Text

Regional Radiological Environ Monitoring Program, 841222-31
	ML20117C354
Person / Time
Site:	Limerick
Issue date:	12/31/1984
From:	; RADIATION MANAGEMENT CORP. (RMC), TELEDYNE ISOTOPES
To:	;
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ML20117C329	List: ML20117C327; ML20117C354;
References
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e-=-4 DOCKET NO.: 50-352 50-353 l

LIMERICK GENERATING STATION Units 1 and 2 Regional Radiological Environmental Monitoring Program Report ft1 22 December through 31 December 1984 I

Prepared for PHILADELPHIA ELECTRIC COMPANY 2301 Market Street Philadelphia, Pennsylvania 19101 By TELEDYNEISOTOPES 50 Van Buren Avenue Westwood, NJ 07675 And RADIATION MANAGEMENT CORPORATION Fr:cks Lock Road R D 1 Pottstown, PA 19464 I

May 1985 8505090397 850424 I

PDR ADOCK 05000352 R

POR

i DOCKET HO.: 50-352 50-353 LIMERICK GENERATING STATION Units 1 and 2 I

I Regional Radiological Environmental I

Monitoring Program Report #1 I

22 December through 31 December 1984 Prepared for I

Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101 By I

T E L E D Y r( E ISOTOPES 50 Van Buren Avenue Westwood, NJ 07675 And-Radiation Management Corporation Fricks Lock Road, R.D.

1 I

Pottstown, PA 19464 May 1985

I TABLE OF CONTENTS Page I.

Summary and Conclusions 1

I II.

Introduction 3

A.

Objectives 4

B.

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.

Atmospheric Environment 10 I

1.

Airborne 10 a.

Air Particulates 10 b.

Airborne Iodine 11 l

l 2.

Terrestrial 11 i

a.

Milk 11 l.

b.

Well Water 11 c.

Food Products 11 l

d.

Game 12 C.

Ambient Gamma Radiation 12 V.

References 13

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I 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 F-LGS Surveys I

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SUMMARY

AND CONCLUSIONS E

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Summary and Conclusions

'l This report on the Radiological Environmental Monitoring program E

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.

I Consequently, only data from samples collected during this time period are included in the report.

I concentrations Surface and drinking (potable) water samples were analyzed for of gross beta (soluble and insoluble fractions),

tritium, cnd 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 end 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

. I observed in other years.

In assessing all the data gathered for this report and compartag these I

Limerick results with preoperational data, it was evident that the operation of the Generating Station resulted in no significant radiological impact on the environment.

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INTRODUCTION f

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L LIMERICK GENERATING STATION Radiological Environmental Monitoring program F

L 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, p

Pennsylvania.

Unit No.

1 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 bank elevation rises 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 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.(23 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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I 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.

2.

To evaluate the relationship between quantities of radioactive material released from the plant and resultant E radiation doses to individuals from principal pathways of 5 exposure.

B.

Implementation 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.

In order to achieve the stated objectives, the current program includes the following analyses on samples collected:

1.

Concentrations of tritium in surface

water, drinking (potable) water, and well water.

2.

Concentrations of beta emitters in surface water, drinking (potable) water, and air particulates.

3.

Concentrations of gamma emitters in

surface, drinking (putable),

and well

water, air particulates,

milk, vegetation, game, fish, and sediment.

l 4.

Concentrations of I-131 in air and milk.

5.

Ambient gamma radiation levels at various site environs.

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E PROGRAM DESCRIPTION E

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III.

program Description A.

Sample Collection This section describes the collection methods used to obtain I

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 I

from continuous samplers located at five surface water locations (10F2,

15FS, 16B2,

24S1, and 24S2) and four drinking water locations (15F4, 15F7, 16C2, and 28F3).

One I

additional drinking water location (13H2) uns sampled monthly by a hand composite.

Control locations were

10F2, 24S1,

24S2, and 28F3.

All containers used were new unused plastic bottles, which were rinsed at least twice with source water I

prior to collection.

Fish samples comprising the flesh of two groups, catfish / bullhead (bottom feeder) and sunfish (predator),

were collected semi-annually at three locations:

I 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) a r.d 33A2 (control).

Atmospheric Environment The atmospheric environment was examined by analyzing samples of air particulates, airborne I

iodine, milk, well

unter, food products and game.

Air particulate and airborne iodine samples were collected weekly at seventeen locations (2B1,

6C1, 9C1, 1053, 1151, 13C1, I

13H4, 14S1, 15D1, 1781, 20D1, 22G1, 26B1, 29B1,

31D1, 3452, and 35B1).

Of the airborne iodine samples at these seventeen locations, eight (10S3, 11S1, 13C1, 13H4, 14S1,

22G1, 31D1, and 35B1) were analyzed for I-131.

The remaining nine I

samples 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 1 cubic foot per minute.

Milk samples were collected bi-weekly at four locations (5C1, 10B1, 22F1, and 25B1) and monthly at eight locations (36E1, I

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 I

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.

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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 g

broad leafy vegetation and root crops were collected monthly B

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 (36S1, 3S1, 551, 751, 1053, 1151,

14S1, 16S2,

18S1, 2151,

23S2, l

25S1, 26S3,

29S1, 32S1 and 34S2) near and within the site perimeter representing fencepost doses (i.e.,

at locations

=

where the deses will be greater than maximum annual off-site doses) from IGS releases; A middle ring consisting of twenty seven locations (281, 2E1, 4E1, 6C1, 7E1, 9C1, 10E1, 10F3, 13C1, 13E1, 15D1, 16F1, 17B1, g

19D1, 20D1, 20F1, 24D1, 25D1, 26B1, 28D2, 29B1, 29E1, 31D1, g

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 g

miles from the site and considered to be unaffected by LGS g

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-d eg ree s ec t o rs around 3

the

site, where estimated annual dose from LGS, if any, I

would be most significant; 3.

On hilts free from local obstructions and within sight of the vents (where practical);

4.

And near the closest dwelling to the vents in the g

prevailing downwind direction.

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One TLD set

- comprising four thermoluminescent dosimeters sealed in plastic to maintain integrity - was placed at each location in a

pVC conduit located approximately three feet above ground level.

The TLD set was exchanged monthly and sent to the laboratory for analysis.

B.

Data Interpretation The radioanalytical and direct radiation data collected prior to LGS becoming operational will be used as a baseline with which operational data may be compared.

For the purpose of this report, LGS was considered operational at initial criticality.

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.

The minimum detectable level (MDL) was defined as the tuo sigma counting statistic.

It represents the range of values into which 95%

of repeated counts of the same aliquot would fall.

For all analyses (gross beta, I-131, H-3 and gamma) an activity that was greater than or equal to the MDL was reported as " activity

[

plus/minus the MDL value".

For nongamma analyses (gross beta, I-L 131 and H-3) when an activity was less than the MDL, the result was reported as the "< the MDL value".

When an activity from a

gamma isotopic analysis was less than the MDL value it was reported as "< MDL" for the specific nuclide searched for unless a

positive occurrence had been found in other samples.

In those cases the actual MDL values were listed.

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 l

observation represents a "real" signal.

The LLD was intended as w

a before the fact estimate of a

system (including instrumentation, procedure and sample type) and not as an after the fact criteria for the presence of activity.

All analyses were designed to achieve the required LGS detection capabilities for environmental sample analysis.

For a

more detailed description of the results calculation, see Appendix D.

Results for each type of sample were grouped according to the analyses performed.

Means and standard deviations of these results were calculated.

These standard deviations represent the variability of measured results for different samples rather than E

single analysis uncertainty.

For these calculations, all results below the MDL were considered to be at the MDL.

As a result, the means were biased

high, and the standard deviations were generally biased low.

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I 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 ag day

period, resulting in some additional exceptions to the program.

The LGS annual surveys (nearest

farm, nearest residence, and nearest garden),

included in the environmental program, were not required for the t.i m e period of this report.

l In addition to this, well water, milk, sediment, game, and food W

product samples were not scheduled for collection during the reporting period.

Consequently, data from these media were not g

available for this report.

Due to a

pump malfunction, the g

surface water sample collected from location 10F2 was a grab sample.

D.

program Changes None I

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RESULTS AND DISCUSSION E

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I IV.

Results and Discussion A.

Aquatic Environment 1.

Surface Water E

Samples were taken from five locations on a monthly schedule.

Samples were collected from a continuous sampler at all five locations (10F2,

15F5, 1682,

24S1, and 24S2).

Of these I

locations, tuo (15F5 and 16B2) could be affected by Station discharge.

The following analyses were performed.

