Text

Radiological Environ Monitoring Program,1986. W/870430 Ltr
	ML18150A072
Person / Time
Site:	Surry
Issue date:	12/31/1986
From:	Laransino C, Stewart W; TELEDYNE ISOTOPES MIDWEST LABORATORY, VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	87-250, NUDOCS 8705050274
	Download: ML18150A072 (142)
	v • d • e

1111, ~- ... : _ }' - ,.

e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 30, 1987

"\\'. L. STEWABT

'"ICE PRESIDE~T Nt:CLEAB OPERATIONS U. S. Nuclear Regulatory Commission Serial No.87-250 Attn: Document Control Desk NO/PML:vlh Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Attached is the Annual Radiological Environmental Operating Report for Surry Power Station for the calendar year 1986 as required by Technical Specification 6.6.B.2.

Very truly yours,

~/{~

,w. L. Stewart

[;/ Attachment cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219 Carolyn Schreider Department of Health 109 Governor Street Richmond, Virginia 23219

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FOR 1986 Prepared by VIRGINIA ELECTRIC AND POWER COMPANY and TELEDYNE ISOTOPES

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SURRY POWER STATION January 1, 1986 through December 31, 1986

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TABLE OF CONTENTS SECTION TITLE PAGE I. I NT RO DUCT I ON ********.************************** * ************** 1 I I. SAMPLING AND ANALYSIS PROGRAM ................................ 4 I I I. PROGRAM EXCEPTIONS .......................................... 16 IV.

SUMMARY

AND DISCUSSION OF ANALYTICAL RESULTS ******.********* 22 A. AIRBORNE EXPOSURE PATHWAY *************.**********..***** 23

1. Air Iodine/Particulates ***************************.* 23 B. WATERBORNE EXPOSURE PATHWAY ***************************** 40

1. River Water ************.************************* **** 40

2. Wel 1 Water ****************************************** 49 C. AQUATIC EXPOSURE PATHWAY ................................ 52

1. Silt ***.*************************************.****** 52

2. Shoreline Sediment. ................................. 61 D. INGESTION EXPOSURE PATHWAY ******************.*********** 64

1. Mi 1k . ............................................... 64

2. Aquatic Biota .************************************** 70

3. Food Products *************************************** 81 E. DIRECT RADIATION EXPOSURE PATHWAY *********************** 84

1. TLD Dosimeters *************************************** 84 V. CONCLUSION ............ 0 ********** I ************** I **********

91 VI. 1986 LAND USE CENSUS **************************************** 96 VI I. SYNOPSIS OF ANALYTICAL PROCEDURES ************************** 100 VI I I.

EPA I NTERLABORATORY COMPARISON PROGRAM ********************* 112 IX. REFERENCES.*.*...******..*.********************************* 134

TABLE OF CONTENTS (Cont)

LIST OF FIGURES

1. LAND BASED ENVIRONMENTAL SAMPLING LOCATIONS ***.*.*******.*.* 10

2. RIVER BASED ENVIRONMENTAL SAMPLING LOCATIONS ***********.**** 11

3. TLD LOCATIONS ..*..**...************************************* 12

4. LAND USE CENSUS MAP ......................................... 99 ii

.L

FORWARD This report is submitted as required by Technical Specification 6.6.B.2, Annual Radiological Environmental Operating Report for Surry, Units 1 and 2, Virginia Electric and Power Company Docket Nos. 50-280 and 50-281 .

;;i

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I. INTRODUCTION The operational radiological environmental monitoring program conducted for the year 1986 for the Surry Power Station is provided in this report.

The results of measurements and analyses of data obtained from samples collected from January 1, 1986 through December 31, 1986 is summarized.

A. The Surry Power Station of Virginia Electric and Power Company is located on the Gravel Neck peninsula adjacent to the James River, approximately 25 miles upstream of the Chesapeake Bay. The site consists of two units, each with pressurized water reactor (PWR) nuclear steam supply system and turbine generator furnished by Westinghouse Electric Corporation. Each unit is designed with a gross electrical output of 822.6 megawatts electric (MWe). Unit 1 achieved commercial operation on December 22, 1972, and Unit 2 on May 1, 1973.

B. The United States Nuclear Regulatory Commission (USNRC) regulations (10CFR50.34a) require that nuclear power plants be designed, con-structed, and operated to keep levels of radioactive material in effluents to unrestricted areas as low as reasonably achievable (ALARA). To ensure these criteria are met, the operating license for Surry Power Station includes Technical Specifications which

govern the release of radioactive effluents .. Inplant monitoring is used to determine that these predetermined release limits are not exceeded. As a precaution against unexpected or undefined 1

environmental processes which might allow undue accumulation of radioactivity in the environment, a program for monitoring the plant environs is also included in Surry Power Station Technical Specifications.

C. Virginia Electric and Power Company is responsible for collecting the various indicator and control (background) environmental s.amples.

Teledyne Isotopes is responsible for sample analysis and the submission of reports of radioanalyses. The results are used to determine if changes in radioactivity levels could be attributable to station operations. Measured values are compared with background levels, which vary with time due to such external events as cosmic ray bombardment, weapons test fallout, and seasonal variations of naturally occurring isotopes. Data collected prior to the plant operation is used to indicate the degree of natural variation to be expected. This preoperational data is compared with data collected during the operational phase to assist in evaluating the radiological impact of the plant operation.

D. Occasional samples of environmental media show the presence of man-made isotopes. As a method of referencing the measured radio-nuclide concentrations in the sample media to a dose consequence to man, the data may be compared to the reporting level concentrations listed in the USNRC Regulatory Guide 4.8 and Table 4.9-4 of Surry Power Station's Technical Specifications. These concentrations are based upon the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion of 11 As Low As Is Reasonably Achievable".

2

E. This report documents the results of the Radiological Environmental Monitoring Program for 1986 and satisfies the following objectives of the pro gr am.

1. To provide measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of the maximum exposed members of the public resulting from the station operation.

2. To supplement the radiological effluent monitoring program by verifying that radioactive releases are within allowable limits.

3. To identify changes of radioactivity in the environment.

4. To verify that the plant operations have no detrimental effect on the health and safety of the public.

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II. SAMPLING AND ANALYSIS PROGRAM A. Sampling Program

1. Table 1 summarizes the sampling program for Surry Power Station during 1986. The symbols on this table refer to the sample locations shown on Figures 1 through 3. Figure 1 indicates the locations of the land based samples while Figure 2 shows the locations of the river based samples. The small triangles in Figure 3 designate the position of environmental thermoluminescent dosimeters (TLDs) at the site boundary.

2. For routine TLD measurements, two dosimeters made of CaS04:Dy in a teflon card are deployed at each sampling location. Several TLDs are co-located with NRC and Common-wealth of Virginia direct radiation recording devices.

These are indicated as 11 co-location 11 samples.

3. In addition to the Radiological Environmental Monitoring Program required by Surry Technical Specifications, Virginia Electric and Power Company splits samples with the Corrrnon-wealth of Virginia. All samples listed in Table 1 are collected by Vepco personnel except for those labeled state split. All samples are shipped to Teledyne Isotopes in Westwood, New Jersey.

4. All samples listed in Table 1 are taken at indicator loca-tions e*xcept those labeled 11 control 11

4

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B. Analysis Program

1. Table 2 summarizes the analysis program conducted by Teledyne Is~topes for Surry Power Station during 1986 .

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T/\BL E 1 VIRGINIA POWER - SURRY - 1986 ll/\OIOLOGICI\L SAMPLING SlATION lll~TI\NCE AND IJIRECllON FHOM UNlr NO.

~AMPLE lJISl/\NCE COLLECTION MED IA LOCATION ST/\llON MILES DIRECTION DEGREES rnEQUENCY REMARKS Environmental Control ( 00) Quarterly On site*

( TllJ IS) West North West 292* Quarterly Site Boundary Surry Station Discharge North North West 18~ l

( 04)

0. 1 7 0.6 0.4 WNW NW NNW 309° 330° Quarterly Quarterly Site Boundary Site Boundary North ( 05) 0.33 N 357* Quarterly Site Boundray North North East ( 06) 0.28 NNE 22* Quarterly Site Boundary North East ( 0 7) 0.31 NE 45* Quarterly Sile Boundary East North East 0.43 ENE 6 fl 0

Quarterly Site Boundary East (Exclusion) fg~l 0.31 E 9 o* Quarterly On site West ( 1 0) 0.40 w 270° Quarterly Site Boundary West South West ( 11 ) 0. 4 5 WSW 250° Quarterly Site Boundary South West ( 12) 0.30 SW 225° Quarterly Site Boundary South South West ( I 3) 0.43 SSW 203° Quarterly Site Boundary South ( 14 ) 0.48 s 180° Quarterly Site Boundary South South East ( l 5) 0. 7 4 SSE 157° Quart er l y Site Boundary South East ( 1 6) 1. 00 SE 135° Quarterly Site Boundary East ( I 7) 0.57 E go* Quarterly Site Boundary Station Intake ( 18) 1. 2 3 ESE 113° Quarterly Site Boundary Hog Island Reserve ( 1 9) 1. 94 NNE 26° Quarterly Near Resident, co-location Bacons Castle ( 20) 4. 4 5 SSW 202* Quarterly Apx. 5 mile TllJ, co-location Route 633 (21) 3. 5 SW 224° Quarterly Apx. 5 mile TLD Alliance ( 2 2) 5. 1 WSW 248° Quarterly Apx. 5 mile TLD, co-location Surry ( 2 3) 8.0 WSW 250° Quarterly Population Center Route 636 and 637 ( 2 4) 4.0 w 2 70* Quarterly Apx. 5 mi le TLD Scotland Wharf ( 2 5) 5.0 WNW 2ss* Quarterly Apx. 5 mile TLD, co-location Jamestown ( 2 6) 6.3 NW 310° Quarterly Apx. !J mile TLLJ, co-location Colonial Parkway (27) 3. 7 NNW 330° Quarterly Apx. 5 mi le TLO Route 617 and 618 (28) 5. 2 NNW 340° Quarterly Apx. S mile TLIJ Kingsmi 11 ( 2 9) 4.8 N 2 0 Quarterly Apx. 5 mi le TLIJ Wi 11 i amsburg ( 3 0) 7.B N o* Quarterly Population* Center, co-location i j 1l Kingsmill North 5.6 NNE 14 ° Quarterly Apx. 5 mile TLLJ Budweiser 5.7 NNE 27 ° Quarterly Population Center

Located onsile in a lead shield.

TAil!.[ I (Cont.)

VIRGINIA POWER - SURRY - 1986 RAUIULOGJCAL SAMPLING STATION DISTANr:E ANU IJ!H[CTION FROM UNIT NO. 1 SAMPLE DISTANCE COLLECTION MEDIA

- ----* LOCATION STATION MILES DIRECTION DEGREES FREQUENCY REMARKS Environmental Water Pl ant ( 33) 4. 8 NE 41° Quarterly Apx. 5 mile TLD TL D's (Cont.) Dow ( 3 4) 5. 1 ENE 70* Quarterly APX. 5 mile TLD 73*

D Lee Hall Goose Island Fort Eustis Newport News

( 3 5)

( 36)

( 3 7)

( 38)

7. 1 5.0 4.8

16. 5 ENE E

ESE ESE 88° 107" 102*

Quarterly Quarterly Quarterly Quarterly Population Center, co-location Apx.5mileTLD Apx. 5 mi le, TLD co-location Population Center James River Bridge ( 39) 14.8 SSE 147° Quarterly Control Location Benn's Church ( 40) 14. 5 s 175° Quarterly Control Location Smithfield ( 4 1) 11 . 5 s 176° Quarterly Population Center Rushmere ( 4 2) 5.2 SSE 156° Quarterly Apx. 5 mile TLD Rt. 628 ( 4 3) 5. 0 s 177 ° Quarterly Apx. 5 mile, TLD co-location Air Charcoal Surry Station ( ss) .37 NNE 15° Weekly Site boundary location with and Particulate Highest D/Q Hog Isl and Reserve (HI R) 2.0 NNE 26° Weekly Co-location D Bacons Castle Alliance Co 11 o,n i al Parkway Dow Chemical (BC)

(ALL)

( CP)

(DOW)

4. 5

5. 1

3. 7

5. 1 SSW WSW NNW ENE 202*

248° 330° 70° Weekly Weekly Weekly

Weekly Co-location Fort Eustis (FE) 4.8 ESE 107° Weekly Newport News ( NN) 16. 5 ESE 122* Weekly Control Location River Water Surry Discharge 0. 17 NW 325° Monthly State Split Scotland Wharf 5.0 WNW 285° Monthly Control Location/State Split Surry Station Intake Hog Island Point Newport News

1. 9

2. 4 12.0 ESE NE SE 77*

52° 140° ,

Bi-monthly Bi-monthly Bi-monthly Chickahominy River 11. 2 WNW 300° Bi-monthly Control Location Surry Station Discharge 0. 17 NW 325° Bi-monthly Scotland Wharf 5.0 WNW 285° Bi-monthly

1ABLE 1 (Cont.)

VIRGINIA POWER - SURRY - 1986 RADIOLOGICAL SAMPLING STATION DISTANCE ANO DIRECTION FROM UNIT NO.

SAMPLE DISTANCE COLLECTION MED I A LOCATION MILES DIRECTION DEGREES FREQUENCY REMARKS Well Water Surry Station Quarterly Ons i te*

Hog Island Reserve 2. 0 NNE 27° Quarterly Bacons Castle 4.5 SSW 203° Quarterly Jamestown 6. 3 NW 309° Quarterly Shoreline Hog Island Reserve 0.8 N 5* Semi-Annually Sediment Burwell's Bay 7. 7 6 SSE 167° Semi-Annually OJ Silt Chickahominy River 11. 2 WNW 300° Semi-Annually Control Location Surry Station Intake 1. 9 ESE 77

Semi-Annual Ty 0 Hog Island Point 2.4 NE 52* Semi-Annually Point of Shoals 6.4 SSE 15 7 ° Semi-Annual Ty Newport News 12. 0 SE 140° Semi-Annually Surry Station Discharge 0. 5 NNW 341 ° Semi-Annually Milk Lee Hall 7. 1 ENE 64° Monthly State Split Epps 4.8 SSW 201* Monthly State Split Colonial Parkway 3. 7 NNW 33 7* Mon th 1y Judkins 6. 2 SSW 211 ° Monthly Wi 11 i ams 2 2. 5 s 182° Mon th l y Control Location Oysters Deep Water Shoals 3. 9 ESE 105° Bi-Monthly Point of Shoals 6.4 SSE 157° Bi-Monthly Clams Newport News Chickahominy R~ver 12.0

11. 2 SE WNW 140° 300° Bi-Monthly Bi-Monthly State Split Control Location Surry Power Discharge 1. 3 NNW 341° Bi-Monthly State Split Hog Island Point 2. 4 NE 52* Bi-Monthly Jamestown 5. 1 WNW 300° Bi-Monthly Lawnes Creek 2.4 SE 131° Bi-Monthly

Well water sample taken onsite at Surry Environmental Building.

TA ll LE 1 (Cont . )

VIRGINIA POWER - SURRY - 1986 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO.

DISTANCE COLLECTION SAMPLE FREQUENCY REMARKS MED IA LOCATION MILES DIRECTION DEGR~ES Surry Station Discharge 0.6 NW 312° July/August Crabs September

@) NW 312° Semi-Annually Fi sh Surry Station Discharge 0.6

Crops Brock's Farm 3.8 s s

188° 1 77 ° Annually Annually State Split State Split (Corn,Peanuts, Slade's Farm 2.4 Soybeans) 2.3 s 132* Annually State Split (Cabbage,Kale) Pool's Garden Annually State Split Carter's Grove Garden 4.8 NE 56° Annually State Split/Control Location Ryan's Garden (Chester, Va.)

FIGURE 3 SITE BOUNDR Nov os 1985

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TABLE 2 SURRY POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Thermo luminescent Quarterly Ga!TITia Dose mR/month Dosimetry (TLD)

Air Iodine Weekly I-131 0.07 pCi/m3 Air Particulate Week 1y Gross Beta 0.01 pCi/m3 Quarterly ( 1) Gamma Isotopic pCi/m3 Cs-134 0.05 Cs-137 0.06 River Water Quarterly Tritium 2000 pC i / .e composite of monthly sample Monthly and . Gamma Isotopic pCi / .e Bi-monthly Mn-54 15 Fe-59 30 Co-58, 60 15 Zn-65 30 Zr-95 30 Nb-95 15 I-131 10 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Well Water Quarterly Tritium 2000 pCi/£ Gamma Isotopic pCi/£ Mn-54 15 Fe-59 30 Co-58,60 15 Zn-65 30 Zr-95 30 Nb-95 15 I-131 1 Cs-134 15 Cs-137 18 Ba-140 60

( 1)

La-140 15 Quarterly composites of each locations's weekly air particulate samples will be analysed for Gamma Emitters.

13

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TABLE 2 (Cont.)

SURRY POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UN ITS Shoreline Sediment Semi-Annual Gamma Isotopic pCi/kg-dry Cs-134 150 Cs-137 180 Si 1t Semi-Annual Gamma Isotopic pCi/kg-dry Cs-134 150 Cs-137 180 Mi 1k

Monthly

1-131 1 pCi / £ Gamma Isotopic pCi / £.

Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Oyster .* B.i -Month 1y Gamma Isotopic pCi /kg.-wet Mn-54 130 Fe-59 260 Co-58, 60 130 Zn-65 260 Cs-134 130 Cs-137 150 Clams Bi-Monthly Gamma Isotopic pCi/kg-wet Mn-54 130 Fe-59 260 Co-58, 60 130 Zn-65 260 Cs-134 130 Cs-137 150

Crabs 3 Summer Months Gamma Isotopic Mn-54 Fe-59 Co-58, 60 Zn-65 Cs-134 Cs-137 130 260 130 260 130 150 pCi/kg-wet 14

. TABLE 2 (Cont.)

SURRY POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY . ANALYSIS LLD* REPORT UNITS Fi sh Semi-Annual Gamma Isotopic pCi /kg-wet Mn-54 130 Fe-59 260 Co-58, 60 130 Zn-65 260 Cs-134 130 CS-137 150 Crops Annually Gamma Isotopic pCi/kg-wet I-131 60 Cs-134 60

Note:

Cs-137 80 This table is not a complete listing of nuclides which can be detected and reported. Other peaks that are measurable and identifiable, together With the above nuclides, shall also be identified and

reported.

LLD's indicate those levels that the environmenta~l samples should be analyzed to, in accordance with the Surry Radiological Environmental Program. Actual analysis of the samples by Teledyne Isotopes may be lower than those listed.

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III. EXCEPTIONS 16

REMP EXCEPTIONS FOR SCHEDULED SAMPLING AND ANALYSIS PROGRAM DURING 1986 During the environmental reporting period, several samples were not available, the ar,alysis of the samples did r,ot meet the required ser,sitivity (LLD) or the sample was r,ot collected ir, the usual samplir,g frequer,cy. Ir, addition to the loss of some samples currently in the Radiological Environ-mental Monitoring Program, several sample locations and/or types of analysis included in the 1985 REMP but not required by Station Technical Specifica-tions, were deleted from the 1986 REMP. The following is a discussion of the exceptions and actions taken to limit reoccurrence.

Four direct radiation TLD's were vandalized during the reporting period.

The currer,t program requires two sets of TLD' s at each sample locatior,, thus

the backup TLD set provided readings for two of the four TLD stations.

TLD sample locations are visually checked once pei month to eliminate loss of data.

All TLD sample location #01 along with an air iodine/particulate station were located or,site durir,g 1985. Ir, September 1985, these sample statior,s were moved to the site boundary because of onsite construction. TLD location

01 was deleted from the 1986 REMP because there are TLD sample locatior,s in the site boundary sectors on either side of the site boundary air iodine/particulate sampling station.

Two air iodir,e/particulate samples were lost because of failure of the carbor, var,es ir, the sample pumps. The air samplir,g equipmer,t was replaced with new equipment early in 1986. Sampler failure rate has decreased dramatically as compared with 1985 failure rate .

The analysis of gross alpha activity was eliminated from the 1986 REMP because it is not required by Station Technical Specifications. The 17

weekly analysis of gross beta, weekly analysis of iodine and the quarterly gamma analysis of composite particulate filters will continue to monitor possible radiological releases from the power station.

River water samples are collected and composited at the Surry Discharge Canal (downstream location) and at Scotland Wharf (upstream control location) by the State of Virginia. These samples are split with VEPCO on a monthly basis. The analysis for barium/lanthanum-140 and iodine-131 failed to meet the required Lower Limit of Detection (LLD) in many of these samples because bf delay in receipt of composite samples from the State of Virginia. To satisfy the Technical Specification requirements of upstream and downstream river water samples, a monthly grab sample was taken by VEPCO at approximately the same locations.

