ML20133D205
| ML20133D205 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 10/02/1984 |
| From: | Yates C NUS CORP. |
| To: | |
| Shared Package | |
| ML20133D190 | List: |
| References | |
| NUS-4679, NUDOCS 8508070259 | |
| Download: ML20133D205 (100) | |
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NUS-4679 PRELIMINARY PREOPERATIONAL
SUMMARY
REPORT OF THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM AT THE PERRY NUCLEAR POWER PLANT Prepared for The Cleveland Electric illuminating Company by Carl R. Yates April 1985 NUS Corporation 910 Clopper Road
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Gaithersburg, MD 20878 fl WA VWh l'
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David K. Dougherty,llanager A. Edgar Mitchell, Jr.
Radiological Programs Department Project Manager ll RBR X888% 8$8o$!4o R
Preface This report presents the results of the Perry Nuclear Power Plant (PNPP)
Radiological Environmental Monitoring Program (REMP) through the f all of 1984.
It is a preliminary report of the preoperational REMP. After Perry Unit I goes critical, additional data will be incorporated into a final pre-l operational summary report.
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Table of Contents Section Title Page 1.0 Introduction 1
A.
Site and Station Description 1
B.
Objectives and Overview of PNPP Monitoring Program 1
2.0 Program Description 4
3.0 Sampling Methods and Procedures 21 A.
Direct Radiation 21 B.
Fish 22 C.
Sediment 22 D.
Airborne Particulates/ Airborne Iodine-131 23 E.
Water 23 F.
Milk / Silage 24 G.
Vegetation 24 4.0 Summary and Discussion of Analytical Results 25 A.
Direct Radiation 25 B.
Fish 30 C.
Sediment 33 D.
Airborne Particulates/ Airborne Iodine-131 35 E.
Water 38 F.
Milk / Silage 38 G.
Vegetation 43 5.0 Land Use Survey - Most Recent 53 b
6.0 Conclusions 57 7.0 References 58 Appendix A Laboratory Quality Assurance Appendix B Reporting of Analytical Results Appendix C Deviations from the Program Appendix 0 Raw Data Tables Appendix E NUS Analytical Procedures 1
LIST OF TABLES,
(Page 1 of 2)
Table Number Title Pg 1
PNPP Radiological Environmental Monitoring Program 7
2 Sample Locations and Media for the Perry Radiological Environmental Monitoring Program 9
3 Chronological History - PNPP REMP 1981 through 1984 17 4
Direct Radiation - Thermoluminescent Dosimetry - Monthly Averages - May 1981 through September 1984 26 5
Comparison of Average-Annual and Average-Monthly Direct Radiation Measurements (by station) -
1981 through 1984 29 6
Direct Radiation - Thermoluninescent Dosimetry -
Average Annual Dose Rates - 1981 through 1984 31 7
Genna Spectrometry of Fish Samples - Annual Averages, 1981 through 1984 32 8
Gamma Spectrometry of Sediment Samples - Annual Averages, 1981 through 1984 34 9
Gross Beta in Air Particulate Filters - Monthly Averages - October 1982 through August 1984 36 10 Gamma Spectrometry of Composited Air Particulate Filters - Quarterly Averages - 4th Quarter 1982 through 2nd Quarter 1984 39 11 Gross Beta in Water - Quarterly Averages - 3rd Quarter 1982 through 3rd Quarter 1984 40 12 Tritium in Water, Quarterly Composite by Location -
Quarterly Averages 3rd Quarter 1982 through 3rd Quarter 1984 42 13 Gamma Spectrometry of Milk Samples - Annual Averages - 1982 through 1984 44 11
e LIST OF TABLES (Page 2 of 2)
Table Number Title Py 14 Strontium-90 in Milk - Annual Averages - 1983 through 1984 45 15 Gamma Spectrometry of Feed / Silage - Annual Averages -
1982 through 1984 46 16 Gamma Spectrometry of Vecetation Samples - Annual Averages - 1982 through 1984 47 17 Summary of Data for the Perry NPP Radiological Environmental Monitoring Program - 1981 through 1984 48 18 Nearest Gardens and Residences by Sector Identified During the 1984 Perry NPP Annual Land Use Survey, 54 19 Milk Animals Identified During the 1984 Perry
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NPP Annual Land Use Survey.
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20 Control Milk Sampling Locations Identified
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During the 1984 Perry NP,P Annual Land Use Survey.
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LIST OF FIGURES f
Figure Numbers Title M
1 Sampling Locations Within 5 Miles of the PNPP 15 2
Sampling Locations Greater than 5 Miles from the PNPP 16 3
Sapling Media Milestones for the PNPP REMP -
t 1981 through 1984 20 4
Average Monthly Ambient Radiation Levels in the Vicinity of the Perry NPP - May 1981 through September 1984 28 5
Average Monthly Gross Beta Activity in Air Particulates in the Vicinity of the Perry NPP -
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October 1982 through August 1984 37 6
Average Monthly Gross Beta Activity in Water r
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in the Vicinity of the Perry NPP-September 1982 through July 1984 41 I
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1.0 INTRODUCTION
The preoperational radiological environmental monitoring program (REMP) for the Perry Nuclear Power Plant (PNPP) was initiated in March 1981 and is ongoing.
Pressurized lonization Chamber (PIC) readings were made on March 24, 1981 as an initial environmental characterization and to detect gross anomalies.
The first REMP samples (fish and sediment) were collected on May 20, 1981.
This is the Preliminary Preoperational Summary Report for the radiological environmental monitoring program. This report covers the period March 24, 1981 through October 2,1984 and summarizes the results of measurements and analyses of data obtained from samples collected during this interval. This program was conducted by NUS Corporation under contract with Tne Cleveland Electric illuminating Company (CEI) until October 1984. This report will be reissued in final form when all data, through the date of criticality, (expected mid 1985) are available.
A.
Site and Station Description PNPP will consist of two BWR units, each designed to operate at a power level
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of about 1205 megawatts-electric with the main condenser circulating water cooled by a system of closed-loop natural draft cooling towers. The plant is located on Lake Erie, on approximately 1100 acres, about thirty-five (35) miles northeast of Cleveland, Ohio and about seven (7) miles northeast of Painesville, Ohio. PflPP is situated in North Perry Village in northeastern Lake County, Ohio.
B.
Objectives and Overview of PNPP Monitoring Program United States Nuclear Regulatory Commission (USNRC) regulations require that nuclear power plants be designed, constructed, and operated to keep levels of radioactive material in effluents to unrestricted areas as low as reasonably achievable (ALARA) (10 CFR 50.34). To ensure that these criteria are met, each license authorizing reactor operation includes technical specifications
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(10 CFR 50.36a) governing the release of radioactive ef fluents.
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i In-plant monitoring will be used to assure that these predetermined release limits are not exceeded. However, as a precaution against unexpected and undefined processes which might allow undue accumulation of radioactivity in any sector of man's environment, a program for monitoring the plant environs is also included.
The regulations governing the quantities of radioactivity in reactor affluents allow nuclear power plants to contribute, at most, only a few percent increase above normal background radioactivity. Background levels at any one location are not constant but vary with time as they are influenced by external events such as cosmic ray bombardment, weapons test fallout, and seasonal variations.
These levels also can vary spatially within relatively short distances reflect-ing variations in geological composition. Because of these spatial and tempo-ral variations, the radiological surveys of the plant environs are divided into preoperational and operational phases. The preoperational phase of the program of sampling and measuring radioactivity in various media permits a general characterization of the radiation levels and concentrations prevail-(
ing prior to plant operation, along with an indication of the degree of natural variation to be expected. The operational phase of the program obtains data which, when considered along with the data obtained in the preoperational phase, assist in the evaluation of the radiological impact of plant operation.
Implementation of the preoperational monitoring program fulfills the following objectives:
1.
Evaluation of procedures, equipment and techniques.
2.
Identification of potentially important pathways to be monitored af ter the plant is in operation.
3.
Measurement of background levels of radioactivity and radiation and their variations along potentially important pathways in the area surrounding the plant.
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Provision of baseline data for statistical comparison with future operational analytical results.
Sampling locations were selected on the basis of local ecology, meteorology, physical characteristics of the region, and demographic and land use features
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of the site vicinity. The preoperational program was designed based on the USNRC Radiological Assessment Branch Technical Position on radiological environ-mental monitoring as revised in Revision 1 November 1979 (reference 1),
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I 2.0 PROGRAM DESCRIPTION As of October,1984 there were forty locations within a radius of about 15 miles from the PNPP site included in the monitoring program. The number and location of monitoring points were determined from predictions of the highest expected offsite environmental concentrations. For these predictions, the plant effluent source terms provided the release rates of various radioisotopes.
Then site hydrology, meteorology, and design parameters were used to calculate dilution and dispersion factors and probable decay times. Other factors considered were applicable regulatory guidelines (Appendix I to 10CFR50, Regulatory Guides 4.1, 4.2, and 4.8), population distribution (from environmental report), ease of access to sampling stations, security, and future program integrity (o.g., not placing TLDs near areas under construction or where the potential for vandalism is high).
In addition, certain locations where PNPP operations are unlikely to affect levels of radiation or radioactivity were selected as control locations.
The PNPP radiological environmental monitoring program includes the measurement I
of ambient gamma radiation by thermoluminescent dosimetry; the determination of gamma emitters in shoreline sediments and fish; the determination of gross beta and gamma emitters in air particulates; the measurement of airborne I-131 in charcoal cartridges; the measurement of gross beta, gamma emitters, and tritium in Water; and the determination of gamma emitters and !=l31 in mil k.
These media and analyses were selected since they provide measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from station operation, in addition, beyond the minimum program requirements, fodder and food products were collected annually (starting in 1982) and analyzed for gamma emitting nuclides. Also, starting in August,1903, sediment, water, and milk samples were analyzed for Sr-89 and Sr-90.
The preoperational radiological environmental monitoring program for verry was initialed in 1981. The program is summarized in Table 1.
Table 2 describes sample locations, associated media, approximate distance and direction from 4
k the site, and the initial date of sampling. Figures 1 and 2 illustrate the locations of sampling stations relative to PNPP, Table 3 presents a chronological history of the PNPP monitoring program.
This table lists the various media and the sum of the control and indicator l
locations that were sampled during each year of the program.
Figure 3 indicates the sampling media milestones for the PNPP monitoring program.
The data tables included in the preoperational summary report are for those analyses in which many positive activities have been detected, lodine-131 in Air, iodine-131 in milk, gamma spectrometry of water, strontium-89 and strontium-90 in water, strontium-89 in milk, and strontium-89 and strontium-90 in sediment are not included in individual data tables since no or very few i
positive activities were detected over the course of the program. Only Lower Limits of Detection (LLDs) (see Appendix B) were reported for 1-131 in air and milk, Sr-89 and Sr-90 in sediment, gamma spectrometry of water, and Sr-89 l
in milk and water.
Threetrending figures have also been included: Figure 4 - Average Monthly Ambient Radiation Levels in the Vicinity of the PHPP, Figure 5 - Average Monthly Gross Beta Activity in Air Particulates in the Vicinity of the Perry NPP, and Figure 6 - Average Monthly Gross Beta Activity in Water in the Vicinity of the Perry NPP. Trending figure averages include both indicator and control locations.
All calculated averages in Tables 4 through 16 include both indicator and control locations.
Indicator and control data are combined in the averages since there was no observable dif ference between the two. This is readily apparent from the indicator and control averages presented in Table 17.
A statistical summary of the results apooars in Table 17.
The reported averages are based only on concentrations above the limit of detection.
In Tablo 17, the fraction (f) of the total number of analysos which were datoctable follows in parenthesis. Also given in parenthesis are the minimum and maximum values of detectablo activity during the reporting period.
In addition to the described analytical program, a milk animal, vegetable f
garden, and residence survey was performed annually. This survey identifies the nearest garden and residence in each sector and all milk animals out to 5 miles and is updated annually. Land-use survey data from 1984 is presented in Tables 18 through 20.
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TABLE 1 (Page 1 of 2)
FliFP RADIOLOGICAL EirrIR0mpfmTAL MONITORING PROGRAM Analysis imple Media tocations Sampling Frequency Type Frequency Atrtorne Radioiedine 1, 3, 4, 5, 6, 35 Conttauous satpler operation Radiolodine beekly following aos with collection weekly or 1-131 canister change Particulates as required by dust loading, Particulateg)
Weekly following whichever is more frequent Gross Beta filter change Gamma Isotopic (b)
Composite, by location quarterly Direct Radiation 1 through 24 Continuous sampitag, one Gausa Dose Monthly (2 TLDs/ location) piss 35 TLD exchanged monthly Continuous saroling, one Gama Dose Annually TLD exchanged annually IEI Gross Beta Monthly laaterterne 23, 34, 35, 37, Manthly Composite saf ace Gauna Isotopic Monthly H-3 Composite, by location, er esAisg quarterly Sr-89 -90 Quarterly (analyses performed on one monthly sample per station per quarter)
Sedament from 25,26, 27, 32 Sestannually--spring and Gmuna Isetopic Semiannually shoreline f all as meather permits Strontium-89, 90 Semiannually M, M, 31. U hthly e animals are not 1-U1, Gamma Monthly Ingestig Mala Lgy on pasture Isotopic Semisonthly when antaals are I-131, Gmuna Semimonthly on pasture isotopic Sr-89. -90 Quarterly (analyses performed on one monthly sample per station per quarter)
See f octactes at ew of tatie.
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TABLE I (Page 2 of 2)
P2PP RADICLOGICAL DeVIRCepfnTAt peuiTORIM PROGtq Analysis Sagle media Locaticas Samp1tng Frequency Type Frequency F tsk 25, 32 Semiannually--spring and Gauna Isotopic Semiannually f all as meather permits (edible portion)
Stiege
- 29. E, 31. 33 Annually Gamma Isotopic Annually Food Prodnatts 33, 39, 40 Annually Gauta Isotopic Annually (a)
Particulate sample filters mill be analyzed for gross beta 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more af ter sampilng to allow for radba am$ thoram daagt'er decay. If gross beta activity is air is greater than ten times the mean af t2e centrol samples for any medium, gauna isotopic analysis will be performed on the indiviesal samples.
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Gauta isetapic analysis means the identificattom and quantification of gausa-emitting radionuclides that say be attributable to the effloents from the f acility.
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Camposite samples util be collected with equipment that is capable of collecting an aliquot at time totervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly).