Gross Beta Samples from all locations were analyzed for concentrations of I

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, I

Appendix C) and ranged from 3 to 4 pCi/l for the soluble fraction 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 the sample from the downstream

location, 15F5, did not show significantly higher activity than the control locations.

However, the same fraction of downstream sample location 16B2 I

showed a

higher activity (2 pCi/1) than the control locations.

This higher activity is attributable to the elevated sediment content of the sample.

An activity of 2 pCi/l is still below the I

required sensitivity for this analysis and therefore this activity is not considered significant.

Gamma Spectrometry Samples from all locations were analyzed f or gamma emitting nuclides (Table C-III, Appendix C).

All nuclides searched for I

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

Tritium Samples from locations

10F2, 16B2, and 24S1 were analyzed for I

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

Positive tritium activity (130 pCi/1) was observed only at location 24S1 (control).

2.

Drinkinn (potable) Water I

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 I

I 16C2) could be affected by Station discharge.

The following analyses were performed:

Gross Beta Samples from all stations were analyzed for concentrations of g

gross beta in the soluble and insoluble fractions (Tables C-V and g C-VI, Appendix C).

The values ranged from 3 to 5 pCi/1 for the soluble fraction and from <.4 to

.5 pci/1 for the insoluble l

fraction.

No significant difference in activity levels was observed between indicator and control locations for both the W 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 I

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 l

occurring K-40, which was detected (30 pci/1 and 20 pci/l 5

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).

positive tritium activity was observed in 3 of 4 samples with 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 No sediment samples were collected from any of the three locations during the period of this report.

B.

Atmospheric Environment 1.

Airborne a.

Air Particulates continuous air particulate samples were collected from seventeen locations on a

weekly basis.

The seventeen g locations are separated into three groups: Group I represents g locations within the LGS site boundary (1053, 1151, 14S1 and 34S2),

Group II represents locations near the LGS site (2B1, 6C1, 9C1, 13C1, 15DI, 17B1, 20DI, 26B1,

29B1, 31DI, 35B1), L

k h

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-3

.028 pCi/m.

No significant. difference in activity was observed between the control and indicator stations.

In

{-

addition, concentrations detected were consistent with those observed in previous yeat 1 (Figure C-5, Appendix C).

^

Gamma Spectrometry Weekly samples were composited and analyzed monthly for gamma-emitting nuclides (Table C-X, Appendix C).

Naturally l

' 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, p

22G1, 31D1, 3581) were analyzed weei.ly 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

(

Ho samples were collected from any of the milk farms during

(

the period of this report.

1 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

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the period of this report.

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d.

Game Ho Game sample was collected during the period of this report.

C.

Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing CaSog: Tm 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 W the site boundary; a

" middle ring" of twenty-seven locations within a ten mile radius of the site; and an " outer ring" of five g locations at distances outside the ten mile radius of the site.

3 Results of TLD measurements are listed in Table C-XII, Appendix C.

All TLD measurements were below 10 mrad /std. month, with a range of 5.26 to 9.66 meads /std.

month.

Ho 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 l years (Figure C-6, Appendix C).

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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.

I 2.

Branch Technical Position Paper, Regulatory Guide 4.8, Revision 1,

November 1979.

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i RALIOLOGICAL ENVIRONMENTAL j

MONITORING REPORT

SUMMARY

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APPEt0IX A RADIOLOGICAL ENVIR0t#1 ENTAL NONITORING PROGRAtt At#AJAL SUNNARY HAME OF FACILITYs LIMERICK GENERATING STATION DOCKET NO.s 50-352 LOCATION OF FACILITY MONTGOMERY COUNTY, PA 50-353 REPORTING PERIODS 12/22-12/31/84 INDICATOR CONTROL LOCATICH WITN REQUIRED LOCATIONS LOCATIONS HIGHEST NEAN NUMBER NEDIUN OR TYPE OF NUMBER OF LOWER LIMIT NEAN HEAN HEAN STATION 8 0F HONROUTINE PATHWAY SAMPLED ANALYSES ANALYSES OF DETECTION (F )

(F)

NAME REPORTED UNIT OF MEASUREMENT) PERFORNED PERFORMED

( LLD )

RANGE RANGE RANGE DISTANCE C DIRECTION NEASUREMENTS AIR PARTICULATE GROSS BETA 34 0.01

.021

.022

.023 1033 (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 gat 1NA f7 BE-7 N/A

.11

.10

.15 9C1 (INDICATOR) 0 (15/15)

(2/2)

(t/t)

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)

(1/11 PLEASANTVIEW ROAD

(.02.09)

(.09) 1.9 NILES t#M OF SITE CS-134 0.05

< LLD

< L LD 0

CS-137 0.06

< LLD

< LLD 0

AIR IDDINE I-131 16 0.07

< LLD

< LLD 0

( PC/CU. NETER )

SURFACE WATER GROSS BETA 5

4 1.4

< LLD 2.0 16B2 (INDICATOR) 0 EPC/ LITER)

INSOLUBLE (2/2)

(1/11 LINFIELD BRIDGE

(.8-2.0)

(2.0-2.0) 1.1 NILES SSE OF SITE GROSS BETA 5

4 4

3 4

15F5 (INDICATOR) 0 SOLUBLE (2/2)

(3/3)

(1/1)

PHILADELPHIA SUBURBAN WATER CONPANY (3-4)

(3-3)

(4-4) 7.8 NILES SSE OF SITE AQUEOUS H3 3

2000

< LLD 130 130 2451 (CONTROL) 0 TOTAL (t/2)

(1/1)

LINERICK IHTAKE (130-130)

(130-130) 0.3 NILES WSW OF SITE MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE HEASURENENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES. (F)

APPENDIX A (CONTINUED)

RADIOLOGICAL ENVIRONMENTAL MCHITORING PROGRAN ANNUAL

SUMMARY

NAME OF FACILITY: LIMERICK GENERATING STATION DOCKET NO.* 50-352 LOCATION OF FACILITY: NONTGONERf COUNTY, PA 50-353 REPORTING PERIOD: 12/22-12/31/84 INDICATOR CONTROL LOCATION WITH REQUIRED LOCATIDHS LOCATIONS HIGHEST NEAN NUMBER NEDIUM OR TYFE OF NUNDER OF LOWER lit 1IT NEAN NEAN NEAN STATICH #

OF NONROUTINE PATHWAY SAMPLED ANALYSES ANALYSES OF DETECTION (F )

(F)

NAME RFf'ORTED LDt!T OF MEASUREMENT) PERFORMED PERFORMED (LLD)

RANGE RANGE RANGE DISTANCE C DIRECTION HEASUREt1ENTS

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

SURFACE WATER GAMMA 5

(PCI/ LITER)

TOTAL K-40 N/A

< LLD 30 30 24S2 (CONTROL) 0 (1/3)

(1/1)

FRICKS LOCK BOAT HOUSE (30)

(30) 0.3 HILES WSW HH-54 15

< LLD

< LLD 0

FE-59 30

< LLD

< LLD 0

CO-58 15

< LLD

< LLD 0

CD-60 15

< LLD

< LLD 0

ZH-65 30

< LLD

< LLD 0

ZR-95 30

< LLD

< LLD 0

HS-95 15

< LLD

< LLD 0

CS-134 15

< LLD

< LLD 0

CS-137 18

< LLD

< LLD 0

BA-140 60

< LLD

< LLD 0

LA-140 15

< LLD

< LLD 0

DRINKING WATER GROSS BETA 5

4

.5

< LLD

.5 13H2 (INDICATOR) 0 (PC/ LITER)

INSOLUBLE (2/4)

(1/1)

BELHONT WATER WORKS (PHILA. )

(.4.51

(.5.5) 25.5 MILES SE OF SITE GROSS BETA 5

4 4

3 5

15F4 (INDICATOR) 0 SOLUBLE (4/4)

(1/1)

PHILADELPHIA SUBURBAN WATER COMPANY (3-5)

(3-3)

(5-5) 7.8 NILES SSE OF SITE AQUEOUS H3 4

2000 170 150 240 16C2 (INDICATOR) 0 TOTAL (2/3)

(1/1)

CITIZENS HOME WATER COMPANY (100-240)

(150-150)

(240-240) 2.4 MILES SSE OF SITE NEAN AND RANGE BASED UPON DETECTABLE NEASUREMENTS ONLY. FRACTION OF DETECTABLE HEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES. (F)

