ML20195B624
| ML20195B624 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 12/31/1998 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20195B622 | List: |
| References | |
| 56, NUDOCS 9906020077 | |
| Download: ML20195B624 (121) | |
Text
__
Docket No:
PEACH BOTTOM ATOMIC POWER STATION UNITS 2 and 3 Annual Radiological Environmental Operating Report Report #56 1 January Through 31 December 1998 Prepared By v
PECO Nuclear a Unit of PECO Energy 965 Chesterbrook Blvd.
Wayne, PA 19087-5691 DO OD0cd o5000$77 R
PDR May 1999
Docket No:
PEACH BOTTOM ATOMIC POWER STATION UNITS 2 and 3 Annual Radiological Environmental Operating Report Report #56 1 January Through 31 December 1998 Prepared By PECO Nuclear 965 bhesIerhr b kIf[.
Wayne, PA 19087-5691 May 1999
c TABLE OF CONTENTS
- 1. Summary and Conclusions....,......................................................................1
. I I. Introduction..................................................................................
A. Obj.ectives.................................................................................................................3
- 8. 1mP ementat 0n............................................................. _........... _
1 1
Ill. Program Desen. t.p ion..._..
.............................................................................................4 A. Sample C ollection..................................................................................................
B. Data Interpretation....................................................................................................
C. Program Exception,s......................................................... _............ _.. _.......... _ _. 7 D. Program Changes......................................................................................... 7 IV. Results and Discussion......................................................................................
A. Aquatic Environment........................................................................................... 8
- 1. S u rface Water...................................................................................
- 2. Drinking ( Potable) Water.................................................................................. 8
- 3. Fish.................................................................,...............................................9
- 4. Sediment..............................................................................................................9 B. Atmospheric Environment..................................................................................... 10 1, Airborne............................................................................................._.__..._10
- a. Air Particulate s.............................................................................
- b. Ai rborne lod ine...............................................................................
- 2. Terre stri al................................................................................
- a. Milk....................................................................................
.........11 C. Ambient Gamma Radiation.......
...............................................................12 V. R efe ren ce s..................................................................................
l
Radiological Environmental Monitoring Report Summary Appendix A Sample Designation and Locations Appendix B Data Tables and Figures - Primary Laboratory Appendix C Data Tables and Figures - QC Laboratory Appendix D Synopsis of Analytical Procedures Appendix E Quality Control - EPA Intercomparison Program Appendix F PBAPS Surveys
. Appendix G
- )
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-_.___.________-_____-_.__.__._________m__
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1.
Summary and Conclusions This report on the Radiological Environmental Monitoring Program conducted for the Peach Bottom Atomic Power Station (PBAPS) by PECO Nuclear covers the period 1 January 1998 through 31 December 1998. During that time period, 975 analyses were performed on 872 samples.
Surface water samples were analyzed for concentrations of tritium and gamma emitting nuclides. No fission or activation products were found. Tritium activities
~
detected were consistent with those observed in other years.
Drinking water samples were analyzed for concentrations of gross beta (soluble and
~
insoluble fractions), tritium, and gamma emitting nuclides. No fission or activation products were found. Gross beta and tritium activities detected were consistent with those observed in other years.
The remaining sample media representing the aquatic environment included fish and sediment samples. These media were analyzed for concentrations of gamma emitters. Fish samples showed no measurable effects from the operation of PBAPS.
Sediment Location 4J, located below the discharge, showed the activation product Co-60, which was attributable to PBAPS operations. Cesium-137 activity was found at all locations and was consistent with data from previous years. The dose to a teenager's skin from the sediment pathway was calculated to be 1.08 E-03 mrem /yr, which represents 0.005% of the allowable fraction of 10 CFR 50, Appendix I limits.
The atmospheric environment was divided into two parts for examination: airbome and terrestrial.
Sample media for determining airbome effects included air particulates and air iodine samples. Analyses performed on air particulate samples included gross beta and gamma spectrometry. No fission or activation products were found. The gross beta results were consistent with results from the previous years. Furthermore, no notable differences between control and indicator locations were observed. These findings indicate no measurable effects from the operation of PBAPS.
High sensitivity lodine-131 analyses were performed on weekly air samples. All results were less than the minimum detectable activity.
Examination of the terrestrial environment was accomplished by analyzing milk samples for concentrations of lodine-131 and gamma emitters.
No fission or activation products were found.
Ambient gamma radiation levels were measured quanerly throughout the year. All measurements were below 10 mR/std. month and consistent with those measured in previous years. - _________
in assessing all the data gathered for this report and comprising these results with preoperational data, it was evident that the operation of PBAPS had no adverse radiological impact on the environment.
O O.
ll.
Introduction Peach Bottom Atomic Power Station (PBAPS) is located along the Susquehanna River between Holtwood and Conowingo Dams in Peach Bottom Township, York County, Pennsylvania. The initial loading of fuel into Unit 1, a 40 MWe (net) high temperature, gas-cooled reactor, began on 5 February 1966, and initial criticality was achieved on 3 March 1966.
Shutdown of Peach Bottom Unit 1 for decommissioning was on 31 October 1974. For the purposes of the monitoring
' program, the beginning of the operational period for Unit 1 was considered to be 5 February 1966. A summary of the Unit 1 preoperational monitoring program was presented in a previous report m. PBAPS Units 2 and 3 are boiling water reactors, each with a power output of approximately 1159 MWe. The first fuel was loaded into Peach Bottom Unit 2 on 9 August 1973.
Criticality was achieved on 16 September 1973, and full power was reached on 16 June 1974. The first fuel was loaded into Peach Bottom Unit 3 on 5 July 1974. Criticality was achieved on 7 August 1974, and full power was first reached on 21 December 1974.
Preoperational summary reports " for Units 2 and 3 have been previously issued and summarize the results of all analyses performed on samples collected from 5 February 1966 through 8 August 1973.
A.
Objectives The objectives of the REMP are:
1.
To identify, measure, and evaluate existing radionuclides in the environs of PBAPS site and any fluctuations in radioactivity levels which may occur.
2.
To monitor and evaluate ambient radiation levels 3.
To determine within the scope of the program, any measurable quantity of radioactivity introduced to the environment by the operation of PBAPS.
B.
Implementation Implementation of the stated objectives is accomplished by identifying significant exposure pathways, establishing baseline radiological data of media within those pathways, and monitoring those media during plant operation to assess plant effects (if any) on man and the environment.
In order to achieve the stated objectives, the current programs include the following analyses on samples collected:
1.
Concentrations of beta emitters in drinking (potable) water, and air (
particulates.
Concentrations of gamma emitters in surface and drinking (potable) 2.
water, air particulates, milk, fish, and sediment.
3.
Conc ntrations of tritium in surface and drinking (potable) water.
4.
Concin seiions of I-131 in air and milk..
5.
Ambient gamma radiation levels at various site environs.
Ill.
Program Description A.
Sample Collection This section describes the collection methods used to obtain environmental samples for the PBAPS REMP in 1998. Samples for the PBAPS REMP were collected for PECO by Normandeau Associates, RMC Environmental Services Division. (RMC). Sample locations and descriptions can be found in Table B-1 and Figures B-1 through B-3, Appendix B.
Amdic Environment The aquatic environir nt was examined by analyzing samples of surface water, drinking water, fish, end sediment. Surface water from two locations (1LL and 1MM) were collected weekly by automatic sampling equipment Drinking water from two locations (4L and 61) were collected weekly from a
. tank at each location. Both surface and drinking water samples were each composited into separate monthly sample for analysis. Two quarts of water are removed from the tank each week and placed into a clean two-gallon polyethylene bottle to form a monthly coraposite. Control locations were 1LL and 61.
Fish samples comprising the flesh from two groups: Bottom Feeder (catfish) and Predator (smallmouth bass, largemouth bass, or bass) were collected semiannually at two locations: 4 (indicator) and 6 (control) using several ir thods such as trapnet, seine or electroshocking.
Sediment samples composed of recently deposited substrate were collected semiannually at three locations: 4J, 4T (indicators), and 6F (control) using one of two methods, determined by the depth from which the sediment was obtained. In water greater than 4 feet deep, sediment was collected by either a Ponar or Ekman Grab with a surface area of 81 square inches. In shallow i
-'I
water (1-4 feet), sediment was collected by scooping up mud with a plastic bucket.
Atmosoberic Environment
. The atmospheric environment was examined by analyzing airborne and terrestrial samples. These consisted of air particulates, airborne iodine, and milk. Air particulate and air iodine samples were collected and analyzed weekly from five locations (1B,1Z, 2(1C), 3A, and 5H2). The control location was 5H2. Air samples were obtained using a vacuum sampler, glass fiber and charcoal filters, respectively. The filters were replaced weekly and sent to the laboratory for analysis. The vacuum samplers were run continuously at approximately 1 cubic foot per minute.-
Milk samples were collected from five locations (A, G, J, O and R) monthly from December through March and biweekly April through November.
Additionally, samples from seven locations (B, C, D, E, L, P, and T) were collected quarterly. Locations A, B, C, and E were controls. Farm T was a goat farm. Milk samples were obtained by removing two gallons from the dairyman's bulk tank after mixing. The sample from each location was therefore a composite of all the milk collected from the dairy herd (from 1 to 3 milkings). The milk was W from the agitated bulk tank and placed in new plastic containers.
Ambient Gamma Radiation Direct radiation measurements were made using Panasonic 801 calcium sulfate (CaSO4) thermoluminescent dosimeters (TLD). The TLD locations were placed on and around the LGS site as follows:
A site boundary rino consisting of nineteen locations (1L,1P,1A,1Q, 1D,2,1M,1R,11,2B,1C,1J,1F,40, 1NN,1H,1G,18, and 1E) near and within the site perimeter representing fencepost doses (i.e., at locations where the doses will be potentially greater than maximum annual off-site doses) from LGS release.
An intermediate distance rina consisting of nineteen locations (15, 22, 44, 32, 45,.14,17, 31 A, 4K, 23, 27, 48, 3A, 49, 50, 51, 26, 6B, and 42) extending to approximately 5 miles from the site designed to measure possible exposures to close-in population.
The balance of eight locations (43,5,16,24,46,47,18, and 19) representing control and special interests areas such as population centers, schools, etc.....
The specific TLD locations were determined by the following criteria:
1.
The presence of relatively dense population;
- 2. -
Site meteorological data taking into account distance and elevation for each of the 36 ten-degree sectors around the site, where estimated annual dose from PBAPS, if any, would be more significant; 3.
On hills free from local obstructions and within sight of the vents (where practical);
4.
.Near the dwelling closest to the main stack in the prevailing down wind direction.
A TLD set was placed at each location in a locked Formica " birdhouse" or polyethylene jar located approximately six feet above ground level. The TLD sets were exchanged quarterly, then sent to the laboratory for analysis.
B.
Data interpretation Several factors are important in the interpretation of the data. These factors are discussed here to avoid undue repetition in the discussion of the results.
1.
Lower Limit of Detection and Minimum Detectable Activity The lower limit of detection (LLD) was defined as the smallest concentration of radioactive material in a sample that would yield a not count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD was intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criteria for the presence of activity. All analyses were designed to achieve the required PBAPS detection capabilities for environmental sample analysis.
The minimum detectable activity (MDA) is defined above with the exception that the measurement is an after the fact estimate of the
~
presence of activity.
- 2. '
Net Activity Calculation and Reportina of Results Net activity for a sample was calculated by subtracting background activity from the sample activity. Since the REMP measures extremely small changes in radioactivity in the environment, background variations will result in sample activity being lower than !
the background activity effecting a negative number. For a more detailed description of the result calculations, see Appendix E.
Results for each type of sample were grouped according to the analyses performed. For gamma analyses, fifteen nuclides (Be-7, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Zr-95, Nb-95, Cs-134, Cs-137, Ba-140, La-140, Ra-226 and Th-232) were reported.
