ML20116P223

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Regional Radiological Environ Monitoring Program Rept 1, 841222-31
ML20116P223
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 12/31/1984
From:
RADIATION MANAGEMENT CORP. (RMC), TELEDYNE ISOTOPES
To:
Shared Package
ML20116P201 List:
References
NUDOCS 8505070556
Download: ML20116P223 (72)


Text

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a DOCKET NO.: 50-352 50-353 LIMERICK GENERATING STATION Units 1 and 2 Regional Radiological Environmental Monitoring Program Report ft1 22 December through 31 December 1984 l

Prepared for PHILADELPHIA ELECTRIC COMPANY l 2301 Market Street Philadelphia, Pennsylvania 19101 By TELEDYNE ISOTOPES 50 Van Been Asenue Wmtwoort NJ 07675 Ard RAD lATION MANAGEMENT CORPORATION Fr:cks i ock Road. R D .

Po tstown PA 19464 May 1985 8505070556 850424 PDR ADOCK 05000352 R PDR

DOCKET No.: 50-352 50-353 LIMERICK GENERATING STATION Units 1 and 2 Regional Rhdiological Environmental Monitoring Program Report #1 22 December through 31 Dect mber 1984 Prepared for Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101 By TELEDYNE ISOTOPES 50 Van Buren Avenue Westwood, NJ 07675 And l

Radiation Management Corporation Fricks Lock Road, R.D. 1 Pottstown, PA 19464 May 1985 hme e--m-m ----- -- -

TABLE OF CONTENTE Page I. Summary and Conclusions 1

!I. Introduction 3 A. Objectives 4 D. Implementation 4 III. Program Description 5 A. Sample Collection 5 B. Data Interpretation 7 C. Program Exceptions 8 D. Program Changes 8 IV. Results and Discussion 9 A. Aquatic Environment 9

1. Surface Water 9
2. Drinking Water 9
3. Fish 10
4. Sediment 10 B. Atmo' spheric Environment to
1. Airborne 10
a. Air Particulates 10
b. Airborne Iodine 11
2. Terrestrial 11 l
a. Milk 11 l

l b. Well Water 11 l

c. Food Products 11
d. Game 12 C. Ambient Gamma Radiation 12 V. References 13

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Appendix A - Radiological Environmental Monitoring Report Summary Appendix B - Sample Designation and Locations Appendix C - Data Tables Appendix D - Synopsis of Analytical Procedures Appendix E - Quality Control Appendix r - LGS Surveys

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SUMMARY

AND CONCLUSIONS

I. Summary and Conclusions This report on the Radiological Environmental Monitoring Program conducted at the Limerick Generating Station for Philadelphia Electric Company covers the period December 22, 1984 through December 31, 1984.

During that time period, 152 analyses were performed on 108 samples.

The ten day period that this report covers represents the portion of 1984 after which Limerick Generating Station achieved initial criticality.

Cons eq u en t l y, only data frcm samples collected during this time period Ire included in the report.

Surface and drinking (potable) water samples were analyzed for concentrations of gross beta (soluble and insoluble fractions), trititm, and gamma emitting nuclides. Concentrations detected were consistent with those observed in other years.

High sensitivity I-131 analyses were performed on weekly air samples.

All results were less than the minimium detectable level.

Air particulate samples were analyzed for concentrations of gross beta and gamma emitting nuclides. Concentrations detected were consistent with those observed in other years.

Environmental gamma radiation measurements were made monthly using thermoluminescent dosimeters. Levels detected were consistent with those observed in other years.

In assessing all the data gathered for this report and comparing these results with preoperational data, it was evident that the operation of the Limerick Generating Station resulted in no significant radiological impact on the environment.

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9 INTRODUCTION

LIMERICK GENERATING STATION Radiological Environmental Monitoring Program II. Introduction The Limerick Generating Station (LGS), consisting of two 1055 MWe boiling water reactors owned and operated by Philadelphia Electric Company (pECo), is located adjacent to the Schuylkill River in Montgomery County, pennsylvania. Unit No. I went critical on 22 December 1984 and Unit No. 2 is under construction. 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 i bank elevation rises approximately 50 feet MSL to the western site i boundary.

A Radiological Environmental Monitoring program (REMP) for LGS uns initiated in 1971. Review of the 1971 through 1977 REMP data resulted in the modification of the program to comply with changes in the Environmental Report Operating License Stage (EROL)(13 and the current revision of the Branch Technical Position Paper.(2) The preoperational period for most media covers the periods 1 January 1982 through 21 December 1984. The results of this period will be summarized in a separate report. This operational report covers those analyses performed by Teledyne Isotopes (TI) on samples collected during the period 22 December 1984 through 31 December 1984.

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A. Objectives The objectives of the Radiological Environmental Monitoring Program are:

1. To provide data on measurable levels of radiation and _

radioactive materials in the site environs.

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2. To 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 i Implementation of the stated objectives is accomplished by identifying significant exposure pathways, establishing baseline radiological data of media within those pathways, and continuously monitoring those media before and during plant operation to assess plant effects (if any) on man and the environment. g In order to achieve the stated objectives, the current program f includes the following analyses on samples collected: 1

1. Concentrations of tritium in surfaca water, drinking (potable) unter, and well unter.

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2. Concentrations of beta emitters in surface unter, drinking (potable) water, and air particulates.
3. Concentrations of gamma emitters in surface, drinking (potable), and well water, air particulates, milk, vegetation, game, fish, and sediment.
4. Concentrations of I-131 in air and milk.
5. Ambient gamma radiation levels at various site environs.

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PROGRAM DESCRIPTION t

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III. program Description A. Sample Collection This section describes the collection methods used to obtain environmental samples for the LGS REMP in 1984, including those media that were not sampled during the time period covered by this report.

Aquatic Environment The aquatic environment was examined by analyzing samples of surface water, drinking unter, fish, and sediment. Two gallon water samples were collected monthly from continuous samplers located at five surface unter locations (10F2, 15F5, 16B2, 2451, and 24S2) and four drinking water locations (15F4, 15F7, 16C2, and 28F3). One additional drinking unter location (13H2) was sampled monthly by a hand composite. Control locations were 10F2, 2451, 2452, and 28F3. All containers used were new unused plastic bottles, which were rinsed at least twice with source water orior to collection. Fish samples comprising the flesh of two groups, catfish / bullhead (bottom feeder) and sunfish (predator), were collected semi-annually at three locations:

16C5 and 20S1 (indicators) and 29C1 (control). Sediment samples composed of recently deposited substrate were collected at three locations semi-annually: 16B2 and 16C4, (indicators) and 33A2 (control).

Atmospheric Environment The atmospheric environment was examined by analyzing samples of air particulates, airborne iodine, milk, well water, food products and game. Air particulate and airborne iodine samples were collected weekly at seventeen locations (2B1, 6C1, 9C1, 10S3, 11S1, 13C1, 13H4, 14S1, 15D1, 17B1, 20D1, 22G1, 26B1, 29B1, 31DI, 34S2, and 35B1). Of the airborne iodine samples at these seventeen locations, eight (10S3, 1151, 13C1, 13H4, 14S1, 22G1, 31D1, and 35B1) were analyzed for I-131. The remaining nine namples were collected and retained for analysis if necessary. Control locations were 13H4 and 22G1. Air particulate and airborne iodine samples were obtained using a vacuum sampler, glass fiber and charcoal filters, respectively. The filters were replaced weekly and sent to the laboratory for analysis. The vacuum samplers were run continuously at approximately I cubic foot per minute.

Milk samples were collected bi-weekly at four locations (5C1, 10B1, 22F1, and 25B1) and monthly at eight locations (36E1, 9E1, 9G1, 11D1, 11E1, 17C2, 18C1, and 21B1) during April through November, and monthly at all locations during December through March. Locations 9G1 and 22F1 were controls. 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. .

Well water samples were- collected semi-annually from two locations 1151 (indicator) and 18A1 (control) in new unused two gallon plastic bottles. Food product samples composed of broad leafy vegetation and root. crops were collected monthly from one location (1151) during the growing season (May through September). A game sample was collected annually from one location (2655) by hunting.

Ambient Gamma Radiation Direct radiation measurements were made using.thermoluminescent dosimeters (TLD) consisting of calcium sulfate (CaSO4) doped with Thalium (Tm). The TLD locations were placed on and around the LGS site using a "three ring concept" consisting of:

A site boundary ring consisting of sixteen locations (3651, 351, 551, 751, 1053, 1151, 14S1, 16S2, 18S1, 2151, 2352, 2551, 2653, 2951, 3251 and 3452) near and within the site perimeter representing fencepost doses ( i . e . ,' at locations.

Where- the doses will be greater than maximum annual off-site doses).from LGS releases; A middle ring consisting of twenty seven locations (2B1, 2E1, 4E1, 6C1, 7E1, 9C1, 10E1, 10F3. 13C1, 13E1, 15D1, 16F1, 1781, 19D1, 20DI, 20F1, 24D1, 25DI, 26B1, 28D2, 2981, 29E1, 31DI, 31D2, 34E1, 35B1 and 35F1) extending to approximately 5 miles from the site designed to measure possible exposures to close-in population; And an outer ring consisting of five locations (5H1, 13H3, 18G1, 22G1 and 32G1) extending from approximately 12 to 30 miles from the site and considered to be unaffected by LGS releases.

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 16 22-1/2-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.

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One TLD set - comprising four thermoluminescent dosimeters J. s. '

sealed in plastic to maintain integrity - was placed at location in a PVC conduit located approximately three feet each CI

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above ground level. The TLD set was exchanged monthly and $

sent to the laboratory for analysis. I4 B. Data Interpretation  ;.

The radioanalytical and direct radiation data collected prior to i[q c LGS becoming operational will be used as a baseline with which c.

operational data may be compared. For the purpose of this ( ~%.,

report, LGS was considered operational at initial criticality. ,1 Several factors are important in the interpretation of the data.  ? , J - J--

These factors are discussed here to avoid undue repetition in the {,'t discussion of the results. .c, ll%

The minimum detectable level (MDL) was defined as the two sigma L'bh*

counting statistic. It represents the range of values into which I','

95% of repeated counts of the same aliquot would fall. For all O,'"

analyses (gross beta, I-131. H-3 and gamma) an activity that was .,,

greater than or equal to the MDL was reported as " activity }, ;s >

plus/minus the MDL value". For nongamma analyses (gross beta, I-  ;.

131 and H-3) when an activity was less than the MDL, the result 0.J:74 was reported as the "< the MDL value". When an activity from a "" ~

gamma isotopic analysis was less than the MDL value it was k~

reported as "< MDL" for the specific nuclide searched for unless J. tr a positive occurrence had been found in other. samples. In those W' .

f cases the actual MDL values were listed. ' "l .