The analysis of the river water grab samples for the Hog Island Point (HIP), Newport News (NN) and Scotland Wharf (SW) failed to meet the LLD for lanthanium-140 because of delay in analysis by the vendor lab.

Gross alpha/beta analysis on all well water samples were deleted during 1986. Current Technical Specifications require only gamma analysis to be performed on well water samples.

Elemental calcium analysis and strontium analysis on milk samples were deleted during 1986. Current Technical Specifications require only gamma and iodine analysis. The State Split samples from Lee Hall and Epps were analyzed for strontium during 1986 and will continue as a quarterly composite analysis in 1987.

Fish samples were taken in accordance with the required sampling program during 1986. The sample taken for the Station Discharge on 9/2/86 did not meet the LLD for cesium because of its small size. After VEPCO was notified of the LLD problem, several attempts were made to acquire another sample.

18

A sample was collected in January 1987 and sent to the vendor lab.

The results of this sample are included in this report.

Precipitation samples requiring gross beta and tritium analysis, were deleted from the sampling program in 1986. These samples are not required by the current Technical Specifications .

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REMP EXCEPTIONS FOR SCHEDULED SAMPLING AND ANALYSIS DURING 1986 Date of Reason(s) for Loss/

Location Description Sampling Exception 01 Direct Radiation A11 1986 Not required by current REMP.

03 Direct Radiation First Quarter TLD Vandalized 05 Direct Radiation First Quarter TLD Vandalized 18 Direct Radiation Thi rd Quart er TLD Vandalized; back-up TLD available for analysis.

35 Direct Radiation First Quarter TLD Vandalized; replaced 2/12/86; back-up TLD available for analysis.

ss Air Particulate/ 01/20/86-01/29/86 Malfunction of carbon Air Iodine vanes in sample pump.

1 Alliance Air Particulate/ 03/25/86-04/01/86 Malfunction of carbon Air Iodine vanes in sample pump.

All Stations Gross Alpha/ Al 1 1986 Analysis not required Air Particulate by current Technical Specifications.

SW, SD River Water 03/15/86-12/15/86 LLD's not met due to (State Split) Ba/La-140 late receipt from I-131 05/15/86-08/15/86 State of Virginia.

HIP, NN, River Water 07 /14/86 LLD not met due to

SW La-140 delay in analysis by vendor lab.

20

REMP EXCEPTIONS FOR SCHEDULED SAMPLING AND ANALYSIS DURING 1986 Date of Reason(s) for Loss/

Location Description Sampling Exception SW, SD Monthly Analysis of All 1986 Monthly samples (VEPCO) River Water Tritium composited for quarterly analysis as required by Technical Specification.

CHIC, HIP, Bi-monthly Analysis All 1986 Analysis not required SI, NN of River Water by current Technical Tritium Specifications.

BC, HIR, We 11 Water All 1986 Gross alpha/beta analysis JMTN, SS Gross Alpha/Beta not required by current Technical Specifications; gamma analysis performed on all samples.

All Stations Calcium Analysis Al 1 1986 Calcium analysis not on Mi 1k required by current Technical Specifications.

CP, JDKS; WMS Strontium-89, A11 1986 Strontium analysis not 90 Analysis on Milk required by current Technical Specifications.

SD Gamma Analysis 9/2/86 Cesium LLD not met due in Fish Sample to small volume sent to vendor lab; re-sample taken.

SS, NN Gross Beta and All 1986 Precipitation sampling Tritium in not required by current Precipitation Technical Specifications.

Ryan's Garden Gamma Analysfs of Kale Sample 6/1986 Sample lost in transfer from State of Virginia to VEPCO.

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V.

SUMMARY

AND DISCUSSION OF 1986 ANALYTICAL RESULTS

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IV.

SUMMARY

AND DISCUSSION OF 1986 ANALYTICAL RESULTS Data from the radiological analyses of environmental media collected during the report period are tabulated and discussed below. The procedures and specifications followed in the laboratory are in accordance with the Teledyne Isotopes Quality Assurance Manual and are explained in the Teledyne Isotopes Analytical Procedures. A synopsis of analytical procedures used for the environmental samples is provided in Section VII. In addition to internal quality control measures performed by Teledyne, the laboratory also participates in the Environmental Protection Agency's Interlaboratory Comparison Program. Participation in this program ensures that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples are performed. The results of the EPA Interlaboratory Comparison are provided in Section VIII.

Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods. Teledyne Isotopes analytical methods meet or exceed the Lower Limit of Detection (LLD) requirements given in Table 2 of the USNRC Branch Technical Position of Radiological Monitoring, Revision I, November 1979; The following is a discussion and summary of the results of the environmental measurements taken during the reporting period.

A. Airborne Exposure Pathway

1. Air Iodine/Air Particulates On April 25, 1986 at 1725 hours0.02 days 0.479 hours 0.00285 weeks 6.563625e-4 months EST there was a nuclear accident at

a Russian reactor at Chernobyl. Sufficient quantities of radioactivity were released into the atmosphere so that various radioisotopes were 23

were measured in certain sample media collected at all the corrnnercial nuclear utilities in the U.S. for which Teledyne Isotopes provides environ-mental analytical services. At the Surry Power Station the radioactivity was first detected during the week beginning May 5, 1986. Elevated gross beta activity levels in weekly air particulates were measured from May 5 through June 10. The second quarter composite (by sampling location) of air particulates analyzed by gamma ray spectroscopy had measurable levels of ruthenium-103, cesium-134 and cesium-137. Iodine-131 was measured in weekly

_charcoal cartridges from May 5 through June 10.

Result~ of airborne iodine-131 analyses of charcoal cartridges are presented in Tabl~ 4. Iodine-131 attributable to the Chernobyl accident, was detected in all eight sampling locations during the three week period May 6 through May 27. The average concentration per week was 0.94, 0.30, and 0.20 pCi/m3. In *subsequent weeks as the iodine-131 continued to decrease due to radioactive decay and atmospheric mixing, the concentrations dropped below the detection limit. During the week of May 27 to June 3, iodine-131 was detected in six sampling locations with an average activity of 0.062 pCi/m3. During the week of June 3 to June 10, iodine-131 was detected in only three sampling locations with an average activity of 0.056 pCi/m3. There was no statistical difference of the average of the weekly iodine-131 results of the ~even indicator locations compared to the control location.

During the same five week period of May 6 through June 10 elevated gross beta activities of all eight sampling locations were measured with weekly average concentrations of 0.226, 0.143, 0.107, 0.070, and 0.092 pCi/m3. For the week of highest gross beta activity the individual 24

sampling locations had a range of 0.19 to 0.32 pCi/m3. During the remaining 47 weeks of 1986 the gross beta activity was measured in all of the 375 samples collected with an average concentration of 0.017 pCi/m3 and a range from 0.0076 to 0.035 pCi/m3. The results of the gross beta activities are listed in Table 5. The monthly averages of the gross beta concentrations for the seven indicator locations and the control locations are. plotted for 1969 through 1986. With the exception of the five week period influenced by the Chernobyl accident, the gross beta activities were comparable to levels in the 1982-1985 period. Prior to that period the gross beta activities were higher due to atmospheric nuclear weapons testing by other countries.

Air particulate filters were composited by locations on a quarterly

basis and were an~lyzed by gamma ray spectroscopy.

in Table 6.

The resul}s are listed Cosmogenically produced beryllium-7 was measured in all 32 composite samples with an average activity of 0.094 pCi/m3 and a range between 0.056 and 0.163 pCi/m3. Naturally occurring potassium-40 was detected in four samples with an average activity of 0.012 pCi/m3 and a range from 0.0054 to 0.027 pCi/m3. In the second quarter composites, three fission-produced isotopes, ruthenium-103, cesium-134 and cesium-137 were measured in the eight samples. These isotopes are attributed to the Chernobyl accident; there was no statistical significance to the average concentrations in the seven indicator locations compared to the control location. The average activity of ruthenium-103 was 0.0085 pCi/m3 and the range was from 0.0072 to 0.0109 pCi/m3. The average activity of cesium-134 was 0.0070 pCi/m3 and the range was 0.0052 to 0.0082 pCi/m3. The average activity of cesium-137 was 0.0148 pCi/m3 and the fange was 0.0129 to 0.0196 pCi/m3.

25

AIR PARTICULATE GROSS BETA p 0.1 C

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1982 1983 1984 1985 1986

- INDICATOR CONTROL

AIR PARTICULATE GROSS BETA 1

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I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 1977 1979 1980 1981

-INDICATOR ******* CONTROL

AIR PARTICULATE GROSS BETA 1

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I I I I I I 1973 1974 1975 1976

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AIR PARTICULATE GROSS BETA 1

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I I 1969 1970 1971 1972

-INDICATOR ******** CONTROL

TABLE 3 RADIOLOGICAL ENVIRONMENTAL MONITORING f'ROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1986 ANALYSIS AND LOWER L!Ml T NUMIJER OF MEIJI UM OR PATHWAY TOTAL NUMBER OF ALL INDICATOR LOCATIONS LOCAl!ON WITH HIGHEST MEAN CONTROL LOCATION NONROUT!NE SAMPLED OF ANALYSES DETECTION MEAN NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD) (I) RANGF DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Air Iodine l-131 414 0. 07 0.37(29/362) CP 0.60(3/52) 0.30(4/52) 0 (pCi/m3) (0 .04-1. 27) (0.17-1.27) (0.06-0.74) w Airborne Gross Beta 414 2 30(362/362) CP 32(52/52) 26(52/52) 0 0

Particulates (7.6-320) (8-320) (9.1-210)

(lE-03 pCi/m3)

Gamma Spec 32 Quarterly Be-7 32 96.4(28/28) ALL 108.3(4/4) 77(4/4) 0 (56.4-138) (67.9-163) (59.6-90. 7)

K-40 32 11.8(4/28) FE 26.9(1/4) -(0/4) 0 (5.4-26.9)

Ru-103 32 8.6(7/28) ALL 10.9(1/4). 7.7(1/4) 0 (7.2-10.9)

Cs-134 32 0.6 7.3(7/28) CP 8.2(1/4) 5.2(1/4) 0 (6.1-8.2)

Cs-137 32 0.7 15.1(7/28) ALL 19.6(1/4) 13.0(1/4) 0 (12.9-19.6)

(1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.

TABLE 4 (Page of 3)

VIRGINIA POWER - SURRY - 1986 CONCENTRATIONS OF IOOJNE-131 IN FILTERED AIR pCi/m3 +/- 2 Sigma STATION ss HIR BC ALL CP DOW FE NN COLLECTION DATE JANUARY 12/31/85-01/07/86 <.01 <.02 <.03 <.03 <.03 <.03 <.03 <.02 01/07/86-01/13/86 <.02 <.03 <.05 <.05 <.03 <.03 <.03 <.02 w Ol/13/86-01/20/86 <.03 <.03 <.05 <.06 <. 0 3 <.03 <.03 <. 02

...... 01/20/86-01/29/86 ( a) <. 02 <.01 <.03 <.02 <. 02 <. 02 <.007 Ol/29/8fi-02/05/86 <.03 <.03 <.05 <.05 <.04 <.07 <.07 <.04 FEBRUARY 02/05/86-02/12/86 <.03 <. 05 <.06 <.06 <.05 <.04 <.04 <.03 02/12/86-02/18/86 <.04 <.04 <.06 <. 07 <. 04 <. 04 <.04 <. 02 02/18/86-02/25/86 <.02 <.02 <.03 <. D3 <.04 <.04 <.04 <.03 02/25/86-03/04/86 <.02 <.OZ <.04 <.04 <.02 <.03 <.03 <. 02 MARCH 03/04/86-03/11/86 <.01 <.DI <.02 <.03 <.02 <.02 <.02 <. 01 03/ll/86-03/18/86 <.OZ <.02 <.03 <.04 <.02 <.02 <.02 <.01 03/18/86-03/25/86 <.01 <.01 <.02 <.02 <.OZ <.01 <.02 <.01 03/25/86-04/0l/86 <.02 <.02 <.04 (a) <. 03 <.02 <.02 <.01 APRIL 04/01/86-04/08/86 <.02 <.02 <.03 <.04 <.03 <.03 <.03 <.02 04/08/86-04/15/86 <.02 <.02 <.04 <.05 <.03 <.03 <.03 <.02 04/15/86-04/22/86 <.OZ <.02 <.03 <.05 <.04 <.03 <.03 <.02 04/22/86-04/29/86 <.02 <.02 <.02 <.03 <.04 <.03 <.03 <.02 (a) Sampler malfunction; no sample available.

T/\BLE 4 (Page 2 of 3)

VIRGINIA POWER - SURRY - 1986 CONCENTRATIONS OF IODINE-131 IN FILTERED AIR pCi/m3 +/- 2 Sigma STATION 55 HIR BC ALL CP DOW FE NN COLLECTION DATE MAY 04/29/86-05/06/86 <. 02 <. 02 <.02 <.02 <.03 <.03 <.03 <.02 05/06/86-05/13/86 .737 +/-.081 . 948 +/-. 100 . 769 +/-.077 1.02 +/-0.10 1.27 +/-.021 .769 +/-.131 1.26 +/-.015 .741 +/-.074 w 05/13/86-05/20/86 .361 +/-.064 .344 +/-.061 .313 +/-.031 .375 +/-.038 .354 +/-.035 .222 +/-.022 .308 +/-.033 .147 +/-.015 N 05/20/86-05/27/86 .157 +/-.019 .122 +/-.012 .224 +/-.022 .190 +/-.019 .173 +/-.022 .151 +/-.039 .303 +/-.040 . 244 +/-. 055 05/27/86-06/03/86 .046 +/-.022 .057 +/-.012 . 068 +/-. 020 .077 +/-.015 <.05 .060 +/-.014 <.02 .061 +/-.016 JUNE 06/03/86-06/10/86 .074 +/- .011 .054 +/- .011 <.04 <.04 <. 05 <.05 .039 +/- .019 <.04 06/10/86-06/17/86 <.03 <.03 <. 03 <.03 <.05 <.03 <.03 <.03 06/17/86-06/24/86 <.OZ <.02 <.02 <.02 <.03 <.02 <.02 <. 02 06/24/86-07/01/86 <.02 <.01 <.02 <.01 <.02 <.01 <.01 <.01 JULY 07/01/86-07/08/86 <.02 <.02 <.02 <.02 <.05 <.02 <.02 <.02 07/08/86-07/14/86 <.03 <.03 <.03 <.03 <.05 <. 02 <.02 <.02 07/14/86-07/22/86 <.02 <.02 <.02 <.02 <.03 <.02 <.02 <.02 07/22/86-07/29/86 <.01 <.01 <.01 <.01 <.04 <.009 <.009 <.009 AUGUST 07/29/86-08/05/86 <. 01 <.01 <.02 <.01 <. 02 <.01 <.01 <.01 08/05/86-08/12/86 <.02 <.02 <.02 <.02 <.04 <. 02 <.02 <.02 08/12/86-08/19/86 <.02 <. 02 <.02 <.02 <.03 <.01 <.02 <.02 08/19/86-08/26/86 <.02 <. 02 <.02 <.02 <. 02 <.02 <.02 <.02 08/26/86-09/02/86 <.02 <.02 <.03 <.02 <.01 <.01 <.03 <.02

TABLE 4 (Page 3 of 3)

VIRGINIA POW EH - SURRY - 1986 CONCENTRATIONS OF IODINE-131 IN FILTERED AIR pCi/m3 +/- 2 Sigma

*~---------~----- ----- *--------------*---------

STATION ss HIR BC ALL CP DOW FE NN COLLECTION DATE *----------

SEPTEMBER 09/02/86-09/09/86 <.02 <.02 <.02 <.02 <.02 <.02 <.03 <.02 09/09/86-09/16/86 <.02 <.02 <.02 <.01 <.01 <.01 <.01 <.01 09/16/86-09/22/86 <. 02 <.02 <.02 <.03 <.02 <.02 <.02 <. 02 09/22/86-09/29/86 <.02 <.02 <.02 <.02 <.02 <.02 <.02 <.02 w

w OCTOBER 09/29/86-10/07/86 <.01 <.01 <.01 <.01 <.008 <. 008 <.008 <.009 10/07/86-10/14/86 <.02 <.02 <.02 <. 02 <.02 <.02 <.02 <.02 10/14/86-10/21/86 <.02 <.01 <.01 <.01 <.03 <.03 <.02 <.03 10/21/86-10/28/86 <.02 <.02 <.02 <.02 <.02 <.02 <.02 <.02 NOVEMBER 10/28/86-11/04/86 <.01 <.01 <.01 <.01 <.02 <. 02 <.02 <.02 ll/04/86-11/11/86 <.03 <.02 <.02 <.02 <.02 <.02 <.02 <.02 ll/11/86-11/18/86 <.04 <.03 <.03 <.03 <.02 <.02 <.02 <.02 ll/18/86-11/25/86 <.03 <.03 <.03 <.03 <. 02 <.02 <.02 <.02 ll/25/86-12/02/86 <.02 <.02 <.02 <.02 <.01 <.01 <.01 <.01 DECEMBER 12/02/86-12/09/86 <.02 <.02 <.02 <.02 <.01 <.01 <.01 <.01 12/09/86-12/16/86 <.02 <.02 <.02 <.02- <.01 <.01 <.01 <.01 12/16/86-12/22/86 <.04 <.04 <.03 <.04 <.03 <.03 <.03 <.03 12/22/86-12/30/86 <.02 <. 02 <.02 <.02 <. 02 <.02 <.02 <.02

TABLE 5 (Page 1 .Q f 4)

VIRGINIA POWER - SURRY 1986 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES 10-3 pCi/m3 +/- 2 Sigma STATION Average COLLECTION DATE ss HIR BC ALL er DOW FE NN +/- 2 s.d JANUARY 12/31/85-01/07/86 21 +/- 2 21 +/- 2 26 +/- 3 13 +/- 2 28 +/- 3 25 +/- 3 24 +/- 3 23 +/- 2 23 +/- 9. 1 w Ol/07/86-01/13/86 18 +/- 2 21 +/- 2 28 +/- 4 31 +/- 4 30 +/- 4 24 +/- 3 26 +/- 3 22 +/- 2 25 +/- 9. 1

.i,.

01/13/86-01/20/86 17 +/- 2 14 +/- 2 17 +/- 3 17 +/- 3 9 +/- 2 19 +/- 3 18 +/- 3 13 +/- 2 16 +/- 6.6 Ol/20/86-01/29/86 (a) 16 +/- 2 16 +/- 2 18 +/- 3 17 +/- 2 19 +/- 2 15 +/- 2 15 +/- 2 17 +/- 3. 0 Ol/29/86-02/05/86 21 +/- 2 20 +/- 2 18 +/- 3 28 +/- 3 23 +/- 3 26 +/- 3 26 +/- 3 18 +/- 2 23 +/- 7. 7 FEBRUARY 02/05/86-02/12/86 14 +/- 2 13 +/- 2 24 +/- 3 14 +/- 3 13 +/- 2 17 +/- 3 18 +/- 3 12 +/- 2 16 +/- 7. 9 02/12/86-02/18/86 28 +/- 3 21 +/- 2 13 +/- 3 30 +/- 4 30 +/- 4 17 +/- 3 19 +/- 3 17 +/- 2 22 +/- 13. 2 02/18/86-02/25/86 15 +/- 2 16 +/- 2 18 +/- 3 19 +/- 3 17 +/- 3 21 +/- 3 11 +/- 2 17 +/- 2 17 +/- 5. 9 02/25/86-03/04/86 15 +/- 2 16 +/- 2 15 +/- 2 17 +/- 3 8 +/- 2 19 +/- 2 15 +/- 2 15 +/- 2 15 +/- 6. 3 MARCH 03/04/86-03/11/86 16 +/- 2 14 +/- 2 16 +/- 3 23 +/- 3 20 +/- 3 17 +/- 3 15 +/- 3 20 +/- 2 18 +/- 6. 1 03/11/86-03/18/86 12 +/- 2 13 +/- 2 16 +/- 2 10 +/- 2 14 +/- 2 16 +/- 2 11 +/- 2 15 +/- 2 13 +/- 4.5 03/18/86-03/25/86 17 +/- 2 24 +/- 2 12 +/- 2 15 +/- 3 9 +/- 2 16 +/- 2 10 +/- 2 14 +/- 2 15 +/- 9.4 03/25/86-04/01/86 20 +/- 2 15 +/- 2 21 +/- 3 ( a) 15 +/- 2 11 +/- 2 21 +/- 3 19 +/- 2 17 +/- 7.6 Quarter Average 18 +/- 8 17 +/- 7 18 +/- 10 20 +/- 14 18 +/- 16 19 +/- 8 18 +/- 11 17 +/- 7 18 +/- 7

+/- 2 s. d.

( a) Sampler malfunction; no sample available.

