ML20205T058
| ML20205T058 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 12/31/1998 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20205T046 | List: |
| References | |
| 15, NUDOCS 9904270123 | |
| Download: ML20205T058 (135) | |
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Docket No: 50-352 50-353 LIMERICK GENERATING STATION UNITS 1 and 2 Annual Radiological Environmental Operating Report Report #15 1 January Through 31 December 1998 Prepared By PECO Nuclear 96 hes e r o BI Wayne, PA 19087-5691 l
3 May 1999 9904270123 990417
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PDR ADoCK 05000352 R pop
Docket No: 50 352 50-353
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LIMERICK GENERATING STATION UNITS 1 and 2 {
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I Annual Radiological )
Environmental Operating Report Report #15 1 January Through 31 December 1998 Prepared By PECO Nuclear i
- 96 hes e o BI :
Wayne, PA 19087-5691 l
l l
t May 1999
7 j TABLE OF CONTENTS
- 1. Summary and Conclusions.. . . .. ... . . . . . . . . . . . . . . . . . .. . . . .1
- 11. Introduction ., .. . . . . . . ... . ... .. ... . .. . .. . . . . . . . . . . . . . . . . . . . . .
3
. A. Objectives of the REMP . . .. . . . . . . . . ,, .. . . . .3 B. Implementation of the Objectives... . . . ,, . .. . . . .. . . .
3 lit. Program Description... .. .. . . , . . . . . . . .. . . . . . . .4 A. Sample Collection .. . . . . .. . . . . . . . . . . . . . . . . . ... . ..4 B. Sample Analysis. . . ..... . . .. . . . . . . . .
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C. Data interpretation. . . . . .. .. . . . . . . . .6 1 D. Program Exceptions... . .. . . . .. . . . . . . . . . . . . . .7 E. Program Changes.... . . . . . . . . . .. . . .. . . . . . . . . .
8 IV. Results and Discussion . . . . .... ..... . . . . . . . . . .. . . . . . . . . . . . .8 A. Aquatic Environment. . .... ,.8 I
- 1. Surface Water. . . . . ,. . . . . . . . . . . . . . . . . , , . . .. . . .8
- 2. Drinking Water. ... , , , . . , .. . . . . . . . . .9
- 3. Fish... . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . .
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- 4. Sediment . . .. , ,. .. . . . . . . 10 B. Atmospheric Environment... . .. . . .. . . . . . . . . . . . . . . 11
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. 1. Airbome .. ,. . ... . . .. . .. . . . . . . . . , .
11
- a. Air Particulates.. . . . . . . . , . . . . . . . .
11
- b. Airbome lodine. . . . . . . , .. .
12 l
l 2. Terrestrial. . . . . .. . .. .. . .. 12
- a. Milk.
.. . .. . .. . . .. 12 C. Ambient Gamma Radiation. .. .. .. . . . . . .. 12 D.10 CFR 20.2002 Permit Storage Area. .. . . . . . . . ... . . 13 V. References.. . .. . . . . . . . .. . . . . . . . . . .. . . 13 i 3
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Appendix A - Radiological Environmental Monitoring Report Summary Appendix B - Sample Designation and Locations Appendix C - Data Tables and Figures - Primary Laboratory Appendix D - Data Tables and Figures - QC Laboratory Appendix E - Synopsis of Analytical Procedures Appendix F .
Quality Control - EPA Intercomparison Program
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Appendix G - LGS Surveys 1
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- 1. Summary and Conclusions This repo.i on the Radiological Environmental Monitoring Program conducted for the Limerick Generating Station by PECO Nuclear covers the period 1 January 1998 through 31 December 1998. During that time period,1131 analyses were
, performed on 884 samples.
l Surface and drinking water samples were analyzed for concentrations of tritium l
. and gamma emitting nuclides. In addition, drinking water samples were I analyzed for concentrations of gross beta (soluble and insoluble fractions). No fission or activation products were found. Gross beta activities detected were consistent with those observed in other years. Tritium activity was detected at the surface and drinking water stations located downstream of the LGS discharge during the second quarter. The levels detected were consistent with those observed in previous years.
Fish (predator and bottom feeder) and sediment samples were analyzed for concentrations of gamma emitting nuclides. No fission or activation products were found in fish. lodine-131 was found in fish samples and was due to an upstream medical source. The dose from this source to the maximum exposed individual (adult) was 1.3 mrem to the thyroid. Sediment samples collected .
below the discharge had Cs-137 concentrations consistent with levels observed l during the preoperational years. In addition, Co-60 and Zn-65 were found in l sediment at a downstream indicator location and was the result of LGS releases.
The dose to a teenager's skin through the sediment pathway was calculated as 1.6 E-3 mrem.
Air particulate samples were analyzed for concentrations of gross beta and gamma emitting nuclides. Cosmogenic Be-7 and naturally occurring K-40 were observed at levels consistent with those observed in other years. No fission or activation products were detected.
High sensitivity I-131 analyses were performed on weekly air samples. All results were less than the minimum detectable activity.
Cow and goat milk samples were analyzed for concentrations of I-131 and gamma emitting nuclides. All 1-131 results were below the minimum detectable activity. Concentrations of K-40 were consistent with those observed in other years. No fission or activation products were found.
Environmental gamma radiation measurements were made quarterly using thermoluminescent dosimeters. Levels detected were consistent with those i observed in other years.
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l Review of the gamma spectroscopy results from the surface water sampler (25S1) located at the Limerick's intake and downstream of the 10CFR20.2002 permitted storage area indicated no offsite radioactive nuclide transport was evident.
In assessing all the data gathered for this report and comparing these results with preoperational data, it was evident that, the operation of LGS had no '
adverse radiological impact on the environment.
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r ll. Introduction The Limerick Generating Station (LGS), consisting of two 3458 MWt boiling water reactors owned and operated by PECO Nuclear (PECO), is located adjacent to the Schuylkill River in Montgomery County, Pennsylvania. Unit No.1 went critical on 22 December 1984. Unit No. 2 went critical on 11 August 1989.
, The site is located in Piedmont countryside, transversed by numerous valleys containing small tributaries that feed into the Schuylkill River. On the eastem river bank elevation rises from approximately 110 to 300 feet mean sea level
,. (MSL). On the western river bank elevation rises to approximately 50 feet MSL l to the western site boundary.
A Radiological Environmental Monitoring Program (REMP) for LG5 yas initiated in 1971. Review of the 1971 through 1977 REMP data resulted in ine modification of the program to comply with changes in the Environmental Report Operating License Stage (EROL) and the Branch Technical Position Paper l
(Rev.1,1979). The preoperational period for most media covers the periods 1 January 1982 through 21 December 1984 and was summarized in a separate i report. This report covers those analyses performed by GPU Nuclear and l
Teledyne Brown Engineering (TBE) on samples collected during the period 1 January 1998 through 31 December 1998.
On July 6,1998 a 10CFR20.2002 permit was issued to Limerick for storage of slightly contaminated soils, sediments and sludges obtained from the holding
]
pond, cooling tower and spray pond systems. These materials while in storage l will decay to background. Final disposition will be determined at I
decommissioning of the Station.
A. Objectives of the REMP The objectives of the REMP are to:
- 1. Provide data on measurable levels of radiation and radioactive materials in the site environs.
- 2. Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals l- from principal pathways of exposure. l B. Implementation of the Objectives l
The implernentation of the objectives is accomplished by:
- 1. Identifying significant exposure pathways.
- 2. Establishing baseline radiological data of media within those pathways.
- 3. Continuously monitoring those media before and during Station operation to assess Station radiological effects (if any) on man and the environment.
Ill. Program Description ,
A. Sample Collection Samples for the LGS REMP were collected for PECO Nuclear by Normandeau Associates, RMC Environmental Services Division (RMC).
This section describes the collection methods used by RMC to obtain environmental samples for the LGS REMP in 1998. Sample locations and descriptions can be found in Tables B-1 and B-2, and Figures B-1 through B-3, Appendix B.
Aouatic Environment The aquatic environment was examined by performing radiological analyses on samples of surface water, drinking water, fish, and sediment.
Two gallon water samples were collected monthly from continuous samplers located at two surface water locations (13B1 and 24S1) and four drinking water locations (15F4,15F7,16C2, and 28F3). One additional surface water location (10F2) was sampled only during the months when water was taken from the Perkiomen Creek for cooling. Control locations were 10F2,24S1, and 28F3. All samples were collected in new unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising the flesh of two groups, catfish / bullhead (bottom feeder) and sunfish (predator), were collected semiannually at two locations: 16C5 and 29C1 (control). Sediment samples composed of recently deposited substrate were collected at -
three locations semiannually: 16B2 and 16C4 (indicator) and 33A2 (control).
Atmospheric Environment The atmospheric environment was examined by performing radiological analyses on samples of air particulate, airborne iodine, and milk.
Airborne iodine and particulate samples were collected and analyzed weekly at five locations (10S3,11S1,13C1,14S1, and 22G1). The ;
control location was 22G1. Airborne iodine and particulate samples were i obtained at each location, using a vacuum pump with charcoal ar'd glass fiber filters attached. The pumps were run continuously and sampled air I
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at the rate of approximately one cubic foot per minute. The filters were replaced weekly and sent to the laboratory for analysis.
l Milk samples were collected biweekly at five locations (9G1,10B1,18C1, 19B1, and 21B1) during April through November, and monthly during December through March. Four additional locations (36E1, 22C1,23F1 i
, and 25C1) were sampled quarterly. Locations 36E1,9G1 and 23F1 were controls. All samples were collected in new unused two gallon plastic bottles from the bulk tank at each location, refrigerated, and shipped
. promptly to the laboratory. No preservative was added. i Ambient Gamma Radiation l
Direct radiation measurements were made using Panasonic 801 calcium I sulfate (CaSO4) thermoluminescent dosimeters (TLD). The TLD locations were placed on and around the LGS site as follows:
A site boundary rina consisting of sixteen locations (36S2, 3S1, SS1,7S1, l l 10S3,11 S1,13S2,14S1,18S2, 21 S2, 23S2, 25S2, 26S3, 29S 1, 31 S 1 and 34S2) near and within the site perimeter representing fence post l
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 sixteen locations (36D1,2E1, l 4E1, 7E1,10E1,10F3,13E1,16F1,19D1, 20F1, 24D1, 25D1, 28D2, '
29E1,31D2, and 34E1) extending to approximately 5 miles from the site j designed to measure possible exposures to close-in population.
The balance of eight locations (5H1,6C1,9C1,13C1,15D1,1781,20D1 and 31D1) representing control and special interests areas such as population centers, schools, etc.