(d)
I-131 t-te performed at least for 6 months of the lest fell pasture season prior to operation.
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Table 2 (Page 1 of 6)
Sample Locations and Media for the Perry Radiological Environmental Monitoring Program for 1984 Date Location Distance Sampling No.
Description (Miles)
Direction Media (3)
Began
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1 Redbird (Haines Road, North of West Chapel Road) 3.4 ENE TLD May 1981 On pole 3303609; first pole south of first drivemay AP, AI Oct. 1982 on lef t h
2 Site boundary; tree line 0.7 E
TLD May 1981 Ash tree 1000 feet MMW of second transmission tower from road 3
Meteorciogical tower 1.0 SE TLD May 1981 On fence surrounding the equipment shelter AP, AI Oct. 1982 4
Site Boundary 0.7 S
TLD May 1981 On pole is79/SPG5-30; inside auxiliary road gate off AP, AI Oct. 1982 Parmly Rd.
5 Site Boundary, Quincy Su5 station 0.6 SW TLD May 1981 On pole #L1283/9300; east side of substation AP, AI Oct. 1982 6
Concord Service Center (Control) 11.0 SSW TLD May 1981 Auburn Road south of Rt. 90; on inside rear fence AP, AI Oct. 1982 next to gate See footnotes at end of table.
l Table 2 (Page 2 of 6)
Sample Locations and Media for the Perry Radiological Environmental Monitoring Program for 1984 Date Locatica Cistance Sampling II)
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Description (Miles)
Direction Media Began 7
Site Soundary; Lockwood Road Bus Turnaround 0.6 NE TLD May 1981 On tree on right,100 feet past the turnaround 8
Site Boundary; Tree Line 0.8 ENE TLD May 1981
..o 1000 feet N cf location #2 on tree near rusted nasure spreader 9
Site b roary; Transmission Line Tower 0.7 ESE TLD May 1981 Third toner from Antioch Road toward the plant 10 Site Ec:r.dary; Southsoutheast Corner Security Fence 0.8 SSE TLD May 1981 On pole at turn in the fence l
11 Site Ecundary; Transsission Line Tower 0.6 SSW TLD May 1981 On toner at SM corner of Center and Paraly Roads l
12 Site Soundary; Transmission Line Tower 0.6 WSW TLD May 1981 Access road from N side of Paraly just W of location
- 5, lef t at first turn af ter 90 degree left; TLD on tower to right See footmtes at end of table.
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Table 2 (Page 3 of 6)
Sample Locztions and Media for the Perry Radiological Environnental Monitoring Progran for 1984 Date Locatios Distance Smpling III 20.
Description (Miles)
Direction Media Bega 13 Madison-on-the-take 4.7 ENE TLD May 1981 At end of idhiteucod Drive, N of Chapel Road, IGi side of turnaround on pole #835803 14 Hubbard Road (South of North Ridge Road) 4.9 E
TLD May 1981 On pole #28974 on is side of road, 5 side of McMackin Creek 15 Madison Substation (Eagle Street) 5.1 ESE TLD May 1981 First pole next to substatlan near railroad tracks 16 Dayton Road (north of Interstate 90) 5.0 SE TLD May 1981 On pole #572203 on left after dirt driveway which is just af ter the sharp lef t on Dayton af ter crossing 1-90 17 Chassick Road (Cui de Sac South of Interstate 90) 5.2 SSE TLD May 1981 On pole #276222/112Z011; last pole on lef t IS Blair Road 5.0 S
TLD May 1981 On pole on left just after road makes 90 degree left curve from south to east heading toward Grand River Bridge.
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See footnotes at end of table.
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Saurple Locations and Media for the Perry Radiological Environmental Monitoring Program for 1984 Date Location Distance Sampling Ka.
Description (Miles)
Direction Media (3)
Began 19 Lane Road aM South Ridge Road 5.3 SSW TLD May 1981 On pole iPC5643, 100 feet north of intersection b
20 Eu sery Rcad at Route 2 Overpass 5.3 SW TLD May 1981 Cr. W e #323976, across fron entrance to Rt. 2 i
21 Hardy Road at Painesville Township Park 5.1 WSW TLD May 1981 l
On pole #373345, east of park entrance 22 Painesville 6.9 SW TLD May 1981 On 5 side of Main Street across from Evergreen Cenetery entrance, on tree 50 feet west of pole
- 2rM 23 Fair;crt Harbor (riigh Street and New Street) 7.9 WSW TLD May 1981 On pole on street side of substation 24 St. Clair Asecue Substation (Control) 15.1 SW TLD May 1981 In Mentor; en rear fence corner near railroad tracks 25 F%FP Discharge 0.6 NNW SED, FSH May 1981 See footnotes at end of table.
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Table 2 (Page 5 of 6)
Sample Locations and Media for the Perry Radiological Envirosamental Monitoring Progran for 1984 Date Location Distance Sanpling No.
Description (Miles)
Direction Media (3)
Segan 26 Offshore at Reeird, vicinty of Ohio Water Service 4.2 ENE SED May 1981 Company Intake C
27 Offshore, victaty of Fairport Harbor Water Supply 7.9 WSW SED May 1981 Systen Intake 23 Ashtabula (Control), CEI Generating Station Intake 22.0 ENE WTR Sept. 1982 29 Milk Farm, J. Waltes, Antioch Road 1.4 ESE EK Feb. 1983 30 Milk Farm. E. Manley, North Ridge Road 2.3 SSW KK Mar. 1983 31 Milk Farm, Hofer, Antioch Road 1.4 ESE EK Feb. 1984 32 Mentor-on-the-Lake (Control) 15.8 WSW SED, FSH May 1981 33 Brockglen Farm (Centrol), Callow Road 10.2 S
EK Oct. 1982 34 PnPP Intake 0.7 NW WTR Sept. 1982 35 Site Boundary, Center of Sector, follow tree line 0.6 E
AP, AI, TLD Nov. 1982 around fields south and west of Location #2 See footnotes at erd of table.
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Table 2 (Page 6 of 6)
Sample Locations and Media for the Perry Radiological Enviremental Monitoring Progra:n for 1984 Date Lccatica Distance Sampling As.
Description (Miles)
Direction Media (3)
Began 36 Painesville Water Supply Intake 3.9 WSW WTR Sept. 1982 37 CP.io Water Service Company, Lake Erie East, Macison; 4.1 ENE WTR Sept. 1982
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33 Farn at site boundary, cff Antioch Road 1.1 E
FP Sept. 1982 l
39 Goldings, M. Ridge Road 1.8 SSW FP Sept. 1983 43 Antioch Road 1.1 E
FP Sept. 1983 (1)
AP = Air particulate AI = Air iodice TLD = Anbient gruta dose rate SED = Sediment WT2 = Water FSH = Fish nut = Milk FP = Foed Products
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SAMPLING LOCATIONS >5 MILES FF40M SITE I
PEFIF4Y NUCLE AF1 POWEF4 PLANT 1 F. 2 THE CLtVEL AND ELECTRIC
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Table 3 Preoperational Summary Report Chronological History PNPP REMP 1981 - 1984 (Sheet 1 of 3)
Year Media Analysis (I)
Number of Stations (2) 1981 Direct Radiation TLD-M, A 24 H
Fish Gamma Isotopic-SA 2
Sediment Gamma Isotopic-SA 4
1982 Direct Radiation TLD-M, A 25 Fish Gamma Isotopic-SA 2
Sediment Gamma Isotopic-SA 4
Airborne Gross Beta-W 6
Particulates Gamma Isotopic-Q Airborne I-131 lodine-131-W 6
Water Gamma Isotopic-M 4
(
Gross Beta-M L
Tritium-Q Milk Gamma Isotopic-M, SM 1
Iodine-131 -M, SM l
Feed / Silage Gamma Isotopic-A 1
F Vegetation Gamma Isotopic-A 1
B 1l 1 I
k Table 3 e
1 Preoperational Summary Report Chronological History PNPP REMP.981 - 1984 (Sheet 2 of 3) j l
Year MIedia Analysis (I)
Number of Stations (2) l 1983 Direct Radiation TLD-M, A 25 Fish Gamma Isotopic-SA 2
Sediment Gamma Isotopic-SA 4
i Strontium-89, 90 -A W
Airborne Gross Beta-W 6
j Particulates Gamma Isotopic-Q Airborne I-131 Iodine-131 -W 6
Water Gamma Isotopic-M 4
I Gross Beta-M Tritium-Q l
Strontium-89, 90 -Q Milk Gamma Isotopic-M, SM 3
l Iodine-131 -M, SM Strontium-89, 90 -Q 5
Feed / Silage Gamma Isotopic-A 3
Vegetation Gamma Isotopic-A 3
'I
.I I
I I
~'*~
I
l Table 3 Preoperational Summary Report Chronological History PNPP REMP 1981 - 1984 (Sheet 3 of 3)
Year Media Analysis (I)
Number of Stations (2) b 1984 Direct Radiation TLD-M, A 25 P
L Fish Gamma Isotopic-SA 2
Sediment Gamma Isotopic-SA 4
y Strontium-89, 90 -A Airborne Gross Beta-W 6
Particulates Gamma Isotopic-Q Airborne I-131 Iodine-131 -W 6
i Water Gamma Isotopic-M 4
Gross Beta-M Tritium-Q Strontium-89, 90 -Q m
Milk Gamma Isotopic-M, SM 4
Iodine-131 -M, SM p
Strontium-89, 90 -Q q
Feed / Silage Gamma Isotopic-A 4
Vegetation Gamma Isotopic-A 2
l (1) W = Weekly I
Q = Quarterly l
M = Monthly lI SA = Semi-Annually A = Annually SM = Se:ni-Monthly l
(2) Sum of indicator and control locations I
I I
m n
m n
M m_
m m.
M m
in Time (Years, Quarters) 1981 1982 1983 1984 1985 l
1 2
3 4
1 2
3 4
1 2
3 4
1 2
3 4
1 2
3 4
III 3
TLD Fish / Sediment e
e e
e g
g Water (2)
Al/AP(3) i I4I Milk e
e g
Feed / Silage Vegetation (1) TLD collectioris are monthly and annually. Dots represent the annual TLD collection.
(2) Water samr'99 s conducted monthly.
i (3) Air lodine (All and Air Particulate (AP) sampling is conducted weekly.
(4) Milk sampling is conducted monthly from November through March and semi-monthly otherwise.
FIGURE 3. SAMPLING MEDIA MILESTONES FOR THE PNPP REMP-1981 THROUGH 1984.
L
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{
3.0 SAMPLING METHODS AND PROCEDURES To derive meaningful and useful data from the radiological environmental monitoring program, sampling methods and procedures are required which will provide samples representative of potential pathways of the area. During the preoperhtional phase of the program, samples are collected and analyzed not only to obtain background radiological levels, but to acquire experience
[
with the sampling methodology and procedural format dictated by site specific requirements (reference 1). The following methods and procedures were applicable E
to the monitoring program as of October 1984 Any changes in the methods or procedural formats during the course of the program are reflected in the individual Annual Reports (see references).
n L
A.
Direct Radiation Thermoluminescent dosimeters (TLDs) were used to determine the direct (ambient)
[
radiation levels at twenty-five (25) monitoring points as described in Tables 1 and 2.
Sampling locations were chosen according to the criteria given
{
in the USNRC Branch Technical Position on Radiological Monitoring (Revision 1, November 1979) (reference 2). A description of the TLDs used in this program is given in Appendix E.
TLDs were located in two rings around the station. An inner ring was located near the site boundary and an outer ring was located at an approximate distance of 4 to 5 miles from the station.
Figures 1 and 2 show the locations of the TLD stations.
I The area around the station was divided into 16 radial sectors of 221/2 degrees each. TLDs were placed in all sectors except those which radiated from the site directly out over the lake without intersecting any unrestricted areas. Additional TLDs were located at three nearby communities and two control locations.
For routine TLD measurements, two dosimeters of CaSO :Dy in teflon cards 4
were deployed at each selected location.
Prior to deployment, individual dosimeters were calibrated by exposure to a known radiation field from a calibrated Cs-137 source. One set of dosimeters was exchanged on a monthly I
1 -
s m
basis and the second set was exchanged on an annual basis. Additional sets of dosimeters were shipped with each exchange cycle to serve as in-transit g
control s.
For routine exchanges TLDs were shipped by ground transportation one evening, picked up and exchanged the following day, and returned by ground transportation on the second evening. This was done to maintain the minimum J
possible in-transit dose. Upon receipt at the laboratory, the TLDs were read and the dose rates were calculated using the previously determined calibra-tion factors.
B.
Fish
~
Fish sampling was conducted semiannually at two locations. The immediate J
vicinity of the discharge was selected as an indicator location (#25), and an offshore location at Mentor-on-the-Lake (#32) was chosen as a control location.
I Using a passive collection technique, an experimental gill net (mesh ranging from approximately 1.0 to 2.5 inches to maximize catches in useful size ranges) was set at each sampling location by biologists under contract to NUS Corpora-tion. Nets were set in the evening and removed the following morning. En-trapped surviving fish not required for sampling were released. A Scientific Collecting Permit was obtained from the Ohio Department of Natural Resources I
to permit this sampling.
Available edible species were filleted at the time of collection. The edible portions were packed in dry ice and shipped to the laboratory for analysis by gama spectrometry.
C.
Sediment Sediment samples were collected semiannually at four locations. Two locations I
were nominally the same as the locations chosen for fish sampling. At Mentor-j on-the-Lake (#32) and Perry discharge (#25) the sediment was collected approxi-mately 1 mile offshore.
Some movement wn necessary to find a suitable sub-strate for sampling. Sediment samples were also collected offshore in the L
l
(
vicinities of Fairport Harbor (#27) and Redbird (#26). Samples were collected with a petite ponar grab sampler in about 30 feet of water. A sample was composited at each location in a plastic container. Approximately 1 kilogram was frozen and shipped to the 1aboratory for analysis by gamma spectrometry, and strontium-89 and -90.
D.
Airborne Particulates/ Iodine-131
(
Research Appliance Company continuous low volume air sampler units (Model
- 209088-2) were used to collect air particulates and airborne iodine-131.
Airborne particulates were collected by drawing air through a 47-millimeter diameter glass fiber filter. Air iodine-131 was collected by drawing air th ough a 57 millimeter diameter TEDA impregnated charcoal cartridge (F &
J Specialty Products, Inc.). The sampling units are housed in ventilated metal cabinets bolted to utility poles.