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M APPENDIX A (CONTINUED 1 RADIOLOGICAL ENVIRONMENTAL NONITORING PROGRAN ANNUAL SUNNARY NAME OF FACILITY: LINERICK GENERATING STATION DOCKET NO.s 50-352 LOCATION OF FACILITY: NONTGONERY COUNTY, PA 50-353 REPORTING PERIOD: 12/22-12/31/84 INDICATOR CONTROL LOCATION WITH REQUIRED LOCATIONS LOCATIONS HIGHEST NEAN NUMBER NEDIUM OR TYPE OF NUMBER OF LOWER LIMIT NEAN HEAN NEAN STATION 8 0F NONROUTINE PATHWAY SAMPLED ANALYSES ANALYST $ OF DETECTION (F)

(F)

NAME REPORTED UNIT OF NEASURENENT) PERFORNED PERFORNED (LLD)

RANGE RANGE RANGE DISTANCE C DIRECTION NEASUREMENTS

_ _ _ _ _ _ _ = _

ORINKING WATER GANNA 5

(PCI/ LITER)

TOTAL K-40 N/A 25

< LLD 30 15F7 (INDICATOR) 0 (2/3) 11/1)

PHOENIXVILLE WATER WORKS (20-30)

(30) 5.2 NILES SSE OF SITE MH-54 15

< LLD

< LLD 0

FE-59 30

< LLD

< LLD 0

CO-58 15

< LLD

< LLD 0

CO-60 15

< LLD

< LLD 0

ZN-65 30

< LLD

< LLD 0

ZR-95 30

< LLD

< LLD 0

NB-95 15

< LLD

< LLD 0

CS-134 15

< LLD

< LLD 0

CS-137 18

< LLD

< LLD 0

BA-140 60

< LLD

< LLD 0

LA-140 15

< LLD

< LLD 0

DIRECT RADIATION TLD 48 N/A (7.58)

( 7.50 )

( 9.66 )

3101 (INDICATOR) 0 NRAD/STD. MONTH (43/43) 15/5)

(1/1)

LINCOLN SUBSTATION (5.26-9.66)

(6.70-7.50)

( 9.66 )

3.0 MILES NW OF SITE HEAN AND RANGE BASED UPON OETECTABLE HEASUREMENTS ONLY. FRACTION OF DETECTABLE HEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES. (F)

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I APPENDIX B:

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 I

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 from the Limerick Generating Station I

FIGURE B-3:

Environmental Sampling Locations at Remote Distances from the Limerick Generating Station I

I I

'I I

I I

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 to degrees each with center at Limerick off-gas vent.

Sector 36 is centered due

North, and others are numbered in a clockwise direction.

1 Radial Zone of Sampling Location (In this report, l

the radial distance from the Limerick vent for all regional stations).

S

on-site location E :

4-5 miles off-site E

A

0-1 mile off-site F :

5-10 miles off-site 3

1-2 miles off-site G : 10-20 miles off-site B

C

2-3 miles off-site H : 20-100 miles off-site D

3-4 miles off-site Z

Station's Numerical Designation within sector and zone, using 1,

2, 3...

in each sector and zone.

I l

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m M

M M

M TABLE B-II SAMPLE COLLECTION AND ANALYSIS PROGRAM TOR THE OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.

LIMERICK GENERATING STATION ENVIRONMENTAL DISTANCE C DIRECTION COLLECTION METHOD ANALYSIS C TREQUENCY STATION LOCATION DESCRIPTION TROM LGS VENT C FREQUENCY PERTORMED A.

Surface Water 10r2 Perkiomen Pumping Station 7.1 miles E Two gallon sample G.

Beta (SCI)-monthly (control) collected from a Gamma Spec-monthly continuous water Tritium-quarterly composite sampler, monthly 15F5 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 10T2 Same as 10r2 (indicator) 2451 Limerick Intake 0.3 miles SSW Same as 10T2 Same as 10r2 (control) 2452 Tricks Lock Boat House 0.3 miles WSW Same as 10F2 Same as 15F5 (control)

B.

Drinkina (Potable) Water 13H2 Belmont Water Works 25.5 miles SE Two gallon hand G.

Beta (SCI)-monthly (indicator) composited sample, Gamma Spec-monthly collected monthly 15T4 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 3.2 miles SSE Same as 15F4 Same as 15F4 (indicator) 16C2 Citizens Home Water Company 2.4 miles SSE Same as 15F4 Same as 15F4 (indicator) 28r3 Pottstown Water Authority 5.9 miles WNW Same as 15r4 Same as 15r4 (control)

TABLE B-II (cont.)

SAMPLE COLLECTION AND ANALYSIS PROGRAM FOR THE OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM, LIMERICK GENERATING STATION EMUIRONMENTAL DISTANCE E DIRECTION COLLECTION METHOD ANALYSIS E FRESUENCY STATION LOCATION DESCRIPTION FROM LGS VENT E FRESUENCY PERFORMED p.

Well Water 1131 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 S Two gallon grab Tritium-semi-annually taken from faucet Gamma Spec-semi-annually semi-annually A_

cou's Milk 36El 4.7 miles N Two gallon grab I-131-monthly sample collected Gamma Spec-quarterly from bulk tank at farm monthly SC1 2.6 miles NE Bi-weekly during I-131-bi-weekly / monthly grazing season (April Gamma Spec-monthly through November):

monthly otherwise 9Et 4.1 miles E Same as 36El Same as 36El CG1 Control 11.4 miles E Same as 36E1 Same as 36E1 11D1 3.8 miles ESE Same as 36El Same as 36E1 11El 4.9 miles ESE Same as 36E1 Same as 36El 17C2 2.5 miles S Same as 36El Same as 36El 18c1 1.9 miles S Same as 36El Same as 36E1 21Bi 1.7 miles SW Same as 36F1 Same as 36E1 22F1 Control 9.8 miles SW Same as SC1 Same as 5C1 3581 1.3 miles WSW Same as SC1 Same as SCI m

W W

M M

M

m m

e e

m e

e m

W m

W TABLE B-II (cont.)

SAMPLE COLLECTION AND ANALYSIS PROGRAM TOR THE OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM, LIMERICK GENERATING STATION ENVIRONMENTAL DISTANCE E DIRECTION COLLECTION METHOD ANALYSIS C TREQUENCY STATION LOCATION DESCRIPTION FROM LGS VENT E FREQUENCY PERFORMFJ E.

Goat's Milk 1051 1.1 mile ESE Two gallon grab I-131-bi-ueekly/ monthly sample collected Gamma Upec-monthly from bulk tank at farm, bi-ueekly during grazing season (April through November)3 monthly otherwise F.

Air Particulates/ Air Todine 2B1 Sanatoga substation 1.5 miles NME pyroximately 1 cfm G.

Beta-Weekly continuous flow Gamma Spec-monthly composite through glass fiber I-131-if necessary and charcoal filters (approx.

2" diameter) which are installed for one week and replaced 6C1 Pottstown Landing Field 2.1 miles ENE Same as 2B1 Same as 2B1 9C1 Reed Road 2.2 miles E Same as 2B1 Same as 2B1 1053 Keen Road 0.5 miles E same as 2B1 G.

Beta-weekly Gamma Spec-monthly composite I-131-weekly 1151 LGS Information Center 0.5 miles ESE Same as 251 Same as 1053 13C1 King Road 2.9 miles SE Same as 251 Same as 1053 13H4 2301 Market Street, 28.8 miles SE Same as 2B1 Same as 1053 Philadelphia (control) 1951 Longview Road 0.6 miles SE Same as 2B1 Same as 1053 15D1 Spring City Substation 3.2 miles SE Same as 2B1 Same as 2B1

TABLE B-II (cont.)

SAMPLE COLLECTION AND ANALTSIS PROGRAM FOR THE OPERATIONAL RADIOLOGICPL ENVIRONMENTAL MONITORING PROGRAM, LIMERICK GENERATING STATION ENVIRONMENTAL DISTANCE E DIRECTION COLLECTION METHOD ANALYSIS E FREQUENCY STATION LOCATION DESCRIPTION FROM LGS VENT E FREQUENCY PERTORMED F.

Air Particulates/ Air Iodine (contd.)

1781 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 1033 (control) 2651 Old Schuylkill Road 1.7 miles W Same as 2B1 Same as 2B1 2951 Iost Road 1.8 miles NW Same as 251 Same as 281 31D1 Lincoln Substation 3.0 miles NW Same as 281 Same as 1053 3452 Met. Tower 81 0.6 miles MMW Same as 2B1 Same as 2B1 3581 Pleasantvieu Road 1.9 miles HMW Same as 2B1 Same as 1053 G.

Fish 16C5 Vincent Pool Downstream of Fish flesh from tuo Gamma Spec-Semi-a..ually (indicator)

Discharge groups representing predator and bottom feeder species collected by electrofisher or other appropriate fishery gear. semi-annually 2051 Discharge Area Downstream of Same as 16C5 Same as 16C5 (indicator)

Discharge l

29C1 Pottstown Vicinity Upstream of Intake Same as 16CS Same as 16C5 (control) l M

m M

M m

W m

m m

m

E E

TABLE B-II (cont.)

