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Radiological Environ Monitoring Program for 1987.
	ML18151A536
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Site:	Surry
Issue date:	12/31/1987
From:	Benson D, Blount P; TELEDYNE ISOTOPES
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VIRGINIA POWER COMPANY SURRY POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FOR 1987 Prepared by VIRGINIA POWER COMPANY and TELEDYNE ISOTOPES

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SURRY POWER STATION JANUARY 1, 1987 to DECEMBER 31, 1987 Reviewed by:

Health Physics Reviewed by:

Reviewed by:

Approved by:

TABLE OF CONTENTS SECTION TITLE PAGE I. INTRODUCTION ................................................. 1 I I. SAMPLING AND ANALYSIS PROGRAM ................................ 4 I I I. PROGRAM EXCEPTIONS .......................................... 16 IV.

SUMMARY

AND DISCUSSION OF 1987 ANALYTICAL RESULTS ........... 19 A. AIRBORNE EXPOSURE PATHWAY ............................... 20

1. Air Iodine/Particulates ............................. 20 B. WATERBORNE EXPOSURE PATHWAY ............................. 37

1. River Water ......................................... 37

2. Well Water .......................................... 46 C. AQUATIC EXPOSURE PATHWAY ................................ 49

1. Silt ................................................ 49

2. Shoreline Sediment .................................. 58 D. INGESTION EXPOSURE PATHWAY .............................. 61

1. Milk ................................................ 61

2. Aquatic Biota ....................................... 66

3. Food Products ....................................... 77 E. DIRECT RADIATION EXPOSURE PATHWAY ....................... 80

1. TLD Dosimeters ....................................... 80 V. CONCLUSION ........................................... .- ...... 87 VI. 1987 LAND USE CENSUS ........................................ 92 VI I. SYNOPSIS OF ANALYTICAL PROCEDURES ........................... 96 VI I I. EPA INTERLABORATORY COMPARISON PROGRAM ..................... 108 IX. REFERENCES ................................................. 130

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 ......................................... 95 ii

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 Power Company Docket Nos. 50-280 and 50-281 .

iii

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I. INTRODUCTION The operational radiological environmental monitoring program conducted for the year 1987 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, 1987 through December 31, 1987 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 Conmission (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 l)recaution 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 samples.

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 corrmitment recommended by 10CFR50,

Appendix I, to meet the criterion of "As Low As Is Reasonably Achievable".

2

E. This report documents the results of the Radiological Environmental Monitoring Program for 1987 and satisfies the following objectives of the program:

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 i~ 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 1987. The S)fTlbols 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 Corrmon-wealth of Virginia direct radiation recording devices.

These are indicated as "co-location" samples.

3. In addition to the Radiological Environmental Monitoring Program required by Surry Technical Specifications, Virginia Electric and Power Company splits samples with the Corrmon-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 except those labeled "control".

4

B. Analysis Program

1. Table 2 summarizes the analysis program conducted by Teledyne Isotopes for Surry Power Station during 1987 .

5

TABLE 1 VIRGINIA POWER - SURRY - 1987 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 SAMPLE DISTANCE COLLECTION MEDIA LOCATION STATION MILES DIRECTION DEGREES FREQUENCY REMARKS Environmental (TLD's)

Centro l West Nort.h West Surry Station Discharge rngi (03) 0.17 0.6 WNW NW 292" 309" Quarterly Quarterly Quarterly Onsite*

Site Boundary Site Boundary North North West ~04) 0.4 NNW 330" Quarterly Site Boundary North 05) 0.33 N 357* Quarterly Site Boundray North North East (06) 0.28 NNE 22* Quarterly Site Boundary North East 0.31 NE 4 5" Quarterly Site Boundary East North East East (Exclusion) rn~J (09) 0.43 0.31 ENE E

68° 90° Quarterly Quarterly Site Boundary On site w 270" Quarterly Site Boundary West West South West South West H~l

( 12) 0.40 0.45 0.30 WSW SW 250" 225" Quarterly Quarterly Site Boundary Site Boundary South South West 0.43 SSW 203" Quarterly Site Boundary South South South East HiJ (15) 0.48

0. 74 s

SSE 180" 157" Quarterly Quarterly Site Boundary Site Boundary South East (16) 1. 00 SE 135" Quarterly Site Boundary East (17) 0.57 E 90" Quarterly Site Boundary Station Intake (18) 1. 23 ESE 113" Quarterly Site Boundary Hog Island Reserve (19) 1. 94 NNE 26" Quarterly Near Resident, co-location Bacons Castle (20) 4.45 SSW 202* Quarterly Apx. 5 mi le TLD, co-location Route 633 ( 21) 3.5 SW 224" Quarterly Apx. 5mileTLU Alliance (22) 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 (24) 4.0 w 270" Quarterly Apx. 5 mi le TLD Scot land Wharf (25) 5.0 WNW 285" Quarterly Apx. 5 mi le TLD, co-location Jamestown ( 2 6) 6.3 NW 310" Quarterly Apx. 5 mi le TLU, co-location Colonial Parkway (2 7) 3. 7 NNW 330" Quarterly Apx. 5 mile TLD Route 617 and 618 5.2 NNW 340" Quarterly Apx. 5 mile TLD Kingsmill Williamsburg rn:J (30) 4.8

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Quarterly Quarterly Apx. 5 mile TLD Population Center, co-location Kingsmill North Budweiser BB 5.6

5. 7 NNE NNE 14" 2 7*

Quarterly Quarterly Apx. 5 mile TLD Population Center

TLD stored in a lead shield in environmental building.

TABLE l (Cont.)

VIRGINIA POWER - SURRY - 1987 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 SAMPLE DISTANCE COLLECT ION MEDIA LOCATION STATION MILES DIRECTION DEGREES FREQUENCY REMARKS Environmental Water Plant 4.8 NE 41" Quarterly Apx.5mileTLD TL D's (Cont. ) Dow 5. 1 ENE 70* Quarterly APX. 5 mi le TLD Lee Hall 7 .1 ENE 73* Quarterly Population Center. co-location Goose Island 5.0 E 88° Quarterly Apx. 5 mile TLD Fort Eustis 4.8 ESE 107" Quarterly Apx. 5 mile. TLD co-location Newport News 16.5 ESE 102* Quarterly Population Center James River Bridge 14.8 SSE 147" Quarterly Control Location Benn's Church 14.5 s 175" Quarterly Control Location Smithfield 11. 5 s 176" Quarterly Population Center Rushmere 5.2 SSE 156" Quarterly Apx. 5 mile TLD .

Rt. 628 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 Island Reserve (HIR) 2.0 NNE 26" Weekly Co-location Bacons Castle - (BC) 4.5 SSW 202* Weekly Alliance (ALL) 5. 1 WSW 248" Weekly Co-location Collonial Parkway (CP) 3.7 NNW 330" Weekly Dow Chemical (DOW) 5. 1 ENE 70" Weekly Fort Eustis (FE) 4.8 ESE 101* 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 1. 9 ESE 77* Bi-monthly Hog Island Point 2.4 NE 52" Bi-monthly Newport News 12.0 SE 140" 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

TABLE 1 (Cont.)

VIRGINIA POWER - SURRY - 1987 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 SAMPLE DISTANCE COLLECT ION MEDIA LOCATION MILES* DIRECTION DEGREES FREQUENCY REMARKS Well Water Surry Statton Quarterly On site*

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 co Sediment Burwell's Bay 7.76 SSE 167" Semi-Annually Silt Chickahominy River 11. 2 WNW 300" Semi-Annually Control Location Surry Station Intake 1. 9 ESE 77* Semi-Annually Hog ls land Point 2.4 NE 52" Semi-Annually Point of Shoals 6.4 SSE 157" Semi-Annually Newport News 12.0 SE 140" Semi-Annually Surry Station Discharge 0.5 NNW 341" Semi-Annually Mi 1k Lee Hall 7. 1 ENE 64" Monthly St ate Sp 1 it Epps 4.8 SSW 201* Monthly State Split Colonial Parkway 3.7 NNW 337* Monthly Judkins 6.2 SSW 211

Monthly Wi 11 iams 22.5 s 182" Monthly Control Location Oysters Deep Water Shoals 3.9 ESE 105" Bi-Monthly Point of Shoals 6.4 SSE 157" Bi-Monthly Newport News 12.0 SE 140" Bi-Monthly State Split Clams Chickahominy River 11. 2 WNW 300" Bi-Monthly 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.

TABLE 1 (Cont.)

VIRGINIA POWER - SURRY - 1987 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 SAMPLE DISTANCE COLLECT ION MEDIA LOCATION MILES DIRECTION DEGREES FREQUENCY REMARKS Crabs Surry Station Discharge 0.6 NW 312* July/August September Fish Surry Station Discharge 0.6 NW 312* Semi-Annually Crops Brock's Farm 3.8 s 188° Annually State Split (Corn,Peanuts, Slade's Farm 2.4 s 177* Annually St ate Split Soybeans)

(Cabbage,Kale) Pool's Garden 2.3 s 102* Annually State Split Carter's Grove Garden 4.8 NE 56° Annually St ate Split Ryan's Garden Annually St ate Split/Control Location (Chester, Va.)

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

Air Iodine Weekly I-131 0.07 pCi/m3 Air Particulate Weekly 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 pCi/£ composite of monthly sample Monthly and Gamma Isotopic pCi/£ 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 La-140 15 (1) Quarterly composites of each locations's weekly air particulate samp 1es wi 11 be analysed for Gamma Emitters.

13

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 Silt Semi-Annual Gamma Isotopic pCi/kg-dry Cs-134 150 Cs-137 180 Milk Monthly I-131 1 pCi/£ Gamma Isotopic pCi/£ Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Oyster 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 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 Gamma Isotopic pCi/kg-wet Months Mn-54 130 Fe-59 260 Co-58, 60 130 Zn-65 260 Cs-134 130 Cs-137 150 14

TABLE 2 (Cont.)

SURRY POWER STATION I

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 Cs-137 80 Note: 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 environmental 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.

15

III. PROGRAM EXCEPTIONS 16

I I I. PROGRAM EXCEPTIONS

During this environmental reporting period, several samples were not available or the analysis of the samples did not meet the required sensitivity (LLD). The following is a discussion of the exceptions and actions taken to limit reoccurrence.

Two TLD sampling stations were lost during 1987. Compared to the large number of TLD stations placed in the field the vandalism rate is relatively low. Station procedures require that all TLD locations be visually checked once per month to eliminate loss of data. When TLDs are found missing, *they are replaced with new TLDs and the data is averaged over the period of exposure.

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 of these samples for barium/lanthanium-140 and iodine-131 failed to meet the required Lower Limit of Detection (LLD) in many of these samples because of delay in receipt of the samples from the State of Virginia. The state has been contacted and informed of our require-ments for the timely analysis of the samples.

River water samples taken by VEPCO at Surry Discharge and Scotland Wharf were not collected during the month of August as required by Technical Specification Table 4.9-3. State split samples taken at the same locations were misidentified as the VEPCO river water samples. The environmental sampling schedule is routinely reviewed by personnel prior to sampling.

This one missed surveillance compared to the amount of sampling done in 1987

does not indicate a weakness in the sampling program. The river water sampling requirements were reviewed with the environmental sampling personnel and a reoccurrence is not anticipated.

17

REMP EXCEPTIONS FOR SCHEDULED

Location SAMPLING AND ANALYSIS DURING 1987 Description Date of Sampling Reason(s) for Loss/

Exception 23 Direct Radiation Second Quarter TLD Vandalized

{Sets 1/2)

SD/SW River Water 08/15/87 Sample not collected due to oversight.

SD, SW River Water LLD's not met due to (State Split) I-131 01/15/8 7 late receipt from Ba/La-140 Ol/15/87-07/15/87 State of Virginia.

09/15/87-11/15/87 18

VI.

SUMMARY

AND DISCUSSION OF 1987 ANALYTICAL RESULTS 19

IV.

SUMMARY

AND DISCUSSION OF 1987 ANALYTICAL RESULTS Data from the radiological analyses of environmental media collected during the report period are provided in this section. 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 are 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 Progr~. Participation in this program ensures that independent v

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 SlJllmary of the results of the environmental measurements taken during the reporting period.

A. Airborne Exposure Pathway

1. Air Iodine/Air Particulates Results of gross beta activities are presented in Table 5. The average concentration for the control station (Newport News) is 0.017 pCi/m3 with a range of 0.007 to 0.029 pCi/m3. The average measurement for the indicator 20

locations is 0.017 pCi/m3 with a range of 0.006 to 0.031 pCi/m3. The monthly averages of the gross beta concentrations for the seven indicator and one control location are plotted for 1969 through 1987. The gross beta activities observed are comparable to the levels detected in the 1982-1986

~eriod. However, prior to that period the gross beta activities were higher due to atmospheric weapons testing by other countries.

The results of airborne iodine-131 analyses of charcoal cartridges are presented in Table 4. All results were below the lower limit of detection.

Air particulate filters were composited by locations on a quarterly basis and were analyzed by gamma ray spectroscopy. The results are listed in Table 6. Cosmogenically produced beryllium-? was measured in all 32 composite samples with an average activity of 0.088 pCi/m3 and a range between 0.049 to 0.163 pCi/m3. Naturally occurring potassium-40 was detected in seven samples with an average activity of 0.008 pCi/m3 and a range of 0.002 to 0.022 pCi/m3. Also naturally occurring thorium-228 was observed in one second quarter sample with an activity of 0.0005 pCi/m3.

All other gamma emitters were below the lower limit of detection.

21

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SURRY NUCLEAR POWER STATION TABLE 3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1987 ANALYSIS AND LOWER LIMIT NUMBER OF 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) (l) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Air logine 1-131 416 0.07 -(0/364) N/A N/A -(0/52) 0 (pCi/m )

Airborne Gross Beta 416 10 17.1(364/364) ALL 17 .9(52/52) 16.8(52/52) 0 Particulates (5.7-31) (8.1-31) (7.3-29)

(lE-03 pCi/m3)

N O'I Gan111a Spec 32 Quarterly Be-7 32 86.5(28/28) BC 97 .0(4/4) 95.9(4/4) 0 (49.1-148) (62.7-143) (53.2-163)

K-40 32 7.5(7/28) ALL 22.3(1/4) -(0/4) 0 (2.34-22.3)

Th-228 32 0.51(1/28) ALL 0.51(1/4) -(0/4) 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 4 (Page 1 of 4)

VIRGINIA POWER - SURRY - 1987 CONCENTRATIONS OF IODINE-131 IN FIL TE RED AIR pCi/m3 +/- 2 Sigma STATIONS ss HIR BC ALL CP DOW FE NN COLLECT ION DATE JANUARY 12/30/86-01/06/87 <.02 <. 02 <. 02 <. 02 <. 02 <.02 <.02 <. 02 Ol/06/87-01/13/87 <.02 <. 02 <. 02 (a) <.02 <.01 <. 02 <. 02 <. 02 Ol/13/87-01/20/87 <.03 <.03 <.03 ( b) <.03 <.03 <.03 <.03 <.03 Ol/20/87-01/28/87 <.03 <.03 <.03 <.03 <. 02 <. 02 <. 02 <. 02 Ol/28/87-02/03/87 <.03 <.04 <.03 <.04 <.02 <.02 <. 02 < :02 N

....... FEBRUARY 02/03/87-02/10/87 <.04 <.04 <.04 <.04 <.02 <.02 <.02 <. 02 02/10/87-02/19/87 <. 02 <. 02 <.02 <. 02 <.02 <. 02 <. 02 <. 02 02/19/87-02/24/87 <. 02 <. 02 <.02 <. 02 <.03 <.03 <.03 <.03 02/24/87-03/03/87 <. 02 <. 02 <. 02 <. 02 <.01 <.02 <.02 <. 02 MARCH 03/03/87-03/11/87 <.01 <.01 <.01 <.01 <.01 <.01 <.01 <.02 03/11/87-03/17/87 <.03 <.03 <.03 <.03 <. 02 <.02 <. 02 <.02 03/17/87-03/24/87 <. 02 <. 02 <. 02 <. 02 <.01 <. 02 <.02 <.01 03/24/87-03/31/87 <. 02 <. 02 <. 02 <. 02 <.01 <.01 <.01 <. 01 (a) Collection dates Ol/06/87-01/12/87.

