Text

Environ Surveillance Rept,1988
	ML20245E750
Person / Time
Site:	Brunswick
Issue date:	12/31/1988
From:	Shearin R; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20245E747	List: BSEP-89-0392, Forwards Environ Surveillance Rept for 1988 & Environ Surveillance Repts for Jan-June & Jul-Dec 1988; ML20245E750; ML20245E755; ML20245E759;
References
	NUDOCS 8905020124
	Download: ML20245E750 (48)
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Environmental Surveillance Report January 1,1988 - December 31,1988 BRUNSWICK sr g y3 g ggggNT y n u a ggy j

Shearon Harris Energy & Environmental Center Carolina' Power & Light Company

.. n New Hill, North Carolina ENVIRONMENTAL RADIOLOGICAL MONITORING REPORT FOR BRUNSWICK STEAM ELECTRIC-PLANT JANUARY 1 THROUGH DECEMBER-31, 1988 Reviewed by:

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fu Ronald L. Shearin Technical Specialist.- Health Physics Approved by:

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Princ(10s1 Health Physics Specialist

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TABLE OF CONTENTS L

Page 1.0

SUMMARY

1-1

- 2.0 GENERAL INFORMATION................................................

2-1 3.0 INTERPRETATIONS AND CONCLUSIONS....................................

3-1

-3.1 Air Samples..................................................

3-1 3.2 Milk Samples.................................................

3-1 3.3 Vegetation--Food Crops.......................................

3-1 3.4 Soil--Shoreline Sediment.....................................

3-2 3.5 Surface Water................................................

3-2 3.6 Fish and Invertebrates.......................................

3-2 3.7 Groundwater..................................................

3-2 3.8 External Radiation Dose (TLD)................................

3-3 4.0 ANNUAL LAND-USE CENSUS.............................................

4-1 5.0 MISSED SAMPLES AND ANALYSES........................................

5-1 5.1 Air Cartridge and Air Particulate............................

5-1 5.2 Food. Crops...................................................

5-1 5.3 M11k.........................................................

5-1 6.0 ANALYTICAL PROCEDURES..............................................

6-1 6.1 Gross Beta...................................................

6-1 6.2 Tritium......................................................

6-1 6.3 Iodine-131...................................................

6-1 6.4 Gamma Spectrometry Ge(Li)....................................

6-1 6.5 Thermoluminescent Dosimetry..................................

6-2 6.6

. EPA Laboratory Intercomparison Program.......................

6-3 6.7 Lower Limits of Detection (LLD)..............................

6-4 7.0 INDEX TO TECHNICAL SPECIFICATION REQUIREMENTS......................

7-1 1

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LIST OF TABLES Table Pg 1-1 Environmental Radiological Monitoring Program Summary............

1-2 2-1 Environmental Radiological Monitoring Program....................

2-3 3-1 Gross Beta Air Particulate Activity Averages Reoperation, 1986, 1987, 1988...................................

3-5 3-2 Historical TLD Results...........................................

3-6 4-1 Land-use Census Distances to Nearest Locations of Interest.......................

4-2 4-2 Land-Use Census Listing of Gardens Within Three Miles............................

4-3 6-1 Typical Lower Limits of Detection (a priori LLD) Ge(L1)

G ama S p e c t rome t ry...............................................

6-5 i

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I LIST OF FIGURES Figure P_ age 2-1 Locations of Radiological Environmental Direct Radiation Monitors (TLDs).......................................

2-6 2-2 Locations of Radiological Environmental Direct

. Radiation Monitors (TLDs).......................................

2-7 j

2-3 Locations of Radiological Environmental Direct Radiation Monitors (TLDs).......................................

2-8 2-4 Locations of Radiological Environmental Waterborne and Ingestion Pathway Stations..................................

2-9 2-5 Locations of Radiological Environmental Air Monitoring Stations.............................................

2-10 3-1 Plot of Air Particulate Gross Beta Activity by Date at Location 200 Versus Control Location Activity................