The air sampling network consists of six (6) stations; one is located in
{
Redbird (#1) approximately 3.4 miles ENE of the Perry plant and four are located at the site boundary (#3,4,5 and 35). The control location is located at the Concord Service Center (#6), approximately 11 miles SSW of the plant.
These locations are identified in Figures 1 and 2 and described in Tables 1 and 2.
The samplers were run continuously and the filter and charcoal cartridge
{
exchanged weekly. The elapsed time of sampling was recorded on an elapsed-time meter. Total air volume was calculated and recorded by the site techni-cian from the initial and final volumes as registered on the dry gas meter.
E.
Water
[
The water sampling network consists of four (4) stations as identified in
{
Figures 1 and 2 and described in Tables 1 and 2.
Stations 28 and 34 utilize Horizon Interval Samplers, which collect a small volume of water at short intervals, nominally 15 minutes. Stations 36 and 37 utilize an interval
[ -
e
._.__._._-_.___.____.A
k
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timer (Dayton #2E357) to control a solenoid valve (Dayton #6X230) on a pres-surized sampling line. This arrangement draws small aliquots at periodic intervals. The small volumes are automatically composited into a five-gallon container. Samples from the four (4) stations are collected monthly by the site technician.
F.
Milk / Silage Milk samples were collected monthly during the months of flovember, December, January, February, and March, and semi-monthly during the remaining months.
The control location, Brookglen Farm (station 33), is located approximately 10.2 miles sjuth of the Perry plant. The other 3 milk sampling locations
{
are Station 29 (1.4 miles ESE), Station 30 (2.3 miles SSW) and Station 31 (1.4 miles FSI). As a preservative, formalin was added to each sample at the time of collection. A feed / silage sample was taken annually from each of the milk sampling locations.
G.
Vegetation
(
Vegetation (various fruits and vegetables) was collected annually. Samples were collected from station 38 in 1982, stations 38, 39, and 40 in 1983, and stations 38 and 39 in 1984.
1i 1
1 1I
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4.0
SUMMARY
AND DISCUSSION OF ANALYTICAL RESULTS Data from the radiological analyses of environmental media collected during the report period are averaged and tabulated below. The procedures and specifi-cations followed in the laboratory for these analyses were as required in
{
Section 5.0 of the NUS Environmental Services Division Quality Assurance Manual, 9019xx-2, and were detailed in the NUS Radiological Laboratory Work Instructions.
[
Radiological analysis of environmental media characteristically approach
(
and frequently fall below the detection limits of state-of-the-art measurement methods (reference 1).
(See Appendix B). The data tables presented in this
{
report include averages based only on concentrations above the limit of detection.
The frequency of the averages (i.e., quarterly, monthly, annually) is based on the sampling frequency and the expected degree of variability of the analytical results.
Included in the discussion are ranges of average values for various reporting periods and an overall range of individual values for the total program.
(
Individual data points used to calculate the averages contained in this report are found in Appendix D and the respective annual reports. Values of the range limits are followed (in parentheses) by an indication of the station and reporting period in which that value occurred.
A.
Direct Radiation
(
Average monthly environmental radiation dose rates determined by thermoluminescent dosimeters (TLDs) are given in Table 4.
Average monthly dose rates are plotted
{'
in Figure 4.
A comparison of the average-annual a nd average-monthly dose rates, by station, is presented in Table 5.
The original PIC (pressurized ionization chamber) readings (3/24/81), which were used as an initial environmental characterization and to detect gross anomalies, are also included in Table 5.
Average annual dose rates (in units of mR/ year) from the monthly and annual cycles are presented in Table 6.
E
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Table 4 Preoperational Summary Report Direct Radia Thermoluminescent Dosimetry Monthly AveragesgiopMay 1981 Through September 1984 y
(Sheet 1 of 2)
Year Month Dose Rate (mR/ day 12s)
{
1981 May 0.18 + 0.06
(
June 0.2310.09 July 0.16 + 0.04
~
August 0.17 1 0.06
[
September 0.19 + 0.05 October 0.24 + 0.04 November 0.21 T 0.09 December 0.1810.08 Annual Y 0.19 1 0.08 1982 January 0.17 + 0.07
{
February 0.15 T 0.05 March 0.16 T 0.04 April 0.19 T 0.09 b
May 0.18 1 0.09 June 0.21 + 0.07 July 0.17 T 0.08
{
August 0.2110.09 September 0.18 + 0.13 October 0.21 T 0.05 November 0.26 T 0.07
[
December 0.2210.06 Annual Y 0.19 1 0.10 1983 January 0.22 1 0.06 February 0.21 + 0.05 f
March 0.22 T 0.04 L
April 0.22 I 0.06 May 0.22 T 0.05 June 0.21 T 0.06
(
July 0.2410.06 August 0.24 + 0.06 September 0.24 T 0.06 F
~ October 0.21 T 0.05 November 0.21 T 0.07 December 0.2210.04 Annual Y 0.22 1 0.06 ll E
Table 4 Preoperational Summary Report
{
Direct Radia Thermoluminescent Dosimetry Monthly AveragesgiopMay 1981 Through September 1984 y
(Sheet 2 of 2)
Year Month Dose Rate (mR/ day 12s) 1984 January 0.18 1 0.04
{
February 0.19 1 0.05 March 0.15 + 0.09 April 0.2110.09 r
May 0.21 + 0.06 L
June 0.22 + 0.09 July 0.2210.09 August 0.24 + 0.07
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September 0.2430.06 Annual Y 0.21 1 0.09 (1) Simple average 12s. Annual average (and its 2s) is calculated from the individual station results.
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Table 5 Preoperational Summary Report Comparison of Average-Annual and Average-Monthly Direct Radiation Measurements,1981 Through 1984 Results in Units of mR/ day + 2s j
PICReadings(1)
Annual Cycle TLD(2)
Monthly Cycle TLD(3)
(
Station (March 24, 1981)
(1981-1984)
(May 1981-September 1984) 1 0.20 + 0.02 0.19 + 0.03 0.20 + 0.07
(
2 0.18 T 0.01 0.18 I 0.04 0.19 I 0.08 3
0.19 I 0.03 0.18 I 0.06 0.20 T 0.07 4
0.21 I 0.02 0.20 T 0.04 0.21 T 0.07 5
0.20 T 0.02 0.17 T 0.04 0.20 T 0.08
(
6 0.20 I 0.02 0.18 I 0.03 0.19 I 0.08 7
0.19 I 0.02 0.18 T 0.05 0.21 T 0.09 r
8 0.19 I 0.02 0.18 T 0.06 0.18 T 0.06 L
9 0.19 I 0.04 0.17 I 0.06 0.18 T 0.07 10 0.19 7 0.02 0.18 T 0.03 0.19 7 0.06 11 0.21 T 0.03 0.18 + 0.08 0.19 7 0.08 12 0.19 7 0.02 0.19 7 0.02 0.19 T 0.09 13 0.21 T 0.01 0.17 7 0.08 0.20 T 0.07 14 0.20 T 0.02 0.21 T 0.05 0.19 7 0.06 15 0.21 T 0.02 0.20 T 0.08 0.20 T 0.06 16 0.25 7 0.03 0.23 T 0.06 0.25 T 0.08 17 0.23 T 0.01 0.21 T 0.08 0.23 7 0.09 18 0.28 T 0.02 0.29 I 0.08 0.28 T 0.09
(
19 0.21 T 0.02 0.20 7 0.07 0.20 T 0.07 20 0.21 T 0.02 0.21 I 0.06 0.20 T 0.08 21 0.22 7 0.01 0.21 7 0.06 0.22 T 0.08 22 0.20 T 0.02 0.22 T 0.03 0.21 7 0.08
(
23 0.23 T 0.02 0.22 T 0.04 0.22 T 0.07 24 0.20 7 0.02 0.21 T 0.04 0.20 T 0.10 35 (3) 0.18 I_ 0.03 0.19 7 0.04
{
Average (4) 0.21 1 0.04 0.20 1 0.07 0.21 1 0.09 (1) PIC readings were taken once at the beginning of the program as a preliminary characterization and to detect gross anomalies. Errors of PIC readings are two standard deviations of the average of 10 field readings.
e L
(2) Errors of annual cycle TLDs are two standard deviations of the annual cycle TLD station results.
(3) Errors of monthly cycle TLDs are two standard deviations of the monthly
{
cycle TLD station results.
(4) Error of the PIC Reacings average is two standard deviations of the column data. Errors of the Annual Cycle and Monthly Cycle TLD averages are calculated from the individual Annual and Monthly station results.
(5) Sampling at station 35 was begun in November of 1982. -
l
(
{
Monthly averages (from Table 4) ranged from 0.15 1 0.09 mR/ day (Mar. 1984) te 0.26 1 0.07 mR/ day (Nov. 1982).
Individual monthly dose rates ranged from 0.07 1 0.03 mR/ day (station 12, Mar. 1984) to 0.37 1 0.12 mR/ day (station 18 June 1981). Preoperational station averages from the monthly and annual TLD cycles are given in Table 5.
Station 18 (5.0 miles S) had consistently higher monthly dose rates throughout the prograrr, as the annual-cycle and monthly-cycle averages indicate. Significant variations occur between geograph-
[
ical areas as a result of geological composition. Temporal variations result from changes in cosmic ray intensity, local human activities, and factors
{
such as ground cover and soil moisture.
Oakley (reference 3) calculates an ionizing radiation dose equivalent of 82.2 mR/ year for Ohio including a terrestrial component of 45.6 mR/ year and an ionizing cosmic ray component of 36.6 mR/ year (excludes neutron component).
b Since Oakley's values represent averages covering wide geographical areas, the measured ambient radiation averages in Table 6 for the immediate locale
[
of Perry is consistent with Oakley's observations.
{
B.
Fish Average annual gamma spectrometry results for fish are found in Table 7.
Naturally occurring K-40 constituted the major detectable nuclide activity in the flesh portions of the fish. Annual averages for K-40 ranged from b
2800 1 1600 pCi/kg, wet (1984)to400014400 pCi/kg, wet (1981).
Individual K-40 results ranged from 1600 1 300 pCi/kg, wet (station 32, May 1981) to
(
9900 1 900 pCi/kg, wet (station 25,May1981). Cs-137 was detected in all years, except 1984 (as of May,1984). Annual Cs-137 averages ranged from
{
22 1 13 pCi/kg, wet (1982) to 30 1 39 pCi/kg, wet (1981).
Individual Cs-137 results ranged from 6.113.0 pCi/kg, wet (station 25, Oct. 1983) to 56 1 39 pCi/kg, wet (station 25, May 1981).
Since it is present in global fallout, the occasional detection of Cs-137 in environmental media is not unusual. Because of its relatively long half-life, the abundant gamma of Cs-137's equilibrium daughter (Ba-137), and the b
[
[
Table 6 Preoperational Summary Report
{
Direct Radiation-Thermoluminescent Dosimetry Average Annual Dose Rates - 1981 through 1984 Year (I)
Dose Rate (mR/ year) 1981-M 69.4 1981-A 62.1
[
1982-M 69.4 1982-A 76.7 1983-M 80.3 r
1983-A 69.4 L
1984-M 76.7 1984-A 80.3 Preoperational Average-M 76.7 I
Preoperational Avgge-A 73.0 Oakl ey,1972 82.2 l
(1) M = Average dose rate calculated from individual monthly I
results. A = Average dose rate calculated from individual annual results.
j I
(2) Oakley's value is for Ohio and includes a terrestrial component of 45.6 mR/ year and an ionizing cosmic ray l
component of 36.6 mR/ year (excludes neutron component).
l I
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Table 7 Preoperational Summary Report
(
Ganna Spectrometry of Fish Samples Annual Averages (I) - 1981 Through 1984
{
Results in Units of pCi/kg (wet) 12s Year K-40 Cs-137 Others 1981 4000 1 4400 30 1 39 (2) 1982 3400 1 1500 22 1 13 (2) 1983 3900 1 2600 28 1 25 (2) 1984 2800 1 1600 (2)
(2)
(1) Positive activities only, simple average 12s.
(2) Only LLD's reported or not detected.
E c
L
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E r -
I chemical properties of cesium, this isotope is the one most frequently observed resulting from long-term fallout.
(Note:
to determine the activity of Cs-137 (a pure beta emitter) through gamma spectrometry, the gamma emitting equilibrium daughter of Cs-137 (Ba-137) is measured.)
C.
Sediment The processes by which radionuclides and stable elements are concentrated in bottom sediments are complex, involving physicochemical interaction in the environment between the various organic and inorganic materials from the watershed. These interactions can proceed by a myriad of steps in which the elements are adsorbed on or displaced from the surfaces of colloidal particles enrir ed with chelating organic materials. Biological action of bacteria and n ner benthic organisms also contribute to the concentration of certain elements and in the acceleration of the sedimentation process.
I Table 8 presents the average annual concentrations of the various gamma emitting isotopes detected in the sediments sampled from the PNPP environment.
K-40 was detected in all samples with annual averages ranging from 12,000 1 10,000 pCi/kg, dry (1982) to 17,000 1 10,000 pCi/kg, dry (1981).
Individual K-40 results ranged from 7300 1 700 pCi/kg, dry (Station 26, Oct. 1982) to 24,000 1 4000 pCi/kg, dry (station 26, May, 1981).
The man-made radioisotope, Cs-137, was detected in samples from all years except 1984 (as of May, 1984). Annual Cs-137 averages ranged from 200 1 150 pCi/kg, dry (1983) to 370 1 420 pCi/kg, dry (1982).
Individual Cs-137 values ranged from 24112 pCi/kg, dry (Station 27, May 1981) to 670 + 150 pCi/kg, dry (station 32, May 1982). Since it is present in global fallout, the occasional detection of Cs-137 in environmental media is not unusual.
Co-60 was detected in 4 samples from 1981, with an annual average of 1401 90 pCi/kg, dry.
Individual Co-60 values ranged from 87130 pCi/kg, dry to 190 1 30 pCi/kg, dry. On October 16, 1980, the Peoples Republic of China conducted an above-ground nuclear weapons test (reference 4).