O,p 3 The lower limit of detection (LLD) was defined as 'the smallest concentration of radioactive material in a sample that would

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yield a net count (above background) that would be detected with "[O ,

only a 5% probability of falsely concluding that a blank mf-observation represents a "real" signal. The LLD was intended as system (including

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a before the fact estimate of a 4; .' 1 instrumentation, procedure and sample type) and not as an after ,% d . '

the fact criteria for the presence of activity. All analyses f'

were designed to achieve the required LGS detection capabilities i .S , ,' l for environmental sample analysis. For a more detailed y , f.

description of the results calculation, see Appendix D. t 7. r ,

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Results for each type of sample were g rouped according to the hf-]-[, '^

analyses performed. Means and standard deviations of these .g-results were calculated. These standar.d deviations represent the 73 (% ,q.

variability of measured results for different samples rather than 1  ;.

single analysis uncertainty. For these calculations, all results J .NPi below the MDL were considered to be at the MDL. As a result, the [3 means were biased high, and the standard deviations were n ' t,' i generally biased lou, j ac P- .

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C. Program Exceptions Surface water and drinking water samples were composited for tritium analysis during October and Hovember for the preoperational period and December's samples were analyzed for tritium for the operational period. This report spans only a ten ,

day period, resulting in some additional exceptions to the program. The LGS annual surveys (nearest farm, nearest g residence, and nearest garden), included in the environmental ]

program, were not required for the time period of this report.

In addition to this, well water, milk, sediment, game, and food product samples were not scheduled for collection during the reporting period. Consequently, data from these media were not available for this report. Due to a pump malfunction, the surface water sample collected from location 10F2 was a grab h, sample.

D. Program Changes Hone 4

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RESULTS AND DISCUSSION i

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IV. Results and Discussion __

ul A. Aquatic Environment -

1. Surface Water Samples were taken from five locations on a monthly schedule.

Samples were collected from a continuous sampler at all five l locations (10F2, 15F5, 16B2, 2451, and 24S2). Of these i locations, two (15F5 and 16B2) could be affected by Station I discharge. The following analyses were performed.

Gross Betn

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Samples from all locations were analyzed for concentrations of -

gross beta in the soluble and insoluble fractions (Tables C-I and ,

C-II, Appendix C). Detectable activity was observed in the _

soluble and insoluble fraction of the surface water samples. The -

values were constant with previous years (Figures C-1 and C-2, _

Appendix C) and ranged from 3 to 4 pCi/l for the soluble fraction l and from < .4 to 2.0 for the insoluble fraction. No difference in activity levels was observed between indicator and control i locations for the soluble fraction. The insoluble fraction of a the sample from the downstream location, 15F5, did not show "I significantly higher activity than the control locations.

However, the same fraction of downstream sample location 16B2 E showed a higher activity (2 pCi/1) than the control locations. 3 This higher activity is attributable to the elevated sediment content of the sample. An activity of 2 pCi/l is still below the required sensitivity for this analysis and therefore this -

activity is not considered significant. y Gamma Spectrometry l Samples from all locations were analyzed for gamma emitting nuclides (Table C-III, Appendix C). All nuclides searched for -

were below the minimum detectable level, with the exception of I naturally occurring K-40 which was detected at location 2452 (30 l pCi/1). "

Tritium -

s Samples from locations 10F2, 16B2, and 24S1 were analyzed for .

aqueous tritium activity (Table C-IV, Appendix C). positive 7

tritium activity (130 pCi/1) was observed only at location 2451 -

(control).

2. Drinkinn (potable) Water -

Monthly samples were taken from five locations. A hand  ;

composited sample was collected from location 13H2, Samples from locations 15F4, 15F7, 16C2 and 28F3 were collected from a continuous water sampler. Four stations (13H2, 15F4, 15F7 and -

16C2) could be affected by Station discharge. The following analyses were performed:

Gross Beta Samples from all stations were analyzed for concentrations of gross beta in tha soluble and insoluble fractions (Tables C-V and C-VI, Appendix C). The values ranged from 3 to 5 pCi/l for the soluble fraction and from <.4 to .5 pCi/l for the insoluble fraction. No significant difference in activity levels was observed between indicator and control location.s for both the soluble and insoluble fractions. In addition, concentrations detected in both fractions were consistent with those observed in previous years (Figures C-3 and C-4, Appendix C).

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-VII, Appendix C). All nuclides searched for were below the minimum detectable level, except naturally occurring K-40, which was detected (30 pci/l and 20 pCi/l respectively) at locations 15F7 and 13H2.

Tritium Samples from locations 15F4, 15F7, 16C2 and 28F3 were analyzed for aqueous tritium activity (Table C-VIII, Appendix C).

i positive tritium activity was observed in 3 of 4 samples with l activities ranging from 100 to 240 pCi/1. No significant difference in tritium activity was observed between the control and indicator locations.

3. Fish No fish samples were collected from any of the three locations during the period of this report.
4. Sediment -

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No sediment samples were collected from any of the three %Ql%

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B. Atmospheric Environment j '. ', 'a, .

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1. Airborne s , o. 4 e
a. Air particulates
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Continuous air particulate samples were collected from I 23c seventeen locations on a weekly basis. The seventeen .:/'3J' locations are separated into three groups: Group I represents 3. 3. j locations within the LGS site boundary (1053, 1151, 1451 and ' .:

34S2), Group II represents locations near the LGS site (2B1, j f'hI s. / ..

6C1, 9C1, 13C1, 15DI, 1781, 20D1, 26B1, 29B1, 31DI, 35B1), I C,

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and Group III represents control locations at remote distances from LGS (13H4 and 22G1). The following analyses were performed:

Gross Beta Weekly samples were analyzed for concentrations of beta emitters (Table C-IX, Appendix C). Detectable activity was observed at all locations. The values ranged from .015 to

.028 pCi/m3 No significant difference in activity was observed between the control and indicator stations. In addition, concentrations detected were consistent with those observed in previous years (Figure C-5, Appendix C).

Gamma Spectrometry Weekly samples were composited and analyzed monthly for gamma-emitting nuclides (Table C-X, Appendix C). Naturally occurring Be-7 was detected in all samples, due to cosmic ray activity. These values ranged from .08 to .15 pCi/m3 K-40, also naturally occurring, was found in five of seventeen samples. These values ranged from .02 to .09 pCi/m3 All other nuclides searched for were below the minimum detectable levels. No significant difference in activity was observed between the control and indicator stations.

b. Airborne Iodine Continuous air samples were collected from the same seventeen locations as the air particulate samples. However, of the seventeen locations, eight (10S3, 1151, 13C1, 13H4, 1451, 22G1, 31DI, 35B1) were analyzed weekly for I-131 The remaining nine samples were held and analysis was not necessary. Results of the I-131 analysis are found in Table C-XI, Appendix C. All results were less than the minimum detectable level.
2. Terrestrial
a. Milk No samples were collected from any of the milk farms during the period of this report.
b. Well Water No samples were collected from either of the well water locations during the period of this report.
c. Food Products No samples were collected from the vegetation location during the period of this report.

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d. Game No Game sample was collected during the period of this report.

C. Ambient Gamma Radiation ,,

Ambient gamma radiation levels were measured utilizing CaSog: Tm j i thermoluminescent dosimeters. Forty-eight TLD locations were '

l established around the site in a three ring concept for .

comparison purposes: an " inner ring" of sixteen locations around the site boundary; a " middle ring" of twenty-seven locations within a ten mile radius of the site; and an " outer ring" of five locations at distances outside the ten mile radius of the site. .

Appendix c' Results of TLD measurements are listed in Table C-XII, C. All TLD measurements were below 10 mrad /std. month, with a range of 5.26 to 9.66 meads /std. month. No significant differences were observed among the results from the site, middle, and outer rings (Table C-XIII, Appendix C). In addition, levels measured were consistent with those observed in previous yearn (Figure C-6, Appendix C). p-t

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REFERENCES l

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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 le November 1979.

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l RADIOLOGICAL ENVIRONMENTAL MONITOP.ING REPORT

SUMMARY

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APPECOIX A RADIOLOGICAL ENVIROtttENTAL ttONITC:(ItG PROGRDt1 A04UOL SUNNARY NaNE OF FACILITY: LINERICCC GENERATING STATION DOCKET KD.: 50-352 LOCATION OF FACILITY: NONTGONERY COUNTY, PA 50-353 REPORTItG PERICO s 12/22-12/31/84 INDICATOR CONTROL LOCATION WITH REQUIRED LOCATIONS LOCATIONS HIGHEST NEAN NUMBER NEDItR1 OR TYPE OF NUMBER OF LOWER LIMIT MEAN MEAN HEAN STATION 8 0F NONROUTINE PATHWAY SAMPLED ANALYSES ANALYSES OF DETECTION (F) (F) (F) HAME REPORTED UNIT OF MEASUREMENT) PERFORNED PERFORNED (LLD) RANGE RANGE RANGE DISTANCE C DIRECTION NEASURENENTS

_ .... _ ___ _..- _ __ - _ _ _ - - _ = - ___ ....__.__.

AIR PARTICULATE GROSS BETA 34 0.01 .021 .022 .023 10S3 (INDICATOR) 0

( PC/CU. NETER ) (30/30) (4/4) (2/2) KEEN ROAD

(.015 .028) (.021 .026) (.021 .025) 0.5 MILES E OF SITE GANNA I7 BE-7 N/A .31 .30 .15 9Cl (INDICATOR) 0 (15/15) (2/2) (1/1) REED ROAD

( . 08 .15 ) (.10 .10) (.15) 2.2 NILES E OF SITE K-40 N/A .05 < LLD .09 3581 (INDICATOR) 0 (5/15) (1/1) PLEASANTVIEW ROAD

(.02 .09) (.09) 1.9 NILES t#64 0F SITE CS-134 0.05 < LLD < LLD < LLD 0 CS-137 0.06 < LLD < LLD < LLD 0 AIR IODINE I-131 16 0.07 < LLD < LLD < LLC 0 (PC/CU. NETER)

SURFACE WATER GROSS BETA 5 4 1.4 < LLD 2.0 16B2 (INDICATOR) 0 (PC/ LITER) INSOLUBLE (2/2) (1/1) LINFIELD BRIDGE

(.8-2.0) (2.0-2.0) 1.1 NILES SSE OF SITE GROSS BETA 5 4 4 3 4 15F5 (ItOICATOR) 0 SOLUBLE (2/2) (3/3) (1/1) PHILADELPHIA SUBURBAN WATER COMPANY (3-4) (3-3) (4-4) 7.8 NILES SSE OF SITE AQUEDUS H3 3 2000 < LLD 130 130 24S1 (CONTROL) 0 TOTAL (1/2) (t/1) LINERICK INTAKE (130-130) (130-130) 0.3 NILES WSW OF SITE NEAN Ato RANGE BASED UPON DETECTABLE NEASURENENTS CHLY. FRACTION OF DETECTABLE NEASURENENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES. (F) m n ."a m a