Annual means and standard deviations of the individual results were calculated.. The standard deviation represent the variability of measured results for different samples rather than the single analysis uncertainty.
C.
Program Exceptions For 1998 the PBAPS REMP had a sample collection recovery rate of better than 99%. The exceptions to this program are listed below:
1.
Drinking water sampler at location 4L was out of service for the following dates:
01/04/98 to 01/09/98 for installation of a new composite sampler and from 06/26/98 to 07/03/98 due to electrical problems. A weekly grab sample was taken.
2.
Air particulate and air iodine samples from location 1C were not available for the period 09/18/98 to 09/25/98 due to a blown fuse.
3.
Air particulate and air iodine samples from location 1Z were not available for the periods of 5/01/98 to 05/08/98 and 06/15/98 to 06/13/98 due to electrical problems.
4.
Farm G went out of business on 11/9/98.
Each program exception was reviewed to understand the causes of the program exception. Sampling and maintenance errors were reviewed with the personnel involved to prevent a recurrence.
Occasional equipment breakdowns and power outages were unavoidable. The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.
D.
Program Changes 1.
A goat farm (T) was added to the quarterly program beginning in February 1998.
Six additional Site TLDs were added to the program in the fourth 2.
quarter 1998. These TLDs will be use to assess the radiological impact of the Interim Spent Fuel Storage Project scheduled for second quarterof 2000.
Air particulate and air iodine sampling location 2 was replaced by 3.
location 1C at the end of the first quarter 1998.
IV.
Results and Discussion A.
Aquatic Environment 1.
Surface Water Samples were collected from two locations monthly (1LL and 1MM).
1LL served as the control location. The following analyses were performed.
Tritium Samples from both locations were analyzed for concentrations of tritium (Table C-l.1, Appendix C). Results ranged from 49 to 140 pCi/l and averaged 81 pCill at the control location and 98 pCi/l at the indicator location.
Cc,nceiigstions found were lower than those observed during the preoperational period.
Gamma Soectrometry Samples from both locations were analyzed for concentrations of gamma emitters (Table C-l.2, Appendix C). No statistically significant fission or activation products were found.
2.
Drinkino (Potable) Water Samples were collected from two locations monthly (4L and 61). 61 served as. the control location.
The following analyses were performed Gross Beta
' Samples from both locations were analyzed for concentrations of gross beta activity in insoluble and soluble fractions (Tables C-II.1 and C-II.2 and Figures C-1 and C-2, Appendix C). Gross beta activity in - - --
I the insoluble fraction ranged from -1.2 to 1.3 pCi/l. The values in the soluble fraction ranged from 1.0 to 5.9 pCi/l. No differences were observed between the means of the control and indicator stations.
The values were generally below those seen in the preoperational period.
Tritium Samples from both locations were analyzed for tritium concentration quarterly (Table C-II.3, Appendix C). The values for the indicator location (4L) ranged from 61 to 170 pCill with a mean of 128 pCi/l.
Control location (61) values ranged from 70 to 140 pCi/l with a mean of 113 pCill. The concentrations found were lower than those observed during the preoperational period.
Gamma Spectrometry Samples from both locations were analyzed for concentrations of gamma emitters (Table C-II.4, Appendix C). ).
No statistically significant fission or activation products were found.
3.
Fish Samples were collected from two locations semi-annually (4 and 6).
The control location was 6. The following analyses were performed.
Gamma Spectrometry Statistically significant activity was observed only for the nuclide K-40 which ranged from 2500 to 3300 pCi/kg (wet) (Table C-Ill.1, Appendix C).
No statistically significant fission or activation products were found. Figure C-3 illustrates the Cs-137 activity for indicator and control locations from the beginning of the operational period through the present.
Cesium-137 activity has declined to non-detectable levels.
4.
Sediment Samples were collected from three locations semi-annually (4J, 4T and 6F). The control location was 6F. The following analyses were performed.
Gamma Spectrometry Samples from all locations were analyzed for concentrations of >
gamma emitters (Table C-IV.1, Appendix C). Statistically significant activity for naturally occurring Be-7, K40, Ra-226 and Th-228 was found at all locations. K-40 results ranged from 8,500 to 22,000 pCi/kg (dry).
Statistically significant activity for the Plant produced nuclide Co-60 was found in both samples from the indicator location 4J located downstream of the discharge. The results ranged from 8 to 52 pCi/kg (dry) for the indicator locations and -4 to 6.2 pCi/kg (dry) for the control location. Statistically significant activity for Cs-137 was found at all
-locations with a mean value of 176 pCi/kg (dry) for the indicator locations and 61'pCi/kg (dry) for the control location. The maximum calculated dose from this pathway to a teenager's skin was 1.08 E-03 mrem /yr. This value is based upon the assumption the maximum concentrations of Co-60 and Cs-137 at the downstream location (4J) were present the entire year. This dose represents 0.005% of the allowable fraction of 10 CFR 50, Appendix I limits. Results found were consistent with those from previous years. Figure C-4, Appendix C illustrates the comparison of activities of Cs-137 detected at the control location and indicator locations from the preoperational period through the present.
B.
Atmospheric Environment 1.
Airborne a.
Air Particulates Samples were collected from five locations (1B,1Z, 2(1C), 3A, and 5H2). Control location was 5H2. The following analyses were performed Gross Beta Samples from all locations were analyzed for concentrations of gross beta (Tables C-V.1 and C-V.2 and Figures C-5 and C-6,
~
Appendix C). Air particulate locations were divided into three groups: Group I, consisting of 1B,1Z, and 2(1C), located on PBAPS site; Group 11, comprised of 3A, located at an intermediate distance from PBAPS; and Group Ill, consisting of SH2, located at a remote distance from PBAPS. Comparison i
of results among these three groups aids in detemMhg the effects, if any, resulting from the operation of _PBAPS. The results from site location samples ranged from 4 E-3 to 42 E-3 1
i pCi/m', with a mean of 17 E-3 pCi/m'.
The results from intermediate distance location ranged from 7 E-3 to 35 E-3 pCi/m*, with a mean of 17 E-3 pCi/m*. The results from the distant location ranged from 5 E-3 to 33 E-3 pCi/m', with a mean of 16 E-3 pCi/m'. Comparison of the values indicate no notable difference among the three groups suggesting no effects from the operation of PBAPS (Figure C-5, Appendix C).
Gamma Spectrometry Weekly samples from five locations (1B,1Z, 2(1C), 3A, and 5H2) were composited and analyzed quarterly for the presence of gamma emitters (Table C-V.3). Naturally occurring Be-7 was found in all samples with activity values similar to those j
from the preoperational years.
No statistically significant i
activation or fission products were detected.
b.
Airborne lodine Continuous air samples were collected weekly at five locations (18,1Z, 2(1C), 3A, and SH2) and analyzed for 1-131 (Table C-VI.1, Appendix C). All results were less than the minimum detectable activity.
I 2.
Terrestrial a.
Milk Samples were collected from twelve locations (A, B, C, D, E, G, J, L, 0, P, R and T). Farms A, B, C, and E were control locations. The following analyses were performed.
lodine-131 Samples from all locations were analyzed for concentrations of I-131 (Tables C-Vil.1, Appendix C). All results were less than i
the minimum detectable activity and ranged from -0.5 to 0.3 pCi/l.
Gamma Soectrometry Samples from five locations were analyzed quarterly for concentrations for gamma emitters (Table C-Vil.2, i
Appendix C).
Naturally occurring K-40 was found in all samples with values ranging from 1,300 to 1,600 pCi/l. All other nuclides searched for were less than the minimum detectable activity. Figure C-7 (Appendix C) illustrates the Cs-137 activity in milk from the beginning of the operational period through the present. Cesium-137 activity has declined to non-detectable levels.
C.
Ambient Gamma Radiation Ambient gamma radiation levels were measured quarterly at forty-six locations (as described in the program description section) using Panasonic 801 (CaSO4) thermoluminescent dosimeters (Tables C-Vill.1 through C-Vill.3 and Figures C-8 and C-9, Appendix C). All TLD readings were below 10 mR/std. month with a range of 3.4 to 7.5 mR/std. month No notable differences were observed between the site, intermediate, and distant TLD
. groupings.
O 4
J VI.
References 1.
Preoperational Environs Radioactivity Survey Summary Report, March,1960 through January,1966. (September 1967).
2.
Interex Corporation, Peach Bottom Atomic Power Station Regional Environs Radiation Monitoring Program Preoperational Summary Report, Units 2 and 3, 5 February 1966 through 8 August 1973, June 1977, Natick, Massachusetts.
3.
Radiation Management Corporation Publication, Peach Bottom Atomic Power Station Preoperational Radiological Monitoring Report for Unit 2 and 3, January,1974, Philadelphia, Pennsylvania.
G I
4 APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT
SUMMARY
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- APPENDIX B: SAMPLE DESIGNATION AND LOCATIONS LIST OF TABLES AND FIGURES TABLES TABLE B-1:
Sample Collection and Analysis Program for the Radiological Environmental Monitoring Program, Peach Bottom Atomic Power
~ * -
Station,1998 FIGURES FIGURE B-1:
Environmental Sampling Locations on Site or Near the Peach Bottom Atomic Power Station,1998 FIGURE B-2:
Environmental Sampling Locations at Intermediate Distances from the Peach Bottom Atomic Power Station,1998 FIGURE B-3:
Environmental Sampling Locations at Remote Distances from the 4
Peach Bottom Atomic Power Station,1998 O
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APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY I
APPENDIX C:
DATA TABLES AND FIGURES - PRIMARY LABORATORY TABLES Table C-l.1 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1998.
Table C-l.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1998.
Table C-II.1 Concentrations of Gross Beta insoluble in Drinking Water Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1998.
Table C-II.2 Concentrations of Gross Beta Soluble in Drinking Water Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1998.
Table C-II.3 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1998.
l Table C-II.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1998.
Table C-Ill.1 Concentrations of Gamma Emitters in Fish Samples Collected in the
)
Vicinity of Peach Bottom Atomic Power Station,1998.
Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1998.
Table C-V.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1998.
Table C-V.2 Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu. meter) in Air Particulate Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1998.
Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1998.
j Table C-VI.1' Concentrations of I-131 in Air lodine Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1998.
Taole C-Vil.1 Concentrations of I-131 in Milk Samples Collected in the Vicinity of i
Peach Bottom Atomic Power Station,1998.
C-i
)
i i
Table C-Vil.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1998.
Table C-Vill.1 Quarterly TLD Results for Peach Bottom Atomic Power Station,1998.
Table C-Vill.2 Mean TLD Results from Peach Bottom Atomic Power Station Site Boundary, Middle, and Outer Rings,1998.
Table C-Vill.3 Summary of the Ambient Dosimetry Program for Peach Bottom Atomic Power Station,1998.
Table C-IX.1 Summary of Collection Dates for Samples Collected in the Vicinity of Peach Bottom Power Station,1998.
FIGURES Figure C-1 Monthly Insoluble Gross Beta Concentrations in Drinking Water Samples Collected in the Vicinity of PBAPS,1998.
Figure C-2 Monthly Soluble Gross Beta Concentrations in Drinking Water Samples Collected in the Vicinity of PBAPS,1998.
Figure C-3 Mean Annual Cs-137 Concentrations in Fish Samples Collected in the Vicinity of PBAPS, 1971-1998.
Figure C-4 Mean Semi-Annual Cs-137 Concentrations in Sediment Samples Collected in the Vicinity of PBAPS, 1971-1998.
Figure C-5 Mean Weekly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of PBAPS,1998.
Figure C-6 Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of PBAPS,1970-1998.
Figure C-7 Mean Annual Cs-137 Concentrations in Milk Samples Collected in the Vicinity of PBAPS, 1971-1998.