1 The specific TLD locations were determined by the following criteria: l
- 1. The presence of relatively dense population;
- 2. Site meteorological data taking into account distance and elevation for each of the sixteen-221/2 degree sectors around the site, where estimated annual dose from LGS, if any, would be most significant;
- 3. On hills free from local obstructions and within sight of the vents (where practical);
- 4. And near the closest dwelling to the vents in the prevailing downwind direction.
f' Two TLDs --each comprised of two thermoluminescent phosphors enclosed in plastic- were placed at each location in a PVC conduit located approximately three feet above ground level. The TLDs were exchanged quarterly and sent to the laboratory for analysis.
10CFR20.2002 Permit Storaae Area
- 1. The results of the surface water sampling program is used to ,
determine any radioactive nuclide transport from the storage area into the Schuylkill River.
B. Sample Analysis in order to achieve the stated objectives, the current program includes the following analyses:
- 1. Concentrations of beta emitters in drinking water, and air particulates.
- 2. Concentrations of gamma emitters in surface and drinking water, air particulates, milk, fish, and sediment.
- 3. Concentrations of tritium in surface and drinking water.
- 4. Concentrations of I-131 in air and milk.
- 5. Ambient gamma radiation levels at various site environs.
C. Data Interpretation The radiological and direct radiation data collected prior to LGS becoming operational was used as a baseline with which this operational data will be compared. For the purpose of this report, LGS was considered -
operational at initial criticality, in addition data will be compared to previous years' operational data for consistency and trending. Several factors are important in the interpretation of the data. The! ' 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 net count (above background) that would be detected with only a 3
5% probability of falsely concluding that a blank observation )
represents a "real" signal. The LLD was intended as a before the i 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 LGS 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 Activitv 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 radiosctivity in the environment, background variations may vc . in sample activity being lower than the background activity n#udng a negative number. For a more detailed description of the a,sult 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, Nm-95, Cs-134, Cs-137, Ba-140, La-140, Ra-226 and Th-232) were
! reported. Means and standard deviations of the results were l
calculated. The standard deviations represent the variability of measured results for different samples rather than single analysis uncertainty.
D. Program Exceptions For 1998 the LGS REMP had a sample recovery rate of better than 99%.
The exceptions to this program are listed below:
- 1. Surface water samples collected at location 24S1 (LGS Intake) were composites of weekly grabs during the period of 5/27/98 -
6/2/98 due to equipment related problems.
- 2. Surface water samples collected at location 13B1 (Vincent Dam) were composites of weekly grabs during the periods of 1/9/98 1/12/98, 3/9/98 - 3/11/98, and 5/12/98 - 5/14//98 due to equipment related problems.
- 3. Surface water samples collected at location 10F2 (Perkiomen Creek) were composites of weekly grabs during the period of 6/18/98 - 7/16/98 due to equipment related problems.
- 4. Drinking water samples collected at location 16C2 (Citizen's Utilities) were composites of weekly grabs during the period of 7/21/98 - 7/27/98 due to equipment related problems.
- 5. Milk samples from farm 10B1 were not available from January 1 to ,
April 21 and November 17 through December 31,1998, because the goats had stopped lactating.
- 6. TLD location 25S2 was vandalized during the second quarter of 1998.
- 7. The air particulate and air iodine filters from sampling location 11S1 were not available for week no. 27 due to a sample equipment problem.
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 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.
E. Program Changes There were no program changes made for 1998.
IV. Results and Discussion l A. Aquatic Environment I 1. Surface Water l
Samples were taken from a continuous sampler at three locations -
(10F2,1381, and 24S1) on a monthly schedule. Of these locations, only 1381 could be affected by Station discharges. The following analyses were performed.
Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity (Table C-l.1, Appendix C). Tritium activity ranged from -29 to 190 pCi/l.
Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-l.2, Appendix C). One positive K-40 result was found out of 30 samples. Potassium-40 results ranged from -41 to 39 pCill. All other nuclides were less than the minimum detectable
, activity.
- 2. Drinkina Water Monthly samples were collected from continuous water samplers at four locations (15F4,15F7,16C2, and 28F3). Three locations (15F4,15F7, and 16C2) could be affected by Station discharges.
The following analyses were performed:
Gross Beta Samples from all locations were analyzed for concentrations of gross beta in the insoluble and soluble fractions (Tables C-II.1 and C-II.2, Appendix C). The values ranged from -0.7 to 1 pCill for the insoluble fraction and from -0.1 to 7.9 pCill for the soluble fraction.
Concentrations detected in both fractions were consistent with those observed in previous years (Figures C-1 and C-2, Appendix C).
Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity (Table C-II.3, Appendix C). Tritium activity ranged from -32 to 120 pCill.
i l Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-II.4, Appendix C). All nuclides were less than the minimum detectable activity.
- 3. Fish Fish samples comprised of catfish / bullhead (bottom feeder) and redbreast /pumpkinseed (predator) were collected at two locations (16C5 and 29C1) semiannually. Location 16C5 could be affected by Station discharges. The following analysis was performed:
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Gamma Spectrometry The edible portion of fish samples from both locations was analyzed for gamma emitting nuclides (Table C-Ill.1, Appendix C).
With the exception of naturally occurring K-40, no fission or activation products attributable to the Plant were found. The K-40 activity ranged from 2,900 to 3,700 pCi/kg wet. lodine-131 was found in both control and indictor samples ranging from -1 to 31 pCi/kg wet. The presence of lodine is attributed to thyroid ~
radiotherapy treatments conducted at an upstream hospital. A dose to the maximum exposed individual (adult) would receive 1.3 mrem from ti a consumption of fish containing the maximum concentration of I-131 of 31 pCi/kg. Historical levels of Cs-137 are shown in Figure C-3, Appendix C.
- 4. Sediment Aquatic sediment samples were collected at 'hree locations (1682, 16C4 and 33A2) semiannually. Of these locations, two (1682 and 16C4) could be affected by Station discharge. The following
( analysis was performed:
Gamma Spectrometry Sediment samples from all three locations were analyzed for gamma emitting nuclides (Table C-IV.1, Appendix C). Nuclides detected were cosmogenic Be-7; naturally occurring K-40, Ra-226 l and Th-232, the activation product Co-60 and fission products
! Zn-65,1-131 and Cs-137. The nuclides Th-232 and Ra-226 commonly occur in sediment from the daughter decay of natural uranium.
Beryllium-7 and K-40 were found at all stations and ranged from -
l 42 to 3,200 pCi/kg dry for Be-7 and from 9,600 to 19,000 pCi/kg .
! dry for K-40. Concentrations of the fission product Cs-137 were I found in sediment samples from both indicator locations. Location 16C4 had the highest average concentration of 105 pCi/kg dry. -
The activity detected was consistent with those observed in the j pre-operational years (Figure C-4, Appendix C). Cobalt-60 (58 pCi/kg dry) and Zn-65 (150 pCi/kg dry) were found at the downstream indicator station 16C4. In addition to these nuclides, 1-131 (210 pCi/kg dry) was found at the upstream control location 33A2. As with the fish pathway,1-131 was attributed to an upstream hospital. The dose to a teenager's skin through the sediment pathway was calculated as 1.6 E-3 mrem.
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3 B. Atmospheric Environment
- 1. Airborne
- a. Air Particulates
, Continuous air particulate samples were collected from five locations on a weekly basis. The five locations were separated into three groups: Group I represents locations within the LGS site boundary (10S3,11S1, and 14S1),
Group ll represents the location at an intermediate distance from the LGS site (13C1), and Group til represents the control location et a remote distance from LGS (22G1). The following analyses were performed:
Gross Beta Weekly samples were analyzed for concentrations of beta emitters (Table C-V.1 and C-V.2, Appendix C).
Detectable gross beta activity was observed at all locations.
Comparison of results among the three groups aid in determining the effects, if any, resulting from the operation of LGS. The results from the On-Site locations (Group I) l ranged from 4 to 35 E-3 pCi/m* with a mean of 16 E-3 /
pCi/m' The results from the intermediate Distance location (Group II) ranged from 4 to 32 E-3 pCi/m' with a mean of 16 E-3 pCi/m', The results from the Distant locations (Group Ill) ran pCi/m'ged from of Comparison 5 the to 33 1998E-3 pCi/m' with air particulate a mean data with of 16 E-previous years data suggest no effects from the operation of LGS (Figure C-5, Appendix C). In addition a comparison of j the weekly mean values for 1998 indicate no notable ;
l differences among the three groups (Figure C-6, Appendix C).
Gamma Spectrometry l
Weekly samples were composited quarterly and analyzed l for gamma emitting nuclides (Table C-V.3, Appendix C). l Naturally occurring Be-7 due to cosmic ray activity was '
detected in all samples. These values ranged from 47 to 94 E-3 pCi/m All other nuclides were less than the minimum detectable activity.
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- b. Airborne lodine Continuous air samples were collected from five (10S3, 11S1,14S1,13C1, and 22G1) locations and analyzed weekly for 1-131 (Table C-VI.1, Appendix C). All results were less than the minimum detectable activity and ranged from -13 to 14 E-3 pCi/m'
- 2. Terrestrial ,
- a. Milk Samples were taken from five locations (1081,18C1,1981, 21B1 and 9G1) biweekly April through November and monthly December through March. Samples from four additional locations (23F1,22C1,25C1 and 36E1) were taken quarterly. The following analyses were performed:
lodine-131 Milk samples from all locations were analyzed for concentrations of I-131 (Table C-Vil.1, Appendix C). All results were less than the minimum detectable activity and ranged from -0.2 to 0.3 pCill.
Gamma Spectrometry Each milk sample from locations 1081,18C1,1981, 21 B1 and 22F1 were analyzed for concentrations of gamma emitting nuclides (Table C-Vil.2, Appendix C).
l Potassium-40 activity was found in all samples. The values ranged from 1,300 to 2,000 pCill. All other nuclides were less than the minimum detectable activity. -
C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Panasonic 801 (CaSO4) thermoluminescent dosimeters. Forty TLD locations were established around the site. Results of TLD measurements are listed in Tables C-Vill.1 to C-Vill.3, Appendix C.
Most TLD measurements were below 10 mrad /std. mor.th, with a range of 4.5 to 10.8 mR/std. Month. A comparison of the Site Boundary and Intermediate Distance data to the Control Location data indicate that the ambient gamma radiation levels from the Control Location 5H1 was consistently higher. The historical ambient gamma radiation data from Location SH1 was plotted along with similar data from the Site, intermediate Distance and Outer Ring Locations (Figure C-7, Appendix C). The data indicate that Location 5H1 had a historical high bias, but tracked with the data from all three groups.
. D. 10 CFR 20.2002 Permit Storage Area The results of the surface water aquatic monitoring program from Location 25S1 was used to determine if radioactivity from the 2002 permit area has made it to the Schuylkill River. The data obtained from the gamma analysis program did not detect any radioactivity from the 2002 permit area.
V. References
- 1. Environmental Report Operating License Stage, Limerick Generating Station, Units 1 and 2, Volumes 1-5 Philadelphia Electric Company.
- 2. Branch Technical Position Paper, Regulatory Guide 4.8, Revision 1, November 1979.