APPENDIX A (CONTINUED)

RADIOLOGICAL UNIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

NAME OF FACILITY 8 LIMERICK GENERATING STATION DOCKET NO.8 50-352 LOCATION OF FACILITYs MONTGOMERY COUNTY, PA 50-353 REPORTING PERIOD: 12/22-12/31/84 INDICATOR CONTROL LOCATION WITH REQUIRED LOCATIONS LOCATIONS HIGHEST MEAN NUMBER NUMBER OF LOWER LIMIT MEAN MEAN MEAN STATION # OF NONROUTINE MEDIUM DR TYFE OF ANALYSES OF DETECTION (F) (F) (F) HAME REPORTED PATHWAY SAMPLED ANALYSES PERF ORME D (LLD) RANGE RANGE RANGE DISTANCE C DIRECTION MEASUREMENTS UNIT OF MEASUREMENT) PERF ORMED

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l SURFACE WATER GAMMA 5 l (PCI/ LITER) TOTAL 0 l K-40 N/A < LLD 30 30 2452 (CONTROL)

(1/3) (1/1) FRICKS LOCK BOAT HOUSE (30) (30) 0.3 MILES WSW 15 < LLD < LLD < LLD 0 MN-54 30 < LLD < LLD < LLD 0 FE-59 15 < LLD < LLD < LLD 0 CO-58 15 < LLD < LLD < LLD 0 C0-60 30 < LLD < LLD < LLD 0 IN-6 5 30 < LLD < LLD < LLD 0 ZR-95 15 < LLD < LLD < LLD 0 NB-95 15 < LLD < LLD < LLD 0 CS-134 18 < LLD < LLD < LLD 0 CS-137 60 < LLD < L LD < LLD 0 BA-140 15 < LLD < LLD < LLD 0 LA-140 5 4 .5 < LLD .5 13H2 ( INDICATOR ) 0 DRINKING WATER GROSS BETA

( PC/ LITER ) INSOLUBLE (2/4) (1/1s BELMONT WATER WORKS (PHILA. )

(.4 .5) (.5 .5) 25.5 NILES SE OF SITE GROSS BETA 5 4 4 3 5 15F4 (INDICATOR) 0 SOLUBLE (4/4) (1/1) (1/1) PHILADELPHIA SUDURBAN WATER COMPANY l (5-5) 7.8 MILES SSE OF SITE (3-5) (3-3)

AQUEDUS H3 4 2000 170 150 240 16C2 (INDICATOR) 0 TOTAL (2/3) (1/1) (1/1) CITIZENS HOME WATER COMPANY (100-240) (150-150) (240-240) 2.4 HILES SSE OF SITE MEAN AND RANGE BASED UPON DETECTABLE MEASURENDITS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIDHS IS INDICATED IN PARENTHESES. (F)

APPEtOIX A (CONTINUEDI RADIOLOGICAL ENVIR0tPTENTAL HONITORING PROGRAtt At#1UAL SUNNARY NAME OF FACILITY: LINERICK GENERATING STATION DOCKET NO.s 50-352 LOCATION OF FACILITTs NONTGONERY COUNTY. PA 50-353 REPORTItG PERIODS 12/22-12/31/84 ItOICATOR CONTROL LOCATION WITH REQUIRED LOCATIDHS LOCATIONS NIGHEST NEAN NUMBER NEDIUM OR TYPE OF NUMBER OF LOWER LIMIT NEAN HEAN NEAN STATION 8 CF HONROUTINE PATHWAY SAMPLED ANALYSES ANALYSES OF DETECTION (F) (F) (F) NAME REPORTED UNIT OF NEASUREMENT) PERFORNED PERFORNED (LLD) RANGE RANGE RANGE DISTANCE C DIRECTION NEASUREMENTS

. . . _ _ _ _ . _ _ _ _ . _ -- -- - =- _--- ------- - -. - ------- -==- - -- - -

DRItMING WATER gat 1MA 5 (PCI/LITERI TOTAL K-40 N/A 25 < LLD 30 15F7 (INDICATORI O (2/3) (1/11 FiiOENIXVILLE WATER WORKS (20-30) (30) 5.2 NILLS SSC OF SITE NN-54 15 < LLD < LLD < LLD 0 FE-59 30 < LLD < LLD < LLD 0 CO-58 15 < Lt>l < LLD < LLD 0 CD-60 15 < LLD < LLD < LLD 0 ZN-65 30 < LLD < LLD < LLD 0 ZR-95 30 < LLD < LLD < LLD 0 ND-95 15 < LLD < LLD < LLD 0 CS-134 15 < LLD < LLD < LLD 0 CS-137 18 < LLD < LLD < LLD 0 BA-140 60 < LLD < LLD < LLD 0 LA-140 15 < LLD < LLD < LLD 0 DIRECT RADIATION TLD 48 N/A (7.58) ( 7.50 ) ( 9. 66 ) 3101 (IPOICATORI O NRAD/STD. HONTH (43/43) (5/53 (f/1i LINCOLN SUBSTATION (5.26-9.66) (6.70-7.50) 19.66) 3.0 MILES NW OF SITE NEAN AND RANGE BASED UPON DETECTABLE HEASUREMENTS ONLY. FRACTION OF DETECTABLE HEASURENENTS AT SPECIFIED LOCATIONS IS IPOICATED IN PARENTHESES. (F)

l SAMPLE DESIGNATION f AND LOCATIONS 4

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APPENDIX 8: SAMPLE DESIGNATION AND LOCATIONS LIST OF TABLES AND FIGURES TABLES TABLE B-It Location Designation and Identification System for the Limerick Generating Station TABLE B-II: Sample Collection and Analysis Program for the Operational Radiological Environmental Monitoring Program, Limerick Generating Station, 22 December through 31 December 1984 FIGURES FIGURE B-1: Environmental Sampling Locations on site or near the Limerick Generating Station FIGURE B-2: Environmental Sampling Locations at Intermediate Distances trom the Limerick Generating Station FIGURE B-3: Environmental Sampling Locations at Remote Distances from the Limerick Generating Station I

I o

TABLE B-I Location Designation and Identification System for the Limerick Generating Station XXYZ General code for identification of locations, where:

XX -

Angular Sector of Sampling Location The compass is divided into 36 sectors of 10 degrees each witG center at Limerick off-gas vent. Sector 36 is centered due Northc ar.d others are numbered in a clockwise direction.

1 -

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-sitr G : 10-20 miles off-site c  : 2-3 miles off-site H : 20-100 miles off-site D  : 3-4 miles off-site 1 - Station's Numerical Designation within sector and zono, using 1, 2, 3... in each sector and zone.

I s l l

l

r- -

i l

l TABLE B-II SAMPLE COLLECTION AMD ANALYSIS PROGRAM TOR THE OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.

LIMERICK GENERATING STATION l

ENVIRONMENTAL DISTANCE C DIRECTION COLLECTION METHOD ANALYSIS C FEEQUENCY STATION LOCATION DESCRIPTION FROM LG5 VENT C FREQUENCY PERFORMED i

l l A. Surface Water 10F2 Perkiomen Pumping Station 7.1 miles E Two gallon sample G. Beta (SCI)-monthly (control) collected from a Gamma Spec-ronthly continuous water Tritium-quarterly composite sampler, monthly 15r5 Philadelphia Suburban 7.8 miles SE Same as 10r2 G. Beta (SCI)-monthly Water Company (indicator) Gamma Spec-monthly 1652 Linfield Bridge 1.1 miles SSE Same as 1072 Same as 1072 (indicator) 2451 Limerick Intake 0.3 miles SSW Same as 10T2 Same as 10F2 (control) 2452 Tricks Lock Boat House 0.3 miles WSW Same as 10T2 Same as 15r5 (control)

B. Drinkina (Potable) Water 13H2 Belmont Water Works 25.5 miles SE Tuo gallon hand G. Beta (SCI)-monthly (indicator) composited sample. Gamma spec-monthly collected monthly 15r4 Philadelphia suburban 7.8 miles SE Tuo gallon composite G. Beta (SCI)-monthly Water Company (indicator) sample collected from Gamma Spec-monthly a continuous water Tritium-quarterly composite sampler, monthly 15F7 Phoenixville Water Works 5.2 miles SSE Same as 15F4 Same as 15r4 i (indicator) 1 16C2 Citizens Home Water Company 2.4 miles SSE Same as 15F4 Same as 15r4 (indicator) 28r3 Pottstown Water Authority 5.9 miles WMW Same as 15F4 Same as 15F4 (control)

I 1

TABLE B-II (cont.) SAMPLE COLLECTION AND A)ALTSIS PROGRAM FOR THE OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MOMITORING PROGRAM.

LIMERICK GENERATING STATIOM ENVIRONMENTAL DISTANCE E DIRECTION COLLECTION METHOD ANALTSIS E.FRESUENCT STATION LOCATION DESCRIPTION TROM LCS VENT E FRESUENCT PERFORMED

c. Well Water 1151 LGS Information Center 0.5 miles ESE Two gallon grab Tritium-semi-annually taken from faucet Gamma Spec-semi-annually semi-annually 18A1 Control 1.0 miles 5 Two gallon grab Tritium-semi-annually taken from faucet Gamma Spec-semi-annually semi-annually D. Cou's Milk 36E1 4.7 miles M Two gallon grab I-131-menthly sample collected Gamma Spec-quarterly from hulk tank at farm monthly SC1 2.6 miles ME Bi-veekly during ~ I-131-bi-weekly / monthly grazing season (April Gamma Spec-monthly through November):

monthly otherwise 9Et 4.1 miles E same as 36E1 Same as 36E1 9G1 Control 11.4 miles E Same as 36El Same as 36El 11D1 3.8 miles ESE Same as 36E1 Same as 36E1 11E1 4.9 miles ESE Same as 36E1 Same as 36E1-17C2 2.5 miles 5 Same as 36E1 3ame as 36E1 18C1 1.9 miles S Same as 36Et same as 36Et 2181 1.7 miles SW Same as 36E1 Same ar 36El 22F1 Control 9.8 miles SW same as SCI Same as SC1 23B1 1.3 miles WSW same as SCI same as SC1

l L.

I l.

