ML20217M647
| ML20217M647 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 12/31/1997 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20217M607 | List: |
| References | |
| 14, NUDOCS 9805050077 | |
| Download: ML20217M647 (116) | |
Text
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1 Docket No:
50-352 50-353 LIMERICK GENERATING STATION UNITS 1 and 2 Annual Radiological Environmental Operating Report Report #14 1 January Through 31 December 1997 Prepared By PECO Nuclear 96 hes er r o BI Wayne, PA 19087 5691 May 1998 gg50ggy gjggg52 R
Docket No-50-352 50-353 LIMERICK GENERATING STATION UNITS 1 and 2 Annual Radiological Environmental Operating Report Report #14 l
1 January Through 31 December 1997 l
l Prepared By i
l v
PECO Nuclear 96 hes e r ok I
Wayne, PA 19087-5691 1
May 1998
TABLE OF CONTENTS l
- 1. Summary and Conclusions,.,
.1
- 11. Introduction.,.........................
3 A. Objectives of the REMP.,,,,,.............
3 B. Implementation I the Objectives.,.,,.............................,
.....3 Ill. Program Description,,...,,...,,,,,
.4 A. S ample C ollection...................................,,,,
.4 B. S am ple Analysi s.,,.................,,......................,................,.,...... 6 C. Data Interpretation,,,,.....,,..................,.......
.......,....,6 D. Program Exceptions.,.
7 E. P rog ra m C h ange s,,,,,...,,,,........,....,,,,............,,,........,,,,,,,
,,,.9 IV, Results and Discussion............................................................................. 9 A. Aquatic Environment.,.
.,,,,,,,,,,9
- 1. Surface Water..,........,,,
,,,.......,9
- 2. Drinking Water,,,....,,,
,,,.9 3,
Fish..........................................,.,,.......,,,,,,,,,.,.....10
- 4. Sediment.................,
...10 B. Atmospheric Environment..,
,,,..........,,,,,................,.,,,.11
- 1. Airborne,.,,,,,,
.. 11
- a. Air Particulates........
11
- b. Airborne lodine......
.12
- 2. Terrestrial.
12
- a. Milk,
12 C. Ambient Gamma Radiation,,,,,,
,13
+
D,10 CFR 20.2002 Permit Storage Area.
13 V. References.,,.
14
.g.
i
i i
Appendix'A -
' Radiological Environmental Monitoring Report Summary
' Appendix'B
. Sample Designation and Locations Appendix C -
Data Tables and Figures - Primary LEboratory Appendix D Data Tables and Figures - OC Laboratory
.ippendix E -
Synopsis of Analytical Procedures Appendix F Quality Control - EPA Intercomparison Program Appendix G -
LGS Surveys
- ii -
t-
~
1.
Summary and Conclusions ~
.-This report on the Radiological Environmental Monitoring Program conducted for the Limerick Generating Station by PECO Nuclear covers the period 1 January 1997 through 31 December 1997.- During that time period,1134 analyses were performed on 914 samples.
Surface and drinking water samples were analyzed for concentrations of tritium
= and gamma emitting nuclides.
In addition, drinking water _ samples were 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 fourth quarter. The levels detected were very low, but were
' the result of LGS effluent releases.
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. Sediment samples collected below the discharge had Cs-137
. concentrations consistent with levels observed during the preoperational years.
In addition, zinc-65 was found in sediment at the downstresm indicator locations and was the result of LGS releases. The dose to a teenager's skin through the sediment pathway was calculated as 1.2 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 l
observed at levels consistent with those observed in other years. No fission or j
activation products were detected.
High sensitivity 1-131 analyses were performed on weekly air samples. All results were less than the minimum detectable activity.l Cow and goat' milk samples were analyzed for concentrations of I-131 and gamma emitting nuclides. All 1-131 results detected were below the minimum detectable activity Concentrations of K-40 were consistent with those observed in other yeas. No fission or activation products were found.
Environmental gamma radiation measurements were made quarterly using thermoluminescent dosimeters. Levels detected were consistent with those observed in other years.
. 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 impact on the environment.
l I
II.
Introduction -
.The Limerick Generating Station (LGS). Mnsisting of two 3458 MWt boiling -
water reactors owned and operated b; 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 which feed into the Schuylkill River. On the eastern 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 to the western site boundary.
' A Radiological Environmental Monitoring Program (REMP) for LGS was initiated-in 1971. Review of the 1971 through 1977 REMP data resulted in the modif: cation of the program to comply with changes in the Environmental Report
. Operating License Stage (EROL) and the Branch Technical Position Paper (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 ~
J I
report. This report covers those analyses performed by GPU Nuclear and Teledyne Brown Engineering (TBE) on samples collected during the period 1 l
January 1997 through 31 December 1997.
J On July 6,1997 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 -
will decay to background. Final disposition will be determined at decommissioning of the Station.
A.
Objectives of the REMP The objectives of the REMP are to:-
-l 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 from principal pathways of exposure.
B.
. implementation of the Objectives
- The implementation 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 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 1997. Sample locations and descriptions can be found in Tables B-1 and B-2, and Figures B-1 through B-3, Appendix B.
Aauatic Environment The aquatic environment was examined by analyzing 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 i
feeder) and sunfish (predator), were collected semiannually at two locations: 16CS and 29C1 (control). Sediment samples composed of recently deposited substrate were collected at three locations semiannually: 1682 and 16C4 (indicator) and 33A2 (control).
Atmospheric Environment The atmospheric environment was examined by analyzing 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 controllocation was 22G1. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately 1 1
cubic foot per minute. The filters were replaced weekly and sent to the laboratory for analysis.
Milk' samples were collected biweek'y at five locations (9G1,10B'1,18C1, l
1981, and 2181) during April through November, and monthly during December through March. Four additional locations (36E1,22C1,23F1 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.
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 rina consisting of sixteen locations (36S2,3S1, SS1,7S1, 10S3,11 S1,.13S2,14S1,18S2, 21 S2, 23S2, 25S2, 26S3, 29S1, 31 S1 -
and 34S2) near and within the site perimeter representing fence post 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, 4E1, 7E1,10E1,.10F3,13E1,16F1,19D1, 20F1, 24D1, 25D1, 28D2, 29E1, 31D2, and 34E1) extending to approximately 5 miles from the site designed to measure possible exposures to close-in population.
The balance of eight locations (SH1,6C1,9C1,13C1,15D1,1781,20D1 and 31D1) 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 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.
4 i
.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 Storaoe Area l
- 1. The results of the surface water sampling program is used to i
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.
l 3.
Concentrations of tritium in surface and drinking water.
l 4.
Concentrations of I-131 in air and milk.
1 5.
Ambient gamma :0diation levels at various site environs.
C.
Data Interpretation f-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, LGR 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. These factors are discussed here to avoid undue repetition in the discussion of the results.
1.
Lower Limit of Detection and Minimum Detectable Activity l
l 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 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.
1 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 Activity Calculation and Reportina of Results q
l 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 may 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 f
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 these results were calculated.
These standard deviations represent the variability of measured results for different samples rather than single analysis uncertainty.
]
D.
Program Exceptions For 1997 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 weeks of 5/6/97, 7/28/97,8/26/97,11/3/9,11/24/97 and 12/1/97 due to equipment related problems.
2.
Surface water samples collected at location 24S1 (LGS Intake) were composites of weekly grabs during the week of 5/19/97 due to a sample collection error.
3.
Surface water samples collected at location 13B1 (Vincent Dam) were composites of weekly grabs during the weeks of 1/27/97, and 5/19/97 due to equipment related problems. -
i 4.
Surface water samples collected at location 13B1 (Vincent Dam) were composites of weekly grabs during the weeks of 1/6/97, 3/10/97 and 4/14/97 due to sample collection errors.
\\
5.
Surface water samples collected at location 10F2 (Perkiomen Creek) were composites of weekly grabs during the week of 6/2/97 due to equipment related problems.
l 6.
Drinking water samples collected at location 16C2 (Citizen's Utilities) were composites of weekly grabs during the week of 2/14/97 due to equipment related problems.
7.
Drinking water samples collected at location 15F7 (Phoenixville) i were composites of weekly grabs during the weeks of 6/30/97, 7/7/97,7/14/97,7/21/97,7/28i97 and 8/4/97 due to equipment related problems.
8.
Drinking water samples collected at location 28F3 (Pottstown) were composites of weekly grabs during the week of 4/22/97 due to equipment related problems.
9.
Milk samples from farm 10B1 were not available from January 1 to May 29 and September 30 through December 31,1997, because the goats had stopped lactating.
10.
TLD location 6C1 was vandalized during the first quarter of 1997.
?
The TLDs were recovered but the data was suspect.
11.
The air particulate and air iodine filters from sampling location 11S1 were not available for week no 51 due to a sample collection j
error.
12.
The air particulate and air iodine filters from sampling location 22G1 were not available for week no 28 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.
3 I
W
' E.
- Program Changes There were no program changes made for 1997.
IV.
Results and Discussion 1
I A.
Aquatic Environment 1.
Surface Water Samples were taken from a continuous samp,ler at three locations (10F2,1381, and 24S1) on a monthly schedule. Of these =
locations, only 1381 cc,uld be affected by Station discharges. The following analyses were performed.
Tritium Monthly samples from al_l locations were composited quarterly and analyzed for_ tritium ac.tivity (Table C-l.1, Appendix C). Tritium activity ranged from -32 to 380 pCi/l. The elevated tritium level of 380 pCi/l was observed during the fourth quarter at the indicator location 1381. Ar investigation indicated that during that quarter approximately 30 curies of tritium were released to the river.
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 31 samples. ' Potassium-40 results ranged from -26 to
'44 pCill.. All other nuclides searched for 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.
(15F4,115F7, and 16C2) could be affected by Station discharges.
The following analyses were performe'd:
i l
Gross Beta -
Semples 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 -2.6 to 4.1 pCi/l for
~ the insoluble fraction and from -0.5 to 5.5 pCill for the soluble
.g.
fraction. Co'ncentrations 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 9.6 to 240 pCi/l. The tritium that was found was due station releases.
Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-II.4, Appendix C). All nuclides searched for 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:
l-j Gamma Spectrometrv l
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 were found. The K-40 activity ranged from 2900 to 3700 pCi/kg (wet). Historical levels of Cs-137 are shown in Figure C-3, Appendix C.
4.
Sediment Aquatic sediment samples were collected at three locations (16B2, 16C4 and 33A2) semiannually. Of these locations, two (16B2 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 and Th-232 and the fission products Zn-65, and Cs-137-. The l
lnuclides 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 50 '
to 1,100 pCi/kg for Be-7 and from 820018,000 pCi/kg for K-40.
Concentrations of the fission product Cs-137 were found in sediment samples from both indicator locations. Location 16C4 -
had the highest average concentration of 116 pCi/kg (dry). The activity detected was consistent with those observed in the
- pre-operational years (Figure C-4, Appendix C). Zinc-65 was j
.found at both downstream indicator stations'. Location 16C4 had the highest average concentration of 107 pCi/kg (dry).~ The dose to a teenager's skin through the sediment pathway was calculated as-1.2 E-3 mrem.
B.
Atmospheric Environment l
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),
j Group ll represents the location at an intermediate distance from the LGS site (13C1), and Group Ill represents the control location at a remote distance from LGS (22G1). The j
following analyses were performed:
i 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 l}
ranged from 4 to 28 E-3 pCi/m with a mean of.15 E-3 pCi/m. The results from the Intermediate Distance location (Group il)' ranged from 6 to 28 E-3 pCi/m' with a mean of 16 E-3 pCi/m The results from the Distant locations (Group lil) ran pCi/m'ged from 7 to 31 E-3 pCi/m with a mean of 16 E-3 Comparison of the 1997 air particulate data with previous years data suggest no effects from the operation of LGS (Figure C-5, Appendix C). In addition a comparison of the weekly mean values for 1997 indicate no notable differences among the three groups (Figure C-6, Appendix C).
Gamma Spectrometry Weekly samples were composited quarterly and analyzed for gamma emitting nuclides (Table C-V.3, Appendix C).
Naturally occurring Be-7 due to cosmic ray activity was detected in all samples. These values ranged from 42 to 110 E-3 pCi/m' All other nuclides searched for were less than the minimum detectable activity.
b.
Airborne lodine Continuous air samples were collected from five (10S3, 1181,14S1,13C1, 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 -16 to 27 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 -0.3 to 0.4 pCi/l.
Gamma Spectrometry Each milk sample from locations 10B1,18C1,19B1,21 B1 and 22F1 were analyzed for concentrations of gamma emitting nuclides (Table C-Vil.2, Appendix C).
Potassium-40 activity was found in all samples. The values - - -
ranged from 1300 to 1900 pCill. All other nuclides searched for 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. month, with a range of 4.1 to 10.3 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 SH1 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 historic.al 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.
1 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.-
4.
Radiological Environmental Operating Report No. 2, Limerick' Generating Station Units 1 and 2,1 January through 31 December 1985,' Philadelphia Electric Company, analyses by Teledyne isotopes.
. 5.
Radiological Environmental Operating Report Noc 3, Limerick Generating Station Units 1 and 2,1 January through 31 December 1986, Philadelphia :
i Electric Company, analyses by Teledyne isotopes.
o 6.
Radiological Environmental Operating Report No. 4, Limerick Generating Station Units 1 and 2,1 January through 31 December 1987, Philadelphia Electric Company, analyses by.Teledyne isotopes.
7.
. Radiological Environmental Operating Report No. 5, Limerick Generating Station Units.1 and 2,1 January through 31 December 1988, Philadelphia Electric Company, analyses by Teledyne isotopes.
8.
Radiological Environmental Operating Report No. 6, Limerick Generating Station Units 1 and 2,1 January through 31 December 1989, Phi!adelphia Electric Company, analyses by Teledyne isotopes.
9.
Radiological Environmental Operating Report No. 7, Limerick Generating Station Units 1 and 2,1 January through 31 December 1990, Philadelphia Electric Company, analyses by Teledyne isotopes.
10.
Radiological Environmental Operating Report No. 8, Limerick Generating Station Units 1 and 2,1 January through 31 December 1991, Philadelphia Electric Company, analyses by Teledyne isotopes.
11.
Radiological Environmental Operating Report No. 9, Limerick Generating Station Units 1 and 2,1 January through 31 December 1992, Philadelphia Electric Company, analyses by Teledyne isotopes.
12.
Radiological Environmental Operating Report No.10, Limerick i
Generating Station Units 1 and 2,1 January through 31 December 1993, PECO Energy Company, analyses by Teledyne isotopes.
13.
Radiological Environmental Operating Report No.11, Limerick Generating Station Units 1 and 2,1 January through 31 December 1994, PECO Energy Company.
14.-
Radiological Environmental Operating Report No.12, Limerick Generating Station Units 1 and 2,1 January through 31 December 1995,.
PECO Nuclear.
15.
Radiological Environmental Operating Report No.13, Limerick Generating Station Units 1 and 2,1 January through 31 December 1996, PECO Nuclear.
l
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1 APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT
SUMMARY
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l APPENDIX B SAMPLE DESIGNATION AND LOCATIONS i
l
1 APPENDIX B:
SAMPLE DESIGNATION AND LOCATIONS
- LIST OF TABLES AND FIGURES TABLES 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,1997 FIGURES FIGURE B-1:
Environmental Sampling Locations Within One Mile of the Limerick Generating Station,1997 FIGURE B-2:
Environmental Sampling Locations Between One and Five Miles from the Limerick Generating Station,1997 FIGURE B-3:
Environmental Sampling Locations Greater Than Five Miles from the j
Limerick Generating Station,1997 B-i
TABLE B-1: Location Designation and Identification System for the Limerick Generating Station XXYZ -
General code for identification of locations, where:
}%
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.
Radial Zone of Sampling Location (in this report, the radial distance from X
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 q
D 3-4 miles off-site Z
Station's Numerical Designation within sector and zone, using 1, 2, 3... in each sector and zone.
B-1
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i APPENDIX C 2
DATA TABLES AND FIGURES PRIMARY LABORATOPsY t
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APPENDIX C:
DATA TABLES AND FIGURES - PRIMARY LABORATORY i
TABLES Table C-l.1 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, i
1997.
Table C-l.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Limerick Generating Station,1997.
Table C-II.1 Concentrations of Gross Beta Insoluble in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station,1997.
i Table C-II.2 Concentrations of Gross Beta Soluble in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station,1997.
Table C-II.3 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 1997.
Table C-II.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station,1997.
)
Table C-Ill.1 Concentrations of Gamma Emitters in Fish Samples Collected in the Vicinity of Limerick Generating Station, 1997.
I 1
Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples j
Collected in the Vicinity of Limerick Generating Station, j
1997.-
i i
i Table C-V.1 Concentrations of Gross Beta in Air Particulate Samples i
Collected in the Vicinity of Limerick Generating Station, 1997.
l i
C-i
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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,1997, j
l Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station,1997.
Table C-VI.1 Concentrations of I-131 in Air lodine Samples Collected in the Vicinity of Limerick Generating Station,1997.
Table C-Vil.1 Concentrations of I-131 in Milk Samples Collected in the Vicinity of Limerick Generating Station,1997.
Table C-Vil.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 1997.
Table C-Vill.1 Quarterly TLD Results for Limerick Generating Station, 1997.
Table C-Vill.2 Mean TLD Results for the Limerick Generating Station Site Boundary, Middle and Outer Rings,1997.
Table C-Vill.3 Summary of the Ambient Dosimetry Program for Limerick Generating Station,1997.
Table C-IX.1 Summary of Collection Dates for Samples Collected in the Vicinity of Limerick Generating Station,1997.
FIGURES Figure C-1 Mean Monthly insoluble Gross Beta Concentrations in Drinking Water Samples Collected in the Vicinity of LGS, 1982-1997.
Figure C-2 Mean Monthly Soluble Gross Beta Concentrations in Drinking Water Samples Collected in the Vicinity of LGS, 1982-1997.
C -ii
[
f Figure C-3 Mean Annual Cs-137 Concentrations in Fish Samples
]
Collected in the Vicinity of LGS, 1982-1997.
Figure C-4 Concentrations of Cs-137 in Sediment Samples Collected in the Vicinity of LGS, 1982-1997.
Figure C-5 Mean Monthly Gross Beta Concentrations in Air Particulate Samples Co'lected in the Vicinity of LGS, 1982-1997.
Figure C-6 Mean Weekly Gross Beta Concentrations in Air Particulate Samples Collecwd in the Vicinity of LGS,1997.
Figure C-7 Mean Quarterly Ambient Gamma Radiation Levels in the i
Vicinity of LGS, 1985-1997.
