ML19309A891

Environ Surveillance Rept,Jan-Dec 1979

ML19309A891
Person / Time
Site:	Brunswick
Issue date:	03/24/1980
From:	Denise Edwards CAROLINA POWER & LIGHT CO.
To:
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ML19309A884	List: ML19309A883 ML19309A891
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Text

. _. _ - _ -. - -

I N

O Environmental Surveillance Report January 1,1979 - December 31,1979 y~~ ~~.

BRUNSWICK STEAM ELECTRIC PLANT CAROUNA PCM/ER & LK?MT COMPANY 8001OIO4)68

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-Shearon Harris Energy & Environ = ental Center Carolina Power & Light Company New Hill, North Carolina l

.EtiVIRONMENTAL RADIOLOGICAL f10NITORIflG REPORT FOR BRUNSWICK STEAf1 ELECTRIC PLANT JANUARY 1, 1979, THROUGH DECEl1BER 31, 1979 i

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Prepared By:

Approved By:

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]_ i L C L.L a. u-Don H. Edwards George H. Warriner Senior Specialist - Environmental Project Specialist - Environmental l

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March 24, 1980

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• A TABLE OF CONTENTS

?.*$ *.

1.0 INTRODUCTION

1 1.1 Plant and Location.

1 1.2 Environmental Monitoring Program.

2 2.0 PROGRAM

SUMMARY

11 3.0 INTERPRETATIONS AND CONCLUSIONS.

24 3.1 Air Samples.

24 3.2 Milk Samples..

27 3.3 Vegetation.

28 3.4 Surface Water.

33 3.5 Benthos, Shrimp, Oysters, and Fish..

35 3.6 Zooplankton.

38 3.7 Bottom Sediment and Aquatic Vegetation.

38 3.8 Soil and Groundwater.

39 3.9 External Radiation Dose.

40 4.0 MISSED SAMPLES AND ANALYSES.

40 4.1 Aquatic Vegetation.

40 4.2 Fodder and Feed...

41 4.3 Milk....

41 4.4 Environmental TLDs.

41 s

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- - -. - ~, - -, ~ -

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TABLE OF CONTENTS (continued)

P.*KL 5.0 ANALYTICAL PROCEDURES...........

42 5.1 Gross Beta.

42 5.2 Tritium.

42 i

5.3 Iodine-131....................... 43 s

5.4 Strontium-89, 90.....

43 5.5 Canna Spectrometry Ge-(Li).

44 5.6 Thermoluminescent Dosimetry.

46 i

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k LIST OF TABLES Table h

1-1 Environmental Radiological Monitoring Program - Brunswick Steam Electric Planc...................

6 2-1 Environmental Radiological Monitoring Program Summary.

13 3-1 Gross Beta Air Particulate Six-Month Averages for Comparison of Preoperational Data to 1979.

25 3-2 Summary of Average Concentration and Frequency of Detection for Radionuclides in Quarterly Composite Gamma Scans for Air Particulate Filters.

26 3-3 Maximum Inhalation Exposure From Environmental Air Particulate Data.

27 i

3-4 Summary of Detectable Radionuclides for 1979 in Terrestrial Vegetation and Fodder Crops.

30 t

3-5 Summary of Radioactivity Observed in Fish, Crab, and Shrimp Samples From Discharge Canal (Second Quarter 1979) 37 3-6 Dose (mrem /yr) Computed Frem Fish, Crab, and Shrimp Samples..

37 3-7 Average Concentration and (Frequency) of Detectable Radionuclides in 1979 Bottom Sediment Samples......

39 5-1 Typical Minimum Detectable Concentrations - Ge(Li)

Camma Spectrometry.

45 t

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LIST OF FIGURES i

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1.1 Location of Radiological Environmental Monitoring 4

Stations...

1.2 Location of Radiological Environmental Monitoring Stations..

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3.1 History of Cs-137 in Milk-Station 35..........

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1.0 INTRODUCTION

The following report summarizes the Environmental Radiological Monitoring conducted for the Brunswick Steam Electric Plant during _he calendar year 1979. This is the third year in which the program's sample analyses and data interpretation have been entirely performed by Carolina Power & Light Company.

1.1 PLANT AND LOCATION The Brunswick Steam Electric Plant (BSEP) includes two units, both boiling water reactors, which are desigred to generate a total of 1,642 MW (net).

Unit 2 first achieved criticality on March 21, 1975, and went into commercial production on November 3, 1975. Unit 1 achieved criticality on November 22, 1976, and went into commercial production on March 18, 1977.

The BSEP is located in the southeastern corner of North Carolina, in Brunswick County, approximately 2.5 miles' north of Southport.

This location is near the mouth of the Cape Fear River which is a source of condenser cooler water. An intake canal extends approxi-mately three miles east of the plant to the Cape Fear River, and the discharge canal proceeds southwest and south for approximately six miles to the Atlantic Ocean. The discharge canal passes under the Intercoastal Waterway by inverted siphon, proceeds to a pumping basin at the shoreline, and is carried out into the i

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l ocean by a 2,000 ft. pipeline. Supplemental or alternate cooling methods are still under litigation.

Elevation of the plant areas ranges from sea level to 30 f t.

(MSL) and extensive swamps and marshes occur in the area.

Beaches, within 20 miles of the plant, are a source of recre-ation, and fishing and boating are popular. Within 50 miles of the plant, less than half the land is used for agriculture with small truck, dairy, and poultry farms alo'ng with crops, including corn, soybeans, and tobacco. Most of the industrial activity is in the Wilmington area (approximately 16 miles north of BSEP). Sunny Point Army Terminal is located approxi-mately 4.5 miles north of the BSEP and primarily transfers munitions, received by truck and rail, to ships. A ship channel in the Cape Fear River allows traffic to Wilmington and the Atlantic Intercoastal Waterway intercepts the ship channel at Southport.