I l

l TABLE B-II (cont.) SAMPLE COLLECTION AND ANALYSIS PROGRAM TOR THE OPERATIONAL RADIOLOGICAL ENVIRONMENTAL FOMITORING PROGRAM.

i LIMERICK GENERATING STATIOM 1

t i

l ENVIRONMENTAL DISTANCE & DIRECTION COLLECTION METHOD ANALYSIS E FRE9UENCT'

! LTATIO;t LOCATION DESCRIPTION TROM LGS VENT E FRESUENCT PERTORMLD j E. Goat's Milk i

l 1051 1.1 mile ESE Tuo gallon grab I-131-bi-veekly/ monthly 12 sample collected Gamma Spec-monthly l from hulk tank at farm, bi-weekly j during grazing season I (April through November);

monthly otheruise F. Air Particutates/ Air Todine 231 Sanatoga Substation 1.5 miles MNE Approximately 1 cfm G. Beta-veekly continuous flow Gamma Spec-monthly composite

( through glass fiber I-131-if necessary and charcoal filters (approx. 2" diameter) l uhich are installed for one week and replaced 6C1 Pottstown Landing Tield 2.1 miles EME Same as 251 Same as 2B1 9C1 Reed Road ( 2.2 miles E Same as 251 Same as 251 1053 Keen Road 0.5 miles E same as 251 G. Beta-veekly Gamma Spec-monthly composite I-131-ueekly 1151 LGS Information Center 0.5 miles ESE Same as 251 Same as 1053 13C1 King Road 2.9 miles SE Same as 231 Same as 1053 13H4 2301 Market Street. 28.8 miles SE Same as 251 Same as 1053 Philadelphia (control) 1431 Longvieu Road 0.6 miles SE Same as 2B1 Same as 1053 l 15D1 Spring City Substation 3.2 miles SE Same as 281 Same as 251 l

l

i TABLE B-II (cont.) SAMPLE COLLECTION AND ANALTSIS' PROGRAM FOR THE OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MOMITORING PROGRAM.

LIMERICK GENERATING STATION I

( ENVIRONMENTAL DISTANCE & DIRECTION COLLECTION METHOD ANALTSIS E FREQUENCT STATION LOCATION DESCRIPTION FROM LGS VEMT & FREQUENCT PERFORMED l F. Air particulates/Rir Todine (contd.)

17B1~ Linfield Substation 1.6 miles S Same as 2B1 Same as 2B1 20D1 Ellis Wood Road 3.1 miles SSW Same as 251 Same as 251 22G1 Manor Substation 17.6 miles SW Same as 2B1 Same as 1053 l (control) i 2651 Old Schuylkill Road 1.7 miles W Same as 251 Same as 2B1 l 2931 Test Road 1.8 miles MW Same as 251 Same as 251 31D1- Lincoln Substation 3.0 miles NW Same as 2B1 Same as 1053 3452 Met. Tower 81 0.6 miles MMW Same as 251 Same as 251 j 3551 Pleasantvieu Road 1.9 miles MMW Same as 251 Same as 1053 l

l G. Fish 16C5 Vincent Pool Downstream of- Fish flesh from two Gamma Spec-Semi-annually (indicator) Discharge groups represanting l

! predator and bottom feeder

! species collected by electrofisher or other l

appropriate fishery gear, semi-annually 2051 Discharge Area Dounstream of Same as 16C5 Same as 16C5 (indicator) Discharge 29C1 Pottstown Vicinity Upstream of Intake Same as 16CS Same as 16C5 (control)

l TABLE B-II (cont.) SAMPLE COLLEC' TION AND ANALYSIS PROGRAM FOR THE OPERATIONAL' RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM, LIMERICK GENERATING STATION i

i l ENVIRONMENTAL DISTANCE E DIRECTION COLLECTION METHOD ANALYSIS C FREQUENCY STATION LOCATION DESCRIPTION FROM LGS VENT C FRESUENCY PERFORMED H. Sediment 16B2 Linfield Bridge Downstream of Recently deposited Gamma Spec-Semi-annually (indicator) Discharge sediment collected below the waterline, l

i semi-annually i 16C4 Vincent Dan Downstream of Same as ISB2 Same as 16B2 I

(indicator) Discharge 33A2 Control Upstream of Same as 1682 Same as 16B2 Discharge I. Game 2655 Fricks Lock Area Site Vicinity Game animal col',ected Gamma Spec-annually by huntina -Lavally J. Veaetation 1151 LGS Information Center 0.5 miles ESE Broad leafy vegetation Gamma Spec-monthly and root crops, monthly during the growing season (May-September)

K. Environmental Dosimetrv-TLD 36S1 Evergreen C Sanatoga Road 0.6 miles N Collection method and TLD-monthly frequency is described in placement procedure,Section III, A.

2B1 Sanatoga substation 1.5 miles NME Same as 3651 Same as 3651 2E1 Laughing Waters GSC 5.1 miles HNE Same as 3651 Same as 3651 351 Sanatoga Road 0.6 miles NME Same as 3651 Same as 36S1 4E1 Heiffer Road 4.6 miles NE Same as 3651 Same as 3651 551 Possum Hollow Road 0.4 miles NE Same as 3651 Same as 3651

..g. .

. TABLE B-II (cont.) .5 AMPLE COLLECTION AND AMALYSIS PROGRAM'FOR THE.0PERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.

LIMERICK GENERATING STATION.

ENVIRONMENTAL DISTANCE C. DIRECTION JCOLLECTION METMOD ANALYSIS.E FRE9UENCT STATION. LOCATION DESCRIPTION FROM LG5 VENT? C'FRESUENCT PERFORMED K. Environmental Dosimetrv-TLD (contd.)

5H1 Birch substation ~ 25.8 miles ME Same as 3651 Same as 3651 6C1 Pottstown Landing Field 2.1 miles EME Same as.3651 Same-as 3651 751 LGS Training Center 0.5 miles EME same as 3651 Same as 3651 7El Pheasant Road 4.2 miles EME - same as 3651' Same as 3651 9C1 Reed Road 2.2 miles E same as-3651 Same as 3651 1053 Keen Road 0.5 miles E same as 3651 same as 3651 10E1 Royersford Road 3.9 miles E Same.as-3651 Same as 3651 10F3 TraPPe substation 5.5 miles ESE. Same as 3651 Same as 3651 1151 LG5 Information Center 0.5 miles ESE Same as 3651 same as 3651 13C1 King Road 2.9 miles SE same as 3651 Same as 3651 13E1 Vaughn substation 4.3 miles SE  ; Same as 3651- Same as.3651 13H3 3508 Market street, 28.2 miles SE Same as 3651 Same as 3651 Philadelphia (control) 1451 Longview Road.lsE Sector 0.6 miles SE Same as 3651 Same as 3651 15D1 Spring. City substation 3.2 miles SE same as 3651 Same as 3651 1652 Longview Road. SSE Sector 0.6 miles SSE Same as.3651 same as 3651 16 F 1 - Pikeland Substation 4.9 miles SSE Same as 3651 same as 3651 1781 Linfield Substation' 1.6'ailes S Same as 3651 same as 3651 1851 Rail Line along 0.3 miles s_ same as 3651 same as 3651 Longview Road 18G1 Planebrook' Substation 12.9 miles S Same as 3651 same as 3651

TABLE B-II (esnt.)T SAMPLE CILLECTIEM AND ANALTSIS PR31 RAM FCR THE CPERATICMAL RADI3LS31 CAL ENVIRIMMENTAL MONITECIM3 PR20 RAM, LIMERICK GENERATING STATION l

ENVIRONMENTAL DISTANCE E DIRECTION COLLECTION METHOD ANALTSIS E FREQUENCT STATION LOCATION DESCRIPTION FROM LGS VENT E FRESUENCT PERFORMED M. Environmental Dosimeterv-TLD (contd.)

34E1 Tarnell Road 4.6 miles MMW Same as 3651 Same as 3631 l

3551 Pleasantville Road 1.9 miles MMW Same E3 3651 Same as 3651 35F1 Ringing Rock Substation 4.2 miles M Same as 3651 Same as 3651

.s

  • 7 l

l i

i r

l l

r --

c TABLE B-II (cont.) 5 AMPLE COLLECTION AND ANALYSIS PROGRAM FOR THE OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.

LIMERICK GENERATING STATION ENVIRONMENTAL DISTANCE C DIRECTION COLLECTION METHOD ANALYSIS'C FREQUENCY STATION LOCATION DESCRIPTION FROM LGS VENT C TRE9UENCY PERFORMED K. Environmental Dosimetry-TLD (contd.)

19D1. Snouden Substation 3.6 miles 5 same as 3651 Same as 3651 20D1 Ellis Woods Road 3.1 miles SSW Same as 3651 Same as 3651

,20F1 Sheeder Substation 5.2 miles 55W Same as 3651 same as 3651 21S1 Impound Basin 0.5 miles SSW . Same as 3651 Same as 3651 22G1 Manor Substation 17.6 miles SW Same as 3651 Same as 3651 2352 Transmission Tower 0.5 miles WSW Same as 3651 Same.as 3651 24D1 Porters Mill Substation 3.9 miles SW Same as 3651 Same as 3651 2551 sector site Boundary 0.5 miles SW Same as 3651 Same as 36S1 25D1 Hoffecker C Kain streets 4.0 miles WSW Same as 36S1 Same as 3651 2653 Met. Tower 92 0.4 miles W . Same as 3651 Same as 3651 2651 Old Schuylkill Road 1.7 miles W Same as-3651 Same as 3651 28D2 W. Cedarville Road 3.8 miles W Same as 36S1 Same as 3651 2951 Sector site Boundary 0.5 miles WNW Same as'3651 Same as 36S1 2951 Yost Road 1.8 miles NW Same as 3651 Same as 3651 29E1 Prince Street 4.9 miles WNW Same as 36S1 Same as 3651 31D1 Lincoln Substation 3.0 miles NW Same as 36S1 same as 3651 31D2 Poplar substation 3.9 miles NW Same as 3651 Same as 3651 3251 Sector Site Bourdary 0.6 miles NW Same as 3651 Same as 36s1 32G1 Friedensburg substation 15.6 miles NW Same as 3651 same as 3651 3452' Met. Tower el 0.6 miles NNW Same as 3651' Same as 3651

' ~

NNE e , 36S1 EVERGREEN & SANAT0GA RDS.

NW '

34S2 NE 36SI 351 SANAT0GA ROAD 551 POSSUM HOLLOW ROAD j 3 gg 3gg j 7Sl LGS TRAINING CENTER WNW NE E3

  • 2AD l SSI 11S1 LGS INFORMATION CENTER i e 1451 LONGVIEW ROAD 76I

] 29SI , 1652 LONGVIEW ROAD

)

1851 RAILROAD TRACKS /LONGVIEW RD.

W .

- 1053 E 20S1 LGS DISCHARGE AREA

  • 21S1 IMP 0UNDING BASIN i 26
  • 2352 TRANSMISSION TOWER l g ,
24SI ll$l 2451 LGS INTAKE 18 51 24S2 FRICKS LOCK

! 24S2

ESE 25S1 SW SECTOR

' 26S3 MET'. TOWER #2 1 WSW

  • 2951 WNW SECTOR l ,

3251 NW SECTOR 2iSI 1451

'

  • 34S2 MET. TOWER #1 16 S 2 i

2OSI -

1 SW SE

FIGURE B-1 l ENVIRONMENTAL SAMPLING LOCATIONS ON-SITE OR NEAR THE LIMERICK GENERATING'; STATION s SSE i

\

SITE B0UNDARY f

S$W S i

1 N

  • I / NNE NNW 15F4 PHIL. SUBURBAN WATER CO.