TABLE 5 (Page 2 of 4)

VIRGINIA POWER - SURRY 1986 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES 10-3 pCi/m3 +/- 2 Sigma STATION Average COLLECTION DATE ss HIR BC ALL CP DOW

---~--------- FE NN +/- 2 s.d APRIL 04/01/86-04/08/86 16 +/- 2 14 +/- 2 21 +/- 3 19 +/- 3 21 +/- 3 13 +/- 2 23 +/- 3 15 +/- 2 18 +/- 7.5 04/08/86-04/15/86 14 +/- 2 15 +/- 2 16 +/- 3 18 +/- 3 16 +/- 3 17 +/- 3 16 +/- 3 16 +/- 2 16 +/- 2.4 04/15/86-04/22/86 8.4+/- 1.4 7. 6+/- 1. 2 24 +/- 3 14 +/- 3 20 +/- 3 15 +/- 2 18 +/- 2 9.6+/- 1.4 15 +/- 11.8 w

(.11 04/22/86-04/29/86 16 +/- 2 15 +/- 2 18 +/- 2 15 +/- 2 29 +/- 3 24 +/- 3 20 +/- 3 18 +/- 2 19 +/- 10 MAY 04/29/86-05/06/86 24 +/- 2 20 +/- 2 23 +/- 2 18 +/- 2 24 +/- 3 26 +/- 3 24 +/- 3 22 +/- 2 23 +/- 5.1 05/06/86-05/13/86 230 +/- 10 200 +/- 10 220 +/- 10 190 +/- 10 320 +/- 10 220 +/- 10 220 +/- 10 210 +/- 10 226 +/- 80 05/13/86-05/20/86 130 +/- 10 150 +/- 10 160 +/- 10 180 +/- 10 160 +/- 10 140 +/- 10 150 +/- 10 71 +/- 4 143 +/- 65.1 05/20/86-05/27/86 95 +/- 4 100 +/- 10 130 +/- 10 120 +/- 10 99 +/- 6 90 +/- 4 110 +/- 10 110 +/- 10 107 +/- 26.8 05/27/86-06/03/86 63 +/- 4 64 +/- 4 67 +/- 4 86 +/- 4 86 +/- 6 55 +/- 3 69 +/- 5 69 +/- 4 70 +/- 21.8 JUNE 06/03/86-06/10/86 85 +/- 4 100 +/- 10 100 +/- 10 100 +/- 10 85 +/- 5 80 +/- 4 91 +/- 4 91 +/- 4 92 t 15.7 06/10/86-06/17/86 25 +/- 3 11 +/- 2 17 +/- 2 23 +/- 3 9.6+/- 3.2 16 +/- 2 15 +/- 2 16 +/- 2 17 +/- 10.6 06/17/86-06/24/86 23 +/- 2 23 +/- 2 23 +/- 2 22 +/- 2 13 +/- 3 20 +/- 2 21 +/- 2 26 +/- 3 21 +/- 7.6 06/24/86-07/01/86 16 +/- 2 17 +/- 2 18 +/- 2 19 +/- 2 15 +/- 3 13 +/- 2 18 +/- 2 18 +/- 2 17 +/- 4.0 Quarter Average 57 +/- 129 57 +/- 125 64 +/- 135 6 3 +/- 1 30 69 +/- 176 56 +/- 126 62 +/- 130 53 +/- 116 60 +/- 131

ft 2 s .d.

TAl3LE 5 (Page 3 of 4)

VIRGINIA POWER - SURRY 1986 CONCENTRATIONS OF GROSS BE TA IN AIR PARTICULATES 10-3 pCi/m3 +/- 2 Sigma STATION Average COLLECTION DATE ss H IR BC ALL CP DOW FE NN +/- 2 s.d JULY 07/01/86-07/08/86 22 +/- 2 21 +/- 2 22 +/- 2 20 +/- 2 19 +/- 3 21 +/- 2 25 +/- 2 21 +/- 2 21 +/- 3. 5 07/08/86-07/14/86 24 +/- 3 19 +/- 2 22 +/- 2 20 +/- 2 19 +/- 4 21 +/- 2 23 +/- 2 23 +/- 2 21 +/- 3. 8 w

07/14/86-07/22/86 17 +/- 2 21 +/- 2 18 +/- 2 18 +/- 2 25 +/- 3 19 +/- 2 21 +/- 2 19 +/- 2 20 +/- 5. 1 CTI 07/22/86-07/29/86 19 +/- 2 23 +/- 2 16 +/- 2 19 +/- 2 35 +/- 6 16 +/- 2 16 +/- 2 21 +/- 2 21 +/- 12. 7 AUGUST 07/29/86-08/05/86 24 +/- 2 23 +/- 2 27 +/- 2 19 +/- 2 22 +/- 3 21 +/- 2 25 +/- 2 12 +/- 2 22 +/- 9.2 08/05/86-08/12/86 20 +/- 2 21 +/- 2 26 +/- 2 18 +/- 2 22 +/- 3 20 +/- 2 17 +/- 2 17 +/- 2 20 +/- 6.0 08/12/86-08/19/86 8. 7+/- 1. 5 11 +/- 2 11 +/- 2 11 +/- 2 13 +/- 3 11 +/- 2 12 +/- 2 10 +/- 2 11 +/- 2. 5 08/19/86-08/26/86 11 +/- 2 13 +/- 2 17 +/- 2 14 +/- 2 14 +/- 3 12 +/- 2 12 +/- 2 11 +/- 2 13 +/- 4. 0 08/26/86-09/02/86 18 +/- 2 15 +/- 2 22 +/- 3 16 +/- 2 19 +/- 2 13 +/- 2 16 +/- 3 14 +/- 2 17 +/- 5.8 SEPTEMBER 09/02/86-09/09/86 21 +/- 2 17 +/- 2 15 +/- 2 17 +/- 2 19 +/- 2 15 +/- 2 18 +/- 3 9. 1+/- 1. 7 16 +/- 7. 1 09/09/86-09/16/86 29 +/- 3 24 +/- 2 23 +/- 2 28 +/- 7 28 +/- 2 21 +/- 2 25 +/- 2 14 +/- 2 24 +/- 9.8 09/16/86-09/22/86 24 +/- 2 21 +/- 2 16 +/- 2 23 +/- 3 26 +/- 3 15 +/- 2 19 +/- 2 18 +/- 2 20 +/- 7. 8 09/22/86-09/29/86 28 +/- 3 22 +/- 2 22 +/- 2 20 +/- 2 22 +/- 2 22 +/- 2 24 +/- 2 11 +/- 2 21 +/- 9. 6 Quarter Average 20 +/- 12 19 +/- 8 20 +/- 9 19 +/- 8 22 +/- 12 18 +/- 8 20 +/- 10 15 +/- 9 19 +/- 7

+/- 2 s. d.

T l\13L E 5 (Page 4 of 4)

VIRGINIA POWER - SURRY 1986 CONCENTRI\TIONS OF GROSS BETA IN AIR PARTICULATES I0-3 pCi/m3 +/- 2 Sigma STATION Average COLLECTION -UATE

ss- - - - - - -HI R

BC- ALL CP DOW FE NN +/- 2 s. d OCTOBEI!

09/29/86-10/07/86 14 +/- 2 20 +/- 2 16 +/- 2 18 +/- 2 19 +/- 2 16 +/- 2 19 +/- 2 21 +/- 2 18 +/- 4.7 10/07/86-10/14/86 15 +/- 2 14 +/- 2 14 +/- 2 15 +/- 2 14 +/- 2 16 +/- 2 17 +/- 2 14 +/- 2 15 +/- 2.3 10/14/86-10/21/86 19 +/- 2 19 +/- 2 18 +/- 2 21 +/- 2 23 +/- 2 19 +/- 2 19 +/- 2 18 +/- 2 20 +/- 3.4 10/21/86-10/28/86 31 +/- 2 32 +/- 2 33 +/- 2 30 +/- 2 32 +/- 2 22 +/- 2 25 +/- 2 30 +/- 2 29 +/- 7.7

~ NOVEMBER 10/28/86-11/04/86 20 +/- 2 20 +/- 2 13 +/- 2 19 +/- 2 15 +/- 2 14 +/- 2 19 +/- 2 16 +/- 2 17 +/- 5.7 ll/04/86-11/11/86 19 +/- 3 17 +/- 2 17 +/- 2 17 +/- 2 15 +/- 2 15 +/- 2 19 +/- 2 14 +/- 2 17 :i: 3. 7 ll/11/86-11/18/86 20 +/- 2 18 +/- 2 12 +/- 2 20 +/- 2 21 +/- 2 17 +/- 2 20 +/- 2 20 +/- 2 19 +/- 5.9 ll/18/86-11/25/86 20 +/- 2 19 +/- 2 12 +/- 2 22 +/- 2 22 +/- 2 17 +/- 2 19 +/- 2 15 +/- 2 18 +/- 6.9 DECEMBER ll/25/86-12/02/86 19 +/- 2 15 +/- 2 14 +/- 2 20 +/- 2 20 +/- 2 18 +/- 2 20 +/- 2 14 +/- 2 18 +/- 5. 5 12/02/86-12/09/86 19 +/- 2 18 +/- 2 14 +/- 2 16 +/- 2 18 +/- 2 16 +/- 2 18 +/- 2 16 +/- 2 17 +/- 3. 3 12/09/86-12/16/86 16 +/- 2 16 +/- 2 15 +/- 2 19 +/- 2 18 +/- 2 14 +/- 2 19 +/- 2 17 +/- 2 17 +/- 3. 7 12/16/86-12/22/86 30 +/- 3 28 +/- 3 25 +/- 2 32 +/- 3 28 +/- 3 23 +/- 2 27 +/- 3 24 +/- 3 27 +/- 6. 1 12/22/86-12/30/86 21 +/- 2 23 +/- 2 17 +/- 2 23 +/- 2 23 +/- 2 18 +/- 2 24 +/- 2 16 +/- 2 21 +/- 6.3 Quarter Average 20 +/- 10 20 +/- 10 17 +/- 12 21 +/- 10 21 +/- 10 17 +/- 6 20 +/- 6 18 +/- 9 19 +/- 8

+/- 2 s. d.

Annual Average 29 +/- 72 28 +/- 70 30 +/- 77 31 +/- 75 32 +/- 96 28 +/- 7 0 30 +/- 73 26 +/- 65 29 +/- 4

+/- 2 s. d.

TABLE 6 (Page 1 of 2)

VIRGINIA POWER - SURRY - 1986 CONCENTRATIONS OF GAMMA EMITTERS* IN QUARTERLY AIR PARTICULATES 10-3 pCi/m3 +/- 2 sigma FIRST QUARTER SECOND QUARTER TH !RD QARTER FOUR TH QUARTER AVERAGE STATION NUCLIDE 12/31/85-04/01/86 04/01/86-07/0l/86 07/01/86-09/29/86 09/29/86-12/30/86 +/ s. d -

ss Be - 7 132 +/- 13 88 - 1 +/- 11-4 95-8 +/ 6 61-2 +/ 8 94.3 +/- 58.4 K-40 <5 <9 <4 <7 Co-60 . <0. 3 <0.6 <O - 2 <0-4 Ru-103 <0-9 8. 13 +/- 1. 36 <0_3 <0.4 8- 13 +/- 1. 36 Cs-134 <0.3 6.83 +/- 0.94 <0.2 <0.4 6.83 +/- 0.94 Cs-137 <0.3 14.8 +/- 1. 5 <O. 3 <0.4 14.8 +/- 1. 5 w <0.5 CXl Th - 2 2 8 <l <0.4 <0.8 HIR Be-7 133 +/- 13 95.8 +/- 11. 8 9 3. 1 +/- 9. 3 80.5 +/- 10. 7 100.6 +/- 4 5. 2 K-40 <3 <8 <10 <2 0 Co-60 <O. 2 <0.6 <O. 3 <O. 7 Ru-103 <O. 7 7.22 +/- 1. 31 <O. 5 <l 7 _2 2 +/- 13. 1 Cs-134 <0.2 7.64 +/- 1. 09 <0.4 <0.7 7.64 +/- 1. 09 Cs-137 <0.2 12. 9 +/- 1. 3 <O. 3 <0.7 12.9 +/- 1. 3 Th -2 2 8 <0-5 <0.9 <0.5 <2 BC Be-7 123 +/- 12 105 +/- 1 3 60.0.+/- 6.0 57.8 +/- 8. 4 86.5 +/- 6 5. 3 K-40 8.42 +/- 3.34 <10 5.41 +/- 2.39 <10 6.9 +/- 4.3 Co-60 <0.3 <0. 5 <0.3 <O. 7 Ru-103 <l 9.87 +/- 1. 5 7 <0.3 <0.6 9.87 +/- 1. 5 7 Cs-134 <0.4 7.94 +/- 0.99 <0.3 <0.5 7.94 +/- 1. 0 Cs-137 <0.4 17. 1 +/- 1. 7 <0.3 <0.7 17. 1 +/- 1. 7 Th-228 <0.8 <l <0.4 <l ALL Be - 7 163 +/- 22 110 +/- 15 92.2 +/- 9. 2 67.9 +/- 7. 4 108.3 +/- 80.7 K-40 <20 <10 6.53 +/- 2.22 <7 6.53 +/- 2.22 Co -60 <O. 7 <O. 9 <0.3 <0.4 Ru-103 <3 10.9 +/- 1. 6 <0.4 <0.6 10.9 +/- 1. 6 Cs -134 <0.9 8.21 +/- 0.99 <0.3 <0.4 8. 21 +/- 0.99 Cs-137 <0.8 19.6 +/- 2.0 <0.3 <0.5 19.6 +/- 2.0 Th - 2 2 8 <2 <l <0.5 <O _7

All other gamma emitters were <LLD.

TABLE 6 (Page 2 of 2)

VIRGINIA POWER - SURRY - 1986 CONCENTRATIONS or GAMMA EMITTERS* IN QUARTERLY AIR PARTICULATES 10-3 pCi/m3 +/- 2 sigma

--- - --- -- - ****---~------ - - - - - - - - * - - - - * * - - * - - - - - - ------------------------- ----*-----------**--- - - - - - - - - - - - - - - - - - - - - * - - - - - --- --*-

FIRST QUARTER SECOND QUARTER TH I RD QARTER FOURTH QUARTER AVERAGE STATION NUCLIDE 12/31/85-04/01/86 04/01/86-07/0l/86 07/01/86-09/29/86 09/29/86-12/30/86 +/- 2. s. d.

CP Be-7 105 +/- 1 5 93.4 +/- 16.6 104 +/- 10 85.5 +/- 8.8 9 7. 0 +/- 18.6 K-40 <10 <20 <10 <20 Co-60 <0.6 <l <0.6 <0.6 Ru-103 <2 7.39 +/- 2.07 <0.8 <0.8 7. 39 +/- 2.07 Cs-134 <0.5 8. 2 2 +/- 1. 68 <0.5 <0.6 8. 2 2 +/- 1. 68 w Cs-137 <O. 7 13.9 +/- 1. 6 <O. 5 <O. 6 13. 9 +/- 1. 6

\D Th - 2 2 8 <l <2 <0.9 <0.8 DOW Be-7 138 +/- 14 87.5 +/- 13. 2 60.9 +/- 6. 1 56.4 +/- 5.9 85.7 +/- 74.9 K-40 <6 <10 <4 <6

Co-60 <0.4 <0.7 <O. 2 <0.4 Ru-103 <1 7. 5 7 +/- 1. 45 <0.3 <0.5 7.57 +/- 1. 45 Cs-134 <0.4 6.10 +/- 1. 28 <0.2 <0.3 6.10 +/- 1. 28 Cs-137 <0.4 13.6 +/- 1. 4 <0.2 <0.4 13.6 +/- 1. 4 Th-228 <O. 7 <1 <0.5 <0.6 FE Be-7 129 +/- 13 124 +/- 23 83. 1 +/- 8.3 73.3 +/- 7. 3 102.4 +/- 56.5 K-40 <20 26.9 +/- 12.9 <5 <4 26.9 +/- 12.9 Co-60 <0.5 <1 <0.2 <0.2 Ru-103 <2 9.33 +/- 2.34 <0.3 <0.3 9.33 +/- 2.34 Cs-134 <0.6 5.96 +/- 1. 66 <0.3 <0.2 5.96 +/- 1. 66 Cs-137 <0.5 14. 1 +/- 1. 9 <0.2 <0.3 14. 1 +/- 1. 9 Th - 2 2 8 <0.8 <2 <0.5 <0.4 NN Be-7

90. 7 +/- 6. 3 88.3 +/- 12.8 59.6 +/- 6. 0 69.5 +/- 7.0 77. 0 +/- 30.0 K-40 <9 <8 <4 <9 Co-60 <0.3 <O. 6 <0.2 <0.3 Ru-103 <0.8 7. 7 0 +/- 1. 36 <0.2 <0.4 7.70 +/- 1. 36 Cs-134 <0.3 5. 19 +/- 1. 12 <0.2 <O. 3 5. 19 +/- 1. 12 Cs-137 <0.3 13. 0 +/- 1. 3 <0.2 <0.3 I 3. O f 1. 3 Th-228 <0.4 <1 <O. 3 <0.5

AI I other gamma emitters were <LLD.

B. Waterborne Exposure Pathway

1. River Water The James River is an estuary near Surry Power Station and undergoes tidal exchange with the Chesapeake Bay. River water samples thus represent saline bay water. Samples of James River water are collected as both monthly grab samples at the Surry Discharge and Scotland Wharf stations and bi-monthly grab samples at the Hog Island Point, Newport News, Chickahominy River, and Surry Intake stations. All the samples were analyzed for gamma emitting isotopes by gamma spectrometry and for iodine-131 by a radiochemical*

procedure. In addition, Scotland Wharf and Surry Discharge samples are composited and ~nalyzed for triti~m on a quarterly basis. The results are presented in Table 8. Potassium-40 was measured in seventeen of the samples

with an average concentration of 103 pCi/£ and a range of 11.8 to 173 pCi/£.

No other gamma emitters were detected.

The Surry Discharge and Hog Island Point samples taken on May 15, 1986 had measurable activity with an average of 1.3 pCi/£ and a range of 1.2 to 1.3 pCi/£. These samples were taken during the period of measurable airborne iodine-131 resulting from the Chernobyl accident. The activity detected in thtse samples was slightly above the required LLD of 1 pCi/£.

Tritium was measured in 7 of the 8 composite samples with an average activity of 217 pCi/£ for Surry Discharge location and 193 pCi/£ for Scotland Wharf (control) location.

Monthly composites of river water are collected by the Commonwealth of Virginia . .Results of gamma spectrometry and tritium analyses on these samples are presented in Table 9. Except for natu:al.ly occurring potassium-40,

all the gamma emitting nuclides were below their respective detection limits. Potassium-40 was measured twelve times with an average activity of 40

88 pCi/£ and a range of 43.7 to 174 pCi/£. The average tritium activity for eleven samples collected at the Surry Discharge location was 578 and the range was from 170 to 1490 pCi/£. At the Scotland Wharf location eleven measured tritium levels had an average activity of 205 pCi/£ and a range from 110 to 290 pCi/£. The attached trend graphs provide a comparison of tritium measured in the downstream sample (Surry Discharge), the upstream control location (Scotland Wharf) and the station effluents, sampled prior to discharge. The environmental sample from the Station Discharge indicates good comparison with measured station effluents. The average Station Discharge tritium was measured, as indicated above, at 578 pCi/£ and the average station effluents measured 400 pCi/£. Variations between the two samples may be due to the sampling method of the environmental sample. The Station Discharge location is sampled approximately once per 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and composited for monthly analysis.

The trend graphs also indicate that there is no long term build up of tritium in the environment. All gamma emitters were below their lower limit of detection .

41

RIVER WATER TRITIUM-1986 10000 ----------------------------------------------------------------.

p

..i:,.