3-7 3-2 Plot of Air Particulate Gross Beta Activity by Date at Location 201 Versus Control Location Activity................

3-8 3-3 Plot of Air Particulate Gross Beta Activity by Date at Location 202 Versus Control Location Activity................

3-9 3-4 Plot of Air Particulate Gross Beta Activity by Date at Location 203 Versus Control Location Activity................

3-10 3-5 Plot of Air Particulate Gross Beta Activity by Date at Location 205 Versus Control Location Activity................

3-11 3-6 Plot of Air Particulate Gross Beta Activity by Date at Location 1200 Versus Control Location Activity...............

3-12 3-7 Plot of Air Particulate Gross Beta Activity by Date at Location 1201 Versus Control Location Activity...............

3-13 3-8 Plot of Air Particulate Gross Beta Activity by Date at Location 1202 Versus Control Location Activity...............

3-14 3-9 Plot of Surface Water Tritium Activity by Date at Location 401 Versus Control Location Activity................

3-15 3-10 Plot of TLD Averages for Inner and Outer Rings..................

3-16 l

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111

1.0 SLM4ARY The 19L3 Annual Radiological Environmental Operating Report for the Brunswick Steam Electric Plant (BSEP) has been prepared in accordance with Technical Specification 6.9.1.7.

This report is being submitted in accordance with Technical Specification 6.9.1.6 and applies to both BSEP Units 1 and 2 (license Nos. DPR-071 and OPR-062, respectively).

The purpose of the Radiological Environmental Surveillance Program is to measure any accumulation of radioactivity in the environment, to deter-mine whether any radioactivity detected is the result of the operation of the Brunswick Plant, and to assess the potential dose to off-site popula-tions from plant effluents detected in t h environment.

As shown in Table 1-1 over 1,250 sample analyses and measurements were taken from eight media of the Brunswick environs. No detectable activity cr activity that did not differ significantly from their respective controls were observed in all samples.

All samples analyzed met the LLD requirem r,ts as established by Tech' ical Specification 6.9.1.7.h and Table 4.12.1-1.

Overall, the radiological environmental data indicates that the Brunswick Nuclear Plant operations during 1988 had no signifi-cant impact on the environment or the public health and safety.

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FOOTNOTES TO TABLE 1-1 1.

Lower limit of detection (LLD) is calculated based on 4.66 standard deviatio6s above background using typical sample size in a given counting time.

Due to counting statistics and varying volumes, occa-siona11y lower LLDs are achieved.

See Table 6-1.

2.

Mean and range are based on detectable measurements only.

The frac-tions of detectable measurements at specific locations are indicated in parentheses.

3.

Air particulate and charcoal cartridges were collected weekly.

There were 52 weeks.in 1988 times 9 air monitor stations for a total of 468 possible samples.

A total of 464 charcoal cartridges and 465 partic-ulate filters was analyzed.

Missing samples are discussed in Section 5.

4.

Four groundwater. locations in the Brunswick Steam Electric Plant i

landfill were sampled each quarter in 1988.

A second sr.t of samples was taken in the fourth quarter, 1988.

A total of 20 groundwater samples was collected for the year.

5.

Dependent on ambient background conditions.

6.

Minimum sensitivity is approximately.4 to.8 mR per week.

Refer to Section 6.5 for additional information.

7.

Summary of gama analysis results in this report does not include the following naturally occurring isotopes since most environmental sam-ples contained some or all of these:

Be-7, K-40, T1-208, Pb-212, B1-212. Bi-214, Pb-214, Ra-226, Ac-228, and Th-234.

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1-4 i

1 2.0 GENERAL INFORMATION The Brunswick Steam Electric Plant (BSEP) consists of two boiling water.

reactors with a design rating of 821 MWe net each. Commercial production was initiated by Unit 2 on November 3,1975, and by Unit 1 on March 18, 1977.

