- DIAMCW C" E .- 8 4 meery g -
il 4 6 2, ti f,, !!
a 5; c'- .F is 9
.
- IO iI E w A:-- - s,w' $'
a * . ,
V A ';9t-GER
.I ,
7%s '\s' < . N;.T'r
^
y !
i!
R
"' WD *H M&N s -.. -
d ---
'N.
lj
/ # ;: R II @h ,._, K l .sy _
hREC WINGG c r,. ~/ D J )
l- -
.~ s s' ". - - - - -
- [
SI Su I i:
28 m .
9 -
g 9 Note: !!ap numbers correspond to
-- g.--VASA 4' ,# code numbers without the
\ prefix P -
r/
O ! 2 3 4 5 6 7 c 10 E. . .
SCALE IN MILIS .
15a
O O 8 ~
.3 '
s><EliP!,ne N s
~
e,
/
-m 4%
N
' JQ,
--- - i
- g .
I ,,
S 3_)
uns g, i (A =/ de scou e
~
~ ~>d'-FI"'"
'Phe =u gjo i
g cd st y, s J -- .a f
un g .
y
= -
y ,
y (oTiglygypg -
y 2
l t.I M
ge nanwa 9'
- g. Ol%D e g ( c' Gl l I
n 3
- '[E ig p3 /,$_ \
'I O
~
' yI
-n~
O y ch 16 -. p 10wi as Ra x=E fi s~ Syn y6E j a- \ E\
Ak @ \ LEGENO "e
/
? ,"
e g l> .i". a o-i
,Jo- A,.
i .
- m*
TABLE 5.2 NOR II?lf 33 33 N N G*
pyAm ISwm NUC*7G. GL'I?AS" ?W~
4 - 5 F.ile Ring. Con:::1, and Special
- *- *7 I- In:arasc C Inca:i::s
- c::. se,,' n
[. :: : u . ..
. .e ,, m.* . -
-~
.; ;)
m l O,'j y
'o, I
,s ' -
s
+. :::,
.'{ . . . . .~ . b,, , ar .
l
?s's.'4 4
~ .... ~- % ,
./ [
) ,l ' ..* .-~ . .:-
,.J '
- =. -
- 3 J 4 ,-'
g/ . .
Mad
.' ' gEs %
' !, 4 '
,, N
.] / .?
hf.
=. p 'MiA*
L ,M N r;L; J , A. vi i.,
1
- I
-( %-:%-(g ,- .
i '
n tI -}l ~ b/.\ h. .;'.-.
,o. - - l .
% ,r/*
l I '
- i %.
- 0 Q.f .
i ,, / -
N-PI , ~.t % xe l j@ l G ,3,% * ;!/ii:. .
i +
/.
'. h. .-
2 e.
I' ,,.
.Ut_ . .(h.'
'\h v'*3..,- N, km .
dd.i--/
. N 4, n
a
?I s , A. - 2 .
3 ._
l 34
,,,M, . N, .
g t( 2.. . _i N* f [{qg?\O '
Qq % s e .,, h; l C-. 7 P, , N's$
, s .,
s .;r )N gW. t'.-
< "M u ,n. . , -
.n.
"-+.'-+
itis , ,
9 i, n.. ,2
.; g. DF '
Y Ut k f' j
n-m/i ~ r..:
= . ... .
Q. . l ~
. m .,. . %. . .* ,,
aQ.. v .2 pr.I; k
<b) f.g e6v y r & 2'1 >-
P ,-
V.m h,..,w.';::k, N . .~
A A ._.Y&% l'I-%&
y
- " 4
..i.:.-
e.h
. . . .e- .- R e
.g Q& hos z.=s;o* -
f- dlO.y :- :--aff
'A--a - (Cy( ~p. f
~ v
. ~= y g e %f' \ -
l~ F~ -
\ .--
4 ', f f
///
VNf . I 'c s,
'k ~ . i l ;1g3 qf;1k, rM)f'.'$
. 5us w g.
{ ..v ! -- ' r
!^ 1Pi
% 'l Hote: IIap numbers correspond to I 1, 4 % W ' j j"'"** I ,
f code numbers uithout the l
'3 ~('i w. l*~~l
- j - c,T Prefix P -
o, 1 2 3 4 5 6 7 E 9 10 scis.I.I I::.m rz 15e .
. C- .
L
-Table 5.3' Missed collections and analyses,1985. Prairie Island Nuclear Generating Plant. All required samples were collected and analyzed as' scheduled except the following.
Collection Date Sample Analysis Location or Period Comments Thermoluminescent -Ambient P-108 1st Qtr. 1985 Lost in the Dosimeters (TLDs) _ Radiation f.iel d.
P-148 1st Qtr. 1985' Lost in the
' fi el d.
P-02S 3rd Qtr.1985 Lost in the-field.
P-108 4th Qtr. 1985 Lost in the-field.
Air Particulate Gross Beta P-1 02-11-85 Lost in the field.
P-1 11-18-85 Lost in shipment.
P-2 11-18-85 Lost in .
shipment.
P-3 11-18-85 Lost in shipment.
P-4 11-18-85 Lost in shipment.
P-6 18-85 Lost in shipment.
f 16
p ..