C Required LLD (2000 pCi/1)

N i 1000 I

I 100 +------+------+------+-------+-------+--------+-------,.------+------+------t------f JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC

- SD SW (control) ****** Station Effluent

AVERAGE RIVER WATER TRITIUM A

p C

i I 1-------4't-----....Jll'~--------:::1rt11r.~c.**-**_'------~..-------------..;:::m.._~----I I

I .~**' *, ,,---------~--lllliiii;;.;;;,;;;;J ---...._

.---~,-------'t---~_.-..a._-________

I --t:"

1::::::::....---=.;.--------~

___J ~ -***** ~. ---.,-!!.l. * ..,__ _ _ _ _ _

o.a,...__ _ _ _ _ _ _ _ _ ___.,....._ _ _

100 ....,_________:~------t:-------+:----------*------+:--------+--:------i*-------+'------~*-------t 1976 1977 1978 1979 I 1980 1981 1982 1983 1984 1985 1986

- SURRY DISCHARGE **** CONTROL

TABLE 7 RAOIOLOGJCAl ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

su,rn y NlJCL EAH l'OWEH sTAT I ON DOCKET NlJ. 5-2/JO-c/Jl SURRY CllllNTY, VJRGINII\ JANUARY 1 Lo ULLEMBER 31, 1986 ANALYSIS AND LOWER LIMIT NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER OF ALL INUICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTI NE SAMPLED OF ANALYSES DETECTION ME/IN N/\ME MEAN MEAN REPORTED

{UNIT UF M~ASUREMENT) PERFORMED (LLD) ( 1) RANGE DISTANCE AND OIRECTJON RANGE RANGE MEASUREMENTS River Water (a) Gamma 48

( pCi/ £)

K-40 48 60 103(14/36) SD 104(5/12) 64. 3 ( 3/12) 0 (27.9-173) (60.4-144) (11. 8-120) 1-131 {b) 48 0.5 1.3(2/36) SD 1.3(1/12) -(0/12) 0 (1.2-1.3)

Tritium 14 100 254( 10/11) SD 397(3/3) 230(3/3) 0

( 120-660) (240-660) (150-380)

Tritium 16 100 193(11/12) fl IP 235(2/2) 193(3/4) 0 (Quarterly) (81-490) ( 180-290) (180-220)

River Water (c) Gamma 24 pCi/£ - State Split K-40 24 60 93.8(9/17) SD 93.8(9/12) 71. 7(3/12) 0

( 48.0-174) (48.0-174) (43.7-111)

Tritium 24 100 578(11/12) SD 578(11/12) 205( 11/12) 0 (170-1490) (170-1490) ( 110-290)

( 1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.

Analyses for monthly and bi-monthly samples listed in Table 8.

Analyses by radiochemistry.

Monthly State Split analyses presented in Table 9.

TABLE 8 (Page of 3)

VIRGINIA POWER - SURRY - 1986 CONCENTRATIONS OF GAMMA EMITTERS* AND TRITIUM IN RIVER WATER pCi/£ +/- 2 Sigma STATION DATE Be-7 K-40 I -131 Cs-137 Ba-140 La-140 TH-228 H-3 JANUARY CHIC 01/10/86 <4 0 <60 <O. 5 <4 <2 0 <6 <7 HIP 01/10/86 <60 <200 <0.4 <6 <30 <9 <l 0 NN 01/10/86 <40 147 +/- 41 <O. 3 <4 <2 0 <6 <8 SD 01/10/86 <30 <40 <0.3 <3 <8 <3 <7

_,,. SI 01/10/86 <40 <100 <0.3 <5 <2 0 <8 <9 u, SW 01/10/86 <30 <50 <0.3 <3 <10 <5 <7 FEBRUARY SD 02/18/86 <30 <4 0 <0.3 <3 <10 <5 <6 SW 02/18/86 <30 <50 <0.3 <3 <10 <5 <7 MARCH CHIC 04/01/86 ** <30 <40 <0.5 <3 <10 <5 <6 HIP 04/01/86 <40 <5 0 <O. 5 <4 <20 <5 <8 NN 04/01/86 <30 59.7 +/- 29.2 <0.5 <4 <10 <6 <7 SD 04/01/86 <30 <50 <0.5 <3 <10 <6 <7 160 +/- 80 SI 04/01/86 <30 <50 <0.4 <3 <10 <6 <7 SW 04/01/86 <40 <100 <0.4 <4 <20 <7 <8 180 +/- 80 APRIL SD 04/2 2/86 <40 109 +/- 3 7 <0.5 <4 <2 0 <6 <9 SW 04/22/86 <40 <50 <O. 3 <4 <20 <7 <7 All other gamma emitters were <LLD.

, ** Samples collected 04/01/86 for March sample.

TABLE 8 (Page 2 of 3)

VIRGINIA POWER - SURRY - 1986 CONCENTRATIONS OF GAMMA EMITTERS* AND TRITIUM IN RIVER WATER pCi/£ +/- 2 Sigma STAl ION DATE Be-7 K-40 I - 1 31 Cs-137 Ba-140 La-140 TH-228 11-3 MAY CH IC 05/15/86 <40 <50 <O. 5 <3 <30 <10 <7 HIP 05/15/86 <4 0 57.9 +/- 29.2 1.2 +/- 0.3 <4 <30 <10 <8 NN 06/02/86** <30 112 +/- 18 <0.9 <2 <40 <10 <5 SD 05/15/86 <40 60.4 +/- 30.8 1.3 +/- 0.3 <4 <30 <10 <7 SI 06/02/86** <30 27.9 +/- 16.2 <0.3 <2 <30 <10 <4 SW 05/15/86 <40 <60 <0.3 <4 <30 <10 <8 a,

JUNE SD 06/17 /86 <30 <60 <0.6 <4 <2 0 <9 <9 110 +/- 80 SW 06/17/86 <60 <200 <0.3 <5 <40 <10 <10 <110 JULY CHIC 07/23/86 <40 <60 <0.5 <4 <30 <10 <8 HIP 07/14/86 <50 <60 <l <4 <50 <20 (a) <8 NN 07/14/86 <50 134 +/- 39 <l <4 <50 <20 ( a) <8 SD 07 /2 3/86 <40 85. 1 +/- 3 4. 1 <0.5 <4 <30 <10 <8 SI 07/29/86 <40 173 +/- 40 <0.5 <4 <30 <10 <8 SW 07 /14/86 <40 61. 1 +/- 31. 5 <1 <4 <50 <20 (a) <7 AUGUST SD 08/19/86 <40 144 +/- 2 9 <0.3 <3 <20 <8 <7 SW 08/19/86 <30 11. 8 +/- 4.6 <0.5 <3 <2 0 <7 <6

All other gamma emitters were <LLD.

- Samples collected 06/02/86 for May sample.

(a) LLD analysis not met because of delay in analysis at vendor lab.

TAll LE 8 (Page 3 of 3)

VIRGINIA POWER - SURRY - 1986 CONCENTRATIONS OF GAMMA EMITTERS* AND TRITIUM IN RIVER WATER pCi/£ +/- 2 Sigma SI/\ TI ON DATE Be-7 K-40 I -1 31 Cs-137 lla-140 La-140 TH-228 H-3 SEPTEMBER CH IC 09/10/86 <40 <100 <0.5 <4 <30 <10 <8 HIP 09/10/86 <60 <200 <O. 5 <5 <4 0 <10 <10 NN 09/10/86 <70 <100 <0.5 <5 <40 <10 <10 so 09/10/86 <50 <100 <0.5 <5 <30 <10 <9 110 +/- 80

.p.

SI 09/10/86 <50 101 +/- 33 '<O. 5 <5 <30 <10 <8

_, SW 09/10/86 <40 <60 <0.5 <5 <30 <10 <8 180 +/- 80 OCTOBER so 10/21/86 .(40 122 +/- 31 <0.3 <4 <20 <7 <8 SW 10/21/86 <50 <200 <0.4 <6 <30 <10 <10 NOVEMBER CHIC 11/25/86 <40 <60 <0.4 <4 <20 <9 <7 HIP 11/25/86 <40 115 +/- 45 <0.3 <4 <20 <10 <8 NN 11/25/86 <70 <2 00 <0.4 <7 <40 <10 <10 SD 11/25/86 <60 <100 <0.4 <6 <30 <9 <lD SI 11/25/86 <BO <2 00 <0.4 <7 <40 <10 <20 SW 11/25/86 <50 120 +/- 39 <0.3 <5 <30 <9 <9 DECEMBER SD 12/22/86 <50 <BO <0.3 <5 <20 <6 <10 490 +/- 70 SW 12/22/86 <50 <200 <0.4 <5 <30 <10 <10 220 +/- 90 Average 103 +/- 82 1.3 +/- 0.1 206 +/- 264

+/- 2 s. d.

A11 other gamma emitters were <LLD.

TAllLE 9 VIRGINIA POWER - SURRY - 1986 CONCENTRATIONS OF.GAMMA EMITTERS* AND TRITIUM IN RIVER WATER pCi/£ +/- 2 Sigma - STATE SPLIT MONTH COLL. DATES Be-7 K-40 I - 131 Cs-137 Ba-140 La-140 Th-228 H-3 1986 January 01/01-01/31 <40 <40 <l <3 <40 <10 <6 <140 February 02/01-02/28 <30 <4 0 <1 <3 <30 <10 <6 130 +/- 80 Mar.ch 03/15/86 <30 <20 ( b) <2 <90 (a) <40 (a) <4 260 +/- 80 l\p r i 1 04/01-04/30 <70 <100 ({]. 3 <5 <100 ( a) <30 (a) <10 170 +/- 80 May 05/15/86 <100 <50 <200(a) <4 <2000(a) <800(a) <9 190 +/- 80

,lune 06/15/86 <70 <50 <3 O (a) <4 <300 (a) <lOO(a) <7 280 +/- 80

,lu*l y 07/15/86 <60 43.7 +/- 2 3. 6 <6 0 (a) <4 <100 (a) <50 (a) <7 110 +/- 80 August 08/15/86 <60 <60 <20 (a) <4 <300 (a) <100( a) <7 270 +/- 90 September 09/15/86 <50 <50 <0.3 <3 <70 (a) <30 ( a) <7 140 +/- 100 October 10/01-10/31 <50 60.5 +/- 34.8 <2 <4 <70 (a) <30 (a) <7 240 +/- 100 November 11/15/86 <50 111 +/- 35 <0.8 <4 <60 (a) <20 ( a) <9 170 +/- 100 Dece~ber 12/15/86 <60 <50 <7 <4 <100 ( a) <6 0 (a) <7 290 +/- 90 Aver.age +/- 71.7 +/- 70 205 +/- 131 2 s. d.

SURRY DIS. (SD)

January 01/01-01/31 <40 59.1 +/- 27.6 <l <3 <40 <15 <7 <140 February 02/01-02/28 <40 48.0 +/- 28.2 <l <3 <30 <10 <7 700 +/- 90 March 03/15/86 <30 <50 ( b) <2 <100 ( a) <50 ( a) <4 230 +/- 80 April 04/01-04/30 <50 <50 <0.5 <4 <70 (a) <30 ( a) <8 1490 +/- 120 May 05/15/86 <100 61.1+/-32.4 <200(a) <4 <2000(a) <700( a) <8 530 +/- 90 J u ne 1

06/15/86 <100 92.2 +/- 45.9 <2 O ( a) <5 <500 (a) <200( a) <10 690 +/- 90 J lJ l y 07/15/86 <50 119 +/- 36 <50 (a) <3 <100 ( a) <60 ( a) <6 170 +/- 80 August 08/15/86 <80 <50 <20 (a) <4 <400 (a) <100( a) <9 260 +/- 90 September 09/15/86 <40 104 +/- 28 <0.3 <3 <70 (a) <30 ( a) <7 350 +/- 110 October 10/01-10/31 <60 108 +/- 40 <l <4 <BO ( a) <30 ( a) <9 700 +/- 100 November 11/15/86 <50 174 +/- 30 <l <4 <BO ( a) <30 ( a) <7 390 +/- 100 December 12/15/86 <70 78.6 +/- 31. 2 <10 <4 <200 (a) <50 ( a) <9 850 +/- 100 P,verage +/- 93.8 +/- 77 578 +/- 755 2 s. d.

All other gamma emitters were <LLD.

(a) LLO not met because of late receipt of sample from the State of Virginia.

( b) 1-131 analysis not performed since samples received ~4 days after collection and 1-131 was not requested on the sample receipt form.

2. We 11 Water The results of analyses of well water samples are presented in Table 11. Well water was collected from four indicator locations during March, June, September and December. Tritium was measured in ten of the sixteen samples with an average activity of 230 pCi/£ and a range of 90 to 560 pCi/£. Each well water sample was also analyzed for gamma emitters and the results are presented in Table 11. All gamma emitters that may result from releases from the power station were below the detection limits .

49

TABLE 10 R/IUIOLOGICAL ENVIHONMENT/IL MONITORING l'ROGRIIM SUMM/lllY SURRY NUCLEAR POWER STATION DOCKET NO. 5-?80-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1986 ANALYSIS AND LOWER LJMJT NUMBER OF MEDIUM UR PATHWAY TOTAL NUMBER OF ALL INDICATOR LOC/ITIONS LOCATION WJTH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLEU OF ANALYSES DETECTION MEAN N/IME MEAN MEAN REPORT Ell (UNIT OF MEASUREMENT) PERFORMED (LLD) ( 1) R/INGE DISTANCE AND DIRECT ION RANGE RANGE MEASUREMENTS Well Water Tritium 16 100 220(10/16) ss 320(4/4) NONE 0

(.J"1 (pCi/ £) (90-560) (170-560) 0 Th-228 16 10. 7(1/16) HlR 10.7(1/4) NONE 0 (1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.

TABLE 11 VIRGINIA POWER - SURRY-1986 CONCENTRATIONS OF TR IT I UM AND GAMMA EMITTERS* IN WELL WATER pCi/£ +/- 2 Sigma DA TE STATION Be-7 K-40 I - 1 31 Cs-137 Ba-140 La-140 Th-228 H-3 FIRST QUARTER 03/18/86 BC <40 <70 <0.2 <6 <2 0 <7 <9 130 +/- 80 03/18/86 HJR <4 0 <100 <0.2 <5 <IO <6 10.7 +/- 4.2 90 +/- IO 03/18/86 JMTN <40 <60 <0.2 <5 <IO <5 <7 220 +/- 80 03/18/86 ss <30 <50 <0.2 <3 <10 <4 <7 240 +/- 80

<J1 SECOND QUARTER 06/17/86 BC <50 <100 <0.3 <5 <30 <10 <9 <110 06/17/86 HIR <30 <50 <0.3 <3 <2 0 <9 <8 <110 06/17 /86 JMTN <40 <60 <0.3 <3 <20 <10 <7 190 +/- 80 06/17 /86 ss <40 <50 <0.4 <4 <2 0 <9 <8 310 +/- 80 TH I RD QUARTER 09/16/86 BC <30 <40 <0.4 <3 <20 <8 <6 <140 09/16/86 HIR <40 <50 <0.3 <3 <20 <9 <7 130 +/- 100 09/16/86 JMTN <40 <50 <0.4 <3 <20 <10 <7 <140 09/16/86 ss <30 <40 <0.3 <3 <2 0 <8 <6 560 +/- 120 FOURTH QUARTER 12/16/86 BC <50 <80 <0.3 <6 <20 <6 <10 <130 12/16/86 HIR <40 <70 <0.4 <6 <10 <7 <10 160 +/- 100 12/16/86 JMTN <70 <ZOO <0.3 <7 <2 0 <8 <20 <130 12/16/86 ss <50 <200 <0.5 <5 <20 <7 <10 170 +/- 100

All other gamma emitters were <LLD.

C. Aquatic Exposure Pathway

1. Silt Sediment samples were collected in April and September from each of six locations and were analyzed by gamma spectroscopy. The results are presented in Table 13. A number of man-made and naturally occurring radioisotopes were measured in five samples from three loca-tions. The Surry Discharge location measured cobalt-58 activity with an average of 5124 pCi/kg (dry weight) with a range of 839 to 9410 pCi/kg (dry weight). These results were slightJy higher than samples taken at the same location in 1985 and the previous years samples. Cobalt-58 results from Hog Island Point and Point of Shoals were comparable to results from 1985 and remain close to the Lower Level of Detection (LLD) .

Cobalt-60 was measured in all twelve samples including the control location (CHIC). Surry Discharge was, as expected, the location with the highest activity measuring an average of 12535 pCi/kg (dry weight) with a range of 8070 to 17000 pCi/kg (dry weight). Samples taken at downstream location Hog Island Point, Surry Intake, Point of Shoals and Newport News indicate the dilution provided by the James River.

Cobalt-60 was also detected at the control location (CHIC) in both samples. All samples were generally higher than in previous years.

Cesium-134 was measured in all locations except Newport News with the highest location at Surry Discharg~. This location measured an average activity of 671 pCi/kg (dry weight) with a range of 599 to 743 pCi/kg (dry weight). The trend graphs indicate decreasing activity as compared to previous years.

Cesium-137 was measured in all samples, again with the highest at Surry Disc~arge location. The average at Surry Discharge was 2935 52

pCi/kg (dry weight) and a range of 2440 to 3430 pCi/kg (dry weight).

The average from all other sample locations was 923 pCi/kg (dry weight) and a range of 223 to 1550 pCi/kg (dry weight). The average from the control location (CHIC) was 943 pCi/kg (dry weight) and a range of 877 to 1010 pCi/kg (dry weight). The trend graphs generally indicate no long term increases in cesium-137 activity .

53

Co-58 1n SILT 10000

,,,,,, ~

I 1000

'>< ' = < LLD I\ *...

I.

(Jl p

1J I - ' ,.

I

\ I

""" C L.lr'-\ ' \. I I

I

.r

.I

~

I

. / ,,Y \ \I l

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)( xtf.:...... >< r ,)( .......

L

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8 100 **** .......... -* ...

)(*

I

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)(

10 I I

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I I I I I I 1972 1974 1976 1978 1980 . 1982 1984 1986

- Station Discharge Hog Island Station Intake

Co-60 1n SILT 100000 10000 I

I --

c..n c..n p

C l

I 1000 I )C I= < LLD I

I.

.. ,P"'

V

/"

't

~-'

'.~><-'I*-..

-* . ~ . , * '

/ , ~:\. I I

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LL&&&L!_..

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/

..__~.1-,IIL..;.-_ _.........

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..*. *.... *** ... ,I

_,,,,___~,,.____

._f- - - ~ " - - - -

k g -----,-

I *" *~. ..~

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'/ "' LL /

"P... u.,,,

~l. ~.--------

""'l'*

.,>< ,c' n K n ~

100 ~""

fl

__ ; _ ,

t . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

)(;

10 -f------4;-----4--;---+,----~.1-----1-,-.--~.~---+-,---+.----~.~---+-,----+.----~;~---+-,----1 1972 1974 1976 1978 1980 1982 1984 1986

- Station Discharge - Hog Island Station Intake

Cs-134 in SILT 10000 I )( * = < LLD * ,

1000 .,- ~

L u,

p C .r Jrf I I/

'\'

'\' ..

-- - ~

' "' I I

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g 100 10 I I I I I I . I I I I I I I 1972 1974 1976 1978 1980 1982 1984 1986

- Station Discharge Hog Island Station Intake

. Cs-137 in SILT p

C u, 1000

-..J 1 I

k 8

100 ......___._____~---'-----'----.......----1----...._--....____....____._____~--~----"..;....----I 1972 1974 1976 1978 1980 1982 1984 1986

- Station Discharge - Hog Island Station Intake * ** ** Chickahominy

TABLE 12 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1986 ANALYSIS AND LOWER LIMIT NUMBER~

MEDIUM OR PATHWAY TOTAL NUMBER OF ALL INDICATOR LOCATIQNS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD) (1) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Si 1t Gamma Spec 12 (pCi/kg dry)

Be-7 12 1330(2/10) POS 1620(1/2) 595(1/2) 0

( 1040-1620)

K-40 12 16420(10/10) POS 18350(2/2) 15650(2/2) 0 (13800-22800) (13900-22800} (15500-15800)

Cr-51 12 1430(1/10) SD 1430(1/2) -(0/2) 0

<.n

0) Mn-54 12 269(2/10) SD 269(2/2) -(0/2) 0 (210-328) (210-328)

Co-58 12 2160(5/10) SD 5125(2/2) -(0/2) 0 (96.3-9410) (839-9410)

Co-60 12 3228(10/10) SD 12535(2/2) 223(2/2) 0 (136-17000) (8070-17000) (160-285)

Cs-134 12 150 326( (8/10) SD 671(2/2) 186(1/2) 0 (123-599) (599-743)

Cs-137 12 180 1177(10/10) SD 2935(2/2) 944(2/2) **o (223-3430) (2440-3430) (877-1010)

Ra-226 12 2064(10/10) HIP 2450(2/2) 2855(2/2) 0 (1400-2580) (2320-2580) (2750-2960 Th-228 12 l?.95(10/10) SD 1435(2/2) 1470(2/2) 0 (835-1520) (1430-1440) (1380-1560)

(1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.

TABLE 13 (Page 1 of 2)

VIRGINIA POWER - SURRY-1986 CONCENTRATIONS OF GAMMA* EMITTERS IN SILT pCi/kg (dry) +/- 2 Sigma STAT JON CHIC HIP NN POS SD SI COLLECTION DATE 04/01/86 04/01/86 04/01/86 04/01/86 04/01/86 04/01/86 Be-7 <500 <500 <300 1620 +/- 510 <700 <600 K-40 15500 +/- 1600 14600 +/- 1500 15600 +/- 1600 22800 +/- 2300 17100 +/- 1700 16900 +/- 1700 tn

\0 Mn-54 <50 <40 <20 <50 210 +/- 72 <50 Co-58 <50 96.3 +/- 44.6 <30 141 +/- 49 839 +/- 92 <60 Co-60 160 +/- 44 2400 +/- 240 64.4 +/- 19.7 1050 +/- 110 8070 +/- 810 873 +/- 57 Cs-134 <60 160 +/- 45 <30 202 +/- 47 599 +/- 82 299 +/- 49 Cs-137 877 +/- 88 825 +/- 83 223 +/- 28 1270 +/- 130 2440 +/- 240 1550 +/- 160 Ra-226 2750 +/- 800 2320 +/- 640 1400 +/- 370 1910 +/- 520 2150 +/- 800 2280 +/- 710 Th-228 1380 +/- 140 1450 +/- 150 835 +/- 84 1470 +/- 150 1430 +/- 140 1520 +/- iso

All other gamma emitters were <LLD.