(b) Collection dates Ol/12/87-01/20/87.

TABLE 4 (Page 2 of 4)

VIRGINIA POWER - SURRY - 1987 CONCENTRATIONS OF IODINE-131 IN FILTERED AIR pCi/m3 +/- 2 Sigma STATIONS ss HIR BC ALL CP DOW FE NN COLLECTION DATE APRIL 03/31/87-04/07/87 <.01 <.01 <.01 <. 01 <. 02 <. 02 <.01 <. 02 04/07/87-04/14/87 < .. 03 <.03 <.03 <.03 <. 02 <. 02 <.02 <.02 04/14/87-04/21/87 <.02 <. 02 <.02 <.02 <. 02 <.02 <. 02 < ..02 04/21/87-04/28/87 <.02 <. 02 <.02 _<.02 <. 02 <. 02 * <.02 <. 02 MAY N

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04/28/87-05/05/87 <.02 <. 02 <. 02' <. 02 <.02 <. 02 <.02 <. 02 05/05/87-05/12/87 <.01 <;01 <.01 <.01 <. 02 <. 02 <.01 <. 02 05/12/87-05/19/87 <.02 <. 02 <.02 <. 02 <.02 <. 02 <. 02 <. 02 05/19/87-05/26/87 <.02 <.02 <.02 <. 02 <.02 <.02 <.02 <. 02 05/26/87-06/02/87 <.01 <. 02 <.01 <. 01 <. 02 <. 02 <.02 <.02 JUNE 06/02/87-06/09/87 <.02 <. 02 <.02 <. 02 <. 01 < .0.1 <.01 <.01 06/09/87-06/16/87 <.03 <.03 <.03 <.03 <.03 <.03 <.03 <.03 06/16/87-06/23/87 <.01 <.01 <.01 <.01 <.02 <.02 <.01 <.02 06/23/87-07/01/87 <.02 <. 02 <.02 <. 02 <. 02 <. 02 <. 02 <.02

TABLE 4 (Page 3 of 4)

VIRGINIA POWER - SURRY - 1987 CONCENTRATIONS OF IODINE-131 IN FILTERED AIR pCi/m3 +/- 2 Sigma STATIONS ss HIR BC ALL CP DOW FE NN COLLECTION DATE JULY 07/0l/87-07/07/87 <. 02 <. 02 <. 02 <. 02 <.02 <. 02 <. 02 <.03 07/07/87-07/14/87 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 07/14/87-07/21/87 <.04 <. 02 CO2 <. 02 <. 02 <. 02 <.02 <. 02 07/21/87-07/28/87 <.02 <. 02 <. 02 <. 02 <. 02 <. 02 <.02 <. 02 07/28/87-08/04/87 <. 02 <. 02 <. 02 <. 02 <.02 <. 02 <. 02 <. 02 N

<.O AUGUST 08/04/87-08/11/87 <.02 <. 02 <.02 <. 02 <.02 <. 02 <. 02 <.02 08/11/87-08/18/87 <. 02 <. 02 <.02 <. 02 <. 02 <. 02 <. 02 <.02 08/18/87-08/25/87 <. 02 <. 02 <. 02 <. 02 <.03 <. 02 <. 02 <.01 08/25/87-08/31/87 <. 02 <. 02 <. 02 <. 02 <.02 <.02 <.02 <. 01 SEPTEMBER 08/31/87-09/08/87 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 09/08/87-09/15/87 <. 02 <. 02 <.05 <. 02 <.02 <. 02 <.02 <.02 09/15/87-09/22/87 <. 02 <. 02 <.02 <. 02 <. 02 <. 02 <. 02 <.01 09/22/87-09/29/87 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 <.02

TABLE 4 (Page 4 of 4)

VIRGINIA POWER - SURRY - 1987 CONCENTRATIONS OF IODINE-131 IN FILTERED AIR pCi/m3 +/- 2 Sigma STATIONS ss HIR BC ALL CP DOW FE NN COLLECTION DATE OCTOBER 09/29/87-10/06/87 <.01 <. 01 <.01 <.01 <.01 <.01 <.01 <.01 10/06/87-10/13/87 <. 02 <. 02 <. 02 <. 02 <. 02 <.02 <. 02 <. 02 10/13/87-10/20/87 <. 02 <.02 <. 02 <.02 <. 02 <. 02 <.02 <. 02 10/20/87-10/27/87 <.01 <.01 <. 02 <. 02 <.01 <.01 <. 01 <.01 w 10/27/87-11/03/87 <.01 <.01 <. 01 <.01 <.01 <. 01 <.01 <.01 0

NOVEMBER ll/03/87-11/10/87 <.02 <. 02 <.02 <. 02 <. 02 <. 02 <. 02 <. 02 ll/10/87-11/17/87 <.01 <.01 <. 01 <.01 <.01 <.01 <.01 <.01 ll/17/87-11/24/87 <.03 <.03 <.03 <.04 <. 02 <. 02 <. 02 <.02 ll/24/87-12/01/87 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 DECEMBER.

12/01/87-12/08/87 <.01 <.01 <. 02 <.01 <. 01 <.01 <. 01 <.01 12/08/87-12/16/87 <.01 <.01 <.01 <.01 <.01 <.01 <.01 <.01 12/16/87-12/21/87 <.03 <. 03 <.03 <.03 <. 02 <. 02 <. 02 <. 02 12/21/87-12/29/87 <. 01 <. 01 <. 01 <. 01 <. 01 <.01 <. 01 <.009

TABLE 5 (Page 1 of 4)

VIRGINIA POWER - SURRY 1987 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 JANUARY 12/30/86-01/06/87 27 +/- 2 24 +/- 2 20 +/- 2 24 +/- 2 25 +/- 2 18 +/- 2 25 +/- 2 22 +/- 2 23 +/- 6 Ol/06/87-01/13/87 18 +/- 2 19 +/- 2 17 +/- 2 11 +/- 2 17 +/- 2 17 +/- 2 20 +/- 2 14 +/- 2 17 +/- 6 Ol/13/87-01/20/87 5.7 +/- 1. 2 ( b) 16 +/- 2 15 +/- 2 f~i 17 +/- 2 13 +/- 2 13 +/- 2 17 +/- 2 14 +/- 2 14 +/- 7 Ol/20/87-01/28/87 14 +/- 2 16 +/- 2 16 +/- 2 12 +/- 2 14 +/- 2 13 +/- 2 12 +/- 2 12 +/- 2 14 +/- 3 Ol/28/87-02/03/87 22 +/- 2 22 +/- 2 23 +/- 2 25 +/- 3 19 +/- 2 18 +/- 2 22 +/- 2 18 +/- 2 21 +/- 5 w

...... FEBRUARY 02/03/87-02/10/87 16 +/- 2 17 +/- 2 16 +/- 2 19 +/- 2 15 +/- 2 10 +/- 2 17 +/- 2 12 +/- 2 15 +/- 6 02/10/87-02/19/87 14 +/- 1 18 +/- 2 18 +/- 2 17 +/- 2 20 +/- 2 18 +/- 2 16 +/- 2 15 +/- 2 17 +/- 4 02/19/87-02/24/87 8.9 +/- 1. 7 15 +/- 2 13 +/- 2 17 +/- 2 18 +/- 2 12 +/- 2 17 :t 2 12 :t 2 14 :t 6 02/24/87-03/03/87 8. 9 :t 1. 7 11 :t 2 10 :t 2 14 +/- 2 12 :t 2 14 :t 2 12 +/- 2 11 +/- 2 12 :t 4 MARCH 03/03/87-03/ll/87 16 :t 2 13 :t 2 16 :t 2 18 :t 2 13 :t 1 14 :t 2 16 :t 2 16 :t 2 15 :t 4 03/11/87-03/17/87 15 :t 2 20 :t 2 16 :t 2 20 +/- 2 18 +/- 2 17 +/- 2 21 +/- 2 18 +/- 2 18 +/- 4 03/17/87-03/24/87 10 +/- 2 10 +/- 2 11 +/- 2 13 +/- 2 11 +/- 1 10 +/- 2 12 +/- 2 11 +/- 1 11 +/- 2 03/24/87-03/31/87 11 +/- 2 16 +/- 2 14 +/- 2 18 +/- 2 17 +/- 2 11 +/- 2 15 +/- 2 11 +/- 2 14 +/- 6 Quarter Average 14 +/- 12 17 +/- 8 16 +/- 7 17 +/- 8 16 +/- 8 14 +/- 6 17 +/- 8 14 +/- 7 16 :t 3

+/- 2 s .d.

f~ J Collection dates - Ol/06/87-01/12/87 Result confirmed by second count.

( C) Collection dates - Ol/12/87-01/20/87

TABLE 5 (Page 2 of 4)

VIRGINIA POWER - SURRY 1987 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 03/31/87-04/07/87 9.5 +/- 1. 5 12 +/- 2 10 +/- 2 13 +/- 2 10 +/- 2 8.9 +/- 1. 5 12 +/- 2 11 +/- 2 11 +/- 3 04/07/87-04/14/87 13 +/- 2 15 +/- 2 15 +/- 2 14 +/- 2 13 +/- 2 14 +/- 2 16 +/- 2 16 +/- 2 15 +/- 2 04/14/87-04/21/87 10 +/- 2 12 +/- 2 12 +/- 2 13 +/- 2 13 +/- 2 12 +/- 2 9.5 +/- 1. 4 12 +/- 2 12 +/- 3 04/21/87-04/28/87 7.9 +/- 1. 5 9.1 +/- 1. 5 7. 1 +/- 1. 4 8. 1 +/- 1. 5 8.0 +/- 1. 5 10 +/- 2 8.9 +/- 1. 5 9.4 +/- 1. 6 9 +/- 2 MAY w

N 04/28/87-05/05/87 14 +/- 2 17 +/- 2 17 +/- 2 20 +/- 2 17 +/- 2 15 +/- 2 16 +/- 2 16 +/- 2 17 +/- 4 05/05/87-05/12/87 17 +/- 2 17 +/- 2 18 +/- 2 18 +/- 2 16 +/- 2 19 +/- 2 19 +/- 2 17 +/- 2 18 +/- 2 05/12/87-05/19/87 15 +/- 2 18 +/- 2 14 +/- 2 15 +/- 2 17 +/- 2 17 +/- 2 16 +/- 2 17 +/- 2 16 +/- 3 05/19/87-05/26/87 6.6 +/- 1. 6 9.3 +/- 1. 8 6.5 +/- 1. 6 8.1 +/- 1. 7 9. 1 +/- 1. 8 7.3 +/- 1. 7 9.1 +/- 1.8 7. 3 +/- 1. 7 8 +/- 2 05/26/87-06/02/87 8.4 +/- 1. 4 16 +/- 2 15 +/- 2 16 +/- 2 15 +/- 2 16 +/- 2 16 +/- 2 16 +/- 2 15 +/- 5 JUNE 06/02/87-06/09/87 16 +/- 2 18 +/- 2 19 +/- 2 19 +/- 2 19 +/- 2 19 t 2 20 +/- 2 20 +/- 2 19 +/- 3 06/09/87-06/16/87 19 +/- 2 20 +/- 2 17 +/- 2 16 +/- 2 16 +/- 2 14 t 2 15 +/- 2 15 +/- 2 17 +/- 4 06/16/87-06/23/87 11 +/- 2 7.8 +/- 1. 5 13 +/- 2 14 +/- 2 14 t 2 14 t 2 14 t 2 14 +/- 2 13 +/- 4 06/23/87-07/01/87 13 +/- 1 8.7 +/- 1.1 12 +/- 1 15 +/- 1 12 +/- 1 15 +/- 1 16 +/- 1 16 +/- 1 13 +/- 5 Quarter Average 12 +/- 8 14 +/- 8 14 +/- 8 15 +/- 7 14 +/- 7 14 +/- 7 14 +/- 7 14 +/- 7 14 +/- 2

+/- 2 s.d.

TABLE 5 (Page 3 of 4)

VIRGINIA POWER - SURRY 1987 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 JULY 07/01/87-07/07/87 12 +/- 2 13 +/- 2 13 +/- 2 14 +/- 2 14 +/- 2 14 +/- 2 13 +/- 2 17 +/- 2 14 +/- 3 07/07/87-07/14/87 9.0 +/- 1. 5 21 +/- 2 19 +/- 2 16 +/- 2 17 +/- 2 19 +/- 2 20 +/- 2 25 +/- 2 18 +/- 9 07/14/87-07/21/87 22 +/- 3 21 +/- 2 19 +/- 2 20 +/- 2 21 +/- 2 19 +/- 2 20 +/- 2 21 +/- 2 20 +/- 2 07/21/87-07/28/87 29 +/- 2 29 +/- 2 29 +/- 2 31 +/- 3 28 +/- 2 29 +/- 2 31 t 2 29 t 2 29 t 2 07/28/87-08/04/87 22 +/- 2 21 +/- 2 21 t 2 24 t 2 21 +/- 2 22 t 2 23 t 2 24 +/- 2 22 t 3 w AUGUST w

08/04/87-08/11/87 19 t 2 25 t 2 23 t 2 25 t 2 23 t 2 19 t 2 22 t 2 27 t 2 23 t 6 08/11/87-08/18/87 13 t 2 14 t 2 14 t 2 12 t 2 14 t 2 12 +/- 2 11 +/- 2 13 +/- 2 13 +/- 2 08/18/87-08/25/87 24 t 2 24 +/- 2 21 +/- 2 20 +/- 2 23 +/- 3 22 t 2 21 t 2 21 t 2 22 +/- 3 08/25/87-08/31/87 21 t 2 21 +/- 2 18 +/- 2 22 t 2 27 t 3 19 t 2 19 +/- 2 22 +/- 2 21 +/- 6 SEPTEMBER 08/31/87-09/08/87 16 +/- 2 13 +/- 2 17 t 2 17 +/- 2 11 :I: 1 16 +/- 2 15 t 2 14 t 2 15 +/- 4 09/08/87-09/15/87 18 +/- 2 20 +/- 2 22 +/- 3 17 +/- 2 24 t 3 18 +/- 2 19 +/- 2 20 +/- 2 20 +/- 5 09/15/87-09/22/87 18 +/- 2 23 +/- 2 22 +/- 2 24 t 2 23 +/- 2 19 +/- 2 24 +/- 2 22 +/- 2 22 +/- 4 09/22/87-09/29/87 21 +/- 2 24 +/- 2 26 +/- 2 26 +/- 2 24 +/- 2 22 t 2 28 +/- 2 26 t 2 25 +/- 5 Quarter Average 19 +/- 11 21 +/- 10 20 +/- 9 21 +/- 11 21 +/- 10 19 +/- 8 20 +/- 11 22 +/- 10 20 +/- 2

+/- 2 s.d.