The BSEP is located approximately 2.5 miles north of Southport, North Carolina.

This location is near the mouth of the Cape Fear River, which is the source of condenser cooling water.

The cooling water is then discharged into the Atlantic Ocean.

The plant site lies at sea level to 30 feet (MSL) surrounded by extensive swamps and marshes.

Recreational beaches are located within 20 miles of the plant.

Fishing and boating are popular activities in the area.

Within 50 miles of the plant, less than half of the land is used for agriculture.

The agricultural activities include small truck farms, cattle, and poultry farms as well as farms producing corn, soybeans, and tobacco.

Most of the industrial activity is in the Wilmington area, approximately 16 miles north of BSEP.

Sunny Point Military Ocean Termi-nal is located approximately 4.5 miles north of BSEP.

Pfizer Chemical Company, located 1.5 miles southeast r< BSEP, manufactures citric acid.

A shipping channel in the Cape Fear River intercepts the Atlantic Intra-coastal Waterway near Southport.

The sampling program developed during preoperational surveillance pro-vided the basis for the environmental monitoring program required by the BSEP Technical Specifications.

Details of this sampling program--

including sampling type, distance, and direction frorr the plant site--are listed in Table 2-1.

Maps, including the sampling locations with respect to the ple.nt, are shown in Figures 2-1 through 2-5.

Types of samples collected include air cartridge (iodine), air particulate, fish and invertebrates, food crops, shoreline sediment, surface water, and direct radiation monitoring.

4 2-1

To supplement the required environmental monitoring, additional surveil-lance of air cartridge, air particulate, food crops, bottom sediment, and groundwater was performed.

Table 2-1 lists these sample locations with the sample type, distance, and location from the plant site and is de-noted by double asterisks (**).

Groundwater samples were collected from the four BSEP landfill monitoring wells during each quarter of 1988.

Twenty groundwater samples were collected for the year.

The following is a tabulation of the specific methods used in monitoring the gaseous effluent and liquid effluent pathways of exposure to man.

Pathway of Exposure to Man Media Sampled External Dose TLD Ingestion Pathway Food Crops Fish'and Invertebrates Samples Surface Water Inhalation Air Samples Note: Shoreline sediments are collected as indicator samples.

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3.0' INTERPRETATIONS AND CONCLUSIONS 3.1 Air Samples The average of-the gross beta results for air particulate samples collected from indicator stations during 1988 was 1.60E-2 pico-3 i

curies per cubic meter (pC1/m).

The 1987 average was j

3 1.58E-2 pC1/m,

and the preoperational average' was 3

8.7E-02 pC1/m,.The airborne concentrations of gross beta activity for.1988 have returned to values similar to the preoperational-values of first quarter 1973 following a slight _ increase in first quarter 1986 ' likely.due to the Chernobyl accident.

Table 3-1 presents data depicting this effect.

Gamma scans performed on the particulate filters indicated that radionuclides indicative of plant effluents were less than LLD.

Those radionuclides. identified by these analyses were typical naturally occurring materials.

Analyses of air cartridges determined that concentrations of I-131 for all indicator and control locations were less than LLD.

l 3.2 Milk Sanples No milk sampling locations are currently identified.

3.3 Vegetation--Food Croa The technical specifications require vegetation sampling from two sectors with historically higher D/Q values and at one location l

> 15 km to serve as a control location to estimate a potential milk pathway.

Four gardens are maintained on the site boundary to satisfy the first requirement.

Four of 15 samples from the spoil pond garden (0.6 mi SSE) at the site boundary contained detectable Cs-137 (1.97E-2 to 5.25E-2 pC1/g).

None of the samples from the other three site boundary gardens had detectable concentrations of l

p 3-1

l Cs-137.

Eight of fourteen control broadleaf samples indicated similar concentrations of Cs-137 (1.91E-2 to 5.06E-2 pC1/g).

Past sampling studies have demonstrated a phenomenon of local recycling of cesium-137 originating from world-wide fallout and is not attributed to plant effluents.