TABLE 13 (Page 2 of 2)

VIRGINIA POWER - SURRY-1986 CONCENTRATIONS OF GAMMA* EMITTERS IN SILT pCi/kg (dry)+/- 2 Sigma STATION CHIC HIP NN POS SD SI Average COLLECT ION DATE 09/10/86 09/10/86 09/10/86 09/10/86 09/10/86 09/10/86 +/- 2 s.d Be-7 595 +/- 230 <700 <500 <400 1040 +/- 450 <700 818 +/- 629 K-40 15800 +/- 1600 15300 +/- 1500 16700 +/- 1700 13900 +/- 1400 17600 +/- 1800 13800 +/- 1400 15517 +/- 3024 Cr-51 <400 <1000 <600 <600 1430 +/- 520 <1000 1430 +/- 520 a,

0 Mn-54 <30 <70 <50 <50 328 +/- 60 <60 328 +/- 60 Co-58 <30 312 +/- 74 <50 <50 9410 +/- 940 <70 4861 +/- 12867 Co-60 285 +/- 29 1270 +/- 130 136 +/- 40 286 +/- 48 17000 +/- 1700 . 548 +/- 69 3254 +/- 13492 Cs-134 186 +/- 28 340 +/- 59 <60 123 +/- 46 743 +/- 74 142 +/- 60 307 +/- 517 Cs-137 1010 +/- 100 1380 +/- 140 427 +/- 51 674 +/- 67 3430 +/- 340 998 +/- 100 1320 +/- 2167 Ra-226 2960 +/- 470 2580 +/- 740 1540 +/- 640 2580 +/- 620 2400 +/- 720 1480 +/- 620 2257 +/- 1214 Th-228 1560 +/- 160 1420 +/- 140 1090 +/- 110 1330 +/- 130 1440 +/- 140 961 +/- 96 1300 +/- 457

All other gamma emitters were <LLD.

2. Shoreline Sediment Four shoreline sediment samples were collected in April and November from two indicator locations and were analyzed by gamma spectrometry. The results are presented in Table 15. Naturally occurring potassium-40 was observed in all samples with an average of 4423 pCi/kg (dry) and a range of 2340 to 7060 pCi /kg (dry). Two samples measured ces i um-137 with an average activity of 82 pCi/kg (dry) and a ra~ge of 80.2 to 84.5 pCi/kg {dry).

Thorium-228 was observed in three samples with an average concentration of 93 pCi/kg (dry) and a range of 68.8 to 106 pCi/kg (dry). Radium-226 was observed in one sample with an activity of 391 pCi/kg (dry) .

61

TABLE 14 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1986 ANALYSIS AND LOWER LIMIT - NUMBER or--

MEDIUM OR PATHWAY TOTAL NIJ,1BER OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECT JON ME/IN NIIME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD) (1) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Shoreline Sediment Gamma Spec 4 (pCi/kg dry)

K-40 4 4423(4/4) HIR 6455(2/2) NONE 0 (2340-7060) (5850-7060)

Cl'\

N Cs-137 4 180 82.4(2/2) HIR 82.4(2/2) NONE 0 (80.2-84.5) (80.2-84.5)

Ra-226 4 391(1/4) HIR 391(1/2) NONE 0 Th-228 4 92.9(3/4) BURWELL'S 106(1/2) NONE 0 (68.8-106)

(1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.

TABLE 15 VIRGINIA POWER - SURR1-1986 CONCENTRATIONS OF GAMMA EMITTERS* IN SHORELINE SEDIMENT pCi/kg (dry) +/- 2 Sigma STATION HIR BURWELL'S HI R BURWELL'S AVERAGE COLLECTION DATE 04/08/86 04/08/86 11/18/86 11/18/86 +/- 2. s. d.

Be-7 <100 <2 00 <200 <200 K-40 5850 +/- 590 2340 +/- 230 7060 +/- 710 2440 +/- 240 4423 +/- 4797 Co-60 <20 <20 <20 <20 a, Cs-134 <10 <20 <20 <2 0 w

Cs-137 84.5 +/- 13.1 <20 80.2 +/- 15. 0 <20 82 +/- 6. 1 Ra-226 <300 <400 391 +/- 221 <400 391 +/- 221 Th-228 68.8 +/- 11.1 106 +/- 18 104 +/- 12 <40 93 +/- 42

All other gamma emitters searched for were <LLD.

D.. Ingestion Expbsure Pathway l; Milk The results of iodine-131 and gamma analysis of milk samples are presented in Table 17. A total of 60 analyses were performed, 48 from indicator locations and 12 from the control location. lodine-131, attributed to the Chernobyl accident was detected in six indicator locations and one control location during the months of May and June.

The activities ranged from 0.63 to 61.2 pCi/£ with each result referenced for radioactive decay to the collection date. From the remainder of the samples, 42 from indicator locations and 10 from the control location, no iodine-131 was detected. A lower limit of detection 0.5 pCi/£ or.

better was achieved in those 52 samples.

Cesium-137, which has been detected occasional.ly in recent years and attributed then to past atmospheric nuclear weapons testing (global fallout), was not measured in the milk samples, until the Chernobyl accident ea~ly in 1986. Beginning in May, cesium-137 was detected in five milk samples; four from indicator locations and one from the control location. The average cesium-137 activity was 10.6 pCi/£ with a range between 3.7 and 20.0 pCi/£ .. The required sensitivities for all other gamma emitting isotopes listed in Table 2 were met.

Milk samples from Lee Hall and Epps locatiohs were also analyzed for strontium-89 and strontium-90 during 1986. Strontium-89 was not detected in any of the samples. Strontium-90 was measured in 23 out of 24 samples with an average of 1:4 pCf/£ and a range of 0.81 pCi/£ to 2.2

pCi/£. For four months before radioactivity from Chernobyl reached the eastern U.S. the average strontium-90 of eight samples was 1.5 pCi/£ as 64

compared to 1.3 pCi/£ for the remainder of the year. Therefore, the Chernobyl accident did not increase the strontium-90 activity in milk samples. The strontium-90 activity is attributed to global fallout from past weapons tests. During the preoperational radiological monitoring program for Surry Power Station, strontium-90 was detected in milk samples in the range of 5.2 to 13 pCi/£ .

65

TABLE 16 RAOJOLOGJCAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NlJCLlAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1, to DECEMllER 31, 1986 ANALYSIS AND LOWER LIM IT NUMllER OF MEDIUM OR PATHWAY TOTAL NUMBER OF ALL INDICATOR LO CAT IONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NDNRDUTINE SAMPLED OF ANALYSES DETECTION MEAN NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD) (1) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Mi 1k Gamma Spec 60 (pCi/ £)

K-40 60 100 1283(48/48) CP 1358(12/12) 1305(12/12) 0 a,

a, (916-1510) (1230-1470) (1160-1460)

Cs-137 60 18 6.8(4/48) JDKS 20.0(1/12) 3. 7(1/12) 0 (9.1-20.0) 1-131 60 0.5 22.7(6/48) JDKS 34.8(2/12) 4. 7(1/12) 0 (1.4-61.2) (8.4-61.2)

Sr-89 27 5 -(0/26) NA NA -(0/1) 0 Sr-90 27 1 1.6(25/26) CP 3.7(1/1) 0.86(1/1) 0 (0.81-3.7)

( 1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision l, November 1979.

TABLE 17 (Page l of 3)

VIRGINIA POWER - SURRY - 1906 CONCENTRATIONS OF STRONTIUM-89 AND -90 AND GAMMA EMITTERS** IN MILK pCi/£ +/- 2 sigma MONTH NUCLIDE LEE HALL* EPPS* CP WMS JIJKS JANUARY Sr-89 <l <l Sr-90 l. 5 +/- 0.5 2.2 +/- 0.5 K-40 1300 +/- 130 1280 +/- 130 1380 +/- 140 1270 +/- 130 1260 +/- 130 Cs-137 <7 <4 <7 <4 <8 en

-.J I -131 <0.3 <0.3 <0.3 <0.2 <0.3 FEBRUARY Sr-89 <l <l Sr-90 l. 8 +/- 0.5 l. 7 +/- 0.6 K-40 1300 +/- 130 1350 +/- 140 1280 +/- 130 1300 +/- 130 1240 +/- 120 Cs-137 <5 <4 <4 <5 <3 1-131 <0.3 <0.4 <0.5 <0.2 <0.4 MARCH Sr-89 <2 <2 <l <1 <2 Sr-90 l. 4 +/- 0.6 l. 2 +/- 0. 7 3.7 +/- 0.7 0.86 +/- 0.48 3.2 +/- 0.7 K-40 1340 +/- 130 1300 +/- 130 1380 +/- 140 1370 +/- 140 1200 +/- 120 Cs-137 <4 <6 <4 <4 (4 1-131 <0.4 <0.5 <0.4 <0.2 <0.3 APRlL Sr-89 <1 <1 Sr-90 1. 3 +/- 0.6 1. 1 +/- 0.5 K-40 1370 +/- 140 1260 +/- 130 1300 +/- 130 1460 +/- 150 1340 +/- 130 Cs-137 <4 <4 <4 <4 <4 1-131 <0.3 <0.3 <0.3 <0.4 <0.3

St ate split

- A 11 other gamma emitters were LLD.

TABLE 17 (Page 2 of 3)

VIRGINIA POWER - SURRY - 1986 CONCENTRATIONS OF STRONTIUM-89 AND -90 AND GAMMA EMITTERS** IN MILK pCi/£ +/- 2 sigma MONTH NUCLIDE LEE HALL* EPPS* CP WMS JDKS MAY Sr-89 <3 <3 Sr-90 1.6 +/- 0.8 0.96 +/- 0.34 K-40 1420 +/- 140 1200 +/- 120 1470 +/- 150 1270 +/- 130 1050 +/- 110 Cs-137 <5 <4 6.82 +/- 3.64 <5 <6 m

I-131 <O. 5 1.4 +/- 0.6 50.l +/- 8.9 4.7 +/- 0.4 61.2 +/- 11.1 Cl)

JUNE Sr-89 <2 <l Sr-90 1.5 +/- 0.6 1.1 +/- 0.7 K-40 1380 +/- 140 1270 +/- 130 1240 +/- 120 1340 +/- 130 956 +/- 96 Cs-137 <5 <4 13.2 +/- 6.4 <4 20.0 +/- 6.3 I-131 0.63 +/- 0.31 2.0 +/- 0.3 3.2 +/- 0.3 <0.3 8.4 +/- 0.5 JULY Sr-89 <1 <1 Sr-90 1.2 +/- 0.6 1.2 +/- 0.6 K-40 916 +/- 92 1300 +/- 130 1230 +/- 120 1180 +/- 120 1070 +/- 110 Cs-137 <8 <6 <8 <4 <7 1-131 <0.5 <0.5 <0.4 <0.3 <0.5 AUGUST Sr-89 <2 <l Sr-90 0.99 +/- 0.63 0.81 +/- 0.43 K-40 1510 +/- 150 1260 +/- 130 1470 +/- 150 1370 +/- 140 1170 +/- 120 Cs-137 <4 <4 <6 <7 <5 I -131 <0.4 <0.5 <0.4 <0.4 <0.5

State split

- All other gamma emitters were LLD.

TABLE 17 (Page 3 of 3)

VIRGINIA PUWER - SURRY - 1986 CONCENTRATIONS OF STRONTILJM-89 ANO -90 AND GAMMA EMITTERS** IN MILK pCi/£ +/-?. sigma MONTH NUCLIDE LEE HALL* EPPS* CP WMS JDKS SEPTEMBER Sr-89 <2 <l Sr-90 1.2 +/- 0.7 1.1+/-0.7 K-40 1450 +/- 150 1180 +/- 120 1420 +/- 140 1270 +/- 130 1110 +/- 110 Cs-137 9.08 +/- 3.77 <4 <4 <4 <5 1-131 <0.4 <0.4 <0.5 <0.3 <0.4 OCTOBER Sr-89 <4 <3 Sr-90 1.9 +/- 0.7 1.8 +/- 0.7 K-40 1310 +/- 130 1150 +/- 120 1300 +/- 130 1320 +/- 130 1300 +/- 130 Cs-137 <5 <4 <7 (4 <7 I -131 <0.3 <0.3 <0.3 (0.3 <0.3 NOVEMBER Sr-89 <4 <5 Sr-90 1.6 +/- 0.9 <0.7 K-40 1360 +/- 140 1280 +/- 130 1410 +/- 140 1160 +/- 120 1140 +/- 110 Cs-137 <8 <6 <5 <7 <5 1-131 <O. 2 <0.3 <0.5 <0.4 <O. 5 DECEMBER Sr-89 <5 <5 Sr-90 1.5 +/- 0.8 1.2 +/- 0.8 K-40 1390 +/- 140 1360 +/- 140 1420 +/- 140 1350 +/- 140 1210 +/- 120 Cs-137 <5 <4 <6 3.71 +/- 1.95 <4 1-131 <0.4 <0.4 <0.4 <0.3 <0.3

State Split

- All other gamma emitters were <LLD.

2. Aquatic Biota Marine biota can be sensitive indicators of radionuclide accumula-tion in the environment because of their ability to concentrate certain chemical elements which have radioactive isotopes. Gamma spectrometry was performed on bi-monthly samples of clams and oysters from the James River,. The results are shown in Table 19 for clams and Table 20 for oysters. As expected, naturally occurring potassium-40 was the nuclide most frequently detected.

For the clam samples the average potassium-40 activity was 575 pCi/kg (wet weight) with a range from 246 to 1010 pCi/kg (wet weight).

Thorium-228, also naturally occurring, was measured in one sample from

the Chickahominy River location (CHIC) with an activity of 97.5 pCi/kg (wet weight). Cobalt-58 was measured. in two samples at the Surry Discharge (SD) location with an average activity of 65 pCi/kg (wet weight) and a range of 61.8 to 69 pCi/kg (wet weight)~ Cobalt-60 was measured in five samples from Surry Discharge with an average of 60.7 pCi/kg (wet weight) and a range of 52.0 to 74.2 pCi/kg (wet weight); and four samples from Hog Island Point measured an average of 46.2 pCi/kg (wet weight) with a range of 32.0 to 59.7 pCi/kg (wet weight). Cobalt-60 activity measured in the 1986 clam samples indicated a similar range as the activity measured in the 1985 clam samples taken at the same loca-tions. Cesium-137 was also measured in five samples from one control location and three indicator locations with an average of 26.8 pCi/kg (wet weight) and a range of 21.1 to 36.7 pCi/kg (wet weight). All positive results showed activity to be present in quantities well below the required sensitivities as listed in Table 2.

70

For oyster samples the average potassium-40 activity for 17 of the 18 samples was 1386 pCi/kg (wet weight) with a range of 326 to 11800 pCi/kg (wet weight). Cesium-137 was measured in one sample from the Newport News location with an activity of 30.5 pCi/kg (wet weight).

Thorium-228 was also measured in one sample from the Point of Shoals location with an activity of 109 pCi/kg (wet weight).

During July, August, and September, crabs were collected from the Surry Discharge (SD) location and analyzed by gamma spectrometry.

Naturally occurring potassium-40 was found in all three samples, with an average activity of 2423 pCi/kg (wet weight) and a range of 2210 to 2760 pCi/kg (wet weight) as presented in Table 21 .

Four fish samples (perch and catfish) were collected during February, March, August and September from the same Surry Discharge location (SD).

The results of gamma spectrometry on these samples are presented in Table 22. The September, 1986 catfish sample missed the LLD for cesium and was re-sampled on January 27, 1987. The results of this analysis is also presented on Table 22. One sample showed positive results for cesium-137 and was measured at 45.5 pCi/kg (wet weight). In comparison with the 1986 data, all fish samples taken in 1985 measured cesium-137 with an average activity of 87.1 pCi/kg (wet weight) .

71

Co-58 in CLAM SAMPLES 1000

. )( I

= < LLD

'* \

Required LLD - 130 pCi/kg p 100

~A*,A*,,~VM_V,,ll-WN,

_/'

,.;;, )(*"*'".W,*-,.*.*,,*,* x-**.*.*=,**.*=,.,.)(,A".WAW,N="U.W, ) ( W . ~ V N N . . . . . . . . . . . W - ~ * " * " , W * - Y N

,. -,.u*,w

-....J

~

C I

a

.. ' ** '" \. /

/

~, -

i I

\.

V

/

x..

- ~

k '*, '\.

g )(.'

'* '* ,-., '\.

r-:7:T ** ~ ) (

)(

10 I I

I I I I I I

I I

I I .

I 1974 1976 - 1978 1980 1982 1984 1986

- Surry Discharge Chickahominy Hog Island

Co-60 in CLAM SAMPLES 1000 I

)(

I

- <LLD

\ Required LLD - 130. pCi/kg

~.."' '

,11.*.*.*,1.*N11.-.*1H,l',-.Y,"NAV,l,,1,*1.,*.*1N,1,.,.*N.*,1.*,N,Y,'.I','~,* _A><-,m--.w.*.*.*)(,_,_,,m,~*xu.*.-,.-,AWN'N,'No )("=Nh'-",-,NNWV'~--M"-rll ,,...,,,.

. *~"

-.....J t,J p 100 '- T

~

C '- ~ ;

~. *' ' "----

~ /

l F=-->

.--..... /

I k

g

' *'* I I *'

.. ,* ,* )(

~

r.*,,~

., **0-------

'* )(

1 .. )CI*** PI*****><

10 .. I I I

I I I I

I I

I .

I I I I I

I I

1974 1976 1978 1980 1982 1984 1986

- Surry Discharge Chickahominy Hog Island

Cs-137 in CLAM SAMPLES 1000

)( I

= < LLD Required LLD - 150 pCi/kg

.........,.\",'.0. - A Y . " A W r V I N \ W A _

_ v . _ . . , , . , , , , , . , _ . _ ,...,.......\","*"N,"A\."o..",WN)(""v.¥.""'""*"*"*\"o""'..,.,.,.,. )("""""~"....\._'Yl,_.,.NIYA>< -*-x*-*=**,-)(,. . VN,W,*.-

A -~w..--.*.*.,*.*,*,,.*,*,*.v,.,._

~ P 100 .....~ ...

C *1

\.

III '

i I ....... ::..

\. "

"' '?.*-~ - 1/

.If/

r1

"--~

~-

~

k g - \ / ' _/::.J

'\. ~

)(~

.... )( I

- - ,II** a.A.!.'.

10 I I

I I

I I .

I

.*

I I I

I 1974 1976 . 1978 1980 1982 1984 1986

- Surry Discharge Chickahominy Hog Island

TABLE 18 (Page 1 of 2)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1986 ANALYSIS AND LOWER LIMIT NUMIJER OF MEDIUM OR PATHWAY TOTAL NUMBER OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN N/\ME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD) (1) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Clams Gamma Spec 30 (pCi/kg wet) K-40 588(21/24) LC 654(5/6) 528(6/6) 0

...., (246-1010) (356-1000) (387-942)

(J1 Co-58 130 65.4(2/24) SD 65.4(2/6) -(0/6) 0 (61.8-69.0) (61.8-69.0)

Co-60 130 54.3(9/24) SD 60.7(5/6) -(0/6) 0 (32.0-74.2) (52.0-74.2)

Cs-137 150 28.3(4/24) LC 36.7(1/6) 21.1 ( 1/6) 0 (22.3-36.7)

Th-228 -(0/24) CHIC 97 .5(1/6) 97.5(1/6) 0 Oysters Gamma Spec 18 (pCi/kg wet) K-40 1386(17 /18) NN 3286(5/6) NONE 0 (326-11800) (592-11800)

Cs-137 18 150 30.5(1/18) NN 30.5(1/6) NONE 0 Th-228 18 109(1/18) POS 109(1/6) NONE 0 Crabs Gamma Spec 3 2423(3/3) SD 2423(3/3) NONE 0 (pCikg wet) K-40 (2210-2760) (2210-2760)

( 1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.

TABLE 18 (Page 2 of 2)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1986 ANALYSIS ANO LOWER LIMIT NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECT ION ME/IN NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD) (1) RANGE DISTANCE ANO DIRECTION RANGE RANGE MEASUREMENTS cr, Fish Gamma Spec 5

( pCi /kg wet)

K-40 5 100 1526(5/5) so 1526(5/5) NONE 0 (791-2850) (791-2850)

Cs-137 5 60 45.5(1/5) so 45.5(1/5) NONE 0

( 1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 19°79.