1.2 ENVIRONMENTAL MONITORING PROGRAM The significant elements of the preoperational dose estimates were used to establish both the preoperational and operational surveillance programs.

The program that evolved during preoper-ational surveillance and was incorporated into the Brunswick Environmental Technical Specifications is detailed in Table 1-1.

Figures 1.1 and 1.2 show the environmental monitoring locations..

Below is a tabulation of the specific methods used in monitoring the various pathways of exposure to man.

Gaseous Effluent Path Submersion Dose and Thermoluminescent Dosimetry Area Other External Dose Monitors Vegetation Path Vegetation Samples Soil Samples Air Samples Milk Path Milk Samples Vegetation and Cattle Feed Samples Air Samples Inhalation Path Air Samples Liquid Effluent Path Fish and Shellfish Path Water Samples Bottom Scdiment Samples Aquatic Vegetation Samples Zooplankton Samples Benthic Organisms Fish Samples Oyster Samples Shrimp Samplee Water and Shoreline Exposure Thermolumincescent Dosimetry Area Monitors Water Samples Bottom Sediment Samples Soil and Beach Sand Drinking Water Path Ground Water Samples l

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TABLE 1-L ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM BRUNS

• DICK STEAM ELECTRIC PLANT Sample Sampling Sample Sample Type Sampling Point and Description Frequency Size Analysis Air 2-Information Center Weekly 300 cu. m.

Iodine Cartridge 5-caswell Beach at Pump Station (AC) 18-Southport near CP&L Substation 22-Sutton Plant

• 23-Projscted Maximum Annual Concentration Point - NE 24-CP&L Substation on Construction Access Road 8

45-On Site as i

Air 2-Information Center Weekly 300 cu. m.

Weekly-Cross Beta Particulate 5-Caswell Beach at Pump Station Quarterly Composite-(AP) 18-Southport near CP&L Substation Gamma and Sr-89,90 22-Sutton

• 23-Projected Maximum Annual Concentra-tion Point - NE 24-CP&L Substation on Construction Access Road 45-On Site Aquatic 29-Ocean - 0.5 Mile East of Semiannual 500 grams Canana and Sr-89,90 Vegeta-Discharge Outfall tion 30-Ocean near Discharge Outfall (AV) 31-Ocean - 0.5 mile West f Discharge Outfall 42-Lower Cape Fear River Away from Plant Discharge

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Sample Sampling Sample Sample Type Sampling Point and Description Frequency Size Analysis Ground 5-Caswell Beach at Pump Sestion Quarterly 4 liters Camma and Tritium Water 25-Southport*

(GW) 26-liighway 87 - West Side of Discharge Canal 27-liighway 211 - West Side of Discharge Canal 28-BSEP - On Site - Well #1 35-Stevens Farm Milk 35-Stevens Farm Weekly 8 Ifters Weekly--Todine (MK) 36-Tewis Farm Monthly Composite -

37-Johnson rarma Gamma and Sr-89,90 Oyster 44-Lower Cape Fear River

.iemiannual 500 grams causna (OY)

Shrimp 46-Ocean near Discharge Semiannual 500 grams Camma and Sr-89.90 (Sil)

Soil 2-Information Center Every 1hree

.500 grams Camma and Sr-89,90 (SS) 10-State Road 1525 at RR Crossing Years 18-Southport near CP&L Substation 22-Sutton Plant 23-Projected Maximum Annual Concen-tration Point - NE 24-CP&L Substation on Construction Access Road

• Control Station

1 TABLE l-1 (cont'd)

Sample Sampling Sample Sample ppe Sampling Point and Description Frequency Size Analysis Soll 27-liighway 211 - West Side of Every Three 500 grams Ga -a and Sr-89, 90 (SS)

Discharge Canal Years cont.

35-Stevens Farm 36-Lewis Farm 37-Johnson Farm

• 41-ilighway 211 - 0.25 mile East of liighway 133 38-Caswell Beach - 0.5 mile East Semiannual 500 grams C==a and Sr-89, 90 of Discharge Pipe 39-Caswell Beach at Discharge Pipe 40-Caswell Beach - 0.5 mile West of Discharge Pipe i

Surfaca 29-Ocean - 0.5 mile East of Monthly 4 liters Monthly - Cross Beta, Water Discharge Outfall Tritium and Camma (SW) 30-Ocean near Discharge Outfall Quarterly Composite-31-Ocean - 0.5 mile West of Sr-89, 90 Discharge Outfall 32-Discharge Canal 48-Intake Canal

• Terres-2-Information Center Quarterly 500 grams Ca-a trial 13-River Road at Intake Canal Vegeta-27-liighway 211 - West side *of Lion Discharge Canal (TV) 37-Johnson Farm

• External 1-Junction of Ilighways 87 and 211 Quarterly Not Applicable TLD Readout Radiation 2-Information Center (TL) 3-Junction of liighways 211 and 133 4-Standard Products Access Road of f liighway 133 near Intercoastal Waterway

• Cont rol St at ion

TABLE l-1 (cont 'd)

Sample Sampling Sample Sample Type Sampling Point anu Description Frequency Size Analysis Exte rnal 5-Caswell Beach at Pump Station Quarterly Not TLD Readout Radiation 6-Sunny Point Access Road and RR Applicable (TL)

Crossing cont.