- 3. Pre-operational Radiological Environmental Monitoring Program Report, Limerick Generating Station Units 1 and 2,' 1 January 1982 through 21 December 1984, Teledyne isotopes and Radiation Management Corporation.
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APPENDIX A !
RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT
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APPENDIX B SAMPLE DESIGNATION AND LOCATIONS 4
e APPENDIX B: SAMPLE DESIGNATION AND LOCATIONS' OST OF TABLES AND FIGURES T BLES
.l TABLE B-1: Location Designation and identification System for the Limerick - !
Generating Station TABLE B-2: Sample Collection and Analysis Program for the Operational Radiological Environmental Monitoring Program, Limerick Generating
' Station,1998 FIGURES FIGURE B-1: Environmental Sampling Locations Within One Mile of the Limerick Generating Station,1998.
FIGURE B-2: Environmental Sampling Locations Between One and Five Miles from the Limerick Generating Station,1998 FIGURE B-3: Environmental Sampling Locations Greater Than Five Miles from the Limerick Generating Station,1998 l<
i i
B-i
TABLE B-1: Location Designation and Identification System for the Limerick Generating Station XXYZ - General code for identification of locations, where:
M -
Angular Sector of Sampling Location. The compass is divided into 36 sectors of 10 degrees each with center at Limerick's Units 1 and 2 off-gas vents. Sector 36 is centered due North, and others are numbered in a -
clockwise direction.
Y -
Radial Zone of Sampling Location (in this report, the radial distance from the Limerick vent for all regional stations).
S on-site location E 4-5 miles off-site A 0-1 mile off-site F 5-10 miles off-site B 1-2 miles off-site G 10-20 miles off-site C 2-3 miles off-site H 20-100 miles off-site D 3-4 miles off-site Z -
Station's Numerical Desigr,3 tion within sector and zone, using 1,2,3.. in each sector and zone.
O B-1
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APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY l
l l
1 j
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 Limerick Generating Station, 1998.
Table C-l.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Limerick Generating Station,1998.
Table C-II.1 Concentrations of Gross Beta insoluble in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station,1998.
Table C-!!.2 Concentrations of Gross Beta Soluble in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station,1998.
Table C-II.3 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 1998.
Table C-II.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station,1998.
Table C-Ill.1 Concentrations of Gamma Emitters in Fish Samples Collected in the Vicinity of Limerick Generating Station,
, 1998.
Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Limerick Generating Station, 1998.
Table C-V.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 1998.
C-i
i Table C-V.2 Monthly and Yearly Mean Values of Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station,1998.
Table C-V.3 Concentrations of Gamma Emitters in Air Particulate '
Samples Collected in the Vicinity of Limerick Generating Station,1998.
Table C-VI.1 Concentrations of I-131 in Air lodine Samples Collected in the Vicinity of Limerick Generating Station,1998.
Table C-Vil.1 Concentrations of I-131 in Milk Samples Collected in the Vicinity of Limerick Generating Station,1998.
Table C-Vil.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 1998.
Table C-Vill.1 Quarterly TLD Results for Limerick Generating Station, 1998.
Table C-Vill.2 Mean TLD Results for the Limerick Generating Station Site Boundary, Middle and Outer Rings,1998.
Table C-Vill 3 Summary of the Ambient Dosimetry Program for Limerick Generating Station,1998.
Table C-IX.1 Summary of Collection Dates for Samples Collected in the Vicinity of Limerick Generating Station,1998.
FIGURES Figure C-1 Mean Monthly Insoluble Gross Beta Concentrations in Drinking Water Samples Collected in the Vicinity of LGS, 1982-1998.
Figure C-2 Mean Monthly Soluble Gross Beta Concentrations in Drinking Water Samples Collected in the Vicinity of LGS, 1982-1998.
C -ii i
Figure C-3 Mean Annual Cs-137 Concentrations in Fish Samples Collected in the Vicinity of LGS, 1982-1998.
Figure C-4 Concentrations of Cs-137 in Sediment Samples Collected in the Vicinity of LGS, 1982-1998.
Figure C-5 Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 1982-1998.
Figure C-6 Mean Weekly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS,1998.
Figure C-7 Mean Quarterly Ambient Gamma Radiation Levels in the Vicinity of LGS, 1985-1998.
O I
C - iii -
TABLE C-l.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION,1998 RESULTS IN UNITS OF PCl/ LITER +/- 2 StGMA COLLECTION PERIOD 10F2 1381 24S1
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TABLE C-II.1 CONCENTRATIONS OF GROSS BETA INSOLUBLE IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION,1998 RESULTS IN UNITS OF PCl/ LITER +/- 2 SIGMA COLLECTION PERIOD 15F4 15F7 16C2 28F3 l JAN 0206 0.1206 -0.320.6 -0.3206
. FEB 0.2200 0.1206 -0320.6 -0.310.6 MAR -0.1208 -0.3208 -0320.8 -0.3208 APR 04207 -0.2207 0 2 t o.7 020.7 i MAY 02207 0.1207 020.7 0.7207
- JUN -02206 -0720.6 -0.3206 020.7 JUL 0.5206 -0.1206 0.120.6 -04206 AUG 0.420.3 0.2
- 0.3 0.220.3 0220.3 SEP 03204 -0.5204 020.5 -0.210.4 OCT 04205 0.110.4 0.120.4 0.3205 NOV 08206 09206 120.6 120.6 DEC -0.3208 -0620.8 -02:08 -0 4 : 08 MEAN 02:07 -01 : 08 020,7 0209 TABLE C-II.2 CONCENTRATIONS OF GROSS BETA SOLUBLE IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION,1998 l
RESULTS IN UNITS OF PCl/ LITER +/- 2 SIGMA '
l COLLECTION j
- PERIOD 15F4 15F7 16C2 28F3 J
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MAR 1.521.1 221.2 1921.2 1.321.1 APR 06209 1.921.1 7.9 t 1.4 0.121.1 l l MAY 2.021.1 2.2
- 1.1 1911.1 3 6 e 1.1 l JUN 3221.2 2.521.2 1.921.2 1.221.1
, JUL 4421.3 3721.3 2.421.2 3.321.3 l AUG 3208 1.720.8 1.420.7 2.520.8 t SEP 47t11 621.3 49212 5 7 t 1.3 j OCT 4621.2 3221.1 2.421.1 3821.2 NOV 2.821.3 41214 1.521.2 2.521.3 DEC 49*1.2 54i1.3 3.121.2 46*1.3 MEAN 33*2.7 31129 2.7238 2.823.1 TABLE C-II.3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN !
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TABLE C-V 1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION,1998 RESULTS IN UNITS OF E-3 PCl/CU METER +/- 2 SIGMA GROUP 1 GROUP 11 GROUP 11!
VVEEK 1053 11S1 14S1 13C1 22G1 1 1824 1524 1824 1624 1724 2 924 1024 724 824 1124 .
3 1223 1223 1624 1814 1223 4 1024 1524 1524 1524 1624 5 1724 1624 1624 1724 1524 6 1914 1824 1624 1524 -1824 .
7 1423 1423 1523 1524 13 t 3 8 924 614 1024 924 724 9 1624 1314 924 824 1024 10 923 423 823 423 823 11 1924 2024 2124 1924 21 24 12 823 11 24 723 823 523 13 1824 2024 1924 21 24 2525 14 14 4 1523 1324 1524 1324 15 1424 1524 1524 1424 1624 16 1524 2124 16 24 1524 1323 17 1724 1624 1724 1924 18 i 4 18 1023 1324 11t3 1324 1023 19 71 'J 823 923 823 823 20 1424 1724 1324 1624 1524 21 1923 1823 1923 1823 1823 22 1724 2025 1824 1814 2225 23 1024 924 10 24 13 t 4 1324 24 623 1125 1224 1224 13 4 25 1123 11 23 1023 1123 1424 26 1123 1414 15 t4 15 24 1724 27 1324 (1) 1124 1224 1324 28 1324 7*4 11 t4 1224 1324 29 1924 2024 2124 19 t 4 1624 30 1724 1124 1424 21 24 1524 31 16 24 1824 1514 1924 1924 32 2024 1524 19 2 4 2024 1824 33 1224 11 24 1324 12 24 1224 34 2424 2324 2224 20 14 2424 35 2825 26 25 2625 2624 2825 36 2124 2224 23 : 4 1824 2424 37 2025 24 t 5 2425 22 25 2625 38 2524 3125 3525 3225 33 5 39 20t3 22 t 3 2223 2023 2524 40 1023 1123 1023 1223 14 s 3 41 11 23 1023 1123 923 1023 .
42 1623 1223 1423 1523 1323 43 2024 1523 1924 1623 1824 44 1523 1423 1623 1423 1724 45 613 523 413 523 623 .
46 2824 2724 3024 3224 2924 47 2223 2424 26 24 2423 20s3 48 2023 2023 2424 2223 2023 49 21 3 25 4 2524 2424 2424 50 1724 1724 1524 1724 923 51 1424 1724 15
- 4 1824 1624 52 1423 16 23 1924 1723 1924 MEAN 15211 16:12 16 t 12 16 12 16 : 12 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION 1
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TABLE C-VI.1 CONCENTRATIONS OF l-131 IN AIR LODINE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION,1998 RESULTS IN UNITS OF E-3 PCl/CU METER +/- 2 SIGMA GROUPi GROUP ll GROUP lil VVEEK 10S3 11S1 14Si 13C1 22G1 1 5110 3212 -5
- 8 -52 14 -6 t 14 2 -7210 5211 -52 14 -2213 029 3 -4211 4 : 10 -82 13 428 0210 4 729 529 -9210 -2 14 -729 5 229 428 4213 3212 127 6 -1 2 9 -i t 11 -5 16 10215 129 7 227 -727 4210 -92 10 6 7 8 -9 2 12 5 ! 11 0215 72 17 0210 9 12211 5!9 -1 2 7 -6 2 12 -1214 10 -729 4 *10 -5210 J + 12 2!8 11 11211 1210 -9212 2 12 528 12 128 -4210 1214 t 14 -1 t 7 13 3210 8 10 -4 t 10 -3212 -4 2 8 14 8*13 -13218 -10212 -1129 0210 15 828 O s 10 3216 -5114 59 16 -1210 5219 4219 -3211 -8 2 12 17 -58 -1210 -2210 -10212 -26 18 10 : 10 029 5 : 12 429 52 12 19 419 -1210 4210 72 12 -11113 20 -4 2 9 -4 2 0 -5212 -126 -32 11 21 3!7 -1211 228 6110 -3211 22 -7210 10213 9115 0214 -4 9 23 -7 2 8 7212 128 5110 7212 24 1210 4210 -329 828 2210 25 028 -6210 2210 329 -6 13 26 327 1110 -2211 -628 0211 27 1210 (1) 4210 229 4 13 28 228 -10114 5214 4112 -8 2 9 29 -817 -92 12 -1210 4210 8210 30 10212 627 -11 : 11 528 -4 ! 12 31 029 329 6214 -227 72 11 32 2215 -7211 3212 -2212 i t 11 33 1 115 -9218 329 -6111 129 34 -2211 -5 10 -628 0212 -328 35 -5211 -7211 -5210 4e11 10113 36 -1210 11:11 0213 1212 4210 37 329 -5212 229 10 14 52 17 38 -4210 517 -9112 -7 t 9 3t 12 39 -6 2 9 328 8 11 14213 027 40 2212 -829 -4213 12 13 4213 41 327 -3213 127 92 11 -82 10 42 2212 0213 8111 42 14 -6210 43 -7213 -7211 529 328 -328 44 9210 -4114 029 12213 12214 45 -7210 -4211 -7211 -1 2 7 4113 46 -10212 -229 6214 1214 -8 2 11 47 -4 2 8 -6110 328 2 t 12 -52 13 48 1.1 11 -4212 -1211 2212 -6211 49 1 112 7213 -1215 6:17 2211 I 50 4 :12 9 12 2: 20 -1213 029 51 -2113 0212 029 -4113 -a t 8 52 -329 928 -10211 -1211 3211 MEA'.4 0211 -1212 -1110 1111 12 10 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C - 11
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TABLE Vill.1 QLIARTERLY TLD RESULTS FOR LIMERICK GENERATING STATION,1998 RESULTS IN UNITS OF MILL 1-ROENTGEN /STD. +/- 2 SIGMA STATION MEAN JAN-MAR APR-JUN JUL-SEP OCT-DEC l CODE +/- 2 S D.