Table 5.4. Environmental Radiological Monitoring Program Summary. .
Name of Facility Prairie Island Nuclear Generating Plant Docket No. 50-282. 50-306 Location of Facility Goodhue. Minnesota Reporting Period January - December 1985 (County, State)
Indicator Location with Highest Control
' Sample Type and Locations Annual Mean Locations Number of Type Number of Mean (F)C Mean (F) Mean (F) Non-routine (Units) Analysesa LLDb RangeC Locationd Range Range Resultse TLD Ganna 40 3.0 13.5 (40/40) P-OlA, Property Line 14.8 (4/4) (See control 0 (mR/91 days) (12.0-21.6) 0.4 al 9 359*/N (12.0-21.6)
(Inner Ring, below)
General Area at
- Site Boundary)
TLD Gamma 57 3.0 14.J (57/57) P-028, Roy Kinneman 16.2 (4/4) (See control 0 (mR/91 days) (7.7-20.6) Farm (13.4-20.6)
(Outer ring, below) 4.8 at # 17*/NNE 4-5 miles distant)
" TLD Gamma 23 3.0 13.4 (23/23) P-035, C. Gustafson 15.8 (4/4) (See control 0 (mR/91 days) (6.9-19.0) Farm (12.6-19.0)
(Special below) 2.2 al 9 168*/55E Interest Areas)
TLD Ganna 4 3.0 None P-01C, R. Kinnesan 15.3 (4/4) 15.3 (4/4) 0 (mR/91 days) Farm (12.8-19.1) (12.8-19.1)
(control) 11.1 al 9 331*/NW Airborne G8 254 0.002 0.024 (204/204) P-6, Station P-6 0.026 (51/51)
Particulates 0.025 (50/50) O (0.006-0.102) 1.6 at W 129'/SE (0.010-0.102) (0.013-0.108)
(pC1/m3)
G5 20 8e-7 0.022 0.073 (10/16) P-3. Station P-3 0.076 (4/4) 0.072 (3/4) 0 (0.059-0.095) 0.8 at # 313*/NW (0.059-0.095) (0.062-0.089)
Mn-54 0.0017 (LLO - - (LLD 0 Co-58 0.0024 (LLD - - <tLD 0 Co-60 0.0020 (LLD - - (LLD 0 Zn-65 0.0037 (LLD - - (LLD 0 Zr-Mb-95 0.0042 (LLD - - <LLD 0
, a.
Table 5.4. Environmental Radiological Monitoring Program Summary (continued) hane of Facility Prairie Island IIuclear Generating Plant . Docket No. 50-282. 50-306 Location of Facility Goodhue. Minnesota Reporting Period January - Deceaner 1986 (County, State)
Indicator Location with Highest Control Sample Type and Locations Annual Mean -Locations Nunter of-Type IIueber of Mean (F)c Mean (F) Mean (F) Non-routine.-
(Units) Analysesa Ltob gang.c Locationa Range' Range Results*
Airborne Ru-103 0.0099 (LLD - -
(LLu o Particulates (pct /m3) Ru-106 0.012 (LLD - -
<LLD 0 (cont'd)
Cs-134 0.0014 (LLD - -
(LLD 0 Ba-La-140 0.087 (LLD - - -
(LLU 0 E Ce-141 0.0038 <tLD -
- <LLD u Ce-144 0.0058 (LLD - -
(LLO O -
Airborne 'l-131 254 0.07 (LLD - -
(LLO O todine -
(pC1/m3)
Mtik lI-131 66 1.0 (LLD - -
(LLU u (pCl/I)
GS 66
. K-40 100 1340 (54/54) P-14, Gustafson 1300 (18/18) 1350 (12/12) 0 (1170-1600) Farm (1200-1600) (1170-1510)
- 2.2 at # 168*/SSE
- Cs-134 15 (LLD - -
<LLU 0 ,
J ,
P
Table 5.4 Environmental Radlelogical Monitoring Program Samary (continuse) mane of Facility Prairie Island nuclear Generatine Plant ' Docket me. '50-282. W-30b Location of Factitty- Goodhue. Minnesote' Asperting Perled January - December 19u5 (County, State)
Indicator ; Location with Nighest Control Sample Type and Locattens Annual Mean ' Locattens- Nunser of.
Type number of Mean (F)C' Nean (F) Mean (F) non-routine (Units) Analysesa LLDb RangeC Locattend Range Range. Results'.
Drinking Water G8 12 1.0 7.1 (12/12) P-11, City of Red 7.1 (12/12) None 0 (pCl/1) (5.0-9.0) Wing (5.0-9.0) 7.1 al 9 135'/SE I-131 12 1.0 RLD . - -
None 0 H-3 4 330 (LLD - - None O GS' 12 Mn-54 15 RLD - -
None 0 .
g Fe-59 30 RLD - .
None -
0 Co-58 15 (LLD .
- None O Co-60 15 (LLO - - None 0 Zn-65 30 ' RLp - .
None 0
~
Zr-Nb-95 15 (LLO - -
None O Cs-134 10 (LLO - -
none o Cs-137 10 RLD - - none 0 Ba-La-140 'S <tLD - -
none O Ce-144 69 RLS - -
none O River Water H-3 8 330 (LLD .- - <LLO O (PCl/l) !