SAMPLE COLLECTION AND ANALYSIS PROGRAM FOR THE OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM, LIMERICK GENERATING STATION ENVIRONMENTAL DISTANCE E DIRECTION COLLECTION METHOD ANALYSIS E FREQUENCY STATION LOCATION DESCRIPTION FROM LGS VENT E FREQUENCY PERFORMED H.

Sediment 1682 Linfield Bridge Downstream of Recently deposited Gamma Spec-Semi-annually (indicator)

Discharge sediment collected belou the waterline, semi-annually 16C4 Vincent Dan Dounstream of same as 1652 Same as 16B2 (indicator)

Discharge 33A2 Control Upstream of Same as 16B2 Same as 1682 Discharge T.

Game 2655 Fricks Lock Area Site Vicinity Game animal collected Gamma Spec-annually by hunting annually J.

Vegetation 1151 LGS Information Center 0.5 miles ESE Broad leafy vegetation Gamma Spec-monthly and root crops, monthly during the growing season (May-September)

M.

Environmental Dosimetrv-TLD 3651 Evergreen E Senatoga 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 NNE Same as 3651 Same as 3651 2E1 Laughing Waters GSC 5.1 miles NME Same as 3651 Same as 3651 351 Sanatoga Road 0.6 miles NNE Same as 3651 Same as 3651 4E1 Neiffer Road 4.6 miles NE Same as 36S1 Same as 3651 551 Possum Hollow Road 0.4 miles NE Same as 3651 Same as 3651

TABLE B-II (cont.)

SAMPLE COLLECTION AND ANALYSIS PROGRAM FOR THE OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MGNITORING PROGRAM, LIMERICK GENERATING STATION ENVIRONMENTAL DISTANCE E DIRECTION COLLECTION METHOD ANALTSIS C TREQUENCT STATION LOCATION DESCRIPTION FROM LGS VENT C FRE9UENCT PERFORMED K.

Environmental Dosimetrv-TLD (contd.1 SH1 Birch Substation 25.8 miles NE Same as 3651 Same as 3651 6C1 Pottstown Landing Field 2.1 miles ENE Same as 3651 Same as 3651 751 LGS Training Center 0.5 miles ENE Same as 3651 Same as 3651 7El Pheasant Road 4.2 miles EME Same as 36S1 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 36S1 10E1 Royersford Road 3.9 miles E Same as 36S1 Same as 3651 10F3 Trappe Substation 5.5 miles ESE Same as 3631 Same as 3651 1131 LGS 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 36S1 Same as 3651 13H3 3508 Market Street.

28.2 miles SE Same as 3651 Same as 36S1 Philadelphia (control) 14S1 Longview Road, SE Sector 0.6 miles SE Same as 3651 Same as 36S1 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 16F1 Pikeland Substation 4.9 miles SSE Same as 3651 Same as 36S1 1781 Linfield Substation 1.6 miles S Same as 3651 Same as 36S1 1851 Rail Line along 0.3 miles S Same as 36S1 Same as 36S1 Longview Road 18G1 Planebrook Substation 12.9 miles 5 Same as 3651 Same as 3651 m

m m

M M

M TABLE B-II (cont.)

SAMPLE COLLECTION AND ANALTSIS PROGRAM FOR THE OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM, LIMERICK GENERATING STATION ENVIRONMENTAL DISTANCE E DIRECTION COLLECTION METHOD ANALYSIS E FREQUENCT STATION LOCATION DESCRIPTION FROM LGS VENT E FREQUENCT PERFORMED M.

Environmental Dosimetery-TLD (contd.)

34E1 Yarnell Road 4.6 miles NNW Same as 3651 Same as 3651 3581 Pleasantville Road 1.9 miles NNW Same as 36S1 Same as 36S1 35FI Ringing Rock Substation 4.2 miles N Same as 3651 Same as 3651

TABLE B-II (cont.)

SAMPLE COLLECTION AND ANALYSIS PROGRAM FOR THE OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM, LIMERICK GENERATING STATION ENVIRONMENTAL DISTANCE C JIRECTION COLLECTION METHOD ANALYSIS E FREQUENCY STATION LOCATION DESCRIPTION TROM LGS VENT C TREQUENCY PERFORMED K.

Environmental Dosimetry-TLD (contd.)

19D1 Snouden Substation 3.6 miles S Same as 3651 Same as 3651 20D1 Ellis Woods Road 3.1 miles SSW Same as 3651 Same as 3651 20rt Sheeder Substation 5.2 miles SSW Same

.s 3651 Same as 3651 2151 Impound Basin 0.5 miles SSW Same as 3651 Same as 36S1 82G1 Manor Substation 17.6 miles SW Same as 36S1 Same as 3651 2352 Transmission Tower 0.5 miles WSW Same as 3651 Same as 3651 84D1 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 3651 25D1 Hoffecker C Keim Streets 4.0 miles WSW Same as 3651 Same as 3651 86S3 Met. Tower 82 0.4 miles W Same as 3651 Same as 3651 86B1 Old Schuylkill Road 1.7 miles W Same as 3651 Same as 3651 88D2 W.

Cedarville Road 3.8 miles W Same as 3651 Same as 3651 2951 Sector Site Boundary 0.5 miles WNW Seme as 3651 Same as 3651 8981 Yost Road 1.8 miles NW Same as 3651 Same as 3651 29E1 Prince Street 4.9 miles WNW Same as 3651 Same as 3651 31D1 Lincoln Substation 3.0 miles NW Same as 3651 Same as 3651 31D2 Poplar Substation 3.9 miles NW Same as 3651 Same as 3651 3251 Sector Site Boundary 0.6 miles NW Same as 3651 Same as 36S1 32G1 Triedensburg Substation 15.6 miles NW Same as 3651 Same as 3651 3452 Met. Tower 81 0.6 miles NNW Same as 3651 Same as 3651 m

m m

m M

W W

W M

M M

M m

m e

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m NNO N

i NNE i

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36S1 EVERGREEN & SANAT0GA RDS.

i NW NE

~

34S2 36SI 3S1 SM0M ROAD SS1 POSSUM HOLLOW ROAD 3 gg 3gg 751 LGS TRAINING CENTER f

WNW ENE 1053 KEEN ROAD SSl 1151 LGS INFORMATION CENTER j

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14S1 LONGVIEW ROAD 75l i

29SI 16S2 LONGVIEW ROAD 18S1 RAILR0AD TRACKS /LONGVIEW RD.

1053 E

20S1 LGS DISCHARGE AREA W

s 21S1 IMPOUNDING BASIN l

26 23S2 TRANSMISSION TOWER 23 S 2 e

2 4SI llSl 24S1 LGS INTAKE 18 51 24S2 FRICKS LOCK 24S2 e

l ESE 25S1 SW SECTOR 2653 MET. TOWER #2 ggw e

29S1 WNW SECTOR l

21S1 145:

3251 NW SECTOR 8

16S2 34S2 MET. TOWER #1 e

20S1 l

SW SE FIGURE B-1 ENVIRONMENTAL SAMPLING LOCATIONS j

ON-SITE OR NEAR THE LIMERICK GENERATING STATION s

SSE

\\

SITE BOUNDARY 4

S$W S

N

/

NNE NNW 15F4 PHIL. SUBURBAN WATER CO.

4 15F5 PHIL. SUBURBAN WATER C0.

l 15F7 PHOENIXVILLE WATER C0.

16B2 LINFIELD BRIDGE 36El NE 16C2 CITIZENS HOME WATER CO.

NW 35FI 16C4 VINCENT POOL 16C5 VINCENT POOL h *4 El 35B1 16F1 PIKELAND SUBSTATION 3 01 3

2BI 1781 LINFIELD SUBSTATION 6CI 3102 29Cl 2El SCI 17C2 FARM IN S SECTOR

/

I 4El ENE 18Al ANDERSON ROAD WNW f29El

.7 18C1 FARM IN S SECTOR y

298 19D1 SNOWDEN SUBSTATION SCI 2001 ELLIS WOODS ROAD

//

m 20F1 SHEEDER SUBSTATION IO F2 E

2181 FARM IN SW SECTOR l,

W 3

22F1 FARM IN SW SECTOR 28F3 25B1 2BD2 10 81 2401 PORTERS MILL SUBSTATION 25Dl?

IBl

.N 25B1 FARM IN WSW SECTOR e

Y 25D1 H0FFECKER & KEIM ST.

e 26B1 OLD. SCHUYLKILL ROAD I

ESE 28D2 W. CEDARVILLE ROAD 2.4DI WSW [

L

)

N 28F3 POTTST0WN WATER AUTHORITY 13 I O F,8

(

N 2981 Y0ST ROAD g

29Cl VINCENT POOL 10 E l 22Fl.