Depa rtment of Energy (D.O.E.) monitoring data indicate that high altitude debris from m
M M
M M
M M
M M
M Table 8 Preoperational Sumary Report Gama Spectrometry of Sediment Sanples Annual AveragesIII - 1981 Through 1984 Results in Units of pCi/kg (dry) + 2s Uranium-233 Daughters Thorium-232 Daughters Year K-40 Cs-137 Co-60 81-214 Pb-214 Ra-226 Bi-212 Pb-212 T1-208 Ac-228 R a-224 Others 1981 17,000 1 10,000 220 1 330 140 1 90 1100 1 600 1100 1 800 1100 1 730 780 1 580 830 1 680 280 1 290 850 1 570 2400 1 1800 Ce-144 9 {4) 950 1 130 1932 12,000 1 10,000 370 1 420 (2) 570 1 230 910 1 760 1300 1 670 790 1 490 680 1 900 480 1 190 770 1 840 2700 1 2300 (2) 1983 13,000 1 6,000 200 1 150 (2) 800 1 480 900 1 510 850 1 480 940 1 170 590 1 430 710 1 380 740 1 510 (2)
(2)
O 1984 12,000 1 4,000 (3)
(2) 970 1 810 940 1 640 940 1 690 (2) 650 1 480 680 + 390 860 1 600 (2)
(2) u e
(1) Positive activities only, simple average 12s.
(2) Not Detected.
(3) Only LLDs reported.
(4) Positive activity detected in only (1) one sample. In these cases the error reported is the 25 counting error for the individual analysis.
I the test passed over the east coast of the United States about 19 days after the announced detonatio1 date. The presence of Co-60 in Pf4PP sediment samples in 1981 may be attributed to this weapons test. One would expect to detect increased levels of activity in air initially and then, after deposition and settling, to appear in sediments.
An assortment of daughters from the naturally occurring uranium and thorium decay chains were also detected. Average annual values for these radioisotopes ranged from 280 1 290 pCi/kg, dry (T1-208, 1981) to 2700 1 2300 pCi/kg, dry (Ra-224,1982).
Individual values for the uranium and thorium daughters ranged from 150 1 20 pCi/kg, dry (T1-208, station 27 May 1981) to 3400 1 1000 pCi/kg, dry (Ra-224. Station 26,flov. 1981).
Beginning in 1983, Sr-89 and Sr-90 analyses were performed on sediment samples.
tio detectable activity has been observed.
D.
Airborne Particulates/ Airborne I-131 Average monthly gross beta results for airborne particulates are listed in Table 9 and plotted in Figure 5.
Airborne 1-131 results are not tabulated since there was no detectable activity during the pre-operational program.
In considering the results of gross activity measurements, it is important I
to keep in mind the inherent limitations of gross beta counting for mixtures of unknown composition. The counting efficiency for an unknown mixture of activities varies considerably with the energy of decay and the amount of absorbing material in the sample. Because of this, the results of gross activity measurements are difficult to interpret. Gross activity measurements are used primarily as a screening device to determine whether further analyses should be performed.
Average monthly gross beta activity in airborne particulates ranged from I
12 1 7 E-03 pCi/m3 (May 1983) to 25 1 10 E-03 pCi/m3 (Jan. 1984).
Individual weekly gross beta results ranged from 4.714.6 E-03 pC1/m3 (station 1, April 1984) to 42 1 8 E-03 pCi/m3 (station 5, Oct. 1981).
I i
[
Table 9 Preoperational Summary Report Gross Beta in Air Particulate Filters Monthly Averages (1) - October 1982 Throug1 August 1904 3
Year Month Activity (E-03pCi/m 2s) 1982 October 21 + 17 November 21 I 7 December 19111 Ar.nual Y 20 1 12 1983 January 17 1 6 February 20 1 17 March 13 + 9 April 13 T 7 May 12 7 7
{,
June 22 7 22 July 19 1 15 August 22 + 15 September 20I7 October 19 + 16 November 19 I 8 December 2419 Annual Y 19 1 14 1984 January 25 1 10 February 18 + 5 March 17 7 11 April 1219 May 13+5 June 16 I 11 I
July 1819 August 23 1 5 Annual I 17 1 12 1
(1) Simple average 12s. Annual average (and its 2s) is calculated from the individual station results.
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I Average quarterly gamma spectrometry data is presented in Table 10. Cosmogenic Be-7 was the only nuclide detected in the composite samples. Quarterly averages 3
' for Be-7 ranged from 49116 E-03 pCi/m3 (Q4, 1983) to 68 1 16 E-03 pCi/m (Q1,1984).
Individual Be-7 results ranged from 39119 E-03 pCi/m3(station 35, Q1, 1983) to 94 1 28 E-03 pCi/m3 (station 5, Q3, 1983).
E.
Water Gamma spectrometry results are not tabulated since there was no detectable activity during the pre-operational period.
Monthly gross beta averages are found in Table 11 and plotted in Figure 6.
Average monthly activities ranged from 2.011.3 pCi/1 (January,1984) to 6.4 1 4.8 pCi/l (June, 1983).
Individual monthly gross beta activities ranged
[
from 1.4 1 1.4 pCi/l (station 34, Jan. 1984) to 9.0 1 1.3 pCi/l (station 37, June,1983).
Quarterly tritium averages are found in Table 12. All LLD values were found for quarter 4 of 1982 and quarters 1 and 4 of 1983. Average quarterly activities
(
ranged from 220 1 70 pC1/1 (Q3, 1984) to 780 1 200 pCi/l (Q2, 1983).
Individual tritium activities ranged from 190 1 190 pC1/1 (stations 34 and 37, Q3, 1984) to 780 1 200 pCi/l (station 37, Q2, 1983).
Beginning in 1983, quarterly Sr-89 and Sr-90 analyses were performed on water samples.
In 1983, positive Sr-90 activity (0.62 1 0.61 pCi/1) was detected in one August sample from station 28.
In 1984, positive Sr-90 activity (1.4 1 0.5 pCi/1) was detected in one February sample from station 36. There was no detectable Sr-89 activity.
F.
Milk / Silage Average annual gamma spectrometry of milk results are found in Table 13.
There was no detectable I-131 in milk during the program.
Table 10 Preoperational Summary Report Gamma Spectrometry of Composited Air Particulate Filters Quarterly Averages (I) - Fourth Quarter 1982 Through Second Quarter 1984 3
Results in Units of E-03 pC1/m 2s Year Quarter Be-7 Others 1982 4
51 1 24 (2) 1983 1
49 1 15 2) 2 53 + 17 3
62 I 33 4
49116 Annual 7 54 1 25 1984 1
68 + 16 (2) 2 55113 (2)
Annual 7 61 1 20 (1) Positive activities only, simple average 12s. Annual average (and its 2s) is calculated from the individual station results.
(2) Only LLDs reported og not detected. _ _ _ _ _ _ _
f r
Table 11 Preoperational Summary Report Gross Beta in Water Monthly Averages (II - September 1982 Through July 1984 Year Month Activity (pCi/l 1 2s) 1982 September 4.6 1 1.3 October 3.7 + 2.5 L
November 4.2 I 1.7 December 4.2}1.2 Annual i 4.2 1 1.7 1983 January 4.6 1 1.6 February 2.9 1 1.4 March 3.0 + 0.4 April 3.5 7 0.9
/
May 5.4 I 2.7 6.414.8(2)
L June July 5.5 1 1.5 August 5.1 1 2.7 g
September 3.2 + 2.1 i
h October 3.5 I 2.8 November 4.2 I 3.0 December 4.3I4.9 f
Annual i 4.2 1 3.3 1984 January 2.0 1 1.3 February 2.5 + 1.9 March 5.4 7 2.8 April 2.5 I 0.6 L
May 4.5I5.3 June 3.5 + 2.3 July 3.4I1.2 Annual i 3.4 1 3.3 F
(1) Positive activities only, simple average 1 2s. Annual average (and its 2s) is calculated from the individual station results.
(2) Positive activity detected in only (1) one sample, in these cases the error reported is the 2s counting error for the individual analysis.
40-5
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Table 12 4
Preoperational Summary Report Tritium in Water, Quarterly Composite by Location Quarterly AveragesIII - Third Quarter 1982 Through Third Quarter 1984 Year Quarter Activity (pCi/l 1 2s) f 1982 3
310 + 160(4) 4 (5)
Annual Y 310 1 160(4)
(5) 1983 1
2 780 + 200(4) 3 300 T 120 4
(3)
Annual Y 420 1 490 1984 1
300 + 200 490 T 190
)
~
220 1 70 3
Annual 7 280 1 220 (1) Positive activities only, simple average 12s. Annual average (and
(
its 2s) is calculated from the individual station results.
Only September 1982 data was used to calculate Third Quarter average.
Tritium water samples were not collected during October,1982.
Positive activity detected in only (1) one sample.
In these cases the error reported is the 2s counting error for the individual analysis.
1 Only LLDs reported.
Only July 1984 data was used to calculate the Third Quarter average. _. _......
Naturally occurring K-40 was detected in all milk samples. Annual averages ranged from 1300 1 100 pCi/1 (1982) to 1500 1 500 pCi/1 (1983).
Individual K-40 results ranged from 8601150 pCi/1 (station 33, July 1983) to 20001 200 pCi/1 (station 29, Oct. 1983).
Cs-137 was detected in fourteen milk samples during the program, eight in 1983 and six in 1984. Annual averages ranged from 2.411.7 pC1/1 (1983) to 3.0 1 2.3 pC1/1 (1984).
Individual Cs-137 results ranged from 1.411.3 pC1/1 (station 29, Sept.1983) to 4.411.6 pC1/1 (station 29, May 1984).
Beginning in 1983, quarterly Sr-89 and Sr-90 analyses were performed on milk samples (Table 14). Positive Sr-90 activity was detected in six samples, two in 1983 and four in 1984. Annual averages ranged from 0.84 1 0.70 pCi/1 (1984) to 2.7 1 2.4 pC1/1 (1983).
Individual Sr-90 results ranged from 0.471 0.43 pC1/1 (station 33, Feb. 1984) to 3.5 1 1.5 pC1/1 (station 30, Nov. 1983).
Average annual gama spectrometry of feed / silage results are presented in Table 15. Naturally occurring K-40 was detected in all samples. Annual averages ranged from 4900 1 700 pC1/kg, wet (1982) to 8100 1 10,000 pCi/kg, wet (1984).
Individual K-40 results ranged from 2600 1 300 pCi/kg, wet (station 31, Aug. 1984) to 18,000 1 2000 pCi/kg, wet (station 31,Aug.1984).
Cosmogenic Be-7 was also detected in many of the feed / silage samples. Annual f
averajes ranged from 360 1 330 pCi/kg, wet (1983) to 5000 1 2600 pC1/kg, wet (1982).
Individual Be-7 results ranged from 240 1 120 pCi/kg, wet (station
(
29, Aug. 1983) to 5000 1 2600 pCi/kg, wet (station 33, Oct.1982).
G.
Vegetation Average annual results for gama spectrometry of vegetation are presented in Table 16. Naturally occurring K-40 was the only nuclide detected. Annual averages ranged from 1900 1 1500 pCi/kg, wet (1982) to 210012000 pCi/kg, wet (1984).
Individual K-40 resuits ranged from 630 1 200 pCi/kg, wet (station 40, Sept.1983) to 41001500 pC1/kg, wet (station 38, July 1984).
1 Table 13 c
Preoperational Summary Report Gamma Spectrometry of Milk Samples Annual Averages (I) - 1982 Through 1984 Results in Units of pC1/112s Year K-40 Cs-137 1982 1300 1 100 (2) 1983 l
1500 1 500 2.4 1 1.7 1984 1500 1 400 3.0 1 2.3 (1) Positive activities only, simple average 12s.
(2) Only LLDs reported.
l
(
i
(
-44
e Table 14 Preoperational Summary Report Strontium-90 in Milk Annual Averages (1) - 1983 Through 1984 Year Activity (pC1/112s) 1983 2.7 1 2.4 1984 0.84 1 0.70 (1) Positive activities only, simple average 12s.
h f
Table 15 Preoperational Summary Report Gamma Spectrometry of Feed / Silage Annual Averages (I) - 1982 Through 1984 Results in Units of pCi/kg (wet) 12s Year K-40 Be-7 1982 4900 _+ 700(2) 5000 _+ 2600(2)
~
1983 7000 1 6000 360 1 330
[
1984 8100 1 10,000 1200 1 900 L
T (1) Positive activities only, simple average 12s.
(2) Positive activity detected in only (1) one sample.
In these cases the error reported is the 2s counting error for the individual analysis.
r t
L E -
Table 16 L
Preoperational Summary Report
[_
Gamma Spectrometry of Vegetation Samples Annual Averages (I) - 1982 Through 1984 l
L
(
Results in Units of pCi/kg (wet) i 2s Year K-40 1982 1900 1 1500 j
1983 2100 1 1800 1984 2100 1 2000
(
(1) Positive activities only, simple average 12s.
L
(
-[
1 I
l I
L-t.....