Figure C-8 Mean Quarterly Ambient Gamma Radiation Levels (TLD) in the Vicinity of PBAPS, 1973-1998.
C - ii
TABLE C-l.1 CONCENTRATIONS OF TITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF PEACH BOTTOM ATOMIC POWER STATION,1998 RESULTS IN UNITS OF PCL/ LITER +/- 2 SIGMA COLLECTION 1LL 1MM PERIOD JAN MAR 83 t 52 110i50 l
APR-JUN 49tS2 55 t S3 JUL-SEP 80i57 85 57 OCT-DEC.
110i50 140 t 50 MEAN 81 i50 98172 1
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t TABLE C-IL1 CONCENTRATIONS OF GROSS BETA INSOLUBLE IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF PEACH BOTTOM ATOMIC POWER STATION,1998 RESULTS IN UNITS OF PCl/ LITER +/- 2 SIGMA.
COLLECTION 4L 61 PERIOD JAN 0.220.6 1.320.6 FEB 0.410.6 0.320.6 MAR 0.220.8
-0.310.5' APR 0.120.7 0.220.7 MAY
-0.110.7 0.510.7 JUN 0.220.6 0.320.6 JUL 0.420.6 0.820.6 AUG 0.320.3
-0.110.3 l
SEP 0.720.8 1.220.8 OCT 0.120.6 1.020.7 NOV 0.210.8
-0.820.7 DEC 0.720.7
-0.310.8 MEAN 0.010.7 0.0
- 1.5 TABLE 11.2 CONCENTRATIONS OF GROSS BETA SOLUBLE IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF PEACH BOTTOM ATOMIC POWER STATION,1998 RESULTS IN UNITS OF PCl/ LITER +/- 2 SIGMA COLLECTION 4L 61 PERIOD JAN 1.120.8 1.920.9 FEB 1.910.9 1.610.8 MAR 1.9 t 1.1 1.2 i 1.2 APR 5.021.3 3.321.2 MAY 1.020.9 ~
2.021.0 JUN 1.121.0 2.321.1 j
JUL 1.221.0 1.821.1 AUG 1.410.7 1.720.7 SEP 4621.2 4.511.1 OCT 5.421.3 2.911.2 NOV 2.221.3 2.321.3 DEC 5.921.3 4411.2 MEAN 2.7 t 3.8 2.512.2 TABLE 11-3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF PEACH BOTTOM ATOMIC POWER STATION,1998 RESULTS IN UNITS OF PCl/ LITER +/- 2 SIGMA COLLECTION 4L 61 PERIOD JAN-MAR 61 150 140250 APR-JUN 120*50 120250 JUL-SEP 170 260 70 t56 l
OCT-DEC 160260 120150 MEAN 128 1 99 113 *60 C-3
2 394 333 4 7 34 38 4
3 633933 34 336 4
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TABLE C.V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF PEACH BOTTOM ATOMIC POWER STATION,1998 RESilLTS IN UNITS OF E-3 PCl/CU METER +/-2 SIGMA GROUPl GROUP 11 GROUP lt!
VVEEK NO 1B 1Z 2
1C 3A SH2 1
9 23 10 23 9 *3 (2) 12 23 17 14 2
10 t 3 13 23 13 23 (2) 14 *3 11 14 3
12 24 10 t 4 16 24 (2) 11
- 4 12 23 4
16 24 16
- 5 16 24 (2) 16
- 4 16 24 5
16 24 15
- 4 17
- 4 (2) 17 24 15 t 4 6
14
- 4 14 24 14 24 (2) 8*4 18 24 7
10 23 13 24 9 23 (2) 11 14 13
- 3 8
10 t 4 8 14 9 24 (2) 9 24 7*4 9
12 23 11 24 13
- 3 (2) 13
- 4 10 24 10 12 24 12 24 12 24 (2) 15
- 4 8 23 11 14 24 13 24 12 24 (2) 16.* 4 21 24 12 19 24 13 *4 12 24 (2) 13 24 5 23 13 18 24 14 25 15 4 (2) 16 24 25 *5 14 11 24 14 24 12 24 (2) 10 24 13 24 15 20 24 21 24 (2) 20 24 18 24 16 24 16 16 24 13 t 4 (2) 13 14 14 t4 13
- 3 17 17
- 4 18 24 (2) 15 24 15 *4 18 14 18 9*3 (1)
(2) 9*3 10 23 10 23 19 4 23 6 24-p) 8 13 7 13 8 13 20 28 24 24 24 (2) 24 24 25 t4 15 24 21 16 24 16 24 (2) 16 24 16 24 18 13 22 23 *4 28 210 (2) 20 4 17 24 22 25 23 8 23 (1)
(2) 7*3 9 13 13 14 24 10 24 12
- 5 (2) 9 t4 7 24 13 24 25 20 t4 23 24 (2) 19 t 4 18 14 14 24 26 8 24 11 24 (2) 13
- 4 12 24 17 14 27 14
- 4 15
- 4 (2) 15 *4 15
- 4 13 24 28 18 24 18 24 (2) 15 t 4 14 24 13 24 29 25
- 4 19 24 (2) 26 24 25 *4 16 24 30 22 24 20 24 (2) 20 24 17 24 15 24 31 21 24 19 24 (2) 19 24 22 24 19 24 32 15 24 16 14 Q) 14 24 15 24 18 24 33 12
- 4 11 24 (2) 12 24 15 24 12 24 34 35 25 35 15 (2) 31 25 28 24 24 24 35 31 25 32 *5 (2) 27 t 5 27 5 28 25 36 24 24 27 *4 (2) 21 24 30 24 24 24 37 29 25 32 t 5 (2) 42 25 35
- 5 26 *5 38 20 13 19 13 (2)
(1) 21 23 33 t5 39 2B *5 25 25 (2) 26 15 24 25 25 *4 40 11 23 10 t 3 (2) 8 23 11 23 14 23 41 8 t2 9 t3 (2) 11 23 8 22 10
- 3 42 15 23 21 24 (2) 20 24 16 23 13 23 43 26 24 25 t 4 (2) 29 t 4 27 24 18 24 44 13 23 12 23 (2) 12 *3 9 23 17
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TABLE C-VI.1 CONCENTRATIONS OF l-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF PEACH BOTTOM ATOMIC POWER STATION,1998 RESULTS IN UNITS OF E-3 PCl/CU METER +/- 2 SIGMA GROUPI GROUP 11 GROUP fil WEEK NO 18 1Z 2
1C 3A SH2 1
4
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SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION (2)
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1 1 1 1 1
11 1 1 1
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6666 5
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4 0000 7
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1 1 1 1 6
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B 8652 4
1 1 3 2
1 123 6
3183 3
1924 M
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N 9999 999 9999 9999 9999 O
////
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61 69 61 7 61 69 61 /69 6179 R
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1 1 i
T 1 1 1 0 1 1 1 1 1 1 0 1 1 1 0 1 1 1 0 P
////
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////
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0001 0001 N
E O00 C001 N
E O 0001 N
N E
OE E
)
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M 1(
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TABLE C-Vil.1 QUARTERLY TLD RESULTS FOR PEACH BOTTOM ATOMIC POWER STATION,1998 RESULTS IN UNITS OF MILLl-ROENTGENISTD. +/- 2 SIGMA STATION MEAN*
JAN-MAR APR-JUN JUL-SEP OCT-DEC CODE
+/- 2 S.D.
1A 5.420.7 5.8
- 0.5 5.3
- 0.5 5.020.1 5.4204 1B 4.910.5 5.120.5 48*0.5 4620.5 5.120.3 1C 6.120.8 6.520.3 5.710.9 5.810.3 6.220.3 1D 6.0 (3)
(3)
(3) 60204 1E 5.420.2 5.420.8 5.3204 5.620.4 5.520.2 1F 7.1 t 0.6 7.520.6 6.9
- 0.6 6.8106 7.220.2 1G 4.220.5 4.5201 3.9
- O 4 4.220.1 4.3 t 0.2 1H 5810.6 6.0 t 0.6 5.520.6 5.820.1 6.120.3 11 4.620.5 4.920.4 4.3
- 0.6 4420.3 4.720.2 1J 6.720.7 7.110.4 6.420.4 6.510.1 7.020.7 1L 4.2103 4.420.1 4.2
- 0.4 4.1 a 0.2 4.220.4 iM 4.2 (3)
(3)
(3) 4.220.5 1P.
3.9 (3)
(3)
(3) 3.920.2 10 44 (3)
(3)
(3) 4 4 t 0.4 iR 7.3 (3)
(3)
(3) 7.320.5 2
5.5 t 0.5 5.710.5 5.320.9 5.520.3 5.7204 2B 5.7 (3)
(3)
(3) 5.7
- 0.4 3A 4.020.3 4.2 t 0.5 3.820.5 3.910.1 4020.3 4K 3.620.3 3810.3 3.420.3 3.510.3 3.7
- 0.2 5
5.4
- 0.6 5.7
- 0.3 5.1 t 0.8 5.120.1 5.5 t 0.3 1NN 6.5
- 0.4 6.6
- 0.8 6.3
- 0.6 6.320.5 6.710.4 68 4.520.6 4620.2 4.110.2 4.420.3 4.8
- 0.3 14 5.6
- 0.4 5.720.6 5.510.4 5.420.4 5.720.3 15 5.920.9 6.0
- 0.4 5.420.7 5.720.3 6.5204 16 5.910.5 6.120.5 5.720.4 5.6
- 0.3 6.1
- 0.3 17 6.520.8 6.520.5 6.320.1 6.2
- 0.5 7.020.3 18 6.320.7 6.320.6 5.8
- 1.2 6.320.3 6.7
- 0.3 19 6.120.4 6.220.7 5.80.2 6020.2 6.3
- 0.3 22 6.010.4 6.220.4 5.8*04 6.020.5 6.2
- O 6 23 6020.7 6.320.8 5620.3 5.920.7 6.320.5 24 4.5
- 0.6 4.720.3 4 0 t 0.3 4.520.4 4.710.2 26 6.720.5 6.920.3 6420.3 6.620.5 6.8
- 0.5 27 5.821.2 6.320.7 5.0 t 0.9 5.720.2 6.320.3 31A 4.4
- 0.6 4.620.2 3.920.5 4.310.3 4620.3 32 6410.8 6.520.9 5.920.5 6.420.3 6.920.4 40 7.310.3 7.120.6 7.3 $ 0.5 7.2
- 0.4 7.520.3 42 5.020.3 5.220.4 4.820.5 5.020.3 5.0204 43 6.8
- 0.3 6.7*00 6.620.3 6820.3 6.920.0 44 5.620.9 6.120.5 5.120.5 5.6 0.4 5820.2 45 6.3204 6.320.5 6.010.9 6.520.2 6.520.1 46 5.520.5 5.320.6 5.220.2 5.6
- 0.5 5.720.5 47 6.710.6 e.3 2 0.5 6.820.6 7.010.5 6.820.6 48 6.020.2 5820.6 5.920.5 6.020.4 6020.3 49 6,020.9 6.110.5 54i0.4 6.320.2 6.3
- 0.3 50 7.120.4 7 0 t 0.6 6.9100 7.120.3 7.420.2 51 6.320.5 6.320.8 5.9
- 0.5 6.420.6 6.520.2 (1) MEAN AND TWO TIMES THE STANDARD DEVIATION OF THE QUARTERLY RESULTS (2) SEE PROGRAM EXCEPYlONS SECTION FOR EXPLANATION (3). SEE PROGRAM CHANC.ES SECTION FOR EXPLANATION 1
l 1
C-13
I 1998 MEAN TLD RESULTS FROM PEACH BOTTOM ATOMIC POWER STATION TABLE C-Vill.2 FOR THE SITE BOUNDARY, MIDDLE, AND OUTER RINGS 1998 RESULTS IN UNITS OF MILLl-ROENTGEN /STD. MO. +/- 2 STANDARD DEVIATIONS OF THE STATION DATA EXPOSURE SITE RING MIDDLE RING OUTER RING PERIOD JAN-MAR 5.922.1 5.821.7 5.921.5 APR JUN 5.5
- 2.1 5.4 t 1.9 5.311.8 JUL-SEP 5.5
- 2.0 5.721.9 5.621.6 OCT DEC 5.622.3 6.022.0 5.9
- 1.8
SUMMARY
OF THE 1998 AMBIENT DOSIMETRY PROGRAM FOR PEACH TABLE C-Vill.3 BOTTOM ATOMIC POWER STATION RESULTS IN UNITS OF MILLI-ROENTGEN /STD. MO.