13Cl 29El HIGH SUBSTATION 31D1 LINCOLN SUBSTATION SE 13 El SW 3102 POPLAR SUBSTATION f 682 33A2 UPSTREAM 0F DISCHARGE 18 A l 34El YARNELL ROAD 2001 iS FS 35B1 PLEASANTVIEW ROAD S

15 F4 SSE ISF7 35F1 RINGING ROCKS SUBSTATION SSW 19 DI 1781 16CS \\

16 F 1 18 Cl 17C2 '16C4'.

ISDI to ulLE RADIUS 36El FARM IN N SECTOR 1081 FARM IN ESE SECTOR 2B1 SANAT0GA SUBSTATION 10El ROYERSFORD ROAD 2El LAUGHING WATERS 10F2 PERK!0 MEN CREEK 4E1 NEIFFER ROAD 10F3 TRAPPE SUBSTATION FIGURE B-2 SCl FARM IN NE SECTOR 11D1 FARM IN ESE SECTOR ENVIRONMENTAL SAMPLING STATIONS AT 6C1 POTTST0WN 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 1501 SPRING CITY SUBSTATION M

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L 5H1 BIR01 SUBSTATi(N

{g N

i 9G1 FARM IN E SECTOR HHW b

NNE 13H2 BELMET IIATER WORKS s

13H3 3508 MARKET ST PHil.

13H4 2301 MARKET ST PHIL.

g y(

NE 18Gl PLANEBROOK SUBSTATION NW 22G1 MANOR SUBSTATi(N 32G1 FRIEDENBERG SUBSTATION v$~

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ESE ENVIRONMENTAL SAMPLING

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13H2 STATIONS AT REMOTE DIS-i TANCES FROM THE LIMERICK

,e l H4 GENERATING STATION

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13H3 SW 4

SE 6

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I APPENDIX C:

DATA TABLES LIST OF TABI.ES AND FIGURES TABLES Table 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.

Table 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.

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

I Table C-VI concentrations of gross beta (insoluble) in drinking unter samples collected in the vicinity of Limerick Generating Station, December 1984.

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

Table C-VIII concentrations of aqueous tritium in drinking water samples collected in the vicinity of Limerick Generating Station, December 1984.

Table C-IX Concentrations of gross beta in air particulate samples collected in the vicinity I

of Limerick Generating Station, December 1984.

Table C-X Concentrations of gamma emitters in air I

particulate samples collected in the vicinity of Limerick Generating Station, December 1984.

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

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

I

I I

h 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 l

of Limerick Generating Station, December 1984.

m Fiaures 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 unter samples col-lected in the vicinity of Limerick Generating j

Station, 1982-1984.

Figure C-5 Comparison of mean monthly gross beta concentra-

[

tion in air particulate samples collected in l

the vicinity of Limerick Generating Station, l

1982-1984.

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

1 I

I

I I

TABLE C-I COHCENTRATIONS OF GROSS BETA (SOLUBLE) IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, DECEMDER. 1984 1

RESULTS IN UNITS OF PCI/L i 2 SIGMA i

C:LLECTION PERIOD 10F2 15F5 16B2 2451 2452 MEAN DEC 64 3 11 4

i1 3

11 3

i1 3

11 3

11 I

I TABLE C-II CCHCENTRATIDHS OF GROSS BETA 1 INSOLUBLE) IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, DECEMBER, 1984 I

RESULTS IN UNITS OF PCI/L i 2 SIGMA COLLECTIDH PERIOD 10F2 15F5 1682 2451 24S2 MEAN DEC 64

<.4

.8 i.4 2.0 i.5

<.4

.8 1 1.4 I

TABLE C.III CONCENTRATIONS OF GAMMA EMITTERS

IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, DECEMBER, 1984 RESULTS IN UNITS OF PCI/L i 2 SIGMA I

.OLLECTION

=.....

C PERIOD NUCLIDE 10F2 15F5 16B2 2431 2452 NEAN OTHERS

< MDL

< r1DL

< MDL

FOR TYPICAL MINIMUt1 DETECTABLE LEVELS OF HUCLIDES SEARCHED FOR AND HOT FOUND, SEE TADLE C-XV.

I I

TABLE C.IV CONCENTRATIONS OF AQUEOUS TRITIUM IH SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, DECEt1BER, 1984 i

RESULTS IH UNITS OF PCI/L i 2 SIGMA COLLECTION 10F2 15F5 16B2 24St 2452 MEAN I

.. PERIOD DEC 64

< 200

< 100 130 1 70 140 1 100 I

I

TABLE C.V C0t4CENTRATI0 tis OF GROSS BETA (SOLUBLE) IN DRItEING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATIt4G STATI0tl. DECEMBER, 1984 5

RESULTS IN UNITS OF PCI/L i 2 SIGMA COLLECTION FERIOD 13H2 15F4 15F7 16C2 28F3 MEAN I

TABLE C-VI CollCENTRATIONS OF GROSS BETA (INSOLUBLE) IN DRIfEIt1G WATER SAMPLES COLLECTED g

IN THE VICINITY OF LIMERICK GEttERATIt4G STATI0H. DECEMBER, 1984 RESULTS IN UNITS OF PCI/L 2 SIGMA COLLECTION PERIOD 13H2 15F4 15F7 16C2 28F3 MEAN

-..._____...........__....__....... __..................__......==-

DEC 64.5 i.4

<.4

.4 i.4

<.4

.4 i.1 I

TABLE C-VII CONCEllTRATIONS CF Git 1MA EMITTERS

IN DRIllKIllG WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GEllERATING STATICtle DECEt1BER, 1984 RESULTS IN UNITS OF PCI/L i 2 SIGMA COLLECTIOH PERIOD HUCLIOE 13H2 15F4 15F7 16C2 2BF3 MEAH DEC 84 K-40 20 i to

<8 30 1 10

<8

< 20 20 1 20 OTHERS

< MDL

< MDL FOR TYPICAL MINIMUM DETECTABLE LEVELS OF HUCLIOES SEARCHED FOR AND tl0T FOUt10 SEE TABLE C.XV.

I TABLE C-VIII C0tlCENTRATIONS OF AQUEOUS TRITIUM IN DRItEIttG WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, DECEMBER, 1984 RESULTS IN Ut3ITS OF PCI/L i 2 SIGNA COLLECTION PERIOD 13H2 15F4 15F7 16C2 28F3 MEAH

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

===1- - - - - ---.. _____

DEC 84

< 100 100 2 100 240 1 90 150 1 70 150 130 I

I

TABLE C-IX CCHCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, DECEMBER 1984 RESULTS IN UNITS OF PCI/CU. H 2 2 SIGMA 1984 GROUP I - LIMERICK SITE BOUNDARY LOCATIONS 8

10S3 11S1 1451 3452 00h 023 00 024

.0b4 51.025 i.bo4 021 i

=

> ^

52.021 i.004.016

.003.018 i.004.017

.003 MEAN.023

.006

.019 i.007.021 i.007.021

.010 1

1984 GROUP II - NEAR SITE LOCATIONS WEEK 8

2B1 6C1 9C1 13C1 1501 1781 51.026 i.004.022

.004.023 i.004

.024 i.004.023

.004.019 i.004 52.020 i.004.017 i.003.018 i.003

.019 i.004.019 i.004.018

.003 MEAH.023 i.008.020 i.007.021

.007.022

.007.021

.006

.019 i.001 I

I WEEK 8

2001 26B1 2981 3101 3581 I

.. = - - - -

51.028

.004.022 i.004.020 t.004

.024 i.004.022

.004 52.018 i.004.015 i.003.018

.003.019 i.004.017 i.003 MEAN.023 i.014.019 i.010

.019 i.003.022 i.007.020 i.007 1984 GROUP III - CONTROL LOCATIONS

=

WEEK 8

13H4 22G1 I'

51.026 i.004

.021 i.004 52.021

.003.021

.004 MEAN.023

.008.021 i.000 I

I I

I

I TABLE C-X CONCENTRATIONS OF GAMMA EMITTERS

IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION. DECEMBER. 1984 RESULTS IN UNITS OF PCI/CU. M 2 SIGMA i