W v
v
-v v
m--
Tabla 17 Summary of Data for the Perry NPP Radiological Environmental Monitoring Program - 1981 Through 1984 I
(Sheet 1 of 5)
Name of Facility: Perry NPP Units I and 2. Docket Nos. 50-440 and 50-441 Location of Factifty: 35 Miles Northeast of Cleveland, Ohio (Lake County)
Reporting Period: March 23,1981 Through October 2,1984 All Indicator location with Hlqhest Preoperational Mean Medium er Type and total Locatio Name Distance, and Mean (f)(2)
ControlLocgons Mean(f)dI Pathway SampleJ Mumber of Lower Limi f
Mean (f)
(Units of Measurement) Analyses Performed Detection (Range)
Direction (Range)
(Range)
TLDs Ganna Dose-991 0.21 (913/913) Station 18 0.28 (41/41) 0.20 (78/78)
(mR/ day)
(0.07 - 0.37) 5.0 miles 5 (0.19 - 0.37)
(0.11 - 0.36)
Fish Gamma - 66 (pC1/kg wet)
K-4 0 3900 (32/32)
Only one indicator location 3300 (31/34)
(1800 - 9900) sampled for this medium (1600 - 4700)
Cs-137 150 36 (9/32) 21 (11/34)
(20 - 56)
(6.1 - 46) 4 Co-58 130 LLD LLD Co-60 130 LLD LLD l
Cs-134 130 LLD LLD l
Fe-59 260 LLD LLD l
Zn-65 260 LLD LLD Sediment Gamma Spec-28 (pCl/kg, dry)
K-40 14,000 (21/21) Station 26 15,000 (7/7) 13,000 (7/7)
(7300 - 24000) 4.2 miles ENE (7300 - 24,000)
(8800 - 16,000)
Cs-137 180 280(13/21)
Station 26 340 (6/7) 230 (5/7)
(24 - 470) 4.2 mile ENE (150 - 470)
(38 - 670)
Co-60 150 (3/21)
Station 26 170 (2/7) 87 (1/7)
(120 - 190) 4.2 miles ENE (150 - 190)
(87 - 87)81-214 940 (17/21)
Station 26 1200 (6/7) 700 (6/7)
(430 - 1500) 4.2 miles ENE (630 - 1500)
(510 - 980)
M g
W m
v n
-v m
m Yable 17 Sus: mary of Data for the Perry NPP Radiological Environmental Monitoring Program - 1981 Through 1984 (Sheet 2 of 5)
Name of Facility: Perry NPP Units I and 2. Docket Nos. 50-440 and 50-441 Location of facility: 35 Miles Northeast of Cleveland. Ohio (Lake County)
Reporting Period: March 23.1981 Through October 2. 1984 All Indicator location with Highest Preoperational Mean Medium or Type and total Locatlo Name, Distance,ar.d Mean (f)III Control Locgons Mean(f)gI Pathway Sampled Number of Lower Limi f
Mean (f)
(Units of Measurement) Analyses Performed Detection (Range)
Direction (Range)
(Range)
Sediment (pC1/kg, dry)
(Continued)
Pb-214 1000 (21/21 Station 26 1300 (7/7) 810 (7/1)
(460 - 1600 4.2 miles ENE (590 - 1600)
(570 - 970)
Ra-226 1100 (19/21)
Station 26 1300 (6/7) 810 (6/7)
(490-1800) 4.2 miles ENE (1100 - 1600)
(630 - 980) b Bi-212 890 (6/21)
Station 25 960 (1/7) 610 (2/7)
?
(610 - 1200) 0.6 alles NNW (960 - 960)
(550 - 660)
Pb-212 740 (20/21)
Station 26 900 (7/7) 580 (7/7)
(270 - 1600) 4.2 mile ENE (320 - 1300)
(280 - 900)
TI-208 620 (13/21)
Station 26 830 (4/7) 530 (5/7)
(150 - 940) 4.2 miles ENE (590 - 940)
(250 - 880)
Ac-228 810 (19/21)
Station 26 980 (7/1) 740 (5/7)
(280 - 1400) 4.2 miles ENE (430 - 1200)
(580 - 1000)
Ra-224 2900 (3/21)
Station 25 3500 (1/7) 1900(2/7)
(1800 - 3500) 0.6 miles NNW (3500 - 3500)
(1900 - 1900)
Ce-144 950 (1/21)
Station 26 950 (1/7)
(3)
(950 - 950) 4.2 miles ENE (a50 - 950)
Cs-134 150 LLD LLD Strontium-8 Sr-89 LLD LLD Sr-90 LLD tto
~w m
v_
_v.
.m m-
~
Tablo 17 Summary of Data for the Perry NPP Radiological Environmental Monitoring Program - 1981 Through 1984 (Sheet 3 of 5)
~
Name of Facility: Perry NPP Units 1 and 2. Docket Nos. 50-440 and 50-441
'J Location of Facility: 35 Miles Northeast of Cleveland Ohio (Lake County)
Reporting Period: March 23.1981 Through October 2.1984 All Indicator Location with Highest Preoperational Mean Medium or Type and total Locati Name, Distance, and Mean(f)(2 ControlLocgons Lower Limi{Ijf Mean(f)N)
Mean (f)
)
Pathway Sampled Number of (Units of Measurement) Analyses Performed Detection (Range)
Direction (Range)
(Range) j I,
Gross Beta-582 10 18 (463/484)
Station 5 19 (92/97) 18(96/98)
Airborne Particu 3) lates (E-03 pCl/m (4.7 - 42) 0.6 miles SW (8.1 - 42)
(5.7 - 37) l l
Ganna Spec-42 Be-7 56 (29/35)
Station 5 62 (6/7) 54 (6/7)
(39 - 94) 0.6 miles SW (46 - 94)
(40 - 72)
Ce-144 LLD LLD d,
Cs-134 50 LLD LLD o
Nb-95 LLD LLD l
Zr-95 LLD LLD l
Airlogine 1-131 - 583 0.07 LLD LLD (pct /m )
l Water (pC1/l)
Gross Beta-92 4
4.0 (65/69)
Station 37 4.5 (21/23) 3.9 (23/23)
(1.4 - 9) 4.1 miles ENE (1.5 - 9)
(1.6 - 6.2)
Ganna Spec-Ba-140 60 LLD LLD Co-58 15 LLD LLD Co-60 15--
LLD LLD Cs-134 15 LLD LLD Cs-137 18 LLD LLD Fe-59 30 LLD LLD La-140 15 LLD LLD Mn-54 15 LLD LLD Nb-95 15 LLD LLD Zn-65 30 LLD LLD Nr-95 30 LLD LLD
~ ~ ~ ~ ~ ~ ~ ~ ~ ~
w---
Table 17 Summary of Data for the Perry NPP Radiological Environmental Monitoring Program - 1981 Through 1984 -
(Sheet 4 of 5)
~
Name of Facility:, Perry NPP Units I and 2. Docket Nos. 50-440 and 50-441 Location of Facility: 35 Miles Northeast of Cleveland. Ohio (Lake County)
Reporting Period: March 23. 1981 Through October 2.1984 All Indicator Location with Highest Preoperational Mean Medium or Type and total Mean(f)gI Name, Distance, and Mean (f)gII ControlLocgons Locatto Mean (f)
Ps -
Sampled.
Number of Lower Limi f
(Units of Measurement) Analyses Performed Detection (Range)
Direction (Range)
(Range)
Water (pCl/l)
Tritium-36 2000 350 (9/27)
Station 37 410 (4/9) 240 (2/9)
(Continued)
(190 - 780) 4.1 miles ENE (190 - 780)
(240 - 240)
Strontium-8 Sr-89 LLD LLD Sr-90 1.4 (1/4)
Station 36 1.4 (1/4) 0.62 (1/4)
(1.4 - 1.4) 3.9 alles WSW (1.4 - 1.4)
(0.62 - 0.62)
Milk (pC1/l)
Gamma Spec-105 K-40 1600 (70/70)
Station 31 1700 (11/11) 1300 (35/35)
(1100 - 2000) 1.4 miles ESE (1500 - 1900)
(860 - 1500)
Cs-137 18 2.7 (13/70)
Station 31 3.6 (1/11) 2.0 (1/35)
.(1.4 - 4.4) 1.4 miles ESE
.(3.6 - 3.6)
(2.0 - 2.0)
Ba-140 60 LLD LLD Cs-134 15 LLD LLD La-140 15 LLD LLD lodine-131 - 105 1
LLD LLD Strontium-Il Sr-89 LLD LLD Sr-90 1.6 (4/8)
Station 30 2.4 (2/3) 1.1 (2/3)
(0.72 - 3.5) 2.3 miles SSW (1.3 - 3.5)
(0.47 - I.8)
1 N
L-V W7 v
v v
Table 17 Summary of Data for the Perry NPP Radiological Environmental Monitoring Program - 1981 Through 1984 (Sheet 5 of 5)
Name of Facility: Perry NPP Units I and 2. Docket Nos. 50-440 and 50-441 Location of Facility: 35 Miles Northeast of Cleveland. Ohio (Lake County)
Reporting Period: March 23.1981 Through October 2,1984 All Indicator tocation with Highest Preoperational Mean Medium or Type and total Lower Limi{Ijf Mean(f)g)
Name, Distance, and Mean (f)I2)
ControlLocgons Locatto Mean (f)
Pathway Sampled Number of (Units of Measurement) Analyses Performed Detection (Range)
Direction (Range)
(Range) 1 l
Feed / Silage Gamma Spec-14 I
(pCi/kg, wet) l Be-7 890 (5/10)
Station 29 1000 (2/4) 2900 (2/4) l (240 - 1800) 1.4 miles ESE (240 - 1800)
(890 - 5000) 1 K-40 8200 (10/10)
Station 31 10,000 (2/2) 5700 (4/4) l (2600 - 18,000) 1.4 miles ESE (2600 - 18,000)
(2800 - 11,000)
Cs-134 60 LLD LLD Cs-137 80 LLD LLD e
Vegetation Ganua Spec-21 s
l (pCi/1)
K-40 2000 (21/21)
Station 38 2300 (11/11)
Only indicator loca-(630 - 4100) 1.1 mile E (980 - 4100) tions sampled for this medium j
1 l
Cs-134 60 LLD l
Cs-137 80 LLD l-131 60 LLD (1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on An Acceptable Radiological Environmental Monitoring Program, Revision 1 November 1979.
(2)(f) is the ratio of positive results to the number of samples analyzed for the parameter of interest.
(3) Not Detected.
I I
5.0 LAND USE SURVEY I
The annual land use survey was performed in the environs of the Perry NPP on July 9th and July 10th 1984(5)
The purpose of this survey was to identify the potential indicator milk sampling locations as well as the nearest vegetable garden and residence in each of the sixteen standard sampling sectors around I
the plant. The outer bound of the survey for identifying the " nearest" or potential indicator locations was 5 miles.
In addition, candidate " control" milk sampling locations were verified. Table 18 identifies the nearest garden and residence in each sector for which one could be identified within the 5 mile radius. Table 19 identifies all the potential indicator milk sampling locations within 5 miles of the plant. Control milk sampling locations are
, given in Table 20.
I E
I I
I I
I I
I I - -
Table 18 Nearest Gardens and Residences by Sector Identified During the 1984 Perry NPP Annual Land Use Survey Nearest Residence Nearest Garden Direction (Distance / Address)
(Distance / Address)
NE 0.6 miles 0.6 miles 4384 Lockwood 4384 Lockwood i
ENE 1.0 miles 1.1 miles 4602 Lockwood 4611 Lockwood E
1.2 miles 1.2 miles 2684 Antioch 2684 Antioch f
ESE 1.2 miles 1.2 miles 2774 Antioch 2774 Antioch SE 1.2 miles 1.0 mile 4495 North Ridge 4495 North Ridge SSE 0.8 miles 0.8 miles 3119 Parmly 3119 Parmly S
0.9 miles 0.8 miles
(
3121 Center 3157 Center SSW 0.9 miles 1.5 miles 3850 Clark 3787 North Ridge SW 1.2 miles 1.3 miles 3440 Clark 3078 Perry Park WSW 1.2 miles 1.2 miles 3462 Parmly 2970 & 2971 Perry Park Note: Closest residences and gardens are not identified for sectors over water. These sectors are as follows:
W, WNW, NW, NNW, N, and NNE.
(
y..
k Table 19 Milk Animals Identified During the(g84
(
Perry NPP Annual Land Use Survey
[
Number / Type Location of Animals Comments 1 mile SSE 3 Goats 3291 Parmly (and 2 kids) 2 miles E 12 Goats 2541 Townline 2.6 miles SSE 1 Dairy cow No longer has goat; 2 beef 3907 Cal 1 animals
(
1.1 mile S 3 Goats 3830 Center
(
1.4 miles SE 2 Goats 4776 North Ridge 1.4 miles ESE 2 Goats Waites, sampling location (2) 2908 Antioch 2.6 miles SSE 1 Dairy cow Possible future sample
(
4761 Davis location 1.4 miles ESE 10 Goats Hofer, sampling location (2) 2897 Antioch 2.3 miles SSW 30 Goats Manley, sampling location (2) 3203 North Ridge (1) All locations are within 5 miles of the plant.
i (2) Participant in the Perry NPP Radiological Environmental Monitoring Program.
(
(
Table 20 ControI II) Milk Sampling Locations Identified g
(
During The 1984 Perry NPP Annual Land-Use Survey Location Description 12 miles SSE Brookglen Farm (2) 8187 Callow Road Major dairy herd 11 miles SSE Rettger 13863 Painesville -
Major dairy herd Warren Road (1) Control locations are greater than 10 miles from the plant.
(2) Participant in the Perry NPP Radiological Environmental Monitor-ing Program.
[
[
[
L D
E C
[
[ -
l l
l
6.0 CONCLUSION
S I
l The preoperational radiological environmental monitoring program for the Perry Nuclear Power Plant has fulfilled the objectives as stated in Section 1.0.
Procedures, equipment, and techniques have been evaluated and modifica-l tions, when necessary, have been implemented. Important pathways to be monitored I
af ter the plant is in operation have been identified. Background levels of radiation and concentrations of radioactive, materials in environmental media in the area surrounding the plant have been measured. Finally, baseline l
data for statistical comparison with future operational analytical results have been established. A statistical summary of the preoperational results l
appears in Table 17.
' There were no unusual levels of radiation or concentrations of radioactive l
materials during the PNPP preoperational program. The man-made radioisotope, 1
Cs-137, was detected during all years of the program and in a variety of media.
l This isotope is the one most frequently observed resulting from long-term global l
f allout. Cesium-137 was detected at its expected range of activities. Cobal t-60 l
was detected in 4 sediment samples from 1981. Since it is also present in global fallout, the occasional detection of Co-60 is not unusual, however, this particular instance can probably be attributed to the October 1980 Chinese i
weapons test (reference 4).
In general, the PNPF data are comparable to data obtained at other sites during the preoperational phase.
I l
I ll 1
[
(
(
7.0 REFERENCES
(
1.
National Council on Radiation Protection and Measurements, Environmental Radiation Measurement, NCRP Report No. 50, Washington, D.C. December 27, 1976 2.
U. S. Nuclear Regulatory Comission, An Acceptable Radiological Environ-mental Monitoring Program, Radiological Assessment Branch Technical Position, November 1979, Revision 1.
3.
Oakley, D.C., Natural Radiation Exposure in the United States, ORP/SID 72-1 Office of Radiation Programs, U. S. Environmental Protection Agency, Washington, D.C., June 1972.
4.
Department of Energy, Environmental Monitoring in the Vicinity of the Savannah River Plant, Annual Report for 1980, DPSPU 81-30-1.
5.
NUS Corporation, " Perry Nuclear Power Plant Land-Use Survey for 1984.
{
NUS-4628, November 1984.
6.
NUS Corporation, "Preoperational Radiological Environmental Monitoring Program at the Perry Nuclear Power Plant", Partial Annual Report, NUS-4649, 1984.
7.