3.4 Soil--Shoreline Sediment The technical specifications require semiannual samples to be col-lected from a downstream location with existing or potential recre-ational value.

The samples for Brunswick are collected from the beach near the ocean discharge location of the Caswell Beach pump-ing station.

All samples had radioactivity concentrations less than LLD.

A control location for shoreline sediment is not re-quired.

3.5 Surface Water Surface water is sampled monthly from the intake canal and at the Caswell Beach pumping station stilling pond.

The samples are ana-lyzed for tritium and gamma-emitting radionuclides.

In all sam-ples, the activities were less than LLD.

The tritium data is presented in Figure 3-9.

3.6 Fish and Invertebrates Fish and invertebrate samples are collected semiannually when in season from two locations:

(1) near the ocean discharge pipe at Caswell Beach and (2) as a control location in an area not in-fluenced t, plant operations in the Atlantic Ocean.

In all sam-ples, activities were less than LLD.

3.7 Groundwater Groundwater samples are collected and analyzed quarterly for gamma-emitting radionuclides from four wells in the BSEP landfill.

All samples had activities less than LLD.

3-2

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3.8 External Radiation Dose (TLD) l Environmental dosimetry data for 1988, although numerically de-

creasing, is not considered as demonstrating any significant 1.

changes from measurements in previous years. The averaq,e dose rate for 1988 was 0.86 mrem per week as compared to 0.92 mrem per week l

for 1987 and 0.89 mrem per week in 1986.

The preoperational data i

indicated 1.02 mrem per week (fourth quarter 1972--second quarter 1975).

The location with the highest average was at Kure Beach, North Carolina, with a 1.04 mrem / year average.

Table'3-2 provides a comparison of recent data with preoperational data.

Figure 3-10 depicts average inner and outer TLD rings for each quarter of 1988.

The calculational method used to determine net u on the environ-a mental TLDs was modified for the 1988 fourth,

er data.

This modification provides for a more accurate estir; sn of that por-tion of the TLD dose that is extraneous to the environmental expo-sure.

i l

3-3 i

l

INDEX FOR PLOTS GROSS BETA ACTIVITIES AIR PARTICULATE SAMPLES Figure 3-1 Location 200 Figure 3-2 Location 201 Figure 3-3 Location 202 Figure 3-4 Location 203 Figure 3-5 Location 205 Figure 3-6 Location 1200 Figure 3-7 Location 1201 Figure 3-8 Location 1202 TRITIUM ACTIVITY SURFACE WATER SAMPLES Figure 3-9 Location 401 TLD AVERAGES INNER AND OUTER RING LOCATIONS Figure 3-10 50 locations 3-4

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Average Dose of All TLD-Year Monitoring Locations (mrem / week) 1972 (Fourth Quarter).

0.8 1973' 1.25

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l 4.0 ANNUAL LAND-USE CENSUS Technical specifications require that a land-use census shall be con-1 ducted and identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors - of the nearest milk animal, the nearest resident, and the nearest garden of greater than 50 square meters (500 square feet) producing broadleaf vegetation.

The land-use census is I

to identify within a distance of 5 km (3 miles) the location in each of the 16 meteorological sectors of all milk animals and all gardens of greater than 50 square meters producing broadleaf vegetation.

Sampling of at least three different kinds of broadleaf vegetation may be l

performed at the site boundary in each of two different direction sectors I

with the highest D/Qs in lieu of the garden census.

The land-use census shall be conducted during the growing season at least once mr 12 months using techniques such as door-to-door survey, aerial survey, or consulting local agricultural authorities.

The 1988 BSEP land-use census was performed using aerial photographs and by performing a visual inspection from roads within a five-mile radius excluding those within the Sunny Point Military Ocean Terminal.

Addi-tional information was obtained from residents, the county extension agents, and farm supply businesses. The census was performed by the BSEP environmental staff during the period June 23, 1988, to June 27, 1988.