1984 GROUP I - LIMERICK SITE BOUNDARY LOCATIONS COLLECTION PERIOD HUCLIDE 1033 1151 1451 34S2 MEAN DEC 84 BE-7

.11 i.02

.10

.02

.10 i.02

.10 i.03

.10 i.01 K-40

<.01

.02

.01

<.01

.06

.02

.03 i.05 OTHERS

< MDL

< MDL 1984 GROUP II - HEAR SITE LOCATIONS COLLECTION PERIOD HUCLIDE 2B1 6C1 9C1 13C1 15D1 17B1

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

- -= =-===-

DEC 84 BE-7

.12 i.02

.10

.02

.15

.03

.12

.03

.10 i.02

.12 i.02 K-40

<.009

<.01

<.03

<.02

.04 i.02

<.01 OTHERS

< MDL

< t1D L COLLECTION PERIOD HUCLIDE 2001 26B1 29B1 31D1 35B1 NEAN DEC 84 BE-7

.14

.03

.08 i.01

.12 i.02

.10

.03

.10 i.03

.11

.04 K-40

<.03

.03

.02

<.01

<.04

.09

.03

.05 OTHERS

< MDL

< MDL I

1984 GROUP III - CONTROL LOCATIONS COLLECTION PERIOD NUCLIDE 22G1 13H4 MEAN

-=

DEC 84 BE-7

.10 t.02

.10 i.03

.10 10 K-40

<.009

<.02

<.015 OTHERS

< MDL

< MDL s FOR TYPICAL NINIMUM DETECTABLE LEVELS OF HUCLIDES SEARCHED FOR AHD HOT FOUltD. SEE TABLE C-XV.

I I

I

I I

TABLE C-XI CONCENTRATIONS OF I-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, DECEMBER, 1984 RESULTS IN LRIITS OF PCI/CU. H i

GROUP I CROUP II GROUP III WEEK

=

5 1053 1151 1451 13Cl 31D1 3581 13H4 22G1 52

<.02

<.01

<.02

<.01

<.008

<.01 MEAN

<.02

<.03

<.02

<.01

<.02

<.009

<.02 I

I I

I 1

I I

I

I TABLE C-XII MONTHLY AMBIENT GAMMA RADIATION LEVELS IN THE VICINITY OF LIMERICK GEHERATING STATION. DECEMDER, 1984 RESULTS IN UNITS OF MRADS/STD. MONTH i 95% C. LIMITS STATICH STATION CODE EQV.MO. AVG. 12/02-01/02 CODE EQV.MO. AVG. 12/02-01/02 2Bt 7.30 i 0 7.3010.38 2001 7.39 i 0 7.3910.47 2E1 8.31 1 0 8.31 1.13 20FI 7.61 0

7.61 0.39 351 7.32 i 0 7.3211.19 21SI 7.10 1 0 7.t010.44 4Et 5.90 0

5.9010.67 22G1 7.23 0

7.23il.46 SH1 8.50 0

8.5010.52 23S2 6.85 i 0 6.85t0.90 551 7.48 0

7.48i0.52 2401 6.70 0

6.70it.21 6C1 7.84 0

7.8410.89 2501 6.54 1 0 6.54io.44 7El 8.03 2 0 8.03 0.58 25S1 7.14 1 0 7.1410.77 751 8.90 1 0 8.9011.37 26B1 7.29 0

7.2911.03 9C1 8.10 0

8.1010.47 26S3 6.84 0

6.5411.28 10El 9.05 1 0 9.05 0.60 2002 7.49 i 0 7.4910.56 5

10F3-7.16 i O 7.16 0.30 29B1 7.74 1 0 7.7410.45 1053 8.51 i 0 8.5110.87 29Et 6.81 0

6.8110.98 1151 9.00 i 0 9.00 1.67 29S1 6.96

0 6.9611.15 13C1 6.00 0

6.00io.72 3tDI 9.66 0

9.66 1.43 13E1 7.73 0

7.7110.68 3102 8.36 0

8.36 1.44 1451 7.61 i 0 7.6110.56 32G1 7.74 0

7.74it.71 ISDI 7.77 0

7.77i2.24 32S1 5.26 i 0 5.26 0.52 16F1 7.76 0

7.76 0.61 34E1 7.35 0

7.35 1.28 l

1652 6.41 0

6.41 0.86 3452 9.24 0

9.24i0.98 m

l 1781 7.98 0

7.98!0.64 35B1 8.59 0

8.5910.64 18G1 7.34 0

7.34 0.89 35F1 8.19 1 0 8.1911.29 1851 7.14 0

7.14 0.78 36S1 7.96 i 0 7.96it.19 1901 7.47 0

7.47 0.65 STATION M

CODE EQV.MO. AVG. 12/03-01/04 13 3 70 i 0 6

_I 2 I

I I

l

I I

TABLE C-XIII MEAN MONTHLY AMBIENT GAMMA RADIATION LEVELS IN THE VICINITY OF LIMERICK GENERATING STATION, DECEMBER, 1984 1

1 HO. OF SAMPLES PERIO']

PERIOD PERIOD MEAN LOCATION ANALYZED MINIMUM MAXIMUM 2 STD. DEV.

UNITS I

SITE 16 5.26 0.52 9.24 1 0.98 7.48 i 2.08 MRAD /STD. MONTH MIDDLE RIHG 27 5.90 i 0.67 9.66 i 1.43 7.63 i 1.66 MRAD /STD. MONTH OUTER RING 5

6.70 1 1.25 8.50 1 0.52 7.50 i 1.34 MRAD /STD. MCHTH I

I I

I SITE BOUNDARY RING STATI0HS-351, 5S1, 751.1053.1151,1451.1652,18St.21St.2352.25SI,

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

I MIDDLE RING STATIONS

- 2B1, 2E1, 4Et, 6C1. 7Et, 9C1,10Et,10F3.13C1.f3Et,15Dt.

- 16F1.17Bl.1901.2001,20F1,2401,2501,26B1,2802.29Bl.29E1

- 3101.3102.34El.35B1.35F1.

DUTER RING STATIONS

- 5H 1.13H3,18G1,22Gl. 32Gl.

I

~

I I

I

11 TABLE C-XIV

SUMMARY

OF COLLECTIDH DATES FOR SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, DECEMDER. 1984 W

AIR PARTICULATES GROUP I - LIMERICK SITE BOUNDARY LOCATIONS WEEK 8

1053 1131 1451 3452

=..

_===

51 12/t7-12/24/84 12/20-12/24/84 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 I

GROUP II - NEAR SITE LOCATIONS WEEK 8

2B1 6C1 9C1 13C1 15D1 1781

=__

51 12/97-12/24/84 12/17-12/24/84 12/17-12/24/84 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 ll

.E,K 8

2001 26B1 2981 3101 35B8

-- - =...==____

51 12/17-12/24/84 12/17-12/24/84 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 GROUP III - CONTROL LOCATIONS WEEK 8

13H4 22G1 5

___ =

51 12/17-12/24/84 12/17-12/24/84 52 12/24-01/02/85 12/24-12/31/84 OIR IODINE GROUP I GROUP II GROUP III WEEK 8

1053 1151 1451 13C1 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 12/17-12/24/84 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 12/24-01/02/85 12/24-12/31/84 SEIFACE WATER m

COLLECTIm1 FERIOD 10F2 15F5 1682 24S1 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 DOIK21NG WATER COLLECTIm1 PERIOD 1 912 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 Il ll ll

I TABLE C-XV TYPICAL

HINIMUN DETECTABLE LEVELS OF NUCLIDES SEARCHED FOR BUT NOT FOUND IN SAMPLES CDLLECTED IN THE VICINITY OF LIMERICK GENERATING STATI0H. DECEMBER, 1984 I

NUCLIDE AIR PARTICULATES SURFACE WATER DRINKING WATER (PCI/CU. H)

(PCI/L) 1PCI/L)

BE-7 8

9 K-40

.07 34 33 CR-51

.02 9

9 I

t24-54

.002

.9

.8 CO-57

.001

.6

.7 CO-58

.002

.9

.9 FE-59

.004 2

3 I

CO-60

.001

.9

.9 ZH-65

.003 2

3 ZR-95

.003 2

2 te-95

.002 1

1 RU-103

.002 1

1 I

RU-106

.01 7

8 AG-110N

.002 1

1 58-125

.004 2

3 TE-129H

.002

.9 1

I I-131

.008 3

3 CS-134

.001 1

1 CS-136

.006 3

3 CS-137

.001

.9 1

BA-140

.01 4

4 I

LA-140

.005 1

1 CE-141

.003 1

1 CE-144

.008 4

5 RA-226

.02 12 10 TH-228

.003 1

1

TYPICAL REFERS TO MEAN PLUS TWO STANDARD DEVIATIONS ROUNDED TO THE FIRST SIGNIFICANT FIGURE.

- A PCSITIVE CONCENTRATION WAS NEASURED IN ALL SAMPLES ANALYZED.