.k 15F5 PHIL. SUBURBAN WATER CO.

> \- l\

15F7 PHOENIXVILLE WATER C0.

16B2- LINFIELD BRIDGE L NE 16C2 CITIZENS HOME WATER C0.

NW 35FI j 16C4 VINCENT POOL r 16C5 VINCENT P0OL 3101 3581 16F1 PIKELAND SUBSTATION 34El 281 6CI 17B1 LINFIELD SUBSTATION 3102 29CI 2El SCI 17C2 FARM IN S SECTOR I 4 ENE 18Al ANDERSON ROAD WNW i 29El e7 18C1 FARM IN S SECTOR

- L

  • 298 '

19D1 SNOWDEN SUBSTATION SCI 2001 ELLIS WOODS ROAD 20F1 SHEEDER SUBSTATION

- - //_ e e IO F2 E 21B1 FARM IN SW SECTOR W ~

' e 3 22F1 FARM IN SW SECTOR 2BF3 25B1 2002 10 81 e 24D1 PORTERS MILL SUBSTATION e . 25B1 FARM IN WSW SECTOR 25D8e IBl e .N 2501 H0FFECKER & KEIM ST.

e e 26B1 OLD. SCHUYLKILL ROAD WSW [ '2.4 DI e* ESE 28D2 28F3 W. CEDARVILLE ROAD POTTSTOWN WATER AUTHORITY OFI llEl 29B1 YOST ROAD

  • lI '

e 29C1 VINCENT P0OL lOEl 22Fte t3Cl 29El HIGH SUBSTATION SE 31D1 LIrlCOLN SUBSTATION SW ifEgB2 31D2 POPLAR SUBSTATION 33A2 UPSTREAM OF DISCHARGE 18 AI 34El YARNELL ROAD 2001 iS F5 S 35B1 PLEASANTVIEW ROAD 15 F4 SSW , SSE 15F7 35F1 RINGING ROCKS SUBSTATION 19 DI 1781 3 16CS \ 16FI 18 Cl 17C2 '16C4'. 15D1 10 EILE RADIUS 36El FARM IN N SECTOR 10B1 FARM IN ESE SECTOR 2B1 SANAT0GA SUBSTATION 10El ROYERSFORD ROAD 2El LAUGHING WATERS 10F2 PERKIOMEN CREEK 4El NEIFFER ROAD 10F3 TRAPPE SUBSTATION FIGURE B-2 SCl FARM IN NE SECTOR 11D1 FARM IN ESE SECTOR ENVIRONMENTAL SAMPLING STATIONS AT 6Cl POTTSTOWN AIRPORT llEl FARM IN ESE SECTOR INTERMEDIATE DISTANCES FROM THE 7El GAME FARM 13Cl KING ROAD LIMERICK GENERATING STATION 9Cl REED ROAD 13F1 VAUGHN ROAD 9El FARM IN E SECTOR 15D1 SPRING CITY SUBSTATION

b

, h 5H1 BIRCH SUBSTATION N

{D i ,

, 9G1 FARM IN E SECTOR NNW h NNE 13H2 BELMONT WATER WORKS 13H3 3508 MARKET ST PHil.

l g 13H4 2301 MARKET ST PHil.

NW NE 18G1 PLANEBROOK SUBSTAT10N

, 22G1 MANOR SUBSTATION 32G1 FRIEDENBERG SUBSTATION l .,

i g- .f #

WNW '

ENE e SHI 32GI

'J:t l < 'J 9GI i

~

Wr --

6 '

i ~

e h

L 3 . ., g . .,k r

j e .. FIGURE B-3 i WSW 22GI 18 GI -

ESE ENVIRONMENTAL SAMPLING

! \ 13H 2 STATIONS AT REMOTE DIS-

/ -

i TANCES FROM THE LIMERICK l ,e -

I H4 GENERATING STATION j 13H3 1

SW  ;

- ] '

SE l 7_ _-

l i SSW SSE 50 MILE' A010 4

- x -- -. . _ _ .

4 A

J DATA TABLES

=

APPENDIX C DATA TABLES LIST OF TABLES AND FIGURES TABLES Tchle C-I Concentrations of gross beta (soluble) in sur-face water samples collected in the vicinity of Limerick Generating Station, December 1984.

Table C-II Concentrations of gross beta (insoluble) in sur-face water samples collected in the vicinity of Limerick Generating Station, December 1984.

.Toblo C-III Concentrations of gamma emitters in surface water samples collected in the vicinity of Limerick Generating Station, December 1984.

/

Table C-IV Concentrations of aqueous tritium in surface water samples collected in the vicinity of Limerick Generating Station, December 1984.

Toble C-V Concentrations of gross beta-(soluble) in drinking water samples collected in the vicinity of Limerick Generating Station, December 1984.

Teble C-VI Concentrations of gross beta (insoluble) i n' drinking water samples collected in the vicinity of Limerick Generating Station, December 1984.

Table C-VII Concentrations of gamma emitters in drinking water samples collected in the vicinity of Limerick Generating Station, December 1984.

-Toble C-VIII Concentrations of aqueous tritium in drinking unter samples collected in the vicinity of Limerick Generating Station, December 1984.

Toble C-IX Concentrations of gross beta in air particulate samples collected in the vicinity of Limerick Generating Station, December 1984.

Tchle C-X Concentrations of gamma emitters in air particulate samples collected in the vicinity of Limerick Generating Station, December 1984.

Tablo C-XI Concentrations of I-131 in air iodine sam-ples collected in the vicinity of Limerick Generating Station, December 1984.

Toblo C-XII Monthly ambient. gamma radiation levels in the vicinity of Limerick Generating Station, December 1984.

l I

l

i Table C-XIII Mean monthly ambient gamma radiation levels in the vicinity of Limerick Generating Station, December 1984.

Table C-XIV Summary of collection dates for samples col-lected in the vicinity of Limerick Generating Station, December 1984.

Table C-XV Typical minimum detectable levels of nuclides searched for but not found in the vicinity of Limerick Generating Station, December 1984.

Fiqures Figure C-1 Comparison of mean monthly gross beta (soluble) concentrations in surface water samples col-lected in the vicinity of Limerick Generating Station, 1982-1984.

-Figure C-2 Comparison of mean monthly gross beta (insoluble) concentrations in surface water samples col- -

lected in the vicinity of Limerick Generating Station, 1982-1984.

Figure C-3 Comparison of mean monthly gross beta (soluble) concentrations in drinking _ water samples col-lected in the vicinity of Limerick Generating Station, 1982-1984.

Figure C-4 Comparison of mean monthly gross beta (insoluble) concentrations in drinking water samples col-lected in the vicinity of Limerick Generating Station, 1982-1984.

Figure C-5 Comparison of mean monthly gross beta concentra-tion in air particulate samples collected in the vicinity of Limerick Generating Station, 1982-1984.

Figure C-6 Comparison of mean monthly ambient gamma radiation levels in the vicinity of Limerick Generating Station, 1982-1984.

o

, - - - , - , - , ---m ------,v.- r . -., , e . . - ~ - - - .,-

TABLE C-I CONCENTRATIONS OF GROSS BETA (SOLUBLE) IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION. DECEMBER, 1984 RESULTS IN UNITS OF PCI/L i 2 SIGMA COLLECTION PERIOD 10F2 15F5 16B2 2451 2452 NEAN

._ ... ............. _ _ . . . . . _ . _ _ __ = _

DEC 84 3 11 4 i1 3 i1 3 1 3 11 3 11 TABLE C-II CONCENTRATIONS OF GROSS BETA (INSOLUBLE) IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION. DECEt1BER, 1984 RESULTS IN UNITS OF PCI/L i 2 SIGMA COLLECTION PERIOD 10F2 15F5 16B2 2431 24S2 NEAN

. . . . . . . . . . _ _ _ _ _ _ _ _ - - - - _ _ _ . =-__ __ __ _ =_ _ _ _ ====___

DEC 84 < .4 .8 i .4 2.0 i .5 < .4 < .4 .8 l.4 TABLE C-III CONCENTRATIONS OF GAtt1A EMITTERS

  • IN SURFACE WATER SAMFLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION DECEMBER. 1984 RESULTS IN UNITS OF PCI/L i 2 SIGMA COLLECTION PERIOD NUCLIDE 10F2 15F5 16B2 24S1 2452 NEAN

._ ___. . _ _ _ _ - _ _ _ ______ _ _____=_ ======_ .== .... _

DEC 84 K-40 <5 <5 <6 < 10 30 1 10 10 20 OTHERS < t10L < tel < tel < MOL < MDL 0 FOR TYPICAL NINIMUM DETECTABLE LEVELS OF NUCLIDES SEARCHED FOR AND NOT FOUND SEE TABLE C-XV.

TABLE C-IV CONCENTRATIONS OF AQUEOUS TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATItG STATION, DECEt1BER,1984 RESULTS IN UNITS OF PCI/L 2 SIGMA CILLECTION PERIOD 10F2 15F5 1652 2451 2452 NEAN

.......... .....= - - - - - - = = _ . ___ . ____.... -_ __ _ = _ _ __-_ __

DEC 84 < 200 < 100 130 1 70 140 100 l

TABLE C-V CONCENTRATIONS OF GROSS BETA 1 SOLUBLE) IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, DECEMBER. 1984 j RESULTS IN UNITS OF PCI/L 2 SIGMA COLLECTIDH PERIOD 13H2 15F4 15F7 16C2 28F3 NEAN

- _ _ ._ _ _ .- ..,==

.=--. _ _

DEC 64 4 11 5 11 4 11 3 11 3 11 4 12 TABLE C-VI' CONCENTRATIONS OF GROSS BETA IIHSOLUBLEI IN CRIHKIllG WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, DECEMBER 1984 RESULTS IN UNITS OF PCI/L i 2 SIGMA COLLECTION PERIOD 13H2 15F4 15F7 16C2 28F3 NEAH

- = __ __ - = = == ...........-- ___ _ =_____

.......... ===_

DEC 84 .5 i .4 < .4 < .4 .4 i .4 < .4 .4 .1 TABLE C-VII CONCENTRATIONS OF GAtt1A EMITTERS # IN DRIHKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GEHERATING STATION. DECENDER. 1984 RESULTS IN UNITS OF PCI/L i 2 SIGMA COLLECTION PERIOD HUCLIDE 13H2 15F4 15F7 16CE 28F3 MEAN

.......... .......... ... ......... _ =. ---_______ __ ............. ......==- = -_____ __-_

DEC 84 K-40 20 1 10 <8 30 10 - <8 < 20 20 1 20 OTHERS < MDL < MDL < MDL < MDL < MD L

  • FOR TYPICAL MINIMUM DETECTABLE LEVELS OF HUCLIDES SEARCHED FOR AND HOT FOUND, SEE TABLE C .*V.