TABLE 5 (Page 4 of 4)

VIRGINIA POWER - SURRY 1987 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES 10-3 pCi/m3 +/- 2 Sigma STAT ION Average COLLECTION DATE ss HIR BC ALL CP DOW FE NN +/- 2 s.d OCTOBER 09/29/87-10/06/87 13 +/- 2 14 +/- 2 19 +/- 2 15 +/- 2 16 +/- 2 13 +/- 2 18 +/- 2 18 +/- 2 16 +/- 5 10/06/87-10/13/87 15 +/- 2 15 +/- 2 16 +/- 2 17 +/- 2 16 +/- 2 9.2 +/- 1. 5 16 +/- 2 16 +/- 2 15 +/- 5 10/13/87-10/20/87 26 +/- 2 22 +/- 2 31 +/- 2 29 +/- 2 29 +/- 3 28 +/- 2 28 +/- 2 25 +/- 2 27 +/- 6 10/20/87-10/27/87 21 +/- 2 22 +/- 2 27 +/- 2 26 +/- 2 23 +/- 2 25 +/- 2 24 +/- 2 20 t 2 24 t 5 10/27/87-11/03/87 23 +/- 2 18 +/- 2 28 +/- 2 24 +/- 2 23 +/- 2 27 +/- 2 26 t 2 20 +/- 2 24 +/- 7 w NOVEMBER

~

ll/03/87-11/10/87 14 +/- 2 18 +/- 2 20 +/- 2 22 +/- 2 20 +/- 2 19 +/- 2 21 +/- 2 21 t 2 19 t 5 ll/10/87-11/17/87 20 +/- 2 20 +/- 2 24 +/- 2 21 +/- 2 21 +/- 2 21 +/- 2 21 +/- 2 19 t 2 21 t 3 ll/17/87-11/24/87 18 t 2 18 +/- 2 22 t 2 18 +/- 2 16 +/- 2 19 t 2 24 t 2 18 t 2 19 t 5 11/24/87-12/0l/87 12 t 2 13 +/- 2 8.7 +/- 1. 5 11 t 2 14 +/- 2 14 t 2 10 +/- 2 13 t 2 12 t 4 DECEMBER 12/01/87-12/08/87 12 t 2 14 +/- 2 17 +/- 2 11 +/- 2 12 +/- 2 14 +/- 2 14 +/- 2 13 +/- 2 13 +/- 4 12/08/87-12/16/87 15 +/- 2 16 +/- 2 20 +/- 2 18 +/- 2 15 +/- 2 14 +/- 2 17 +/- 2 15 +/- 2 16 +/- 4 12/16/87-12/21/87 14 +/- 2 18 +/- 2 19 +/- 2 16 +/- 2 17 +/- 2 12 +/- 2 15 +/- 2 14 +/- 2 16 +/- 5 12/21/87-12/29/87 15 +/- 2 18 +/- 2 22 +/- 2 19 +/- 2 19 +/- 2 19 +/- 2 16 +/- 2 8.1 t 1. 2 17 +/- 8 Quarter Average 17 +/- 9 17 +/- 6 21 +/- 12 19 +/- 11 19 +/- 9 18 +/- 12 19 +/- 11 17 +/- 9 18 +/- 3

+/- 2 s .d.

Annual Average 16 +/- 11 17 +/- 9 18 +/- 11 18 +/- 10 17 +/- 10 16 +/- 10 18 +/- 10 17 +/- 10 17 +/- 2

+/- 2 s .d.

_ _ _ _ __J

6 (Page 1 of 2)

VIRGINIA POWER - SURRY - 1987 CONCENTRATIONS OF GAMMA EMITTERS* IN QUARTERLY AIR PARTICULATES 10-3 pCi/m3 +/- 2 sigma FIRST QUARTER SECOND QUARTER THIRD QARTER FOURTH QUARTER AVERAGE STATION NUCLIDE 12/30/86-03/31/87 03/31/87-07/01/87 07/01/87-09/29/87 09/29/87-12/29/87 +/- 2.s.d.

ss Be-7 66.6 +/- 6.7 82.6 +/- 8.3 143 +/- 14 49.1 +/- 4.9 85.3 +/- 81. 6 K-40 <4 7.79 +/- 2.27 <10 <5 7.79 +/- 2.27 Co-60 <0.2 <O .1 <0.5 <0.2 Cs-134 <0.2 <0.2 <0.5 <0.2 Cs-137 <0.2 <0.2 <0.5 <0.2 Th-228 <0.5 <0.3 <0.7 <0.4 HIR Be- 7 75.0 +/- 7.5 68.1 +/- 6.B 82.8 +/- 8.3 55.1 +/- 5.5 70.3 +/- 23.5 K-40 <4 <3 <5 6.03 +/- 2.86 6.03 +/- 2.86 w Co-60 <0.2 <0.2 <0.3 <0.4

(.J1 Cs-134 <0.2 <0.2 <0.3 <0.4 Cs-137 <0.2 <0.2 <0.3 <0.4 Th-228 <0.4 <0.3 <0.5 <0.5 BC Be-7 103 +/- 10 79.3 +/- 7.9 143 +/- 14 62.7 +/- 6.3 97.0 +/- 69. 70 K-40 <9 3.27 +/- 1.20 <4 <4 3.27 +/- 1. 20 Co-60 <0.4 <O. 1 <0.2 <0.3 Cs-134 <0.4 <O. 1 <0.2 <0.2 Cs-137 <0.4 <O. 1 <0.2 <0.2 Th-22B <0.9 <0.2 <0.5 <0.4 ALL Be-7 95.8 +/- 9.6 52.4 +/- 5.2 153 +/- 15 55.5 +/- 5.6 89.2 +/- 93.8 K-40 <6 22.3 +/- 2.2 <6 <4 22.3 +/- 2.2 Co-60 <0.4 <O. 1 <O. 4 <0.2 Cs-134 <0.4 <O.l <0.4 <0.2 Cs-137 <0.5 <O. 1 <0.4 <0.2 Th-228 <0.6 0.51 +/- 0.19 <0.7 <0.3 0.51 +/- 0.19

All other gamma emitters were <LLD.

TABLE 6

{Page 2 of 2)

VIRGINIA POWER - SURRY - 1987 CONCENTRATIONS OF GAMMA EMITTERS* IN QUARTERLY AIR PARTICULATES 10-3 pCi/m3 +/- 2 sigma FIRST QUARTER SECOND QUARTER THIRD QARTER FOURTH QUARTER AVERAGE STAT ION. NUCLIDE 12/30/86-03/31/87 03/31/87-07/01/87 07/0l/87-09/29/87 09/29/87-12/29/87 +/- 2.s.d.

CP Be-7 85.6 +/- 8.6 84.9 +/- 8.5 128 +/- 13 55.6 +/- 5.6 88.5 +/- 59.6 K-40 <4 2. 34 +/- I. 02 <IO <4 2.34 +/- I. 02 Co-60 <0.2 <O. I <0.5 <0.2 Cs-134 <0.2 <O.l <0.4 <0.2 Cs-137 <0.3 <0.2 <0.4 <O. 2 Th-228 <0.4 <0.2 <0.7 <O. 2 DOW Be- 7 75.7 +/- 7.6 86.2 +/- 8.6 136 +/- 14 51.5 +/- 5.2 87.4 +/- 71.1 K-40 <10 <6 7.18 +/- 3.54 <4 7.18 +/- 3.54 w Co-60 <0.4 <0.2 <0.2 <0.2 O"I Cs-134 <0.4 <O. 2 <0.2 <0.2 Cs-137 <0.4 <0.2 <0.3 <0.2 Th-228 <0.5 <0.3 <0.5 <0.3 FE Be-7 62.0 +/- 6.2 81.9 +/- 8.2 148 +/- 15 59.2 +/- 5.9 87.8 +/- 82.8 K-40 <10 3. 50 t 1. 72 <IO <20 3.50 t 1. 72 Co-60 <0.3 <0.2 <0.5 <0.5 Cs-134 <0.3 <O. I <0.5 <0.5 Cs-137 <0.3 <O.l <0.5 <O. 4 Th-228 <0.3 <0.2 <0.8 <0.6 NN Be-7 7LOt7.7 90.3 t 9.0 163 t 16 53.2 t 6.0 95.9 t 94.6 K-40 <8 <6 <5 <IO Co-60 <0.4 <0.3 <0.3 <0.6 Cs-134 <0.4 <0.3 <0.3 <0.6 Cs-137 <0.4 <O. 3 <0.3 <0.5 Th-228 <0.6 <0.5 <0.5 <0.7

All 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 in contrast to the fresh water samples discussed above.

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 by gamma spectrometry and for Iodine-131 by a radiochemical procedure; The samples were also analyzed for tritium on a quarterly basis. The results are presented in Table 8.

Potassium-40 was measured in ten of the samples with an average concentration of 80.9 pCi/£ and a range of 63.9 to 107 pCi/£. Cobalt-58 was observed in one sample with an activity of 32.3 pCi/£. This value compares well with the average cobalt-58 activity discharged from the station during the environmental sampling. No other gamma emitters were detected. Radiochemical analysis of the samples detected no iodine-131 analyzed to levels well below the required sensitivity (LLD).

Tritium was measured in four out of eight composites of Surry Discharge and Scotland Wharf monthly samples. One composite sample from Scotland Wharf indicated tritium activity of 290 pCi/£. The average activity of Surry Discharge was 897 pCi/£ with a range of 220 to 1260 pCi/£. The low end of the range is indicative of normal (background) levels of tritium activity in the river water while the upper end compares well with the predicted concentrations of the discharge canal during releases from the station.

37

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 naturally occurring potassium-40, all the-,--gamma emitting nuclides were below their respective detection limits. Potassium-40 was measured seven times with an average activity of 71.8 pCi/£ and a range of 48.l to 123 pCi/£. The average tritium activity for the four quarterly samples collected at the Surry Discharge location was 550 pCi/£ and a range from 190 to 840 pCi/£. The attached trend graphs provide a comparison of tritium activity measured in the downstream sample (Surry Discharge), the upstream control location {Scotland Wharf) and the station effluents sample. The Station Discharge indicates good comparison with measured station effluents. The average tritium activity in station effluents was 361 pCi/£ with a range of 142 to 562 pCi/£. Variations between the two samples may be due to sampling and composite methodology of the environmental samples. At Scotland Wharf location the four quarterly samples had an average tritium activity of 163 pCi/£ with a range of 130 to 210 pCi/£.

The trend graphs indicate that there is no long term build up of tritium in the environment. All gamma emitters were below their Lower Limit of Detection (LLD).

38

AVERAGE RIVER WATER TRITIUM 100000 I

~

t 10000

' ~

8 w

i

s

\

'° ....Cb 1\ j l i!::

~

(j Q. 1000

\ ~... \--. .

I \...

,I l

,~I "" / ,,.....i .....

I ', ~

1 I

,1 I '

'\ I l

" \ / ~

"' /

~~ / l(

100 . . .

'l

.1968 1969 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987

-e- Scot Wharf

-+- SurDis.

RIVER WATER TRITIUM- 1987

+ SurDis First Qtr Second Otr Third Otr Fourth Qtr

... ScotWharf

-a- Sta Effluent

TABLE 7 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1987 ANALYSIS AND LOWER LIMIT NUVIBER OF 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 River Water (a) Gamma 46

( pCi/ £)

K-40 46 83.7(9/35) NN 86.5(4/6) 56.4(1/11) 0 (63.9-107) (78.6-101)

Co-58 46 15 32.3(1/35) SD 32.3(1/11) -(0/11) 0

..i::,.

Tritium 16 2000 897(3/4) SD 897(3/4) 290(1/4) 0 (Quarterly) (220-1260) (220-1260)

River Water (b) Gamma 24 pCi/£ - State Split K-40 24 79.4(5/12) SD 79.4(5/12) 53.0(2/12) 0 (49.3-123) (49.3-123) (48.1-57.8)

Tritium 8 2000 550(3/4) SD 550(3/4) 163(3/4) 0 (190-840) (190-840) (130-210)

(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.

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

(b) Monthly State Split analyses presented in Table 9.

T.8 (Page 1 of 3)

VI RGI.NI A POWER - SURRY - 1987 CONCENTRATIONS OF GAMMA EMITTERS* AND TRITIUM IN RIVER WATER pCi/£ +/- 2 Sigma STATION DATE Be-7 K-40 1-131 Cs-137 Ba-140 La-140 TH-228 H-3 JANUARY CHIC 01/14/87 <60 <100 <0.5 <5 <40 <10 <10 HIP 01/14/87 <40 <60 <0.5 <4 <20 <10 <8 NN 01/14/87 <40 83.9 +/- 33.3 <0.5 <4 <30 <10 <8 SD 01/14/87 <40 <60 <0.5 <4 <30 <10 <8 220 +/- 90 (a)

SI 01/14/87 <40 <60 <0.5 <4 <30 <10 <8 SW 01/14/87 <50 <60 <0.4 <4 <30 <9 <9 <130 ( a)

FEBRUARY SD 02/19/87 <40 <50 <O. 4 <4 <20 <7 <8 v SW 02/19/87 <40 <60 <0.5 <4 <20 <9 <8 MARCH CHIC 04/01/87 <40 <60 <0.2 <4 <10 <5 <8 HIP 03/26/87 <40 <60 <0.4 <4 <20 <8 <8 NN 03/26/87 <60 <100 <0.5 <6 <30 <10 <10 SD 04/01/87 <30 <60 <0.2 <4 <10 <6 <8 SI 03/26/87 <40 <60 <0.4 <4 <20 <7 <8 SW 04/01/87 <30 <60 <0.2 <4 <10 <6 <8 APRIL so 04/21/87 <40 <60 <0.3 <4 <10 <6 <8 <130 ( b)

SW 04/21/87 <50 <100 <0.2 <5 <20 <7 <10 <110 ( b)

All other gamma emitters were <LLD.

( a) First Quarter Composite

( b) Second Quarter Composite

_____ ___J

(Page 2 of 3)

VIRGINIA POWER - SURRY - 1987 CONCENTRATIONS OF GAMMA EMITTERS* AND TRITIUM IN RIVER WATER pC i / £ +/- 2 Si gm a STATION DATE Be-7 K-40 I-131 Cs-137 Ba-140 La-140 TH-228 H-3 MAY CHIC 05/19/87 <30 <50 <0.4 <3 <10 <6 <7 HIP 05/19/87 <40 <100 <0.3 <5 <20 <8 <9 NN 05/14/87 <40 78.6 +/- 34.2 <0.5 <4 <20 <8 <8 SD 05/19/87 <40 <60 <0.3 <4 <20 <8 <7 SI 05/14/87 <40 <60 <0.5 <4 <20 <8 <8 SW 05/19/87 <40 <60 <0.4 <5 <20 <7 <8 JUNE i,.

.A)

SD 06/16/87 <40 <50 <0.3 <3 <20 <7 <8 SW 06/16/87 <30 <60 <0.3 <3 <20 <7 <7 JULY CHIC 07/15/87 <40 <70 <0.5 <5 <20 <8 <8 HIP 07/15/87 <40 <100 <0.5 <4 <20 <8 <8 NN 07/15/87 <50 82.4 +/- 41.4 <0.4 <5 <20 <10 <10 SD 07/15/87 <30 67.0 +/- 27.3 <0.5 <3 <20 <7 <7 1210 +/- 100 ( b)

SI 07/15/87 <30 63.9 +/- 26.3 <0.4 <3 <10 <7 <7 SW 07/15/87 <30 <60 <0.5 <4 <20 <7 <7 <140 (b)

AUGUST SD 08/15/87 (a)

SW 08/15/87 (a)

All other gamma emitters were <LLD.

( a) No sample collected due to oversight in fie 1d.