LOCATION SAMPLES PERIOD PERIOD PERIOD MEAN PRE-OP MEAN ANALYZED MINIMUM MAXIMUM
+/ 2 S.D.
+/ 2 S.D.
SITE RING 58 3.9 7.5 5.622.1 5.421.7 MIDDLE RING 92 3.4 7.4 5.711.9 5.321.3 OUTER RING 16 4.0 6.7 5.721.6 5.7
- 1.8 THE PRE-OPERATIONAL MEAN WAS CALCULATED FROM TLD READINGS 01/07/73 TO 0845/73 SITE BOUNDARY RING STATIONS 1 A,18,1C,1D,1E,1F,1G,1H,11,1J,IL,1M,1NN,1P,1W,1R,2,28,40 MIDDLE RING STATIONS 3A 4K,5,6B,14,15,17,22,23,26,27,31 A,32,42,43,44,45,46,47,48,49, OUTER RING STATIONS.16,18,19,24 9
C - 14
TABLE C-IX.1
SUMMARY
OF COLLECTION DATES FOR SAMPLES COLLECTED IN THE VICINITY OF PEACH BOTTOM ATOMIC POWER STATION,1998
)
I SURFACE WATER. (TRITIUM)
COLLECTION 1LL 1MM 1
)
PERIOD JAN-MAR 12/31/1997 - 04/01/1998 12/31/1997 - 04/01/1998 APR JUN 04/01/1998 - 07/01/1998 04/01/1998 - 07/01/1998 JUL-SEP 07/01/1998 - 0900/1998 07/01/1998 - 09/30/1998
' OCT-DEC 09/30/1998 - 12/30/1998 09/30/1998 - 12/30/1998 SURFACE WATER ' (GAMMA SPECTROSCOPY) i COLLECTION 1LL 1MM PERIOD.
JAN 12/31/1997 - 01/28/1998 12/31/1997 - 01/28/1998 FEB 01/28/1998 - 02/25/1998 01/28/1998 - 02/25/1998 MAR 02/25/1998 - 04/01/1998 02/25/1998 - 04/01/1998 APR 0401/1998 - 04/29/1998 04/01/1998 - 0429/1998 MAY 04/29/1998 - 08/03/1998 04"29/1998 - 06/03/1998 JUN 08/03/1998 - 07/01/1998 0603/1998 - 07/01/1998 JUL 07/01/1998 - 07/29/1998 07/01/1998 - 07/29/1998 1
AUG 07/29/1998 - 09/02/1998 07/29/1998 - 0902/1998 SEP 0902/1998 - 09/30/1998 09/02/1998 - 09/30/1998 OCT 09/30/1998 - 10/28/1998 09/30/1998 - 10/28/1998 l
NOV 10/28/1998 - 12/02/1998 10/28/1998 - 12/02/1998 DEC 1202/1998-12/30/1998 12/02/1998 - 12/30/1998 i
DRINKING WATER (TRITIUM) l COLLECTION 4L 81 PERIOD JAN-MAR 01/04/1998 - 04/02/1998 01/03/1998 - 04/03/1998 APR-JUN 04/03/1998 - 07/03/1998 04/02/1998 - 07/03/1998 JUL SEP 07/03/1998 - 10/02/1998 07/03/1998 - 10/02/1998 OCT-DEC 10/02/1998 - 01/02/1999 10/02/1998 - 01/02/1999 i
DRINKING WATER (GROSS BETA & GAMMA)
COLLECTION 4L 61 1
PERIOD JAN 01/04/1998 - 01/31/1998 01/03/1998 - 01/31/1998 FEB 01/31/1998 - 02/27/1998 01/31/1998 - 02/27/1998 MAR 02/27/1998 - 04/03/1998 02/27/1998 - 04/02/1998 APR 04/03/1998 - 05/01/1998 04/02/1998 - 0501/1998 l
MAY 05/01/1998 - 06/05/1998 0501/1998 - 06/05/1998 l
JUN 06/05/1998 - 07/03/1998 06/05/1998 - 07/03/1998 JUL 07/03/1998 - 07/31/1998 07/03/1998 - 07/31/1998 AUG 07/31/1998 - 09/04/1995 07/31/1998 - 0904/1998 SEP 09/04/1998 - 10/02/1998 09/04/1998 - 10/02/1998 OCT 10/02/1998 - 10/30/1998 10/02/1998 - 1000/1998 NOV 10/30/1998 - 12/08/1998 10/30/1998 - 12/08/1998 DEC 12/08/1998 - 01/02/1999 12/08/1998 - 01/02/1999 NOV 10/30/97 - 12/07/97 10/30/97 - 12/07/97 C - 15
SUMMARY
OF COLLECTION DATES FOR SAMPLES COLLECTED IN THE VICINITY c TABLE C-lX.1 OF PEACH BOTTOM ATOMIC POWER STATION,1998 w
AIR PARTICULATE & AIR IODINE -
SAMPUNG' 18 1Z 2
1C 3A 5H2 PERIOD
'1 ~
1201.' 01/09/1998 12/31 - 01/09/1998 12/31 - 01/09/1996' 12/31 - 01/09/1998 12/20 - 01/05/1998 01/00 01d8/1998 01/05- 01/12N998 2
012 01/18/1998 L' 01/00 0148/1998 01/00 014 8/1998 01/18 01/25/1998- 01/12 01/19/1996 0148' 01/25N996 01/18 01/25/1998 01N6 - 01/25/1998 3
01G5 01/31/1998 01h8- 01/28N998 4
01/25 01/31/1998 01/25 01/31/1998 01/25 - 01/31/1998 5
01/31 02/08/1998. 01/31 02/08/1998 01/31 02/08/1998
~.
01/31 02/06/1998 01/26- 02/02M998 02 2 - 02/13/1998 02/02 02/09/1998 e 6
'02/06 - 02N3/1998 - 02 2 02/13/1998 02 2 - 02/13/1998
'02/13 - 02/20/1998 02/00- 02n7hS08 7.
02N3 ; 02/20N908 02/13 / 02Q0/1998 02/13 02/20/1998 02/20 - 02/27/1998 02/17- 02/23N998 8-02Q0 02/27/1998 02GO 02/27M998 02/20- 02/27h008 02/27 - 03/06/1998 02/23 - 03/02/1998 9
' 02/27 i 03f08/1998 02/27 03/08/1998 02/27 - 03/06/1996 03M- 03N3/1998 03/02 - 03/0M998. :
l10 03f06 03/13/1998 03M - 03/13/1998 ' 032 - 03/13N996 03/13 03G0/1998 0300 - 03/1M998 !
11 03N3- 03/20/1998 03/13 03/20/1998- 03/13 - 03/20/1998 03/20- 03/27M998 03/16 03G3/1998
.12 03GO. 03/27N006' 03/20 03/27M998 03G0 03G7/1998 03/27- 0403N998 03/23 - 0340/1998 13 03G7 04/03M908 ~ 03/27 - 0403/1998 ' 03/27 - 0403/1998 0403-OW104000 0300 0406/1998 '
14 0403 - 0410/1998 04/03 - 04/10/1998. 04/03 - OW10/1998 OW10- OW17M998 OW10 04/17N998 04/06 - OW13/1998 15 04/10 0W17/1998 OW10 04/17h000' 04/17 - 04/2#1000 04/17 04/24/1998 OW13 04/20/1008 16 04N7- 04GW1908 OW17 04241998.
04/24- 05/01M998 04/24 05/01/1998 04G0 04/27/1998 17 04/24 05/01/1998 OW24- 05/01/t008 05/01 06dOON008 06/01 - 06 DOM 998 04/27 - 06/04N998 18 05/01 - 05dOON998 -
OE M - 06N5N006 0608 06/1M906 - 06 04 05/11/1998 10' 05/06 05/1M998 05/08 05/15/1998 06NS - 05/22/1998 06N5 05/22/1998 05/11 05N8N908 20 05/15- 06/22/1998 ~ 05N5 06/22/1998 21 05/22- 05G9/1998 ' 05/22- 05/20/1998 05/22 05G9/1998 OW22- 05G0/1998 05N6- 05/26/1998 05/29 06/06N998 06GS- 0$054908 05G6 06/01/1998 22-05G9 - 06/05N908 L 05/29 0805N998 08/06 06/13/1998 08/05 - 08/13/1998 0$01 06/08N998 23-0805 - 06/13/1998 06/13 06/19/1996 08/13 06/19/1996 08/06 06/15/1998
. 24 06/13 06/19/1998 08N3- 06/194908 06/19 06G8/1998 08/10- 06GM998 08N5- 06/22/1998 25
' 06/19- 08G6N908 064 9 - OS26/1998 OSG6 07/03/1998 06G6- 07/03/1996 08/22 - 06/29/1996 26 06/26 07/03/1996 06G8- 07/03/1998 07/03 07h0/1998 07/03 07/10/1996 06G9 07/06N998 27 -
07/03 07/10/1998 07/03 07/104 908 07/10 074 7/1996 07NO. 07M7/1998 072 07/13N998 26 07do. 07/17/1998 07/10- 07d7/1006 07d7 - 07/2N1998 07/17 - 07/24/1998 07M3 07/20N998 29 07/17 i 07/2N1998 074 7 07/24/1998 07/24 - 07/31/1998. 07/24 - 07/31/1998 07/20 07/27/1998 30 07/24 07/31/1998 07/24 - 07/31/1996 07/31 08dO74908 07/31 08/074 908 07/27 08/03N998 31-07/31 - 08/07/1998 07/31 0847/1998 0W07 08MN1998 08/07- 08t141998 08/03 08M0/1998 32 08/07i 08/1N1998 08/07 08/1 41998 ;
08/14 - 08/21/1998 08/14 08/21N998 08/10 08/17/1998 33 08/14 - 08/21/1998 08/14 08/214 906 08/21 08/28/1998 08/21 - 08/28/1996 08/17 08/24/1998 34.'
08/21 08/28/1998. 0W21 08/28/1000 08G8 00dOW1998 08/28 00f04/1998 08/24-OW31/1996 35-08G6 4 09/04/1998 08/28 00dO4/1998 09/04 - OM1N998 09/04 08/11/1998 08/31 09/08N996 36 00f04 - OW11dS08 0004 - 09/11/1998 08/11 004 8/1998 08/11 09/18/1998 09/08 08/1 41998 37 '
09/11. OW18/1998 08/11 09/18N998 08/16 00G5/1998 09/14 09/21M908 38 -
08/16 09/25M908 OW16- 09/25/1996 00G5 10/024908 OW25 + 10/02/1998 09/21 - 00GM998 30 00G5 1002/1998 00G5 - 10/02/1998 -
1002 1000/1998 1002 10f00/1998 09/28 - 10/05N998 40 '
1002 - 1000/1998 1002-10/0W1008 1000 1046/1998 10C0- 10/16N998 10/05 10/12/1998
' 41.