I l

TABLE C-VIII- CONCENTRATIONS OF AQUEDUS TRITIUM IN DRINKING WATER SAMPLES COLLECTED f IN THE VICINITY OF LIMERICK GENERATING STATION, DECEMBER, 1984 RESULTS IN UNITS OF PCI/L i 2 SIGMA COLLECTION PERIOD 13H2 15F4 15F7 16C2 28F3 MEAN

_=....

.......... ............. .... _.... _ ___ .......--.... .=-_=_

< 100 100 1 100 240 90 150 i 70 150 i 130 DEC 84

TABLE C-IX CONCENTRATIONS OF GROSS EETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATIOH DECEMBER 1984 RESULTS IN UNITS OF PCI/CU. M i 2 SIGMA 1984 GROUP I - LIMERICK SITE BOUNDARY LOCATIDHS WEEK 8 1053 1151 1451 34S2

.... ............. =- .-____ __=_

51 .025 i .004 .021 i .006 .023 .004 .024 i .004 52 .021 . 004 .016 i .003 .018 i .004 .017 i .003 MEAN .023 i .006 .019 i .007 .021 .007 .021 i .010 1984 GROUP II - HEAR SITE LOCATIONS WEEK

  1. 281 6Cl 9C1 13C1 1501 1781 51 .026 i .004 .022 .004 .023 .004 .024 .004 .023 i .004 .019 i .004 52 .020 i .004 .017 i .003 .018 i .003 .019 i .004 .019 i .004 .018 i .003 MEAN .023 2 .008 .020 i .007 .021 i .007 .022 i .007 .021 .006 .019 i .001 WEEK
  1. 2001 26B1 29B1 3101 35B1

...___ __ .. _____________ _== _- _ -- _____-

51 .028 i .004 .022 i .004 .020 i .004 .024 i .004 .022 .004 52 .018 i .004 .015 i .003 .018 i .003 .019 i .004 .017 i .003 MEAN .023 i .014 .019 i .010 .019 i .003 .022 i .007 .020 .007 1984 GROUP III - CONTROL LOCATIONS WEEK

  1. 13H4 22G1

' 51 .026 i .004 .021 i .004 4 52 .021 i .003 .021 .004 MEAN .023 i .008 .021 i .000 t'

4

, __ r.;__,_ _ . , , - . - _ _ , - _ _ _ . . , . , _ . , _.._, _ . , _ _ -_, ._, _..m.., _ _ , , , _ _ , , , . _ , , -

TABLE C-X CONCENTRATIONS OF GANNA ENITTERSm IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LINERICK GENERATING STATION, DECENDER. 1984 RESULTS IN UNITS OF PCI/CU. N i 2 SIGNA 1984 GROUP I - LINERICK SITE BOUNDARY LOCATIONS COLLECTIDN PERIOD NUCLIDE 1053 1151 1451 3452 NEAN

..__......... -- _ .-== ............. .............

DEC 84 BE-7 .11 1 .02 .10 i .02 .10 i .02 .10 i .03 .10 i .01 K-40 < .01 .02 1 .01 < .01 .06 i .02 .03 i .05 OTHERS < ND L < HDL < HDL < NDL 1984 GROUP II - NEAR SITE LOCATIDHS COLLECTION s PERIOD HUCLIDE 2B1 6C1 9C1 13Cl 15D1 1781

.......... .......... ... __..... .... ........ ________ == ..._ -. ==-- - - ___= __=

DEC 64 BE.7 .12 02 .10 i .02 .15 .03 .12 i .03 .10 i .02 .12 .02 K-40 < .009 < .01 < .03 < .02 .04 i .02 < .01 OTHERS < NDL < NDL < HDL < NDL < HDL < HD L COLLECTION PERIOD HUCLIDE 2001 26B1 29B1 3101 3581 NEAN DEC 84 BE-7 .14 1 . 03 .08 i .01 .12 i .02 .10 i .03 .10 i .03 .11 i .04 K-40 < .03 .03 i .02 < .01 < .04 .09 i .03 .03 .05 OTHERS < HDL < NO L < HD L < ND L < MDL 1984 GROUP III - CONTROL LOCATIONS COLLECTION PERIOD HUCLIDE 22G1 13H4 NEAN

.......... ==--- _ _ _ - __ ..........--. .._

DEC 84 BE-7 .10 i .02 .10 i .03 .10 i0 K-40 < .009 < .02 < .015 OTHERS < HDL < NDL

  1. FOR TYPICAL MIllINUM DETECTABLE LEVELS OF NUCLIDES SEARCHED FOR AND HOT FOUND. SEE TABLE C-XV.

]

+

1 I

1

TA8LE C.XI CONCENTRATIONS OF I.131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION. DECE118ER,1964 RESULTS IN LA4ITS OF PCI/CU. M GROUP I GROUP II GROUP III WEEK - -- -- --

8 1053 1151 1451 13C1 3101 3581 13H4 22G1 51 < .02 < .03 < .02 < .01 < .02 < .02 < .01 < .02 52 < .02 < .02 < .02 < .01 < .02 < .01 < .008 < .01 MEAN < .02 < .03 < .02 < .01 < .02 < .02 < .009 < .02 4

4 i

TABLE C-XII MONTHLY AMBIEifT GANt1A RADIATION LEVELS IN THE VICINITY OF LINERICK GEMERATING STATIDH, DECENDER, 1984 RESULTS IN UNITS OF NRADS/STD. HONTH 95% C. LINITS STATIDH STATIDH CODE EQV.HO. AVG. 12/02-01/02 CODE EQV.HO. AVG. 12/02-01/02 2B1 7.30 0 7.30io.38 2001 7.39 1 0 7.3910.47 2E1 8.31 1 0 8.31 1.13 20Ft 7.61 i 0 7.61 0.39 351 7.32 0 7.32it.19 21S1 7.10 k 0 7.1010.44 4Et 5.90 0 5.90 0.67 22GI 7.23 i 0 7.2311.46 5H1 8.50 0 8.50io.52 23S2 6.85 1 0 6.85 0.90 551 7.48 1 0 7.4810.52 2401 6.70 0 6.7011.21 6C1 7.84 0 7.84to.89 2501 6.54 0 6.5410.44 7El 8.03 1 0 8.03 0.58 2551 7.14 1 0 7.14io .77 751 8.90 1 0 8.9011.37 2601 7.29 0 7. 29i t . 03 9C1 8.10 1 0 8.10!0.47 2653 6.84 1 0 6.8411.28 10Et 9.05 1 0 9.05 0.60 2002 7.49 i 0 7.49 0.56 10F3 7.16 1 0 7.16t0.30 2981 7.74 1 0 7.74io.45 1053 8.51 0 8.5110.87 29El 6.81 1 0 6.8110.98 1151 9.00 1 0 9.00 1.67 29S1 6.96 i O 6.9611.1F 13C1 6.00 1 0 6.00i0.72 31D1 9.66 i 0 9.66t1.43 13Et 7.73 1 0 7.7310.68 3102- 8.36 1 0 8.3611.44 1451 7.61 1 0 7.61io.56 32G1 7.74 0 7.7411.71 1501 7.77 1 0 7.7712.24 1251 5.26 1 0 5.26 0.52 16F1 7.76 i 0 7.76 0.61 34Et 7.35 0 7.35il.28 1652 6.41 1 0 6.4tio.86 34S2 9.24 1 0 9.24t0.98 17B1 7.98 0 7.9Eto.64 35B1 8.59 i 0 8.59io.64 18G1 7.34 2 0 7.34 0.89 35F1 8.19 0 8.19 1.29 1851 7.14 1 0 7.14 0.78 3651 7.96 0 7.9611.19 1901 7.47 i 0 7.4710.65 STATIDH CDOE EQV.NO. AVG. 12/03-01/04 ,

....... .. _- - ___= ...........

13H3 6.70 1 0 6.70 1.25 l

4 TA8LE C-XIII MEAN MONTHLY AMBIENT GAMMA RADIATIDH LEVELS IN THE VICINITY OF LINERICK GENERATING STATIDH, DECEMBER, 1984 NO. DF SAMPLES PERIOD PERIOD PERIOD MEAN LOCATIDH ANALYZED MININUM MAXINUM i 2 STD. DEV. UNITS

..-- . === - .... ............. -- . - . ===--

SITE 16 5.26 0.52 9.24 1 0.98 7.48 2.08 NRAD/STD. MONTH MIDDLE RING 27 5.90 i 0.67 9.66 i 1.43 7.63 i 1.66 HRAD/STD. NCHTH DUTER RING 5 6.70 1 1.25 8.50 1 0.52 7.50 i 1.34 HRAD/STD. HOHTH SITE BOUNDARY RING STATIDHS- 351, 551, 75l.1053.1151,1451,1652,1851,2151,23S2,25S1,

- 26S3,29S1,32S1,34S2,36St.

MIDDLE RING STATIONS - 2B1, 2Et , 4El, 6C1, 7Et , 9C1,10E1,10F3,13C1,13E1,1501.

- 16F1,1781,1901.2001,20F1,2401,2501,26B1,28D2,2981,29Et ,

- 3101,3102,34E1,35B1,35F1.

DUTER RING STATIDHS - 5H1,13H3,18G1,22G1,32G1.