7-Entrance to Old Brunswick Tm.n 8-Highway 87 at Boiling Springs Iake 9-Exclusion Boundary, Dirt Road which intersects Highways 87 and 133 10-State Road 1525 at RR Crossing Il-Eastern End of State Road 1525 12-Exclusion Boundary on Construction e

Access Road r-13-River Road at Intake Canal

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14-River Road Opposite I.D. Smith Residence 15-River Road and State Road 1534 16-River Road and Site of Old Brcun &

Root Construction Office 17-Southport - Fort Fisher Ferry Slip 18-Southport near CP&L Substation 19-Fort Fisher Ferry Slip 20-Kure Beach - Across from AFB Housing 21-Carolina Beach 22-Sutton Plant

• 23-Projected Maximum Annual Concentration Point - NE Zooplankton 29-Ocean - 0.5 mile East of Discharge Semiannual 10 grams Camma and Sr-89,90 (ZO)

Outfall 30-Ocean near Discharge Outfall 31-Ocean - 0.5 mile West of Discharge Outfall 42-Lower Cape Fear River Away from Plant Discharge

• Af*no t r(il 9t1t lawn

2.0 PROGRAM

SUMMARY

The purposes of the Environmental Radiological Monitoring Program are:

To measure any accumulation of radioactivity in the environment and to assess whether this radioactivity is the result of the operation of the Brunswick Plant.

To provide an evaluation of the environmental impact of operating releases of radioactive materials from the' Bruns' wick Plant.

To compare population doses from environmental sample data with corresponding doses predicted in the Final Environmental Statement.

The Brunswick Plant's preoperational radiological monitoring was conducted from July 24, 1972, until plant startup in March, 1975, and data therefrom were reported to the Nuclear Regulatory Commission in June, 1975.

The following locations are designated as the Control Locations for the respective measurements and are intended to indicate conditions away from Brunswick Plant influence:

L. V. SUTTON PLANT - 23 Mi. NNE (Sample Station 22)

Thermoluminescent Dosimetry Area Monitors Air Particulate Stmples Charcoal Cartridge Samples - Airborne I-131 s !

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4 INTAKE CANAL (Sample Stations 48 and 13)

Surface Water Samples (48) at Plant Bottom Sediment Samples (13) at River Road SOUTHPORT WATER SUPPLY (Sample Station 25)

Groundwater Samples JOHNSON FARM - 14.5 Mi. NNW (Sample Station 37)

Terrestrial Vegetation Samples i

Cattle Fodder and Feed Samples Soil Samples Milk Samples VARIABLE LOCATION AWAY FROM PIANT (Sample Station 42)

Plankton Samples Benthos Samples Aquatic Vegetation Samples VARIABLE LOCATION AWAY FROM PLANT (Sample Station 47)

Food Crop Samples No control locations are designated for shrimp, oysters, or fish.

Table 2-1 summarizes the results of the environmental radiological monitoring program for calendar year of 1979.

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i TABI.E 2-1 kJNikONMENTAL RADIOllMICAL HONITONING FN(n.EAM SUtetANY Bruumulck Steam Electric Plant Ncket hat.ers 324 and 325 Bsuumuick County, North Carolina Calender Year 1979 k Jium or Patlauay Type &

Hisi % ms All Indicator locat ion v/Bligliest Annual W an Control locations f of Blom-SampicJ ur Mcamured Total # of I)s t ec t alen e locations (2) hoe kan Nao routine (Usitt of N amiere-N amure:inents Activity Heau Distance &

'kange (2)

Bange (2)

Beported ment)

PerformeJ (HDA) (t) huge Direction Measure-mentn (3) sotton SeJiimenit G.ar e (pci/ gram dry) 12 Ocean Near co-t,0 3.00 E-2 7.46 E-2 (4/10)

Discliarge outf all 1.19 E-1 (1/2)

A!! less tiaan HDA 0

3.57 E 1.19 E-1 5.7 n!. SSW (single value)

Ocean - 0.5 m!.

West of Discisarge ku-106 2.43 E-!

8.93 E-1 (1/10)

Outfall 8.95 E-1 (!/2)

All less than MBA 0

(single value) 5.7 at. SSW (single value)

S i

ocean - 0.5 mi.

e Went of Disch.stge l

Cs-137 2.80 E-2 l.65 E-1 (2/10)

Outfall 2.20 E-1 (1/2)

All less Elian MnA 0

1 (1.09 E 2.20 E-1) 5.7 mt. SSW (single value) ocean - 0.5 mi.

West of Disclarge Ce-144 1.99 E-1 1.31 Et0 (1/10)

Outfall 1.31 Et0 (1/2)

All less than HDA 0

(single value)

(single value) 5.7 mi. SSW y,g,(6) g _ (6)

(pct / gram Jry) 9 Ha-54 6.50 E-2 7.61 E-1 (2/9)

Discliarge Canal 7.61 E-1 (2/5)

No Control 0

7.46 E 7.75 E-1 1.5 m!. WSW 7.46 E 7.75 E-l

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TAtl.E 2-1 1.NVikONHkRTAL kADIO!AM;ICAl. HONITORING PNik;kAM SutetARY Brunswicl6 Steam Electric Plant Docket Numberm 324 and 325 brunswick County, Nosth Carolina CalenJar Year 1979 McJium or Patleway Type &

Minimum All inJIcator location w/Higliest Annual Mean Control locatiosas i of Ikne-Sampled ur Hemmused Total # of Detectable locations (2)

Naane Heen Mean routine (Unit ul Hemmeere-Hemmusements Activity Hean Distance &

Range (2) kange (2)

Reported ment)

Perfoamed (HDA) (4)

Range Direction Hessure-ments (3)

Surface Water Camma N/A All less staan HDA All less than HDA All less than HpA 0

(pol /I) 60 Terscatrial('

.egetatton Gammu (pCl/ gram Jry) i7 Hn-54 6.50 E-2 1.65 E-1 (6/12)

Intornation Center 1.75 E-! (4/4) 5.10 E-2 (2/5) 0 1.43 E 2.13 E-1 1.0 al. SW l.54 E 2.13 E-3 4.82 E 5.38 E-2 e

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j; Co-60 6.50 E-2 1.08 E-l (5/12)