NUS Corporation, "Preoperational Radiological Environmental Monitoring
(
Program at the Perry Nuclear Power Plant", Annual Report, NUS-4514, 1983.
8.
NUS Corporation, "Preoperational Radiological Environmental Monitoring Program at the Perry Nuclear Power Plant", Annual Report, NUS-4338,
(
1982.
(
9.
NUS Corporation, "Preoperational Radiological Environmental Monitoring Program at the Perry Nuclear Power Plant", Annual Report, NUS-4082A, 1981.
t
7.0 REFERENCES
t 1.
National Council on Radiation Protection and Measurements, Environmental
(
Radiation Measurement, NCRP Report No. 50, Washington, D.C. December 27, 1976 2.
U. S. Nuclear Regulatory Commission, An Acceptable Radiological Environ-mental Monitoring Program, Radiological Assessment Branch Technical Position, November 1979, Revision 1.
(
3.
Oakley, D.C., Natural Radiation Exposure in the United States, ORP/SID 72-1 Office of Radiation Programs, U. S. Environmental Protection Agency.
(
Washington, D.C., June 1972.
4.
Department of Energy Environmental Monitoring in the Vicinity of the Savannah River Plant Annual Report for 1980, DPSPU 81-30-1.
5.
NUS Corporation, " Perry Nuclear Power Plant t.and-Use Survey for 1984.
NUS-4628 November 1984.
6.
NUS Corporation, "Preoperational Radiological Environmental Monitoring
{
Program at the Perry Nuclear Power Plant", Partial Annual Report, NUS-4649, 1984.
7.
NUS Corporation, "Preoperational Radiological Environmental Monitoring Program at the Perry Nuclear Power Plant". Annual Report, NUS-4514,
(
1983.
(
8.
NUS Corporation, "Preoperational Radiological Environmental Monitoring Program at the Perry Nuclear Power Plant", Annual Report, NUS-4338, 1982.
9.
NUS Corporation, "Preoperational Radiological Environmental Monitoring Program at the Perry Nuclear Power Plant", Annual Report, HUS-4082A, 1981.
C ~
[
[
[
[
Appendix A
[
[
[
[
[
[
[
E E
l
[
[
[
haammmmmmmuu u um si e mumimmi u imummm
I APPENDIX A I
LABORATORY QUALITY ASSURANCE I
l 1.
Introduction I
The quality assurance program of the Radiological Laboratory of NUS is briefly described in this appendix.
Information on each incoming sample is enterrd in a permanent log book.
A sample number is assigned to each sample at the time of receipt. This sample number uniquely identifies each sample.
Laboratory counting instruments are calibrated, using radionuclide standards I
obtained from the National Bureau of Standards, the EPA, and reliable commer-cial suppliers, such as Amersham-Searie. Calibration of counting instruments is maintained by regular counting of radioactive reference sources.
Background
counting rates are measured regularly on all counting instruments. Additional performance checks for the gamma-ray scintillation spectrometer include regular checks and adjustment, when necessary, of energy calibration.
Blank samples are processed, with each group of samples analyzed for specific radionuclides, using radiochemical separation procedures. Blank, spiked (known quantities of radioactivity added), and replicate samples are processed periodically to determine analytical precision and accuracy.
I 2.
Laboratory Analyses for Quality Assurance The quality assurance precedures employed in the conduct of radiological monitoring programs by the Environmental Services Division Radiological Labora-tory are as required in the Division Quality Assurance Manual and detailed in the NUS Radiological Laboratory Work Instruction. These procedures include the requirement for (1) laboratory analysis of samples distributed by appropri-ate government or other standards-maintaining agencies in a laboratory inter-comparison program, (2) analysis of some of the client's environmental samples I
k 1
(
split with other independent laboratories, and (3) analysis in duplicate of a specific fraction of the client's environmental samples.
F L
The NUS Radiological 1.aboratory participated in the U.S. Environmental Pro-
[
tectionAgencyRadioactivityIntercomparisonStudies(Cross-check) Program.
L
[
[
[
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E E
E E
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I I
I I
Appendix B I
I I
I I
I I
I I
I I
I I
I w
[
(
APPENDIX B
{
REPORTING OF ANALYTICAL RESULTS In the tables presenting analytical measurements, the calculated value is reported with the two sigma counting error (25) derived from a statistical analysis of both the sample and background count rates. The precision of I
(
the results is influenced by the size of the sample, the background count rate, and the method used to round off the value obtained to reflect the
{
degree of significance of the results. For analytical results obtained from gansna spectral analysis, the precision is also influenced by the composition C
and concentrations of the radionuclides in the sample, the size of the sample, and the assumptions used in selecting the radionuclides to be quantitatively determined. The two sigma error for the net counting rate is:
[R3 + R \\ 1/2 b
2s = 2 t
I)
(s b
Where:
R = sample counting rate 3
Rb = background counting rate
(
t = sample counting time 3
tb = backgrote.d counting time If the measurements on the samples are not statistically significant (i.e.,
{
the two sigma count error is equal to or greater than the net measured value),
then the radioactivity concentrations in the samples are considered not de-tected.
Results reported a less than ("LT") are below the lower limit of detection
(
(LLD). The LLD is defined as the smallest concentration of radioactive mate-rial in a sample that will yield a net count (above system background) that
{
will be detected with 95 percent probability with only 5 percent probability of falsely concluding that blank observation represents a "real" signal.
b
[
For a particular measurement system (that may include radiochemical separation):
4.66s b l'U "
E x V x 2.22 x Y x exp (-Aat) where:
LLD is the lower limit of detection as defined above (as pCi per unitmassorvolume) s is the standard deviation of the background counting rate or b
of the counting rate of a blank sample as appropriate (as counts per minute)
E is the counting efficiency (as counts per disintegration)
V isthesamplesize(inunitsofmassorvolume) 2.22 is the number of disintegrations per minute per picocurie f
Y isthefractionalradiochemicalyield(whenapplicable)
{
A is the radioactive-decay constant for the particular radionuclide At is the elapsed time between the end of sample collection and counting b
The following are definitions or descriptions of statistical terms used in the reporting and analysis of environmental monitoring results.
(
Precision relates to the reproducibility of measurements within a set, that is, to the scatter or dispersion of a set about its central value.
{
Measures of th Central Value of a Set. Mean(orAverageorArithmeticMean)
X of the values of individual results divided by the is the sum j i g
number of results in the set. The mean is given by:
k R = (Xg+X2 +... X ) / " " i 1 n
(
l l
l l
Measures of Precision with a Set.
';andard Deviation is the square root of the quantity (sum of squares of deviations of individual results from j
the mean, divided by one less than the number of results in the set).
The standard deviation, s, is given by:
l (x, - 7)2 / (n.1) s.
1 Standard deviation has the same units as tre measurement.
It becomes a more reliable expression of precision as n becortes larger. When the measurements j
are independent and normally distributed, tne most useful statistics are B
the mean for the central value and the standard deviation for the dispersion.
l Note:
In the USEPA Intercomparison Program, the standard deviation given l
by EPA is for the expected laboratory result from three analyses.
The standard deviation given by NUS is the standard deviation from the mean of three report-ed values.
Relative Standard Deviation is the standard deviation expressed as a fraction of the mean, s/X.
It is sometimes multiplied by 100 and expressed as a percent-age.
l Range is the difference in magnitude between the largest and the smalle:,t l
results in a set.
Instead of a single value, the actual limits are sometimes expressed (minimum value/ maximum value).
1I 1I 1
I
t
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[
[
[
Appendix C
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E
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E E
E
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ummmmm-me m-
.i d
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{
k APPEN01X C
(
DEV!ATIONS FROM THE PROGRAM
{
The following deviations in the PNPP preoperational monitoring program have been documented in the individual Annual Reports (see references).
There were no problems that resulted in serious losses of data. Following is a b
brief summary of the deviations encountered during the preoperational period.
(
Medium Year Deviation Cause of Deviation Ofrect Radiation 1981 Missing TLDs:
Vandalism May, station 7 June, station 24 August, stations 6, 14, y
and 22 L
October, station 6 December, station 22
(
1982 Missing TL0s:
Vandalism January, station 22 February, station 22 October, station 17
(
November, station 15 December, station 6 Annual cycle,17stations
(
6, 15, and 1983 Missing TL0s:
Vandalism
(
June, station 15 L
September, station 8 November, station 21 December, station 2
(
Annual cycle, station 21
{
1984 None
(
(
[
L W
Medium Year Deviation Cause of Deviation
~
s Fish 1981 Sensitivities of Fe-59, Laboratory equip-Co-58 and Zn-65 exceeded ment failures and Branch Technical Position delays in counting, guidelines for several May and November samples, s
1982 None
[
1983 Garana Spectrometry analy-Sample was sis was not performed on destroyed in one May Yellow Perch analysis.
sample from station 25.
~
1984 None
[
Sediment 1981-1984 None Air Particulates/
1982 Nonc
~
Air lodine 1983 March:
Air Particulate Air Sampler mal-and Air lodine samples function.
were not collected from
~
station 5 for the week s
3/1 to 3/8.
~
1984 July: Air Particulate Air sampler mal-sample not collected
- function,
^
from station 3 for the week 7/3 to 7/11.
Son-
~
sitivity for I-131 exceeded Branch Technical Position guidelines.
Water 1983 August, September, Delays in counting.
October:
Sensitivities for Oa-140 and La-140 exceeded Oranch Tech-I nical Position 9uidelines for all stations.
i
!I I
[
E Medium Year Deviation Cause of Deviation Water (cont.)
1984 February:
Sr-89 and Positivo Sr-89
[
Sr-90 analyses were not activity was performed on samplo detected in the from station 34 original sample r
and a confirmatory L
analysis was scheduled.
- However, an insufficient
[
amount of sample remained for re-analysis. No p
data was reported L
since the results could not be confirmed.
Milk 1982 None F
1983 August through November:
Dolays in counting.
L Sensitivities for 04-140 and/or l,a-140 exceeded Branch Technical Position
[
guidelinos for 90% of the samples.
1983 August:
Sr-89 and Sr 90 Insufficiont analysos woro not per-sample for formed on sample from re-anal sis, station 30.
Ort ina resul ts
[
November Sr-89 and cou d not bo Sr 90 analysos were not confirmed, performod on samples
[
from stations 29 and 33, 1984 Nono b
Teod/Silago 1982-1984 Nono Vogotation 1982 1984 Nono I
NNIM 'II'W I'EI
i Appendix 0 Note: This appendix lists detectable measurements only. Lower limits of detection are not included. Any gaps appearing in these tables can be attributed to being either LLO values or missing data, which can l
be found in the annual reports (references 6 through 9) or Appendix C. respectively.
l
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W TAtle C-1 01 rect Radiation - Theracli=timese.t Msimetry Eesults f cr pit:=tr.ly U-* my CWies WIP SIMP 1951-84 (Results in m2/ day)
(Steet 2 cf 4)
Year Locatice. Jemry Fettury N.arcta April May
.7.ca Jaly Aagat Septemter Octcber November December 1952 1
0.19 0.14 0.15 0.15 0.20 0.22 0.17 0.21 0.13 0.20 0.26 0.20 2
0.17 0.13 0.13 0.20 0.20 0.20 0.18 0.19 0.11 0.19 0.26 0.19 3
0.26 0.13 0.17 0.16 0.13 0.20 0.16 0.21 0.12 0.20 0.26 0.22 4
0.16 0.17 0.16 0.23 0.22 0.21 0.18 0.22 0.11 0.20 0.25 0.23 5
0.13 0.14 0.18 0.14 0.18 0.19 0.21 0.25 0.12 0.20 0.26 0.20 6
0.13 0.13 0.21 0.14 0.16 0.17 0.18 0.20 0.11 0.17 0.25 l
7 0.13 0.15 0.15 0.19 0.16 0.21 0.14 0.22 0.12 0.22 0.25 0.22 1
8 0.15 0.16 0.14 0.11 0.18 0.17 0.17 0.22 0.11 0.18 0.23 0.19 9
0.14 0.17 0.13 0.16 0.18 0.18 0.10 0.22 0.18 0.23 0.20 0.20 10 0.16 0.12 0.14 0.18 0.21 0.22 0.17 0.20 0.13 0.21 0.23 0.20 11 0.16 0.15 0.17 0.18 0.18 0.18 0.11 0.23 0.34 0.20 0.26 0.21 12 0.15 0.18 0.13 0.18 0.13 0.18 0.17 0.22 0.32 0.22 0.25 0.20 13 0.16 0.15 0.14 0.19 0.13 0.20 0.21 0.20 0.26 0.20 0.25 0.21 14 0.15 0.15 0.15 0.17 0.16 0.20 0.11 0.21 0.18 0.19 0.23 0.22 15 0.15 0.13 0.14 0.21 0.19 0.22 0.18 0.23 0.21 0.21 0.21 16 0.22 0.21 0.17 0.26 0.24 0.27 0.22 0.28 0.21 0.26 0.28 0.28 17 0.17 0.15 0.17 0.28 0.18 0.26 0.12 0.26 0.20 0.30 0.26 18 0.21 0.21 0.20 0.28 0.27 0.29 0.23 0.36 0.23 0.28 0.32 0.31 19 0.16 0.13 0.15 0.18 0.18 0.20 0.18 0.17 0.17 0.22 0.28 0.22 20 0.20 0.13 0.14 0.21 0.29 0.20 0.12 0.17 0.18 0.20 0.24 0.26 21 0.22 0.16 0.16 0.13 0.17 0.23 0.24 0.17 0.19 0.22 0.26 0.26 22 0.16 0.17 0.11 0.24 0.20 0.16 0.18 0.22 0.25 0.24 23 0.18 0.17 0.15 0.24 0.18 0.24 0.22 0.17 0.20 0.21 0.27 0.25 24 0.23 0.18 0.15 0.15 0.11 0.16 0.12 0.16 0.16 0.25 0.36 0.22 0.23 0.19 35 m
O M
M Y
U O
S M
M M
M M'
M M
Table D-1 Direct Radiation - Thermoluminesent Dosimetry Results for Monthly Exchange Cycles PNPP REMP 1981-84 (Results in mR/ day)
(Sheet 3 of 4)
Year Location January February March April May June July August September October November December 1983 1
0.22 0.20 0.22 0.25 0.23 0.20 0.23 0.28 0.24 0.20 0.19 a.24 2
0.23 0.20 0.22 0.20 0.21 0.24 0.20 0.24 0.23 0.20 0.20 0.23 3
0.22 0.21 0.21 0.21 0.21 0.23 0.27 0.25 0.28 0.21 0.20 0.21 4
0.22 0.21 0.23 0.23 0.22 0.21 0.23 0.23 0.27 0.21 0.18 0.24 5
0.21 0.21 0.22 0.19 0.20 0.19 0.24 0.24 0.23 0.21 0.18 0.22 6
0.21 0.21 0.22 0.18 0.23 0.22 0.27 0.27 0.28 0.20 0.19 0.19 7
0.22 0.19 0.20 0.22 0.24 0.17 0.18 0.24 0.17 0.17 0.20 8
0.20 0.18 0.20 0.15 0.23 0.18 0.20 0.22 0.21 0.21 0.19 0.19 9
0.20 0.19 0.23 0.17 0.25 0.18 0.20 0.23 0.21 0.19 0.19 0.22 10 0.20 0.21 0.23 0.18 0.17 0.20 0.22 0.25 0.22 0.18 0.20 0.20 11 0.23 0.19 0.20 0.20 0.20 0.18 0.22 0.20 0.22 0.19 0.18 0.21 12 0.20 0.19 0.21 0.24 0.18 0.19 0.23 0.21 0.30 0.22 0.20 0.21 13 0.22 C.21 0.20 0.19 0.21 0.17 0.23 0.21 0.23 0.19 0.21 0.22 14 0.20 0.19 0.18 0.21 0.22 0.24 0.21 0.22 0.22 0.22 0.25 15 0.21 0.22 0.23 0.21 0.23 0.28 0.28 0.29 0.27 0.25 0.31 0.24 16 0.26 0.26 0.27 0.22 0.26 0.25 0.24 0.27 0.25 0.22 0.25 0.29 17 0.24 0.22 0.23 0.23 0.22 0.28 0.31 0.32 0.33 0.31 0.30 0.22 18 0.32 0.28 0.28 0.29 0.30 0.20 0.24 0.22 0.26 0.23 0.22 0.22 19 0.20 0.21 0.20 0.19 0.21 0.22 0.24 0.22 0.24 0.21 0.24 0.23 20 0.25 0.23 0.20 0.22 0.21 0.21 0.25 0.27 0.22 0.22 0.23 21 0.24 0.22 0.20 0.23 0.23 0.26 0.25 0.21 0.25 0.23 0.22 0.23 22 0.24 0.21 0.23 0.25 0.23 0.23 0.24 0.24 0.24 0.23 0.24 0.23 23 0.25 0.22 0.22 0.27 0.25 0.20 0.28 0.22 0.23 0.21 0.21 0.20 24 0.24 0.18 0.21 0.24 0.23 0.20 0.20 0.21 0.20 0.21 0.20 0.19 35 0.19 0.17 0.19 0.21 0.20 0.24 0.24 0.23 0.20 0.20 0.23
W W
W W
W W
W W
W W
M M
M M
M M
M M
M.'