1000 10/16/1998 10M.10/16/1998 10/16 - 10G3/1998 10/16 - 10G3/1996 10N2-10/19N996 42-10/16 - 10/23/1998 10M 10/23/1998 10/23 10/30/1996 10/23 - 10/30/1996 10/19 10G6N998 43 10/23 - 10/30/1998 10/23 10/30/1996 10/30 11/08/1998 10/30 11/06N998 10/26 - 11/02/1998 44
'10/30 11/06/1996 1000 11/06/1998 11/08 11/13/1996 11/06 - 11n3/1998 11/02 - 11/09/i998 45 11/06 11/13N998 11/06-11M3/1996 11n3 - 11/20/1998 11M3-11/20/1996 11/00 - 11/16/1998 46 11/13 - 11/204 908 11n3-11/20/1998 11/20 - 11!27/1998 11/20- 11/27h006 11/16 11/23/1996 47' 11/20 11/27d908 11/20 11/27n998 11/27 12/06/1998 11/27 - 12/06/1996 11/23 - 12/01/1996
'48 11/27 12/06/1996 11/27 12/06/1998 12/06 - 12N2/1998 12/06 12/12/1998 1201 1207N99B*
de
- 12/06 - 12/12/1996 12/06 12/12/1996 12/12 12/10/1996 12/12 12/19/1996 1207-12/14/1998 50 12/12-12N9/1996 12/12 - 12M9/1998 12/19 12/26/1998 12de.12G6/1998 12h4 12/21M998 51.
~ 12N9.' 12/26/1998 12/19 12/26N996 12/26 01/02N969 12/26 - 01/02/1990 12/21 12/29/1998 52-12/26- 01/02N990 12/26 01/02N900 AIR PARTICULATE ' (GAMMA SPECTROSCOPY) 12/31 0403/1998 12/29 03/30/1998 JAN-MAR 12/31. 0403/1996 12/31 0403/1998 12/31. ONO3/1998 04/03 - 07/03/1998 04/03 - 07/03/1998 03/30 06/29/1998 APR-JUN 0403 07/03/1998 0403 - 07/03/1998 07/03 - 1002n998 07/03 - 1002/1998 06/29 - 09/26/1998 JUL-SEP ' 07/03 - 1092/1998 '07/03 10/02/1996 10/02 01/02/1900 10/02 - 01/02/1999 09/28 12/29N996
'OCT-DEC 10/02 01/02/1900 1002 01/02N990 C - 16 i
TABLE C-IX.1
SUMMARY
OF COLLECTION DATES FOR SAMPLES COLLECTED IN THE VICINITY OF PEACH BOTTOM ATOMIC POWER STATION,1998 j
STATION CODE JAN4AAR APR-JUN JUL-SEP OCT-DEC 1A-01/04/1998 04/03/1998 04/03/1998 07/03/1998 07/03/1998 10/02/1998 10/02/1998 - 01/02/1999 1B 01/04/1998 0403/1998 04/03/1998 - 07/03/1998 07/03/1998 - 10/02/1998 1002/1998 - 01/02/1999 1C 01/04/1998 - 0403/1998.
04/03/1998 - 07/03/1998 07/03/1998 - 1002/1998 10/02/1998 - 01/02/1999 10/09/1998 - 01/04/1999 1D 1E 01/04/1998 04/03/1998 04/03/1998 07/02/1998 07/02/1998 09/30/1998 09/30/1998 01/02/1999 1F 01/04/1998 0403/1998 0 6 1998 - 07/02/1998 07/02/1998 09/30/1998 09/30/1998 01/04/1999 1G 01/04/1998 04/03/1998 04/03/1998 07/03/1998 07/03/1998 - 09/30/1998 09/30/1998 - 01/02/1999 1H 01/04/1998 '0403/1998 04/03/1998 - 07/03/1998 07/03/1998 - 10/02/1998 10/02/1998 - 01 02/1999 11 01/04/1998 - 04/03/1998 04/03/1998 - 07/03/1998 07/03/1998 09/30/1998 09/30/1998 - 01 02/1999
. 1J 01/04/1998 - 0403/1998 04/03/1998 - 07/02/1998 07/02/1998 1002/1998 1002/1998 01/02/1999 it 01/04/1998 - 0403/1998 04/03/1998 07/03/1998 07/03/1998 09/30/1998 09/30/1998 01/02/1999 10/28/1998 - 01/02/1999 1M 1009/1998 0102/1999 1P 1009/1998 - 01/02/1999 10 10/28/1998 - 01/02/1999 1R 2
01/04/1998 04/03/1998 04/03/1998 07/01/1998 07/01/1998 09/30/1998 09/30/1998 - 01/02/1999 1000/1998 01/02/1999 2B 3A 01/04/1998 04/03/1998 0403/1998 07M1998 07/03/1998 1002/1998 1002/1998 - 01/02/1999 4K 01/04/1998 - 0403/1998 0403/1998 07/03/1998 07/03/1998 - 10/02/1998 10/02/1998 01/02/1999 5
01/03/1998 - 0402/1998 0402/1998 - 07/02/1998 07/02/1998 - 1001/1998 10/01/1998 - 01/03/1999 1NN 01/04/1998 04/03/1998 0403/1998 07/03/1998 07/03/1998 - 10/02/1998 10/02/1998 - 01 02/1999 8B 01/03/1998 - 04/02/1998 0402/1998 - 07/03/1998 07/03/1998 - 10/02/1998 10/02/1998 01/02/1999 14 01/03/1998 - 04/02/1998 0402/1998 - 07/02/1998 07/02/1998 - 1001/1998 1G01/1998 - 01/03/1999 15 01/03/1998 - 0402/1998 04/02/1998 07/02/1998 07/02/1998 - 10/01/1998 1001/1998 01;03/1999 16 01/03/1998 - 04/02/1998 0402/1998 - 07/02/1998 07/02/1998 10/01/1998 1001/1998 - 01 6 1999 17 01/03/1998 04/02/1998 0402/1998 - 07/02/1998 07/02/1998 10/01/1998 1001/1998 01/03/1999 18 01/03/1998 - 04/02/1998 0402/1998 07/01/1998 07/01/1998 09/30/1998 09/30/1998 - 01/02/1999 19 01/03/1998 - 0402/1998 0402/1998 - 07/01/1998 07/01/1998 09/30/1998 09/30/1998 - 01/04/1999 22 01/03/1998 - 0402/1998 04/02/1998 - 07/02/1998 07/02/1998 - 1001/1998 1001/1998 - 01/03/1999 23 01/04/1998 0403/1998 04/03/1998 07/01/1998 0701/1998 09/30/1998 09/30/1998 - 01/02/1999 24 01/03/1998 0402/1998 0402/1998 - 07/02/1998 07/02/1998 - 1001/1998 10/01/1998 - 0103/1999 26 01/03/1998 0402/1998 0402/1998 07/01/1998 07/01/1998 - 1001/1998 1001/1998 - 01/04/1999 27 01 0 3/1998 04/02/1998 04C2/1998 07/01/1998 07/01/1998 09/30/1998 09/30/1998 01/04/1999 j
31A 01/03/1998 04/02/1998 0402/1998 - 07/02/1998 07/02/1998 - 1001/1998 1001/1998 01/03/1999 i
32 01/03/1998 0402/1998 0402/1998 07/02/1998 07/02/1998 - 1001/1998 1001/1998 - 01/03/1999 40 01/04/1998 0403/1998 0403/1998 0701/1998 07/01/1998 - 09/30/1998 09/30/1998 01/04/1999 42 01/03/1998 - 04C2/1998 0402/1998 07/02/1998 07/02/1998 - 1001/1998 1001/1998 - 01/03/1999 43 01/03/1998 - 04/02/1998 04/02/1998 - 07/02/1998 07/02/1998 - 1001/1998 1001/1998 - 01/03/1999 44 01/03/1998 04C2/1998 04/02/1998 07/02/1998 07/02/1998 - 1001/1998 1001/1998 - 01/03/1999 45 01/03/1998 - 0402/1998 0402/1998 07/02/1998 07/02/1998 - 1001/1998 1001/1998 - 01/03/1999 46 01/03/1998 04/03/1998 0403/1998 - 07/01/1998 07/01/1998 09/30/1998 09/30/1998 - 01/03/1999 47 01/03/1998 0402/1998 04/02/1998 07/01/1998 07/01/1998 - 09/30/1998 09/30/1998 - 01/03/1999 48 01/03/1998- 04C2/1998 04/02/1998 - 07/01/1998 07/01/1998 09/30/1998 09/30/1998 01103/1999 49 01/03/1998 - 04C2/1998 -
04/02/1998 - 07/01/1998 07/01/1998 - 09/30/1998 09/30/1998 - 01/02/1999 50 01/03/1998 - 04/03/1998 04/03/1998 07/01/1998 07/01/1998 09/30/1998 09/30/1998 01/02/1999
)
61 01/03/1998 - 04/02/1998 04/02/1998 07/01/1998 07/01/1998 1001/1998 1001/1998 - 01/04/1999 i
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l APPENDIX D DATA TABLES AND FIGURES COMPARISON LABORATORY o
F DATA TABLES AND FIGURES - COMPARISON LABORATORY
. APPENDIX D:
TABLES Table D-l.1 -
Concentrations Of Gross Beta Insoluble in Drinking Water Samples Collected in The Vicinity Of Peach Bottom Atomic Power Station,1998.
Table D-l.2 Concentration Of Gross Beta Soluble in Drinking Water Samples Collected in The Vicinity Of Peach Bottom Atomic Power Station, 1998.
Table D-l.3 Concentrations Of Gamma Emitters in Drinking Water Samples Collected in The Vicinity Of Peach Bottom Atomic Power Station, 1998.
Table D-II.1 Concentrations Of Gross Beta in Air Particulate Samples Collected in The Vicinity Of Peach Bottom Atomic Power Station,1998.
Table D-II.2 Concentrations Of Gamma Emitters in Air Particulate Samples Collected in The Vicinity Of Peach Bottom Atomic Power Station, 1998.
Table D-Ill.1 Concentrations Of I-131 By Chemical Separation And Gamma Emitters in Milk Samples Collected in The Vicinity Of Peach Bottom Atomic Power Station,1998.
' Table D-IV.1 Summary Of Collection Dates For Samples Collected in The Vicinity Of Peach Bottom Atomic Power Station,1998.
i FIGURES Figure D-1' Comparison Of Monthly insoluble Gross Beta Concentrations in Drinking Water Samples Split Between GPU And TBE,1998.
Figure D-2 Comparison Of Monthly Soluble Gross Beta Concentrations in Drinking Water Samples Split Between GPU And TBE,1998.
Figure D-3 Comparison Of Weekly Gross Beta Concentrations in Air Particu-late Samples Collected From Collocated PBAPS Locations 1 A And 1Z,1998.
D-i
I.
The following section contains data and figures illustrating the analyses performed by the quality control laboratory. Duplicate samples were obtained from several locations cnd media and split between the primary laboratory, GPU Nuclear and the quality control laboratory, Teledyne Brown Engineering (TBE). Comparison of the results for most media were within expected ranges, though occasional differences were seen:
TBE's results for gross beta insoluble and soluble in drinking water samples were slightly higher than the results from GPU except for the November soluble result of 20.1 pCi/l, which was about ten times higher than the corresponding split GPU result of 2.2 pCill (Figures D-1;and D-2, Appendix D); A recount of the TBE sample showed a result of 16 pCill confirming the original result. However, a TBE reanalysis showed a result of 2.6 pCill, which agreed with the GPU results and historical data. No gamma emitting.
nuclide activity was found in the sample that would explain the elevated gross beta cctivity. As a result, the original TBE results are considered anomalous.