Information Center 1.14 E-1 (3/4)

All less tisain IS)A 0

9.43 E 1.29 E-1 1.0 ml. SW 9.98 E 1.29 E-1 River lload at Os-137 7.00 E-2 1.34 E-1 (11/12) lutake Canal 1.80 E-1 (4/4) 5.14 E-1 (5/5) 0 4.'s2 E 2.66 E-1 1.3 m! ENE 1.17 E-l - 2.66 E-3 1.64 E 1.03 Et0 River Road at 4.02 E-! (1/4) 4.59 E-1 (4/5) 0 Ce-144 2.65 E-1 3.82 E-! (4/12) lutake Canal 3.70 E-l - 4.02 E-1 1.3 m!. ENE (single value) 3.17 E 5.34 E-l Southport Near TI.D TI.ls ReaJout 3.00 E-1 9.28 E-1 (83/83)

CP&l. Substation 1.22 EiG (4/4) 8.23 E-! (4/4) 0 II )

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Footnotes:

1.

Minimum detectable concentration is calculated based on three standard deviations above background, using typical sample size in a given counting ttse. Due to counting statistics and varying volumes, occasionally lower miniswn detectable activities are achieved.

2.

Mean and range are. based on detectable measurements only. The fractions of detectable measurements at specific locations are indicated in parenthesis.

3.

Measurements in excess, at the 99.5% confidence level, of ten times the control station value or ten times the minimum detectable activity (MDA), whichever is larger.

4.

Air particulate and charcoal cartridge samples were collected every Monday. There were 53 Mondays in 1979, therefore having a total of 371 samples instead of having 364 samples.

5.

Collections of aquatic vegetation samples were attempted, but except for two cases, these attempts were unsuccessful since there were no permanent beds of same at the required sampling stations.

6.

Fish (resampled), benthos, and shrimp samples were collected from the discharge canal on May 8, 1979, for gamma analysis in addition to the technical specifications (see Section 3.5).

7.

No fodder samples were available at Station 35 (Stevens' Farm) during January, February, March, and December.

8.

Milk samples were collected every Monday. There were 53 Mondays in 1979, therefore having a passibility of 159 samples. No milk samples were available at Station 35 (Stevens' cow) from July 2 through September 10, 1979, (11 weeks) due to cow being dry. One weekly sample from Station 35 was lost in analysis (October 1) due to high fat content.

9.

No milk was available at Station 35 for the months of July and August. The September " composite" consisted of two weekly samples.

10.

No milk was available at Station 35 for the =enths of July and August. The September " composite" consisted of two weekly samples.

The month of November strontium was lost in analysis due to high fat content.

11.

Soil samples which are required to be collected at three-year intervals were last collected and analyzed in 1978.

12.

Terrestrial vegetation at Station 37 was resampled during the first quarter of 1979. Both samples were included in the statistics.

13.

Four TLDs were missing from the field, and one was ruined due to wetting.

I l

3.0 INTERPRETATION AND CONCLUSIONS 3.1 AIR SAMPLES The gross beta results for air particulate samples collected during the year of 1979 are below the preoperational levels.

All indicator station activities averaged 3.87 E-2 pCi/m compared to 9.83 E-2 pCi/m which is computed over the entire preoperational monitoring period. The 1979 average activity of control station samples also decreased to 3.81 E-2 pCi/m which is a more meaningful comparison to the indicator stations due to yearly weather conditions (amount of rainfall) and other sources of activity (fallout from nuclear testing) that occurred during the preoperational program.

Comparing the centrol station to all indicator stations shows results similar to the observations made during preoperational testing with the exception of Station 2 (Information Center) (see Table 3-11).

The second half of 1979, Station 2 revealed gross beta activity higher than the control station at a frequency of 18 out of 27 weeks. The largest difference observed was 2.1 times the control station with relative counting errors of

> 65%. Gross beta results are primarily used for screening and long-term trend and not for dose measurements. -

TABLE 3-1 Cross Beta Air Particulate Six-tionth Averages for Comparison of Preoperational Data to 1979 Data 1st 11alf '79 2nd llalf '79 1st llalf '73 2nd Half '73 1st IIalf '74 2nd Italf '74 3

Stations pCi/

AP-2 Information Center 4.3 E-2 4.1 E-2 1.5 E-2 2.9 E-2 1.7 E-1 1.1 E-1 AP-5 Caswell Beach @

Pump Station 3.6 E-2 2.7 E-2 1.5 E-2 2.8 E-2 1.6 E-1 1.1 E-1 AP-18 Southport near CP&L Substation 4.2 E-2 3.7 E-2 1.6 E-2 2.4 E-2 1.5 E-1 1.1 E-1 O

e AP-22 Sutton Plant (Control Station) 4.1 E-2 3.5 E-2 1.7 E-2 3.2 E-2 1.6 E-1 1.0 E-1 AP-23 Pf!AC 4.5 E-2 3.9 E-2 Not in Use 3.1 E-2 1.6 E-1 1.2 E-1 AP-24 CP&L Substation on Construction Access Road 3.7 E-2 3.2 E-2 Not in llse 3.4 E-2 1.7 E-1 1.1 E-1 AP-45 on Site 4.8 E-2 3.9 E-2 1.6 E-2 3.1 E-2 1.8 E-1 1.1 E-1 (2 Samples Only)

The quarterly composite gamma and strontium analysis for the air particulate samples revealed only two fission products (strontium-90 and cesium-137) and two activation products (cobalt-60 and manganese-54) for 1979. Using a t-test at 99.5% confidence level, the control station is comparable to all indicator locations as summarized in Table 3-2.

The strontium-90 and cesium-137 are not attributed to operations of Brunswick Plant since they were observed sporadically at similar concentrations throughout the preoperational surveillance period.