Forty-four gardens of greater than fif ty square meters were found to be located within three miles.

No milk animals were found.

Eight goats were found in the survey area but were not kept for milk production.

Table 4-1 summarizes the locations of the nearest meat animal, residence, and garden in each of the 16 compass sectors.

Table 4-2 summarizes the locations of gardens greater than 50 square meters which are located within a three-mile radius of the plant.

4-1

TABLE 4-1 DISTANCE TO THE NEAREST SPECIAL LOCATIONS FOR THE i

BRUNSWICK STEAM ELECTRIC PLANT (MILES)

Milk Milk Meat Sector Residence (Miles)

Cow Goat Animal Garden N

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0.8 0.9 WNW 0.9 0.9 NW 0.9 4.5 NNW 0.8 4.8 Area surveyed is within 5 miles of the plant.

Distances are estimates from composite map--approximate error 0.1 mile.

4-7

TABLE 4-2

. LISTING OF GARDENS WITHIN THREE MILES Sector Distance N

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2. 7-SW 1.0 1.0 1.1 1.5 WSW 1.1 1.3 1.5 1.6 1.6 1.6 1.9 2.2 2.7 2.8 3.0 W

0.9 1.1 1.2 2.4 2.5 WNW 0.9 0.9 1.0 NW NNW Distances are estimates from composite map--approximate error 0.1 mile.

4-3

5.0 MISSED SAMPLES AND ANALYSES 5.1 Air Cartridge and Air Particulate l

1 l

Air particulate and charcoal cartridges are collected weekly.

Nine l

air monitor stations provided for a possible total of 468 samples for 1988.

Listed below are the samples that were not available for analysis:

Location 205--week ending January 25, 1988.

The charcoal cartridge (iodine sample only) was. lost in processing upon becoming separated.

from its label Location 204--week ending November 7, 1988. A storm turned over the sampler and invalidated the samples (particulate and iodine).

Location 202--week ending November 21, 1988.

A power failure reduced the sample volumes below acceptable limits (particulate and iodine).

Location 1201--week ending November 28, 1988.

The sample malfunc-tiened during the week invalidating the' sample set (particulate and iodine).

5.2 Food Crops Samples were not available at any location for the months of Janu-ary, February, and March. Co11ards were available for the remaining

.nine months.

Mustard greens were available on the average of three months of the year at all locations.

Turnips with greens were available for an average of two months per year at each of the locations.

The availability of a food crop was used to define its respective growing season.

5.3 Milk No sampling locations are currently identified.

5-1

6.0 ANALYTICAL PROCEDURES l

6.1 Gross Beta Gross beta radioactivity measurements are made utilizing a Tennelec Low-Background Alpha / Beta Counting System..

The LLO for air par-3 ticulates is approximately 0.004 pC1/m,

Air particulate samples are mounted in 2-inch stainless steel plan-chets and counted directly.

6.2 Tritium Liquid samples requiring tritium analysis are first distilled.

Five milliliters of the distillate are mixed with ten milliliters of liquid scintillation cocktail and counted on a liquid scintillation counter for 50 minutes.

The LLO is approximately 1200 pCi/1.

6.3 Iodine-131 Iodine-131 airborne concentrations are quantified by the Ge(Li) gamma spectrometry systems. The cartridges are placed on the detec-tor and each charcoal cartridge is counted individually with an 3

approximate LLD of IE-2 pCi/m,

6.4 Gasuna Spectrometry Ge(L1)

Gamma spectrum analysis utilizes germanium or Ge(L1) detectors with thin aluminum windows housed in steel and lead shields.

The ana-lyzer system is the Nuclear Data 6685.

Table 6-1 summarizes LLD values derived from instrument sensitivity based upon a blank sample background.

Air particulate composites are placed in a Petri dish and analyzed directly.