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C - iii
O TABLE C-l.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION,1997 RESULTS IN UNITS OF PCl/ LITER +/- 2 SIGMA COLLECTION 10F2 1381 24S1 PERIOD JAN-MAR (1) 57 i 60 42 i 59 APR-JUN
-32 i 60 120
- 70
-21 61 JUL-SEP 16 i 60 130 i 70 50 1 64 OCT-DEC 44 i 60 380 i 70
-10 2 57 MEAN 9t 77 172 285 15
- 72 4
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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, 1997 RESULTS IN UNITS OF PCl/ LITER +/- 2 SIGMA fER OD 15F4 15F7 16C2 28F3 JAN O 4 20.8 0.1 20.8 1.4209 0.7208 FEB
-0.2 21.0
-0.8 21.0
-0.9209
-0.8 ti.0 MAR 0.3 20.5 0.5 10.5 0.2 20.5 0.3 20.5 APR 2.6109
-2.3 11.0
-1.1 11.0
-0.8 11.0 MAY
-0.3 10.9 0.6 10.9 0.1 10.9
-0410.9 JUN
-0.2 20.9
-0.4 0.9 0.2 21.0
-0.5 10.9 JUL 0.2 20.8 0.1 20.8
-0.2 20.8 0.1 20.8 AUG
-0.2 10.9 0.1 10.9 1.1 20.8
-0.3 to.9 SEP 1.7 21.2
-1.9 it.2
-0.8 21.3 0.2 t1.3 OCT 0 21.1 0.1 21.1 0 6 ti.1 0.2 21.1 NOV 0.2 20.6 0.6 10.6 0.6 to.6 0.6 10.6 DEC 1.5 21.0 2.1 ti.1 4.1 11.2 3.6 t1.1 MEAN
-0222.1
-0.2 t2.3 0.3 12.9 0.2 22.3 TABLE C-II.2 CONCENTRATIONS OF GROSS BETA SOLUBLE IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION,1997 RESULTS IN UNITS OF PCl/ LITER +/- 2 SIGMA fER OD "
15F4 15F7 16C2 28F3 JAN 2.6 21.1 2.7 21.1 2.3 21.1 3.4 21.2 FEB 2.8 21.3 1.2 211 1.5 21.3 1.8 21.3 MAR 3.3 to.8 2.8 20.8 2.5 10.8 2.6 20.7 APR 3.5 21.3 4.2 21.4 3.8 11.4 3.3 21.3 MAY 4721.3 5.5 21.4 3.8 $1.4 3.6 t1.4 JUN 4421.1 2.5 t1.0 2.4 21.0 2.7 11.1 l
JUL 4121.3 3.6 21.3 1,8 21.2 3 11.3 I
l AUG 4421.6 2.2 21.3 4.2 21.6 3 11.5 SEP 4221.6 4.2 21.7 2.2 t1.6 4.3 ti.7 j
OCT 3 4 ti.2 5.3 ti.3 3.4 21.2 4.6 t1.2 1
NOV 3911.1 3521.1 2.9 21.1 4521.2 DEC 0.3216 0.2 t1.6
-0.5 21.6
-0.2 11.7 I
MEAN 3.5 22.4 3.2 23.1 2.5 22.5 3 12.6 TABLE C-II.3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN i
THE VICINITY OF LIMERICK GENERATING STATION,1997 j
i RESULTS IN UNITS OF PCl/ LITER +/- 2 SIGMA i
l hER OD 15F4 15F7 16C2 28F3 JAN-MAR 43 tS9 57 260 39 259 96159 AP R-JUN 19 260 140 170 44 160 34 260 JUL SEP 75 260 120 270 68 160 43 260 OCT-DEC 130 260 240 160 100 160 40 260 MEAN 67 196 139 215 63 156 32 230 l
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)
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A L R C
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E E
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M M
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1 1
3
TABLE C-V.1' CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION,1997 RESULTS IN UNITS OF E-3 PCl/CU METER +/- 2 SIGMA GROUP 1 GROUP 11 GROUP 111 VVEEK 10S3 11S1 14S1 13C1 22G1 NO 1
17 24 21 24 17 24 18 24 16 24 2
19 24 21 24 27 26 18 t4 16 24 3
22 24 22 24 17 24 21 24 17 24 4
15 24 15 t4 17 24 14 24 21 24 5
19 24 20 24
-17 24 14 $4 18 24
-6 18 24 15 24 17 24 16 24 17 24 7
16 24 18 t4 16 24 17 24 15 24 8
20 25 18 24 12 24 18 24 14 24 9
15 23 1223 12 23 12 23 14 t3 10 14 24 13 23 10 23 13 23 15 14 11 19 24 16 t4 20 14 13 24 20 24 12 16 24 16 24 1624 16 24 13 24 13 13 24 14 24 13 t4 12 24 10 4 14 16 24 11 23 16 t4 15 24 14 $4 15 14 24 13 24 15$4 11 4 13 24 16 14t4 16 24 16 24 16 24 19 t4 17 10 24 9 24 11 4 12 24 12 24 18 11 23 15 24 18 24 9 23 16 14 19 16 24 15 24 20 15 16t4 1224 20 11 14 12 24 12 24 17 24 14 24 21 9 23 8 13 6 23 8 23 8 23 22 6 24 4 23 7 24 6 $4 11 24 23 7 13 11 24 8 23 9 23 7 23 24 15 23 14 23 14 3 17 23 15 i3 25 17 24 15 24 15 4 12 24 17 24 26 1824 18 24 19 24 16 24 22 14 27 10 24 10 24 1024 11 24 17 210 28 17 24 18 24 17 24 19 24 18 15 29 21 24 25 i4 20 4 27 5 22 24 30 14 24 13 14 13 24 15 24 14 24 31 19 24 24 14 21 14 20 24 19 24 32 13 24 17 24 17 14 19 14 17 24 33 15 24 15 24 15 $4 14 24 18 i4 34 11 24 11 24 12 14 12 t4 12 24 35 15 i3 18 23 20 23 14 24 15 23 36 12 24 12 t4 14 25 20 25 1625 37 1924 14 24 17 24 13 24 1624 38 19 24 28 24 27 24 25 24 29 24 39 14t4 9 24 14 24 17 24 12 24 40 19 t4 18 24 21 24 20 14 22 24 41 25 24 14 t4 22 t4 24 24 21 24 42 16 24 13 24 15 24 16 24 21 24 43 8 24 8 24 12 24 11 14 8 14 44 18 24 20 24 19 t4 21 24 16 24 45 9 23 8 13 9 23 12 4 11 24 46 12 24 9 4 14 24 11 14 11 24 47 20 $4 27 15 23 4 28 25 19 24 48 18 24 16 14 13 23 15 24 15 24 49 11 24 9 24 1224 9 24 10 24 50 13 23 14 23 11 23 13 23 12 13 I
51 26 25 (1) 27 15 26 +5 31 25 52 1424 1424 13 24 to 23 13 24 MEAN 15 29 15 tia 16110 16 210 16 29 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-8
s E
TA D
L S
U 2
2 5 2 0
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4 3 8 661 6 51 1 8 2 9
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N 8 5 5 4 25 8 6 8 8 4 6 6
O A
1 1 1 1 1 1 1 1 1 1 1 1 1
A I
M E
T P
A R
C 21 21 1 221 2 2 1 3 3
1 70 9 6 2 28 9 29 1 1
O X
I L
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M L
N O
64 0 287 4 2 2 8 1 0 7
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C 7 77 7 7 7 77 77 77 7
/ 99 99 99S99/S9 9
9
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21 1 1 1 1 21 2222 2
1 8 667779 5 4 8 6 8
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4 221 691 23 1 1 9 6
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7 777 77 77 7 77 7 7
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3 3 1 8 20 429 0 29 9
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1 67 8 5
1 4 6 7 1
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a
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31 63 1
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1 1 1 1 0
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T 52 4 0 3 7 3 02 2 7 023 2 6 3 02 0 8 98 5 3
1 N
s 00 0 0 00 0 0 0 00 0 0 0 0
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I D
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i 1 1 1 1 i i 1 1
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S N
ELP 5
1 3 1 1 1
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21 1 2 1
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9 1 000 0 2000 0 0021 0
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n 021 2 0
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1 323 2 2330 2
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U 2324 2 9 35 4 1
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C M 0000 0 0000 0 00 00 0 01 0 0 0 0000 0
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37 02 0073 3
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K 6 01 3 2 9 8 1 1 7
71 26 0 68 03 4 8661 2
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I OT NA S
5 2 7 6 8
7 08 4 9 56 01 2
1 1 7 7 8
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2 2 2 3
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1 1 11 1 i 1
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7 I
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B 508 2 1
1 4 5 3 3
27 1 3 8
9 7 3 6 6
0 0 1 5 7
7 6 64 6 576 6 6 6 695 6 6765 6
0 1 8 5 8
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1 1 R I N
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D S
O 7 7 7 7 7 7 77 7 7 7 7 77 77 7 7 7 7 NA T
I 9/SS9 9 $99 9 9 9 9 99 99 9 9 9 9 ER L
R
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1 CE U
E 3 3 2 2 3 3 22 3 3 2 2 33 2 2 3 3 2 2
// / /
/
l
/ /
/ / / /
/ / / /
/ / / /
P 3 6 9 2 3 6 9 2 3 6 9 2 3 6 9 2 3 6 9 2 NN 3
N 00 0 1 0 001 00 0 1 0001 00 01 OE E
O CG R
I 67 7 7 N
67 7 7 N
6 7 7 7 N
6 7 7 7 N
67 7 7 N TC 9 9 SS A 9 9 9 / A
/ /
/ / / 9 9 9 9S A / 9 S9 A 9 / / S A
/ / /
9
/ 99
/
E 0 1 09 E 0 1 09 E 01 09 E 01 09 E 0 1 09 E
3 L
3 3 3 2 3 3 3 2 3 3 3 2 3 3 3 2 3 3 3 2 M
M M
M M
/ / / /
/ / / /
V L
/ / / /
/ / / /
/ / / /
2 3 6 9 23 6 9 2 3 69 2 3 6 9 2 3 6 9 O
1 0 00 1 0 0 0 1 0 00 1 00 0 1 0 0 0 C
C E
L 3
1 1
t 1
B C S S
C S
G A
T 0
1 3
4 2
T S
1 1
1 1
2
1 l
]
1 TABLE C VI.1 CONCENTRATIONS OF l-131 IN AIR LODINE SAMPLES COLLECTED IN THE q
VICINITY OF LIMERICK GENERATING STATION,1997 i
J RESULTS IN UNITS OF E-3 PCl/CU METER +/- 2 SIGMA GROUPi GROUP ll GROUP til -
WEEK 10S3 11S1 14S1 13C1 22G1 1
J NO 1
4 211
-7 111 1 29 13 214
-5 216 2
-5 tB 2 215 2 29 2 212 11 212 3
-6 29
-2 110
-16 115 2 213 1 18 4
6 110
-5 112 3 t9 12 212 14 t19 5
0 28 3110 2 211 2 27 0 212 6
-7 215
-2 212 27 121 2 213 0 210 7
0 28 0 i9 1 210
-1 $12
-2 17 B
0 212 0 213 3212
-3 t10
-8 214 9
-8 211
-2 215 1 29 8 210 0215 l
10 3 28 4 111 3113
-5 215
-1 t10 J
11 7 27
-4 29 3 211
-8 210
-8 28 12 if :12 2 28 8 12 4 27 2 t8 J
13 t10
-2 211 4 t13 4 214
-3 29 14 0 29 5 213 0i10 3 211 4 212 15
-7 211
-12 211 0 29 5 210
-6 19 16 2 28 8 210 0214
-3 14 2 27 17 0 210 9213
-9 212 6 215
-1 216 18
-5 28
-5 210
-10 212 6 212
-14 211 19 6 210
-8 212 3t10
-10 14
-7 18 20 2 27 12 212 10 211 0 210
-4 t9 21
-4 17 4 29 10 29 4 111
-1 28 22
-6 29
-8 214 4 215 4 t15 8 112 4
23 10 19
-4 210 4 212 3112 4 tii 24 4 19 4 tii 3210
-7 212 0 17 25 4 19
-9 210 4 112 1 112 3 i7 26 10 t9
-3 111 4212
-5 212
-6 9 27 5 t8
+1210
-2 212 0 211 3 214 28 2 28 4 210 2 $7 7 213
-6 t14 29 3 27 2 28 1 27 0 211 6212 30 12 28 1 29
-14 211
-4 212 5 27 31 2 28
-9 29 10 110 1 12 3 27 32 3 27
- 4 29 4 16 3 211 0 111 33 7 t8 1 *10 15 215 5213
-5 210 l
34
-5 210 2 212 3t12
-1 112 2 29 l
35 1 28 6 29
-2 210 0 27
-3 212
{
36 2 211 2 213 6212 0 211 2212 1
37 0 29 5210 6 211
-5 213 2 28 38
-9 210.