TABLE 3-2 Summary of Average Concentration and Frequency of Detection for Radionuclides in Quarterly Composite Gamma Scans for Air Particulate Filters Sr-90 pCi/m Indicator Locations Control First Quarter 4.45 E-4 (3/6)

.<4.35 E-4 Second Quarter 6.75 E-4 (5/6)

<5.53 E-4 Third Quarter 5.19 E-4 (1/6)

<6.03 E-4 Cs-137 pCi/m Indicator Locations Control First Quarter 1.70 E-3 (1/6)

<l.30 E-3 Second Quarter 1.97 E-3 (1/6)

<l.30 E-3 Fourth Quarter 1.08 E-3 (1/6)

<l.30 E-3 Mn-54 pCi/m Indicator Locations Control First Quarter 2.81 E-3 (1/6)

<1.29 E-3 Co-60 pCi/m Indicator Locations Control l

First Quarter 4.02 E-3

<3.00 E-3 l.

The first quarter of 1979 composites of the air particulate samples at Station 45 (on Site) revealed manganese-54 and cobalt-60 activity at the concentrations of 2.81 E-3 pCi/m and 4.02 E-3 pCi/m, respectively. These radionuclides are attributed to Brunswick operations. Using the assump-tions of Regulatory Guide 1.109, an inhalation dose to the critical organs and total body may be calculated (see Table 3-3).

The average air activity for manganese-54 and cobalt-60 at the concentrations of 1.417 E-3 and 3.085 E-3, respectively, were computed from the air particulate data including minimum detectable activity concentrations for dose calculations.

TABLE 3-3 1

Maximum Inhalacion Exposure From Environmental Air Particulate Data mrem Per Year Liver Kidney Lung Gi-LLi Total Body Adult 9.16 E-5 1.39 E-5 2.04 E-2 9.88 E-4 5.46 E-5 Teenager 1.18 E-A 1.80 E-3 2.97 E-2 8.94 E-4 7.31 E-5 Child 1.01 E-4 1.42 E-5 5.15 E-2 3.29 E-4 8.34 E-5 Infant 6.06 E-5 7.06 E-6 1.53 E-2 1.08 E-4 1.20 E-4 3.2 MILK SAMPLES Weekly milk samples analyzed radiochemically for iodine-131 revealed no measurable activity for the year of 1979.

Radiostrontium analyses of monthly composited milk samples revealed no detectable strontium-89 activity. The 1979 l-

, j i

strontium-90 activity at the average concentration of 5.80 pri/1 for the indicator stations is comparable to the control station's averaged concentration of 4.69 pCi/1.

These concentrations are comparable to the average concentra-tion of 9.0 pCi/1 observed during the preoperational period.

Gamma isotopic analyses of monthly composited milk samples reexhibited the same general trend for September and October as during the preoperational period. Milk Station 35 (Stevens Farm) continued to show higher levels of cesium-137 in milk (10 of 10 samples) averaging 30.8 pCi/1, compared to the control station (1 of 12) at the concentration of 7.23 pCi/1. Figure 3.1 details the history of cesium-137 measure-ments at the Stevens Farm during the preoperation phase in comparison to 1979 results.

The source of activity cannot be attributed to Brunswick Plant effluents. The other milk station (. Station 36) also showed levels of cesium-137 in milk (8 of 12 samples) averaging 25.8 pCi/1 for 1979. The absence of other accompanying fission products (strontium-89, higher concentrations of strontium-90, iodine-131, barium-lanthanum-140) at this station as well as the Stevens Farm (0.6 mile southeast of Brunswick Plant) eliminates the Brunswick Plant at the source of the radioactivity.

3.3 VEGETATION Terrestrial vegetation (pine needles, leaves, grass) and fodder samples (cattle feed, pasture grass) revealed.

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TABLE 3-4 Summary of Detectable Radionuclides for 1979 in Terrestrial Vegetation and Fodder Crops Terreatrial Vegetation Mean (Frequency) pC1/ gram (dry)

Mn-54 Co-60 Cs-137 Ce-144 Information Center (TV-2) 0.175 (4/4) 0.114 (3/4) 0.115 (3/4) 0.373 (1/4)

River Road @

Intake Canal (TV-13)

<0.065 (0/4)

<0.065 (0/4) 0.180 (4/4) 0.402 (1/4)

Highway 211 -

W. Side of Discharge Canal (TV-27) 0.144 (2/4) 0.098 (2/4) 0.102 (4/4) 0.377 (2/4)

Johnson Farm Control Station (TV-37) 0.051 (2/5)

<0.065 (0/5) 0.514 (5/5) 0.459 (4/5)

Fodder Crops Mean (Frequency) pCi/ gram (dry)

Co-60 Cs-137 Ce-141 Stevens Farm (70-35) 0.043 (1/8)

).198 (8/8)

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Lewis Farm (FO-36) 0.0715 (1/12) 6 131 (7/12) 0.102 (1/12)

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The terrestrial vegetation sample (pine needles) collected on January 1,1979, at Station 37 (Control Station) revealed manganese-54 and cesium-137 at the concentrations of 5.38 E-2 pCi/g (dry) and 1.03 E+0 pCi/g (dry), respectively. This station was resampled on January 22 for verification. Again.

manganese-54 and cesium 137 activity was found in pine needles at the concentrations of 4.82 E-2 pCi/g (dry) and 7.84. E-1 pCi/g (dry), respectively. Since there was no other logical source for manganese-54 and elevated concentrations of cesium-137 in comparison to the indicator stations, Station 37 appeared to be an undesirable location for a control station. The concentrations of manganese-54 and cesium-137 appeared to have been due to Brunswick's operations. Further investigation revealed that this was not necessarily the case due to:

(1) The NNW meteorological sector has the lowest annual (D/Q) deposition factor.