l 36S2 68 20.4 6.8 2 0.2 65 20.4 6.9 2 0.3 6.8 2 0.7
- l 36D1 54 20.4 5.4 05 5.2 1 0 5 5.5 0. 3 5.6 20.2 l 2E1 6.7 2 0.9 67 20.6 61 2 0.5 7.3 2 0.5 68 203 l 3S1 6.3 20.6 6 3 1 0.5 59 20.6 6.7 2 0 6 6.4 2 0.5 .
l AE1 48 203 4.9 2 0.2 46 04 5 ! 0.2 4.9 2 0 4 SS1 7.4 20.6 7.6 20.4 6.9 1 0 6 7.5 t 0.5 7.4 205 5H1 7.8 20.6 8 2 0.8 7.4 t 0. 3 8 20.4 7.8 0.8 6C1 65 10.7 65 10.6 6.1 2 0.5 7 2 0.7 66 206 l 7S1 66 204 6.6 2 0.6 64 2 0.5 6 8 2 0.1 6.7 204
( 7E1 6 7 2 0.8 66 20.3 62 105 6.8 2 0.5 7.2 $ 0.3 9C1 6 3 1 0,3 6.2 203 6.2 205 3.5 0.3 6.3 2 0 2 l 10S3 6.7 207 6 6 2 0.5 6.3 1 0 6 7.1 2 0.1 67 206 10E1 66 06 66 *0.3 6.3 06 7 ! 0.3 6.6 208 10F3 65 0.2 6.5 t04 63 204 6 6 ! 0.2 65 06 11S1 76 20.5 7.6 20.4 7.3 20.1 7.9 2 0 6 7.8 004 l 13S2 10 4 2 0.9 10.7 204 98 206 10.5 204 10 8 ! 0.2 13C1 4.7 ! 0.3 4 6 2 0.5 4.5 0.4 4 8 2 0.4 4.8 204
! 13E1 6.6 20.1 6.5 1 0.1 65 20.3 6.6 2 0 2 6.6 20.8 i 14S1 5 8 : 0.5 5 8 2 0.5 5 5 t 0.5 6 2 0.2 59 20.5
! 15D1 67 20.7 6.5 0.5 6.3 10.4 7 2 0.3 69 202 16F1 68 0.7 6.5 2 0.2 66 20.5 7.3 101 6 8 1 0.7 1781 6.1 2 0.7 6.2 2 0.5 56 07 6 0.5 6.4 202 18S2 7.1 207 7.3 2 0.2 6,7 t 0.8 7.2 2 0 5 7.4 2 0.8 19D1 6.1 2 0.6 6 2 0.6 5.7 0.3 6.4 207 6.3 2 0.3 20D1 58 20.4 5.9 t 0.3 5.6 0.2 5.9 0.2 6 2 0.6 20F1 63$06 61 2 0.1 6 202 6.5 2 0.5 66 20.2 21S2 56 20.4 5.7 0.5 52 205 5.7 0.2 5.7 0.3 23S2 5.9 2 0.5 5.7 0.3 56 !O4 6.1 0.4 6.1 204 24D1 55 04 5.8 2 0.6 5.3 2 0.2 5.6 2 0.4 55 04 25S2 5.7 20.1 56 20.3 (2, 5.7 ! 0.4 5.7 2 0.1 25D1 52 0.2 52 20.8 5.1 t 0.4 5.3 0.2 5.3 06 26S3 55 208 52 204 5.2 0.3 5.6 2 0.3 6 2 0.5 28D2 58 0.5 5.8 t 0.2 5.4 2 0.8 6 0.2 5.8 2 0.2
- 29S1 55 20.3 55 0.3 5.3 08 56 0.5 56 !O4 29E1 5.9 2 0.7 5.8 0.6 5.5 10.4 62 20.2 63 0.6 31S1 64 206 65 0,5 5 9 2 0.3 64 204 67 104 -
31D1 7.7 2 0 0 7.7 2 0.8 7.4 0.6 7.8 2 0 3 81 04 31D2 65 205 6.5 2 0.1 6.3 2 0.5 66 203 6 8 2 0.1 34S2 69 205 7 2 0.8 6.5 202 6 8 2 0.3 7.1 209 34E1 61 204 6 204 5.8 204 62 02 62 204 (1) MEAN AND TWO TIMES THE STANDARD DEVIATION OF THE QJARTERLY RESULTS (2) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C - 16
l I
l TABLE C-Vill.2 1998 MEAN TLD RESULTS FROM LIMERICK GENERATING STATION FOR THE SITE BOUNDARY, MIDDLE, AND OUTER RINGS 1998 RESULTS IN UNITS OF MILLl-ROENTGEN /STD. MO. +/- 2 STANDARD l DEVIATIONS OF THE STATION DATA l
EXPOSURE SITE MIDDLE RING 5H1 PERIOD JAN - MAR 6.7 1 2.6 6.1 i 1.3 8.0 1 0.8
- APR - JUN 6.3 1 2.3 5.8 1 1.3 7.4 2 0.3 ;
JUL-SEP 6.8 1 2.4 6.3 i 1.5 8.0 1 0.4 !
OCT-DEC 6.8 t 2.5 6.3 1 1.5 7.8 i 0.8 l l
1 j
TABLE C-Vill.3
SUMMARY
OF THE 1998 AMBIENT DOSIMETRY PROGRAM FOR LIMERICK GENERATING STATION RESULTS IN UNITS OF MILLl-ROENTGEN /STD. MO.
LOCATION SAMPLES PERIOD PERIOD PERIOD MEAN PRE-OP MEAN j ANALYZED MINIMUM MAXIMUM +/- 2 S.D. +/- 2 S.D.
SITE 64 5.2 10.2 6.6 1 2.4 7.6 1 2.4 MIDDLE RING 92 4.5 8.1 6.1 1 1.5 7.8 1 2.2 SH1 4.0 7.4 8.0 7.8 i 0.6 7.8 i 3.0 l
THE PRE-OPERATIONAL MEAN WAS CALCULATED FROM MONTHLY TLD READINGS 01/15/82 TO SITE BOUNDARY RING STATIONS - 36S2,3S1, SS1,7S1,10S3,11S1,13S2,14S1,18S2,21S2,23S2, 25S2, 26S3, 29S1, 31 S1, 34S2 MIDDLE RING STATIONS - 36D1,2E1,4E1,6C1,7E1,9C1,10E1,10F3,13C1,13E1,15D1,16F1.1781, 19D1, 20D1, 20F1, 24D1, 25D1, 2BD2, 29E1, 31 D1, 31 D2, 34E1 C - 17
TABLE C-IX.1
SUMMARY
OF COLLECTION DATES FOR SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION,1998 SURFACE WATER (TRITIUM LIQUID SCINTILLATION)
SAMPLING PERIOD 10F2 1381 24Si JAN-MAR -
12/29 - 03/30/1998 12'29 - 03/30/1998 j APR-JUN -
03/30 - 06/29/1998 03/30 - 06/29/1998 JUL-SE P 06/29 - 09/28/1998 0609 09/28/1998 06C9 - 0908/1998 OCT-DE C 09/28 12/28/1998 09/28 - 12/28/1998 09G8 - 12/28/1998 SURFACE WATER fGAMM A SPECTROSCOPYi SAMPLING PERIOD 10F2 1381 24Si JAN -
12/29 - 02/02/1998 12/29 - 02/02/1998 FEB -
02/02 - 03/02/1998 02/02 - 03/02/1998 MAR -
03/02 - 03/30/1998 03/02 - 03/30/1998 APR -
03/30 - 04'27/1998 03/30 - 04G7/1998 MAY -
04/27 - 06'02/1998 04'27 - 06/02/1998 JUN -
06/02 06/29/1998 06/02 - 06/29/1998 JUL 06'29 - 07G7/1998 06/29 07/27/1998 06'29 - 07/27/1998 AUG 07!27 - 08/31/1998 07/27 08/31/1998 07/27 08/31/1998 SEP 0801 - 09/28/1998 08/31 - 09 28/1998 08/31 09'28/1998 OCT 09'28 - 11/03/1998 09'28 - 11/03/1998 09G8 11/03/1998 NOV 11/03 - 11/30/1998 11/03 11/30/1998 11/03 - 11/30/1998 DEC 11/30 - 12/28/1998 11/30 - 12/28/1998 11/30 - 12'28/1998 DRINKING WATER (TRfTIUM)
SAMPLING PERIOD 15F4 15F7 16C2 2BF3 JAN-MAR 12'29 - 03/30/1998 12/29 - 03/30/1998 12/29 - 03/30/1998 12 29 03/30/1998 APR-JUN 0300 06/29/1998 03!30 06/29/1998 03/3L 0629/1998 03/30 - 06/29:1998 JUL-SEP 06'29 - 09'28/1998 06/29 09/28/1998 06'29 - 09/28/1998 0609 - 09/28/1998 OCT-DEC 09/28 - 12/28/1998 09'28 - 12/28/1998 09'28 - 12'28/1998 09'28 1228/1998 DRINKING WATER (GROSS BETA & GAMMA SPECTROSCOPY 1 .