1 6-1

l liquid samples are boiled down to a small volume, transferred to a 250-m1 polypropylene beaker with lid, and analyzed directly.

i Shoreline sediments are dried, weighed, and then analyzed in a Marinelli beaker.

Food products and broadleaf vegetation samples are weighed wet and analyzed in a Marinelli beaker.

Fish samples are cleaned, dressed, and placed in a Marinelli beaker.

for analysis.

6.5 Thermoluminescent Dosimetry Each area monitoring station includes a TLD packet, which is a-polyethylene bag containing three calcium sulfate phosphors con-tained in a Panasonic UD-814 badge.

The TLD is lighttight, and the bag is weather-resistant.

Dosimeters are machine annealed before field placement.

Following exposure in the field, each dosimeter is read utilizing a Panasonic TLD reader.

This instrument integrates the light photons emitted from traps as the dosimeter is heated above 150*C.

The lower-energy traps are automatically eliminated through a

preheat cycle.

Calibration is checked regularly using dosimeters irradiated to known doses.

Prior to the measurement of each dosimeter, the instrument is checked through use of an internal constant l'ght source as a secondary standard.

The minimum sensitivity of the dosimeters used is approximately 1 mR.

The exposure reported is corrected for exposure received in transit and during storage through the use of control dosimeters.

6-2

l l

l 6.6 EPA' Laboratory Intercomparison Program The Radiological Environmental Laboratory at the Harris Energy &

Environmental Center in New Hill, North Carolina, provides radio-analytical services for CP&L's nuclear plant environmental surveil-lance programs.

The laboratory is a participant in the EPA cross-check program and uses its performance in this program as a major I

determinant of the accuracy and precision of its analytical results.

During 1988, 69 analyses were completed on 27 samples representing 4 I

major environmental media (water, milk, food, and air filters).

Data on the known activities and the normalized standard deviations, j

using the known value, for these 69 analyses have been received from the EPA.

A comparison of the average of our reported values with the EPA known activity and its standard deviation can be summarized as follows:

i Standard Deviation (sigma)

From Known Activity Percent of Analyses 5 1 standard deviation 58 5 2 standard deviation 83 5 3 standard deviation 93 Of the 69 determinations, 5 (7 percent) fell outside the 3 sigma control limit.

In September 1988, gross beta on a sample analyzed for alpha and beta was +3.58 normalized standard deviations above the mean.

Reanalysis of the sample yielded 10.0 pCi/l and 8 pCi/l compared with a true value of 10.0 pCi/1.

Subsequent gross beta analyses yielded a +0.92 and a +1.15 normalized standard deviation.

In October 1988, 3 of 6 isotopes in a gamma analysis were above 3 times the normalized standard deviations.

These were Co-60 at

+5.89 Cs-134 at +11.55, and Cs-137 at +9.58.

Cr-51, Zn-65, and Ru-106 were all less than one normalized standard deviations from 6-3 i

i

the mean..

It was found, upon investigation that the sample had been contaminated during preparation and the importance of clean 11-ness and care was reemphasized.

Subsequent analyses of unknown samples for gamma emitters revealed no problems.

In November 1988, a sample was analyzed for gross - alpha and con,.

tained Ra-226, Ra-228, and natural uranium; and was 3.29 normalized i

standard deviations above the mean.

Investigation revealed that the wrong efficiency, 0.105 instead of 0.12, had been read from the j

i self-absorption curve.

Use of an efficiency of 0.12 would have i

resulted in 2.02 normalized standard deviations above the mean.

Gro'ss alpha analyses run after this sample yielded normalized stan-I dard deviations of -0.23 and -0.12.

6.7 Lower Limits of Detection All samples analyzed met the LLO required by Technical Specifica-tion 6.9.1.7 and Table 4.12.1-1.

Typical "a priori" LLD values for the samples analyzed are listed in Table 6-1.