2 29
-1 214
-6 212 5 27 39
-5 29 5 29 5 213 1 214
. 7 28 40 0 212
-3 210
-5 213 6 212
-4 *12 41 3 28
.-4 19 2212
-3 215 7 27 42
-6 114 18 tie 4 113 5 112
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-6110 3 213 9 214 2 27 MEAN 15 19 15210-1 214 0 111 0 tit (1) SEE PROGRAM EXCEPTIONS SECTIC.4 FOR EXPLANATION C - 11
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TABLE C-Vill 1 QUARTERLY TLD RESULTS FOR LIMERICK GENERATING STATION,1997 RESULTS IN UNITS OF MILLI ROENTGEN /STD. +/ 2 SIGMA Station MEAN JAN-MAR APR-JUN JUL-SEP OCT-DEC Code
+/- 2 S.D.W
~
36S2 6.4 10.5 6.4 10.6 6.1 10.5 6.4 10.2 6.7 10.2 j
36D1 5.2 t0.4 5.1 to.5 5 to.2 5.3 *0.4 5.5 to.3 2E1 6.5 10.7 6.2 10.4 6.2 10.7 6.9 10.5 6.6 20.5 I
3S1 6.1 t0.6 5.9 10.3 5.8 10.6 6.5 t0.6 6.1 10.3 4E1 4.6 i0.5 4.5 10.2 4.3 iO.2 4.7 to.4 4.8 10.1 l
SS1 7.1 t o.2 7.3 to.8 7.1 to.9 7.2 10.6 7 10.5 SH1 7.5 10.2 7.6 10.5 7.4 10.6 7.5 i0.8 7.5 10.6 6C1 6.3 11.0 (2) 5.8 i1.0 6.8 *0.3 6.4 *0.4 7S1 6.3 10.3 6.3 20.5 6.3 to.8 6.6 20.3 6.3 *0.4 7E1 6.4 10.7 6.4 10.6 6.2 1.3 6.90.4 6.3 10.5 9C1 6 10.5 6 10.2 5.7 11.0 6.4 iO.4 6 *0.6 10S3 6.5 t0.7 6.4 to.4 6 10.3 6.9 *0.6 6.5 *0.4 10E1 6.4 10.4 6.3 20.7 6.2 10.1 6.7 iO.6 6.5 10.2 10F3 6.2 10.5 5.9 0.3 6.2 11.0 6.5 10.3 6.3 10.2 11S1 7.4 10.6 7.1 *0.4 7.1 10.6 7.5 i0.1 7.7 10.3 13S2 10.1 10.3 10.2 *1.1 10.1 iO.9 10 10.8 10.3 i0.5 13C1 4.4 10.5 4.1 t0.5 4.2 10.2 4.6 10.3 4.6 10.3 13E1 6.3 *0.7 5.8 i0.5 6.7 i0.4 6.4 iO.6 6.4 to.3 l
14Si 5.6 iO.7 5.2 i0.4 5.6 10.6 6 *0.5 5.6 10.2 15D1 6.4 10.3 6.4 i0.2 6.5 to.7 6.2 10.2 6.6 10.2 16F1 6.5 10.9 6 i0.6 6.4 10.1 7 i0.6 6.8 10.5 17B1 6 iO.4 5.7 10.2 5.9 *0.6 -
6 10.1 6.2 t0.2 18S2 6.9 10.6 6.5 10.3 6.9 i0.5 7.1 i0.4 7.1 0.3 19D1 5.9 t0.4 5.7 *0.4 5.8 iO.7 6.2 iO.6 6 i0.5 20D1 5.6 10.6 5.3 *0.4 5.3 10.4 5.9 10.4 5.8 t0.5 20F1 6.1 10.4 5.8 10.8 6 10.5 6.2 10,4 6.3 i0.3 21S2 5.5 10.1 5.6 10.2 5.5 to.1 5.5 i0.3 5.5 iO.3 23S2 5.6 10.9 5.7 10.6 4.9 10.3 5.8 10.4 5.9 i0.3 24D1 5.3 10.2 5.1 t0.5 5.2 10.7 5.3 iO.1 5.4 *0.5 25S2 5.5 iO.6 5.3 *0.5 5.2 10.4 5.8 10.5 5.7 10.2 25D1 5 10.7 5 i0.4 4.6 iO.4 5.2 *0.3 5.4 10.3 i
26S3 5.3 10.5 5.1 iO.5 5 10.4 5.5 10.2 5.5 10.4 28D2 5.7 10.6 5.9 i0.3 5.4 10.4 6.1 *0.6 5.6 10.3 29S1 5.3 to.5 5.1 to.3 5.1 *0.2 5.5 10.5 5.5 *0.3 1
29E1 5.8 to.7 5.8 i0.3 5.3 i0.3 6.1 to.7 6 *0.5 1
31S1 6.1 to.7 6 10.8 5.7 to.5 6.1 10.1 6.5 to.3 l
31D1 7.7 t1.0 7.7 10.6 7 to.4 7.9 10.4 8.2 iO.6 31D2 6.4 10.4 6.2 10.3 6.3 10.2 6.5 10.5 6.6 10.3 1
34S2 6.7 10.4 6.8 10.4 6.6 *0.6 6.6 10.6 7 *0.3 34E1 6 to.5 6.2 10.2 5.8 10.2 5.8 10.6 6.3 to.5 (1) Mean and two times the standard deviation of the quarterly results (2) See Program Exception Section for Explanation C - 16
i TABLE Vill.2 1997 MEAN TLD RESULTS FROM LIMERICK GENERATING STATIONFOR THE SITE BOUNDARY, MIDDLE, AND OUTER RINGS 1997 RESULTS IN UNITS OF MILLI-ROENTGEN /STD. MO. +/- 2 STANDARD DEVIATIONS OF THE STATION DATA EXPOSURE SITE MIDDLE OUTER PERIOD RING RING JAN-MAR-6.3 i2.5 5.8 *1.5 7.6 i0.0 APR-JUN 6.2 u.5 5.7 11.5 7.4 10.0 JUL-SEP 6.6 12.2 6.2 i1.5 7.5 10.0 l
OCT-DEC 6.6 t2.4 6.1 t1.5 7.5 *0.0 TABLE Vill.3
SUMMARY
OF THE 1997 AMBIENT DOSIMETRY PROGRAM FOR LIMERICK GENERATING 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 64 4.9 10.3 6.4 12.4 7.6 12.4 MIDDLE RING 92 4.1 8.2 5.9 11.5 7.8 12.2 OUTER RING 4
7.4 7.6 7.5 10.2 7.8 13.0 THE PRE-OPERATIONAL MEAN WAS CALCULATED FROM MONTHLY TLD READINGS 01/15/82 TO SITE BOUNDARY RING STATIONS 36S2,3S1, SS1,7S1,10S3,11S1,13S2,14S1,18S2,21S2,23S2,2SS2,26S3. 29S1,31S1,34S2 MIDDLE RING STATIONS 3601,2E1. 4E1, Sci,7E1,9C1.10E1,10F3.13C1,13E1,1SD1,16F1,1781,19D1,20D1,20F1,24D1, 25D1,28D2, 29E1. 31 D1,3102, 34E1 OUTER RING STATIONS SH1 I
l C - 17
TABLE IX.1
SUMMARY
OF COLLECTION DATES FOR SAMPLES COLLECTED IN THE VIC8NITY OF LIMERICK GENERATING STATION,1997 SURFACE WATER (TRITIUM)
COLLECTION PERIOD 10F2 13B1 24S1 03/31/97 12/30/96 - 03/31/97 12/30/96 JAN-MAR
' 06/30/97 06/30/97 03/31/97 06/30/97 03/31/97 APR-JUN 04/28/97 09/29/97 09/29/97 06/30$7 0909/97 06/30/97 JUL-SEP 06/30/97 12/29/97 09/29/97. 12/29/97 12/29/97 09/29/97 OCT-DEC 09/29 S 7 SURFACE WATER (GAMMA SPECTROSCOPY)
COLLECTION PERIOD 10F2 1381 24S1 12/30/96 - 02/03/97 12/30/96 - 02/03/97 JAN 03/03/97 03/03/97 02/03/97 02/03/97 FEB 03/31/97 03/03/97 - 03/31/97 03/03/97 MAR 0428/97 03/31/97 - 04'28/97 03/31/97 APR 06/02/97 06/02/97 04'28/97 MAY 04/28/97 - 06/02/97 04/28/97 06/30/97 JUN 06/02/97 - 06/30/97
. 06/02/97 - 06/30/97 06/02/97 07/28/97 07/28/97 06/30/97 07/28/97 06/30/97 JUL 06/30/97 09/03/97 07/28/97 - 09/03/97 07/28/97 - 09/03/97 AUG 07/28/97 09/29/97 09/03/97 - 09/29/97 09/03/97 - 09/29/97 SEP 09/03/97 11/03/97 11/03/97 09/29/97 11/03/97 09/29/97 OCT 09/29/97 12/01/97 12/01/97 11/03/97 12/01/97 11/03/97 NOV 11/03/97 12/29/97 12/01/97 - 12/29/97 DEC 12/01/97 - 12/29/97 12/01/97 DRINKING WATER (TRITIUM)
COLLECTION PERIOD 15F4 15F7 16C2 28F3 JAN MAR 12/30/96 - 03/3157 12/30/96 03/31/97 12/30/96 03/31/97 12/30/96 03/31/97 APR-JUN 03/31/97 - 06/30/97 03/31/97 06/30/97 03/31/97 06/30/97 03/31/97 - 06/30/97 JUL-SEP 06/30/97 09/29/97 06/30/97 09/29/97 06/30/97 - 09/29/97 06/30/97 09/29/97 OCT-DEC 09/29/97 - 12/29/97 09/29/97 - 12/29/97 09/29/97 - 12/29/97 09/29/97 - 12/29/97 DRINKING WATER (GAMMA SPECT ROSCOPY)
COLLECTION PERIOD 15F4 15F7 16C2 28F3 JAN 12/30/96 - 02/03/97 12/30/96 - 02/03/97 12/30/96 02/03/97 12/30/96 - 02/03/97 FEB 02/03/97