~ The gross beta results for air particulate samples collected at the collocated stations 1Z and.1 A compared very well (Figure D-3, Appendix D). No significant differences were noted. Both laboratories use Cs-137 as a calibration source.
o 1
I D-1
l CONCENTRATIONS OF GROSS BETA INSOLUBLE IN DRINKING WATER TABLE D-l.1 SAMPLES COLLECTED IN THE VICINITY OF PEACH BOTTOM ATOMIC POWER STATION,1998 RESULTS IN UNITS OF PCl/ LITER +/- 2 SIGMA COLLECTION 4L PERIOD JAN 0.8
- 1.0 FEB 0420.9 MAR 0.610.8 APR 0.420.9 MAY 1.221.1 JUN 0.620.9 JUL 121.0 AUG 0.5 t 0.6 SEP 0.220.8 OCT 0.721.1 NOV 0 t 1.4 DEC
-0.120.8 MEAN 0.510.8 CONCENTRATIONS OF GROSS BETA SOLUBLE IN DRINKING WATER SAMPLES TABLE D-l.2 COLLECTED IN THE VICINITY OF PEACH BOTTOM ATOMIC POWER STATION, 1998 RESULTS IN UNITS OF PCl/ LITER +/- 2 SIGMA COLLECTION 4L PERIOD JAN 2.5 t 1.3 FEB 1.521.2 MAR 1.821.1 APR 2.7
DEC 3.921.5 MEAN 4.1 t 10.2 SEE DISCUSSION SECTION FOR EXPLANATION D-2
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RESULTS IN UNITS OF E-3 PCl/CU METER +/- 2 SIGMA WEEK NO 1A i
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SUMMARY
OF COLLECTION DATES FOR SAMPLES COLLECTED IN THE VICINITY OF PEACH BOTTOM ATOMIC POWER STATION,1998 DRINKING WATER (GROSS BETA & GAMMA SPECTROSCOPY)
COLLECTION 4L PERIOD JAN 01/0N1998 - 01/09/1998 FEB 01/31/1998 02/27/1998 MAR 03/27/1998 - 0403/1998 APR ONO3/1998 - 05/01/1998 MAY 05/01/1998 06/05/1998 JUN 06/05/1998 - 07/03/1998 JUL 07/03/1998 07/31/1998 AUG 07/31/1998 - 09/0W1998 SEP 09/0N1998 - 10/02/1998 OCT 10/02/1998 10/30/1998 NOV 10/30/1998 12/06/1998 DEC 12/06/1998 01/02/1999 AIR PARTICULATE (Gross Beta)
WEEK NO 1A WEEK NO 1A 1
12/31/1997 - 01/09/1998 27 07/03/1998 - 07/10/1998 2
01/09/1998 - 01/18/1998 28 07/10/1998 07/17/1998 3
01/18/1998 01/25/1998 29 07/17/1998 07/2N1998 4-01/25/1998 - 01/31/1998 30 07/2N1998 - 07/31/1998 5
01/31/1998 02/06/1998 31 -
07/31/1998 - 08/07/1998 6
02/06/1998 02/13/1998 32 08/07/1998 08/1N1998 7
02/13/1998 02/20/1998 33 08/1N1998 08/21/1998 8
02/20/1998 - 02/27/1998 34 08/21/1998 - 00'28/1998 9
02/27/1998 03/06/1998 35 08/28/1998 - 09/0N1998 10 03/06/1998 - 03/13/1998 36 09/DN1998 09/11/1998 I
11 03/13/1998 - 03/20/1998 37 09/11/1998 09/18/1998 f
12 0370/1998 03/27/1998 38 09/18/1998 09/25/1998 13 03/27/1998 - ONO3/1998 39 09/25/1998 - 10/02/1998 14 ONO3/1998 ON10/1998 40 10/02/1998 10/09/1998 15 ON10/1998. ON17/1998 41 10/09/1998 - 10/16/1998 16 ON17/1998 0#24/1998 42 10/16/1998 10/23/1998 17 04/24/1998 - 05/01/1998 43 10/23/1998 10/30/1998 18 05/01/1998 05/08/1998 44 10/30/1998 - 11/06/1998 19 05/08/1998 05/15/1998 45 11/06/1998 11/13/1998 20 05/15/1998 05/22/1998 46 11/13/1996 11/20/1998 21 -
05/22/1998 05/29/1998 47 11/20/1998 - 11/27/1998 22 05/29/1998 - 06/05/1998 48 11,7//1998 12/06/1998 1
' 23 06/05/1998 06/13/1998 49 12/06/1998 12/12/1998 j
24-08/13/1998 - 06/19/1998 50 12/12/1998 - 12/19/1998 25 06/19/1998 - 06/26/1998 51 12/19/1998 12/26/1996 26-06/26/1998 - 07/03/1998 52 12/26/1998 - 01/02/1999 AIR PARTICULATE - (GAMMA SPECTROSCOPY)
COLLECTION PERIOD 1A JAN-MAR 12/26/1997 - 03f27/1998 APR-JUN 03/27/1998 06/26/1998 JUL-SEP 06/26/1998 09/25/1998 OCT-DEC 09/25/1998 12/26/1998 D-7
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APPENDIX E-
. SYNOPSIS OF ANALYTICAL PROCEDURES l
)
. APPENDIX E: SYNOPSIS OF ANALYTICAL PROCEDURES The following section contains a description of the analytical laboratory procedures along with an explanation of the analytical calculation methods used by GPU Nuclear cnd Teledyne Brown Engineering to obtain the sample activities.
9 4
l E-1
DETERMINATION OF GROSS BETA ACTIVITY IN WATER SAMPLES (TOTAL SUSPENDED AND DISSOLVED FRACTIONS)
GPUN Environmental Radioactivity Laboratorv
' This describes the process used to measure the radioactivity of water samples without identifying the radioactive species present. No chemical separation techniques are involved.
For surface and drinking water samples,400 ml of the sample is filtered under vacuum through a 0.45 micron filter. This filter represents the insoluble portion of the sample.
The filter is dried and mounted on a planchet. The filtrate which represents the soluble portion of the sample is evaporated on a hot plate, and the msidue is transferred and dried on another planchet.
The planchets are counted for 100 minutes in a low-background gas flow proportional counter. Calculation of activity includes a self-absorption correction for counter efficiency based on the weight of residue on each planchet.
Calculation of Samole Activity and 2 Siama Uncertaintv:
R ~ 2.22xEo TFxVxT x
2xJC+ B
~s = 2.22xEo TFxVxT x
4.66x5
-LLD = 2.22xEo TFxVxT x
Where:
Activity of sample in picoeuries per unit volume or weight. Volume R
=
~
or weight units are those used for V.
-2 Sigma Counting Uncertainty 2s
=
- Lower Limit of Detection LLD
=
Sample Counts C
=
Blank Counts B
=
Efficiency of the counter -
Eo
=
Transmission Factor TF
=
Acquisition time in minutes T
=
Volume or weight of aliquot analyzed.
V
=-
E-2
i DETERMINATION OF GROSS BETA ACTIVITY IN WATER SAMPLES (TOTAL SUSPENDED AND DISSOLVED FRACTIONS)
Teledyne Brown Enaineerina This describes the process used to measure the radioactivity of water samples without identifying the radioactive species present. No chemical separation techniques are involved.
For surface and drinking water samples, one liter of the sample is filtered under vacuum through a 0.45 micron Millipore filter. This filter represents the insoluble
~
tion of the sample. The filter is dried and mounted on a planchet. The filter which por represents the soluble portion of the sample is evaporated on a hot plate, and the residue is transferred and dried on another planchet.
The planchets are counted for 50 minutes in a low-background gas flow proportional counter. Calculation of activity includes a self-absorption correction for counter cfficiency based on the weight of residue on each planchet.
Calculation of Sample Activity and 2 Siama Error:
N IN P
Result i~0 Q*i t
=
(pri/1)
(2.22)(v)(E)
(2.22)(v)(E)
Net Activity Counting Error where:
total counts from sample (counts)
N
=
counting time for sample (min) t.
=
background rate of counter (cpm)
B
=
counting time for background (min) to
=
dpm/pCi 2.22
=
volume in liters v
=
efficiency of the counter E
=
multiple of counting error 2~
=
The MDA is defined as that value equal to the two sigma counting error of the result.
i E-3 I
b
l DETERMINATION OF TRITlUM IN WATER BY LIQUID SCINTILLATION COUNTING GPUN Environmental Radioactivity Laboratory Seven (7) milliliters of sample is filtered through a 0.45 micron filter into a vial and 1
mixed with 15 ml of liquid scintillation material and counted for a minimum of 480 minutes to determine its activity. The tritium activity is determined by measuring the count rate in the beta activity energy spectrum in Region A. 20.0 to 2000 represents Region C. If the sample Region C cpm is within i 25% of the average background Region C cpm and the sample Quench Indicating Parameter (QlP) is within 20 of the H-3 source QlP the sample has no contamination and the tritium activity may be calculated directly. If not the sample must be purified before recounting.
Calculation of Sample Activity and 2 Sioma Uncertaintv:
R = 2.22xEo VxDF x
'C-+D 2x 2s " 2.22x Eo VxDF x
$+b 3.29xN T.Ts y, 2.22xEo VxDF x
Where:
Total count time of sample in minutes T.
=
Total count time of background in minutes Ti,
=
~
Tritium activity in picocurie per unit volume (Volume units are R
=
those used in V) 2 sigma Uncertainty in the same units as above 2s
=
Lower limit of detection in same units as above LLD
=
Average count rate of sample C
=
Average count rate of background B
=
Tritium detection efficiency of counter, calculated as shown below Eo
=
Volume of aliquot V
=
E-4
Decay factor, calculated as shown below DF
=
.tn 2xDT DF eun time difference in years from collection stop date to counting date DT
=
of sample 4
The efficiency is calculated as follows:
S-B Eo=,,ry,,gy, Where:
Average count rate for the " efficiency determination" standard S
=
Average count rate of background B
=
Activity of standard in dpm per unit volume As
=
Volume of standard used Vs
=
Decay factor of standard, calculated as follows:
=
.io wr, DFs e an time difference (in years) between calibration date and counting DTs
=
date O
E-5
DETERMINATION OF GROSS BETA ACTIVITY IN AIR PARTICULATE SAMPLES GPUN Environmental Radioactivity Laboratory After allowing at least a three-day (extending from the sample stop date to the sample count time) period for the short-lived radionuclides to decay out, each air particulate filter paper is placed in a 2-inch diameter stainless steel planchet and counted using a gas flow proportional counter.
Calculation of Sample Activity and 2 Sioma Uncertaintv:
R = 2.22x Eo TFxVxT x
2xdC+ B 2s = 2.22xEo TFxVxT x
l 4.66x5 LLD = 2.22xEo TFxVxT x
Where Activity of sample in picoCuries per unit volume or weight. Volume R
=
or weight units are those used for V.
2 Sigma Counting Uncertainty 2s
=
Lower Limit of Detection LLD
=
Sample Counts C
=
Blank Counts B
=
Efficiency of the counter Eo
=
Transmission Factor of filter (i.e.1.00 for gross beta,0.80 for gross TF
=
alpha)
Acquisition time in minutes T
=
Volume analyzed.
V
=-
i E-6
DETERMINATION OF GROSS BETA ACTIVITY IN AIR PARTICULATE SAMPLES Teledyne Brown Enoineerin_g This describes the process used to measure the overall beta activity of air particulate filters without identifying the radioactive species present. No chemical separation techniques are involved. Each air particulate filter is placed directly on a 2-inch stainless steel planchet. The planchets are then counted for beta activity in a low-background gas flow proportional counter. Calculation of activity includes an empirical self-absorption correction curve which allows for the change in effective counting efficiency caused by the residue mass. Self-absorption is not considered in the case of air particulate filters because of the impracticality of accurately weighing the deposit and because the penetration depth of the deposit into the filter is unknown.
Calculation of Sample Activity and 2 Siama Error:
- 0 Result (pCi/m')
2.22(v)(E)(.02832)
- 2.22(v)(E)(.02832)
~
Net Activity Counting Error where:
total counts from sample (counts)
N
=
counting time for sample (min) t.