(2) Manganese-54 and cesium-137 concentrations released in comparison to the concentrations of other radionuclides released during this time period were equal to and considerably lower, respectively.

(3)

In comparison to previous data, the fourth quarter of 1976, the cesium-137 activity was 0.453 pCi/g (dry);

the annual average cesium-137 concentrations for 1977 and 1978 were 0.461 pCi/g (dry) and 0.606 pCi/g (dry),

respectively. These activities were attributed to nuclear testing by the People's Republic of China on,

September 26, November 17, 1976, September 17, 1977, and March 14, 1978. For the same sample location there were no elevated concentrations of cesium-137 in the other sample media (fodder, milk, etc.).

(4) "The flux of cosmic rays incident on matter activates the material through a variety of spallation or neutron capture reactions.

In spallation the incident co'mic s

radiation releases one or more nucleons, resulting in a

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residual radionuclide that is equal to or lighter than the target nuclide. Neutron capture, on the other hand, produces a radionuclide that ir one mass unit heavier than the target atom.

The target matter may be extraterrestrial or terrestrial.

Since the rate of influx of extraterrestrial dust to the earth is estimated to be about 1.0 E+7 kg per year with typical radionuclide concentrations of less than 450 pCi/kg, the extraterrestrially produced radionuclides (Be-7, Na-22, Cr-51, Mn-54, Co-57, Co-50, and Co-60) have atmospheric concentrations which are small."

Manganese-54 activity was detected in pine needles during preoperational testing at Station 2 (Information Center) at the concentration of 1National Council on Radiation Protection and Measurements, Natural Background in the United States, NCRP Report No. 45, Washington, DC 1975..

0.11 pCi/g on July 2, 1974. The occurrence and concentra-tion of manganese-54 at the control station plus the similar observation made during preoperational testing indicates a source other than the Brunswick Planc.

Cattle fodder and feed (pasture grass) sampled monthly for 1979 exhibited cesium-137 activity in 20 of 32 samples averaging 0.147 pCi/g (dry). These concentrations were lower than the preoperational average of 1.44 pCi/g.

Terrestrial vegetation samples at Station 2 (Information Center) i and Station 27 (Highway 211, West Side of Discharge Canal) l revealed low levels of manganese-54 and cobalt-60 activity.

Cobalt-60 was detected in 1 of 8 cattle feed (fodder) samples at Station 35 (Stevens farm). These radionuclides are attributed to Brunswick Plant, but the impact on the environ-ment and the dose to man are insignificant when considering that the concentrations of these radionuclides are less than three times the minimum detectable activity.

Food crops (squashes and cucumbers) sampled during the growing season (June-August) contained no fission or activa-tion products within the analytical detection limits.

3.4 SURFACE WATER Radiostrontium, gac=a isotopic, and tritium analyses of surface I

water samples during 1979 all yielded less than the minimum detectable activity.,

O The 1979 annual average of the monthly goss beta activities for all indicator stations (372 pCi/1) was approximately 66%

higher than the annual average for the control station (223 pC1/1). Similar relationships were observed in 1976, 1977, and 1978 and are comparable to that observed during the preoperational surveillance program when the all-indicator annual average was 21% higher than that of the control station. Interpretation of surface water surveillance results is complicated by two interrelated factors which are tida and sampling methods. As established during the preoperathnal surveillance program, the gross activity of surface water can vary over an order of magnitude from that in relatively fresh water to that in seawater. The salinity of plant intake canal water has been observed to vary from 3 to 30 parts per thousand as a result of tidal action in the Cape Fear estuary. The sampling method employed for the offshore ocean sampling points (Stations 29, 30, and 31) was one monthly grab sample. The intake canal (Station 48, control) was sampled by weekly grab sample composited for monthly analysis. The discharge canal (Station 32) was sampled by automatic sampler which drew six daily aliquots composited for monthly analysis. Grab samples of the offshore ocean stations were generally not taken concurrently with grab samples of the intake canal. The submerged ocean outfall of the discharge canal is designed to provide a rapid tenfold dilution within an area of about 300 by 1,000 yards. Further dilution is provided by the tidal and eddy drift currents in-l 1 '

the area which averages 0.7 feet per second. These considera-tions severely limit the usefulness of the thrJe offshore ocean surface water sampling stations as indicators of plant-contributed radioactivity. A more meaningful comparison of the data at hand can be made between the discharge canal (Station 32) annual average gross beta activity and that of the intake canal (Station 48). The 1979 annual average gross beta activity for Station 32 is 238 pCi/1, about 7%

greater than that of the intake canal. A 7% increase for average gross beta activity from the intake to the discharge canal is comparable when considering the sampling method and the salinity of the water.

3.5 BENTHOS, SHRIMP, OYSTERS, AND FISH Benthic organisms collected semiannually and analyzed for radiostrontium and gamma emitters as per technical specifica-tion closely paralleled the corresponding preoperational results. Only 3 of 8 samples taken showed strontium-90 at an average concentration of 0.091 pC1/g which compares with the preoperational data of 0.141 pC1/g in 3 of 33 samples.

Gamma analysis revealed no detectable radioactivity for 1979.

Shrimp samples collected semiannually and analyzed for radio-strontium and gamma emitters at Station 46 (Ocean and Discharge) revealed no measurable radioactivity.

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Oysters collected semiannually and analyzed for gamma emitters revealed no measurable radioactivity.

Fish samples collected quarterly and analyzed for panna ac.itters at Station 30 (Ocean near Discharge Outfall) are comparable to preoperational results. Only 1 of 4 samples taken revealed cesium-137 activity at the cancentration of 0.022 pci/g. Cesium-137 was detected in 5 of 23 samples at an average concentration of 0.17 pCi/g which ranged from 0.035 pC1/g to 0.42 pCi/g during preoperational testing.