GS 24 .
fei-54 15 (LLD - - 8 (LL0 . ! O re-53 I-
~
15 (LLO - -
(LLD. O
\ ~
Table 5.4. ' Environmental Radiological Monitoring Program Sismary (continued)
Name of Facility Pralrie IsIand leucleer Generatlas P1 ant Decket flo. 50-2412. 50-306 Location of Facility Goomue. Minnesota steporting Period January - December 1985 (County. State)
Indidator Location with Highest Control ,
sample Type and Locations Annual Mean Locations iluster of Type pluster of Mean (F)C flean (F) flean (F) Non-routine (Units) Analysesa LLDb gangec Locationd Range Range Resultse River Water Cs-134 15 <LLD - - <LLO O (pCl/1)
(LLD 0 (continued) Cs-137 18 (LLD - -
Sa-La-140 15 (LLD '
- - (LLU U Ce-144 71 <LLD - - (LLu 0 Well Water M-3 16 330 330(1/12) P-9 Plant Well #2 330 (1/4) <ttu o (ptt/I) 0.3 al 9 306*/NW o GS 16 Mn-54 15' <LLD - - (LLD u Fe-59 30 (LLD - - <LLD 0 Co-58 15 (LLD - - <LLD u Co-60 15 (LLD - - <LLD 0 Zn-65 30 <tLD - - <tLU 0-Zr-Nb-95 15 (LLD - - (LLO O Csil34 10 ' <LLD - - (LLD 0 Cs-137 10 (LLD ,
- - <LLD 0 Ba-La-140 15 (LLD - - . (LLD 0 Ce-144 54 <tLD - - <LLu u a
Crops-Cabbage I-131 2 0.022 (LLD . . - (LLD 0~ ,
(pCl/g met)
Table 5.4 Environmental Radiological Monitoring Program 5.assary (continued)'
name of Facility Prairie Island nuclear Generating Plant Docket No. 50-282. 50-306 Location of Facility Gcedhue, Minnesota Reporting Perios January - Decemoer 1985 (County, State) g Indicator Location with Highest Control Sample Type and Locations Annual mean Locations. Nunner of Type number of Mean (F)C Mean (F) Mean (F) Non-routine (Units) Ar.alysese LLDb RangeC Locationd Range Range Results' Crops-Corn 65 3 Se-7 0.14 (LLD - -
<Ltu O l
K-40 0.5 1.98(2/2) Suter Fare 2.17 (1/1) 2.10 (1/1) 0 (1.79-2.17) 0.6 at # 158*/SSE - -
Mn-54 0.018 <LLD - -
<LLu O Co-58 0.020 (LLD - -
<LLD 0 Co 60 0.018 <tLD - - (LLD u y 2n-65 0.045 (LLD -
w
<LLD 0 Zr-Nb-95 0.019 <LLD -
(LLD 0
Ru-103 0.016 (LLO - -
<LLD 0 Ru-106 0.14 (LLD - - (LLu O Cs-134 0.019 <LLD - -
<LLD 0 Cs-137 0.019 <tLD - - (LLD 0 Ba-La-143 0.028 <tLD - -
<LLO O.
Ce-141 0.017 (LLD - -
<LLO O Ce-144 0.064 (LLD --
<Ltu o
I Fis% - Flesh GS 4 K-40 0.1 5.20 (2/2) P-6, Lock & Das #3 5.20 (2/2) 2.91 (2/2) 0 (3.52-6.88) 1.6 mi y 129*/5E (3.52-b.88) (2.56-3.26) h 54 0.041 (LLD - -
(LLU O Fe-59 0.59 <LLO - -
(LLO O Co-58 0.099 <tLD - -
<LLD u
o A
Table 5.4. Environmental Radiological Monitoring Program Summary (continued) <*
Name of Facility - Prairie Island Nuclear Generating Plant Docket No. 50-282. 50-306 Location of Factitty Goodhue Minnesota Reporting Period January - December 1985 (County, State)
Indicator Location with Highest Contrcl Sample Type and . Locations Annual Mear. Locations Number of Type Number of Mean (F)C Mean (F) Mean (F) Non-routine (Units) Analysesa LLDb RangeC Locationd Ra.ege Range Resultse Fish - Flesh GS 5 k! $nNf3 Zn-65 0.12 (LLD - -
(LLD u Zr-Nb-95 0.11 <LLD - -
<LLU 0 Cs-134 0.040 (LLD - -
<tLO O Ba-La-140 0.026 <LLD - -
<tLD 0 m Invertebrates GS 2 N (pCl/g wet)
Be-7 1.11 <tLD - -
(LLO O K-40 1.0 2.14 (1/1) P-5, Upstream of 6.87 (1/1) 6.87 (1/1) 0 Plant - -
0.6 at tP 60'/ENE m-54 0.041 (LLD - - <LLD 0 Co-58 0.u99 <LLD - -
<LLD u
~
Co-60 0.047 <LLD - -
(LLO O Zn-65 0.12 (LLD - -
<LLD o Zr-Nb-95 0.11 (LLD - - (LLD u Ra-103 0.19 (LLD - -
(LLO u Ru-106 0.38 <LLD - - <LLp u Cs-134 0.040 (LLD - -
<LLD 0 8a-La-140 0.033 <LLD - - (LLU 0 Ce-141 0.42 (LLD - -
<LLD U Ce-144 0.20 (LLD - -
<tLD 0
4"
, s i t
t Table 5.4 Environmental Radiological rionitoring Program Summary (continued)' '
.-Name of Factitty ~ Prairie Island Nuclear Generating Plant Docket No. 50-282. W 306 Location of Facility Goodhue.-Minnesota Reporting Period . January - December 1985 (County, State)' -
Indicator ~ Location with filghest Control-Sample Type and Locations Annual Mean Locations . hunter of -
, Type Number of Mean (F)c Mean (F) Mean (F) Non-routine
, (Units) Analysesa LLDb RangeC Locatland Range ' Range Nesultse i Bottom and G5 '6 ,
I Shoreline -