=
background rate of counter (cpm)
B
=
counting time for background (min) to
=
dpm/pCi 2.22
=
volume of sample analyzed in cubic feet calculated from the v
=
elapsed time meter efficiency of the counter E
=
multiple of counting error 2
=
conversion to cubic meters
.02832
=
The MDA is defined as that value equal to the two sigma counting error of the result.
E-7
DETERMINATION OF l-131 IN MILK SAMPLES GPUN Environmental Radioactivity Laboratory Stable iodine carrier is equilibrated in a 3.5-liter volume of raw milk before pumping through 25cc of anion exchange resin to extract iodine. The system is washed with de-ionized water until clear and the washed resin is transferred to a gamma counting container and analyzed by gamma spectroscopy.
Calculation of Samole Activity and 2 Siama Uncertaintv:
The same calculations are used as in DETERMINATION OF GAMMA EMITTING j
RADIOlSOTOPES below.
i 1
E-8 i
DETERMINATION OF l-131 IN MILK SAMPLES Teledvne Brown Enoineerina Two liters of sample are first equilibrated with stable iodide carrier. A batch treatment with anion exchange resin is used to remove iodide from the sample. The iodine is then stripped from the resin with sodium hypochlorite, reduced with hydroxylamine hydrochloride, and extracted into carbon tetrachloride as free iodine, it is then back-extracted as iodide into sodium bisulfite solution and is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting. The chemical yield is corrected by measuring the stable iodide content of the milk or water with a specific ion electrode.
Calculation of the Samole Activity and 2 Siama Error:
~S
~
Result (pCi /l}
(2.22)(v)(E)(y)(exp'*) ~ (2.22)(s)(E)())(exp'*)
Net Activity Counting Error where:
total counts from -sample (counts)
N
=
counting time for sample (min) t.
=
background rate of counter (cpm)
B
=
counting time for background (min) t.
=
dpm/pCi 2.22
=
volume of sample analyzed (liters) v
=
chemical yield of the amount of sample counted
=
y A
is the radioactive decay constant for 1-131 (0.693/8.05)
=
is the elapsed time between sample collection (or end of the At
=
sample collection) to the midcount time multiple of the counting error 2
=
efficiency of the counter for l-131, corrected for self absorption E
=
effects by the formula:
E = E, (exp'**'")
.a n, u,,
where:
efficiency of the counter determined from an 1-131 standard mount E.
=
mass of Pdl on the sample mount (mg)
M
=
2 mass of Pdl on the standard mount (mg)
M.
=
2 The MDA is defined as that value equal to the two sigma counting error of the result.
E-9
DETERMINATION OF GAMMA EMITTING RADIOlSOTOPES GPUN Environmental Radioactivity Laboratory The procedure for detection of gamma emitting radioisotopes generates high resolution gamma spectra which are used for quantitative determination and identification.
Standard geometries have been established to maximize efficiency for sample types:
air particulate filters, water, milk, soil / sediment and food products.
A description of the analytical methods, beginning with air particulates used for each sample type is presented, followed by the general formula used for calculation of the sample activities.
Air particulate: At the end of each calendar quarter,13 (or 14) weekly air filters from the given location are stacked in a two inch diameter Petri dish in chronological order, with the oldest filter at the bottom, nearest the detector, and the newest one on top.
The Petri dish is closed and the sample counted.
Water and Milk: A well-mixed 3.5-liter sample is poured into a Marinelli beaker. The samples are brought to ambient temperature and counted.
Soil and Sediment: The sample is dried, sieved and put into a counting container and counted.
l Food products: The sample is chopped up and put into a counting container and counted.
Calculation of Sample Activity and 2 Siama Uncertainty.;,
P A Ea A = 2.22xqxctbx Et x e"' x (1 - e**)
where:
the computed specific activity A
=
peak area P
=
dpm/ picocurie 2.22
=
sample quantity
=
q detection efficiency E
=
gamma-ray abundance b
=
elapsed live time Et
=
A
=
decay constant acquisition start time Ts
=
elapsed real time En
=
E - 10
. I
?r y>> 2 e$$s2e$gm e,y,ss a
' M = A)< P s b > < e >
<100s (ADecay),
where:
M
=
uncertainty in the activity
' A Ea 1
ADecay ATuz Tus
- r 1 -' e**'* - A(Ts + En)-1, uncertainty in the peak area P AP
=
. uncertainty in the S-ray abundance
'Ab
=
AE
=
uncertainty in the efficiency-systematic Uncertainty estimate ( in %)
sys
=
AT% =
uncertainty in the half-life i
O j
l E - 11 I
(:
1 DETERMINATION OF GAMMA EMITTING RADIOlSOTOPES I elodyne Brown Enaineerina T
Gamma emitting radioisotopes are determined with the use of a lithium drifted germanium (GeLi) and high purity germanium detectors with high resolution a
spectrometry in specific media; such as, air particulate filters, charcoal filters, milk and water. Each sample to be assayed is prepared and counted in standard geometries such as one liter wrap-around Marinelli containers,300 ml or 150 ml bottles, or 2-inch filter paper source geometries.
. Samples are counted on large (>55 cc volume) GeLi detectors connected to Nuclear Data 6620 data acquisition and computation systems. All resultant spectra are stored on magnetic tape.
The analysis of each sample consists of calculating the specific activities of all detected radionuclides or the detection limits from a standard list of nuclides. The GeLi systems are calibrated for each standard geometry using certified radionsiclides standards traceable to the National Bureau of Standards.
Gamma Spectroscony Statistically Sionificant Activity and 2 Siama Error Calculation for the ND6620 and ND6700 Systems:
Activity AREA
- DECAY
^PCi LIVETIME(sec.)* ABN
- EFF
- 0.037 * (unit mass)
'( nit mass, u
Statistically Significant Activity 42
- BKGND + AREA t 200 *
- Activity
[
2 Sigma Counting Error Where:
' Net Peak Area (from Nuclide Line Activity Report)
. AREA
=
Compton Background (from Nuclide Line Activity Report
'BKGND
=
Decay Correction Factor (from Minimum Detectable Activity DECAY-
=
Report) (Nuclide Half Life - Collection time to Mid Count time)
LIVE TIME Elapsed Live Time ( from Header Information) -
=
. E - 12 p
Nuclide Abundance (from Nuclide Line Activity Report)
ABN
=
Detector Efficiency (from Nuclide Line Activity Report)
EFF
=
Conversion Factor (dps to picocurie) 0.037
=
Sample weight or volume (from Header information) unit mass
=
Gamma Spectroscoov Statistically Non Sianificant Activity and 2 Siama Error Calculation for the ND6620 and ND6700 Systems:
Activity AREA
- DECAY Pi LIVETIME(sec.)* ABN
- EFF
- 0.037 * (unit mass)
C (unit mass, Statistically Non Significant Activity 42
- BKGND ~ NET 200 *
- Net Activity NET 2 Sigma Counting Error where:
Net Peak Area (from Minimum Detectable Activity Report)
NET
=
Compton Background (from Nuclide Line Activity Report)
BKGND
=
Decay Correction Factor (from Minimum Detectable Activity DECAY
=
Report) (Nuclide Half Life - Collection time to Mid Count time)
LIVE TIME = Elapsed Live Time ( from Header Information)
Efficiency
- Abundance (from Minimum Detectable Activity (EFF*B.1)
=
Report)
Conversion Factor (dps to picocurie) 0.037
=
Sample weight or volume (from Header Information) unit mass
=
E - 13
Gamma Soectroscoov Minimum Detectable Activity Calculation for the ND6620 and ND6700 Systems:
MDA 2.83 JBKGN
- DECAY
\\
PCi LIVETIME(sec.) * (EFF
- B. L )
- 0. 037 * (unit mass)
( nit mass, u
where:
Total Peak Background Area (from Minimum Detectable Activity BKGN
=
Report)
Decay Correction Factor (from Minimum Detectable Activity DECAY
=
Report) (Nuclide Half Life - Collection time to Mid Count time)
LIVE TIME = Elapsed Live Time ( from Header Information)
Efficiency
- Abundance (from Minimum Detectable Activity (EFF*B.1)
=
Report)
Conversion Factor (dps to picocurie).
0.037
=
Sample weight or volume (from Header Information) unit mass
=
E - 14
l ENVIRONMENTAL DOSIMETRY t
GPUN Environmental Radioactivity Laboratory GPU Nuclear thermoluminescent dosimeters (TLDS) are Panasonic Type 801 AS l
badges, two of which are deployed at each station. Each badge contains two calcium sulfate and two lithium borate elements. Since each element responds to radiation
["
independently, this provides eight independent ' detectors at each station. The calcium sulfato elements are shielded with a thin layer of lead, which makes the response to different energies of gamma radiation more linear. The lead also shields the calcium i
sulfato elements from beta radiation, so that they respond to gamma radiation only.
iI The two lithium borate elements are shielded differently to permit the detection of beta radiation. Only the calcium sulfate elements normally are used for environmental monitoring; however, the lithium borate elements can be used to evaluate beta
. exposures or as a backup to the calcium sulfate elements should more data be required.
TLDs ree annealed and read using a Panasonic UD701 A TLD Reader equipped with glow curve capture capability. A reader alignment is performed monthly using TLDs irradiated to a known exposure. Run Correction Factors (RCF) are inserted in each read batch to correct for small drifts in reader calibration. An Element Correction Factor (ECF) is generated for each element before a new TLD badge is placed into service to standardize each element to a known exposure. The ECF for each element is updated every two years. Each calcium sulfate element is annealed to a total residual exposure of less than 0.5 mR prior to being issued each time that a badge is
.used.
Control (transit) badges are issued with every batch of field TLDs and accompany the badges into the field to quantify transit exposure. ' After the field badges are deployed, the control badges are kept in a lead shield with minimum 2" thick lead during the period of field exposure. Additional control badges are kept in a lead shield for the entire quarter, and receive ~ essentially no transit exposure. All control and field badges are read together at the end of each quarter, and the average field control badge exposure is subtracted from the average shield control badge exposure to -
i generate the transit exposure. The transit exposure (generally less than 1 mR total) is subtracted from the gross exposures on the field badges to yield the net exposures.
l Net exposures are then converted to mR per standard month. This method of calculating transit exposure conforms to guidance contained in ANSI N545.
Each station comprises two TLD badges, each of which has two calcium sulfate elements. Outliers are identified using predefined algorithms. If all four elements are available, a given exposure value is judged an outlier if the standard deviation exceeds 5%.of the_ mean exposure based on all four elements, and the exposure for
. one element is outside three standard deviations of the mean exposure based on the i-E - 15
other three elements. If only two elements are available, the relative standard deviation based on the two exposure values must be 12% or less, or else both exposure values are considered outliers and no valid data are reported for that station for that Quarter.
e 9
m E - 16 I
n I
i i
l.
APPENDIX F j
l l
i QUALITY CONTROL EPA INTER-LABORATORY COMPARISON PROGRAM t
i..
l l-r e
n 3
APPENDIX F:
QUALITY CONTROL PROGRAM GPU Nuclear (GPU) and Teledyne Brown Engineering (TBE) participate in the EPA Radiological Comparison (cross check) Program. This participation was limited to enalyses of water samples due to budget reductions within EPA. To supplement this
- program both laboratories contracted with an independent vendor Anaijtics to provide cdditional media for analysis. In addition GPU Nuclear participates in the DOE Radiological Comparison Program. Both the Analytics and DOE comparison programs tre traceable to National Institute of Standards and Technology. The results of these Inter-laboratory programs represent the various media as found in the Peach Bottom Atomic Power Plant REMP. As a result of this participation, an objective measurement of analytical precision and accuracy as well as, a bias estimation of the results are obtained.
Examination of the data shows that the vast majority were within the EPA's, DOE's or Analytics's control limits. Each case of exceeding the control limits was investigated.