( b) Third Quarter Composite

TABLE 8 (Page 3 of 3)

VIRGINIA POWER - SURRY - 1987 CONCENTRATIONS OF GAMMA EMITTERS* ANO TRITIUM IN RIVER WATER pCi/£ +/- 2 Sigma STATION DATE Be-7 K-40 1-131 Cs-137 Ba-140 La-140 TH-228 H-3 SEPTEMBER CHIC 09/21/87 <60 <100 <0.3 <6 <30 <7 <10 HIP 09/17/87 <50 <80 <O. 4 <6 <20 <9 <10 NN 09/17/87 <50 <80 <0.4 <6 <30 <10 <9 SD 09/21/87 <70 <200 <0.4 <8 <30 <10 <20 SI 09/17/87 <60 107 +/- 56 <0.4 <6 <30 <10 <10 SW 09/21/87 <40 <60 <0.3 <4 <20 <6 <8 OCTOBER

.i:,.

.i:,. SD 10/20/87 <30 88.0 +/- 39.3 <0.3 <4 <10 <6 <8 1260 +/- 200 ( b ~

SW 10/20/87 <40 56.4 +/- 32.2 <0.3 <4 <20 <6 <8 290 +/- 100 (b NOVEMBER CHIC 11/17/87 <40 <100 <0.3 <4 <20 <6 <8 HIP 11/13/87 <40 <100 <0.4 <4 <20 <7 <8 NN 11/13/87 <30 101 +/- 29 <0.4 <3 <20 <6 <7 SD 11/13/87 <30 81.l +/- 26.8 <0.4 <3 <20 <6 <7 SI 11/13/87 <60 <100 <0.3 <6 <30 <10 <10 SW 11/17/87 <40 <60 <0.2 <4 <20 <7 <7 DECEMBER SD 12/16/87 <50 <100 <0.2 <5 <20 <6 <9 ( a)

SW 12/16/87 <30 <50 <0.3 <3 <10 <5 <6

All other gamma emitters were <LLD.

( a) Positive Co-58 result of 32.3 +/- 5.0 confirmed by recount.

( b) Fourth Quarter Composite

9 VIRGINIA POWER - SURRY - 1987 CONCENTRATIONS Of GAMMA EMITTERS* AND TRITIUM IN RIVER WATER pCi/l t 2 Sigma - STATE SPLIT MONTH COLL. DATES 8e-7 K-40 1-131 Cs-137 8a-140 La-140 Th-228 H-3 1987 SCOTLAND WH. ~

January 01/15/87 <60 <40 <2 O (a) <3 <100 ( a) <5 0 (a) <7 <130 February 02/15/87 <60 <50 <6 <4 <200 ( a) <60 (a) <8 March 03/15/87 <60 57.8 t 30.8 <6 <4 <100 fa~ <40 fa J <8 April 04/15/87 <60 <100 <1 <4 <100 a <40 a <8 150 :t 90 May 05/15/87 (50 <40 <7 <3 <100 ( a) <40 (a) <6 June 06/15/87 <50 <50 <l <4 <100 ( a) <40 (a) <7 July 07/15/87 <80 <80 <7 <5 <100 (a) <50 (a) <IO 130 t 70 August 08/15/87 <30 <50 <3 <3 <30 <10 <6 September 09/15/87 <40 <50 <7 <3 <60 <30 (a) <6 October 10/15/87 <40 48.l t 27.8 <10 <3 <50 (a) <20 (a) <5 210 t 70 November 11/15/87 <.50 <50 <10 <3 <90 (a) <40 (a) <6 December 12/15/87 <30 <40 <3 <2 <30 <IO <5

~

(.Tl Average t 53.0 t 14 168 t 83 2 s. d.

SURRY DIS. ~

January February 01/15/87 02/15/87

<60

<50

<40 (a)

<8

<4

<100

<200 f aJ a

<50

<60 f aJ a

<8

<9

<130 March April 03/15/87 04/15/87

<60

<50

<60

<40

<6

<2

<4

<3

<100

<90 1 aJ a

<50

<30 f aJ a

<8

<7 190 t 110 May 05/15/87 <50 <40 <7 <3 <100 (a) <40 ( a) <7 June 06/15/87 <60 <60 <2 <3 <100 ~ a~ <40 ( aJ <8 July 07/15/87 <70 103 t 43 <IO <6 <100 a <40 (a <10 840 t 100 August 08/15/87 <40 123 t 30 <3 <3 <40 <10 <7 September 09/15/87 <40 62.7 t 31.9 <6 <3 <70 (a) <30 (a) <7 October 10/15/87 <40 <50 <5 <3 <60 (a) <2 0 (a) <7 620 t 80 November 11/15/87 <50 49.3 t 24 <10 <3 <100 ( a) <40 (a) <7 December 12/15/87 <30 58.9 t 22.6 <4 <3 <30 <10 <4 Average t 79.4 t 64 550 t 661 2 s .d.

All other gamma emitters were <LLD.

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

2. Well Water The results of ~nalyses of well water samples are presented in Table

11. Well water was collected from four indicator locations during March, June, September and December. A resample was taken in January 1988 due to the elevated tritium results of the 1987 fourth quarter samples. Cross-*

contamination during sampling is considered unlikely since samples are collected in shipping containers and mailed directly to the analysis lab~

Also, the analysis of the fourth quarter samples revealed no gamma emitting isotopes normally expected with these levels of tritium. The tritium-activity of the resamples compared favorably with samples from previous years.

Excluding the fourth quarter results, the tritium measured in the four samples with positive results had an average of 263 pCi/£ and a range of 110 to 530 pCi/£.

The well water samples were also anlayzed by gamma spectroscopy.

Naturally occurring potassium-40.was observed in one sample with an activity of 92.3 pCi/£. All gamma emitters that may result from station releases were below detection limits.

46

TABLE 10 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1987 ANALYSIS AND LOWER LIMIT NUMBER OF 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 Well Water Tritium 16 2000 (a) 263(4/16) ss 263(4/4) NONE 0

( pCi/ £) ( 110-530) (110-530)

K-40 16 92.3(1/16) JMTN 92.3(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 Progrc111, Revision 1, November 1979.

(a) Does not include 12/21/87 data.

11 VIRGINIA POWER - SURRY-1987 CONCENTRATIONS OF TR IT I UM AND GAMMA EMITTERS* IN WELL WATER pCi / £ +/- 2 Sigma DATE STATION Be- 7 K-40 1-131 Cs-137 Ba-140 La-140 Th-228 H-3 FIRST QUARTER 03/24/87 BC <50 <80 <0.3 <6 <20 <7 <10 <130 03/24/87 HIR <40 <60 <0.3 <4 <20 <6 <8 <130 03/24/87 JMTN <40 92.3 +/- 33.2 <0.3 <4 <20 <9 <8 <130 03/24/8 7 ss <40 <50 <0.2 <4 <10 <6 <8 110 +/- 100 SECOND QUARTER 06/23/87 BC <30 <60 <0.3 <4 <10 <7 <8 <130 06/2 3/8 7 HIR <30 <50 <0.3 <4 <10 <5 <7 <130 06/23/87 JMTN <50 <100 <0.2 <5 <20 <7 <10 <130 06/23/87 ss <60 <100 <0.3 <6 <20 <6 <10 120 +/- 90

~

OJ THIRD QUARTER 09/22/87 BC <30 <50 <0.2 <3 <10 <6 <7 <130 09/22/87 HIR <60 <100 <0.3 <7 <20 <6 <10 <130 09/22/87 JMTN <40 <60 <0.3 <4 <10 <6 <8 <130 09/22/87 ss <50 <90 <0.4 <5 <20 <8 <10 290 +/- 100 FOURTH QUARTER 12/21/87 BC <40 <100 <0.3 <5 <20 <7 <8 390 +/- 120 12/21/87 HIR <30 <50 <0.3 <4 <10 <5 <6 950 +/- 100 12/21/87 JMTN <30 <60 <0.2 <4 <10 <6 <7 120 +/- 70 12/21/87 ss <30 <50 <0.3 <3 <3 <4 <20 6700 +/- 300 FOURTH QUARTER RESAMPLE 01/26/88 BC <60 <200 <0.2 <7 <20 <9 <10 <100 01/26/88 HIR <40 <70 <0.2 <5 <20 <8 <7 <100 01/26/88 JMTN <50 <200 <0.2 <6 <20 <9 <10 <100 01/26/88 ss <50 <200 <0.2 <6 <20 <8 <10 530 +/- 110

All other gamma emitters were <LLD.

C. Aquatic Exposure Pathway

1. Si 1t Sediment samples were collected in March, and in September from each of six locations and were analyzed by gamma spectrometry. The results are presented in Table 13. A number of man-made and naturally occurring radioisotopes were measured. The Surry Discharge location measured cobalt-58 activity with an average of* 1232 pCi/kg (dry weight) and a*range of 873 to 1590 pCi/kg (dry weight). These results were lower than those taken at the same location in 1985 and 1986. Cobalt-58 results from other sample locations were similar to sample results from 1986 and remain close to the lower level of detection (LLD).

Cobalt-60 was measured in all twelve samples which include the control location as Chickahominy. As expected, Surry Discharge was the location with the highest activity measuring an average of 8485 pCi/kg (dry weight) and a range of 8450 to 8520 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. All samples were generally lower than those results from 1986 and comparable to 1985 results.

Cesium-134 was measured in all locations except Newport News with the highest location at Surry Discharge. This location measured an average activity of 474 pCi/kg (dry weight) ~nd a range of 155 to 793 pCi/kg (dry weight). The trend graphs continue to indicate decreasing activity as compared to previous years.

Cesium-137 was measured in all samples, again with the highest activity at Surry Discharge. The average at this location was 2345 pCi/kg (dry

weight) and a range of 1480 to 3210 pCi/kg (dry weight). The average 49

from all other indicator locations was 764 pCi/kg (dry weight) and a range of 194 to 1160 pCi/kg (dry weight). The average from the control location (CHIC) was 960 pCi/kg (dry weight) with a range of 910 to 1010 pCi/kg (dry weight). The trend graphs generally indicate no increases in cesium-137 activity .

50

COBAL T-58 IN SILT 10000

. I Jfl' \

t"' \

J \

~

1000 J\.

I

\.

8 , I

' I

'\ I C.11

~

i

__ ~v

'\

\ ,I I

I

\

\ I I

I

/ ,J' \ - __....., I

~

(.) /

' _/

' V \~.

Q. * ~

100

__, r -- '

... Hog Island 10 . . . - - . . . .

1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 -1985 1986 1987

-+- Station Intake

-a- Station Dis.

COBAL T-60 IN SILT 100000

... ~

10000 t --

~

8

/

) '-

/ V I

~

---i

~

/

~

<.n N

~

0 i

s.

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1000 I

J

-- -I *- -'

o /

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J 100 I\.

I ,

J~

"' ~ ~ .( i V !/ "114,

~*~I

-a- Hog Island 1o . - . . . --.

..... Station Intake 1912 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987

-a- Station Dis.

CESIUM-134 IN SILT 10000 1000 ....,.J. -~.... -~ ["-.

§

,, I -- -

Cl) ~

0

,~ ""'Ir

~ l

'\ ,I

~ .......

~

II u, / ~ ~ ~

w

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...... .J*I""" '""'-..

2'. \ / / *><

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/ ~ .(

~ I 100 10 . . .

~-----.

~

-a- Hog Island 1972 1973 1974 1975 1976 1977 1978 1979 1900 1981 1982 1983 1984 1985 1986 1987

+ Station Intake

+ Station Dis.

CESIUM-137 IN SILT 10000

~

]

(/) .~

' / ~\ ~ V"

/

('"

/

' "\V ~.

<.J1

~

8 Cl.

1000

\\\ /I) \\

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/

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(.) '\ I f \ r """"- / \. A / "-

/\ I I I 7' 7 Cl. '\..\ \

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-m- Hog Island

..... Station Intake 1oo . . . .

Station Dis. 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987

-+- CHIC

2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1987 ANALYSIS AND LOWER LIMIT NUMBER OF 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 Silt Gamma Spec 12 (pCi/kg dry)

Be-7 12 1165(7/10) POS 2030(1/2) 347(1/2) 0 (409-2030)

K-40 12 14670( 10/10) CHIC 17200(2/2) 17200(2/2) 0

( l 3400-16800) (14900-19500) (14900-19500)

Mn-54 12 174(2/10) SD 174(2/2) -(0/2) 0 (130-218) (130-218) u, u,

Co-58 12 562(5/10) SD 1232(2/2) -(0/2) 0 (68.9-1590) (873-1590)

Co-60 12 2136po110J SD 8485~2/2l 382l2/2) 0 (53. -8520 (845 -85 0) (38 -382)

Cs-134 12 150 283(6/10) SD 474(2/2) 155(2/2) 0 (155-793) (155-793) (145-164)

Cs-137 12 180 1041(10/10) SD 2345(2/2) 960(2/2) 0 (194-3210) (1480-3210) (910-1010)

Ra-226 12 1855 ( 10/10 ~ SD 2365(2/2) 3180(2/2) 0 (1230-2560 (2170-2560) (2680-3680)

Th-228 12 1099(10/10) CHIC 1360(2/2) 1360(2/2) 0 (601-1440) (1350-1370) (1350-1370)

(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 - SURRV-1987 CONCENTRATIONS OF GA,..,.,A* EMITTERS IN SILT pCi/kg (dry)+/- 2 Sigma STATION CHIC HIP NN POS SD SI COLLECTION DATE 04/01/87 03/26/87 03/26/87 03/26/87 04/01/87 03/26/87 Be-7 347 +/- 177 923 +/- 327 409 +/- 174 2030 +/- 380 <500 1650 +/- 240 K-40 14900 +/- 1500 13600 +/- 1400 13400 +/- 1300 15900 +/- 1600 15700 +/- 1600 14500 +/- 1500 Mn-54 <30 <40 <20 <30 130 +/- 46 <30 u, Co-:58 <30 <50 <20 157 +/- 40 873 +/- 87 119 +/- 26

°'

Co-60 381 +/- 38 895 +/- 90 53.1 +/- 20.7 745 +/- 75 8450 +/- 850 984 +/- 98 Cs-134 145 +/- 27 189 +/- 64 <30 171 +/- 31 793 +/- 79 235 +/- 27 Cs-137 910 +/- 91 975 +/- 98 194 +/- 28 959 +/- 96 3210 +/- 320 1160 +/- 120 Ra-226 3680 +/- 530 1980 +/- 530 1360 +/- 390 1360 +/- 340 2170 +/- 610 1900 +/- 380 Th-228 1370 +/- 140 1240 +/- 120 601 +/- 60 943 +/- 94 1170 +/- 120 938 +/- 94

All other gamma emitters were <LLD.

TABLE 13 (Page 2 of 2)

VIRGINIA POWER - SURRY-19B7 CONCENTRATIONS OF GAMMA* EMITTERS IN SILT pCi/kg (dry)+/- 2 Sigma STATION CHIC HIP NN POS SD SI Average COLLECTION DATE 09/21/87 09/17/87 09/17/87 09/17/87 09/17/87 09/17/87 +/- 2 s.d Be-7 <500 <400 575 +/- 194 <300 1420 +/- 550 1150 +/- 400 1063 +/- 1222 K-40 19500 +/- 1900 13800 +/- 1400 14400 +/- 1400 13600 +/- 1400 16800 +/- 1700 15000 +/- 1500 15092 +/- 3476 Mn-54 <40 <30 <20 <20 218 +/- 66 <40 174 +/- 124

<.n

--..J Co-58 <50 68.9 +/- 30.7 (30 <30 1590 +/- 160 <50 562 +/- 1325 Co-60 382 +/- 46 620 +/- 62 203 +/- 25 177 +/- 31 8520 +/- B50 714 +/- 71 1844 +/- 6232 Cs-134 164 +/- 40 <40 <30 <30 155 +/- 31 157 +/- 38 251 +/- 442 Cs-137 1010 +/- 100 581 +/- 58 524 +/- 52 361 +/- 36 1480 +/- 150 967 +/- 97 1028 +/- 1550 Ra-226 2680 +/- 450 2130 +/- 440 1230 +/- 320 1840 +/- 440 2560 +/- 720 2020 +/- 530 2076 +/- 1352 Th-228 1350 +/- 130 1320 +/- 130 776 +/- 78 1270 +/- 130 1440 +/- 140 1290 +/- 130 1142 +/- 530

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, thorium-228 and radium-226 were observed in all samples. Cesium-137 was measured in three samples with an average activity of 39.5 pCi/kg (dry weight) and a range of 22.6 to 52.4 pCi/kg (dry weight). These values were lower than 1986 and comparable to the 1984 and 1985 sample results.