Sediments Be-7 0.53 (LLD , -- - (LLD 0 I (pCl/g dry) 4 K-40 1.0 8.67 (4/4) P-5(C), upstream 10.20 (2/2) ,10.20 (2/2) 0
- (7.64-9.84) .of Plant (9.78-10.63) (9.78-10.63) a n. 0.6 al 9 60*/ENE I
m-54 0.028 <LLD - - (LLD 0 i C -58 0.055 (LLD - -
(LLD 0 l ro ca 4 0.025 <tLD - -
(LLD 0 i w ,
Zn-65 0.069 (LLD - -
<LLD 0
- Zr-Ifb-65 0.21 (LLD - -
<LLD 0
- Ru-103 0.12 (LLD - -
<LLu u Ru-106 0.21 -(LLD - - '<LLD 0 I' Cs-134 0.029 (LLD - -
<LLD u Cs-137 0.026l (LLD - - (LLO O i
Ba-La-140 0.085 <tLD - - (LLD 0 Ce-141 0.33 (
,LLD - - <LLD 0 ,
Ce-144 0.18 <LLO - -
(LLO O v
8 G8 = Gross beta; GS = gamma scan. .
c LLD = Nominal lower limit of detection based on 4.66 slyna error for backgroune sample.
Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated d
in parentheses (F). .
- Locations are specified (1) by name and code (Table 2) and (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.
-l d
^
a.C :- - l I
- 6. 0 REFERENCES CITED 1
Arnold, J. R. and H. A. Al-Salih. 1955. Beryl ? ium-7 . Produced l 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 Natu-rally Occuring Raaionuclides 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 1978.
. 1979b. Radiation Environmental Monitoring for Monticello Island Nuclear Generating Plant, Complete Analysis Data Tables, January -
December 1978. .
. 1980a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January -
December 1979. -
. 1980b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables,. Janauary _
- December 1979.
. 1981a. Radiation Environmental -Monitoring for Monticello
- Nuclear Generating Plant, Complete Analysis Data Tables, . January-December
-1980.
. 1981b. Radiation Environmental Monitoring for Prarie Island
~
Nuclear Generating Plant, Complete Analysis Data Tables, ~ January -
December 1980.
- . 1982a. Radiation Environmental Monitoring for Monticel'lo 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 Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - '
. December 1982. ,
24 s* - - . _ . , . -%w - - , , . .,.m- -
,-em,.---,,-._,e- m,--,. - --. , --. .,_-,.,- ,. -
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 Comission, 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 Comission, 41anuary 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 Comission, January 1,1981 to December 31,1981 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.
. 1983. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Comission, 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, January 1,1983 to December 31,1983 (prepared by Teledyne Isotopes Midwest Laboratory). Minneapolis, hinnesota.
. 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 Laboratory). Minneapolis, Minnesota.
Teledyne Isotopes Midwest Laboratory. 1971a. .Quali ty Control Program,
- - Revision 7. 20, November 1984.
. 1985. Quality Control Procedures Manual, Revision 6, 09 August 1985.
. 1985. QJality 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 1963.
25
l n-l
~
. 1984b. . Radiation Environmental 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 -
- l. December 1984.-
1 . 1986a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analyses Data Tables, January -
I December 1985.
. 1986b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analyses Data Tables, January -
' December 1985.
. 1985. Sanpling Procedures, Prairie Island Nuclear Generating Plant, Revision 14,15 December 1985.
U. S. Atomic Energy Comission. 1972. HASL Procedures Manual, Health and Safety Laboratory, New York, NY.,- 10014.
U. S. Public Health Service. 1967. Radioassay Procedures for Environmental
- Samples, National Center for Radiological Health, Rockville, Maryland.
(Public Health Service Publication No. 999-RH-27).
Wilson, D. W. , G. M. Ward and J. E. Johnson. 1969. In Environmental Contam-
, ination by Radioactive Materials, International Atomic Energy Agency.
- p. 125.
k i
26 l
. a Appendix A Interlaboratory Comparison Program Results L.
A-1
'i t .
Appendix A Interlaboratory 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.