Table D-1 i
Direct Radiation - Thermoluminesent Dosimetry Results for Monthly Exchange Cycles PNPP REMP 1981-81 (Results in mR/ day)
(Sheet 4 of 4)
Year Location January February March April May June July August September October November December 1984 1
0.17 0.17 0.10 0.24 0.19 0.23 0.16 0.24 0.22 2
0.18 0.18 0.12 0.19 0.20 0.23 0.21 0.21 0.21 3
0.20 0.20 0.19 0.22 0.20 0.15 0.21 0.26 0.24 4
0.17 0.20 0.10 0.18 0.21 0.18 0.22 0.29 0.24 5
0.17 0.18 0.12 0.17 0.19 0.20 0.21 0.25 0.22 6
0.18 0.20 0.13 0.19 0.20 0.28 0.26 0.22 0.22 7
0.16 0.17 0.09 0.16 0.16 0.14 0.19 0.21 0.21 8
0.17 0.16 0.10 0.12 0.19 0.17 0.21 0.24 0.23 9
0.16 0.19 0.17 0.21 0.21 0.21 0.18 0.23 0.21 10 0.17 0.19 0.09 0.17 0.17 0.21 0.23 0.20 0.21 11 0.17 0.17 0.07 0.32 0.18 0.21 0.21 0.24 0.19 12 0.18 0.21 0.17 0.21 0.21 0.16 0.18 0.18 0.24 13 0.17 0.16 0.15 0.20 0.21 0.20 0.17 0.24 0.23 14 0.18 0.17 0.15 0.22 0.23 0.20 0.24 0.25 0.24 15 0.23 0.21 0.14 0.26 0.23 0.35 0.25 0.27 0.32 16 0.20 0.24 0.17 0.22 0.26 0.24 0.29 0.28 0.26 17 0.25 0.25 0.27 0.32 0.28 0.28 0.28 0.37 0.32 18 0.18 0.20 0.17 0.20 0.19 0.23 0.22 0.23 0.23 19 0.19 0.20 0.19 0.20 0.17 0.26 0.14 0.24 0.22 20 0.19 0.20 0.20 0.23 0.24 0.26 0.34 0.27 0.27 21 0.18 0.18 0.18 0.22 0.26 0.20 0.22 0.25 0.24 22 0.21 0.22 0.19 0.25 0.21 0.21 0.21 0.24 0.22 23 0.17 0.21 0.16 0.21 0.19 0.20 0.24 0.25 0.23 24 0.16 0.19 0.16 0.22 0.18 0.16 0.16 0.23 0.22 35 0.16 0.14 0.18 0.19 0.23 0.22 0.21 0.24
Table D-2 Direct Radiation - Thermoluminescent Dosimetry l
Results for Annual Exchange Cycles l
PNPP REMP 1981-84 (Results in mR/ day)
Location 1981 1982 1983 1984 l
0.18 0.21 0.19 0.19 2
0.17 0.19 0.15 0.19 3
0.15 0.21 0.17 0.20 4
0.18 0.22 0.18 0.20 5
0.14 0.19 0.16 0.18 6
0.19 0.16 0.18 7
0.15 0.18 0.17 0.21 8
0.15 0.21 0.17 0.20 9
0.15 0.18 0.15 0.21 10 0.17 0.19 0.16 0.18 11 0.14 0.20 0.16 0.23 12 0.18 0.18 0.18 0.20 13 0.12 0.20 0.16 0.20 14 0.25 0.20 0.19 0.21 15 0.16 0.21 0.24 l
16 0.20 0.24 0.21 0.27 l
17 0.17 0.22 0.25 18 0.23 0.30 0.30 0.32 19 0.15 0.21 0.21 0.23 20 0.16 0.22 0.23 0.21 21 0.18 0.23 0.23 22 0.20 0.23 0.22 0.22
(
23 0.19 0.22 0.22 0.24 24 0.18 0.22 0.21 0.23 35 0.17 0.19 f
L_
L I
(
Table D-3 Gamma Spectrometry of Fish Samples PNPP REMP 1981-84 (Results in pCi/kg (wet))
(Sheet 1 of 2)
-Year Location Fish Species Cs-137 K-40
(
1981 25 Freshwater Drum 4900 25 Spottail Shiner 2100 25 Walleye 51 3400 25 Yellow Perch 56 9900 32 Brown Trcut 30 4600 32 Carp 11 3000 32 Freshwater Drum 2900 32 Spottail Shiner 1600 32 White Sucker 14 4200
(
32 Yellow Perch 19 3000 32 Yellow Perch 4300 h
1982 25 Freshwater Drum 3000 25 Freshwater Drum 3500 25-Perch 2500
('
25 Rainbow Smelt 2800 25 Stone Cat 4000 25 Walleye 5900
(
25 White Bass 4700
(
25 White Sucker 3700 25 White Sucker 3600 25 White Sucker 3000
(.
25 Yellow Perch 28 3200 32 Freshwater Drum 17 2800
(
32 Freshwater Drum 28 3300
(
32 Golden Redhorse 2900 32 Rainbow Smelt 2800 32 Walleye h
32 Walleye 3000 32 White Bass 2900 32 White Bass 3400 f
32 White sucker 3400 y
32 White Sucker 3200 32 Yellow Perch 3800 32 Yellow Perch 16 3100
I Table D-3 I
Gamma Spectrometry of Fish Samples PNPP REMP 1981-84 (Results in pCi/kg (wet))
(Sheet 2 of 2)
I Year Location Fish Species Cs-137 K-40 l
1983 25 Carp 4600 25 Freshwater Drum 38 3400 I
25 Freshwater Drum 3100 25 Rock Bass 3900 25 Smallmouth Bass 36 4300 8
25 Walleye 2200 25 White Bass 25 8500 25 White Bass 24 3600 I
25 White Sucker 6.1 3700 25 White Sucker 4400 25 Yellow Perch 25 Yellow Perch 20 4300 32 Carp 3300 32 Freshwater Drum 23 2800 I
32 Freshwater Drum 46 3500 32 Walleye 3100 32 Walleye 18 3700 32 White Bass 4100
'32 White Bass 43 5100 32 White sucker 4700 32 White sucker 3600 I
32 Yellow Perch 3900 32 Yellow Perch 2000 1984 25 Freshwater Drum 2500 25 Walleye 2700 25 White Bass 2300 I
25 White Sucker 3900 25 Yellow Perch 1300 32 Freshwater Drum 1900 I
32 Walleye 3200 32 White Bass 32 Yellow Perch 3800 I
I
M M
C Table D-4 Gansna Spectrometry of Sediment Samples PNPP REMP 1981-84 (Results in pCi/kg (dryll Year Location Bi-214 Pb-214 Ra-226 Pb-212 T1-208 Ac-228 K-40 Cs-137 Co-60 Bi-212 Ra-224 Ce-144 1981 25 1200 1300 1100-980 440 1100 17000 190 26 1300 1500 1300 1200 1100 24000 450.
190 950 27 460 490 310 150 410 9700 24 32 800 810 720 470 250 680 12000 38 550 25 1300 1300 1400 910 1100 24000 390 26 1500 1600 1600 1300 1100 17000 390 150 1200 3400 27 800 820 980 720 600 15000 150 120 710 1800 32 830 950 970 760 680 16003 160 87 660 1900 1982 25 1500 1600 1400 14000 3500 26 1300 800 1100 16000 400 27 1200 1800 800 21000 390 32 870 900 900 770 14000 670 1900 25 690 750 1300 490 630 8800 140 960 26 630 590 1300 320 590 430 7300 470 610 27 430 490 1100 270 420 280 7500 32 520 570 280 440 8800 120 1983 25 1000 1100 1100 580 740 12000 26 1000 1300 1100 890 920 850 15000 150 880 27 560 700-630 590 620 13000 32 980 970 980 680 880 1000 15000 160 25 660 680 670 470 620 620 9600 310 26 1100 1100 1100 790 940 1100 18000 190 1000 27 540 590 570-310 430 380 10000 32 560 720 640 380 570 580 11000 1984 25 1200 890 1000 510 810 710 14000 26 1400 1400 1400 1000 880 1200 9800 27 750 710 130 490 500 660 13000 32 510 750..
630 580 520 12000
Q Q
W D
I W
D
. Table D-5 Gross Beta in Air Particulate Filters PNPP REMP 1981-84 (Results in E-03 pC1/m3)
(Sheet 1 of 2) i I
1982 1983 1984 Month.
1 3
4 5
6 35 1
3 4
5 6 35 1
3 4
5 6 35 -
January 20 16 18 16 14 16 24 23 -25. 24 29 26 19 10 16 16 21 16 28 23 27 27 25 23 19 20 17 16 17 16 '
31 29 31 31 34 32
- 19. 15 15 23 23 19 23 20 14 17 17 19 February 15 13 11 12 15 12 18 20 14 19 18 19 31 29 35 35 34 34 17 17 15 16 21 16 28 23 24 16 18 21 14 21 16 18 19 18 12 13 15 14 13 16 23 19 13 16 17 19 March 17 21 15 20 20 14 14.12 8.1 12 13 18 18 13 14 8.7 15 27 27 28 29 23 20 7.2 11 8.2 5.7 16 20 18 14 13 13 8.1 13 12 11 11 8.7 17 19 15 16 12 17 April 15 14 to 12 15 17 14 15 13 13 13 16 9.1 13 15 15 15 15 11 12 8.1 15 12 9.3 9.2 4.7 7.6 8.1 8.1 5.7 7
9.6 16 18 22 13 12 6.5 11 8.3 10 9.5 6.3 13 14 16 14 17 12 19 21 18 18 19 18 May 15 13 17 12 13 11 16 16 13 12 15 13 7.2 8.4. 11 11 9.6 12 8.6 13 9.9 13 11 9.7 11 18 19 12 16 13 12 17 18 16 8 8.6 7.7 13 11 13 12 16 15 June 8.4 20 21 15 18 14 17 27 22 20 26 '26 30 23 23 23 27 25 26 34 41 29 40 34 24 12 15 15 15 12 14 14 6.6 10 9.8 9.9 13 9.2 14 13 20 13 12 9 10 9.7 11 8.6 6.3
1 Table D-5 Gross Beta in Air Particulate Filters.
PNPP REMP 1981-84 (Results in E-03 pC1/m3)
(Sheet 2 of 2)
%)
1982 1983 1984 Month 1
3 4
5 6 35 1
3 4
5 6 35 1
3 4
5 6-35 l
11 14 11
- 12. 12 10 22 16 22 17 18 July 16 12 14 15 11 25 20 22 26 22 20 35 28 23 32 25 22 16 19 14 20 17 17 12 14 12 11 12 16 11 14 13 8.6 27 29 25 24 20 26 24 21 17 16 19 21 25 28 21 22 20 24 August 11 9.8 11 10 21 24 20 20 24 23 25 23 22 26 25 24 31 34 31 33 29 29 September 19 22 18 20 25 22 4
i 18 17 14 22 19 20 19 23 23 16 25 23-15 21 15 17 25 19 October 22 18 14 19 15 32 33 30 32 27 30 36 32 35 42 37 13 9.6 13 13 16 12 l
15 21 15 12 15 25 27 21 23 29 26 16 14 16 15 9.9 11 11 13 13 11 20 22' 22 20 28 15 16 18 16 13 14 15 November 22 21 16 19 17 18 21.21 17 21 21 17 l
21 19 20 18 15 17 17 16 17 18 16 17 23 28 27 26 25 24
.15 17 16 15 18 15 26 23 20 20 23 17 26 24 26 28 22 21 December 11 9 17 19 9 11 19 20 17 15
- 16. 17 20 23 24 26 32 27 24 26 24 23 23 26 22 18 15 22 22 19 23 22 20 29 22 24 l
18 17 27 11 15 22 24 31 25 29 24 29 20 23 19 23 21 16 25 27 25 31 29 24
k
[
Table D-6 Gamma Spectrometry of Composited Air Particulate Filters PNFP RE:4P 1981-84 (Results in E-03 pCi/m3)
Be-7 L
Quarter Location 1982 1983 1984 IL 1
1 57 57 3
57 61 4
44 63 5
46 76 6
52 72 35 39 76 5
2 1
62 3
59 60
~(
4 47 44 5
51 6
52 35 58
{
3 1
61 3
53 4
49 5
94 6
64 35 52 4
1 51 3
58 4
40 44 5
51 52 6
44 40 35 71 B
l lI1 1llll 1!
m m
re b
0081 0759 m
m e
4435 3327 ce D
re b
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Table D-8 Tritium in Water Quarterly Composite by Location
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PNPP REMP 1981-84 (Results in pCi/1)
Year Quarter Location Value 1982 3
37 310 1983 2
37 780
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3 28 240 36 310 37 360 1984 1
36 300 2
36 490 3
28 240 34 190 36 260
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T1bla D-9 Gamma Spectrometry of Milk Samples PNPP REMP 1981-84 (Results in pCi/1)
Year Location January February March April May June July August September October November December Element: K-40 1982 33(1) 1300 1300 1400 33 1300 1
1983 29 1300 1500 1500 1400 1700 1600 1200 1800 2000 1700 1400 f
30 1600 1800 1200 1500 1100 1600 1900 1700 1700 1400 33 1300 1200 1300 1100 1200 1300 860 1300 1300 1500 1500 1300 29 1600 1800 1900 1700 1700 1S00 1700 30 1600 1400 1300 1700 1500 1300 1600 33 1300 1400 1100 1400 1100 1000 1400 1.