58 i J

TABLE 14 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1987 ANALYSIS AND lOWER LIMIT NUMBER OF 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 Shoreline Sediment Gamma Spec 4 (pCi/kg dry)

K-40 4 4843(4/4) HIR 7250(2/2) NONE 0 (1530-7670) (6830-7670)

Cs-137 4 180 39.5(3/4) HIR 47.9(2/2) NONE 0 (22.6-52.4) (43.4-52.4)

U1 I.O Ra-226 4 640(1/4) BURWELL'S 640(1/2) NONE 0 Th-228 4 148(4/4) BURWELL'S 186(2/2) NONE 0 (108-228) (143-228)

(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.

L_ --

TABLE 15 VIRGINIA POWER - SURRY-1987 CONCENTRATIONS OF GAMMA EMITTERS* IN SHORELINE SEDIMENT pCi/kg (dry)+/- 2 Sigma STAT ION HIR BURWELL Is HIR BURWELL'S AVERAGE COLLECTION DATE 04/28/87 04/28/87 11/24/87 11/24/87 +/- 2.s.d.

Be-7 <100 <100 <100 <100 K-40 6830 +/- 680 1530 +/- 150 7670 +/- 770 3340 +/- 330 4843 +/- 5794 Co-60 <10 <10 <10 <10 Cs-134 <10 <10 <10 <10

°'

C)

Cs-137 52.4 +/- 10.7 22.6 +/- 11. 0 43.4 +/- 11.8 <10 39.5 +/- 30.6 Ra-226 <200 640 +/- 208 <200 <300 640 +/- 208 Th-228 lOB +/- 12 143 +/- 14 111 +/- 13 228 +/- 23 148 +/- 112

All other gamma emitters searched for were <LLD.

L _____ _

D Ingestion Exposure Pathway

1. 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. Iodine was not detected in any of the si,><_ty samples, therefore, a lower limit of detection 0.5 pCi/£ or better was achieved in all samples.

Naturally occurring potassium-40 was detected in all samples. The average for the control location (WMS) was 1263 pCi/£ and the range was 1060 to 1370 pCi/£. The average measurement for the 48 indicator samples was 1291 pCi/£ with a range of 1000 to 1490 pCi/£ .

Cesium-137, which has been detected occasionally in recent years and attributed to past atmospheric nuclear weapons testing (global fallout) was measured in four indicator samples with an average activity of 7.1 pCi/£ and a range of 5.2 to 9.8 pCi/£. No other gamma emitters were detected.

Fifteen milk samples from three indicator stations, Lee Hall, Epps and Colonial Parkway locations were also analyzed for strontium-89 and strontium-90 during 1987. Strontium-89 was not detected in any of the samples. Strontium-90 was detected in all samples with an average -

_concentration of 1.8 pCi/£ and a range of 0.67 to 4.2 pCi/£. 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/£.

61

TABLE 16 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1, to DECEMBER 31, 1987 ANALYSIS AND LOWER LIMIT NUMBER OF 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 Milk Garmia Spec 60 (pCi/£)

K-40 60 1291(48/48) CP 1346(12/12) 1263(12/12) 0 (1000-1490) (1090-1460) ( 1060-1370)

CJ)

Cs-137 60 18 7.1(4/48) EPPS 7.7(3/12) -(0/12) 0 N (5.2-9.8) 5.8-9.8) 1-131 60 1 -(0/48) N/A -(0/12) -(0/12) 0 Sr-89 15 -(0/26) NA NA -(0/1) 0 Sr-90 15 }.8(15/15) CP 3.3(3/3) -(0/0) 0 (0.67-4.2) (2.3-4.2)

(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 17 (Page 1 of 3)

VIRGINIA POWER - SURRY - 1987 CONCENTRATIONS OF STRONTIUM-89 AND -90 AND GAMMA EMITTERS** IN MILK pCi/£ +/- 2 sigma MONTH NUCLIDE LEE HALL* EPPS\t CP WMS JDKS JANUARY Sr-89 <4 <5 Sr-90 1. 8 +/- 0.7 1. 3 +/- 0.8 K-40 1300 +/- 130 1360 +/- 140 1310 +/- 130 1060 +/- 110 1170 +/- 120 Cs-137 <5 <6 <5 <4 <6 1-131 <0.4 <0.3 <0.3 <0.3 <0.3 FEBRUARY Sr-89 <4 <4 en Sr-90 1. 7 +/- 0.8 1. 4 +/- 0.8 w K-40 1290 +/- 130 1360 +/- 140 .1300 +/- 130 1340 +/- 130 1080 +/- 110 Cs-137 <5 <5 <7 <4 <7 1-131 <0.4 <0.5 <0.5 <0.4 <0.3 MARCH Sr-B9 <9 <7 Sr-90 1. 8 +/- 1. 0 1.1 +/- 0.6 K-40 1340 +/- 130 1250 +/- 130 1410 +/- 140 1290 +/- 130 1250 +/- 130 Cs-137 <5 7. 40 +/- 3. 71 <4 <5 <8 I -131 <0.5 <0.5 <O. 4 <O. 3 <0.5 APRIL Sr-B9 <2 (a) <2 (a) <5 (a)

Sr-90 1. 4 +/- 0.5 ( a) 1. 2 +/- 0.5 (a) 3.4+/- 0.8 (a)

K-40 1300 +/- 130 1210 +/- 120 1430 +/- 140 1270 +/- 130 1360 +/- 140 Cs-137 <4 .<6 <4 <6 <5 1-131 <0.5 <0.3 <0.5 <0.4 <0.4

State split

- All other gamma emitters were LLD.

( a) Strontium-89 and 90 sample analysis done on a quarterly composite.

TABLE 17 (Page 2 of 3)

VIRGINIA POWER - SURRY - 1987 CONCENTRATIONS OF STRONT)UM~89 AND -90 AND GAMMA EMITTERS** IN MILK pCi/l t 2 sigma MONTH NUCLIDE LEE HALL* EPPS* CP WMS JDKS MAY Sr-89 Sr-90 K-40 1030 t 100 1270 t 130 1270 t 130 1300 t 130 1270 t 130 Cs-137 <6 <4 5.22 t 2.04 <4 <5 1-131 <0.3 <0.3 <0.2 <0.4 <0.3 O'\

JUNE Sr-89

~ Sr-90 K-40 1290 t 130 1390 t 140 1450 t 140 1310 t 130 1410 t 140 Cs-137 <4 5.84 t 3.04 <5 <6 7.12 t 3.29 1-131 <0.5 <0.5 <0.3 <0.3 <0.3 JULY Sr-89 <3 <3 <3 Sr-90 1. 4 t 0.5 1. 2 t 0.5 2.3 t 0.5 K-40 1270 t 130 1030 t 100 1090 t 110 1220 t 120 1310 t 130 Cs-137 <8 9.84 t 5.64 <8 <6 <6 1-131 <O. 3 <0.4 <0.2 <0.4 <0.3 AUGUST Sr-89 Sr-90 K-40 1490 t 150 1080 t 110 1220 t 120 1340 t 130 1320 t 130 Cs-137 <5 <7 <7 <4 <6 1-131 <0.3 <0.3 <0.5 <0.4 <0.5

State split

- All other gamma emitters were LLD.

TABLE 17 (Page 3 of 3)

VIRGINIA POWER - SURRY - 1987 CONCENTRATIONS OF STRONTIUM-89 AND -90 AND GAMMA EMITTERS** IN MILK pCi/£ :I: 2 sigma MONTH NUCLIDE LEE HALL* EPPS* CP WMS JDKS SEPTEMBER Sr-89 Sr-90 K-40 1370 :1: 140 1290 :I: 130 1430 :1: 140 1370 :1: 140 1240 :1: 120 Cs-137 <7 <4 <6 <4 <7 1-131 <0.2 <0.2 . <O. 2 <0.3 . <O. 4 0) u, OCTOBER Sr-89 <2 <2 <3 Sr-90 1. 5 :I: 0.6 0. 67 :I: 0.39 4. 2 :I: 0.6 K-40 1350 :I: 140 1370 :1: 140 1330 :I: 130 1320 :1: 130 1270 :1: 130 Cs-137 <4 <5 <6 <5 <5 1-131 <0.2 <O. 4 <0.3 <0.2 <0.2 NOVEMBER Sr-89 Sr-90 K-40 1350 :I: 130 1000 :I: 100 1460 :1: 150 1180 :1: 120 13~0 :1: 130 Cs-137 <4 <7 <4 <4 <5 1-131 <0.3 <0.2 <0.2 <0.3 <0.2 DECEMBER Sr-89 Sr-90 K-40 1250 :I: 130 1410 :1: 140 1450 :I: 140 1160 :1: 120 1150 :I: 110 Cs-137 <6 <3 <4 <7 <4 1-131 <0.3 <0.3 <0.3 <0.2 <0.3

State split

- All other gamma emitters were LLD.

2. Aquatic Biota Marine biota can be sensitive indicators of radionuclide accumulation 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. Ac;.

expected, naturally occurring potassium-40 was the nuclide most frequently detected.

For the clam samples the average potassium-40 activity was 617 pCi/kg.

(wet weight) and a range from 154 to 1710 pCi/kg (wet weight). Cobalt-60 was measured in three samples from Surry Discharge with an average activity of 65.1 pCi/kg (wet weight) and a range of 38.2 to 106 pCi/kg (wet weight).

Cobalt-60 was also measured in two of the six samples from Hog Island Point with an average activity of 46.3 pCi/kg (wet weight) and a range of 35.4 to 57.1 pCi/kg (wet weight). The activity measured in the 1985 and 1986 clam samples taken at the same locations is comparable with the 1987 results.

Cesium-137 was also measured in five samples. Three indicator locations averaged 20.1 pCi/kg (wet weight) with a range of 14.7 to 27.0 pCi/kg (wet weight). These positive results were well below the required lower level of detection (LLD) and compared well to samples taken in recent years.

Cesium-137 was not detected in any of the other samples from the indicator locations.

One sample from the clam control location measured cesium-137 activity of 138 pCi/kg (wet weight). No other gamma emitting isotopes, attributable to plant discharges, were detected in this or any other samples. All other samples showed no cesium-137 activity when analyzed to levels well below the required LLDs listed in Table 2. With the exception of the unexpected high 66

result from the 09/21/87 sample, the control location compared well with results from previous years.

For oyster samples the average potassium-40 activity for 15 of the 18 samples was 716 pCi/kg (wet weight) with a range of 215 to 1470 pCi/kg (wet weight). All other gamma emitters were well below the required LLDs listed in Table 2.

During July, August, and September, crabs were collected from the Surry Discharge (SD) location and analyzed by gamma spectrometry. Naturally occurring potassium-40 was observed in all three samples, with an average activity of 2057 pCi/kg (wet weight) and a range of 1740 to 2330 pCi/kg (wet weight) as presented in Table 21. All other gamma emitters were well below tt the LLDs required in Table 2.

Six fish samples (catfish and white perch) were collected during January, February, August and November from the same Surry Discharge location (SD). Potassium-40 was measured in all six samples with an average activity of 1552 pCi/kg (wet weight) and a range of 1240 to 1980 pCi/kg (wet weight).

The results of gamma spectrometry on these samples are presented in Table

23. Cesium-137 was observed in four of the fish samples with an average activity of 24 pCi/kg (wet weight) and a range of 15.3 to 31.0 pCi/kg (wet weight); The results from the 1987 fish samples indicated lower cesium-137.

activity in comparison to results from recent years. The 1986 samples averaged 45.5 pCi/kg (wet weight) and 1985 samples averaged 87.1 pCi/kg (wet weight).

67

Co-58 IN CLAM SAMPLES*

1000 I*

\

O'l 100

\,

,/

/. -~

' -" II A

X X X X X

\.

co ~ 7 If

~

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X

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X

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10

....... 1974

. . . . . . . . II . . I I

1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 *

-e- Chickahominy

-+- Surry Discharge X=LLD

-a- Hog Island

Co-60 IN CLAM SAMPLES 1000

\

100

,,\" " .-

I

)

A I X X X X X

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I I

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\

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...., /

x~ ~

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. ~ V ~~

~~

', ~ x~~

X X 10 . . . . . . II I

I

19.74 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987

-e- Chickahominy

-+- Surry Discharge X=LLD . Hog Island ,

. CS-137 IN CLAM SAMPLES 1000

~

~ ,.

8 K :/ ~

C) 5}

s 100 I \

~

\.

~

uQ. ' '

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-e- Chickahominy 0 - . . . . . . .

1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987

-+- Surry Discharge

-a- Hog Island X=LLD

- TABLE 18 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1987 ANALYSIS AND LOWER LIMIT NUMBER OF 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 Clams Gamma Spec 30 (pCi/kg wet) K-40 616(19/24) SD 801(6/6) 617(6/6) 0

( 154-1710) (375-1710) (200-1120)

Co-60 130 57.6(5/24~ SD 65.1(3/6) -(0/6) 0 (35.4-106 ( 38. 2-106)

--.,I Cs-137 150 20.1(4/24~ CHIC 138(1/6) 138(1/6) 0 I-' (14.7-138 Oysters Ganma Spec 18 (pCi/kg wet) K-40 716(15/18) NN 836(6/6) NONE 0 (215-1470) (215-1470)

Crabs Gamma Spec 3 2057(3/3) SD 2057(3/3) NONE 0

( pC.i /kg wet) K-40 (1740-2330) (1740-2330)

(1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Progrill1, Revision 1, November 1979.

VIRGINIA PO

.19 SURRY - 1987 CONCENTRATIONS OF GAMMA EMITTERS* CLAMS pCi/kg (wet) +/- 2 Sigma SAMPLE STATION DATE TYPE Be-7 K-40 Co-58 Co-60 Cs-137 Ra-226 Th-228 CHIC 01/14/87 Clams <200 328 +/- 160 <20 <30 (20 <400 <40 04/01/87 Clams <200 1110 +/- 240 <30 <20 <20 <500 <50 05/19/87 Clams <100 200 +/- 60 <10 <9 <10 <200 <20 07/15/87 Clams <300 1120 +/- 230 <30 <20 <30 <400 <50 09/21/87 Clams <100 346 +/- 121 <10 <10 138 +/- 17 (c) <300 <30 11/17/87 Clams <100 596 +/- 151 <10 <10 <10 <200 <20 JMTN 01/14/87 Clams <200 379 +/- 161 <20 <30 <20 <400 <40 04/01/87 Clams <100 375 +/- 132 <10 <10 <10 <300 <30 05/19/87 Clams <200 418 +/- 135 <20 <20 <20 <300 <30 07/15/87 Clams <200 826 +/- 180 <20 <20 <20 <400 <20 09/17/87 Clams <200 414 +/- 150 <2 0 <20 <30 <300 <30 11/17/87 Clams <300 <700 <30 <20 <20 <400 <40

-....J N

SD 01/14/87**( a) Clams <100 375 +/- 104 <20 106 +/- 16 15.4 +/- 8.4 <300 <20 03/19/87** Clams <300 1710 +/- 240 <30 51.2 +/- 15.2 <30 <400 <50 05/04/87** Clams <200 400 +/- 87 <20 38.2 +/- 11.1 14.7 +/- 6.4 <300 <20 07/06/87** Clams <200 514 +/- 253 <30 <30 <30 <400 <40 08/27/87**(b) Clams <100 797 +/- 137 <20 <2 0 <10 <300 <30 11/09/87** Clams <100 1010 +/- 160 <10 <20 <20 <300 <30 HIP 01/.14/87 Clams <200 375 +/- 121 <20 57.1 +/- 16.4 23.4 +/- 8.8 <300 <30 03/26/87 Clams <200 257 +/- 114 <20 35.4 +/- 14.5 <20 <300 <30 05/19/87 Clams <200 <500 <30 <20 <20 <400 <40 07/15/87 Clams <300 901 +/- 217 <30 <30 <30 <500 (50 09/17/87 Clams <200 <600 <30 <20 <20 <400 <40 11/13/87 Clams <300 <700 <30 <30 <20 <400 <40 LC 01/14/87 Clams <200 619 +/- 185 <30 <20 <20 <400 <40 03/26/87 Clams <200 758 +/- 216 <20 <20 <30 <400 <30 05/14/87 Clams <200 154 +/- 79 <20 <20 27.0 +/- 13. 6 <300 <30 07 /15/87 Clams <100 795 +/- 152 <10 <2 0 <10 <400 <50 09/17/87 Clams <200 <300 <20 <2 0 <20 <300 <30 11/13/87 C.l ams <100 636 +/- 123 <10 <10 <10 <200 <20

All other gamma emitters were <LLD.