TABLE 19 VIRGINIA POWER - SURRY - 1986 CONCENTRATIONS OF GAMMA EMITTERS* CLAMS pCi/kg (wet) +/- 2 Sigma SAMPLE STATION DATE TYPE Be- 7 K-40 C0-58 C0-60 CS-137 Ra-226 TH-228 CHIC 01/10/86 Clams <500 942 +/- 301 <40 <3 0 <30 <400 97.5 +/- 39.6 04/01/86 Clams <300 388 +/- 218 <2 0 <ZO <2 0 <400 <40 05/15/86 Clams <300 481 +/- 152 <2 0 <20 <20 <400 <30 07 /2 3/86 Clams <Z 00 387 +/- 127 <20 <10 21.1 +/- 12.0 <300 <30 09/10/86 Clams <200 458 +/- 157 <20 <20 <20 <400 <40 11/25/86 Clams <100 510 +/- 140 <10 <2 0 <10 <300 <30 JMTN 01/10/86 Clams <200 330 +/- 158 <20 <20 <10 <300 <30 04/01/!:!6 Clams <2 00 469 +/- 253 <20 <20 <2 0 <400 <40 05/15/86 Clams <300 540 +/- 226 <3 0 <2 0 <30 <400 <40

__, 07/14/86 Clams <300 500 +/- 183 <30 <20 <2 0 <400 <40

__, <400 <50 09/10/86 Clams <300 853 +/- 187 <30 <30 <30 11/25/86 Clams <200 <600 <ZO <20 <ZO <400 <40 SD 01/10/86** Clams <200 404 +/- 110 <20 68.3 +/- 16.7 <20 <400 <30 02/27/86** Clams <300 354 +/- 176 <30 56.l +/- 17.4 22.3 +/- 10.6 <400 <30 05/08/86** Clams <ZOO 590 +/- 141 <20 52.9 +/- 14.5 <20 <300 <30 07/10/86** Clams <300 1010 +/- 240 <40 <30 <30 <600 <50 09/02/86** Clams <300 642 +/- 262 61.8 +/- 25.8 52.0 +/- 20.5 27.3 +/- 13.2 <400 <40 11/06/86** Clams <200 797 +/- 153 69.0 +/- 19.3 74.2 +/- 17.4 <20 <400 <30 HIP 01/10/86 Clams <200 429 +/- 137 <2 0 32.0 +/- 12.1 <20 <300 <30 04/01/86 Clams <2 00 246 +/- 119 <20 57.0 +/- 18.l 26.7 +/- 9.8 <400 <30 05/15/86 Clams <200 <300 <2 0 <10 <Z 0 <300 <30 07/14/86 Clams <ZOO 614 +/- 179 <20 <20 <20 <300 <30 09/10/86 Clams <200 488 +/- 216 <30 59.7 +/- 23.9 <30 <400 <40 11/25/86 Clams <100 814 +/- 139 <20 36.3 +/- 13.4 <2 0 <300 <30 LC 01/10/86 Clams <300 449 +/- 165 <30 <30 <20 <400 <40 04/01/86 Clams <200 356 +/- 141 <20 <2 0 <20 <400 <40 06/02/86 Clams <300 <700 <30 <30 <30 <500 <50 07 /14/86 Clams <2 00 900 +/- 162 <2 0 <20 <20 <300 <JO 09/10/86 Clams <2 00 1000 +/- 210 <20 <20 36.7 +/- 15.8 <400 <30 11/25/86 Clams <200 564 +/- 214 <20 <20 <2 0 <400 <30

All other gamma emitters were <LLD.

- State Split

TABLE 20 VIRGIN I A POWER - SURRY - 1986 CUN CE NTl<AT IONS OF GAMMA EM ITH.RS* OYSTERS pCi/kg ( we I.) +/- 2 Sigma

- - - - - - - - - - - - - ------- ---***-**-*------- - - - - - - - - - ~ - - - - - - - - - - - * - ---- - - - - -- . ---- ------**-*------

SAMPLE TH-228 DATE TYPE Be-7 K-40 C0-58 C0-60 CS-137 Ra-226 STATION --------

Oysters <Z 00 592 +/- 134 <Z 0 <10 <10 <300 <30 NN 01/10/86** <400 <50 02/26/86** Oysters <500 2170 +/- 300 <40 <30 <30

<500 <700 . <4 0 <Z 0 <30 <400 <50 05/07/86** Oysters <30 Oysters <2 00 1130 +/- 160 <20 <Z 0 <20 <300 07/09/86** <300 <30 09/11/86** Oysters <200 737 +/- 127 <10 <10 <10

<300 11800 +/- 1200 <30 <20 30.5 +/- 17. 7 <400 <40 11/05/86** Oysters co

<200 567 +/- 162 <20 <2 0 <20 <300 <30 DWS 01/10/86 Oysters <30 Oysters <200 394 +/- 168 <20 <20 <20 <400 04/01/86 <400 <40 06/02/86 Oysters <ZOO 635 +/- 175 <30 <2 0 <20 416 +/- 165 <20 <20 <20 <300 <30 07/14/86 Oysters <2 00 <50 Oysters <300 1140 +/- 240 <30 <30 <30 <500 09/10/86 <400 <30 11/25/86 Oysters <100 579 +/- 159 <10 <10 <20

<2 00 326 +/- 134 <20 <2 0 <20 (400 109 +/- 18 POS 01/10/86 Oysters <300 <30 04/01/86 Oysters <200 335 +/- 166 <20 <10 <10 505 +/- 127 <ZO <10 <20 <400 <40 06/02/86 Oysters <200 <40

<300 540 +/- 173 <30 <20 <20 <300 07 /14/86 Oysters <300 <30 Oysters <200 949 +/- 150 <20 <2 0 <20 09/10/86 <20 <400 <40 11/25/86 Oysters <200 751 +/- 175 <20 <2 0

All other gamma emitters were <LLD.

- State split

TABLE 21 VIRGINIA POWER - SURRY - 1986 CONCENTRATIONS OF GAMM/\ EMITTERS* IN CRABS pCi/kg (wet) +/- 2 Sigma SAMPLE STATION DATE TYPE Be-7 K-40 --*----- C0-58 C0-60 CS-137 Ra-226 TH-228 SD 07/29/86 Crabs <300 2210 +/- 320 <30 <3 0 <30 <600 <50 SD 08/27/86 Cr abs <300 2760 +/- 310 <40 <30 <30 <500 <60

"-J

"° SD 09/25/86 Crabs <400 2300 +/- 270 <30 <30 <30 <400 <50 Average+/- 2423 +/- 590 2 s. d.

All other gamma emitters were <LLD.

TABLE 22 VIRGINIA POWER - SURRY - 19B6 CONCENTRATIONS OF GAMMA* EMITTERS IN FISH pCi/kg (wet) +/- 2 sigma COLLECTION SAMPLE DA TE STATION TYPE K-40 Co-58 Cs-134 Cs-137 02/24/86 SD CATFISH 1240 +/- 280 <30 <30 45.5+/-24.1

.03/13/86 SD PERCH 1620 +/- 530 <50 <50 <50

. CXl 0

08/27/86 SD PERCH 1130 +/- 4 30 <60 <60 <60 09/02/86 SD CATFISH 2850 +/- 1200 <100 <200 ( a) <200 ( a) 01/27/87 SD CATFISH 791 +/- 189 <20 <20 <2 0 Average+/- 1526 +/- 1594 45.5 +/- 24.l 2 S. D.

All other gamma emitters were below <LLD.

(a) LLD's not met due to low sample volume of 0.036 Kg available.

3. Food Products Nine food samples were collected from four locations and analyzed by gamma spectrometry. The samples consisted of kale, cauliflower, cabbage, corn, soybeans and peanuts. Naturally occurring potassium-40 was observed in all samples with an average activity of 6919 pCi/kg (wet weight) and a range of 2840 to 14440 pCi/kg (wet weight). Cosmogenic beryllium-? was measured in one sample from the Poole's Garden location with an activity of 284 pCi/kg (wet weight). Cesium-137 was measured during June in two samples with an average activity of 17.5 pCi/kg (wet weight) and a range of 15.9 to 19.1 pCi/kg (wet weight). The measure-ments can be attributed to the Chernobyl accident. All other gamma emitters were below detection limits .

81

1ABLE 23 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR.POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1986 ANALYSIS AND LOWER LIMIT N MEDIUM OR PATHWAY TOTAL NUMBER OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD) (1) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Vegetation Gamma Spec 9 (pCi/kg wet) K-40 6919(9/9) SLADE's 8067(3/3) NONE 0 (X)

(2840-14400) (3000-14400)

N Be-7 9 100 284(1/9) POOLE'S 284(1/1) NONE 0 Cs-137 9 20 17.5(2/9) CARTER'S 19.1(1/2) NONE 0 (15.9-19.1)

(1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.

TABLE 24 VIRGINIA POWER - SURRY - 1986 CONCENTRATIONS OF GAMMA* EMITTERS IN VEGETATION pCi/kg (wet) +/- 2 sigma SAMPLE COLLECTION STATION TYPE DATE Be-7 K-40 1-131 Cs-134 Cs-137 Carter's Garden** -Cauliflower 06/24/86 <100 5620 +/- 560 <10 <1 <10 Poole's Garden** Kale 06/24/86 284 +/- 73 6430 +/- 640 <10 <10 15.9 +/- 7. 4

())

w Carter's Garden** Cabbage 06/30/86 <200 2840 +/- 280 <6 <10 19. 1 +/- 10. g Brock's Garden Peanut's 10/08/86 <100 5850 +/- 590 <20 <10 <10 Brock's *Garden Corn 10/08/86 <100 3330 +/- 330 <3 0 <20 <2 0 Slade's Garden Peanuts 10/09/86 <100 6800 +/- 680 <20 <10 <10 Slade's Garden Corn 10/09/86 <200 3000 +/- 300 <30 <20 <20 Brock's Garden Soybeans 12/11/86 <200 14000 +/- 1400 <20 <10 <10 Slade's Garden Soybeans 12/11/86 <100 14400 +/- 1400 <20 <10 <10 Average+/- 284 +/- 73 6919 +/- 8777 17.5 +/- 4.5 2 s. d.

All other gamma emitters were <LLD.

- State Split

J. Direct Rad i at ion Environmental radiation dose-rates determined by thermoluminescent dosimeters (TLDs) are given on Table 26 and 27. Two sets of TLD badges of four readout areas each were deployed quarterly at each location. The mean values of four readings (calibrated individually for response to a known dose and for intransit expcisure) are reported in this table, unless indicated otherwise.

Table 25 provides a statistical summary of the four quarters 1986 data~

Individual measurements of external radiation levels in the environs of the Surry site for stations 02 through 43 had an average dose of 6.7 mR/standard month. The average dose for the control stations (39,40) was 6.1 mR/standard

month with a range of 4.9 to 7.5 mR/standard month. The indicatqr locations had an average activity of 6.7 mR/standard month with a range of 4.1 to 9.2 mR/standard month.

A trend graph is provided indicating a plot of TLDs located at the site boundary and approximately 5 miles from the Station.

84

DIRECT RADIATION MEASUREMENT-TLD RESULTS 10 Irl R 8 00 I

(.n Dl 0 6 n

t b 4 2

1980 1981 1982 1983 1984 1985 1986

- Site Boundary TLDs 5 Mile TLDs

TAflLE 25 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1986 ANALYSIS AND LOWER LIMIT NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER OF ALL INDICATOR LOCATIONS LOC/\TION WITH HIGHEST MEAN CONTROL LOCATION NONROUTIN[

SAMPLED OF ANALYSES DETECTION ME/IN NAME ME/IN MEAN REPOl{TED (UNIT OF MEASUREMENT) PERFORMED (LLD) R/\NGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS TLDs Gamma Dose 331 2 6.7(315/315) 38 8.6(8/8) 6.1(16/16) 0 (mr/std. month) (4.1-9.2) (8.1-9.2) (4.9-7.5)

TABLE 26 (Page of 2)

VIRGINIA POWER - SURRY - 1986 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS mR/rnonth +/- 2 Si gm a - Set 1 - 098 STATION AVERAGE NUMBER FIRST QUARTER SECOND QUARTER TH I RD QUARTER FOURTH QUARTER +/- 2 s. d.

02 7 . 1 +/- 0. 5 8.0 +/- 0. 3 7.9 +/- 0.3 8.8 +/- 0.2 8.0 +/- 1. 4 03 (a) 4. 6 +/- 0.6 4. 1 +/- 0.4 5. 1 +/- 0.3 4.6 +/- 1. 0 04 6.3 +/- 0.7 6. 9 +/- 0.8 6.9 +/- 0.4 7. 5 +/- 0.4 6. 9 +/- 1. 0 05 (a) 6.8 +/- 0.5 7.0 +/- 0.5 7.2 +/- 0. 3 7.0 +/- 0.4 06 6. 1 +/- 0. 3 7. 5 +/- 0.1 7.4 +/- 0. 5 7. 8 +/- 0.2 7. 2 +/- 1. 5 07 6.0 +/- 0.4 7. 3 +/- 0.4 7. 0 +/- 0.5 7. 2 +/- 0.3 6.9 +/- 1. 2 08 8.4 +/- 1. 1 6.8 +/- 0.3 6. 7 +/- 0.6 7. 2 +/- 0.1 7. 3 +/- 1. 6 0)

-.J 09 6.6 +/- 0.5 6. 5 +/- 1. 2 7. 2 +/- 1. 0 7.4 +/- 0.4 6.9 +/- 0.9 10 6.8 +/- 1. 1 7.6 +/- 0.4 7. 1 +/- 0.3 7.0 +/- 0.3 7. 1 +/- 0.7 11 7.6 +/- 0.9 6. 7 +/- 0.9 7. 1 +/- 0.4 7. l +/- 0.2 7. 1 +/- 0. 7 12 7.0 +/- 1. 0 6. 9 +/- 0.6 7.4 +/- 0.6 7. 2 +/- 0.3 7. 1 +/- 0.4 13 8.0 +/- 0.6 7.0 +/- 0.6 7. 2 +/- 0.7 7. 5 +/- 0.5 7.4 +/- 0.9 14 6.8 +/- 0.5 7. 1 +/- 0.8 7. 2 +/- 0.8 7. 3 +/- 0.4 7. 1 +/- 0.4 15 6. 3 +/- 0.9 6.9 +/- 0.6 7. 3 +/- 2. 5 7.0 +/- 0.4 6.9 +/- 0.8 16 7. 1 +/- 0.5 7. 0 +/- 0.3 6. 9 +/- 0.3 7.0 +/- 0. 3 7,0 +/- 0.2 17 6.8 +/- 0.8 6. 4 +/- 0.2 6. 2 +/- 0.6 6.3 +/- 0. 5 6.4 +/- 0.5 18 5. 6 +/- 0.8 5. 5 +/- 0.3 5. 4 +/- 0.5 5.9 +/- 0.4 5.6 +/- 0.4 19 5. 3 +/- 0.6 6. 1 +/- 0. 5 6. 1 +/- 0.7 6.6 +/- 0.4 6.0 +/- 1. 1 20 7. 0 +/- 0.5 5. 7 +/- 1. l 5.7 +/- 0.4 6. 1 +/- 0.2 6.1 +/- I. 2 21 6. 5 +/- 1. 6 6. 2 +/- 0.5 6.3 +/- 0. 2 6. 6 +/- o. 6 6.4 +/- 0.4 (a) TLD Vandalized

TABLE 26 (Pnge 2 of 2)

VIRGINIA POWER - SURRY - 1986 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS mR/day +/- 2 Sigma - Set 1 - 098 AVERAGE

+/- 2 s.d.

STATION ____!.t!JRD QUARTER _ _ _ _ FOURTH QUARTER NUMBER FIRST QUARTER SECOND QUARTER 6.4 +/- 0.4 6. I :!. 0. 5 5.8 +/- 0.5 6.0 +/- 0.7 22 6.0 +/- 0.4 6.7 +/- 0.3 6.4 +/- 1.6 6.2 +/- 0.6 7.3 +/- 1.1 23 5.4 +/- 0.9 6.7 +/- 0.4 6.5 +/- 0.5 6.b +/- 0.4 6. 1 +/- 0.5 24 6.5 +/- 0.8 7.2 +/- 0.4 7.3 +/- 1.3 7.7 +/- 0.4 6.4 +/- 0.6 25 7.9 +/- 0.5 6.2 +/- 0.2 6.4 +/- 0.8 6.4 +/- 0.4 6.1 +/- 0.6 26 7.0 +/- 1.0 5.9+/-0.1 5.9 +/- 0.5 b.3 +/- 0.9 5.8 +/- 0.8 27 5.7 +/- 0.7 6.6 +/- 0.4 6.4 +/- 0.4 6.3 +/- 0.3 6.2 +/- 0.2 28 6.6 +/- 0.8 5.7 +/- 0.3 5.8 +/- 0.4 5.9 +/- 0.4 5.6 +/- 0.4 29 6.0 +/- 0.6 6.2 +/- 0.2 6.5 +/- 1.3 co 6.0 +/- 0.2 6.2 +/- 1.4 co 30 7.4 +/- 1.2 5.7 +/- 0.5 5.9 +/- 0.4 6.2 +/- 0.6 5.8 +/- 0.2 31 5.8 +/- 0.5 6.0 +/- 0.2 5.8 +/- 1.1 6.0 +/- 0.4 6.3 +/- 0.5 32 5.0 +/- 0.5 6.7 +/- 0.3 6.5 +/- 0. 7 6.8 +/- 0.8 6.4 +/- 0.7 33 6.0 +/- 0.3 7.0 +/- 0.3 6.6 +/- 1.0 6.8 +/- 1.0 6.5 +/- 0.4 34 5.9 +/- 0.6 7.9 +/- 0.3 7. 7 +/- 0.5 7.3 +/- 0.8 7.6 +/- 0.7 35 7.8 t*0.6 7.7 +/- 0.6 7.8 +/- 1.3 7.0 +/- 0.8 7.9+/-1.1 36 8.6 +/- 1.0 6.9 +/- 0.4 7.1 +/- 1.2 6.7 +/- 0.2 6.8 +/- 0.4 37 8.0 +/- 0.7 8.5 +/- O.b 8.5 +/- 0.7 8.1 +/- 0.9 8.8 +/- 1.7 8.4 +/- 0.4 38 6. 7 +/- 0. 7 6.7 +/- 0.7 6.3 +/- 0.4 7.1 +/- 1.0 6.8 +/- 0.9 39 5.5+/-1.1 4.9 +/- 0.3 5.7 +/- 0.2 40 6.2 +/- 0.4 5.3 +/- 0.3 6.6 +/- 0.4 7.0 +/- 1.3 6.3+/-1.1 7.5 +/- 0.7 41 7.6 +/- 1.5 6.7 +/- 0.4 6.9 +/- 1.4 6.7 +/- 0.5 6.3 +/- 0.8 42 7.9 +/- 1.2 6.1 +/- 0.3 5.8 +/- 1.1 6.2 +/- 0.7 5.8 +/- 0.1 43 5.0 +/- 0.4 6.6 +/- 1.7 6.8 +/- 1.5 6. 7 +/- 0.2 Average 6.7 +/- 2.0 6.6 +/- 1.4

+/- 2 s. d.

TABLE 27 (Page of 2)

VIRGINIA POWER - SURRY - 1986

[)IRE CT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS mR/month +/- 2 Sigma - Set z - 099 STATION AVERAGE NUMBER FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER +/- z s. d.