- 03/03/97 02/03/97 03/03/97 02/03/97 - 03/03/97 02/03/97 03/03/97 MAR 03/03/97 - 03/31/97 03/03/97 03/31/97 03/03/97 - 03/31/97 03/03/97 03/31/97 APR 03/31/97 - 04/28/97 03/31/97 04/28/97 03/31/97 - 04/28/97 03/31/97 04'28/97 MAY 04/28/97 06/02/97 04'28/97 - 06/02/97 04/28/97 06/02/97 04/28/97 - 06/02/97 JUN 06/02/97 - 06/30/97 06/02/97 - 06/30/97 06/02/97 06/30/97 06/02/97 06/30/97 JUL 06/30/97 - 07/28/97 06/30/97 - 07/28/97 06/30/97 - 07/28/97 06/30/97 07/28S7
.AUG 07/28/97 - 09/03/97 07/28/97 - 09/03/97 07/28/97 - 09/03/97 07/28/97 - 09/03/97 SEP 09/03/97 - 09/29/97 09/03/97 - 09/29/97 09/03S7 - 09/29/97 09/03/97 09/29G7 OCT 09/29S 7 - 11/03/97 09/29 S7 11/03/97 09/29/97 - 11/03/97 09/29/97 - 11/03/97 NOV 11/03/97 - 12/01/97 11/03/97 12/01/97 11/03/97 - 12/01/97 11/03/97 - 12/01/97 DEC 12/01/97 - 12/29/97 12/01/97 - 12/29/97 12/01/97 - 12/29S7 12/01/97 - 12/29/97 C - 18
I TATLE IX.1
SUMMARY
OF COLLECTION DATES FOR SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION,1997 AIR PARTICULATE (GAMMA SPECTROSCOPY)
' COLLECTION 1053 11S1 13C1 22G1 PERIOD 14S1 03/31/97 12/30/96 - 03/31/97 03/31/97 12/30/96 - 03/31/97 12/30/96 03/31/97 12/30/96 JAN4/iAR 12/30/96 06/30/97 03/31/97 - 06/30/97 06/30/97 03/31/97 06/30$7 03/31/97 APR-JUN 03/31/97 06/30/97 03/31/97 09/29/97 06/30/97 M/29/97 -
l 09/29/97 06/30/97 09/29/97 06/30/97 JUL-SEP 06/30/97 09/29/97 06/30/97 12/29/97 09/29/97 - 12/29/97 12/29/97 09/29/97 12/29/97 09/29/97 12/29/97 09/29/97 OCT-DEC 09/29/97 AIR PARTICULATE AND AIR LODINE) 01/06/97 12/30S 6 01/06/97 01/06/97 12/30/96 01/06/97 12/30/96 - 01/06/97 12/30/96 1
12/30/96 01/13/97 01/06/97 01/13/97 01/06/97 01/13/97 01/13/97 01/06/97 01/13/97 01/06/97
'2 01/06/97 01/20/97 01/13/97 01/20/97 01/20/97 01/13/97 3
01/13/97 01/20/97 01/13 S 7 - 01/20/97 01/13/97 01/27/97 01/20/97 - 01/27/97 01/27/97 01/20 S 7 01/27/97 01/20/97 01/27/97 01/20 S 7 4
01/20/97 02/03/97 01/27/97 02/03/97 I
02/03/97 01/27/97 02/03/97 01/27/97 02/03/97 01/27/97 5
01/27/97 02/10/97 02/03/97 - 02/10/97 02/03/97 - 02/10/97 02/03/97 02/10/97 1
02/10S7 02/03/97 6
02/03/97 02/18/97 02/10/97 02/18/97 02/10/97 02/18/97 02/10/97 02/18/97 7
02/10/97 02/18/97 02/10/97 02/24/97 02/18/97 - 02/2497 02/18/97 - 02/2497 02/18/97 02/24/97 02/18/97 - 02/24/97 8
02/18S7 03/03/97 02/24/97 - 03/03/97 02/24/97 - 03/03/97 02/24/97 03/03/97
)
9 02/2497 03/03/97 02/24/97 03/10/97 03/03/97 - 03/10/97 03/03/97 - 03/10/97 03/03/97 - 03/10/97 03/03/97 - 03/10/97 10 03/03/97 03/17/97 03/10/97 - 03/17/97 03/10/97 - - 03/17/97 03/10/97 03/17/97 11 03/10/97 03/17/97 03/10/97 12 03/17/97 03/24/97 03/17/97 - 03/24S7 03/17/97 03/24/97 03/17/97 03/2497 03/17/97 03/2497 03/31/97 03/2497 03/31/97 03/24/97 - 03/31/97 03/24/97 - 03/31/97 03/24/97 03/31/97 13 03/24/97 14 03/31/97 04/07/97 03/31/97 - 04/07/97 03/31/97 - 0497/97 03/31/97 04/07/97 03/31/97 - 0497/97 15 0497/97 04/1497 04/07/97 - 04/14/97 04/07/97 04/1497 0497/97 04/1497 04'07/97 04/14/97 16 04/14/97 04/21/97 04/14/97 04/21/97 04/14/97 04/21/97 04/14/97 04/21/97 04/1497 04/21/97 17 04/21/97 04/28/97 04/21/97 - 04/28/97 04/21/97 04'28/97 04/21/97 04/28/97 04/21/97 04/28/97 18 04/28/97 05/05/97 04/28/97 05/05/97 04/28/37 - 05/05/97 04/28/97 - 05/05/97 04'28/97 05/05/97 19 05/05/97 05/12/97 05/05/97 - 05/12/97 05/05/97 - 05/12/97 05/05/97 05/12/97 05/05/97 - 05/12/97 20 05/12/97 05/19/97 05/1297 05/19/97 05/12/97 - 05/19/97 05/12/97 05/19/97 05/12/97 05/19/97 21 05/19/97 05/27/97 05/19/97 05/27/97 05/19/97 05/27/97 05/19/97 - 05/27/97 05/19/97 05/27/97 22 05/27/97 06/02/97 05/27/97 06/02/97 05/27/97 06/02/97 05/27/97 06/02/97 05/27/97 06/02/97 23 06/02/97 06/09/97 06/02/97 06/09/97 06/02/97 - O&99/97 06/02/97 06/09/97- 06/02/97 06/09/97
)
06/16/97 06/09/97 06/16/97 24 06/09/97 06/16/97 06/09S 7 06/16/97 06/09/97 06/16/97 06/09/97 25 06/16/97 06/23/97 06/16/97 06/23/97 06/16/97 06/23/97 06/16/97 06/23/97 06/1&97 06/23/97 j
26 06/23/97 06/30/97 06/2397 06/30/97 06/23/97 06/30/97 06/23/97 06/30/97 06/23/97 - 06/30/97 j
27 06/30/97 07/07/97 06/30/97 07/07/97 06/30 S 7 07/07/97 06/30/97 - 07/07/97 06/30/97 07/07/97 28 07/07/97 07/14/97 07/07/97 07/14/97 07/07/97 - 07/1497 07/07/97 07/14/97 07/07/97 - 07/14/97 29 07/1497 07/21/97 07/1497 07/21/97 07/14/97 - 07/21/97 07/14/97 07/21/97 07/14/97 07/21/97 30 07/21/97 07/28/97 07/21/97 - 07/28/97 07/21/97 07/28/97 07/21/97 07/28/97 07/21/97 - 07/28/97 31 07/28/97 08/0497 07/28/97 08/04/97 07/28/97 - 08/04/97 07/28/97 - 0&94/97 07/28/97 08/0497 4
08/11/97 08/04/97 08/11/97 32 08/04S7 08/11/97 08/04/97 08/11/07 08/0497 - 08/11/97 08/04/97 08/18/97 08/11/97 08/18/97 08/11/97 - 08/18/97 08/11/97 - 08/1&S7 33 08/11/97 08/18/97 08/11/97 08/25/97 08/18/97 08/25/97 34 08/18/97 08/25S7 08/18/97 08/25/97 08/18/97 - 08/25/97 08/18S7 35 08/25/97 09/02/97 08/25/97 - 09/02/97 08/25/97 - 09/02/97 08/25/97 - 09/02/97 08/25/97 - 09/02/97 36 09/02/97 09/0&97 09/02/97 - 09/08/97 09/02/97 - 09/08/97 09/02/97 - 09/08S 7 09/02/97 - 09/08/97 37 09/08/97 09/15/97 09/08/97 09/15/97 09/08/97 09/15/97 09/08/97 09/15/97 09/08/97 - 09/15/97 38 09/15/97 09/22/97 09/1557 - 09/22/97 09/15/97 - 09/22/97 09/15/97 - 09/22/97 09/15/97 - 09/22/97 39 09/22/97 09/29/97 09/22/97 - 09/29/97 09/22/97 - 09/29/97 09/22/97 - 09/29/97 09/2297 09/29/97 40 09/2997 10/06/97 09/29S 7 - 10/06/97 09/29/97 - 10/06S7 09/29/97 10/06S7 09/29/97 - 10/06/97 l
41 10/06/97 10/13S7 10/06/97 10/13/97 10/06/97 - 10/13/97 10/06/97 10/13/97 10/06/97 10/13/97 42 10/13/97 10/20/97 10/13S7 10/20/97 10/13/97 - 10/20/97 10/13/97 - 10/20/97 10/13/97 - 10/20/97 43 10/20/97 10/27/97 10/20/97 10/27/97 10/20/97 - 10/27/97 10/20S7 10/27/97 10/20/97 10/27/97 l
44 10/27/97 11/03/97 10/27/97 - 11/03/97 10/27/97 - 11/03/97 10/27/97 11/03/97 10/27/97 - 11/03S 7 j.