There was no evidence to suggest systematic errors.
The results of GPU's and TBE's participation in the EPA, DOE and Analytics cross check programs can be found in Tables F-1, F-2, F-3 and F-4, respectively.
i 9
9 F-1
TABLE F-1 1998 USEPA Cross Check Program Results EPA Control GPU TBE Collection Limits Results Results Date Media Nuclide (A)
(B)
(B) 01/16/98 Water dr-89 8.0 i 8.7 8.33 1 0.58 5.00 i 1.73 Sr-90 32.0 8.7 34.33 i 1.15 31.67 i 0.58 01/30/98 Water Alpha 30.5 i 13.2 21.00
- 2.65 33.00 t 2.65 Beta 3.9 t 8.7 7.23 i 0.32 5.60 t 0.90 104.9
- 18.2 103.33 t 5.77 (C) 110.00 i 0.00 02/06/98 Water 1-131 104.9 i 18.2 106.67 t 5.77 (D) 03/13/98 Water H-3 2155.0 i 603.8 2166.67 2 57.74 1833.33 1 57.74 04/21/98 Water Alpha 54.4 i 23.6 46.67
- 2.08 50.00 1 1.73 Beta 94.7 i 17.3 87.33 t 11.02 102.00 i 6.56 Co-60 50.0 i8.7 50.00 i 1.00 52.33 i 1.53 Sr-89 6.0 i 8.7 4.67 i 0.58 4.67 t 1.15 Sr 90 18.0 i 8.7 17.33 i 2.31 21.67 i 1.15 Cs-134 22.0 t 8.7 20.00 1 1.00 21.00 i 1.00 Cs-137 10.0
- 8.7 11.00 i 1.00 11.67 i 0.58 06/05/98 Water Co-60 12.0 i 8.7 13.00 t 0.00 13.00 i 1.00 Zn-65 104.0 i 17.3 105.67 t 7.51 111.67 i 2.52 Ba 133 40.0 2 8.7 40.00 1 2.00 35.00 i 2.65 Cs-134 31.0 i8.7 29.00 t 1.73 32.33 t 0.58 Cs-137 35.0 t 8.7 34.33 i 1.15 37.67 1 2.08 07/17/98 Water Sr-89 21.0 i 8.7 21.67 i 2.31 21.00 t 1.00 Sr 90 7.0 8.7 6.67 20.58 6.33 i 0.58 07/24/98 Water Alpha 7.2 t 8.7 6.43 i 0.12 5.'43 i 0.64 Beta 12.8 i 8.7 14.00 i0.00 14.67 i 2.08 08/07/98 Water H-3 17996 i 3122.9 19000.00 t 0.00 16000.00 1 0.00 7.00 t 0.53 (C) 5.93 1 0.55 09/11/98 Water 1-131 6.1 i3.5 6.60 i 0.26 (D) 6.1 i3.5 10/20/98 Water Alpha 30.1 i 13.0 25.33 t 1.53 21.67 2.31 Beta 94.0 1 17.3 84.67 i 3.21 74.67 17.64 (E)
Co-60 21.0 t8.7 22.67 i 2.52 22.33 i 1.15 Sr89 19.0 t 8.7 19.00 2 1.00 18.33 t 1.53 Sr 90 8.0 i8.7 5.00 10.00 8.33 11.15 Cs-134 6.0 1 8.7 6.67 i0.58 6.67 i 0.58 Cs-137 50.0
- 8.7 53.67
- 2.52 56.33
- 3.79 11/6/98 Water Co-60 38.0 t 8.7 38.00 i 1.00 39.67 i 2.52 Zn-65 131.0 t 22.6 146.67 5.77 140.67 i 10.97 Ba 133 56.0 10.4 59.67
- 1.53 46.33 1 2.52 Cs-134 105.0 i 8.7 103.00 1 6.08 103.00 2.00 Cs-137 111.0 10.4 116.67 t 5.77 115.33 i 1.53 23.67 i 4.04 (E) 11/13/98 Water Alpha 47.2 i 11.8 29.33 i 3.21 Beta 3.5
- 5.0 8.67 1 1.53 5.50 i 0.87 F-2
A.
The EPA Control Limit was the known concentration i 3 sigma for three determinations. The units are pCl/L B.
The GPU and TBE results are the average of three determinations i one standard deviation. The units are pCl/L.
C.
The analysis was performed by first concentrating 1-131 on a resin. The resin was then counted by gamma spectroscopy.,
D.
The analysis was performed by gamma spectroscopy. The I-131 in the sample was not concentrated prior to counting, j
l E.
Results are under investigation.
I Criteria are listed in EPA 600/4-81-004.
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A. : The DOE EML value was the mean of replicate determinations for each nuclide.
B. The DOE EML uncertainty was the standard error of the mean.
C. - The GPU Value was an average of 1 to 4 determinations.
D. The units are Bq/L for water, Sq/kg (dry) for soil Sq/kg (wet) for vegetation and total Bq for air filters.
E.. The.GPU uncertainty was the square root of the sum of the squares of the reported two sigma
- uncertainty of the individual determinations for each nuclide.
F. A reanalysis was requested. The reanalysis result agrees with the original analysis. The sample
. must have been contaminated during digestion. Beakers used for high activity samples will be gamma scanned and discarded if contaminated.
G. The Am-241 result (reported on 6/8/98) was too late to be submitted to the EML (due date of 6/1/98) for inclusion in the study. The reported value (11 5 Sq/kg) was not acceptable with the EML value (2.678
- 0.212 Sq/kg). The ratio was 4.108. A reanalysis was requested and the result (5.2 t 1.6 Sq/kg) was similar to the original result and has a ratio with the EML of 1.942 and was Acceptable with Waming. The EML sample consists of approximately 200 grams of an air dried, pulverized and blended soil. Soil samples tested for homogeneity ranged in sample size from 2 to 600 grams. The sample sizes used for Am-241 analysis were 0.49 and 0.44 gram. Because both analysis results agree with each other no further action was necessary.
H. The Co-60 result (17.00 t 2.00 Bq/L) reported to the EML was not within acceptable agreement with the EML value (13.60 t 1.20 Bq/L). A reanalysis was requested. The reanalysis result (14.77 i 1.282 Sq/L) has a ratio of 1.086, which was within acceptable agreement with the EML value. The original raw (non-rounded) results were 16.01 t 1.042 and 16.50
- 1.047 Sq/L. If the mean of these values (16.255 Bq/L) was reported a ratio of 1.195 would have been Acceptable with Waming. The mean of 90 reported values versus the EML value was 1.092 for this nuclide, which indicates a 9%
biasc l.
This sample has been analyzed five times.
The results were:
8.6E-06 0.9E-06 uCi/mi. 319 Bq/L 8.0E-06
- 0.8E-06 296 7.8E-0610.9E-06 289
- 8.0E-06
- 0.9E-06 296 9.8E-06 t 0.1E-05 363 I
All of the results are similar.
The nuclides in this water matrix were unlike any analyzed in the ERL for Fe-55. These nuclides may have caused the high results. Eighteen laboratories reported Fe-55 results to the EML in QAP C
- 48. Seven (7) were Acceptable (A), seven (7) were Acceptable with Waming (W) and four (4) were Not Acceptable. Only two (2) laboratories reported values below the EML value. Of the 14 "A" and "W" reported values the Mean ratio was 1.194 (242 Bq/L). This indicates that the EML value (202.8 Bq/L) may be low. The ERL results for Fe-55 in the previous QAP studies have been acceptable.
Future Fe-55 in EML QAP studies will be monitored to identify continuing trends.
J.
Previously the ERL value was not in agreement with the EML and was less than the minimum acceptable ratio. The library was analyzed and compared to the Kocher isotope table and the decay scheme. The decay scheme was incorrectly evaluated and a change was made to the library to reduce the apparent abundance of the primary gamma line used to calculate the activity. This change to the abundance brought the previous samples results in specification. With the recent
. sample the result was greater than the maximum allowed ratio. This time the library was evaluated,
' and Gary Chevalier at TMI was consulted. We came to the agreement that the Kocher listing could be confusing and that the abundance should be used as stated in the Kocher listing. The library
- EML" was edited and the values from Kocher were placed in the library for Sb-125. Re-analyzing
-F-7 l
l
the spectra resulted in an average result of 10.5 Bq/un. This gives a ratio of 1.18 with the EML known value. The result was acceptable. Alllibraries will be checked to verify the correct abundance for Sb-125.
K. The EML air filter was processed for actinide analyses. During the precipitation step for uranium, titanium chloride (TiCl ) which was used to purify the precipitant appeared not to react as in the past.
3 Notably the dark color of TiCl faded immediately after being added to the final solution. After 3
counting the uranium source, a number of high energy peaks interfered with the U-232 tracer peak.
These peaks resulted in an abnormally high recovery (~140%) and consequently yielded low results for the radionuclides (U-234 and U-238) to be reported. A different cross-check sample (EPA uranium in water) resulted in the same high energy peaks. This sample was reprocessed using extra TiCl and the interfering peaks were eliminated. The reported result was within 0.1 sigma of the 3
known value. Also, the other two media from the EML were processed with extra TiCl and yielded 3
acceptable results. It appears that the TiCl lost its strength and more was needed to purify the final 3
precipitant solution. A new reagent has since been purchased for future analysis.
L. The Sr 90 in EML soil result (19 i 7 Sq/kg) was not acceptable with the EML value (39.6310.003 Bq/kg).The ratio was 0.479. A reanalysis was performed using a larger aliquot and this result (39 i 5 s
Bq/kg) has a ratio with the known value of 0.984 and was acceptable. For future processing of EML soils, a larger aliquot will be used in order to achieve the best result with the lowest error.
M. The EML water for strontium analysis failed to achieve acceptable results because the spiked value j
was at the lower end of the sensitivity for the analysis. Three aliquots,20ml,25ml and 30ml, were used for the analysis. The average result was 1.510.6 Bq/l. The EML value was 2.11 t 0.18 Bq/l giving a ratio of 0.711.Due to the small volume of water submitted by EML, larger aliquots could not be taken for reprocessing. A reanalysis using a similar aliquot volume (25ml) was processed and yielded the same unacceptable result. To prevent this non-agreement from reoccurring, only one aliquot will be initially analyzed. The result will dictate what size aliquot should be used for additional analvsis in order to achieve optimum statistical results.
The control limit concept was established from percentiles of historic data distributions (1982 - 1992).
The evaluation of this historic data and the development of the controllimits are presented in DOE report EML 564. The control limits for QAP-XLVll were developed from percentiles of data distributions for the years 1991 - 1998.
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APPENDIX G PBAPS SURVEY t
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l APPENDIX G: PBAPS SURVEYS A Land Use Census around the Peach Bottom Atornic Power Station (PBAPS) was conducted by Normandeau Associates, RMC Environmental Services Division for PECO Nuclear to comply with Section 3.8.E.2 of PBAPS's Offsite i
Dose Calculation Manual Specifications (ODCMS) and Bases. The survey was conducted during the May to October 1998 growing season. The distance and i
i direction of all locations were positioned from the barn to the PBAPS vents using G!obal Positioning System (GPS) technology. The results of this survey are I
summarized in Table G-1.
No changes.were required to the PBAPS REMP as a result of this survey.
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r TABLE G-1 LOCATION OF THE NEAREST MILK PRODUCING ANIMAL WITHIN A FIVE MILE RADIUS OF PBAPS,1998 Distance (ft.)
Sjitgt__or from Vents N
14,650 NNE 11,078 NE 11,211 ENE 10,978 E
15,163 ESE 20,149 SE 19,085 SSE S
SSW 7,855 SW 12,241 WSW 4,694 W
5,119 WNW NW 17,570 NNW
- INDICATES NO MILK ANIMALS LOCATED 5
G-2