SAMPLING PE RIOD 15F4 15F7 16C2 2BF3 JAN 12/29 - 02/02/1998 1229 - 02/02/1998 12/29 - 02/02/1998 1229 02/02/1998
~
FEB 02/02 - 03/02'1998 02/02 - 03/02/1995 02'02 - 03'02/1998 02/02 - 03'02/1998 MAR 03/02 - 03/30/1998 03/02 - J3/30/199B 03/02 - 0330/1998 03'02 03/30/1998 APR 03/30 - 04 27/1998 03'30 - 0427/1998 03!30 - 04'27/1998 033 0 - 04'27/1998 MAY 04 27 - 06/02/1998 0477 06/02'1998 04 27 - 06/02/1998 04 27 - 06/02/1998 JUN 06/02 - 06'29/1998 06/02 - 06/29/1998 06/02 - 06/29/1998 06/02 - 06/29/1998 JUL 06/29 - 07/27/1998 06/29 - 07/27/1998 06*29 - 07/27/1998 06/29 - 07/27/1998 AUG 07/27 - 08/31/1998 07!27 - 08/31/1998 07/27 08r31/1998 07/27 0831/1998 SEP 08/31 - 092 8/1998 0811 - 09/28/1998 08'31 - 09 28/1998 0831 - 0928/1998 OCT 09<28 - 11/03/1998 0928 - 11/03/1998 09 28 - 11/03/1998 0928 - 11/03/1998 NOV 11/03 - 11/30/1998 11/03 - 11/30/1998 11/03 11/30/1998 11/03 - 11/30/1998 DEC 11/30 - 12'28/1998 11/30 1228/1998 11/30 - 1228/1998 11/30 - 1228/1998 C - 18
TABLE C-IX.1
SUMMARY
OF COLLECTION DATES FOR SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION,1998 AIR PARTICULATE (GAMM A SPECTROSCOPYi SAMPLING 10S3 11S1 14S1 13C1 22G1 PERIOD JAN-MAR 1229 - 03/30/1998 12/29 - 03/30/1998 12/29 03/30/1998 12/29 - 03/30/1998 12/29 - 03/30/1998
- APR-JUN 03'30 - 06/29/1998 0300 06/29/1998 03/30 06/29/1998 03/30 - 06/29/1998 03/30 06/29/1998 JUL-SEP 06/29 09'28/1998 06/29 09/28/1998 06G9 - 09/28/1998 06/29 - 09'28/1998 06/29 09/28/1998 OCT- DEC 09/28 12/29/1998 09'28 - 12/29/1998 09'2B - 12/29/1998 09'28 11'29/1995 09/28 - 12/29/1998
, AIR PARTICULATE (GROSS BETA ANDl-1311 SAMPLING 10S3 11S1 14S1 13C1 22G1 PERIOD 1 12'29 01/05/1998 12/29 - 01/05/1998 12/29 - 01/05/1998 12/29 - 01/05/1998 1229 - 01/05/1998 2 01/05 - 01/12/1998 01/05 - 01/12/1998 01/05 01/12/1998 01/05 - 01/12/1998 01/05 - 01/12/1998 3 01/12 01/19/1998 01/12 01/19/1998 01/12 01/19/1998 01/12 - 01/19/1998 01/12 - 01/19/1998 4 01/19 - 01Q6/1998 01/19 - 01/26/1998 01/19 01/26/1998 01/19 - 01/26/1998 01/19 - 01/26/1998 5 01/26 - 02/02/1998 01/26 - 02/02/1998 01/26 - 02/02/1998 01/26 - 02/02/1998 01/26 - 02/02/1998 6 02/02 - 02/09/1998 02/02 - 0209/1998 02/02 - 02/09/1998 02/02 - 02/09/1998 02/02 - 02/09/1998 7 0209 - 02/17/1998 02/09 - 02/17/1998 02/09 - 02/17/1998 0209 - 02/17/1998 02/09 - 02/17/1998 8 02/17 02/23/1998 02/17 - 02'23/1998 02/17 - 02/23/1998 02/17 - 02/23/1998 02/17 - 02/23/1998 9 02/23 - 03/02/1998 02/23 - 03/02/1998 02/23 03/02/1998 02/23 - 03/02/1998 02/23 03/02/1998 l 10 03/02 - 03/09/1998 03/02 - 03/09/1998 03 02 03/09/1998 03/02 03/09/1998 03/02 - 03/09/1998 11 03/09 - 03/16/1998 0309 - 03/16/1998 03/09 - 03/16/1998 03/09 - 03/16/1998 03/09 - 03/16/1998 12 03/16 - 03/23/1998 03/16 - 03G3/1998 03/16 - 0323/1998 03/16 - 03/23/1998 03/16 - 03/23/1998 13 0F23 03/30/1998 03/23 03/30/1998 03/23 - 0300/1998 03/23 - 03/30/1998 03/23 0300/1998 14 03/30 - 04/06/1998 03/30 - 0406/1998 0300 04/06/1998 03/30 04/06/1998 03/30 04@6/1998 15 0406 - 04/13/1998 04/06 - 04/13/1998 04/06 - 04/13/1998 0406 - 04/13/1998 0406 - 04/13/1998 16 04'13 04'20/1998 04/13 0420/1998 04/13 04'20/1998 04/13 - 0420/1998 04/13 - 04'20/1998 l 17 0420- 0407/1998 0420 - 04/27/1998 04/20 04/27/1998 0420 - 04/27/1998 04/20 - 04'27/1998 18 04'27 05/04/1998 04'27 - 05/04/1998 04/27 - 05/04/1998 04'27 - 0504/1998 04'27 - 0504/1998 19 05/94 - 05/11/1998 05/04 05/11/1998 05/04 05/11/1998 05/04 - 05/11/1098 05/04 - 05/11/1998 20 05/11 - Go/18/1998 05/11 05/18/1998 05/11 - 06/18/1998 05/11 05/18/1098 05/11 - 05/18/1998 71 Of 18 - 05/26/1998 05/18 05/26/1998 05/18 05'26/1998 05/18 05G6/1998 95/18 - 05/26/1998
'.'2 rr 16 - 06/01/1998 05/26 0601/1998 05/26 - 06/01/1998 05/26 06/01/1998 05/26 - 06 01/1998 T, % 1 - 06'08/1998 0601 - 0608/1998 0601 - 06/08/1998 0601 06/08/1998 06/01 - 06/08/1998 24 06/08 06/15/1998 06/08 - 06/15/1998 0608 - 06/15/1998 0608 - 06/15/1998 06/08 - 06/15/1998 25 06/15 - 06/22/1998 06/15 - 06/22/1998 06/15 - 06/22/1998 06/15 - 06/22/1998 06/15 - 06/22/1998 l 26 06/22 - 06'29/1998 06/22 - 06C9/1998 06/22 - 06'29/1998 0622 - 06/29/1998 06/22 06/29:1998 l 27 06/29 07/06/1998 -
06C9 07/06/1998 06/29 - 07/06/1998 06/23 07/06/1998 i 28 07/06 - 07/13/1998 07/06 07/13/1998 07/06 - 07/13/1998 07/06 - 07/13/1998 07/06 - 07/13/1998 29 07/13 - 07/20/1998 07/13 07/20/1998 07/13 - 07/20<1998 07/13 07/20/1998 07/13 - 07/20/1998 30 07/20 07/27/1998 07/20 - 07!27/1998 07/20 - 07/27/1998 07/20 - 07/27/1998 07/20 - 07/27/1998 31 07/27 - 08/03/1998 07/27 0803/1998 07/27 - 08/0 11998 07/27 - 08/03/1998 07/27 - 08/03/1998 32 00'03 - 08/10/1998 08/03 08/10/1998 08/03 - 08/10/1998 0803 - 08/10/1998 08/03 - 08/10/1998 33 08/10 08/17/1998 08/10 - 08/17/1998 08/10 - 08/17/1998 08/10 - 08/17/1998 08/10 - 08'17/1998 34 08/17 - 08/24/1998 08/17 08/24/1998 08/17 - 08'24/1998 08/17 - 08/24'1998 08/17 - 0824'1998
- 35 08 24 - 08/31/1998 0804 08/31/1998 08/24 - 08/31/1998 08/24 - 08/31/1998 08'24 - 08/31/1998 36 08/31 09/08/1998 08/31 09 08!1998 08/31 09 08/1998 06'31 - 09/08/1998 08/31 - 09/08/1998 37 09/08 - 09/14/1998 09/08 09/14/1998 09/08 - 09/14'1998 09/08 - 09/14/1998 09'08 - 09/14/1998 38 09/14 - 09/21/1998 09/14 09/21/1998 09/14 09'21/1998 09'14 09/21/1998 09/14 - 0921/1998
. 39 09/21 - 09/28/1998 09/21 - 09'28/1998 09'21 - 09/28/1998 09 21 - 09/28/1998 09'21 09:28/1998 40 0928 - 10/05/1998 09/28 - 10/05'1998 09/28 - 1005/1998 09/28 - 10/05/1998 09'28 - 10/05/1998 41 10/05 - 10/12/1998 10/05 10/12/1998 1005- 10/12/1998 10/05 - 10/12/1998 10/05 - 10/12/1998 42 10/12 - 10/19/1998 10/12 10/19/1998 10/12 - 10/19/1998 10/12 - 10/19/1998 10/12 - 10'19/1998 43 10/19 - 10/26/1998 10/19 - 10/26/1998 10/19 - 10/26/1998 10/19 - 1026/1998 10/19 - 10'26/1998 44 10/26 11/02/1998 10/26 - 11/02/1998 10/26 1102/1998 1026 - 11/02/1998 10/26 - 11/02/1998 45 11/02 - 11/09/1998 11/02 - 1109/1998 11/02 - 11/09/1998 11/02 - 11'09/1998 11/02 - 11/09/1998 46 11/09 - 11/16i1998 11/09 - 11/16/1998 11/09 - 11/16/1998 11/09 - 11/16/1998 11/09 11/16/1998 47 11/16 - 11/23/1998 11/16 - 11/23/1998 11/16 - 11/23/1998 11/16 - 11/23/1998 11/16 11/23/1998 48 11/23 - 1201/1998 11/23 - 1201/1998 11/23 - 12'01/1998 11 23 - 1201/1998 11/23 12/01/1998 49 12?O1 - 1207/1998 12/01 12/07/1998 12/01 - 12/07/1998 12'01 - 12/07/1998 1201 12'07/1998 50 12/07 - 12/14/1998 12/07- 12/14'1998 12/07 - 12/14'1998 12'07 - 12/14/1998 12/0) - 12/141998 51 12!14 1221/1998 12/14 - 1221/1998 12!14 1221/1998 12/14 - 1221/1998 12/14 - 12'21/1996 52 1221 - 1229/1998 12/21 12'29'1998 12'21 12/29:1998 12/21 - 1229:1998 12!21 12/29'1998 C - 19
I 1
- TABLE C.lX.1
SUMMARY
OF COLLECTION DATES FOR SAMPLES COLLECTED IN l THE VICINITY OF LIMERICK GENERATING STATION,1998 STATION .;AN-MAR APR-JUN JUL-SEP OCT-DEC CODE
~
36S2 01/06/1996 - 04 07/1998 04/07d998 07/07/1998 07/07d998 - 10/06/1998 10/06/1998 01/05/1999 3601 01 06/1998 - 04/07/1998 04/07/1998 07/07/1998 07/07/1998 - 10/06/1993 10/06/1998 01/05/1999 .