45 10/03/97 11/10/97 10/03/97 11/10/97 10/03/97 11/10/97 10/03/97 - 11/10/97 10/03/97 11/10/97 46 11/10/97 11/17/97 11/10/97 - 11/17/97 11/10/97 - 11/17/97 11/10/97 - 11/17/97 11/10/97 - 11/17/97 47 11/17/97 11/24/97 11/17/97 - 11/24/97 11/17/97 - 11/24/97 11/17/97 - 11/24/97 11/17/97 - 11/24/97 48 11/24/97 1292/97 11/24/97 12/02/97 11/2497 - 12/02/97 11/24'97 - 12/02/97 11/24/97 - 12/02/97 49 12/02/97 12/08/97 129297 - 12/08/97 12/0297 12/08/97 12/02/97 12/08/97 12/02/97 12/08/97 50 12/08/97 12/16/97 12/08/97 - 12/16/97 12/08/97 - 12/16/97 12/08/97 - 12/16S7 12/08/97 - 12/16S7 51 12/16/97 12/22/97 12/08S 7 - 12/16/97 12/16/97 - 12/22/97 12/16/97 - 12/22/97 12/16S7 - 12/22/97 52 12/2297 12/29/97 12/22/97 - 12/29/97 12/22/97 12/29/97 12/22/97 - 12/29/97 12/22/97 - 12/29/97 C.19
TABLE IX.1
SUMMARY
OF COLLECTION DATES FOR SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION,1997 I
STATION JAN. MAR APR JUN JUL SEP OCT-DEC CODE 01/06/98 10/07/97 10/07/97 07/01/97 07/01/97 04/01/97 04/01/9~7 36S2 01/07/97 07/01/97 07/01/97 - 10/07/97 10/07/97 - 01/06/98 04/01/97 0401/97 36D1' 01/07/97 01/06/98 07/01/97 07/01/97 - 10/07/97 10/07/97 04/01/97 04/01/97 2E1 01/07/97 10/07/97 10/07/97 - 01/06/98 07/01/97 07/01/97 04/01/97 0401/97 3S1 01/07/97 01/06/98 4E1 01/07/97 04/01/97 04/01/97 - 07/01/97 07/01/97 - 10/07/97 10/07/97 SS1 01/07/97 04/01/97 0401/97 - 07/01/97
' V1/97 - 10/07/97 10/07/97 - 01/06/98 01/06/98 10/07/97 10/07/97 0401/97 04/01/97 - 07/01/97 s'O 97 SHI 01/07/97 01/06/98 10/07/97 10/07/97 07/01/97
- 0. OuG7 0401/97 0401/97 6C1 01/07/97 10/07/97 10/07/97 - 01/06/98 04/01/97 04/01/97 - 07/01/97 07/01/97 7S1 01/07/97 01/06/98 7E1 01/07/97 - 04/01/97 0401/97 - 07/01/97 07/01/97 - 10/07/97 10/07/97 10/07/97 10/07/97. 01/06/98 9C1 01/07/97 - 0401/97 04/01/97. - 07/01/97 07/01/97 01/06/98 0401/97 0401/97 - 07/01/97 07/01/97 - 10/07/97 10/07/97 10S3 01/07/97 10/07/97 10/07/97 - 01/06/98 07/01/97 07/01/97 04/01/97 04/01/97 10E1 01/07/97 01/06/98 07/01/97 07/01/97 - 10/07/97 10/07/97 04/01/97 0401/97 10F3 01/07/97 10/07/97 10/07/97 - 01/06/98 07/01/97 07/01/97 0401/97 04/01/97 11S1 01/07/97 10/07/97 10/07/97 - 01/06/98 07/01/97 07/01/97 13S2 01/07/97 - 0401/97 0401/97 10/07/97 10/07/97 - 01/06/98 13C1 01/07/97 - 0401/97 0401/97 - 07/01/97 07/01/97 01/06/98 10/07/97 10/07/97 07/01/97 07/01/97 13E1 01/07/97 - 04/01/97 0401/97 01/06/98 0401/97 0401/97 - 07/01/97 07/01/97 - 10/07/97 10/07/97 14S1 01/07/97 01/06/98 10/07/97 10/07/97 07/01/97 07/01/97 15D1 01/07/97 - 0401/97 0401/97 01/06/98 10/07/97 10/07/97 0401/97 0401/97 - 07/01/97 07/01/97 16F1 01/07/97 01/06/98 10/07/97 10/07/97 07/01/97 07/01/97 04/01/97 04/01/97 1781 01/07/97 01/06/98 10/07/97 10/07/97 18S2 01/07/97 - 04/01/97 04/01/97 - 07/01/97 07/01/97 01/06/98 10/07/97 10/07/97 07/01/97 07/01/97 0401/97 04/01/97 1901 01/07/97 01/06/98 10/07/97 10/07/97 07/01/97 07/01/97 04/01/97 0401/97 2001 01/07/97 01/06/98 20F1 01/07/97 - 0401/97 04/01/97 - 07/01/97 07/01/97 - 10/07/97 10/07/97 10/07/97 10/07/97 01/06/98 07/01/97 07/01/97 0401/97 04/01/97 21 S2 01/07/97 01/06/98 07/01/97 07/01/97 10/07/97 10/07/97 23S2 01/07/97 - 04/01/07 0401/97 01/06/98 10/07/97 10/07/97 07/01/97 07/01/97 24Di 01/07/97 - 04/01/97 04/01/97 01/06/98 10/07/97 10/07/97 0401/97 0401/97 - 07/01/97 07/01/97 25S2 01/07/97 01/06/98 07/01/97 07/01/97 10/07/97 10/07/97 0401/97 0401/97 25D1 01/07/97 01/06/98 10/07/97 10/07/97 04/01/97 04/01/97 - 07/01/97 07/01/97 26S3-01/07/97 07/01/97 07/01/97 - 10/07/97 10/07/97 01/06/98 2802 01/07/97 - 04/01/97 04/01/97 10/07/97 10/07/97 01/06/98 07/01/97 07/01/97 29S1 01/07/97 0401/97 0401/97 10/07/97
'0/07/97 01/06/98 0401/97 0401/97 - 07/01/97 07/01/97 19E1 01/07/97 01/06/98 31S1 01/07/97. 0401/07 04/01/97 - 07/01/97 07/01/97 - 10/07/97 10/07/97 07/01/97 07/01/97 - 10/07/97
%'7/97 01/06/98 04/01/97 0401/97 31D1 01/07/97 0401/97 04/01/97 - 07/01/97 07/01/97 - 10/07/97 10/0 "97 01/06/98 31D2 01/07/97 10/07/97 10/07/97 - 01/06/98 07/01/97 07/01/97 04/01/97 0401/97 34S2 01/07/97 07/01/97 07/01/97 - 10/07/97 10/07/97 01/06/98 34E1 01/07/97. 04/01/97 04/01/97 I
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t APPENDIX D DATA TABLES AND FIGURES COMPARISON LABORATORY
l APPENDIX D:
DATA TAdLES AND FIGURES - COMPARISON LABORATORY
. TABLES-Table D-l.1 Concentratic Gross Beta insoluble in Drinking Water Samples Collected
.in the Vicinit) uimerick Generating Station,1997.
1 Table D-l.2 Concentration of Gross Beta Soluble in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station,1997.
Table D-l.3 -
Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station,1997.
= Table D-II.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the -
Vicinity of Limerick Generating Station,1997.
l Table D-II.2 Concentrations of Gamma Emitters in Air Particulate Samples Collected in
-l the Vicinity of Limerick Generating Station,1997.~
Table D-Ill.1 Concentrations of 1131 by Chemical Separation and Gamma Emitters in Milk
.j Samples Collected in the Vicinity of Limerick Generating Station,1997.
Table D-IV.1;
. Summary of Collected Dates for Samples Collected in the Vicinity of Limerick Generating Station,1997.
FIGURES Figure D-1 Comp 9rison of Monthly Insoluble Gross Beta Concentrations in Drinking Water Samples Split Between GPU and TBE,1997.
L
- Figure D-2 Comparison of Monthly Soluble Gross Beta Concentrations in Drinking Water Samples Split Between GPU and TBE,1997.
p Figure D-3 Comparison of Weekly Gross Beta Concentrations in Air Particulate Samples Collected from LGS Collocated Locations 11S1 and 11S2,1997.
l D-i U
L
{
l i
1 The following section contains data and figures illustrating the analyses performed by the quality control laboratory.. Duplicate samples were obtained from severallocations and 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:
f 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 rsspective laboratory's analytical procedures. TBE counts the samples for 50 minutes, GPU counts for 100 minutes.