4 The results in Table A-1 were obtained through participation in the environ-4 mental sample crosscheck program for milk, water, air filters, and food
- ~, samples during the period 1982 through October 1985. 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.
l
- The results in Table A-2 were obtained for thermoluminescent dosiineters (TLD's) during the period 1976, 1977, 1979, 1980, and 1981 through parti-3 cipation in the Second, Third, Fourth, and Fif th International Intercomparison
? of Environmental Dosimeters under the sponsorships listed in Table A-2.
l l
i- A-2 t . _ . _ . _ . - _ ~ _ , _ _ _ - _
s e Table 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, 1982 through 1985.a Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis i2ac i3o, n=1d STW-270 Water Jan. 1982 Sr-89 24.3i2.0 21.015.0 Sr-90 9.410.5 12.011.5 STW-273 Water Jan. 1982 I-131 8.610.6 8.411.5
-STW-275 Water Feb. 1982 H-3 1580i147 1820i342 STW-276 Water Feb. 1982 Cr-51 <61 0 Co-60 26.0t3.7 20t5 Zn-65 <13 15 5 Ru-106 <46 20i5 Cs-134 26.810.7 2215 Cs-137 29.711.4 23i5 STW-277 Water Mar. 1982 Ra-226 11.9tl.9 -
11.611.7
. STW-278 Water Mar. 1982 Gross alpha 15.6tl.9 1915 Gross beta 19.210.4 1915 STW-280 Water Apr. 1982 H-3 2690i80 2860i360 STW-281 Water Apr. 1982 Gross alpha 75t7.9 85t21 Gross beta 114.115.9 10615.3 Sr-89 17.411.8 2415 Sr-90 10.510.6 12il.5 Ra-226 11.4*2.0 10.9 1.5 Co-60 <4.6 0 STW-284 Water May 1982 Gross alpha 31.5f6.5 27.517 Gross beta 25.9t3.4 2915 STW-285 Water June 1982 H-3 197011408 18301340 STW-286 Water June 1982 Ra-226 12.611.5 13.413.5 Ra-228 11.li2.5 8.7*2.3 STW-287 Water June 1982 I-131 6.510.3 4.410.7 STW-290 Water Aug. 1982 H-3 3210t140 2890i619 A-3
[
- (
t' 4
. Table A-1. (continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis *2cc 130, n =1d STW-291 Water- -Aug. 1982 I-131 94.6i2.5 87*15 STW-292 Water Sept. 1982 Sr-89 22.7*3.8 24.5i8.7 Sr-90 10.9i0.3 14.5t2.6
- STW-296 Water Oct. 1982 Co-60 20. 0tl. 0 .20t8.7 Zn-65 32.3t5.1 24t8.7 Cs-134 15.3kl.5 19.0t8.7 Cs-137 21. 0tl. 7 20.0i8.7 STW-297' Water Oct. 1982 H-3 2470*20 2560i612 STW-298 Water Oct. 1932 Gross alpha 32130 55t24 Gross beta 81.7*6.1 .81*8.7 Sr-89 ~2
< .0 Sr-90 14.1*0.9 17.2i2.6 Cs-134 <2 1.818.7 Cs-137 22.710.6 20 8.7 Ra-226 13.6t0.3 12.5t3.2 Ra-228 3. 9*1. 0 3.6t0.9 STW-301 Water Nov. 1982 Gross alpha 12. 0t1. 0 19.0t8.7 Gross beta 34.0t2. 7 24.0t8.7
~ STW-302 Water Dec.1982 I-131 40.0i0. 0 37.0*10 STW-303 Water Dec.1982 H-3 1940t20 1990t345 STW-304 Water Dec. 1982 Ra-226 11.7t0.6 11.0*1.7 Ra-228 _
<3 0 STW-306 Water Jan. 1983 Sr-89 20.018.7 29.215 Sr-90 21.7t8.4 17.2il.5 STW-307 Water Jan. 1983 Gross alpha 29.0i4.09 29.0113 Gross beta 29. 3t0. 6 31.0i8.7 STM-309 Milk Feb. 1983 Sr-89 35t2.0 37t8. 7 Sr-90 13.710.6 1812.6 I-131 55.7i3.2 55t10.4 Cs-137 29tl. 0 26t8.7 Ba-140 <27 0 K-40 1637f5.8 15121131 A-4 S
Table A-1. (continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis *2cc i3o, n=1d STW-310 Water Feb.1983 H-3 2470180 23601612 STW-311 Water March 1983 Ra-226 11.9tl.3 12.713.3 Ra-228 <2.7 0 STW-312 Water March 1983 Gross alpha 31.614.59 31113.4 Gross beta R27.0i2.0 28i8.7 STW-313 Water April 1983 H-3 -3240180 3330i627 STW-316 Water May 1983 Gross alpha 94t7 64119.9 Gross beta 133i5 149i12.4 Sr-89 1911 24t8.7 Sr-90 12t1 13i2.6 Ra-226 7.9i0.4 8.5i2.25 Co-60 30*2 30i8. 7 Cs-134 27t2 3318.7 Cs-137 29t1 2718.7 STW-317 Water May 1983 Sr-89 59.7*2.1 5718.7 Sr-90 33.7tl.5 3813.3 STW-318f Water May 1983 Gross alpha 12.811.5 1118.7 Gross beta 49.4t3.9 57i8.7 i Milk STM-320 June 1983 Sr-89 2010 2518.7 Sr-90 10*1 16f2.6 I-131 30i1 30i10.4 Cs-137 52i2 4718.7