2E1 01/06/1998 - 04/07/1998 04/07d95 8 07/07/1998 07/07/1998 - 10/06/1998 10/06d998- 01/05/1999 3S1 01/06/1998 - 04/07/1998 04/07/1998 07/07/1998 07/07d998 - 10/06/1998 10/06/1998 - 01/05/1999 4E1 01/06/1998 - 04/07d998 04/07d998 - 07/07/1998 07/074 398 10/06/1998 10/06d998 01/054999 SS1 01/06/1998 - 04'07/1998 04/07/1998 07/070 990 07/07/1998 - 10/06d998 10/06/1998 01/05d999 SH1 01/06/1998 04S7d998 04/07/1998 - 07/07/1998 07/07/1998 - 10/06d998 10/06/1998 - 01/05/1999 6C1 01/06/1998 0407/1998 04/07/1998 - 07/07/1998 07/07/1998 - 10/06/1998 1006/1998 01/05/1999 7S1 01/06/1998 - 04/07/1998 0407/1998 07/07/1998 07/07d998 - 10/06/1998 10/06d998 - 01/05/1999 7E1 01/06/1998 0407/1998 04/07/1998 - 07/07/1998 07/07d998 - 1006d998 10/06/1998 01/05/1999 9C1 01/06/1998 0408/1998 04/08M998 07/07/1998 07/07/1998 - 1006/1998 10/06/1998 - 01/054 999 10S3 01/06/1998 0407/1998 04/07d998 - 07/07/1998 07/07/1998 - 10/06/1998 10/06d998 01/05d999 10E1 01/06/1998 - 04S8/1998 04/08/1998 07/07/1998 07/07/1998 - 10/06d998 10/06/1998 - 01/054 999 10F3 01/06/1998 - 04085 998 0408d998 - 07/07/1998 07/07/1998 - 10/06/1998 10/06/1998 - 01/054.899 11S1 01/06/1998 - 04S7/1998 04/07/1998 07/07d998 07/07/1998 - 10/06d998 10/06/1998 - 01/05/1999 13S2 0106/1998 04t7/1998 04/07/1998 - 07/07/1998 07/07/1998
- 10/06/1998 10/06/1998 01/05/1999 13C1 01/06/1998 - 04085 998 04 08/1998 - 07/07/1998 07/07/1998 - 10/06/1998 10/06d998 - 01/004999 13E1 01/06/1998 - 04/08/1998 04/08/1998 - 07/07/1998 07/07/1998 - 10/065 998 10/0&1998 - 01/054 999 14S1 01/06/1998 04/07/1998 04/07/1998 - 07/07/1998 07/07d998 10/06/1998 10/06/1998 - 01/05/1999 15D1 01/06/1998 04/07/1998 04/07/1998 - 07/07d998 07/07/1998 10/06/1998 10/06/1998 01/050 999 16F1 01/06d998 - 0407/1998 04/07/1998 - 07/07/1998 07/07d998 - 10/061998 10/06/1998 - 01/05/19'49 1781 01/06/1998 04/07/1998 0407/1998 - 07/07d998 07/07/1998 10/06/1998 10/06/1998 01/05d999 18S2 01/06/1998 - 04/07/1998 04/07/1998 07/07/1998 07/07d998 - 10/06/1998 10/06d998 01/05/1999 4 1901 01/06/1998 04/07d998 0407/1998 07/07d998 07/07/1998 10/06/1998 10/06d998 - 01/054999 2001 01/06/1998 - 0407/1998 0407d998 - 07/07/1998 07/07/1998 - 10/06/1998 10/06/1998 01/05/1999 20F1 01/06/1998 04/07d998 04/07/1998 - 07/07/1998 07/07/1998 - 10/06/1998 1006/1998 - 01/05dP99 21 S 2 01/06/1998 - 0407dD98 04/07/1998 07/07/1998 07/07/1998 10/06/1998 10/06/1998 - 01/05/1999 23S2 ,01/0&1998 - 04/07/1998 04/07d993 - 07/07/1998 07/07d998 - 10/060998 10/06/1998 01/05/1999 24D1 01/06/1998 - 0407/1998 0407/1998 07/07/1998 07'07/1998 - 10/06/1998 10/06/1998 - 01/05/1999 25S2 01/06/1998 0407d998 0407d998 - 07/07/1998 07/07/1998 - 10/06/1998 10/06/1998 01 054 999 25D1 01/065 998 04075 998 0407d998 - 07/07d998 07/07/1998 - 10/06/1998 10/05/1990 - 01/05d999 26S3 01/06/1998 04S7dR98 0407d998 07/07/1998 07/07/1998 1006d998 10/06/1998 - 01/05/1999 2802 01/06/1998 - 04/07/1998 04/07/1998 - 07/07/1998 07/07/1998 - 10/06/1998 10/06/1998 01/054 999 29S1 0106/1998 04/07/1998 04/07/1998 07/07/1998 07/07/1998 10/06/1998 10/06d998 - 01/05/1999 .
29E1 01/06/*098 04/07/1998 04S7/1998 - 07/07/1998 07/07/1998 - 10/06d998 10/06/1998 - 01/05/1999 31 S1 01/06d998 04/07d998 0407/1998 - 07/07/1998 07/07/1998 - 10/06/1998 10/06/1998 - 01/05/1999 31D1 01/06d998 04/07/1998 04/07/1998 - 07/07/1998 07/07/1998 - 10/06/1998 10/06d D98 - 01/05/1999 ,
3102 0106/1998 0407/1998 0407/1998 - 07/07d998 07/07/1998 10/06/1998 1046/1998 - 01/05d999 34S2 01/06/1998 - 0407/1998 0407d998 - 07/07/1998 07/07d998 - 10/06/1998 10/06/1998 01/054 999 34E' 01/06/1998 - 0407/1998 04/07/1998 - 07/07/1998 07/070998 - 10/06d 998 10/06/1998 01/051 999 C - 20
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e APPENDIX D DATA TABLES AND FIGURES COMPARISON LABORATORY e
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APPENDIX D: DATA TABLES AND FIGURES - COMPARISON LABORATORY TABLES
, TABLE D-l.1 Concentrations Of Gross Beta insoluble in Drinking Water Samples Collected in The Vicinity Of Limerick Generating Station, .1998.
TABLE D-l.2 Concentration Of Gross Beta Soluble in Drinking Water Samples Collected in The Vicinity Of Limerick Generating Station.1998.
TABLE D-l.3 Concentrations Of Gamma Emitters In Drinking Water Samples Collected in The Vicinity Of Limerick Generating Station,1998.
TABLE D-II.1 Concentrations Of Gross Beta in Air Particulate Samples Collected in The Vicinity Of Limerick Generating Station,1998.
TABLE D-II.2 Concentrations Of Gamma Emitters In Air Particulate Samples Collected in i The Vicinity Of Limerick Generating Station,1998.
TABLE D-Ill.1 Concentrations Of 1-131 By Chemical Separation And Gamma Emitters in Milk Samples Collected in The Vicinity Of Limerick Generating Station,1998.
TABLE D-IV.1 Summary Of Collected Dates For Samples Collected in The Vicinity Of Limerick Generating Station,1998.
FIGURES FIGURE D-1 Comparison Of Monthly insoluble Gross Beta Concentrations in Drinking Water Samples Split Between GPU And TBE,1998.
l FIGURE D-2 Comparison Of Monthly Soluble Gross Bete Concentrations in Drinking Water Samples Split Between GPU And TBE,1998.
FIGURE D-3 Comparison Of Weekly Gross Beta Concentrations in Air Particulate Samples Collected From LGS Collocated Locations 11S1 And 11S2,1998.
D-i l
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F1 The following section contains data and figures illustrating the analyses performed by the quality control laboratory, Teledyne Brown Engineering (TBE). Duplicate samples were obtained from several locations l and media and split between the primary laboratory, GPU Nuclear and TBE. Comparison of the results for l most media were within expected ranges, though occasional differences were seen:
1:
The gross beta results for the drinking water insoluble and soluble fractions for both GPU and TBE were ;
similar (Figures D-1 and D-2, Appendix D). Any differences noted were probably due to variations in the
, , respective laboratory's analytical procedures. TBE counts the samples for 50 minutes, GPU counts for 100 minutes.
The gross beta results for air particulate samples collected at the collocated stations 11S1 and 11S2 compared very well (Figure D-3, Appendix D). No significant differences were noted. Both laboratories use Cs-137 as a calibration source.
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TABLE D-l.1 CONCENTRATIONS OF GROSS BETA INSOLUBLE IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION,1998 RESULTS IN UNITS OF PCl/ LITER +/- 2 SIGMA COLLECTION 16C2 PERIOD JAN 0.1 1 0.5 FEB 0.3 i 0.5 MAR -0.110.4 -
APR -0.110.4 MAY 0.4 t 0.5 JUN -0.1
- 0.5 JUL -0.110.4 AUG 0.3 1 0.4 SEP 0.1 1 0.4 OCT 0.4 1 0.6 NOV 0.0 1 0.5 DEC -0.1 0.4 MEAN 0.1 i 0.4 TABLE D-l.2 CONCENTRATIONS OF GROSS BETA SOLUBLE IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION,1998 RESULTS IN UNITS OF PCl/ LITER +/- SIGMA COLLECTION 1602 PERIOD JAN 3.3 1 0.9 FEB 3.0 1 0.9 MAR 2.0 1 0.8 APR 2.3 i 0.9 MAY 2.5 t 0.9 JUN 3.4 1 0.9 JUL 3.3 1 0.9 AUG 4.2 1 1.1 SEP 3.7 1 1.0 OCT 5.3 1 1.3
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SUMMARY
OF COLLECTION DATES FOR SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION,1997 DRNONG WATER (GROSS BETA & GAMMA SPdCTROSCOPY)
COLLECTION 16C2 PERIOD JAN 12/29/1997 - 02/02/1998 FEB 02/02/1998 - 03/02/1998 MAR 03/02/1998 03/30/1998 .
APR 03/30/1998 - ON27/1998 '
MAY 04/27/1998 - 0602/1998 JUN 06/02/1998 - 06f29/1998 JUL 06f29/1998 - 07/27/1998 AUG 07/27/1998 08/31/1998 SEP 08/31/1998 - 0928/1998 OCT 09/28/1998 - 11/03/1998 NOV 11/03/1998 - 11/30/1998 DEC 11/30/1998 - 12/28/1998
)
AR PARTICULATE (GAMMA SPECTROSCOPY)
COLLECTION PERIOD 11S2 .