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i SYHOPSIS OF ANALYTICAL PROCEDURES s
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1 APPENDIX D:
SYH0pSIS OF ANALYTICAL PROCEDURES
!lE
}
The following section contains a
description of the analytical laboratory procedures along with an explanation of the analytical calculation methods used by Teledyne Isotopes for sample analysis.
il Semple Preparation and Countino Procedures I
analysis.
Several types of liquid samples are separated by filtration prior to Resulting portions are identified as soluble and insoluble.
Therefore, soluble as used in this report, is defined as that portion of a I
comple that passes through a Ho. 50 Whatman filter paper.
Insoluble is defined as that portion of a sample that is collected on Ho. 50 Whatman filter paper.
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I DETERMINATION OF GROSS ALPHA AND/OR BETA ACTIVITY IN WATER SAMPLES (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 chonical 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 g
ouopended fraction of the sample.
The filtrate is evaporated on a
g
hotplate, and the residue is transferred and dried on another planchet to represent the dissolved fraction of the sample.
I The planchets are counted for 50 minutes in a low-background gas flou proportional counter.
Calculation of activity includes a
self-adsorption correction for counter efficiency based on the weight of residue on each E
planchet.
5 CALCULATION OF THE SAMPLE ACTIVITY OR OF THE MDL N
B em N+S It It Net pCi on collection date
=
At unit voltsne or wt.
2.22 (v) (y) (DF) (E) i 2.22 (v) (y) (DF) (E)
I net activity counting error where: H
=
total counts from sample (counts) counting time for sample (min)
At
=
S background rate of counter (cpm)
=
dpm 2.22
=
PCi volume or weight of sample analyzed g
v(u)
=
chemical yield of the mount or sample counted g
y
=
decay factor from the collection to the counting date DF
=
C efficiency of the counter
=
multiples of counting error am
=
For gross alpha and gross beta calculations set y = 1 and DF 1.
=
N E
If the net activity dE' - f is equal to or is less than the counting 5
orror, the activity on the collection date is below the limits of detection end is called "less than" (L.T.) or " minimum detectable level" (MDL).
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ENVIRONMENTAL DOSIMETRY By TI definition, a thermoluminescent dosimeter (TLD) is considered one ond of a capillary tube containing calcium sulfate (Tm) powder as the
[
thermoluminescent material.
This material was chosen for its characteristic high light output, minimal thermally induced signal loss (foding),
and negligible self-dosing.
The energy response curve has been
(
ficttened by a complex multiple element energy compensating shield supplied by panasonic Corporation, manufacturer of the TLD reader.
There exists four dosimeters per station sealed in a polyethylene bag to demonstrate
[
integrity at the time of measurement, and for visualization of the sample piecement instructions.
The zero dose is determined from TLDs located in
'tho lead shield at Teledyne Isotopes, Westwood, Heu Jersey.
Follou'ing.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
{
rediation exposure.
Data are normalized to standard machine conditions by correcting
(
mcchine 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 period, and its associated error is then calculated.
A Cs-137 source is used to expose TLDs as a reference sample.
An obsorbed dose in tissue is determined using the 0.955 rad / Roentgen
{
conversion factor and dose equivalent (arem) by using a quality factor of Colculation of results and tuo sigma error
[. -Gross TLD (i) = [TLD (i)-00(i)] x CF(i) x CF(ins) x 0.955 mrad /mRoentgen ITO - Net (site 0) - [ NET (RMC 0) (0(sta) / 0(RMC 0))]
NET TLO(i) - gross TLO(i) - ITO
{
AVG =
n
[(sigma NET TLD) / n] [0(STO) / 0(EX)]
1=1 h ERROR (95% CL) = t(n-1) [ sigma NET TLD (i) //6] [0(STO) / 0(EX)]
[
E E
I Individual TLD reading corrected to standard where: Gross TLD(1)
=
instrument conditions
=
Gross reading of dosimeter i TLD(i)
Het dose obtained during exposure period g
HET TLD(i)
=
in the field g
(6.158)
Correction factor of reader CF(ins)
=
=
( g t s _1. o i z s)
External light source ELS
=
=
Zero for dosimeter i l
DO(i)
Calibration factor for dosimeter i CF(i)
=
in-Transit dose l
ITD
=
=
Mean of n dosimeters in site lead shield a
NET (site)0
=
Mean of n dosimeters in RMC lead shield HET(RMC)0 Exposure period of station (SZRO)
D ( s t t-)
=
Exposure period of RMC 0 D(RMC)0
=
AVG
=
Mean exposure per standard exposure period at a given station Humber of readings n
=
Days exposed D(EX)
=
Days in standard exposure period D(STD)
=
T-distribution (student) factor for 95% CL g
t(n-1)
=
Standard deviation of n readings of HET TLD (i) g sigma HET TLD(1)
=
The 95% confidence limit error of AVG ERROR
=
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DETERMINATION OF GAMMA EMITTING RADI0 ISOTOPES TELEDYHE ISOTOPES I
Gamma emitting radioisotopes are determined with the use of a lithium-I drifted germa.ium (Ge(Li)) and high purity germanium detectors with high resolution spectrometry in specific media, for example, air particulate
filters, charcoal
filters, milk,
water, vegetation, soil / sediments,
media, etc.
Each sample to be assayed is prepared and counted I
biological in standard geometries such as'one liter wrap-around Marinelli containers, 300 ml or 150 m1 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 activities of all detected radionuclides or the detection limits from a
list of nuclides.
The Ge(Li) systems are calibrated for each I
standard standard geometry using certified radionuclide standards traceable to the National Bureau of Standards.
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I DETERMINATION OF I-131 IH MILK AHD WATER SAMPLES BY RADIOCHEMISTRY AND LIQUID PHASE BY ANALYSIS TELEDYNE ISOTOPES This describes the radiochemical methods f or determining I-131 activity in milk and unter 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 sodium hypochlorite solution, reduced with hydroxylamine hydrochloride, and extracted into carbon tetrachloride as free iodine.
It is then back-g extracted as iodide into sodium bisulfite solution.
5 The iodide sample solution is oxidized to the free state using HaHO.
E 2
g roegent and is extracted several times into a total of 15 ml of toluene.
A 200 1
aliquot is taken for determining chemical yield by spectrophotometer.
A decolorizing agent (2-methyl-2-butene) is added to the toluene-iodine solution to form an inert molecule and to minimize l
liquid scintillation quenching.
A toluene-based liquid scintillation 5
counting solution is added to the sample, which is then analyzed by a beta-gated gamma-coincidence counting system.
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I CALCULATION OF THE SAMPLE ACTIVITY OR OF THE MDL The Sample Activity and the 2-sioma Countina Error are calculated as Follows:
S 2
N
+S N
At at Net pCi on collection date =
i At I
liter 2.22(v)(y)(DF)({}
2.22 (V)(y)(DF)(E) net activity counting error whore: H
=
total counts from sample (counts)
At counting time for sample (min)
=
background rate of counter (cpm) p
=
I 2.22 dEm
=
s pCi s
volume of sample analyzed (liters) v
=
I chemical yield of the mount or sample counted y
=
decay factor from the collection to the mid count time Dr
=
efficiency of the counter for I-131
=
Note:
Efficiency is determined by counting an 1-131 standard.
I Consequently, the branching intensity (abundance) of the I-131 gamma does not. appear in the above equation.
I calculation of the,MDL If the net activity (previously derined) is equal to or is less than a specified multiple of the background counting error, the activity on I