The gamma analysis for fish samples collected first and fourth quarters of 1979 revealed no detectable radioactivity at Station 43 (Discharge Canal). Fish samples collected on April 13 (second quarter) revealed manganese-54, cobalt-38, cobalt-60, cesium-134, and cesium-137 activity. The discharge canal was resampled on May 8, 1979, which also included benthic organisms (crabs) and shrimp (even though they are l

not required by the technical specifications) in order to evaluate the worse potential dose available to man through the aquatic transport pathway using environmental sample data (see Table 3-5).

No oyster samples were available.

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TABLE 3-5 Summary of Radioactivity Observed in Fish, Crab, and Shrimp Samples From Discharge Canal (Second Quarter 1979)

Activity (pC1/g wet)

Fish Fish Crabs Shrimp Collection Date 4/13/79 5/8/79 5/8/79 5/8/79 Mn-54 0.150 0.149 0.169 0.040 Co-58 0.018 0.037

<MDA

<MDA Co-60 0.169 0.142 0.044 0.036 Cs-134 0.009

<MDA

<MDA

<MDA Cs-137 0.041

<MDA

<MDA

<MDA Ag-110m

<MDA

<MDA 0.028

<MDA The dose for the maximum exposed individual to an adult's fish, crab,.and shrimp consumption using the highst concentration in the above samples and assumption of Regulatory Guide 1.109 is summarized in Table 3-6.

TABLE 3-6 Dose (crem/yr) Computed From Fish, Crab, and Shrimp Samples Organ Dose i

Liver 0.188 Kidney 0.333 l

Gi-LLi 0.225 Total Body 0.105 These doses are based on one individual eating 46.3 pounds of fish, 11 pounds of crabs, and 11 pounds of shri=p, all in one year from the discharge canal. These doses are well 1

l within the plant design objectives.

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3.6 ZOOPLANKTON Zooplankton contcined no measurable strontium isotopes during 1979. The gamma scans revealed cobalt-60 in 2 of 8 samples at an average concentration of 0.671 pC1/g (dry).

All samples consisted of a large water fraction, and an attempt was made to separate water from the residue by filtration.

It became apparent that significant water fraction and-the relative amount of plankton per sample was highly variable. Consultation with aquatic ecologists who perform plankton inventories showed that the measures represent the state of the art.

Classification was performed by micro-scopic examination of slides; the " biomass" inventories of plankton rely upon simple mechanical separation.

These inventories represent plankton, plus other organisms such as algae, and concentrations of dissolved and suspended material once the filter has been dried.

The cobalt-60 activities observed are attributed to Brunswick's operation, but the concentrations were questionable in units of pCi/g in zooplankton. Dose assessments to man cannot be made using Regulatory 1.109 and it appears to be insignificant in comparison to other aquatic sample media.

3.7 BOTTOM SEDIMENT AND AOUATIC VEGETATION Bottom sediment samples collected semiannually at six locations are analyzed for radiostrontium and gamma emitters. There were only five radionuclides detected during 1979 (see Table 3-7)..

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TABLE 3-7 Average Concentration and (Frequency) of Detectable Radionuclides in 1979 Bottom Sediment Samples Sample Station Mn-54 Co-60 Cs-137 Ce-144 Ru-106 30

• <MDA 0.12 (1/2) 0.11 (1/2)

<MDA

<MDA 31

<MDA

<MDA 0.22 (1/2) 1.30 (1/2) 0.90 (1/2) 33 0.12 (1/2) 0.07 (2/2)

<MDA

<MDA

<MDA 34 0.04 (1/2) 0.04 (1/2)

<MDA

<MDA

<MDA

• MDA - Minimum Detectable Activity These radionuclides are attributed to Brunswick Plant. Bottom sediments are not consumed by man; therefore, no dose commit-ment estimates are given. However, it is documentation of trends in planc effluent. The concentrations observed during 1979 are comparable to activities observed in 1978.

Aquatic vegetation samples collected semiannually and analyzed for radiostrontium and gamma emitters revealed no measurable radioactivity.

3.8 SOIL AND GROUNDWATER Soil (beach sand) samples collected semiannually and analyzed for radiostrontium and gamma emitters revealed no measurable radioactivity except for one sample location. On January 3, 1979, Station 39 (Caswell Beach'at Discharge Pipes) revealed strontium-89 and cesium-134 at the concentration of 0.262 pCi/g (dry) and 0.414 pCi/g (dry), respectively. These radionuclides appear to be attributed to Brunswick Plant. However, the.

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sample collected on July 5, 1979, at Station 39 revealed no measurable radioactivity.

Groundwater samples showed no fission or activation products for the year.

3.9 EXTERNAL RADIATION DOSE Environmental dosimetry data does not show any significant changes from the corresponding data of the pas,c seven years except Station 18 (Southport near CP&L Substation), which revealed the highest annual dose (63 mrem /yr). This is approximately 487. higher than observed at the control I

station (43 mrem /yr). In January of 1979, the TLD was relocated approximately 150 feet (inside the substation) due to the power pole (where the TLD is normally placed) being removed. The higher dose readings in comparison to other ILD locations are due to crushed stones, concrete pads, and low X rays from high voltage transformers.

Excluding Station 18, Station 23 (Projected Maximum Annual Concentration Point) continued to show the highest average doses (59 mrem /yr), which has been noted in previous reports.

4.0 MISSED SAMPLES AND ANALYSES 4.1 AOUATIC VEGETATION Aquatic vegetation samples were not collected at Sample Stations 29, 30, and 31 during 1979. Collection of aquatic vegetation samples were atte=pted, but except

[

for Station 49 (Low Cape Fear River Away From Plant Discharge), these attempts were unsuccessful since there were no permanent beds of same at the required sampling stations.