JAN-MAR 12/29/1997 - 03/30/1998 l APR-JUN 03/30/1998 - 06/29/1998 1 JUL-SED 06/29/1998 09/28/1998 OCT-DEC 09/28/1998 - 12f29/1998 AIR PARTICULATE (GROSS BETA)
COLLECTION COLLECTION PERIOD 11S2 PERIOD 11S2 l 1 12/29/1997 - 01/05/1998 27 06/29/1998 07/06/1998 2 01/05/1998 - 01/12/1998 28 07/06/1998 - 07/13/1998 3 01/12/1998 - 01/19/1998 29 07/13/1998 - 07/20/1998 4 01/19/1998 - 01/26/1998 30 07/20/1998 - 07/27/1998 5 01/16/1908 02/02/1998 31 07/27/1998 - 08/03/1998 6 0202/1998 02/09/1998 32 08/03/1998 08/10/1998 7 0209/1998 - 02/17/1998. 33 08/10/1998 - 08/17/1998 l 8 02/17/1998 - 02/23/1998 34 08/17/1998 08/2N1998 l 9 02/23/1998 - 0302/1998 35 08/24/1998 - 08/31/1998 l 10 0302/1998 - 0309/1998 36 08/31/1998 - 09/08/1998 l 11 03/09/1998 - 03/16/1998 37 09/08/1998 - 09/14/1998 12 03/16/1998 - 03/23/1998 38 09/14/1998 - 09/21/1998 13 03/23/1998 - 03/30/1998 39 09/21/1998 09/28/1998 14 03/30/1998 - ON06/1998 40 09/28/1998 10/05/1998 15 0406/1998 - 04/13/1998 41 10/05/1998 10/12/1998 18 04/13/1998 - 04/20/1998 42 10/12/1998 - 10/19/1998 17 04/20/1998 - 04/27/1998 43 10/19/1998 10/26/1998 18 ON27/1998 - 0504/1998 44 10/26/1998 - 11/02/1998 19 0504/1998 - 05/11/1998 45 11 02/1998 11/09/1998 20 05/11/1998 - 05/18/1998 46 11/09/1998 - 11/16/1998 21 05/18/1998 - 05/26/1998 47 11/16/1998 11/23/1998
- 22 05/26/1998 - 0601/1998 48 11/23/1998 - 12/01/1998 23 0602/1998 - 0608/1998 49 12/01/1998 - 12/07/1998 24 06/08/1998 - 08/15/1998 50 12/07/1998 - 12/14/1998 25 06/15/1998 06/22/1998 51 12/14/1998 12/21/1998 26 06f22/1998 06/29/1998 52 12/21/1998 - 12/29/1998 D-7
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. 1 APPENDIX E l
!- SYNOPSIS OF ANALYTICAL PROCEDURES
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APPENDlX 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 and Teledyne Brown Engineering to obtain the sample activities.
O O
E-1
r DETERMINATION OF GROSS BETA ACTIVITY IN WATER SAMPLES (TOTAL SUSPENDED AND DISSOLVED FRACTIONS)
GPUN Environmental Radioactivity Laboratory 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 samp!e is evaporated on a hot plate, and the residue 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 l efficiency based on the weight of residue on each planchet.
Calculation of Sample Activity and 2 Siama Uncertainty:
C-B R=
2.22x EoxTFxVxT 2x4C- B
~w .
2.22x EoxTFxVxT 4.66x5 LLD=
2.22x EoxTFxVxT Where:
R = Activity of sample in picoeuries per unit volume or weight. Volume -
or weight units are those used for V.
2s = 2 Sigma Counting Uncertainty LLD = Lower Limit of Detection -
C = Sample Counts B = Blank Counts Eo = Efficiency of the counter TF = Transmission Factor T = Acquisition time in minutes V = Volume or weight of aliquot analyzed.
E-2
DETERMINATION OF GROSS BETA ACTIVITY IN WATER SAMPLES (TOTAL SUSPENDED AND DISSOLVED FRACTIONS)
Teledyne Brown Enoineerino
. This describes the process used to measure the radioactivity of water samples without identifying the radioactive species present. No chemical separation techniques are involved.
S 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 portion of the sample. The filter is dried and mounted on a planchet. The filter which 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 efficiency based on the weight of residue on each planchet.
Calculation of Sample Activity and 2 Siama Error:
N , B Restill [~ ~)fNt{ 18 (pri l} (2.2 ?)(v)(E) ~ (2.22)(s)(E)
Net Activity Counting Error where:
N = total coun'.s from sample (counts) t, = counting time for sample (min)
G = background rate of counter (cpm) to = counting time for background (min) 2.22 = dpm/pCi
~
v = volume in liters E = efficiency of the counter 2 = multiple of counting error The MDA is defined as that value equal to the two sigma counting error of the result.
E-3
DETERMINATION OF TRITIUM IN WATER BY LIQUID SCINTILLATION COUNTING GP'JN Environmental Radioactivity Laboratorv Seven (7) milliliters of sample is filtered through a 0.45 micron filter into a vial and ,
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 OlP 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 Siama Uncertaintv:
C. IJ R=
2.22x EoxVxDF C fl y,\l T.,Ts
~y. ,
2.22x EoxVxDF .
S 773 , 3.29x\ T. T-2.22x EuxVxDF Where: -
T. = Total count time of sample in minutes T3 = Total count time of background in minutes -
R = Tritium activity in picocurie per unit volume (Volume units are those used in V)
-2s = 2 sigma Uncertainty in the same units as above
-LLD = Lower limit of detection in same units as above C = Average count rate of sample G = Average count rate of background Eo = Tritium detection efficiency of counter, calculated as shown below V = Volume of aliquot E-4 s
DF = Decay factor, calculated as shown below
.io wr DF = c tiss~
DT =
time difference in years from collection stop date to counting date of sample The efficiency is calculated as follows: ,
s t S-B Ev = AsxVsxDFs Where:
S = Average count rate for the " efficiency determination" standard j B = Average count rate of background As =. Activity of standard in dpm per unit volume Vs = Volume ~of standard used !
DFs = Decay factor of standard, calculated as follows: l
. \n 2xDTs
- DFS
- C 12 43 i
DTs = time difference (in years) between calibration date and counting date l
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l E - 5' L
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 Siama Uncertaintv:
C-B R-2.22x EoxTFxVxT 2x4C- B 2.22x EoxTFxVxT LLD=
4.66x5 2.22x EoxTFxl'xT Where R =
Activity of sample in picoCuries per unit volume or weight. Volume or weight units are those used for V.
2s~ = 2 Sigma Counting Uncertainty LLD = Lower Limit of Detection C = Sample Counts B = Blank Counts Eo = Efficiency of the counter TF =
Transmission Factor of filter (i.e.1.00 for gross beta, 0.80 for gross alpha)
T = Acquisition time in minutes -
V = Volume analyzed.
~
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DETERMINATION OF GROSS BETA ACTIVITY IN AIR PARTICULATE SAMPLES Teledyne Brown Enaineerina This describes the process usi d 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:
-N N p i l Result , T~0 ,
ti 1,,
(pri m')
2.22(s)(E)(.02832) ~ 2.22(s9(E)(.02832) l l
Net Activity Counting Error where:
N = total counts from sample (counts) t, = counting time for sample (min)
G = background rate of counter (cpm)
- t. = counting time for background (min) 2.22 = dpm/pCi v = volume of sample analyzed in cubic feet calculated from the elapsed time meter E = efficiency of the counter i
2 = multiple of counting error
.02832 = conversion to cubic meters
=
The MDA is defined as that value equal to the two sigma counting error of the result.
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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 Sample Activity and 2 Siama Uncertainty:
The same calculations are used as in DETERMINATION OF GAMMA EMITTING RADIOlSOTOPES below.
e E-8 i
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1 DETERMINATION OF l-131 IN MILK SAMPLES Teledvoe Brown Enaineerina 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 s 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:
N N P Result t
- 0 . ti to, (pri 'I) (2.22)(v)(E)())(exp"') * (2.22)(v)(E)(y)(exp"')
Net Activity Counting Error where:
N = total counts from sample (counts) j
- t. = counting time for sample (min)
B = background rate of counter (cpm) t, i = counting time for background (min) 2.22 = dpm/pCi v = volume of sample analyzed (liters) y = chemical yield of the amount of sample counted A = is the radioactive decay constant for I-131 (0.693/8.05)
At = is the elapsed time between sample collection (or end of the sample collection) to the midcount time 2 = multiple of the counting error E = efficiency of the counter for 1-131, corrected for self absorption
- , effects by the formula:
L, , E. (exp'* **)
.,, um i
where:
l E. = efficiency of the counter determined from an 1-131 standard mount i M = mass of Pdl2 on the sample mount (mg)
M. = mass of Pdl2 on the standard mount (mg)
The MDA is defined as that value equal to the two sigma counting error of the result.
E-9 l
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DETERMINATION OF GAMMA EMITTING RADIOISOTOPES 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.
Food products: The sample is chopped up and put into a counting container and counted.
Caoulation of Sample Activity and 2 Siama Uncertaintv:
P A Ea Aw x e* x 2.22xqxahx Et (1 - e"')
1 where:
A = the computed specific activity !
P = peak area 2.22 = dpm/ picocurie . l q = sample quantity E = detection efficiency b = gamma-ray abundance Et = elapsed live time A = decay constant T3 = acquisition start time Ea = e ipsed real tirne E - 10 l
p-- 1 l
l 1
e y> 2 r$5s2<ggYr ,9,s 2 M~A (ADecay),
<PJ \b) <es \100) l where: M = uncertainty in the activity e
( ). En ADecay = A Ti:x(, _ ,.n, -).(Ts - Es)- 1 Al' = uncertainty in the peak area P Ah = uncertainty in the S-ray abundance AC = uncertainty in the efficiency sys = systematic Uncertainty estimate ( in %)
AT% = uncertainty in the half-life l.
E - 11
i DETERMINATION OF GAMMA EMITTING RADIOlSOTOPES Teledyne Brown Enaineerina Gamma emitting radioisotopes are determined with the use of a lithium drifted germanium (GeLi) and high purity germanium detectors with high resolution ,
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 mi 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 radionuclides standards traceable to the National Bureau of Standards.
Gamma Spectroscoov Statistically Sianificant Activity and 2 Siama Error Calculation for the ND6620 and NF; 30 Systems:
LIl'EliME(sec.) A V* F 037 * (twit mas.s)
(Imil mass, Statistically Significant Activity yog . 42
- BKGND - AREA , ,
AREA 2 Sigma Counting Error Where:
AREA = Net Peak Area (from Nuclide Line Activity Report)
BKGND = Compton Background (from Nuclide Line Activity Report DECAY = Decay Correction Factor (from Minimum Detectable Activity Report) (Nuclide Half Life - Collection time to Mid Count time)
LIVE TIME = Elapsed Live Time ( from Header Information)
E - 12 i
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ABN = Nuclide Abundance (from Nuclide Line Activity Report)
EFF = Detector Efficiency (from Nuclide Line Activity Report) 0.037 =- Conversion Factor (dps to picocurie) unit mass = Sample weight or volume (from Header Information)
Gamma Spectroscopy Statistically Non Sianificant Activity and 2 Siama Error Calculation for the ND6620 and ND6700 Systems:
Activin' "
AlWA
- DECAY PIC
( , UI'ETIAfE(sec.)