02 7. 2 +/- 1. 7 8.3 +/- 0.7 8.3 +/- 0.6 8. 7 +/- 0.8 8. 1 +/- 1. 3 03 (a) 4.3 +/- 0.4 4.3 +/- 0. 2 5. 1 +/- 0.6 4.6 +/- 0.9 04 5. 5 +/- 1. 2 6.8 +/- 0.3 7.6 +/- 0. 7 7. 4 +/- 0. 1 6.8 +/- 1. 9 05 (a) 6. 7 +/- 0.8 7. 1 +/- 0.3 7.5 +/- 0.8 7. 1 +/- 0.8 06 6.5 +/- 0.7 7. 1 +/- 0.5 7.6 +/- 0.6 8.2 +/- 0. 2 7.4 +/- 1. 4 07 6. 3 +/- 1. 0 6. 9 +/- 0. 5 6. g +/- 0.4 7.4 +/- 0.2 6.9 +/- 0. 9 08 6.9 +/- 2.. 0 6.8 +/- 0.6 6.9 +/- 0.4 7.5 +/- 0.3 7.0 +/- 0.6 a, 09 6.1 +/- 0.6 6. 3 +/- 0.3 7. 1 +/- 0.6 7. 5 +/- 0.8 6.8 +/- 1. 3

\D 10 6.5 +/- 0.8 6. 5 +/- 0.3 7.4 +/- 0. 5 7. 4 +/- 0. 2 7.0 +/- l. 0 11 6.0 +/- 1. 1 6.4 +/- 1. 7 7.7 +/- 0.5 7.4 +/- 1. 5 6.9 +/- 1. 6 12 7. 8 +/- 0.9 7.2 +/- 0. 5 7. 5 +/- 0.5 7. 7 +/- 0.9 7.6 +/- 0.5 13 6. 5 +/- 0.7 7.0 +/- 0.5 7.3 +/- 0.5 8. 2 +/- 0.1 7. 3 +/- 1. 4 14 6.6 +/- 0.7 7. 7 +/- 1. 3 7. 5 +/- 0.4 7. 9 +/- 0. 5 7.4 +/- 1. 1 15 5. 7 +/- 0.6 6. 4 +/- 0.5 6.7 +/- 0.9 7. 3 +/- 0.3 6.5 +/- 1. 3 16 5. 8 +/- 0.7 7. 2 +/- 1. 1 7. 2 +/- 1. 1 7.8 +/- 0.6 7.0 +/- 1. 7 17 6.2 +/- 0.7 6.4 +/- 0.6 6.4 +/- 0.4 6. 7 +/- 0.2 6.4 +/- 0.4 18 4.8 +/- 1. 0 5.5 +/- 0.3 (a) 6.1 +/- 0. 2 5.5 +/- 1. 3 19 5.5 +/- 0 ._3 6.2 +/- 0. 3 6. 3 +/- 0. 3 7. 0 +/- 0.3 6.3 +/- 1. 2 20 4. 7 +/- 0.5 5.8 +/- 0.2 6.0 +/- 0.6 6.5 +/- 0.8 5.8 +/- 1. 5 21 4.8 +/- 0.9 6.0 +/- 0.5 6. 1 +/- 0.7 6.8 +/- 0. 2 5.9 +/- 1 . 7 (a) TLD Vandalized

TABLE 27 (Cont.)

(Page 2 of 2)

VIRGINIA POWER - SURRY - 1986 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLU RESULTS mR/month +/- 2 Sigma - Set 2 - 099 STATION AVERAGE NUMBER FIRST QUARTER SECOND (jUARTER TH I RD QUARTER FOURTH QUARTER +/- 2 5. d.

22 5.2 +/- 0. 7 5. 7 +/- 0.3 5.8 +/- U. 1 6. 6 +/- 0.3 5.8 +/- 1. 2 23 5. 5 +/- U. 3 5.9 +/- 0.2 6.4 +/- 0.5 6.8 +/- U.4 6.2 +/- 1. 1 24 6. 1 +/- 1. 5 5. 7 +/- 0. 6 6.6 +/- 0.5 6. 9 +/- 0.2 6. 3 +/- 1 . 1 25 6.3 +/- 0. 4 6.3 +/- 0.3 6.5 +/- 0.3 7. 6 +/- 0. 9 6. 7 +/- 1. 2 26 4. 9 +/- 0.4 6. 8 +/- 0. 7 6.2 +/- 0. 5 6.8 +/- 0.7 6. 2 +/- 1. 8 27 5.4 +/- 1. 2 6.2 +/- 0.4 5.6 +/- 0.4 6.6 +/- . 0. 2 6.0 +/- 1 . l 28 5.4 +/- 0.7 6. 7 +/- 0. 3 6. 5 +/- 0. 6 7. l +/- 0. 4 6.4 +/- 1. 5 29 4. 6 +/- 1. 4 6. l +/- 0.4 5.8 +/- 0.3 6. l +/- 0. l 5. 7 +/- 1. 4 0

30 5. 5 +/- 0.5 6.2 +/- 0. 3 5. 7 +/- 0. 4 6.9 +/- 0. 4 6. l +/- 1. 2 31 5.2 +/- 0. 7 6.0 +/- 0.4 5.6 +/- 0. 3 6.6 +/- 0. l 5.9 +/- 1. 2 32 5.0 +/- 0.9 6. 5 +/- 0.3 6. l +/- 0.6 6.6 +/- 0.2 6. l +/- 1. 5 33 5. 3 +/- 1. 0 6. 9 +/- 0.6 6. 8 +/- 0. 3 7. 2 +/- 0. 5 6.6 +/- 1. 7 34 6. l +/- 0.8 7. l +/- 0.3 6.4 +/- 0.5 7.8 +/- 0. 3 6.9 +/- 1; 5 35 8. 6 +/- 0. 7 (a) 7.5 +/- 0. 2 7. ':J +/- 0. 5 8. 2 +/- 1. 3 8.0 +/- 1. l 36 7. 5 +/- 1. 5 7. 5 +/- 0. 3 6.9 +/- 0. 5 8. 7 +/- 1. 2 7. 7 +/- 1. 5 37 6. 6 +/- 1. 2 6. 5 +/- 0.6 6. 7 +/- 0.8 7.2 +/- 0.4 6.8 +/- 0.6 38 8.7 +/- 1. 8 8. 7 +/- 0. 5 8.4 +/- 1. 4 9. l +/- 0.6 8. 7 +/- 0.6 39 5. 5 +/- 1. 8 6. 4 +/- 0.4 6.5 +/- 0.8 7. 0 +/- 0.2 6.4 +/- 1. 2 40 5.5 +/- 1. 9 5. 9 +/- 0. 3 5.4 +/- 0.3 5.9 +/- 0. 2

5. 7 +/- 0.5 41 6. 5 +/- 0.8 6. 9 +/- 0.8 7.2 +/- 0. 5 7.6 +/- 0.2 7. l +/- 0.9 42 6. 6 +/- 1. 3 6.8 +/- 0.4 6.7 +/- 0.4 7.0 +/- 0.2 6.8 +/- 0.3 43 6. 5 +/- 1. 2 6. 7 +/- 0.4 5.9 +/- 0.6 7.0 +/- 1. 4 6.5 +/- 0. 9 Average 6.0 +/- 2.0 6.6 +/- 1. 5 6. 7 +/- 1. 6 7.2 +/- 1. 6 6-6 +/- 1. ()

+/-? s.d.

I ' \ TI n *. -. .... ,.1., 11 7,-,,l. rnllnrtinn n,) rind !l;'/l?/f1F,-fl~/!ll/HG.

V. CONCLUSIONS

91

V. CONCLUSIONS The results of the 1986 Radiological Environmental Monitoring Program for Surry Nuclear Power Station have been presented. The Chernobyl nuclear accident on April 25, 1986 produced fission-related isotopes which were detected in the vicinity of the Surry Nuclear Power Station from May 5 through June 30. During the remainder of the year the results were as expected for normal environmental samples. Naturally occurring activity was observed in sample media in the expected activity ranges.

Occasional samples of nearly all media showed the presence of man-made isotopes. These have been discussed individually in the text. Observed activities were at very low concentrations and had no significant dose consequence.

As a method of referencing the measured radionuclide concentrations in sample media to the dose consequence, the data may be compared to the Reporting Level Concentrations listed in the NRC Regulatory Guide 4.8.

These concentrations are based upon 25% of the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion 11 As Low as is Reasonably Achievable. 11 Specific examples of sample media with positive analysis results are discussed below.

Air particulate gross beta concentrations of all the indicator locations for 1986 appear to follow the gross beta concentrations at the control location. Elevated gross beta concentrations, attributed to Chernobyl, were measured at all locations during the five week period beginning May 6. Gamma isotopic analysis of the particulate samples identified the majority of the gamma emitting isotopes as natural products 92

(beryllium-? and potassium-40). The second quarter composites also had measureable concentrations of three fission isotopes (attributed to Chernobyl):* ruthenium-103, cesium-134, and cesium-137. These w~re detected at all locations. No man-made activity was found in the particulate media during the other three quarters.

Iodine-131, attributed to the Chernobyl accident was measured in five milk samples using the radiochemical separation method and in two milk samples analyzed by gamma ray spectroscopy during May and June. Cesium-137 was detected in five milk samples and the most probable source was the Chernobyl accident. Cesium-137 has been detected occasionally in previous years, once in 1985, and then was attributed to past atmospheric nuclear weapons testing. Strontium-90 was measured in all but one of the milk samples. The values were comparable to the levels in 1985 and preopera-tional years. Strontium-90 from those years is attributed to past atmos-pheric nuclear weapons testing. The Chernobyl accident does not appear to have aff~cted strontium-90 levels in the environment. No strontium-89 was detected in any of the milk samples. Naturally occurring potassium-40 was measured in all the milk samples at normal environmental levels.

The four well water sample stations for 1986 have environmental concen-trations of tritium. The sensitivity of the tritium analysis of we11*water

(<130 pCi/£) is substantially better than the analysis from years prior to 1985 (<330 pCi/£). This makes it difficult to compare and trend the low level results found in 1986 to previous data. Also, there is no preopera-tional data to compare with for well water tritium. The tritium concentra-tions in well water are comparable to concentrations found in surface water samples (230 pCi/£ vs 220 pCi/£). These concentrations are 1.15% of the reporting level concentrations for drinking water samples.

93

The river water tritium of the Surry Discharge Canal samples were similar to the measured activity of the Surry effluent samples taken prior to discharge. The average tritium concentration of the environmental discharge sample was 578 pCi/£. The average concentration of Surry discharges, as reported in the 1986 semi-annual reports was 400 pCi/£.

The concentration of tritium in the river water was 2% of the reporting level concentration for non-drinking water. The discharge water is further diluted when mixed with the river water.

Silt is a sensitive indicator of discharges from nuclear power stations.

The silt from Surry environmental samples indicates a number of man-made isotopes present as a result of the operation of the power station. The trend graphs indicate the extent and magnitude of the contamination .

Cobalt-60 and cesium-137 were detected in the samples from a 11 locations.

Cobalt-58 and ces i um-134 were detected at several locations. In addition to these isotopes, manganese-54 and chromium-51 were detected in the samples collected at the Surry Discharge.

The preoperational program analyzed silt samples but found no gamma emitting activity above the sensitivity of the analysis (<5000 pCi/kg). The low sensitivity of the preoperational data eliminates the ability to make comparisons to operational data. No reporting level concentrations have been assigned to this media because silt contamination does not provide a direct dose pathway to man.

Activity in clam and fish samples does present a direct dose pathway to man. Clam samples from 1986 indicates the presence of low level man-made activity. This activity was determined at levels well below the required

sensitivity. Comparison of the 1986 data to 1983-1985 data and to data prior to 1978, does not indicate increasing trends. Samples taken during 94

1978-1982 were not analyzed below the required sensitivity level (<130 pCi/kg) and therefore cannot be compared to the low level activity found in the 1983-1986 samples. Preoperational clam samples were analyzed for gross beta and potassium-40 and are not directly comparable to operational data.

The average concentration of positive results from 1986 Surry Discharge clam samples were 2.2% of the reporting level concentrations.

A low level cesium-137 measurement was founti in one of the five fish samples. Trends of activity in fish is difficult to establish because previous samples were analyzed only to the required sensitivity (<130 pCi/kg). Preoperational samples were analyzed for gross beta.

The one positive result from 1986 Surry Discharge fish samples was 2.3% of the reporting level concentrations.

Based upon the evidence of the environmental monitoring program the station appears to be operating within regulatory limits. Thus, no unusual radiological characteristics were observed in the environs of the Surry Nuclear Power Station in 1986 .

95

VI. 1986 LAND USE CENSUS RESULTS FOR SURRY POWER STATION 96

VI. LAND USE CENSUS Surry Technical Specifications require that a Land Use Census be conducted within a distance of 8 Km (5 miles) from Surry Power Station on an annual basis. This census indentifies, in each of 16 meteorological sectors, the location of the nearest milk cow, the nearest resident and the nearest garden of greater than 50 m2 (500 ft2) producing broad leaf vegetation.

The census also identifies the nearest milk goat within a distance of 9.7 Km (6 miles) from the station.

The results of the Land Use Census are used to calculate the principal exposure pathway from gaseous effluents. This pathway analysis is compared to previous analysis to determine the requirements for modification of the Radiological Environmental Monitoring Program and/or the calculational model used for determining dose contributions to the unrestricted area.

Based on the results of the 1986 Land Use Census, no change to the Monitoring Program nor calculational model is required.

The results of the Land Use Census are presented in tabular form in Table 28. A map indicating the locations of the nearest resident, nearest milk animal, and the nearest garden greater than 50 m2 producing broad leaf vegetation is presented on Figure 4.

97

TABLE 28 CENSUS FOR SURRY POWER STATION - 1986 NEAREST NEAREST NEAREST NEAREST SECTOR RESIDENCE GARDEN cow GOAT A-(N) 4.75 @ 358° 4.95 @ 356° *

B-(NNE) l. 95 @ 34° * *

C-(NE)

4.90 @ 56° *

D-(ENE) 4. 90 @ 63° * *

E-(E) * * *

F-(ESE) * * *

G-(SE) * * *

H-(SSE) 4.70 @ 152° * *

J-(S) l. 60 @ 182° l. 86 @ 182° *

K-(SSW) l. 90 @ 193° l. 90 @ 193° 4.75 @ 201°

L-(SW) 2.25 @ 220° 2.25 @ 220° *

M-(WSW) 2.80 @ 243° 3.42 @ 258° *

N-(W) 3.20 @ 261° 4.33 @ 262° *

P-(WNW) 4. 9 0 @ 282° 4.90 @ 282° *

Q-(NW) * * *

R-(NNW) 3.75 @ 339° 4.90 @ 341° 3.65 @ 337° *

None 98

LUfD USE CENSUS LOCATION MAP, YE!R i986

l

HEJ.REST RESIDENT 2* NEAREST GARDEN 3* NEAREST ccw u* ~sr GOAT 99

VII. SYNOPSIS OF ANALYTICAL PROCEDURES 100

VII. ANALYTICAL PROCEDURES SYNOPSIS Appendix B is a synopsis of the analytical procedures performe.d on-samples collected for the Surry Power Station Radiological Environmental Monitoring Program. All analyses have been mutually agreed upon by VEPCO and Teledyne Isotopes and include those requested by the USNRC Regulatory Guide 4.8,BTP, Rev. l, November 1979.

ANALYSIS TITLE PAGE Gross Beta and Gross Alpha of Air Particulate Samples *...............*** 102 Gross Beta Analysis of Water Samples ..............................**.*.. 102 Analysis of Samples for Tritium ...................................*....* 104 Wat er ..........................................*.............*..... 104 Analysis of Samples for Iodine-131 ..........*.....*....*..............*. 105 Milk or Water ................................................*....* 105 Gamma Spectrometry of Samples ........................................... 106 Milk and Water ...........................................*.......... 106 Dried Solids other than Soils and Sediment ......................... 106 Fish ............................................................... 106 Soils and Sediments ................................................ 106 Charcoal Cartridges (Air Iodine) ..................................* 106 Ai r Part i cu 1ates ............................*..*...............*..* 106 Environmental Dosimetry ..............*.............**.*...*..*.*.*****.* 108 Analysis of Samples for Strontium-89 and -90 ...**...*.**..**..*..**...** 109 Tat al Water ................... *........................... D ********

109 Mi l k ............................................................. .109 o

Soil and Sediment ...............................................*.. 109 Organic Solids ................................................*.... 111 Air Particulates ...........................................*..*.... 111 101

GROSS BETA AND GROSS ALPHA ANALYSIS OF AIR PARTICULATE SAMPLES After a delay of five or more days, allowing for the radon-222 and radon-220 (thoron) daughter products to decay, the filters are counted in a gas-flow proportional counter. The sample is counted at one operating voltage for gross beta and then changed to a second operating voltage for gross alpha.

Calculation of the results, the two sigma error and the lower limit of detection (LLD).

RESULT (pCi/m3) =((S/T) - (B/t))/(2.22 VE)

TWO SIGMA ERROR (pCi/m3) =((S/T2) + (B/t2))1/2/(2.22 VE)

LLD (pCi/m3) =4.66 (Bl/2)/(2.22 VE t) where:

S = Gross counts of sample B = Counts of background (different for alpha and beta)

E = Counting efficiency (different for alpha and beta)

T = Number of minutes sample was counted t = Number of minutes background was .counted V = Sample aliquot size (cubic meters)

102

GROSS BETA ANALYSIS OF WATER SAMPLES One liter of sample is evaporated to near dryness and the residue is trans-ferred to a tared, 211 diameter planchet and final evaporation to dryness takes place under heat lamps. The planchet is weighed and then counted in a gas-flow proportional counter.

Calculation of the results, the two sigma error and the lower limit of detection (LLD) .

RESULT (pCi/£)

TWO SIGMA ERROR (pCi/£)

LLD (pCi/£)

=((S/T) - (B/t))/(2.22 VE)

=((S/T2) + (B/t2))1/2/(2.22 VE)

=4.66 (Bl/2)/(2.22 VE t) where:

S = Gross counts of sample B = Counts of background E = Counting efficiency T = Number of minutes sample was counted t = Number of minutes background was counted V = Sample aliquot size (liter) 103

ANALYSIS OF SAMPLES FOR TRITIUM Water Approximately 2 ml of water are converted to hydrogen by passing the water; heated to its vapor state, over a granular zinc conversion column heated to 400* C. The hydrogen is loaded into a one liter proportional detector and the volume is determined by recording the pressure.

The proportional detector is passively shielded by lead and steel and. an electronic, anticoincidence system provides additional shielding from cosmic rays.

Calculation of the results, the two sigma error and the lower limit detec-.

tion (LLD) in pCi/£:

RESULT = 3.234 TN VN(CG - B)/(CN VS)

TWO SIGMA ERROR 12

= 2((CG + B)6t) 1 3.234 TN VN/((CN Vs)(CG-B))

LLD = 4.66 (3.234)TN VN(CG)l/ 2/(6t CN VS) where: . TN = tritium units of the standard 3.234 = conversion factor changing tritium units to pCi/£

= volume of the standard used to calibrate the efficiency of the detector in psia

= volume of the sample loaded into the detector in psia

= the cpm activity of the standard of volume VN

= the gross activity in cpm of the sample of volume Vs and the detector volume B = the background of the detector in cpm 6t = counting time for the sample 104

f*

ANALYSIS OF SAMPLES FOR IODINE-131

Milk or Water Two liters of sample are first equilibrated with stable iodide carrier.

A batch treatment with anion exchange resin is used to remove iodine from the sample. The iodine is then stripped from the resin with sodium hypochlorite solution, is reduced with hydroxylamine hydrochloride and is extracted into carbon tetrachloride as free iodine. It is then back-extracted as iodide into sodium bisulfite solution and is precipitated as palladium iodide. The.

precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting. The chemical yield is corrected by measuring the stable iodide content of the milk or the water with a specific ion electrode.

Calculations of results, two sigma error and the lower limit of detection-(LLD) in pCi/£:

RESULT = (N/~t-B)/(2.22 EVY OF)

TWO SIGMA ERROR = 2((N/~t+B)/~t) 112(2.22 EVY OF)

LLD = 4.66(B/~t) 112;(2.22 EVY OF) where: N = total counts from sample (counts) tit = counting time for sample (min)

B = background rate of counter (cpm) 2.22 = dpm/pCi V. = volume or weight of sample analyzed y = chemical yield of the mount or sample counted OF = decay factor from the mid-collection date to the counting*date E -- efficiency of the counter for 1-131, corrected for self absorption effects by the formula E = Es(exp-0.0061M)/(exp-0.0061Ms)

= efficie~cy of the counter determined from an 1-131 standard mount

= mass of PdI 2 on the standard ~ount, mg

= mass of PdI 2 on the sample mount, mg 105

Milk and Water GAMMA SPECTROMETRY OF SAMPLES A 1.0 liter Marinelli beaker is filled with a representative aliquot of the' sample. The sample is then counted for at least 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.

Dried Solids Other Than Soils and Sediments A large quantity of the sample is dried at a low temperature, less than l00°C.

As much as possible (up to the total sample) is loaded into a tared 1-liter Marinelli and weighed. The sample is then counted for at least 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisi-tion system which performs pulse height analysis.

Fish As much as possible (up to the total sample) of the edible portion of the sample is loaded into a tared Marinelli and weighed. The sample is then counted for at least 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based ~ata acquisition system which performs pulse height analysis.

Soils and Sediments Soils and sediments are dried to a low temperature, less than l00°C. The soil or sediment is loaded fully into a tared, standard 300 cc container and weighed. The sample is then counted for at least six hours with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.

Charcoal Cartridges (Air Iodine)

Charcoal cartridges are counted up to five at a time, with one positioned on the face of a Ge(Li) detector and up to four on the side of the Ge(Li) detector. Each Ge(Li) detector is calibrated for both positions. The detection limit for I-131 of each charcoal cartridge can be determined (assum-ing no positive I-131) uniquely from the volume of air which passed through it. In the event I-131 is observed in the initial counting of a set, each charcoal cartridge is then counted separately, positioned on the face of the detector.