4

TABLE C-XIV StMtARY OF COLLECTION DATES FOR SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION. DECENBER. 1984  ;

l l

l AI? PARTICULATES GROUP I - LIMERICK SITE BOUNDARY LOCATIONS WEEK 8 1053 1951 1451 3452 51 12/17-12/24/84 12/20-12/24/84 12/17-12/24/84 12/17-12/24/84 52 12/24-12/31/64 12/24-12/31/64 12/24-12/31/84 12/24-12/31/84 ,,'

GROUP II - HEAR SITE LOCATIONS WEEK 8 281 6Cl 9C1 13Cl 1501 17B1 St 12/17-12/24/84 12/17-12/24/84 k 2/17-12/24/84 12/17-12/24/84 12/17-12/24/84 12/17-12/24/84 52 12/24-12/31/84 12/24-12/31/84 12/24-12/31/84 12/24-12/31/84 12/24-12/31/84 12/24-12/31/84 WEEK 8 2001 26B1 2981 3101 3581 51 12/17-12/24/84 12/17-l2/24/84 12/17-12/24/84 12/17-12/24/84 12/17-12/24/84 52 12/24-12/31/84 12/24-12/31/84 12/24-12/31/84 12/24-12/31/84 12/24-12/31/84 GROUP III - CONTROL LOCATIONS WEEK 8 13H4 22G1 51 12/17-12/24/84 12/17-12/24/84 52 12/24-01/02/85 12/24-12/31/84 AI2 IODINE GROUP I GROUP II GROUP III WEEK ----- -

8 1053 1151 1451 13Cl 3101 35B1 13H4 22G1

....= - _ = - _ _ -

51 12/17-12/24/84 12/20-12/24/84 12/17-12/24/84 12/17-12/24/84 12/97-12/24/84 12/17-12/24/84 12/17-12/24/84 12/17-12/24/84 52 12/24-12/31/84 12/24-12/31/84 12/24-12/31/84 12/24-12/31/84 12/24-12/31/84 12/24-12/31/84 12/24-01/02/85 12/24-12/31/84 SURFACE WATER C!LLECTION FERID3 10F2 15F5 16D2 2451 24S2

... ....=_- .- -

DEC 84 12/26/84 11/28-12/26/84 11/28-12/26/84 11/28-12/26/84 11/28-12/26/84 ORINKING WATER CILLECTION PERIOD 1 3112 15F4 15F7 16C2 28F3 DEC 84 11/28-12/26/84 11/28-12/26/84 11/28-12/26/84 11/28-12/26/84 11/28-12/26/84

TABLE C-XV TYPICAL # MINI'1UM DETECTABLE LEVELS OF HUCLIDES SEARCHED FOR BUT NOT FOUte IN SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATI0H. DECEMDER, 1984

_ __-_=................ - . . __ =..._

NUCLIDE AIR PARTICULATES SURFACE WATER DRINKING WATER (PCI/CU. M) tPCI/L1 1PCI/L)

BE-7 ## 8 9 K-40 .07 34 33 CR-51 .02 9 9 MH-54 .002 .9 .8 CO-57 .001 .6 .7 CO-58 .002 .9 .9 FE-59 .004 2 3 CO-60 .001 .9 .9 ZH-65 .003 2 3 ZR-95 .003 2 2 HD-95 .002 1 1 RU-103 .002 1 1 RU-106 .01 7 8 AG-110M k

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7 SYHOPSIS OF AN.ALYTICA

I. PROCEDURE

S i

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s APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES The following section contains a description of the analytical icboratory procedures along with an explanation of -the analytical calculation methods used by Teledyne Isotopes for sample analysis.

Sample Preparation and Countina Procedures Several types of liquid samples are separated by filtration prior to cnelysis. Resulting portions are identified as soluble and insoluble.

Therefore, soluble as used in this report, is defined as that portion of a nonple that passes through a No. 50 Whatman filter paper. Insoluble is defined as that portion of a sample that is collected on yo. 50 Whatman i filter paper.

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DETERMINATION OF GROSS ALPHA AND/OR BETA ACTIVITY l IN WATER SAMPLES l

(SUSPENDED AND DISSOLVED FRACTIONS)

TELEDYNE ISOTOPES This describes the process used to measure the overall radioactivity of unter samples without identifying the radioactive species present. No chGmical separation techniques are involved. One liter of the sample-is filtered under vacuum through a 0.45 pm Millipore filter. The filter is dried and mounted on a 2 inch stainless steel planchet to represent the

'ouopended fraction of the sample. The filtrate is evaporated on a hotplate, and the residue is transferred and dried on another planchet to represent the dissolved fraction of the sample.

The planchets are counted for 50 minutes in a low-background gas flow proportional counter. Calculation of activity includes a self-adsorption correction for counter efficiency based on the weight of residue on each planchet.

CALCULATION OF THE SAMPLE ACTIVITY OR OF THE MDL N -

S em N+B Et Et Net pCi on collection date = At unit volume or wt. 2.22 (v) (y) (DF) (E) i 2.22 (v) (y) (DF) (E) net activity counting error s

where: H = total counts from sample (counts) at = counting time for sample (min)

S = background rate of counter (cpm)

, 2.22 = dEm PCi

, v(u) = volume or weight of samrie analyzed '

y = chemical yield of the mount or sample counted DF = decay factor from the collection to the counting date ,

E = efficiency of the counter em = multiples of counting error For gross alpha and gross beta calculations set y = 1 and DF = 1.

i N l If the net activity 3T* - f is equal to or is less than the counting ceror, the activity'on the collection date is below the limits of detection cnd is called "less than" (L.T.) or " minimum detectable level" (MDL).

i

ENVIRONMENTAL DOSIMETRY By TI definition, a thermolumineccent dosimeter (TLD) is considered one cnd of a capillary tube containing calcium sulfate (Tm) powder as the thermoluminescent material. This material was chosen for its chorocteristic high light output, minimal thermally induced signal loss (feding), and negligible self-dosing. The energy response curve has been flottened by a complex multiple element energy compensating shield supplied by Panasonic Corporation, manufacturer of the TLD reader. There exists fcur dosimeters per station sealed in a polyethylene bag to demonstrate intGgrity at the time of measurement, and for visualization of the sample placcment instructions. The zero dose is determined from TLDs located in

'tha lead shield at Teledyne Isotopes, Westwood, Heu Jersey.

Following the predesignated exposure period the TLDs are placed'in the TLD reader. The reader heats the calcium sulfate (Tm) and the measured light emission (luminescence) is used to calculate the environmental radiction exposure.

Data are normalized to standard machine conditions by correcting occhine settings to designated values before readout. Data are also corrected for in-transit dose using a set of TLDs kept in a lead shield in the field, exposed only during transit. The average dose per exposure paried, and its associated error is then calculated.

A Cs-137 source is used to expose TLDs as a reference sample. An choorbed dose in tissue is determined using the 0.955 rad / Roentgen conversion factor and dose equivalent (mrem) by using' a quality factor of 1.

Celculation of results and two sigma error:

Gross TLD (1) = [TLD (1)-00(i)] x CF(i) x CF(ins) x 0.955 mrad /mRoentgen ITD~- Net (site 0) - [ NET (RMC 0) (0(sta) / 0(RMC 0))]

NET TLD(i) - gross TLO(i) - ITO n

AVG = [(sigma NET TLD) / n] [0(STO) / 0(EX)]

1=1 ERROR (95% CL) = t(n-1) [ sigma NET TLD (i) //5] [0(5TD) / 0(EX)]

1

whore: Gross 7LD(1) = Individual TLD reading corrected to standard instrument conditions TLD(i) = Gross reading of dosimeter i NET TLD(i) = Net dose obtained during exposure period in the field CF(ins) = Correction factor of reader = (6.158)

( ELS 1 812 ')

ELS = External light source Do(i) = Zero for dosimeter i CF(i) = calibration factor for dosimeter i ITD = in-Transit dose MET (site)0. = Mean of n dosimeters in site lead shield NET (RMC)0 = Mean of n dosimeters,in RMC lead shield D(sta) = Exposure period of station (SZRO)

D(RMC)0 = Exposure period of RMC 0 AVG = Mean exposure per standard exposure period at a given station n = Number of readings D(EX) = Days exposed D(STD) = Days in standard exposure period t(n-1) = T-distribution (student) factor for 95X CL sigma NET TLD(1) = Standard deviation of n readings of NET TLD (i)

ERROR = The 95% confidence limit error of AVG i

4 9

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DETERMINATION OF GAMMA EMITTING RADIOISOTOPES TELEDYNE ISOT0 PES 1

Gcama. emitting radioisotopes are determined with the use of a lithium-

.driftsd germanium (Ge(Li)) and high purity germanium detectors with high rocclution spectrometry .in specific media, for enample, air particulate

' f il t ors', charcoal- filters, milk, water, vegetation, soil / sediments,

. biological media, etc. Each sample to be assayed is prepared and counted in atendard geometries such as one liter wrap-around Marinelli containers, 300 c1 or-150 ml bottles, or two-inch filter paper source geometries.

Samples are counted on large (>55 cc volume) Ge(Li) 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 cativities of all detected radionuclides or the detection limits from a otondard list of nuclides. The Ge(Li) systems are calibrated for each otendard geometry using certified radionuclide standards traceable to the Notional Bureau of Standards, t

4 l

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DETERMINATION OF I-131 IN MILK AND WATER SAMPLES ,

BY RADIOCHEMISTRY AND LIQUID PHASE BY ANALYSIS j l

TELEDYME ISOT0 PES I J

This describes the radiochemical methods for determining I-131 activity in milk and water samples by coincidence counting in the liquid phase.

Four 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 oodium hypochlorite solution, reduced with hydroxylamine hydrochloride, and extracted into carbon tetrachloride av free iodine. It is then back-Gxtracted as iodide into sodium bisulfite solution.

The iodide sample solution is oxidized to the free state using hah 05 reagent and is extracted several times into a total of 15 ml of toluene. A 200 f41 aliquot is taken for determining chemical yield by opsctrophotometer. A decolorizing agent (2-methyl-2-butene) is added to the toluene-iodine solution to form an inert molecule and to minimize liquid scintillation quenching. A toluene-based liquid scintillation counting solution is added to the sample, which is then analyzed.by a beta-gated gamma-coincidence counting system.

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EALCULATION OF THE SAMPLE ACTIVITY OR OF THE MDL The sammle Activity and the 2-siana Countina Error are Calculated as Follous N -

0 2 N +6 E D E nit 'pCi on collection date = i at liter 2.22(v)(y)(DF)({} 2.22 (v)(y)(DF)(E)

I j net activity counting error

'Whore: N = total counts from sample (counts) '

At = counting time for sample (min) p = background rate of counter (cpm) 2.22 = dna pCi v = volume of sample analyzed (liters) y = chemical yield of the mount or sample counted DF = decay factor from the collection to the mid count time

& = efficiency of the counter for I-131 Note: Efficiency is determined by counting an I-131 standard.

Consequently, the branching intensity (abundance) of the I-131 gamma does not appear in the above equation.

? calculation of the,MDL If the net activity (previously defined) is equal to or is less than a specified multiple of the background counting error, the activity on the collection date is below the limits of detection and is called "less than" (L.T.) or " minimum detectable level" (MDL).

The L.T. value can be specified by stating only the counting error at a pradetermined multiple (am) of the one sigma statistics. A siSma cultiple (am) of 4.66 is used for calculation of the L.T. values unless cnother multiple such as 2.83 is specified.

i

, em T2.22(v)(y)(UF)(E) i

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DETERMINATION OF TRITIUM BY GAS COUNTING ,

I TELEDYNE ISOTOPES A 2 ml aliquot is oxidized and the hydrogen gas is collected in an activated charcoal trap. The hydrogen is then transferred into a previously evacuated one liter proportional counter. Non-tritiated ,

hydrogen and ultra-high purity methane is added and then counted.

8cckgrounds and standards are counted in the same gas mixture as the ocmples.