- State Split Ag-llOM = 44.1 +/- 9.5 f i} A~-llOM 67.2 +/- 14.3 T is data for this sample date has been excluded from the trend graph.

TABLE 20 VIRGINIA POWER - SURRY - 19B7 CONCENTRATIONS OF GAMMA EMITTERS* OYSTERS pCi/kg (wet) +/- 2 Sigma SAMPLE STATION DATE TYPE Be-7 K-40 Co-58 Co-60 Cs-137 Ra-226 Th-228 NN 01/14/87** Oysters <200 785 +/- 158 <20 <30 <20 <400 <40 03/18/87** Oysters <200 734 +/- 158 <20 <20 <20 <300 <30 05/05/87** Oysters <200 215 +/- 89 <20 <20 <20 <300 <30 07/07/87** Oysters <200 843 +/- 160 <20 <20 <20 <300 <30 08/31/87** Oysters <200 1470 +/- 220 <10 <10 <20 <300 <20 11/04/87** Oysters <100 969 +/- 158 <20 <10 <20 <400 <30 ows 01/14/87 Oysters <200 561 +/- 150 <20 <10 <10 <300 <30 03/2 6/8 7 Oysters <200 533 +/- 184 <20 <20 <20 <300 <30 w

05/14/87 Oysters <200 584 +/- 143 <20 <20 <20 <400 <40

<30 07/15/87 Oysters <100 630 +/- 185 <20 <10 <10 <300 09/17/87 Oysters <200 <500 <20 <20 <20 <300 <30 11/13/87 Oysters <200 389 +/- 137 <20 <20 <20 <300 <30 POS 01/14/87 Oysters <200 553 +/- 139 <20 <10 <20 <400 <40 03/26/87 Oysters <300 1000 +/- 230 <30 <30 <30 <400 <50 05/14/87 Oysters <300 <600 <30 <20 <20 <300 <40 07/15/87 Oysters <200 712 +/- 237 <30 <20 <30 <600 <50 09/17/87 Oysters <300 <700 <30 <20 <30 <300 <40 11/13/87 Oysters <200, 766 +/- 132 <20 <10 <10 <200 <20

All other gamma emitters were <LLD.

- State Split

TABLE 21 VIRGINIA POWER - SURRY - 1987 CONCENTRATIONS OF GAMMA EMITTERS* IN CRABS pCi/kg (wet) t 2 Sigma SAMPLE STAT ION DATE TYPE Be-7 K-40 Co-58 Co-60 Cs-137 Ra-226 Th-228 SD 07/15/87 Crabs <200 2100 t 250 <20 <20 <20 <400 <30 SD 08/03/87 Crabs <200 1740 t 190 <20 <10 <10 <300 <30 SD 09/15/87 Crabs <200 2330 t 230 <20 <20 <20 <300 <30

+:>

Average t 2057 t 595 2 s. d.

All other gamma emitters were <LLD

TABLE 22 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1987 ANALYSIS AND LOWER LIMIT NUMBER OF 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 Fi sh Gamma Spec 6

( pCi /kg wet)

K-40 6 1552(6/6) SD 1552( 6/6) NONE 0 (1240-1980) (1240-1980)

U1 Cs-137 6 150 24.0~4/6) SD 24.0~4/6) NONE 0 (15. -31.0) (15. -31.0)

(l)' LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Progrc111, Revision l, November 1979.

J

TABLE 23 VIRGINIA POWER - SURRY - 1987 CONCENTRATIONS OF GAMMA* EMITTERS IN FISH pCi/}g (wet) +/- 2 sigma COLLECTION SAMPLE DATE STATION TYPE K-40 Co-58 Cs-134 Cs-137 01/21/87 SD WHITE PERCH 1320 +/- 130 <7 <7 30.9 +/- 6.9 02/13/87 SD CATFISH 1240 +/- 120 <9 <10 18.6 +/- 7.0 08/24/87 SD WHITE PERCH 1770 +/- 210 <20 <20 31.0 +/- 13.9

-...J <20 O'I 08/28/87 SD CATFISH 1980 +/- 220 <20 <20 11/17/87 SD CATFISH 1650 +/- 160 <8 <8 15.3 +/- 6.0 11/17/87 SD WHITE PERCH 1350 +/- 210 <20 <10 <20 Average+/- 1552 +/- 588 24.0 +/- 16.4 2 S.D.

All other gamma emitters were below <LLD.

i

3. Food Products Ten food samples were collected from six 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 7233 pCi/kg (wet weight) and a range of 3130 to 15200 pCi/kg (wet weight). Cosmogenic beryllium-? was measured in one sample from Carter's garden and one from Turner's garden.

The average activity was 295 pCi/kg (wet weight) and a range of 225 to 365 pCi/kg (wet weight). Cesium-137 was measured in four samples with an average activity of 21.9 pCi/kg (wet weight) and a range of 8.15 to 34.7 pCi/kg (wet weight). These results are comparable with previous years. All

~ other gamma emitters were below detection limits.

77

TABLE 24 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1987 ANALYSIS AND lOWER LIMIT NUMBER OF 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 Garruna Spec 10 (pCi/kg wet) K-40 7233(10/10) Slade's 9370(3/3) NONE 0 (3130-15200) (3490-15200)

Be-7 10 295(2/10~ Turner's 365(1/1) NONE 0 (225-365

-...J CX)

Cs-137 10 80 21. 9( 4/10) Carter's 25.9(1/1) NONE 0 (8.15-34. 7)

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

25 VIRGINIA POWER - SURRY - 1987 CONCENTRATIONS OF GAMMA* EMITTERS IN VEGETATION pCi/kg (wet) +/- 2 sigma SAMPLE COLLECTION STAT ION TYPE DATE Be-7 K-40 1-131 Cs-134 Cs-137 Poole's Garden Kale 06/09/87 <100 6330 +/- 630 <30 <10 <10 Ryan's Garden Cauliflower 06/09/87 <90 4200 +/- 420 <20 <10 <10 Carter's Garden Cabbage 06/09/8 7 225 +/- 107 3260 +/- 330 <60 <10 25.9 +/- 10.4 Turner's Garden Cabbage 07/19/87 365 +/- 91 4510 +/- 450 <50 <10 <10

-....J Slade's Garden Peanuts 10/27/87 <300 9420 +/- 940 <40 <30 34.7 +/- 18.8

\.0 l,

Brocks Garden** Peanuts 10/27/87 <200 7590 +/- 760 <30 <20 <20 Brock's Garden Corn 10/27/87 <BO 3130 +/- 310 <20 <8 18.7 +/- 7. 7 Slade's Garden ** Corn 10/27/87 <40 3490 +/- 350 <7 <5 8.15 +/- 4.25 Brock's Garden Soybeans 12/02/87 <100 15200 +/- 1500 <20 <10 <10 Slade's Garden Soybeans 12/02/87 <60 15200 +/- 1500 <10 <B <9 Average+/- 295 +/- 198 7233 +/- 9331 21. 9 +/- 22.5 2 s. d.

A11 other gamma emitters were <LLD.

- State Split

E. DIRECT RADIATION EXPOSURE PATHWAY

1. TLD Dosimeters Thermoluminescent dosimeters (TLDs) determined environmental radiation dose rates and the results are presented in Tables 27 and 28 .. Two sets of TLD badges of four readout areas each were deployed quarterly at each location. The mean values of four readings from each badge (calibrated individually for response to a known dose and for intransit exposure) are reported in this table, unless indicated otherwise.

Table 26 provides a statistical summary of the four quarters 1987 data.

Individual measurements of external radiation levels in the environs of the Surry site for stations 02 through 43 had an average dose of 6.5 mR/standard month The average dose for the control stations (39,40) was 5.8 mR/standard month with a range of 4.8 to 7.2 mR/standard month. The indicator locat1ons had an average activity of 6.6 mR/standard month with a range of 3.8 to 10.6 mR/standard month. A trend graph is provided by average readings of TLDs located at the site boundary to those located at approximately five miles from the station.

80

DIRECT RAD/A TION MEASUREMENT-TLD RESULTS 100 00 10 . A I )\ A I-'

1\1 _.m. I I \

, II" ' ,--..., """"~,

" I P.l-1. ..-

\ lliil ... -

., 1, -

l y 111 -

\\

\}

rJ 'll-l' \

\./"\\

- ~ I y 1 .

-a- Site Boundary 1980 1981 1982 1983 1984 1985 1986 1987 1988

-+- 5 Mile J

TABLE 26 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1987 ANALYSIS AND LOWER LIMIT NIJtlBER OF 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 Direct Radiation Ga11111a 333 2 TLD' s (mr/std. month) 6.6(317/317) 38 8.0(8/8) 5.8(16/16) 0 (3.8-10.6) (7.2-9.3) (4.8-7.2)

OJ N

(P,-o: 2) 7 VIRGINIA POWER - SURRY - 1987 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS mR/month +/- 2 Sigma - Set 1 - 098 STATION AVERAGE NUMBER FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER +/- 2 s. d.

02 8.9 +/- 1. 2 7.2 +/- 0.8 7.5 +/- 0.3 7.4 +/- 0.6 7.8 +/- 1. 6 03 5.0 +/- 0.6 4.0 +/- 0.2 4.6 +/- 0.1 3.8 +/- 0.3 4.4 +/- 1. 1 04 6.9 +/- 0.7 6.4 +/- 0.4 7. 1 +/- 0.7 6.6 +/- 0.3 6.8 +/- 0.6 05 7.2 +/- 2.5 6. 1 +/- 0.9 7. 2 +/- 0.3 6.5 +/- 0.6 6.8 +/- 1.1 06 7.5 +/- 1. 1 6.4 +/- 1. 0 7.9 +/- 0.5 6.4 +/- 0.7 7. 1 +/- l. 5 07 7.6 +/- 0.9 6.4 +/- 0.3 7.3 +/- 0.2 6.3 +/- 0.8 6.9 +/- l. 3 08 9.6 +/- 1. 2 6.0 +/- 0.6 7. 1 +/- 0.3 6.6 +/- 0.8 7.3 +/- 3.2 09 7. 1 +/- 0.8 6.0 +/- 0.6 7.3 +/- 0.5 5.9 +/- 0.7 6.6 +/- 1. 5 co w 10 7.0 +/- 1. 3 5.8 +/- 0.3 6.8 +/- 0.9 5.8 +/- 0.7 6.4 +/- 1. 3 11 7.7 +/- 1. 5 6.4 +/- 0.7 7.4 +/- 0.5 6.8 +/- 1. 6 7. 1 +/- l. 2 12 .6. 7 +/- 0.9 6.3 +/- 0.4 7. 7 +/- 0.6 6.3 +/- 0.6 6.8 +/- 1. 3 13 8'.3 +/- 0.9 6. 1 +/- 0.6 7.3 +/- 0.5 6.5 +/- 0.4 7. 1 +/- 1. 9 14 8.2 +/- 1. 0 6. 1 +/- 1.1 7. 1 +/- 0.5 6.6 +/- 0.6 7.0 +/- 1. 8 15 10.6 +/- 1.1 6.1 +/- 0.2 6.6 +/- 0.6 5.9 +/- 0.7 7.3 +/- 4.4 16 8.3 +/- l. 5 6.4 +/- 0.4 6.9 +/- 0.6 5.0 +/- 1. 3 6. 7 +/- 2.7 17 6.6 +/- 1. 0

5. 6 +/- 0.4 6.4 +/- 0.5 5.8 +/- 0.3 6. 1 +/- l. 0 18 6. 7 +/- 0.9 5.0 +/- 0.4 6.0 +/- 0.9 4.6 +/- 0.5 5.6 +/- 1. 9 19 6.4 +/- 0.9 5.5 +/- l. 0 6. 1 +/- 0.4 5.5 +/- 0.6 5.9 +/- 0.9 20 7;8 +/- l. 2 5.3 +/- 0.6 5.9 +/- 0.5 5.4 +/- 0.4 6. 1 +/- 2.3 21 6.6 +/- 0.8 6.1 +/- 0.2 7.2 +/- 4.5 5.2 +/- 0.7 6.3 +/- 1. 7 22 6.1 +/- l. 2 5.6 +/- 0.2 6.2 +/- 0.5 5.0 +/- 0.3 5. 7 +/- 1.1

of 2)

VIRGINIA POW URRY - 1987 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS mR/month +/- 2 Sigma - Set 1 - 098 STATION AVERAGE NUMBER FIRST QUARTER SECOND QUARTER TH !RD QUARTER FOURTH QUARTER +/- 2 s. d.