4.2 F0DDER AND FEED Fodder and feed samples from Sample Station 35 were not available during January, February, March, or December 1979.

Attempts were made to collect these samples, but nothing was growing at this location.

4.3 MILK Five milk samples in July, four samples in August, and two samples in September, from Sample Station 35 were missed due to the cow being dry. Three weekly samples--January 29, April 23, and Occcb.

1,1979-were lost in analysis due to high fat content. However, gamma scans were, performed on January 29 and April 23 weekly samples which revealed iodine-131 less than minimum detectable concentrations of 6.39 pC1/1 and 4.63 pCi/1, respectively. The =ench of November strontium was lost in analysis due to high fat content.

4.4 ENVIRONMENTAL TLDs The following thermoluminescent dosimeter results were missing l

in 1979:

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Quarter Sample Station Reason 1st 10 use in field 1st 19 Due to wetting 2nd 16 Mst in field 3rd 21 Due to wetting 4th 16 Replacement badge was never sent to BSEP 5.0 ANALYTICAL PROCEDURES 5.1 GROSS BETA Gross beta radioactivity measurements are made utilizing a Beckman Widebeca II proportional counter.

The minimum detectable levels (99% confidence level) are approximately 0.82 pCi per sample.

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

Water samples are evaporated to a low volume, transferred onto a 2-inch cared stainless steel plan *chet, evaporated to total dryness, then counted on the Widebeta II with appropriate self-absorption correction, based upon sample weight.

5.2 TRITIUM Liquid samples requiring tritium analysis are first distilled. Five milliliters of the distillate are mixed l

with 10 ml of liquid scintillation cocktail and counted l

on a liquid scintillation counter for 100 minutes. The sensitivities are approximately 320 pCi/ liter at a 99%

confidence level.

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5.3 IODINE-131 Iodine-131 airborne concentrations are quantified by the Ge(Li)-ND4420 gamma spectrometr/ system. The cartridges are placed in a special tarinelli beaker and counted as a unit. If any iodine-131 is detected, each charcoal cartridge is counced individually.

Iodine-131 in milk is analyzed by use of anion exchange resin, sodium hypochlorite leach, and organic. extraction.

Iodine -

acipitated as silver iodide, collected on a tared filter, dried, and counted on a beta-gamma coincidence system. The minimum detectable concentration at time of count is less than 0.5 pCi/ sample at a 99% confidence level.

5.4 STRONTIUM-89, 90 Strontium is removed from environmental samples by the following methods:

(1) leached with dilute acid from air filters, sediment, and soil; (2) direct precipitation from 7

both fresh and saline water; and (3) absorption as Sr+~

from milk and vegetation onto a cation exchange resin column.

In all cases, strontium is precipitated as strontium carbonate, collected on a tared filter, dried, and counted on the Widebeta II.

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5.5 GAMMA SPECTROMETRY Ce-(Li)

Gamma spectrum analysis utilizes a lithium-drifced germanium detector with a thin aluminum window housed in a steel and lead shield. The analyzer system is a Nuclear Data 4420 with ND812 computer. Table 5-1 summarizes minimum detectable concentrations de. rived from instrument sensitivity, based upon a blank sample background at 99% confidence level.

Air particulate composites are fitted into a Petri dish and analyzed directly.

Liquid samples are boiled dow. to a small volume, transferred to a polyethylene beaker, and analyzed directly.

Bottom sediment and soil are dried, weighed, and then analyzed in a marinelli beaker.

After cleaning, fish samples are boiled in order to separate the flesh from the bone. Oyt:ers and shrimp are separated from any shell. These samples are then dried at 100 C and ground to produce a homogeneous mixture. These are placed in a polyethylene beaker and analyzed.

Zooplankton, benthic organisms, and terrestrial and aquatic vegetation are dried at 100 C, ground, and placed in containers to be analyzed..

e TABLE 5 Typical Minimum Detectable Concentrations Ge-Li Camma Spectrometry Air Samples Cs-1M 1.6 x 10 pCi/M Ce-137 1.6 x 10 -2 Ba-140 5.2 x 10 -2 La-140 3.2 x 10 Other Expected 1.2 x 10_2 to g

Gamma Emitters 1.2 x 10 Water Samples Cr-51 80 pC1/1 Co-58 8

Co-60 8

Mn-54 8

Cs-134 9

Cs-137 9

Ba-140 30 La-140 20 Other Expected 8 to Gamma Emitters 80 Soil and Bottom Sediments Cs-134 35 pC1/kg (dry)

Cs-137 35 Cr-51 280 Co-58 30 Co-60 30 Mn-54 30 Other Expected 30 to Gamma Emitters 300 Fish, Shrimp, Ovsters, Benthos, and Vegetation I-131 13 pCi/kg (wet)

Cs-134 14 Cs-137 13 Cr-51 110 Co-58 12 Co-60 13 Mn-54 12 Other Expected 11 to Gamma Emitters 120.

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a 5.6 THERM 0 LUMINESCENT DOSIMETRY Each area monitoring station includes a polyethylene packet, within which is an opaque polyethylene bag containing five each calcium sulfate dosimeters, 12 mm diameter by 0.4 mm thick. The packet is light, tight, and weatherproof.

A standard annealing cycle is used to prepare the dosimeters.

Following receipt from the field, each dosimeter is read under nitrogen flow, utilizing Teledyne TLD-7300 Readers.

This instrument integrates the light photons emitted from traps de-excited above 150 C.

The lower energy traps are automatically eliminated through a preheat cycle. Calibra-tion is checked monthly using dosimeters irradisted to known doses. Prior to, during, and following the measurement of each dosimeter batch, the instrument is checked through use of aa. internal constant light source as a secondary standard.

The instrument background through dark current and other electronic noise is never greater than ten mrem equivalent and is typically two mrem equivalent.

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

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