- ABN
- EFF
- 0.037 * (mlit ma.u) tillit 111GM Statistically Non Significant Activity 42
- BK(iND - NET t 200
- _ ,
- Net Activity 2 Sigma Counting Error where:
NET = Net Peak Asea (from Minimum Detectable Activity Report)
BKGND = Compton Background (from Nuclide Line Activity Report)
DECAY = Decay Correction Factor (from Minimum Detectable Activity Report) (Nuclide Half Life - Collection time to Mid Count time)
LIVE TIME = Elapsed Live Time ( from Header Information)
(EFF*B.1) = Efficiency
- Abundance (from Minimum Detectable Activity Report) 0.037 = Conversion Factor (dps to picocurie) unit mass = Sample weight or volume (from Header Information) e
< E - 13
r-l l
4 l
l Gamma Spectroscoov Minimum Detectable Activity Calculation for the ND6620 and ND6700 Systems:
MDA 2.83 JBKGN
- DECAY \
PiC
( , Lil'ETIME(sec.) * (EFF
- B. L )
- 0. 037 * (imit mass) iiIlll Mt1.%%
where:
BKGN = Total Peak Background Area (from Minimum Detectable Activity Report)
DECAY = Decay Correction Factor (from Minimum Detectable Activity Report) (Nuclide Half Life - Collection time to Mid Count time)
LIVE TIME = Elapsed L.ive Time ( from Header information)
(EFF*B.1) = Efficiency
- Abundance (from Minimum Detectable Activity Report) 0.037 = Conversion Factor (dps to picocurie) unit mass = Sample weight or volume (from Header Information) l O
E - 14 i
ENVIRONMENTAL DOSIMETRY GPUN Environmental Radioactivity Laboratory GPU Nuclear thermoluminescent dosimeters (TLDS) are Panasonic Type 801 AS 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
, sulfate 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 sulfate elements from beta radiation, so that they respond to gamma radiation only.
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 are 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 l entire quarter, and receive essentially no transit exposure. All control end field badges are read together at the end of each quarter, and the average field contro!
l* badge exposure is subtracted from the average shield control badge exposure to 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 E-15 1
l i
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.
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r 4
1 I
J APPENDIX F i
QUALITY CONTROL EPA INTER-LABORATORY COMPARISON PROGRAM I
4 I
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 analyses of water samples due to budget reductions within EPA. To supplement this program both laboratories contracted with an independent vendor Analytics to provide additional media for analysis. In addition GPU Nuclear participates in the DOE Radiological Comparison Program. The results of these Inter-laboratory programs represent the various media as found in the Limerick Generating Station 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.
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F-1
TABLE F-1 1998 USEPA Cross Check Program Results EPA Control GPU TBE Collection Lirnits Results Results Date Media Nuclide (A) (B) (B) 01/16/98 Water Sr-89 8.0 1 8.7 8.33 i 0.58 5.00 i 1.73 Sr-90 32.0 i 8.7 34.33 1 1.15 31.67 1 0.58 01/30/98 W ater Alpha 30.5 i 13.2 21.00 1 2.65 33.00 i 2.65 ,
Beta 3.9 i 8.7 7.23 1 0.32 5.60 10.90 02/06/98 Water 1-131 104.9 1 18.2 103.33 1 5.77 (C) 110.00 1 0.00 104.9 1 18.2 106.67 1 5.77 (D) 03/13/98 Water H-3 2155.0 t 603.8 2166.67 i 57.74 1833.33 i 57.74 04/21/98 Water Alpha 54.4 1 23.6 46.67 1 2.08 50.00 1 1.73 Beta 94.7 1 17.3 87.33 1 11.02 102.00 1 6.56 Co-60 50.0 1 8.7 50.00 1 1.00 52.33 t 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 1 2.31 21.67 i 1.15 Cs 134 22.0 i 8.7 20.00 1 1.00 21.00 i 1.00 Cs-137 10.0 1 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 i 0.00 13.00 i 1.00 Zn-65 104.0 i 17 3 105.67 i 7.51 111.67 i 2.52 l
Ba-133 40.0 1 8.7 40.00 1 2.00 35.00 1 2.65
! Cs-134 31.0 1 8.7 29.00 i 1.73 32.33 1 0.58
! Cs-137 35.0 i 8.7 34.33 i 1.15 37.67 1 2.08 l 07/17/98 Water Sr-89 21.0 8.7 21.67 i 2.31 21.00 i 1.00 i Sr-90 7.0 1 8.7 6.67 i 0.58 6.33 1 0.58 07/24/98 Water Alphe 7.2 i 8.7 6.43 1 0.12 5.43 1 0.64 l Beta 12.8 t 8.7 14.00 i 0.00 14.67 i 2.08 08/07/98 Water H-3 17996 i 3122.9 19000.00 i 0.00 16000.00 1 0.00
! 09/11/98 Water 1131 6.1 1 3.5 7.00 10.53 (C) 5.93 2 0.55 6.1 i 3.5 6.60 0.26 (D) 10/20/98 Water Alpha 30.1 1 13.0 25.33 1 1.53 21.67 i 2.31 ,
Beta 94.0 i 17.3 84.67 i 3.21 74.67 7.64 (E)
Co-60 21.0 i 8.7 22.67 1 2.52 22.33 1 1.15 Sr 89 19.0 i 8.7 19.00 1 1.00 18.33 i 1.53 Sr90 8.0 i 8.7 5.00 1 0.00 8.33 i 1.15 Cs-134 6.0 i 8.7 6.67 10.58 6.67 1 0.58 Cs-137 50.0 i 8.7 53.67
- 2.52 56.33 3.79 11/6/98 Water Co-60 38.0 1 8.7 38.00 i 1.00 39.67 1 2.52 Zn-65 131.0 1 22.6 146.67 i 5.77 140.67 1 10.97 Ba-133 56.0 1 10.4 59.67 1 1.53 46.33 1 2.52 Cs-134 105.0 1 8.7 103.00 1 6.08 103.00 1 2.00 Cs-137 111.0 1 10.4 116.67 1 5.77 115.33 1.53 11/13/98 Water Alpha 47.2 i 11.8 29.33 t 3.21 23.67 14.04 (E)
Beta 3.5 i 5.0 8.67 1 1.53 5.50 1 0.87 F-2 ;
c: .
A. The EPA Control Limit was the known concentration i 3 sigma for three determinations. The units are pCi/L B. The GPU and TBE results are the average of taree determinations 2 one standard deviation. The units are pCi/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 1131 in the sample was not concentrated prior to counting.
!* E. Results are underinvestigation.
Criteria are listed m 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, Bq/kg (dry) for soil. Bq/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 (112 5 Bq/kg) was not acceptable with the EML value (2.678 2 0.212 Bq/kg). The ratio was 4.108. A reanalysis was requested and the result (5.211.6 Bq/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 (17.0012.00 Bq/L) reported to the EML was not within acceptable agreement with the EML value (13.6011.20 Bq/L). A reanalysis was requested. The reanalysis result (14.77 i 1.282 Bq/L) has a ratio of 1.086, which was within acceptable agreement with the EML value. The original raw (non-rounded) results were 16.0121.042 and 16.50 i1.047 Bq/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%
bias.
I. This sample has been analyzed five times.
The results were:
8.6E-06 i 0.9E-06 uCi/ml 319 Sq/L 8.0E-06 i 0.8E-06 296 7.8E-0610.9E-06 289 l 8.0E-0610.9E-06 296 l 9.8E-06 i 0.1 E-05 363 All of the results are similar.
l The nuclides in this water matrix were unlike any analyzed in the ERL for Fe-55. Thesu nuclides y may have caused the high results. Eighteen laboratories reported Fe-55 results to the EML in QAP ;
- 48. Seven (7) were Acceptable (A), seven (7) were Acceptable with Warning (W) and four (4) were !
Not Acceptable. Only two (2) laboratories reported values below the EML value. Of the 14 "A" and i "W" reported values the Mean ratio was 1.194 (242 Bq/L). This indicates that the EML value (202.8 l 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
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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 3) which was used to purify the precipitant appeared not to react as in the past.
Notably the dark color of TiCl3 faded immediately after being added to the final solution. After 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 3and the interfering peaks were eliminated. The reported result was within 0.1 sigma of the
- known value. Also, the other two media from the EML were processed with extra TiCl3 and yielded acceptable results. It appears that the TiCl 3lost its strength and more was needed to purify the final precipitant solution. A new reagent has since been purchased for future analysis.
L. The Sr-90 in EML soil result (19 i 7 Bq/kg) was not acceptable with the EML value (39.6310.003 Sq/kg).The ratio was 0.479. A reanalysis was performed using a larger aliquot and this result (39 i 5 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 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 1.5 t 0.6 Bq/l. The EML value was 2.1110.18 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 analysis 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 control simits are presented in DOE report EML-564. The control limits for QAP-XLVil were developed from percentiles of data distributions for the years 1991 - 1998.
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APPENDIX G LGS SURVEY l
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APPENDIX G: LGS SURVEYS 1
A Land Use Census around the Limerick Generating Station (LGS) was conducted by Normandeau Associates, RMC Environmental Services Division for PECO Energy to comply with Sections 2.5.1 and 3.4.2 of the Plant's Offsite Dose Calculation Manual.
The survey was conducted during the May to September 1998 growing season. The distance and direction of all locations were positioned from the barn to the LGS vents using Global Positioning System (GPS) technology. The results of this survey are summarized in Table G-1 J
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G-1 4
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Table G-1 Location of Nearest Residence, Garden and Milk Farm within a Five Mile Radius of Limerick Generating Station,1998 (Distance in Miles)
Sector Residence Garden (1) Milk Farm , 1 1N 0.6 1.6 4.7 4
2NNE 0.5 0.5 -
3 NE 0.8 1.5 -
4 ENE 0.6 2.5 -
5E 0.6 1.0 -
6 ESE 0.5 1.2 1.1
- 7 SE 1.0 1.1 -
8 SSE 1.0 1.2 -
9S 0.8 1.2 2.3 10 SSW 1.0 1.1 1.8 11 SW 0.6 0.6 3.0 12 WSW 0.8 1.4 2.8 13 W 0.6 2.2 2.7 14 WNW 0.7 0.8 -
15 NW 0.6 1.6 -
16 NNW 0.8 1.5 -
(1) Garden greater than 500 square feet (2) Goat Milk G-2