1984 29 1400 1600 1600 1700 1800 1700 1700 1800 1
30 1400 1400 1300 1500 1500 1400 1600 1700 31 1600 1500 1700 1700 1900 1800 1800 33 1500 1300 1400 1300 1300 1300 1200 1300 29 1800 1700 1800 1700 1
30 1400 1500 1500 1600 31 1600 1700 1500 1700 l
l 33 1300 1300 1400 1300 Element: Cs-137 1983 29(2) 3.4 3.5 1.4 1.6 29 1.8 30 2.3 2.0 3.1 1984 29 2.1 4.4 30 1.7 4.0 31 3.6 33 2.0 (1) Station 33 is listed twice since there was semi-monthly sampling in November, 1982.
(2) Station 29 is listed twice since there was semi-monthly sampling in September, 1982.
Cs-137 was detected in both September samples from station 29.
L.
i Table D-10 Strontium-90 in Milk PNPP REMP 1981-84 (Results in pCi/1)
Year Month station Sr-90 1983 August 33 1.8
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1983 November 30 3.5 L
1984 February 29 0.85 30 1.30
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31 0.72 33 0.47
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Table D-11 Gamma Spectrometry of Feed / Silage PNPP REMP 1981-84
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(Results in pCi/kg (wet))
Year Location Be-7 K-40 1982 33 5000 4900 1983 29(1) 240 6500 29(2) 6500 30(1) 470 12000
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30(2) 6000 33(1) 3900 f
1984 29(1) 1800 11000
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29(2) 5600 30(1) 1100 9200 30(2) 4900
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31(1) 860 18000 31(2) 2600 33(1) 890 11000
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33(2) 2800
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(1) Pasture grass / hay I
(2) Grain L
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Table D-12 Gamma Spectrometry of Vegetation Samples PNPP REMP 1981-84 (Results in Units of pCi/kg (wet))
Year Station Vegetation Type K-40 I
I 1982 38 Peaches 1800 38 Acorn Squash 2800 38 Pears 1200 38 Cauliflower 2700 38 Apples 980 38 Cabbage 2100 1983 38 Squash 3700 38 Cabbage 2000 39 Apples 1700 39 Peaches 1800 40 Tomatoes 2400 40 Cucumbers 2200 40 Peppers 630 I
1984 38 Zucchini 1800 38 Peppers 2500 38 Beets 4100 39 Tomatoes 1800 I
39 Apples 1200 39 Corn 2800 39 Cucumbers 1200 39 Peaches 1400
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Appendix E r
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5
APPENDIX E f
NUS ANALYTICAL PROCEDURES Environmental samples for radiological monitoring programs are collected and analyzed in accordance with procedures described in detail in individual work instructions. The work instructions used in the Radiological Laboratory have been drawn from published analytical methods, including those of the Environmental Measurements Laboratory, DOE (formerly Health and Safety Laboratory
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of the U. S. Energy Research and Development Administration) and the laboratories of the U. S. Environmental Protection Agency. The current versions of these published manuals, copies of methods published in the Regulatory Guides of the U. S. Nuclear Regulatory Commission, and other compendia of government or industry approved analytical methods are at hand at NUS and were relied upon as the basis for laboratory protocol.
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Adaptions and summaries for use by the 1aboratory personnel of the detailed procedures from the above mentioned sources were prepared by the senior labora-tory staff on the basis of their professional knowledge and appraisal of methods and of recent improvements in technique and instrumentation. These work instructions were then reviewed by knowledgeable personnel and approved by the Manager, Radiological Laboratory, in radioanalytical program wo9 Summaries of the typical laboratory operations are presented below.
Sample Preparation
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Samples are processed prior to analysis to satisfy a number of conditions.
Sieving and grinding operations are performed to obtain homogeneous samples and permit removal of representative aliquots. Volume reduction is used to match standard counting geometries or to meet required sensitivities.
Other processes may be used to obtain specific fractions of samples for analy-(
sis (e.g., filleting to obtain edible fractions of fish). Chemical and physi-cal processing will also be used to remove interferences when a specific
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nuclide is being measured.
Preparations of various sample types for the Fermi-2 program are presented below.
Air Particulates For determination of gross alpha and gross beta, air filters are mounted for counting in stainless steel planchets and counted in low-background gas-g L
- proportional counting system. All air filter samples are counted at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> af ter collection in order to allow natural radon and thoron radioactiv-ities to decay.
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For determination of gamma emitters, an individual air filter sample or several air filter samples composited by stacking ara placed in a plastic dish.
The dish is covered, placed on a high resolution germanium detector, and the ganina-ray spectrum obtained. The observed spectral data are processed to obtain radionuclide concentrations.
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Water For the measurement of beta on total water samples, 200 milliliters of water of low solids content (i.e., well, drinking, river, etc.) is evaporated to a low volume in a Teflon beaker; the sample is then transferred to a stainless steel planchet, evaporated to dryness, and weighed to establish the self-absorption correction.
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For the analysis of gamma emitters, up to 3 liters of the total water sample are accurately dispensed into a Marinelli beaker of appropriate size. The
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beaker containing the sample is placed on a high resolution germanium detector, and counted using a multi-channel pulse height analyzer. Background data is obtained with a Maririelli beaker containing distilled water.
To determine tritium in water, a portion of the sample is distilled to remove f
impurities and an accurately measured volume of the distillate is added to a liquid scintillation counting vial containing a liquid scintillation cocktail.
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The sample is counted in a liquid scintillation counter.
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Milk
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A preservative, such as formalin, normally is added to the sample in the field, as soon as possible after collection and mixed thoroughly with the milk. Carrier solutions for specified elements may also be added at time of collection.
For gama spectrometric analysis, three liters of the milk sample are accurately dispensed into the Marinelli beaker. The beaker containing the sample is
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placed on a high resolution germanium detector and counted using a multichannel pulse height analyzer. The observed spectral data is processed to obtain the specific radionuclide concentrations.
Biological Tissues A sufficient amount of raw tissue sample (to yield about 20 grams of ash) l is placed in a heat-resistant dish of suitable size, weighed, and dried for about 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at about 200'C.
The dried sample is ashed in a muffle furnace.
l If Cs-137 analysis is to be performed on the ash,. the maximum ashing temperature is 540'C. The ash weight is obtained and the sample is screened and stored in a plastic container for future analysis.
For gross beta analysis, approximately one hundred milligrams of the ashed l
sample is transferred to a stainless steel planchet, accurately weighed, and distributed evenly on the planchet with a minimum amount of distilled j
water. The sample is dried under a heat lamp and counted in a low-background gas-propcetional counting system.
l For gamma spectrometry of a biological material, the ashed, dried, or raw sample is transferred to a suitably sized plastic container and weighed.
The sample container is sealed, placed on high resolution germanium deter. tor, and counted using a multi-channel pulse height analyzer.
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f.
Vegetation
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A sufficient amount of raw vegetation sample (to yield approximately 30 grams of ash) is placed in a heat-resistant dish, weighed, and dried overnight in an oven at about 110'C.
If the analysis is to be performed on ash, the
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sample is dried as above or on a hot plate set at low heat and ashed in a muffle furnace. After ashing, the ash is weighed, screened and stored for future analysis.
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For determination of gamma emitters, the ashed, dried, or raw sample is trans-ferred to a plastic container, weighed, and the container is sealed. The
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sample container is placed on a high resolution germanium detector and counted using a multi-channel pulse height analyzer. Samples of leafy foods such as cabbage, lettuce, or chard may be pureed in a blender and the sample counted
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in a 3-liter Marinelli beaker to avoid loss of iodine by drying or ashing.
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Soils and Sediment
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Approdmately 500 grams of the soil or sediment sample are oven-dried overnight at 110'C-125'C. The dried sample is ground to a fine consistency, screened, and stored in a plastic container for future analysis.
For determination of gama emitters, 150-200 grams of the prepared soil or h
sediment sample are transferred to a plastic container and weighed. The container is sealed, placed on a high resolution germanium detector, and
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counted using a multi-channel pulse height analyzer.
RADI0 CHEMICAL SEPARATIONS In the analysis of specific isotopes, chemical separations are often necessary to remove interferences or improve sensitivity. The separation methods used in this program are summarized below.
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l kl Iodine-131 in Milk or Water
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To analyze for I-131 in milk or water, iodine carrier (as iodide) is added to the sample and mixed well.
Iodine carrier and activity are separated from the milk or water by adsorption on an ion-exchange resin.
Iodine is
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stripped from the resin by oxidation with hypochlorite solution. The separated iodine is purified by solvent extraction of elemental iodine and finally precipitated as copper iodide. The precipitate is filtered and weighed to determine the chemical yield, then mounted for counting in a low-background
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beta counter or a beta-gama coincidence counter.
MEASUREMENT INSTRUMENTATION
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Proportional Counting Low background gas proportional counters are used for measurement of alpha
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and beta decay.
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Tennelec LB-5100 Automatic Low Background Alpha / Beta Counting Systems and Beckman Widebeta-II's are " pancake type" gas-flow proportional counters with four inches of lead shielding and anti-coincidence guard counters to reduce
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the background counting rate. Samples are changed and counted automatically.
Teletype readouts are used.
Reference source and background counting rates are measured daily and recorded
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in a log. After each gas cylinder change the reference sources are measured at the " plateau point", " low test", and "high test" positions to be sure that the detector is operating on a plateau.
Berthold 770's are alpha / beta counting systems with ten gas-flow sample detectors and a common guard detector. Samples are changed manually. The plateau is checked at 50 volt intervals each time a new tank of gas is installed.
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Backgrounds, blanks, and check sources are counted at the time of use of this instrument and recorded in a separate log.
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The alpha and beta radioactivity concentrations are calculated from the observed counting rates corrected for background. Background counting rates are obtained
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using a blank in the same geometry as the sample. Beta and alpha reference samples are counted on a routine basis.
Liquid Scintillation Counting
~
Both ambient and refrigerated liquid scintillation counters are used for measuring low energy beta emitters. All use automatic changing of samples containea in low-background vials. A teletype readout is used.
Sealed, unquenched tritium and background sources, provided by the manuf acturer,
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are measured frequently to determine that the response of the instrument has not changed significantly. Results of these measurements are recorded in a log kept in the laboratory.
Standard tritium spiked samples and blank samples are counted with each group of samples to determine the counting efficiency and background counting rate.
The results of the measurements are recorded in a log.
Tritium activity is calculated from the observed counting rates using a tritium counting efficiency determined from the HTO standards counted under the same conditions as the samples.
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Gamma Soectrometry Samples for gama spectrometric analysis are placed in 3-liter or 1-liter Marinelli beakers, 2-1/4 inch diameter plastic dishes or 3-1/4 inch plastic dishes, or other geometries depending on the volume available for analysis.
I Prepared samples are then counted on one of several gama spectrometry systems.
Gama spectrometry is performed with high resolution germanium detectors, l
either GeLi or HpGe.
Pulse height analysis is performed with Canberra Series 85 MCAs and a PDP 11/44 data analysis system.
Spectra are analyzed with l
the Spectran-F software supplied by Canberra. The energy calibration of I
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this system is checked with an NBS mixed gamma source. Performance checks and operating records are maintained in a log.
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Thermoluminescent Dosimetry
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The thermoluminescent dosimetry (TLD) system used by NUS for environmental radiation monitoring utilizes Teflon-calcium sulf ate: dysprosium activated
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(Teflon-CaSO :Dy) dosimeters for high sensitivity. The dosimeters are read 4
in a Teledyne Isotopes Model 8300 reader. The dosimeters are exposed in
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the field in a special environmental badge which includes various filte. s to assess the contribution of various gama-ray energies to the observed exposure. There are four primary and four backup readout areas per TLD card.
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The dosimetry system is calibrated by reading dosimeters which have been exposed in an accurately known gama radiation field. The performance of the TLD reader is checked and adjusted, if necessary, immediately before
(
reading a batch of dosimeters using procedures described in the manufacturer's instruction manual for this system. These checks include the measurement
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of reader response to a reference light source built into the instrument.
The radiation dose accumulated by the TLDs before placing them in the field
{
is eliminated by annealing the dosimeters shortly before placing them at the site to be measured. Correction for radiation dose accumulated in-transit between the field location and the NUS Laboratory is made by annealing appropri-ate control dosimeters in order to determine the dose accumulated by the
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TLDs for each part of the shipping cycle. The control dosimeters are returned to the laboratory for readout at the same time as the exposed field dosimeters.
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