, K-40 1553157 1486t129
- STW-321 Water June 1983 H-3 1470189 15291583 STW-322 Water June 1983 Ra-226 4.310.2 4.811.24 Ra-228 <2.5 0 STW-323 Water July 1983 Gross alpha 3t1 718.7 Gross beta 2110 22i8.7 STW-324 Water August 1983 I-131 13.310.6 14t10.4 A-5
Table A-1. (continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis *2c i3c, n=1d STAF-326 Air August 1983 Gross beta 42 2 3618.7 Filter Sr-90 14t2 10i2.6 Cs-137 19t1 1518.7 STW-328 Water Sept. 1983 Gross alpha 2.310.6 5t8.7 Gross beta 10.7tl.2 918.7 STW-329 Water Sept. 1983 Ra-226 3.0t0.2 3.110.81
. Ra-228 3.2 0.7 2.0t0.52 STN-331 Water Oct. 1983 H-3 1300*30 12101570 STW-335 Water Dec.1983 I-131 19.611.9 20i10.4 STW-336 Wster Dec. 1983 H-3 2870i100 2389t608 STAF-337 Air Nov. 1983 Gross alpha 18.010.2 1918.7 Filter Gross beta '
58.611.2 50i8.7 Sr-90 10.910.1 15i2.6 Cs-137 30.112.5 2018.7 STW-339 Water Jan. 1984 Sr-89 47.2il.9 3618.7 Sr-90 22.514.0 24i2.6 STW-343 Water Feb. 1984 H-3 2487t76- 23831607 STM-347 Milk March 1984 I-131 5.3fl.1 611.6 STW-349 Water March 1984 Ra-226 4.0f0.2 4.111.06 Ra-228 3.6t0.3 2.010.52 S
STW-350 Water March 1984 Gross alpha 3.8 1.1 518.7 Gross beta 24.212.0 20i8.7 STW-354 Water April 1984 H-3 3560t50 35081630 STW-355 Water April 1984 Gross alpha 21.0i4.1 35t15.2 Gross beta 127.814.1 147112.7 Sr-89 29.3t2.0 2318.7 Sr-90 16.6i0.7 26t2.6 Ra-226 4.0 1.0 4.0il.04 Co-60 32.3 1.4 3018.7 Cs-134 33.6t3.1 30t8.7 Cs-137 33.312.2 2618.7 A-6
ar .
Table A-1. (continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result <
Code Type Collected Analysis *2cc 13 cr, n=1d STW-358 Water May 1984 Gross alpha- 3.0i0.6 3t8.7.
Gross beta 6.711.2 6t8.7 STM-366 Milk June 1984 Sr-89 21i3.1 2518.7 Sr-90 13i2.0 17*2.6 '
I-131 4515.3 43110.4 Cs-137 2314.0 3518.7 K-40 1577t172 1496t130 STW-368 Water July 1984 Gross alpha 5.111.1 6t8.7 Gross beta 11.9tl.4 1318.7 STW-369 Water August 1984 I-131 34.315.0 34.0110.4 STW-370 Water August 1984 H-3 30031253 28171617 STF-371 Food July 1984 Sr-89 22.015.3 25.018.7 Sr-90 14.7t3.1 20.012.6 I-131 <172 39.0110.4 Cs-137 24.015.3 25.018.7 K-40 2503t132 2605t226.0 STAF-372 Air August 1984 Gross alpha 15.3tl.2 17t8.7 Filter Gross beta 56. 0i0. 0 5118.7 '
Sr-90 14.3*1.2 18*2.4 Cs-137 21.0*2.0 1518.7 STW-375 Water Sept. 1984 Ra-226 5.lt0.4 4.9tl.27 Ra-228 2.210.1 2.310.60 STW-377 Water Sept. 1984 Gross alpha 3.311.2 5.0i8.7 Gross beta 12.7f2.3 16.018.7 STW-379 Water Oct. 1984 H-3 2860t312 2810i356 STW-380 Water Oct. 1984 Cr-51 <36 4018.7 Co-60 20.3tl.2 20i8.7 Zn-65 15018.1 147*8.7 Ru-106 <30 4718.7 Cs-134 31.317.0 3118.7 Cs-137 26.711.2 2418.7 A-7
. - . . = _ _ - _ _ - - - _ . - - - . - _
[
i ' .,
E4 . _
w Table A-1. (continued)
Concentration in pCi/lb Lab Sample Date . TIML Result -EPA Result Code Type . Collected Analysis fasc t3o, n=1d STM-382 Milk Oct. 1984 Sr-89 15.7t4.2 22t8.7 Sr-90 12.7tl.2 16t2.6 I-131 41.7t3.1 42i10.4 Cs-137 31.3t6.1 3218.7 X-40 1447t66 1517t131 STW-384 Water Oct. 1984 Gross alpha 9.7tl.2 14t8.7 (811nd) Sample A Ra-226 3. 3t0. 2 - 3.0t0.8 Ra-228 3.4tl.6 2.1t0.5 Uranium nae 5t10.4 Sample 8 Gross beta 48. 3t5. 0 64t8.7 Sr-89 10.7t4.6 11t8.7 Sr-90 7.3tl.2 12t2.6 Co-60 16.3tl.2 14t8.7 Cs-134 <2 248.7 Cs-137 16.7tl.2 14*8.7 STAF-387 Air Nov. 1984 Gross alpha 18.7tl.2 15t8.7 Filter Gross beta 59.0t5.3. 52t8. 7 Sr-90 18.3tl.2 21*2.6 Cs-137 10.311.2 10t8.7 STW-388 Water Dec. 1984 I-131 28.'Ot2.0 36t10.4 STW-389 Water Dec. 1984 H-3 3583*110 3182*624 STW-391 Water Dec. 1984 Ra-226 8.4tl. 7 8.6t2.2 Ra-228 3.110.2 4.lil.1 STW-392 Water Jan. 1985 Sr-89 <3.0 3. 0t8. 7 Sr-90 27.3t5.2 30.0t2. 6 STW-393 Water Jan.1985 Gross alpha 3.3tl.2 5*8. 7 Gross beta 17.~3t3.0 15t8.7 STS-395 Food Jan. 1985 Sr-89 25.326.4 34.0t5.0 Sr-90 27.0i8.8 26.0tl.5 I-131 38.0t2. 0 35.0t6.0 Cs-137 32.7t2.4 29. 0t5. 0 K-40 1410t212 1382t120 A-8