the collection date is bclou the limits of detection and is called L l "less than" (L.T.) or " minimum detectable level" (MDL).
The L.T.
value can be specified by stating only the counting error a i' a I
predetermined multiple (am ) of the o r. e sigma statistics.
A signa multiple (am) of 4.66 is used for calculation of'the L;T. values unle's s
another multiple such as 2.83 is specified.
I am [
B V
At thus L.T.
=
(2 22(V)(yllUP)lEl I:
q I
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DETERMINATION OF TRITIUM BY GAS COUNTING TELEDYHE ISOTOPES i
A 2
ml aliquot is oxidized and the hydrogen gas is collected in an l
activated charcoal trap.
The hydrogen is then transferred into a
previously evacuated one liter proportional counter.
Non-tritiated W
hydrogen and ultra-high purity methane is added and then counted.
Beck. rounds and standards are counted in the same gas mixture as the ocmples.
Calculation of the sample activity or the MPL:
3.234x(TV)u x VN (CPM)G - BKG ia 6G2 + 68 Net pC1 CPM xy
=
g S
unit vol.
where: (TU)N the tritium units of the standard
=
V
=
volume of 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)g the gross activity of the sample of volume V
=
and the detector background BKG the background of the detector in cpm g
=
3.234 conversion factor changing TU to pC/1 g
=
l At counting time for the sample
=
cm
=
multiple of the counting error a
CG standard deviation of the gross activity of the g
=
sample and the detector background, in cpm 6B standard deviation of the background, in epm
=
I l
If the net activity (CPM)g - BKG is equal to or is less than twice the g
counting error, the activity on the collection date is belou the limits of g
detection and is called "less than" (L.T.) or " minimum detectable level" (MDL).
I 2
2 TG
+
S thus L.T. = 2 x 3.234 x (TV)N X VNx (CPM)N x V5 uhsre:
G
=
standard deviation of the gross activity of the sample and the detector background, in cpm s tandard deviation of the background, in cpn B
=
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QUALITY CONTROL I
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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 I
a result 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 I
analyzed fell within the EPA mean and standard deviations.
Table E-I summarizes the results of all 198'4 samples.
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TAB 12 E-I INTER-LABORATORY COMPARISONS. 1984 TELE 0VNE ISOTOPES Collection Teledyne All Participants Oate Media Nuclide EPA-Results(A)
Isotopes Results(B)
Mean 2 2 s.d.
01/06 Water Sr-89 36.
t 8.7 29.3 i 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.
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.
t 3.
1-131 20.
t 10.4 16.3 i 1.7 20.
t 4.
Cs-137 20.
t 8.7 24.1 0.6 21.
t 3.
K 2720.
t235.
2503.
2555.
2665.
t246.
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 2 16.5 50.
t 8.
Ru-106 61.
t 8.7 58.7 i 33.
55.
t 9.
Cs-134 31.
t 8.7 33.3
3.
29.
t 3.
Cs-137 16.
t 8.7 19.3 i 1.7 16.
t 3.
02/10 Water H-3 2383.
t607.
2270.
t786.
2366.
t247.
03/02 Milk I-131 6.
t 1.6 5.7 t
1.7 6.
t 1.
03/16 Water Gross Alpha 5.
t 8.7 5.
t 1.3 6.
1 2.
Gross Beta 20.
t 8.7 20.
t 3.
20.
i 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.
i 6.0 19.
2 2.
Cs-137 10.
t 8.7 11.
t 3.5 12.
t 3.
04/06 Water I-131 6.
t 1.5 5.5 t
0.4 6.
t 2.
04/13 Water H-3 3508.
1728.
2660.
t342.
3461.
2288.
E E
E E
E E
E E
E E
E E
E E
E E
E E
m W
M M
M M
M e
m M
M M
M e
m TABLE E-1 (Cont.)
INTER-LA8 ORATORY COMPARISONS, 1984 TELEDYNE ISOTOPES Collection Teledyne All Participants Date Media Nuclide EPA-Results(A)
Isotopes Results(8)
Mean 2 s.d.
04/20 Water Gross Alpha 35.
t 15.2 22.
t 4.6 (D)
(Sample A)
Ra-226 4.0 2 1.04 5.4 2
3.3 (D)
Ra-228 8.3 2 2.16 2.9 1
0.6 (D) 04/20 Water Gross 8 eta 147.
t 12.7 117.
17.3 (D)
(Sample 8)
Sr-89 23.
t 8.7 18.
t 7.5 (D)
Sr-90 26.
t 2.6 22.
t 3.5 (D)
Co-60 30.
t 8.7 29.
t 6.2 (D)
Cs-134 30.
t 8.7 29, 1
4.6 (D)
Cs-137 26.
t 8.7 29.
t 6.0 (D) 05/04 Water Sr-89 25.
t 8.7 23.
2 5.
24 t 4 Sr-90 5.
t 2.6 5.0 2
0.5 5.
t 1.
05/18 Water Gross Alpha 3.
t 8.7 2.7 0.8 3.
t 1.
Gross 8 eta 6.
t 8.7 6.9 2
4.0 7
t 2.
06/01 Water Cr-51 66.
t 8.7 L.T.
90.
64 t 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.
t 11.
Cs-134 47.
t 8.7 46.
t 5.
44.
t 6.
Cs-137 37.
t 8.7 39.
i 1.7 37.
t 4.
06/08 Water H-3 3051.
2622.
3210.
1834.
3039.
t235.
06/22 Milk Sr-89 25.
t 8.7 22.
i 1.7 21.
t 5.
Sr-90 17.
t 2.6 17.
t 4.6 15.
2.
1-131 43.
t 10.4 40.
t 9.6 43.
t 4.
Cs-137 35.
t 8.7 37.
t 3.
36.
t 3.
K 1496.
1130.
1653.
t 46.
1560.
t 97.
07/20 Water Gross Alpha 6.
t B.7 3.8 2
2.4 0
Gross 8 eta 13.
t 8.7 11.3 i 3.5 0
TABLE E-1 (Cont.)
INTER-LABORATORY COMPARISONS, 1984 TELEDYNE ISOTOPES Collection Teledyne All Participants Date Media Nuclide EPA-Results(A)
Isotopes Results(8)
Mean 2 2 s.d.
07/27 Food Sr-89 25.0 t 8.7 17.
t 9.
(D)
(C)
Sr-90 20.0 t 2.6 20.
t 9.
(Dl (D,
l-131 39.0 10.4 19.
t 3.5 Cs-137 25.0 2 8.7 26.
t 11.
(D)
K 2605.0 2226.0 3027. t1183.
(D) 08/03 Water 1-131 34.0 t 10.4 31.
t 3.0 36.
t 5.
08/10 Water H-3 2817.
1617.
2930.
t 127.
2842.
1251.
08/24 Air Filter Gross Alpha 17.
t 8.7 16.
i 1.7 17.
t 3.
Gross 8 eta 51.
t 8.7 47.
3.
52.
t 6.
Sr-90 18.
t 2.4 18.
1 1.7 17.
t 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.
t 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.
t 0.0 5.
t 2.
Gross 8 eta 16.0 2 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.
8.7 23.
2 10.4 20.
t 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.
t356.
2720.
t 531.
2814.
1213.
10/22 Water Gross Alpha 14.
t 8.7 11.
t 1.7 13.
t 4.
(Sample A)
Water Gross 8 eta 64.
i 8.7 65.
t 10, 60.
t 7.
(Sample B)
Sr-89 11.
t 8.7 9.
t 3.5 11.
t 4.
Sr-90 12.
t 2.6 13.
t 3.
13.
1 3.
Co-60 14.
t 8.7 19.
t 3.5 16.
t 2.
Cs-134 2
2 8.7 L.T.
5.
3.
t 2.
Cs-137 1
i 8.7 17.
t 7.5 16.
1 2.
m W
W W
W W
M M
M M
M M
M W
W W
m W
W W
W W
W W
W W
W W
W W
W W
TABLE E-I ( Co n t. )
INTER-LABORATORY COMPARISONS, 1984 TELEDYNE ISOTOPES Collection Teledyne All Participants Date Media Nuclide EPA-Results(A)
Isotopes Results(B)
Mean i 2 5.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.
t 2.
1-131 42.
t 10.4 34.
t 9.6 40.
t 5.
Cs-137 32.
t 8.7 32.
t 12, 32.
3.
K 1517 1131.
1370.
t 52.7 1498.
2143.
11/16 Water Gross Alpha 7.0 t 8.7 7.3 t 1.7 7.
t 2.
Gross Beta 20.0 t 8.7 21.7 2 1.7 21.
t 3.
11/23 Air Filter Gross Alpha 15.
t 8.7 15.
t 1.7 (D)
Gross Beta 52.
t 8.7 54 t
3.5 (D)
)
Sr-90 21.
t 2.6 23.
t 3.
(D)
Cs-137 10.
t 8.7 9.
t 4.6 (D) 12/07 Water I-131 36.
t 10.4 36.
t 6.9 36.
t 5.
12/14 Water H-3 3182. 2624 3523.
2868.
3206.
t236.
Notes (A)
EPA Results-Expected laboratory precision (3 sigma). Units are pCi/f for water, urine, and milk except K is in mg/1.
Units are total pC1 for air particulate filters.
(8)
Teledyne Results - Average i three sigma. Units are pC1/f for water, urine, and milk except K is in mg/f. Units are total pCi for air particulate filters.
(C)
Units for food analysts are pC1/kg.
(D)
Results were not released at time of report.
,s x
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i I LGS SURVEY
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I APPENDIX F:
LGS SURVEYS The environmental program includes a requirement for three surveys to be performed during the growing season.
These include a nearest farm, a residence, and a nearest garden survey.
The i nformation obtained I
nearest from the surveys is to be included in the annual report.
However, since the time period of this report does not include the growing season, survey information is not presented here.
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,,m.,
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ML20117C354

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ML20117C354

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