I l

6-4

Table 6-1 Typical Lower Limits of Detection (a priori LLD)

Ge(L1)GammaSpectrometry Surface Water Samples *

(Freshwater T--

Isotope (LLD)

Cr-51 19 pC1/1 Mn-54 3

Co-58 3

Co-60 3

Zn-65 7

Nb-95 5

Zr-95 3

I-131' 7

Cs-134 3

Cs-137 3

Ba-140 20 La-140 7

Other Expected Gama Emitters 1 to 79 Surface Water Samples *

(Saline Water)

Isotope (LLD)

Cr-51 34 pC1/1 Mn-54 4

Co-58 4

Co-60 5

I-131 12 Cs-134 5

Cs-137 4

Ba-140 25 La-140 12 Other expected Gama Emitters 2 to 85

The sample activities were decayed from the middle of the sampling period rather than from the end of the sampling period.

This resulted in LLD values that appear higher than values calculated from the end of the period.

6-5

Table 6-1 (continued)

Air Particulate *

(Quarterly Composite)

Isotope (LLD)

Cs-134 0.002 pCi/ cubic meter Cs-137 0.001 Ba-140 0.048 La-140 0.018 Other Expected Gamma Emitters 0.001 to.040 Groundwater Samples Isotope (LLD)

Cr-51 19 pCi/1 Mn-54 3

Co-58 3

Co-60 3

Cs-134 3

Cs-137 3

Ba-140 20 La-140 7

Other Expected Gamma Emitters 1 to 79 I

The sample activities were decayed from the middle of the scmpling period rather than from the end of the sampling period.

This resulted in LLD values that appear higher than values calculated from the end of the period.

6-6

_ Table _6-1(continued)

Milk (gammascan)

Isotope (LLD)

Cr-51 27 pCi/1 Mn-54 4

Co-58 4

Co-60 6

I-131 4*

Cs-134 5*

Cs-137 5

Ba-140 16 La-140 5

Other Expected Gamma Emitters 2 to 95 Sediments (Shoreline.orBottom)

Isotope (LLD)

Cr-51 263 pCi/kg Mn-54 50 Co-58 36 Co-60 36 Cs-134 61 Cs-137 39 Other Expected Gamma Emitters 28 to 512

Radiological separation procedure decreados this value to 3.0 E-1 pCi/ liter.

6-7

i I

-Table 6-1 (continued)

Fish Isotope-(LLD)

Cr-51 124 pC1/kg Mn-54 13 Co-58 32 Co-60 38 Zn-65 62 I-131 28 Cs-134 33 Cs-137 29 Other Expected Gamma Emitters 13 to 617 Food Products and Vegetation t'

Isotope (LLD)'

l l

Cr-51 105 pCi/kg Mn-54 15 Co-58 17 Co-60 18 I-131-12 Cs-134 16 Cs-137 13 Other' Expected Gamma Emitters 8 to 306 l~

6-8 l.

1 7.0 INDEX-T0 TECHNICAL SPECIFICATION REQUIREMENTS 4

.This page provides correlation between this report and the Brunswick Technical Specifications.

SPECIFICATION REPORT SECTION 6.9.1.7 a 3.0 INTERPRETATIONS AND CONCLUSIONS 6.9.1.7'b 4.0 ANNUAL LAND-USE CENSUS 6.9.1.7 c Table 1-1 (Results of Analysis of Env. Samples) 6.9.1.7 d 2.0 PROGRAM

SUMMARY

6.9.1.7 e Figures 2-1, 2-2, 2-3, 2-4, and 2-5

'6.9.1.7 f 6.6 EPA Laboratory Intercomparison Program 6.9.1.7-g 5.0 MISSING SAMPLES AND ANALYSES 6.9.1~.7 h 6.1 Gross Beta 6.2 Tritium 6.3 Iodine-131 6.7 Lower Limits of Detection Table 6-1 Typical Lower Limits of Detection Ge(Li) Gamma Spectrometry l

I i

L l

7-1

..

ML20245E750

Text

SUMMARY

SUMMARY

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