o c - ,
Table A-1. (continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Codo Type Collected Analysis f2cc i3o, n=1d
~
'STW-397 Water Feb.1985 Cr-51 <29 4818.7 Co-60 21.3*3.0 20i8.7 Zn-65 53.7i5.0 5518.7 Ru-106 <23 25*8.7 Cs-134 32.311.2 3518.7
- Cs-137 25.313.0 25t8.7 STW-398 Water Feb. 1985 H-3 3869i319 37961634 STM-400 Milk March 1985 I-131 7.312.4 9.010.9 STW-402 -Water March 1985 Ra-226 4.6i0.6 5.0tl.3 Ra-228 <0.8 9.0*2.3 Reanalysis Ra-228 9.0*0.4 STW-404 Water March 1985 Gross alpha 4.712.3 618.7 Gross beta 11.3i1.2 1518.7 STAF-405 Air March 1985 Gross alpha 9.3tl.0 10.0t8.7 Filter Gross beta 42.0il.1 36. 0i8. 7 Sr-90 13.3tl.0 15.0*2.6 Cs-137 6.3tl.0 6.0i8.7 STW-407 Water April 1985 I-131 8.0i0.0 7. Sil.'3 STW-408 Hater April 1985 H-3 33991150 35591630 STW-409 Water April 1985 (Blind) Gross alpha 29.7tl.8 32.0i5.0 Sample A Ra-226 4.410.2 4.110.6 Ra-228 nae 6.210.9 Uranium nae 7.016.0 Sample B Gross beta 74.3i11.8 72.0i5.0 Sr-89 12.3*7.6 10.015.0 Sr-90 14.7f2.4 15.011.5 Co-60 14.7*2.4 15.Di5.0 Cs-134 12.0t2.0 15.015.0 Cs-137 14.012.0 12.0t5.0 i
i A-9
.~- ,- . . _ . - , _,-__-,______.-~..-,_,r__.- _
o O' Table A-1. (continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis 120C 130, n =1d STW-413 Water May 1985 Sr-89 36. 0* 1 2.'4 3C.015.0 Sr-90 14.3 4.2 15.0tl.5 STW-414 Water May 1985 Gross alpha 8.3t4.1 12.0t5.0 Gross beta 8.711.2 11.015.0 STW-416 Water June 1985 Cr-51 44. 716.0 44.015.0 Co-60 14e3tl.2 14.015.3 Zn-65 50.317.0 47.015.0 Ru-106 5's.315.8 62.015.0 Ct-134 32.7tl.2 35. 0* 5. 0 Cs-137 22.7*2.4 20.0*5.0 STW-418 Water June 1985. H-3 2446*132 2416i351 STM-421 Milk June 1985 Sr-89 10.3t4.6 11. 0tC. 7 Sr-90 9.012.0 11.0t2.6 I-131 11.7tl.2 11.0110.4 Cs-137 12.7*1.2 11.0*8.7 K-40 1512t62 1525*132 STW-423 Water July 1985 Gross alpha 5.0i0.0 11.0i8.7 1 Gross beta 5.0t2.0 8. 0*8. 7 3TW-425 Water August 1985 I-131 25.7t3.0 33.0110.4 STW-426 Water August 1985 H-3 4363 83 4480i776 STAF-427 Air August 1985 Gross alpha 11.3i0.6 13.018.7 Filter . Gross beta 46.0il.0 44.018.7 Sr-90 17.7i0.6 18.0t2.6 Cs-137 10.310.6 8. 0i8. 7 STW-429 Water Sept. 1985 Sr-89 15.7i0.6 20.018.7 Sr-90 7.0t0.0 7.012.6 STW-430 Water Sept. 1985 Ra-226 8.210.3 8.912.3 Ra-228 4.110.3 4.611.2 STW-431 Water Sept. 1985 Gross alpha 4.710.6 8.018.7 Gross beta 4.7tl.2 8.018.7 A-10
o w a Table A-1. (coctinued)
Concentration in pCi/lb Lab _ Sample. Date TIML Result EPA Result Code Type Collected Analysis *2cc 13a, n=1d STW-433; Water' Oct. 1985 Cr-51 <13 21.0t8.7 Co-60 19.30.6 20.0t8.7
'Zn-65 19.7*0.6 19.0t8.7 Ru-106 <19 20.0t8.7 1
Cs-134 17.0tl.0 20.028.7 Cs-137 19.3tl.2' 20.0t8.7 STW-435 Water Oct. 1985 H-3 1957t50 1974i598
- a -
a Results obtained by Teledyne Isotopts Midwest Laboratory as a participant
. in the' environcentel sample crosscheck program operated by the Intercom-parison 'and Calibration Section, Quality Atsurance Branch, Environmental
. Monitoring and Support Laboratory, U,5. Environmental Protection Agency.