Calculation of the sample activity or the MDL:

3.234x(TU)w x Yg (CPM)G - BKG ia 6G2 + v82 Net pCi = CPM xV unit vol. N s where: (TU) = the tritium units of the standard V

N

= volume f the standard used to calibrate the efficiency of the detector (psia)

V3

= volume of the sample loaded into the detector (psia)

(cpm)g = the cpm activity of the standard of volume V ,

(cpm)3 = the gross activity of the sample of volume V and the detector background BKG = the background of the detector in cpm 3.234 = conversion factor changing TU to pc/1 At = counting time for the sample am = multiple of the counting error UG = standard deviation of the gross activity of the sample and the detector background, in cpm 6B = standard deviation of the background. in opm If the net activity (cpm)g - BKG is equal to or is less than twice the ccunting error, the activity on the collection date is below the limits of detection and is called "less than" (L.T.) or " minimum detectable level" (MDL). l 2 2

+ #

thus L.T. = 2 x 3.234 x (TV)N X VNx TG S (CN1)N x Vs 1

whore G = standard deviation of the gross activity of the sample and the detector background, in epm 8 = standard deviation of the background, in cpn

,, ,,,n- . - - - -

.- . , - . - - ., ,,.,---,,,,,,.,._.,...,n. _ , _ . , - . . , - . , - .

QUALITY CONTROL

APPENDIX E INTER-LABORATORY COMPARISON PROGRAM TI participates in the EPA radiological interlaboratory comparison (cross check) program. This participation includes a number of analyses on various sample media as found in the Limerick Generating Station REMp. As o rcsult of this participation, an objective measurement of analytical precision and accuracy as well as, a bias estimation of the results are obtained. During the time period of this report, the one comparison sample enolyzed fell within the EPA mean and standard deviations. Table E-I susaarizes the results of all 1984 samples, i

)

l l

TAsiz E-I

, INTER-LABORATORY COMPARISONS. 1984 i

TELE 0VNE ISOTOPES Collection .

Teledyne All Participants Date Media Nucilde EPA-Results(A) Isotopes Results(B) Mean i 2 s.d.

01/06 Water Sr-89 36. t 8.7 29.3 2 8.7 36. t 9.

Sr-90 24. t 2.6 23. t 3. 23. t 3.

01/20 Water Gross Alpha 10. t 8.7 8. t 3. 10. t 3.

Gross Beta 12. t 8.7 12. t 3. 13. t 3.

01/27 Food Sr-89 34 t 8.7 33.3 2 1.7 31. t 5.

Sr-90 20. t 8.7 21.7 t 1.7 21. 2 3.

1-131 20.

  • 10.4 16.3 2 1.7 20. t 4.

Cs-137 20. t 8.7 24.1 2 0.6 21. t 3.

K 2720. 2235, 2503. 2555. .2665. 2246.

02/03 Water Cr-51 40. t 8.7 L.T. 80. 40. t 8.

Co-60 10. t 8.7 15. t 7.9 11. t 2.

Zn-65 50. t 8.7 53.3 t 16.5 50. t 8.

Ru-106 61. t 8.7 58.7 t 33. 55. t 9.

Cs-134 31. t 8.7 33.3 t 3. 29. t 3.

Cs-137 16. t 8.7 19.3 2 1.7 16. t 3.

02/10 Water H-3 2383. 2607. 2270. t786, 2366, t247.

03/02 Milk l-131 6. t 1.6 5.7 t 1.7 6. t 1.

03/16 Water Gross Alpha 5. .t 8.7 5. i 1.3 6. t 2.

Gross Beta 20. 2 8.7 20. t 3. 20. t 3.

03/23 Air Filter Gross Alpha 15. t 8.7 19. t 1.7 16. t 3.

Gross Beta- 51. t 8.7 45. t 3.0 56, t 6.

Sr-90 21. t 2.6 20. t 6.0 19, t 2.

Cs-137 10. t 8.7 11. t 3.5 12. 1 3.

04/06 Water I-131 6. t 1.5 5.5 t 0.4 6. t 2.

04/13 Water H-3 3508. 2728, 2660, t342. 3461. 1288.

TABLE E-I (Cont.)

INTER-LA8 ORATORY COMPARISONS, 1984.

TELEDYNE ISOTOPES Collection Teledyne All Participants i Date Media Nuclide EPA-Results(A) Isotopes Results(B) Mean i 2 s.d.

t

! 04/20 Water Gross Alpha 35. 2-15.2 22. t 4.6 (D) l (Sample A) Ra-226 4.0 1 1.04 5.4

  • 3.3 (D).

Ra-228 8.3 2 2.16 2.9 2 0.6 (D) 04/20 Water Gross Beta 147.

  • 12.7 117. t 17.3 ~ (D)

(Sample B) Sr-89 23. t 8.7 18. t 7.5 (D) l Sr-90 26. t 2.6 22. t 3.5 (D) l Co-60 30. t 8.7 29. t 6.2 (D) l Cs-134 30. t 8.7 29. t 4.6 (D)

! Cs-137 26. t 8.7 29. t 6.0 (D) l l 05/04 Water Sr 25. t 8.7 23. t 5. 24. t 4.

l Sr-90 5. t 2.6 5.0 1 0.5 5.

  • 1.

t 05/18 Water Gross Alpha 3. t 8.7 2.7 1 0.8 3. t 1.

j Gross Beta 6. t 8.7 6.9 1 4.0 7. t 2.

06/01 Water Cr-51 66. t 8.7 L.T. 90. 64 2 13.

Co-60 31. t 8.7 33. t 3.5 31. t 4 Zn-65 63. t 8.7 68. t 15, 63. t 9.

Ru-106 29. t 8.7 L.T. 50. 30.

  • 11.

Cs-134 47. t 8.7 46. t 5. 44. t 6.

Cs-137 37, t 8.7 39. t 1.7 37. 1 4.

06/08 Water H-3 3051. 2622. 3210. t834. 3039. 2235.

06/22 Milk Sr-89 25. t 8.7 22. t 1.7 21. t 5.

Sr-90 17. t 2.6 17. t 4.6 15. 2 2.

1-131 43. t 10.4 40. t 9.6 43. t 4.

Cs-137 35. t 8.7 37. t 3. 36.

  • 3.

K 1496. 1130. 1653. t 46. 1560. t 97.

07/20 Water Gross Alpha 6. t 8.7 3.8

  • 2.4 0 Gross Beta 13. t 8.7 11.3
  • 3.5 D

[ TABLE E-I (Cont.)

I

! INTER-LABORATORY COMPARISONS, 1984 i

TELEDYNE ISOTOPES l

Collection _ Teledyne All Participants Date Media Nuclide EPA-Results(A) Isotopes Results(8) Mean i 2 s.d.

07/27 Food Sr-89 25.0 2 8.7 17. t 9. D)

(C) Sr-90 20.0 2 2.6 20. t 9. D) 1-131 39.0 t 10.4 19. t 3.5 D)

Cs-137 25.0 2 8.7 26. t 11. (D)

K 2605.0 2226.0 3027. 21183. (D) 08/03 Water 1-131 34.0 2 10.4 31. t 3.0 36. t 5.

08/10 Water H-3 2817. 2617. 2930. t 127. 2842. 2251.

08/24 Air Filter Gross Alpha 17. t 8.7 16. i 1.7 .17. 1 3.

Gross 8 eta 51. t 8.7 47. t 3. 52. t 6.

Sr-90 18. t 2.4 18. 2 1.7 17. 2 2.

Cs-137 15. t 8.7 17. t 4.6 17. t 4.

09/07 Water Sr-89 34. t 8.7 29. t 4.5 30.

  • 8.

Sr-90 19. t 2.6 19. t 1.0 18. t 3.

09/21 Water Gross Alpha 5.0 t 8.7 6.

  • 0.0 5. t 2.

Gross 8 eta 16.0 t 8.7 14. t 3. 15. t 3.

10/05 Water Cr-51 40. t 8.7 L.T. 107. 38. t 8.

Co-60 20. t 8.7 23. t 10.4 20. 2 3.

2n-65 147. t 8.7 155. t 17.6 149. t 12.

Ru-106 47. t 8.7 L.T. 53. 45. t 9.

Cs-134 31. t 8.7 34. t 12, 29. t 3.

Cs-137 24. t 8.7 28. t 10. 25. t 3.

10/12 Water H-3 2810. 2356. 2720. t 531. 2814. 2213.

10/22 Water Gross Alpha 14. t 8.7 11. 1 1.7 13.

  • 4.

(Sample A)

Water Gross Beta 64, t 8.7 65. t 10. 60. t 7.

(Sample 8) Sr-89 11. t 8.7 9. t 3.5 11. t 4.

Sr-90 12. 1 2.6 13. t 3. 13. t 3.

Co-60 14. t 8.7 19. t 3.5 16. t 2.

Cs-134 2. t 8.7 L.T. 5. 3. t 2.

Cs-137 14. t 8.7 17. t 7.5 16.

  • 2.

.i i

TABLE E-I ( Co n t . )

INTER-LABORATORY COMPARISONS, 1984 l

TELEDYNE ISOTOPES Collection Teledyne All Participants Date Media Nuclide EPA-Results(A) Isotopes Results(B) Mean 2 2 s.d.

10/26 Milk Sr-89 22. t 8.7 '15. t 1.7 19. t 4 Sr-90 16. t 2.6 14. t 3. 15.

  • 2.

1-131 42. t 10.4 34 t 9.6 40. t 5.

Cs-137 32. t 8.7 32, t 12. 32. t 3.

[

K 1517. t131. 1370. t 52.7 1498. 1143.

[ 11/16 Water Gross Alpha 7.0 t 8.7 7.3 t 1.7 7. '* 2.

l Gross Beta 20.0 t 8.7 21.7 1 1.7 21. t 3.

l l 11/23 Air Filter Gross Alpha 15. t 8.7 15. t 1.7- (D;I Gross Beta 52. t 8.7 54, t 3.5 LD; I Sr-90 21. 2 2.6 23. t 3. I,0 ;I Cs-137 10. t 8.7 9. t 4.6 1, D )

j 12/07 Water I-131 36. t 10.4 36, t 6.9 36. t 5.

12/14 Water H-3 3182, t624, 3523. 2868. 3206. t236.

l Notes (A) EPA Results-Expected laboratory precision (3 sigma). Units are pCi/f i

for water, urine, and milk except K is in og/1. Units are total pCi for air particulate filters.

(8) Teledyne Results - Average . three sigma. Units are pC1/f for water, urine, and alik except K is in og/f. Units are total pCi for afr particulate filters.

(C) Units for food analysis are pC1/kg.

(D) Results were not released at time of report.

1 h

i -.

r~

LGS SURVEY

p.

APPENDIX'F: LGS SURVEYS 1

The environmental program includes a requirement for three serveys to bo performed during the growing season. These include a nearest fa-m, a ncorast residence, and a nearest garden survey. The information obtained frea the rurveys is to be included in the annual report. However, rince the time period of this report does not include the growing season, survey information is not presented here.

1 t

2 4