The gross beta results for air particulate samples collectLJ at the cellocated stations 11S1 and 11S2 j
compared very well (Figure D-3, Appendix D). No significant differences were noted. Both laboratories l
use Cs-137 as a calibration source.
l l
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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, 1997 RESULTS IN UNITS OF PCl/ LITER +/- 2 SIGMA l
Collection Period 16C2 JAN 0.1 10.4 FEB 0.3 t0.5 MAR 0.2 to.4 APR 0.4 *0.6 MAY 0.7 *0.5 JUN 0.4 10.7 JUL 0.4 i0.4 AUG 2.2 10.7 SEP 0.6 10.9 OCT
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DEC 0.1 11.0 l
MEAN 0.6 i1.3
]
TABLE D-l.2 CONCENTRATIONS OF GROSS BETA SOLUBLE IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION,1997 i
RESULTS IN UNITS OF PCl/ LITER +/- SIGMA Collection Period 16C2 JAN 1.8 11.0 FEB 1.8 10.9 MAR 2.2 10.8 l
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CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN TH TABLE VICINITY OF LIMERICK GENERATING STATION,1997 RESULTS IN UNITS OF E 3 PCl/CU +/- 2 SIGMA WEEK NO 11S2 1
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TABLE D-IV.1
SUMMARY
OF COLLECTION DATES FOR SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION,1997 DRINKING WATER (Gross Beta & Gamma Spectroscopy)
Collection 16C2 i
Penod JAN 12/30/96 02/03/97 FEB 02/03/97 03/03/97 MAR 03/03/97 03/31/97
- APR, 03/31/97 - 04'28/97 MAY 04"28/97 06/02/97 JUN 06/02/97 - 06/30/97 JUL 06/30/97 - 07C8/97 AUG 07/28/97 - 09 03/97 SEP 09/03/97 - 09/29/97 OCT 09/29/97 - 11/03/97 NOV 11/03/97 12/01/97 DEC 12/01/97 - 12/20/97 AIR PARTICULATE (Gamma Spectroscopy)
Collection Penod 11S1 JAN MAR 12/30/96 03/31/97 APR-JUN 03/31/97 06/30/97 JUL StiP 06/30/97 09/29/97
. OCT-DEC 09/29/97 12/29/97 AIR PARTICULATE (Gross Beta)
Collection Collecten Penod 11S1 Penod 11S1 1
12/30/96 01 S 6/97 27 06/30/97 - 07/07/97 2
01/06/97 - 01/13S 7 28 07S7/97 - 07/1497 3
01/13/97 01/20/97 29 07/1497 - 07/21/97 o's21S7 - 07/28/97 4
01/20/97 01/27/97 30
/
5 01/27/97 02/03/97 31 07/28/97 - 08/0497 6
02/03/97 02/10S7 32 08/04M7 08/11/97 7
02/10S7 02/1 &97 33 08/11/97 08/18S7 8
02/18/97 02/2497 34 08/18/97 - 08/25/97 9
02/2497 - 03/03S7 35 08/25/97 09/02G7
]
10 03/03S7 03/10/97 36 09/02/97 09/08/97 11 03/10/97 03/17/97 37 09/08/97 - 09/15/97 12 03/17/97 - 03/2497 38 09/15/97 09/22/97 13 03/2497 - 03/31/97 39 09/22/97 09/29/97 14 03/31/97 04/07/97 40 09/29/97 10/06/97
.15 04'07/97 04/14S7 41 10/06/97 10/13/97 16 04/1497 0471/97 42 10/13/97 10/20/97 17 04'21/97 - 04/28/97 43 10/20/97 10/27/97 j
18 04/28/97 05/05/97 44 10/27/97 - 11/03S 7 j
19 05/05/97 05/12/97 45 11/03/97 - 11/10/97 20 05/12/97 05/19S7 46 11/10/97 11/17/97 l
21 05/19/97 05/27/97 47 11/17/97 - 11/2497 22 05/27S7 06/02/97 48 11/24/97 - 12/02/97 l
23 06S2/97 06/09S7 49 12/02/97 - 12/08/97 24 06/09/97 - 06/16/97 50 12/08/97 12/16/97 l
25 06/16/97 06/23/97 51 12/16/97 - 12/22/97 26 06/23S7 - 06/30/97 52 12/22/97 - 12/29/97 D-7 1
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1 APPENDIX E SYNOPSIS OF ANALYTICAL PROCEDURES i
. i i
1 4
i l c
- APPENDIX E:l 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..
i l-i l
i i
f-E-1
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 samplos 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 residue is transferred and dried on another planchet.
l The planchets are counted for 100 minutes in a low-background gas flow proportional 1
counter. Calculation of activity includes a self-absorption correction for counter l
e'ficiency based on the weight of residue on each planchet.
Calculation of Sample Activity and 2 Siama Uncertaintv:
C-B 2.22x EoxTFxVxT 2x4C+ B 2.22x EoxTFxVxT 4.66x5 LLD = 2.22xEoxTFxVxT 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
=
C Sample Counts
=
Blank Counts B
=
Eo Efficiency of the counter i
=
Transmission Factor TF
=
T Acquisition time in minutes
=
V
=
Volume or weight of aliquot analyzed.
E-2 i
[
DETERMINATION OF GROSS BETA ACTIVITY IN WATER SAMPLES (TOTAL SUSPENDED AND DISSOLVED FRACTIONS)
Teledyne BrownJna:ner.rina 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 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:
Result i*0
\\li[
- i N
N p
(pri:1)
(2.22)(s)(E) ~ (2.22)(v)(E)
Net Activity Counting Error where:
N total counts from sample (counts)
=
counting time for sample (min) 1
=
G background rate of counter (cpm)
=
counting time for background (min) to
=
dpm/pCi 2.22
=
volume in liters
~v
=
E efficiency of the counter
=
multiple of counting error 2
=
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 GPUN Environmental Radioactivity Laboratory 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 Ragion 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 Uncerts : g C-B 2.22x EoxVxDF c
p 2x - + Ts Ta y,,, 2.22x EoxVxDF S
3.29x\\ T, ' Ts LLD = 2.22xEoxVxDF Where:
Total count time of sample in minutes T.
=
Total count time of background in minutes Te
=
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 G
=
Tritium detection efficiency of counter, calculated as shown below Eo
=
Volume of aliquot V
=
E-4 l
=
Decay factor, calculated as shown below In MT DF=eun DT time difference in years from collection stop date to counting date
=
of sample The efficiency is calculated as follows:
Eo = An!'sxDFs Where:
S Average count rate for the " efficiency determination" standard
=
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:
=
. w wr, DFs e un DTs time difference (in years) between calibration date and counting
=
date E-5 1
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 2.22x EoxTFxVxT 2xJC+ B 2.22x Eo TFxVxT x
4.66x[li 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
=
E-6 1
DETERMINATION OF GROSS BETA ACTIVITY IN AIR PARTICULATE SAMPLES Teledyne Brown Enaineerina This describes the process used to measure the overall beta activity of air rarticulate 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 Result i*0 if ~ 5 (pCi / m')
2.22(v)(E)(.02832) ~ 2.22(v)(E)(.02832)
Net Activity Counting Error where:
N total counts from sample (counts)
=
' counting time for sample (min) t,
=
background rate of counter (cpm)
B
=
counting time for background (min) to
=
2.22 dpm/pCi
=
volume of sample ar,alyzed in cubic feet calculated from the v
=
elapsed time meter E
efficiency of the counter
=
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.
E-7 i
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 Sioma Uncertainty:
The same calculations are used as in DETERMINATION OF GAMMA EMITTING RADIOISOTOPES below.
1 E-8
DETERMINATION OF l-131 IN MILK SAMPLES Teledyne 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 iodide. The precipitate is weighed for chemical yield and is mounted on a nylon I
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 Sample Activity and 2 Siama Error:
N N
p
'i ~ S 5
5 Result (pCi. l}
(2.22)(s)(E)(y)(exp'*)
(2.22)(s)(E)(y)(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) tn
=
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.G93/8.05)
=
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 1-131, correc6d for self absorption E
=
effects by the formula:
= E,s ((exp**"')
E.
exps ani,,
where:
efficiency of the counter determined from an 1-131 standard mount E.
=
mass of Pdl2 on the sample mount (mg)
M
=
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 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 ca!endar 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.
Calculation of Sample Activity and 2 Siama Uncertaintv:
P A Ea 2.22xqxerhx Et x e"' x (1 - e"*)
A-where:
the computed specific activity A
=
P peak area
=
dpm/ picocurie 2,22
=
sample quantity q
=
c
=
detection efficiency b
=
gamma-ray abundance Et elapsed live time
=
2 decay constant
=
Ts acquisition start time
=
En elapsed real time
=
E - 10
$p> 2
<g$8zrggo <sy,,z 6A=A(P> < b s < c > <100s (6 Decay) where:
=-
uncertainty in the activity
( A Ea ADecay = A Turx, _
,.u, - A(Ts + En)- 1, AP
=
uncertainty in the peak area P Ah
~ uncertainty in the S-ray abundance
.=
Ac
=
uncertainty in the efficiency systematic Uncertainty estimate ( in %)
sys
=
AT% =
uncertainty in the half-life i
E - 11
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 Sionificant Activity and 2 Siama Error Calculation for l
the ND6620 and ND6700 Systems:
Activity AREA
- DECA Y.
pCi
" UVETIME(sec.)* ABN
- EFF
- 0.037 * (smit mass) unit mass, Statistically Significant Activity 42
- BKGND + AREA 200 *
- Activity
-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 i
time)
~ LIVE TIME Elapsed Live Time ( from Header information)
=
i E - 12 u
ABN Nuclide Abundance (from Nuclide Line Activity Report)
=
EFF
=
Detector Efficiency (from Nuclide Line Activity Report)
Conversion Factor (dps to picocurie) 0.037
=
Sample weight or volume (from Header Information) unit mass
=
Gamma Spectroscopy Statistically Non Sianificant Activity and 2 Siama Error Calculation for the ND6620 and ND6700 Systems:
Activity AREA
- DECAY
~
C Pi Ul'E11ME(sec.)* ABN
- EFF
- 0.037 * (amit mass)
(unit mass, Statistically Non Significant Activity 42
- BKGND + NET 200 *
^ 'O NET 2 Sigma Counting Error where:
NET Net Peak Area (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.l)
Efficiency
- Abundance (from Minimum Detectable Activity
=
Report) 0.037 Conversion Factor (dps to picocurie)
=
unit mass Sample weight or volume (from Header Information)
=
E - 13
Gamma Spectroscoov Minimum Detectable Activity Calculation for the ND6620 and ND6700 Systems:
MDA 2.83 4BKGN
- DECAY PCi
" LH'E11ME(sec.) * (EFF
- B. I.)