All resnits are in pCi/1, except for elemental potassium (K) data, which are in og/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 *2 standard deviations for three determinations.
d USEPA results are presented as the known values i control limits of 3a for n = 1.
e NA = Not analyzed.
f Analyzed but not reported ~to the EPA.
9 Results af ter calculations corrected (error in calculations when reported to EPA).
A-11
a
/
o Table A-2. Crosscheck program results, thermoluminescent dosimeters (TLDs).
mR Teledyne Average 12o d Lab TLD Result Known (all Code Type Measurement 12aa Value participants) 2nd International Intercomparisonb 115-2b CaF2:Mn Gamma-Field 17.0il.9 17.1C 16.417.7 Bulb Gamma-Lab 20.814.1' 21.3c 18.817.6 3rd International Intercomparisone 115-3e CaF2:Mn Gamma-Field 30.713.2 34.914.8f 31.513.0
? h1b ~
E3 Gamma-Lab 89.6*6.4 91.7i14.6f 86.2124.0 4th International Intercomparison9 115-49 CaF2:Mn Gamma-Field 14.111.1 14.lil.4f 16.019.0 Bulb Gamma-Lab (Low) 9.3fl.3 12.212.4f 12.017.6 Gamma-Lab (High) 40.411.4 45.819.2f 43.9113.2 5th International Intercomparisonh 115-5Ah CaF2:Mn Gamma-Field 31.411.8 30.016.01 30.2114.6 Bulb Gamma-Lab 77.415.8 75.217.61 75.8140.4 at beginning
~
Gamma-Lab 96.615.8 88.418.81 90.7i31.2 at the end
e Table A-2. (Continued) ,
mR Teledyne Average i 20 d Lab TLD Result Known (all Code Type Measurement 12ba Value participants) 115-5Bh LiF-100 Gmuna-Field 30.314.8 30.016I 30,2114.6 Gamma-Lab 81.117.4 75.217.61 75.8140.4
. at beginning Gausna-Lab 85.4111.7 88.418.81 90.7131.2
. at the end i
4 2
.'. a Lab result given is the neari 12 standard deviations of three determinations, w 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 summer of 1977 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas, Houston, Texas, f Value 12 standard deviations as determined by sponsor of the intercouparison using continuously operated pressurized ion chamber.
9 Fourth International Intercomparison of Environmental Dosimeters conducted in sunumer of 1979 by the School of Public Health of the University of Texas. Houston, Texas, h Fifth 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 cf Energy.
, i Value determined by sponsor of the intercomparison using continuously operated pressurized ion chamber.
l
o Appendix B Data Reporting Conventions 4
l l
l B-1
, o Data Reporting Conventions 1.0. All activities are decay corrected to collection time.
2.0. Single Measurementt 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 wnere 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 n background sample.
i
- 3.0. Duplicate Analyses 3.1. Individual results
- x1 i s1 x2 i s2 Reported result
- xis where x = (1/2) (71 + x2) s = \fs2+s2 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 e
B-2
,_,s_ _ - e - - - r ~- -&%----T vr- - r- e t-v--------&---- - w- 're- 'e =- 7
-'----~-
=.: o-
'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 exanple, 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=fEx E(x-x)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 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 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.
B-3
. 1 '
- e,
'?
Appendix C Maximum Permissible Concentrations .
of Radioactivity in Air and Water Above Background in Unrestricted Areas i
S 4
C-1
-c< %o Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas.a ,
Air Water Gross alpha 3 pC1/m3 Strontium-89 3,000 pC1/1 Gross beta 100 pCi/m3 Strontium-90 300 pC1/1 Iodine-131b 0.14 pCi/m3 Cesium-137 20,000 pC1/1 Barium-140 20,000 pCi/1 Iodine-131 300 pC1/1 Potassium-40C 3,000 pC1/1 Gross alpha 30 pCi/1 Gross beta 100 pCi/1 Tritium 3 x 106 pC1/1 a Taken'from Code of Federal Regulations Title 10, Part 20. Table !! 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.
O 9
5 C-2