23 6. 5 +/- o.. 9 (a) 7.0 +/- 0.6 6.2 +/- 0.7 6.6 +/- 0.8 24 8.3 +/- 0. 7 5.8 +/- 0. 1 6. 7 +/- 0.3 5. 3 +/- 0.7 6. 5 +/- 2.6 25 7. 2 +/- 1. 3 6.3 +/- 1. 0 7.0 +/- 0.9 6.4 +/- 0.8 6. 7 +/- 0.9 26 8.4 +/- 1. 6 6.0 +/- 0.7 6.9 +/- 0.1 (a) 7. 1 +/- 2.4 27 6.2 +/- 1. 2 5.3 +/- 0.2 6.2 +/- 0. 1 5.5 +/- 0.5 5.8 +/- 0.9 28 7.5 +/- 1. 0 6.2 +/- 0.6 6. 3 +/- 0.3 5.9 +/- 0. 3 6. 5 :I: 1. 4 29 6. 5 +/- 0.3 5. 1 +/- 1. 3 5.9 +/- 0.3 5.4 +/- 0.2 5. 7 +/- 1. 2 30 6.6 +/- 0.8 5.6 +/- 0.2 6. 2 +/- 0.7 5. 7 +/- 0.5 6.0 +/- 0.9 31 6.5 +/- 0.5 5. 1 +/- 0.9 5. 9 +/- 0.6 5. 0 :I: 0.6 5.6 +/- 1. 4 32 8.6 +/- 1. 0 5. 7 +/- 0.4 6.5 +/- 0.3 5. 7 +/- 0.2 6.6 +/- 2.7 33 6.9 +/- 0.2 6.2 +/- 0.6 6.6 +/- 0.6 6.0 +/- 0.7 6.4 +/- 0.8 CX>

~ 34 7.9 +/- 1. 2 6.2 +/- 0.7 6. 7 +/- 0.5 5.8 +/- 0.4 6.7 +/- 1. 8 35 7.6 +/- 1. 2 7. 5 +/- 0.7 7. 7 +/- 0.7 6.9 +/- 0.4 7.4 +/- 0.7 36 8.6 +/- 1. 5 6. 7 +/- 0.8 8.0 +/- 0.9 7.0 +/- 0.6 7.6 +/- 1. 8 37 7. 1 +/- 1. 6 21. 8 +/- 13.4 ( b) 6. 7 +/- 0.4 5.8 +/- 0.6 6.5 +/- 1. 3 38 9.3 +/- 1. 4 7.9 +/- 0.7 8.4 +/- 0.7 7.6 +/- 0.7 8. 3 :I: 1. 5 39 7. 2 +/- 0.7 6. 1 +/- 0.6 6.3 +/- 0.8 5 .. 9 +/- 0.3 6.4 +/- 1. 1 40 6.4 +/- 1. 0 4.9 +/- 0.4 5.2 +/- 0.2 4.8 +/- 0.9 5.3 +/- 1. 5 41 6.8 +/- 0.9 6.2 +/- 0.6 6.0 +/- 0.5 6.2 +/- 0.5 6. 3 +/- 0.7 42 7. 1 +/- 0.7 6. 2 +/- 0.2 6.5 +/- 0.8 5.8 +/- 0.3 6.4 +/- 1. 1 43 6. 3 +/- 0.7 5. 6 +/- 0.5 6.3 +/- 0.5 5. 3 +/- 0.4 5.9 +/- 1. 0 Average 7.4 +/- 2.1 6.0 +/- 1.4 6. 7 +/- 1. 5 5.9 +/- 1. 5 6. 5 +/- 1. 4

+/- 2 s. d.

(a) TLD Vandalized (b) TLD found missing; replaced 06/09/87. The replacement TLDs for the period 06/09/87 through 07/01/87 appeared to have received a non-uniform dose concentrated in area 4 in particular and to a lesser extent in area 3. The possible cause of the non-uniform dose may be due to station security x-ray. The data for sta-37, for this time period was not included in the averages.

VIRGINIA POWER E 28 (Page 1 of 2)

DIRECT RADIATION MEA~UREMENTS SURRY

- 1987 QUARTERLY TLD RESULTS mR/month +/- 2 Sigma - Set 2 - 099 STAT ION AVERAGE NUMBER FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER +/- 2 s .d.

02 7.8 +/- 0.8 8. 5 +/- 1. 9 8. 1 +/- 0.8 7.4 +/- 0.4 8.0 +/- 0.9 03 5. 7 +/- 1.1 4. 1 +/- 0.4 4.4 +/- 0.2 4. 1 +/- 0.2 4.6 +/- 1. 5 04 7.2 +/- 1. 1 6.8 +/- 0.4 7.0 +/- 0.5 6.3 +/- 0.6 6.8 +/- 0.8 05 9.3 +/- 0.8 6.3 +/- 1. 3 6.9 +/- 0.6 6.1 +/- 0.2 7. 2 +/- 2.9 06 9.3 +/- 1. 7 6.8 +/- 1.1 7.3 +/- 0.7 T:3 +/- 0.5 7.7 +/- 2.2 07 7.0 +/- 1. 8 6.3 +/- 0.9 7.0 +/- 1. 0 6.5 +/- 0.7 6.7 +/- 0.7 08 7.7 +/- 1. 2 6.5 +/- 0.8 7.2 +/- 0.5 6.7 +/- 0.2 7.0 +/- 1.1 co 09 8.5 +/- 0.9 6.3 +/- 0.3 6.7 +/- 0.3 6.4 +/- 0.3 7.0 +/- 2 .1

(.Tl 10 7.6 +/- 1. 8 6.4 +/- 0.2 6.4 +/- 0.6 6.2 +/- 0.7 6.7 +/- 1. 3 11 7.9 +/- 0.6 6.3 +/- 1. 0 6.9 +/- 0.4 6.4 +/- 1. 1 6.9 +/- 1. 5 12 10.l +/- 1. 5 6.7 +/- 0.4 7.0 +/- 0.6 6.6 t 0.8 7.6 t 3.4 13 8.0 t 1.6 6.4 +/- 0.7 7. 2 t 0.6 6.4 t 0.3 7.0 +/- 1. 5 14 8.3 +/- 1. 3 6.9 t 0.7 6.7 t 0.6 6.6 t 0.4 7. 1 +/- 1. 6 15 7.2 +/- 0.9 6.3 +/- 1. 0 6.9 +/- 0.6 6.2 +/- 0.7 6.7 t 1. 0 16 7.5 +/- 1. 2 6.6 t 0.5 6.6 +/- 0.4 6.4 t 0.4 6.8 +/- 1.0 17 6.8 +/- 1. 3 5.8 +/- 0.8 6.6 +/- 0.5 5.6 t 0.4 6.2 t 1. 2 18 6.0 +/- 1. 6 5.3 +/- 0.3 5.6 t 0.5 5.3 t 0.7 5.6 +/- 0.7 19 7. 4 +/- 1. 0 5.7 +/- 0.3 6.0 +/- 1*0. 6 5.6 +/- 0.6 6.2 +/- 1. 7 20 7. 1 +/- 0.9 5.4 +/- 0.6 5. 7 +/- 0.4 5. 7 +/- 0.4 6.0 +/- 1. 5 21 6.0 +/- 1. 2 6.0 +/- 0.3 8.5 +/- 4.8 5.8 +/- 0.5 6.6 +/- 2.6 22 6.8 +/- 0.2 5.6 +/- 0.3 5.8 +/- 0.4 5.7 +/- 0.7 6.0 +/- 1.1

2)

VIRGINIA POW URRY - 1987 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS mR/month +/- 2 Sigma - Set 2 - 099 STATION AVERAGE NUMBER FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER +/- 2 s .d.

23 6.3 +/- 0.9 (a) 6.6 +/- 0.3 6.6 +/- 0.5 6.5 +/- 0.3 24 7.5 +/- 0.8 6.3 +/- 1. 0 6. 3 +/- 0.6 6. 1 +/- 0.5 6.6 +/- 1. 3 25 6.9 +/- 0.6 6.0 +/- 1. 3 6. 7 +/- 0.6 6.3 +/- 0.3 6.5 +/- 0.8 26 6.6 +/- 0.8 6.0 +/- 0.4 5.9 +/- 0.6 5. 5 +/- 0.6 6.0 +/- 0.9 27 6. 7 +/- 1. 1 5. 4 +/- 0.5 5. 5 +/- 0.4 5. 1 +/- 0.4 5.7 +/- 1. 4 28 6.6 +/- 0.6 6.5 +/- 1. 4 5.8 +/- 0.3 6.3 +/- 1. 1 6.3 +/- 0.7 29 8.7 +/- 1. 1 5. 7 +/- 0.3 5. 7 +/- 0.4 5. 1 +/- 0.3 6.3 +/- 3.2 30 7. 5 +/- 0.5 5.6 +/- 0.4 5.9 +/- 0.4 5. 7 +/- 0.2 6.2 +/- 1. 8 31 5.6 +/- 0.9 5.6 +/- 0.2 5.6 +/- 0.3 5.6 +/- 0.6 5.6 +/- 0.0 32 6. 7 +/- 0.9 6.0 +/- 0.6 6.3 +/- 0.3 5.6 +/- 0.4 6.2 +/- o.~

33 7.4 +/- 0.6 5.9 +/- 0.8 6.6 +/- 0.5 6.4 +/- 0.3 6.6 +/- 1. 2 CX>

O'l 34 6.4 +/- 0.5 6.2 +/- 0.8 6.4 +/- 0.2 6.2 +/- 0.3 6.3 +/- 0.2 35 8.0 +/- 0.5 7.3 +/- 0.4 7. 1 +/- 0.2 6.8 +/- 0.5 7.3 +/- 1. 0 36 7.8 +/- 0.9 7. 1 +/- 0.3 7.6 +/- 0.6 7.4 +/- 1. 0 7. 5 +/- 0.6 37 6. 1 +/- 0.6 8.7 +/- 11. 0 ( b) 6.2 +/- 0.5 6. 1 +/- 0.4 6. 1 +/- 0.1 38 7.2 +/- 2.9 7.8 +/- 0.8 8.2 +/- 0.8 7.6 +/- 0.5 7.7 +/- 0.8 39 6.5 +/- 1. 0 6.0 +/- 0.7 6. 7 +/- 0.5 6. 1 +/- 0.3 6. 3 +/- 0.7 40 5. 7 +/- 0.6 5.0 +/- 0.3 5.3 +/- 0.2 4.8 +/- 0.3 5.2 +/- 0.8 41 6.7 +/- 0.7 6.5 +/- 0.4 6.9 +/- 0.6 6.0 +/- 0.5 6.5 +/- 0.8 42 5.9 +/- 1. 0 6.0 +/- 0.7 6.3 +/- 0.6 5.8 +/- 0.4 6.0 +/- 0.4 43 7. 1 +/- 0.9 5.6 +/- 1.1 6.2 +/- 0.6 5. 2 +/- 0.4 6.0 +/- 1. 7 Average 7. 2 +/- 2.0 6. 2 +/- 1. 5 6. 5 +/- 1. 6 6. 1 +/- 1. 4 6.5 +/- 1. 0

+/- 2 s. d.

(a) TLD vandalized

{b) TLD found missing; replaced 06/09/87. The replacement TLDs for the period 06/09/87 through 07/01/87 appeared to have received a non-uniform dose concentrated in area 4 in particular and to a lesser extent in area 3. The possible cause of the non-uniform dose may be due to station security x-ray. The data for sta-37, for this time period was not included in the averages.

V. CONCLUSIONS 87

V. CONCLUSIONS The results of the 1987 Radiological Environmental Monitoring Program for Surry Nuclear Power Station have been presented. The results were as expected for normal environmental samples. Naturally occurring radioactivity 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 "As Low as is Reasonably Achievable." Specific examples of sample media with positive analysis results are discussed below.

Air particulate gross beta concentrations of all the indicator locations for 1987 appear to follow the gross beta concentrations at the control location. The gross beta concentrations were comparable to levels observed since 1982 except for a five week period in 1986 which was influenced by the Chernobyl accident. Gamma isotopic analysis of the particulate samples identified the gamma emitting isotopes as natural products {beryllium-? and potassium-40). No man-made activity was found in the particulate media during 1987. No iodine-131 was detected in charcoal

~ filters in 1987.

88

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 550 pCi/£. The concentration of tritium in the discharge sample was 1.8% of the reporting level concentration for non-drinking water. The discharge water is further diluted when mixed with the river water. No gamma emitters were detected.

Four of the sixteen well water samples for 1987 had measureable concentrations of tritium at normal environmental levels. The sensitivity of the tritium analysis of well 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 1987 to

~ previous data. Also, there is no preoperational data to compare with for well water tritium. The average tritium concentrations in well water are comparable to average concentrations found in the river water control location. (290 pCi/£ vs 263 pCi£). These concentrations are 1.5% of the reporting level concentrations for drinking water samples.

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 all locations.

Cobalt-58 was detected in the Surry Discharge sample and the two downstream samples. Cesium-134 was detected in all but four samples at several loca-tions upstream and downstream of the plant discharge. In addition to these isotopes, manganese-54 was detected in the samples collected at Surry Discharge.

89

The preoperational program analyzed silt samples but found no gamma emitting activity above the sensitivity of the analysis (<5000 pCi/kg). The sensitivity of the analysis of preoperational samples 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.

Iodine-131 was not measured in any of the sixty milk samples. During environmental sampling following the Chernobyl accident in 1986, cesium-137 was detected more frequently and in higher concentrations than in previous years. The sample results from 1987 found cesium-137 to be present more frequently than in milk samples prior to Chernobyl but less frequently and in lower amounts than in milk samples taken during the accident. All of the samples in which cesium-137 was detected were analyzed to levels below the required LLD. The average concentration of positive results was 10% of the Reporting Level Concentrations.

Fifteen milk samples from three indicator stations were analyzed for strontium. No strontium-89 was detected in any of the milk SclTlples.

Strontium-90 was measured in all of the fifteen samples. These values were comparable to values seen in recent years and indicates a decreasing trend from the strontium-90 activity found during the preoperational years. The -- 0,. -

activity found during those years is attributable to past atmospheric nuclear weapons testing.

Activity in clam and fish samples does present a direct dose pathway to man. Clam samples from 1987 indicate the presence of low level man-made radioactivity. This activity was determined at levels well below the

- ~ required sensitivity. Comparison of the 1987 data to 1983-1986 data and to 90

data prior to 1978, does not indicate increasing trends. Samples taken during 1978-1982 were not analyted below the required sensitivity level

(<130 pCi/kg) and therefore cannot be compared to the low level activity found in the 1983-1987 samples. Preoperational clam samples were analyzed for gross beta and potassium-40 and are not directly comparable to opera-tional data.

The average concentration of positive results from Surry Discharge clam samples in 1987 were 0.58% of the reporting level concentrations for cobalt-60 and 0.20% for cesium-137.

Cesium-137 was observed in four of the six 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 average concentration of the cesium-137 results was 0.24% of the reporting level concentration.

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 1987.

91

VI. 1987 LAND USE CENSUS RESULTS FOR SURRY POWER STATION 92

. 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 1987 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 29. 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.

93

TABLE 29

CENSUS FOR SURRY POWER STATION - 1987 NEAREST NEAREST NEAREST NEARSET SECTOR RESIDENT GARDEN cow GOAT A-(N) 4.750358° * *

B-(NNE) 1.95034° * *

C-(NE)

4.90056° *

0-(ENE) 4.90063° * *

E-(E) * * *

F-(ESE) * * *

G-(SE) * * *

H-(SSE) 4.700152° * *

J-(S) 1.600182° 1.760184° *

K-(SSW) 1.900193° 1.900193° 4.750201 °

L-(SW) 2.250220° 4.380219° 4.670215°

M-(WSW) 2.800243° 3.420258° *

N-(W) 3.200261° 4.330262° *

P-(WNW) 4.860281° * *

0-(NW) * * *

R-(NNW) 3.750339° 4.380336° 3.650337° *

None 94

FIGURE 4 RESULTS OF LAND USE CENSUS FOR SURRY POWER STATION fl LlHD USE CENSUS LOCATION MAP, YEAR /98 7 .

95

VII. SYNOPSIS OF ANALYTICAL PROCEDURES 96

VII. ANALYTICAL PROCEDURES SYNOPSIS C )

Appendix Bis a synopsis of the analytical procedures performed 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. 1, November 1979.

ANALYSIS TITLE PAGE Gross Beta and Gross Alpha of Air Particulate Samples .................... 98 Gross Beta Analysis of Water Samples ..................................... 99 An al ys i s of Samples for Tritium ......................................... 100 Water .............................................................. 100 Analysis of Samples for Iodine-131 ...................................... 101 Milk or Water ...................................................... 101 tt Gamma Spectrometry of Samples ........................................... 102 Milk and Water ..................................................... 102 Dried Solids other than Soils and Sediment ......................... 102 Fish ............................................................... 102 Soils and Sect iments ................................................ 102 Charcoal Cartridges (Air Iodine) ................................... 102 Air Particulates ..... ~ ............................................. 102 Environmental *Dosimetry ................................................. 104._

Analysis of Samples for Strontium-89 and -90 ................... -......... 105 Total Water ........................................................ 105 Milk ...................... , ........................................ 105 Soil and Sediment .................................................. 105 Organic Solids .... *....... '.......................................... 106

Air Particulates ........................................... -. ....... 106 97

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)

TWO SIGMA ERROR (pCi/m3)

LLD (pCi/m3)

=((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 (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) 98

GROSS BETA ANALYSIS OF WATER SAMPLES One liter of sample is evaporated to near dryness and the residue is trans-:

ferred to a tared, 2" diameter planchet and final evaporation to dryness takes place under heat lamps. The planchet is weig~ed and then coun~ed in a gas-flow proportional counter.