Air Particulate The four or five (depending on the calendar month) air particulate filters for a monthly composite for each field station are aligned one in front of another and then counted for at least six hours with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.

106

A mini-computer software program defines peaks by certain changes in the slope of the spectrum. The program also compares the energy of each peak with a library of peaks for isotope identification and then performs the radio-activity calculation using the appropriate fractional gamma ray abundance, half life, detector efficiency, and net counts in the peak region. The _

calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/volume or pCi/mass:

RESULT = (S-B)/(2.22 t EV F OF)

TWO SIGMA ERROR = 2(S+B) 112/(2.22 t EV F OF)

LLD = 4.66(B) 112/(2.22 t EV F OF) where: s = Area, in counts, of sample peak and background (region of spectrum of interest)

B = Background area, in counts, under sample peak, deter-mined by a linear interpolation of the representative backgrounds on either side of the peak t = length of time in minutes the sample was counted 2.22 = dpm/pCi E = detector efficiency for energy of interest and geometry of sample V = sample aliquot size (liters, cubic meters, kilograms, or grams)

F = fractional gamma abundance (specific for each emitted gamma)

OF = decay factor from the mid-collection date to the counting date

107

ENVIRONMENTAL DOSIMETRY Teledyne Isotopes uses a CaS04:Dy thermoluminescent dosimeter (TLD) which the company manufactures. This material has a high light output, negligible thermally induced signal loss (fading), and negligible self dosing. The energy response curve (as well as all other features) satisfies NRC Reg. Guide 4.13. Transit doses are accounted for by use of separate TLDs.

Following the field exposure period the TLDs are placed in a Teledyne Isotopes Model 8300. One fourth of the rectangular TLD is heated at a time and the measured light emission (luminescence) is recorded. The TLD is then annealed and exposed to a known Cs-137 dose; each area is then read again. This provides a calibration of each area of each TLD after every field use. The transit controls are read in the same manner.

Calculations of results and the two sigma error in net milliRoetgen (mR):

RESULT = D = (D 1+D 2+D 3+D 4 )/4

TWO SIGMA ERROR= 2((D 1-D) 2+(D 2-D) 2+(D 3-D) 2+(D 4-D) 2)/3)l/Z where Dl = the net mR of area 1 of the TLD, and similarly for D2 , D3, and o4 Dl = 1 K/Rl - A 1

11 = the instrument reading of the field dose in area 1 K = the known exposure by the Cs-137 source Rl = the instrument reading due to the Cs-137 dose on area 1 A = average dose in mR, calculated in similar manner as above, of the transit control TLDs 108

ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 WATER Stable strontium carrier is added to 1 liter of sample and the volume is reduced by evaporation. Strontium is precipitated as Sr(N03)2 using nitric acid. A barium scavenge and an iron (ferric hydroxide) scavenge are performed followed by addition of stable yttrium carrier and a 5 to 7 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting.

MILK Stable strontium carrier is added to 1 liter of sample and trichloracetic acid (TCA) is added to produce a curd. The curd is separated by filtration and is discarded. An oxalate precipitation is performed on the filtrate and the precipitate is ashed in a muffle furnace. The ash is dissolved and strontium is precipitated as SrN03 using fuming (90%) nitric acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge are then performed.

Stable yttrium carrier is added and the sample is allowed to stand for 7 to 10 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 is determined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting.

SOIL AND SEDIMENT The sample is first dried under heat lamps and a 10 gram aliquot is taken.

Stable strontium carrier is added and the sample is leached in nitric acid.

The mixture is filtered and the liquid portion is reduced in volume by evapo-ration. Strontium is precipitated as Sr(N03)2 using fuming (90%) nitric acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for 7 to 10 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to

infer Sr-90 activity. Strontium-89 acti~ity is determined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting.

109

where: N = total counts from sample (counts) flt = counting time for sample (min)

BC = background rate of counter (cpm) using absorber configuration 2.22 = dpm/pCi V = volume or weight of sample analyzed BA = background addition from Sr-90 and ingrowth of Y-90 BA = 0.016 (K) + (K) EY/abs) (IGy_go)

YS = chemical yield of strontium DFSR-89 *=decay factor from the mid collection date to ttie counting date for SR-89 ESR-89 = efficiency of the counter for SR-89 with the 80 mg/cm.sq.

aluminum absorber K = (N/~t - Bc)y_gol(Ey_go IFY-90 DFy_90Y1)

DFY-90 = the decay factor for Y-90 from the "milk" time to the mid count time EY-90 = efficiency of the counter for Y-90 IFY-90 = ingrowth factor for Y-90 from scavenge time to milking t{me IGY-90 = the ingrowth factor for Y-90 into the strontium mount from the 11 milk 11 time to the mid count time.

0.016 = the efficiency of measuring SR-90 through a No. 6 absorber Ey / abs = the efficiency of counting Y-90 through a No. 6 absorber B = background rate of counter (cpm) yl = chemical yield of yttrium y2 = chemical yield of strontium OF = decay factor of yttrium from the radiochemical milking time to the mid count time E = efficiency 6f the counter for Y-90 IF = ingrowth factor for Y-90 from scavenge time to the radiochemical milking time 110

Organic Solids A 200g wet portion of the sample is dried and then ashed in a muffle furnace.

Stable strontium carrier is added and the ash is leached in nitric acid. The sample is filtered and the volume is reduced by evaporation. Strontium is precipitated as Sr(N03)2 using fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carri.er and a 7 to 10 day period for yttrium i.ngrowth. Yttrium is then precipitatd as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is deter-mined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting.

Air Particulates Stable strontium carrier is added to the sample and it is leached in nitric acid to bring deposits into solution. The mixture is then filtered and the filtrate is reduced in volume by evaporation. Strontium is precipitated as Sr(N03)2 using fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a 7 to 10 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is determined by precipi-tating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with 80 mg/cm2 aluminum absorber for level beta counting.

Calculations of the results, two sigma errors and lower limits of detection (LLD) are expressed in activity of pCi/volume or pCi/mass:

RESULT Sr-89 TWO SIGMA ERROR Sr-89 LLD Sr-89 RESULT Sr-90 = (N/6t - B)/(2.22 V Y Y OF IF E) 1 2 TWO SIGMA ERROR Sr-90 = 1 2 2((N/6t+B)/6t) / /(2.22 V Y1 v2 OF E IF))

LLD Sr-90 = 4.66(B/6t) 1/ 2/(2.22 V v v2 IF OF E) 1 111

VIII. EPA INTERLABORATORY COMPARISON PROGRAM

112

VIII. EPA INTERLABORATORY COMPARISON PROGRAM Teledyne Isotopes participates in the US EPA Interlaboratory Comparison

. Program to the fullest extent possible. That is, we participate in the program for all radioact.ive isotopes prepared and at the maximum frequency of availability. In this section trending graphs (since 1981) and the 1986 data summary tables are presented for isotopes in the various sample media applicable to the Surry Power Stations Radiological Environmental Monitoring Program. The footnotes of the table discuss investigations of problems encountered in a few cases .

113

100 US EPA Cross Check Program

AP Filters- Gross Beta 90 80

[I EPA+/- 3 sigma

Tl+/- 3 sigma 70 ua.

...... *1 I

...... 60

+:>

50 .I *I I 40 I I 30 20 10-+-~~.--~--,-~~---.-~~~~---,,--~-.-~~--.---~~r--~--,-~~-.-~~......--~--,

1981 1982 1983 1984 1985 1986 1987 Year

70 US EPA Cross Check Program AP Filters- Cs137 60 50 l:l EPA+/- 3 sigma

Tl+/- 3 sigma 40

...... 0 c..n a.

30 I I I

20 I I 10 0

i I 1981 1982 1983 1984 1985 1986 1987 Year

100 -r----------------------------------,

US EPA Cross Check Program Milk- 1131 80 1:1 EPA +/-3 sigma

Tl +/-3 sigma 60 en 0

C.

40 20

i 0 +.L.-----.-&--..........--....---....----r--"""T"""--~---.----=r---~1------.----1 1981 1982 1983 1984 1985 1986 1987 Year

100

-r------------------------------------,

US EPA Cross Check Program Milk- Cs137 80 l:J EPA +/-3 sigma 60

Tl+/- 3 sigma j

0 a.

40 20 r

0 4---------.----.-----,---.......----~--....---T----,---~--.......------1 1981 1982 1983 1984 1985 1986 1987 Vear

US EPA Cross Check Program Milk- K 2400 -

El EPA+/-3sigma 2000 -

.

Tl +/-3 sigma

~

..... C)

(X)

E

1600

I I*

I*

I*

I*

I*

f t ~ t I *

.~

1200 *

.~

800 ..J.-~~~~~~,------'~.--~.L-,,.---~--.~~~.~~--,.~~~..--.~~.--~---,~r---~--,.~~--t 1981 1 982 1983 1984 1985 1986 1987 Year

100 " " T - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

US EPA Cross Check Program Milk- Sr89 80 1:1 EPA +/-3 sigma 60

Tl +/-3 sigma I

I-' 0 I-'

\.0 a.

40 20 tl 0

1981 1982 1983 1984 1985 I 1986 1987 Year

US EPA Cross Check Program Milk- Sr90 30 a EPA +/-3 sigma

Tl +/-3 sigma N

-(-.)

C)

c. 20

10 O-'----.--------.-------......-----.....-----------...----.-----r----t 1981 1982 1983 1984 1985 1986 1987 Vear

140 US EPA Cross Check Program Water-1-131 120 100 l:J EPA +/-3 sigma

Tl+/- 3 sigma N

0 0.

80

-I I 60 I

40 20 f I .I

.t

.I 0

TI ~ .

1981 1982 1983 1984 Vear

80 US EPA Cross Check Program Water- l-131 60 e EPA +/-3 sigma

Tl+/- 3 sigma

.I N

N 0 40 a.

1. .f I

20 o-1---------r-------,,-------r--------,--.L..-.--.---------'-1 1984 1985 1986 1987 ,

Year

US EPA Cross Check Program 70 Water- Co60 60 a EPA +/-3 sigma

Tl +/-3 sigma 50 I-'

N 0 40 w a.

30 20

.I

-I 10 0 -t----e---.....----a--.....----G--....------r-----------"""'.........,

1981 1982

1983 1984 Year

100 ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - . . ; . . . . _ - - ,

US EPA Cross Check Program 90 Water- Co60 80 70 60 a EPA +/-3 sigma

Tl +/-3 sigma 50 40 30

I .f o-1--=------r-------r-------,------,---_....~~-----,

I 1984 1985 1986 1987 Year

100 - , - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ,

US EPA Cross Check Program 90 Water- Cs134 80 a EPA +/-3 sigma 70

Tl+/-3sigma 60 I

I-'

N ::::::: 50 u,

0 0..

40 30 20 10 0 -+-_ _......__ _ _, _ ; L - - - - - , - - - - ' - - - . . . - - - - - ~ - - - - ~ - _ _ . . _ _ _ . . _ - - - t 1981 1982 1983 1984 Year

100 - , - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ,

US EPA Cross Check Program 90 Water- Cs134 80 1.:1 EPA +/-3 sigma 70

Tl +/-3 sigma 60 S 50 0

Q.

40 30 20 10 O""----------'-----------,.-------.---------~

1984 1985 1986 1987 Year

US EPA Cross Check Program 70 Water- Cs137 60 1a1 EPA +/-3 sigma

Tl +/-3 sigma 50

...... s 0 . 40 N

'4 C.

30 20 10 *I 04--..L..I--L------L----,.------r-----,-------r------L--~

1981 1982 1983 1984 Year

US EPA Cross Check Program Water- Cs137 70 60 m EPA+/-3 sigma 50

Tl +/-3 sigma N

co 0 40 Q.

30 20 I .j .I 10 o+-------r------------r-----,r-------'--...----~

1984 1985 1986 1987 Year

US EPA Cross Check Program Water- H3 5000 a EPA +/-3 sigma

Tl +/-3 sigma 4000

*1 N

U) 0 C.

3000

-I I *i 2000 1000 O-+----_.;._~------r-----=-.-------r------,,-------t 1981 1982 1983 1984 Year

, I 10000 US EPA Cross Check Program Water-H3 8000 a EPA +/-3 sigma .I

Tl +/- 3 sigma I

6000

..... 0 C.

~

w C)

~ II r I 4000 2000 ij I1 1I r ~*

tI o-&------.------r-----r-----r----,-------,

1984 1985 1986 1987 Vear

..,...TELEDYNE ISOTOPES US EPA INTERLABORATORY COMPARISON PROGRAM 1986 VEPCO - SURRY EPA Date TI Mailed Date EPA EPA TI Norm Dev. ** Warning PREPARATION Results Issued Results Media Nuclide Results(a) Results(b) (Known) *** Action 01/31/86 04/03/86 04/28/86 Food Sr-89 25.00 +/- 5.00 23.66 +/- 1. 15 -0.46

( C) Sr-90 10.00 +/- 1. 50 23.66 +/- 1. 5 2 15. 78 *** ( d)

I - 131 20.00 +/- 6.00 18.00 +/- 1. 00 -0.58 Cs-137 15.00 +/- 5.00 19.00 +/- 1. 00 1.38 K 950.00 +/-143.00 959.00 +/- 62.35 0. l 0 02/07/86 03/21/86 04/21/86 Water Cr-51 38.00 +/- 5.00 L. T. 86.66 Co-60 18.00 +/- 5.00 18.66 +/- 0.58 0.23 Zn-65 40.00 +/- 5.00 46.33 +/- 5. 77 2. 19 ** ( e)

Ru-106 0.00 +/- 5.00 <40.00 Cs-134 30.00 +/- 5.00 26.00 +/- 3.60 -1. 38 Cs-137 22.00 +/- 5.00 21. 66 +/- 4.93 -0. 11 w

02/14/86 03/14/86 04/21/86 Water H-3 5227.00 +/-523.00 5266.67 +/- 57.72 0. 13 02/28/86 04/03/86 05/30/86 Milk I-131 9.00 +/- 6.00 9.00 +/- 0.00 0.00 04/04/86 04/29/86 06/08/86 Water I -131 9.00 +/- 6.00 10.00 +/- 0.00 0.29 04/25/86 05/15/86 06/09/86 Air Filter Gross Beta 47.00 +/- 5.00 44.66 +/- 3. 21 -0.81 Sr-90 18.00 +/- 1. 50 15.66 +/- 1. 15 -2.69 ** ( f)

Cs-137 10.00 +/- 5.00 10.33 +/- 0.58 0. 11 06/06/86 07/18/86 08/11/86 Water Cr-51 0.00 +/- 5.00 <92.7 Co-60 66.00 +/- 5.00 66.67 +/- 1.15 0.23 Zn-65 86.00 +/- 5.00 87.67 +/- 8.50 0.58 Ru-106 50.00 +/- 5.00 <48.00 Cs-134 49.00 +/- 5.00 47.66 +/- 0.58 -0.46 Cs-137 10.00 +/- 5.00 9.33 +/- 2.08 -0.23 06/13/86 07/09/86 07/28/86 Water H-3 3125.00 +/-360.00 3033.33 +/-152.75 -0.44 06/27/86 09/22/86 10/06/86 Milk Sr-89 0.00 +/- 5.00 <3.66 Sr-90 16.00 +/- 1. 50 15.00 +/- 0.00 -1. 15 1-131 41.00 +/- 6.00 41.00 +/- 1.00 0.00 Cs-137 31. 00 +/- 5.00 39.00 +/- 1.73 2. 77 ** (g)

K 1600.00 +/-80.00 1593.33 +/-32.14 -0. 14

US EPA INTERLABORATORY COMPARISON PROGRAM 1986 VEPCO - SURRY EPA Date TI Mailed Date EPA EPA TI Norm Dev. ** Warning PREPARATION Results Issued Results Media Nuclide Results(a) Results(b) (Known) *** Action 07/25/86 10/01/86 12/01/86 Food Sr-89 30.00 +/- 5.00 23.66 +/- 1. 15 -2. 19 *** ( h)

( C) Sr-90 19.00 +/- 1. 50 22.33 +/- 1. 52 3.85 *** ( h) 1-131 30.00 +/- 6.00 25.66 +/- 1. 15 -1.25 Cs-137 20.00 +/- 5.00 22.00 +/- 4.58 0.69 K 1150.00 +/- 58.00 1126.66 +/- 5 7. 7 4 -0.70 08/08/86 08/29/86 10/17/86 Water 1-131 45.00 +/- 6.00 27.00 +/- 1. 00 -5.20 *** ( i) 09/12/86 10/27 /86 12/12/86 Air Filter Gross Beta 66.00 +/- 5.00 64.33 +/- 0. 58 -0.58 Sr-90 22.00 +/- 1. 50 18.00 +/- 1. 00 -4.62 *** ( j)

Cs-137 22.00 +/- 5.00 23.33 +/- 2.08 0.46 10/10/86 11/17/86 12/12/86 Water Cr- 51 59.00 +/- 5.00 <113.0 Co-60 31. 00 +/- 5.00 30.33 +/- 0.58 -0.23 w

N Zn-65 85.00 +/- 5.00 84.00 +/- 5. 29 -0.34 Ru-106 74.00 +/- 5.00 <70.00 Cs-134 28.00 +/- 5.00 27.33 +/- 2. 51 -0.23 Cs-137 44.00 +/- 5.00 52.67 +/- 0.58 3.00 *** ( k) 10/17/86 11/14/86 12/12/86 Water H-3 5973.00 +/- 597.00 5900.00 +/- 99.98 -0. 21 NOTES:

(a) EPA Results-Expected laboratory prec1s1on (1 sigma). Units are pCi/£ for water, urine, and milk except K is in mg/£. Units are total pCi for air particulate filters.

(b) Teledyne Results - Average+/- one sigma. Units are pCi/£ for water, urine, and milk except K is in mg/£.

Units are total pCi for air particulate filters.

(c) Units for food analysis are pCi/kg.

(d) This sample is a synthetic food which may contain a substance which interferes with the strontium 89 and 90 analysis. Only 21 laboratories participated in the strontium analyses. Of the 21 who did participate 42.9% had results beyond the three sigma control limits.

(e) The three results reported we*re 43.0, 43.0, and 53.0. The one high result of 53.0 caused the average result to be above the 2 sigma limit. This sample was aliquoted last of the three samples and more of the spike may have settled in the bottom of the container.

(

US EPA INTERLABORATORY COMPARISON PROGRAM 1986 VEPCO - SURRY EPA Date Tl Mailed Date EPA EPA TI Norm Dev. ** Warning PREPARATION Results Issued Results Media Nuclide Results(a) Results(b) (Known) *** Action NOTES: (Cont.)

(f) These air filters are counted for gross alpha, beta and gamma before being analyzed for Sr-90. It was felt that some of the activity had been lost in handling. The air particulate filters will be handled more carefully in the future. This had not been a problem in previous analyses.

( g) The efficiency calibration for Cs-137 for the gamma spectrometer detectors was checked and no reason for the high

....w result was evident. Previous analyses did not exceed the 2 sigma limits. If this situation recurs, a new

(,)

efficieniy for Cs-137 will be determined.

(h) For Sr-90 fourteen of the seventeen laboratories participating were beyond the+/- sigma level. For Sr-89 thirteen of the fifteen laboratories had low results. It would appear that the sample is flawed in some way for this analysis.

(i) This analysis was performed by an inexperienced technician who has since received additional training and is p~rforming satisfactorily. Previous 1-131 analysis in water sample (4/29/86) indicated good agreement with EPA results.

(j) It is believed that too much NaC03 was used in the final precipitation of SrC03 resulting in a falsely high strontium-89 yield. Less NaC03 will be used in the future precipitation of SrC03.

(k) The data for the samples was examined and no obvious reason for the high result could be found. The Cs-137 calibration was checked and found to be in agreement with previous readings. Since this was not a trend in previous analyses for Cs-137 in Water (Test 418 -0.23; Test 40~ -0.11) it was decided to follow the results to see if a trend developed.

!A IX . . REFERENCES 134

- IX. REFERENCES

1. United States Nuclear Regulatory Commission, Regulatory Guide 4.8 11 Environmental Technical Specifications for Nuclear Power Plants 11 ,

December, 1975.

2. Virginia Electric and Power Company, Surry Power Station Technical Specifications, Units 1 and 2.

3. NUREG 0472, 11 Radiological Effluent Technical Specifications for PWRs 11 , Rev. 3, March 1982.

4. United States Nuclear Regulatory Commission. Regulatory Guide 1.109, Rev. 1, 11 Calculation of Annual Doses to Man from Routine

Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I", October, 1977.

5. USNRC Branch Technical Position, 11 Acceptable Radiological Environ-mental Monitoring Program 11 , Rev. 1, November 1979.

135

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