- 0.037 * (tmit mass)
(unit mass, 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 Infctmation) unit mass
=
E - 14 i
ENVIRONMENTAL DOSIMETRY-I GPUN Environmental Radioactivity Laboratorv j
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 l
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 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.
Net exposures are then converted to mR per standard month. This method of calculating transit exposure conforrm 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 l.
E - 15
o 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.
i!'
l l
E - 16
l
\\
APPENDlX F QUALITY CONTROL EPA INTER-LABORATORY COMPARISON PROGRAM
TABLE F-1 1997 USEPA Cross Cheu Program Results Teledyne Collection EPA Control GPUN-ERL Br Date Media Nuclide Limits Results su ts (A)
(B)
(B) 01/17/97 Water Sr 89 12.0 i 8.7 19.67 2
2.52 10.00 i
1.00 Sr-90 25.0
- 8.7 22.33 2.52 25.00 1.00 s
01/31/97 Water Alpha 5.2 i 8.7 5.57 1
1.56 8.10 1
0.89 Beta 14.7 i 8.7 18.33 t
3.21 15.00 1.00 02/07/97 Water 1-131 86.0 1 15.6 92.33 i
5.51 106.00 1
4.36 i
(C)
(E) 86.0 15.6 91.67 2.08 i
(D) 03/07/97 Water H-3 7900.0 i 1370.6 7933.33 57.74 7366.67
- 378.59 i
1 04/15/97 Water Alpha 48.0 i. 20.8 30.00 1.00 54.67 t
1.53 Beta 102.1 t 26.5 83.00 1.73 103.33 i
5.77 Co-60 21.0 i 8.7 24.00 i
1.00 22.67 i
0.58 i
Sr 89 24.0
- 8.7 26.00 i
1.00 23.30 i
1.00 I
Sr-90 13.0
- 8.7 10.00 0.00 12.67 i
1.15 I
Cs-134 31.0 1 8.7 31.00 i
1.00 28.67 i
0.58 j
Cs-137 22.0
- 8.7 24.67 0.58 24.67 i
1.53 06/06/97 Water Co-60 18.0 i 8.7 18.67 i
0.58 19.00 1
0.00 Zn-65 100.0 i 17.3 106.67 i
5.77 99.33 i
1.15 Ba-133 25.0 i 8.7 25.00 1
0.00 22.33 i
2.52 Cs-134 22.0 1 8.7 20.33 i
1.53 18.67 1
1.15 Cs-137 49.0 i 8.7 52.33 2.08 48.67 i
0.58 07/11/97 Water Sr-89 44.0 i 8.7 39.67 0.58 38.33 i
1.53 Sr-90 16.0 i 8.7 16.67 t
1.53 25.00 t
0.00 (F) 07/18/97 Water Alpha 3.1 i
8.7 4.47 1.27 2.93 0.25 Beta 15.1 t 8.7 15.00 1
2.00 14.00 i
1.00
. 08/08/97 Water H-3 11010 1 1910.2 11333.33 i 577.35 12000.00 1 0.00 09/19/97 Water 1-131 10.0 i 10.4 9.00 1
1.00 11.00 1
0.00 (C) 10.0 i 10.4 10.87 2.20 (D) i F-2 A.
TABLE F-1 1997 USEPA Cross Check Program Results Teledyne Collection EPA Control GPUN-ERL B
n ng.
Date Media Nuclide Limits Results (A)
(B)
(B) 10/21/97 Water Alpha 49.9 i 21.7 49.33 0.58 45.67 1.15 Beta 143.4 37.3 140.00 2
0.00 136.67 i
5.77 Co-60 10.0 i 8.7 12.00 i
2.65 10.67 1
0.58 Sr-89 36.0 t 8.7 42.33 i
2.52 36.00 i
1.00 Sr-90 22.v i 8.7 24.33 1
2.31 21.67 i
2.08 Cs-134 41.0 i 8.7 40.67 1
0.58 41.33 1
0.58 Cs-137 34.0
- 8.7 36.33 1
0.58 36.00 t
1.00 10/31/97 Water Alpha 14.7 i 8.7 14.33 i
3.21 19.67 i
1.53 Beta 48.9 i 8.7 47.67 i
7.23 50.67 i
3.51 11/7/97 Water Co-60 27.0 i 8.7 30.00 i
1.00 25.00 i
1.00 Zn-65 75.0 13.9 80.33 1
6.66 71.00 i
3.61 Ba-133 99.0 1 17.3 99.67 i
0.58 78.67 1
0.58 (G)
Cs-134 10.0 t 8.7 10.67 1.53 10.67 0.58 Cs-137 74.0 1 8.7 78.33 1
3.21 76.00 i
1.00 (A)
EPA Control Limits - Known Value i 3 sigma (n = 3). Units are pCi/L.
(B)
Results Average of three determinations i one standard deviation. Units are pCi/L (C)
Low Level 1-131 Method.
(D)
Gamma Srwoscopy of Water Method.
(E)
Erroneously high reading of the stable lodine content by ion specific electrode occun ed, causing ar. erroneously low chemical yield. P the electrode reading is ignored. the average 1131 result becomes go pCi/L. in good agreement with the given value.
An erroneous electrode reading can be caused by certain chemical species in the sample, such as sulfide. TBE will
- investigate suspiciously high electrode readings by performing a gravinetric yield on the sample without the addition of iodde camer or the I-131 content of active samples can also be verified by performing a gamma spectral analysis.
(F)
Error apparently caused by insufficient training. A summer employee pe' formed the strontium separation chemistry on 7/22/97. Initial results for the three samples did not agree well, so all were re-milked by a senicr analyst This was insufficient to correct the problem In-house QC samples showed satisfactory results at this time. There will be additional quahfication of analysts according to performance on in-house blanks and spikes.
(G)
An investigation is being conducted. results will be available shortly.
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1 TABLE F-4 l
1997 ANALYTICS Environmental Cross Check Program Results l eledyne Brown Engineering Collection ANALYTICS Results Ratio Date Media Nuclide Value (a)
(b) 3/20/97 Milk l-131 20
- 1 18 i 1
0.90 Ce-141 232i 12 L.T.1.
See Cr-51 387i 19 381 i 38 Footnote Cs-134 143i 7
132 13 0.98 Cs-137 114*
6 128 i 13 0.92 Co-58 79 i 4
89 i 9
1.12 Mn-54 176 i 9
195 i 20 1.13 Fs-59 144i 7
161 i 16 1.11 Zn-65 165*
8 171 i 17 1.12 Co-60 17?
- 9 179 i 18 1.04 1.02 t
3/20/97 Milk Sr 89 25 i 1
13 i 3
0.52 (c)
Sr 90 19 i 1
16 i 1
0.84 6/19/97 Filter Ce-141 132i 7
143 8
1.08 Cr-51 1981 10 229 i 17 1.16 Cs-134 81 1 4
74 i 4
0.91 Cs-137 115i 6
143 i 8
1.24 Co-58 77 1 4
89 i 5
1.16 Mn-54 84
- 4 102
- 6 1.21 Fe-59 75 i 4
98 6
1.31 Zn-65 139 i 7
188 2 11 1.35 Co-60 104i 5
113 i 7
1.09 6/19/97 Cartridge 1-131 88 i 4
106 i 6
1.20 6/19/97 Filter Sr-90 CfL i 5
88 i 5
0.92 6/19/97 Filter Alpha 93 1 5
103
- 6 1.11 Beta 193i 10 210 1 6
1.09 9/18/97 Milk l-131 87 i 4
97 1 10 1.11 Ce-141 77 i 4
83 i 8
1.08 Cr 51 304i 15 323 i 40 1.06 Cs-134 102 2 5
98 1 10 0.96 Cs-137 107i 5
117 i 12 1.09 Co-58 60 i 3
64 2 6
1.07 Mn-54 88 1 4
99 2 10 1.13 l
Fe-59 119i 6
132 1 13 1.11 Zn-65 196i 10 218 i 22 1.11 Co-60 1971 10 209 i 21 1.06 9/18/97 Milk Sr-89 15 t 1
14 i
1 0.93 Sr-90 14 i 1
18 1 1
1.29 F-9
1
'~
Footnotes:
(a)
Teledyne Results - counting error is two standard deviations. Units are pCl/ liter for water and milk. For gamma results, if two standard deviations are less than 10%, then a 10% error is reported. Units are total pCi for air particulate filters and 1-131 cartridges.
(b)
Ratio of Teledyne Brown Engineering to Analytics results.
.(c)
Caused by incorrect rinsing of the strontium extraction column. Additional training was conducted on
~ 9/5/97 and was documented in the analyst's training file. Subsequent tests on two milk samples spiked j
1 with Sr-89 produced good results.
- Note: Ce-141 was identified by gamma spectrometry system for the 3/20/97 milk sample, but was not reported to Analytics.
1
-+
II
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)
'l I'
l F-10
l l
1 i
1
. APPENDIX G LGS SURVEY
APPENDlX G:
LGS SURVEYS -
. 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 Septenber 1997 growing season. The j
distance and direction of all locations were positioned from the barn to the LGS ' ents j
v using Global Positioning System (GPS) technology. The results of this survey are summarized in Table G-1.
1 i
There were no changes required to the LGS REMP.as a result of this survey.
]
]
4 1
i G-1 1
0 Table G-1 Location of Nearest Residence, Garden and Milk Farm within a Five Mile Radius of Limerick Generating Station,1997 (Distance in Miles)
Sector Residence Garden (1)
Milk Farm 1N 0.6 1.6 4.7 2 NNE 0.5 0.5 3NE 0.8 1.5 4 ENE 0.6 2.5 j
5E 0.6 1.6 1
6 ESE 0.5 1.1 1.1(')
7 SE 1.0 1.3 8 SSE 1.0 1.2 4.7 9S 0.8 1.2 2.3 10 SSW 1.0 1.1 1.8 l
11 SW 0.6 0.6 3.0 j
12 WSW 0.8 1.4 2.8 5
13 W 0.6 2.2 2.7 l
14 WNW 0.7 0.8 15 NW 0.6 1.6 L
16 NNW 0.8 1.2 (1) Garoon greater than.00 square feet I
r (2) Goat Milk G-2 l