Calculation of the results, the two sigma er'ror and the lower limit of detection (LLD).

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

TWO SIGMA ERROR (pCi/l)

LLD (pCi/£)

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

=4.66 (sl/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)

99

Water ANALYSIS OF SAMPLES FOR TRITIUM 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/l:

RESULT = 3.234 TN VN(CG - 8)/(CN VS)

TWO SIGMA ERROR = 2((CG + B)~t) 1/ 23.234 TN VN/((CN Vs)(C 6-B))

12 LLD ~ 4.66 (3.234)TN VN(CG) ' t(at CN Vs) where: = tritium units of the standard 3.234 = conversion factor changing tritium units to pCi/l

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

= vollllle 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 at = counting time for the sample

100

Milk or Water ANALYSIS OF SAMPLES FOR IODINE-131 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 palladillll 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/l:

RESULT = (N/6t-B)/(2.22 EVY OF)

TWO SIGMA ERROR 1

= 2((N/6t+B)/6t) / 2(2.22 EVY DF)

LLD where:

6t N

= 4.66(8/6t) 112/(2.22 EVY DF)

= total counts from sample (counts)

= 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 I-131, corrected for self absorption effects by the formula E = Es(exp-0.0061M)/(exp=0.0061Ms)

= efficiency of the counter determined from an 1-131 standard mount

= mass of PdI 2 on the. standard mount, mg .

= mass of PdI2 on the sample mount, mg 101

GAMMA SPECTROMETRY OF SAMPLES Milk and Water 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 10o*c.

As much as po*ssible (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 data acquisition system which performs pulse height analysis .

Soils and Sediments Soils and~sediments are dried to a low temperature, less than 1oo*c. The soil or sediment is loaded fully into a tared, standard 300 cc container and weighed. The sample is then counted for a.t 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 (ass1.J11-ing no positive 1-131) uniquely from the volume of air which passed through it. In the event 1-131 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.

102

A mini-computer software program define.s 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, ha 1f 1i fe, 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-8)/(2.22 t EV F OF)

TWO SIGMA ERROR = 2(S+B) 1/ 2/(2.22 t EV F OF)

LLD = 4.66(8) 1/ 2/(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 collection to the counting date 103

ENVIRONMENTAL DOSIMETRY Teledyne Isotopes uses a CaS04:Dy thermolumin~scent dosimeter (TLD) which the company manufactures. Th1s material has a high light output, negligible thermally induced s;gnal 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 TLO is heated at a time and the measured light emission (luminescence) is recorded. The TLO 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 TLO 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+o 2+D 3+o 4)/4 TWO SIGMA ERROR= 2((D 1-D) 2+(0 2-o) 2+(D 3-D) 2+(0 4-D) 2)/3) 1/ 2

= the net mR of area 1 of the TLD, and similarly for D2 , D3, *and D4

= I 1 K/Rl - A

= the instrument reading of the field dose in area 1

= the known exposure by the Cs-137 source

= the instrument reading due to the Cs-137 dose on area 1

= average dose in mR, calculated in similar manner as above, of the transit control TLDs 104

ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 WATER Stable strontiLJTI carrier is added to 1 liter of sample and the volume is reduced by evaporation. Strontium is precipitated as Sr{N03)z 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. Yttri1111 is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttriwn 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. Yttrillll is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttri1111 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 grc111 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 f1111ing {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. Yttri1.111 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. Th~s precipitate is mounted on a nylon planchet and is covered with *an 80 mg/cm aluminum absorber for low level beta counting.

105

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. Stronti1111 is precipitated as Sr(N03)2 using flllling (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 yttrillTI ingrowth. YttrillTI 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 aft"er yttrillTI 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 yttrillTI 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 strontillTl-90 activity. Strontium-89 activity is determined by precipi-tating SrC03 from the scrnple after yttrillTI 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/vo\Jme or pCi/mass:

RESULT Sr-89 = {N/At-Bc-BA)/(2.22 V Ys DFSR-89 EsR-89) 1/2

TWO SIGMA ERROR. Sr-89 = 2((N/At+Bc+BA)/At) /(2.22 V Ys DFSR-sg ESR- 89 )

12 LLD Sr-89 = 4.66((Bc+BA)/At) ' t(2.22 V Ys DFsR-89 EsR-89)

RESULT Sr-90 = (N/At - B)/(2.22 V v1 Y2 OF IF E)

TWO SIGMA ERROR Sr-90 = 2((N/At+B)/At) 1/ 2/(2.22 V Y1 v2 OF E IF))

LLD Sr-90 = 4.66(B/At) 112 !(2.22 V Y Y IF OF E) 1 2 106

where: N At Be

=

total counts from sample (counts) counting time for sample (min)

= 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 V-90 B. = 0.016 (K) + (K) Ev/abs) (IGV-90)

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

aluminum absorber K = (N/At - Bc)V-90/(EV-90 IFV-90 DFV-90Vl)

DFV-90 = the decay factor for V-90 from the "milk" time to the mid count time EV-90 = efficiency of the counter for V-90 IFV-90 = ingrowth factor for V-90 from scavenge time to milking time IGv-go = the ingrowth factor for V-90 into the strontium mount from the "milk" time to the mid count time.

0.016 = the efficiency-of measuring SR-90 through a No. 6 absorber Ev/abs = the efficiency of counting V-90 through a No. 6 absorber B = background rate of counter (cpm)

Vl = chemical yield of yttrium V2 = chemical yield of strontit.111 OF = decay factor of yttrit.111 from the radiochemical milking time to the mid count time E = efficiency of the counter for Y-90 IF = ingrowth factor for V-90 from scavenge time to the radiochemical

, milking time 107

VIII. EPA INTERLABORATORY COMPARISON PROGRAM

108

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 radioactive isotopes prepared and at the maximum frequency, of availability. In this section trending graphs (since 1981) and the 1987 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 .

109

US EPA CROSS CHECK PROGRAM Gross Beta in Air Particulates 80

...... tJ

...... Ct L

C> 60

.I 40 I I

1 20 l----r-----,------..--..---...---~----r-----.---r-----r--~----.--....--H----1

.-------- 1981 1982 1983 1984 1985 1986 1987 1988 1:1 EPA+/- 3 sigma

Tl +/-3 sigma

US EPA CROSS CHECK PROGRAM Cs-137 in Air Particulates 60 50

rt u

I-'

a. 40 30 r I 1 I

I I

20 1:1 T/+/-3 sigma 10 0

i I 1981 1982 1983 1984 1985 1986 1987 1988

EPA+/-3 sigma

US EPA CROSS CHECK PROGRAM Sr-90 in Air Particulates 30 I-'

I-'

N

-I 10 0 1---....-----......,......------.------------.--.----r--...-----......,......-----l 1981 1982 1983 1984 1985 1986 1987 1988 1:1 EPA+/- 3 sigma

T/+/-3 sigma

US EPA CROSS CHECK PROGRAM 1-131 in Milk 80 60

....(I)

...... ~

w (..)

Q..

40 20

I 0 .....,_--TG--....,......---.-------,~------......----.---=r----.-+--.---+----......---l 1981 1982 1983 1984 1985 1986 1987 1988 1:1 EPA +/-3 sigma

T/+/-3 sigma

US EPA CROSS CHECK PROGRAM K-40 in Milk 2400 ..

2000 ..

1-1 QJ

,I.J

...... "'i

~

tJI Ej

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US EPA CROSS CHECK PROGRAM Cs-137 in Milk 80 El t,-J t,-J U1 CD

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US EPA CROSS CHECK PROGRAM Sr-89 in Milk 80 60 (1)

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US EPA CROSS CHECK PROGRAM Co-60 in Water 80 60

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US EPA CROSS CHECK PROGRAM Cs-134 in Water 80 60 I->

s; N

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N Q.

40 20 0 .__~_ ___.__........_ _ _ _ _ _ --L.1=------&...------__..-------=--i 1981 1982 1983 1984 1985 1986 1987 1988 a EPA +/-3 sigma

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1981 1982 1983 1984 1985 1986 1987 1988 a EPA +/-3 sigma

Tl+/- 3 sigma ,

US EPA INTERLABORAe:OMPARISON PROGRAM 1987 VEPCO - SURRY (Page 1 of 4)

EPA Date Tl Mailed Date EPA EPA Tl Norm Dev. ** Warning PREPARATION Results Issued Results Media Nuclide Results(a) Results(b) (Known) *** Action 11/04/86 01/09/87 02/09/87 Milk Sr-89 9.00 +/- 5.00 8. 67 +/- 0.58 -0. 11 Sr-90 0.00 +/- 1. 50 <1.33 1-131 40.00 +/- 6.00 54.33 +/- 2:88 1. 54 Cs-137 39.00 +/- 5.00 48.00 +/- 5.29 3. 12 *** ( C)

K 1565.00 +/- 78. 00 1530.00 +/- 95.39 -0. 78 01/09/87 02/24/87 06/16/87 Water Sr-89 25.00 +/- 5.00 22.66 +/- 0.58 -0.81 Sr-90 25.00 +/- 1. 50 26.00 +/- 0.00 1. 15 01/30/87 04/09/87 05/07/87 Food Sr-90 49.00 +/- 10.00 50.00 +/- 2.83 0.14 1-131 78.00 +/- 8.00 74.00 +/- 1. 41 -0. 71 Cs-137 84.00 +/- 5.00 91. 00 +/- 5.66 1. 98 K-40 980.00 +/- 49.00 984.00 +/- 6 7. 10 0.14

...... 02/06/87 03/18/8 7 04/15/8 7 Water .co-60 50.00 +/- 5.00 50.33 +/- 1. 52 0.11 N Zn-65 91. 00 +/- 5.00 108.33 +/- 2.51 6.00 *** ( d)

CT\ 0.11 Ru-106 100.00 +/- 5.00 100.33 +/- 11.15 Cs-134 59.00 +/- 5.00 62.00 +/- 5.57 1. 03 Cs-137 87.00 +/- 5.00 92.00 +/- 3.60 1. 73 02/13/87 03/13/8 7 04/15/87 Water H-3 4209.00 +/-421.00 4100.00 +/-200.00 -0.45 02/27/87 03/12/87 05/2 6/8 7 Milk 1-131 9.00 +/- 0.90 8.67 +/- 0.58 -0.64 04/03/87 04/24/87 06/02/8 7 Water 1-131 7.00 +/- 0.70 6. 67 +/- 0.58 -0.82 04/10/87 06/05/87 07/16/87 Air Filter Gr-Beta 43.00 +/- 5.00 42.00 +/- 2.64 -0.34 Sr-90 17.00 +/- 1. 50 15.66 +/- 0.58 -1. 54 Cs-137 8.00 +/- 5.00 8.00 +/- 1. 00 0.00 04/27/87 06/26/87 07/27/87 Lab Perf. Ra-226 3.90 +/- 0.60 3.80 +/- 0. 10 -0.29 Ra-228 4.00 +/- 0.60 3.86 +/- 0.25 -0.48 Gr-Beta 66.00 +/- 5.00 56.00 +/- 1. 7 3 -3.46 *** ( e)

Sr-89 19.00 +/- 5.00 16.33 +/- 0.58 -0.92 Sr-90 10.00 +/- 1. 50 9.33 +/- 0.58 -0. 77 Co-60 8.00 +/- 5.00 8.00 +/- 1. 00 0.00 Cs-134 20.00 +/- 5.00 15.33 +/- 1. 52 -1. 61 Cs-137 15.00 +/- 5.00 12.33 +/- 1. 15 -0.92 Footnotes at end of table

US EPA I NTERLABORA OMPARISON PROGRAM 1987 VEPCO - SURRY (Page 2 of 4)

EPA Date TI Mailed Date EPA EPA TI Norm Dev. ** Warning PREPARATION Results Issued Results Media Nuclide Results{ a) Results{b) (Known) *** Action 05/08/87 06/12/87 08/31/87 Water Sr-8g 41. 00 +/- 5.00 40.33 +/- 2. 31 -0.23 Sr-90 20.00 +/- 1. 50 21. 33 +/- 0.58 1. 54 05/22/88 06/19/87 07 /09/87 Water Gr-Beta 7.00 +/- 5.00 8.33 +/- 0.58 0.46 06/05/87 07/15/87 08/26/87 Water Cr-51 41. 00 +/- 5.00 <53.33 Co-60 64.00 +/- 5.00 63.00 +/- 4.36 -0.34 Zn-65 10.00 +/- 5.00 <9.67 Ru-106 75.00 +/- 5.00 72.00 i 11.79 -1. 03 Cs-134 40.00 +/- 5.00 34.66 +/- 1. 52 -1. 84 Cs-137 80.00 +/- 5.00 79.00 +/- 4.36 -0.34 06/12/87 07/10/87 07/27/87 Water H-3 2895.00 +/-357.00. 2800.00 +/-100.00 .:0.46 N

........ 06/26/87 08/13/87 10/01/87 Milk Sr-89 69.00 +/- 5.00 63.67 +/- 2.51 -1. 84 Sr-90 35.00 +/- 1. 50 39.66 +/- 1.15 5.39 *** ( f) 1-131 59.00 +/- 6.00 49.33 +/- 3.21 -2.79 ** (g)

Cs-137 74.00 +/- 5.00 77 .00 +/- 5.20 1. 03 K 1525.00 +/- 76.00 1533.33 +/- 98.15 0.19 07/24/87 08/21/87 09/11/87 Water Gr-Beta 5.00 +/- 5.00 6:33 +/- 0.58 0.46 07/31/87 09/30/87 11/09/87 Food Sr-89 20.00 +/- 5.00 18.67 +/- 1.15 -0.46 Sr-90 30.00 +/- 1. 50 31. 00 +/- 1. 00 1.15 1-131 80.00 +/- 8.00 88.00 +/- 10.58 1. 73 Cs-137 50.00 +/- 5.00 57.33 +/- 5.51 2.54 ** (h)

K 1680.00 +/- 84.00 1603.33 +/-201.08 -1. 58 08/07/87 09/02/87 11/05/87 Water 1-131 48.00 +/- 6.00 58.67 +/- 0.58 . 3. 08 *** ( i )

08/28/87 10/07/87 12/14/87 Air Filter Gr-Beta 30.00 +/- 5.00 26.33 +/- 2.89 -1. 38 Sr-90 10.00 +/- 1. 50 9.33 +/- 0.58 -0. 77 Cs-137 10.00 +/- 5.00 9.00 +/- 1. 00 -0.35 09/18/87 09/13/8 7 11/09/87 Water Gr-Alpha 4.00 +/- 5.00 2.67 +/- 0.58 -0.46 Gr-Beta 12.00 +/- 5.00 J3. 00 +/- 1. 00 0.35

US EPA INTERLABORATORY COMPARISON PROGRAM 1987 VEPCO - SURRY (Page 3 of 4)

EPA Date TI Mailed Date EPA EPA TI Norm Dev. ** Warning PREPARATION Results Issued Results Media Nuclide Results( a) Results(b) (Known) *** Action 10/09/87 11/07/87 12/14/87 Water Cr-51 70.00 :t 5.00 90.67 +/- 11. 59 7. 16 *** ( j)

Co-60 15.00 +/- 5.00 16.33 +/- 0.58 0.46 Zn-65 46.00 +/- 5.00 50.67 +/- 0.58 1. 62 Ru-106 61. 00 +/- 5.00 55.67 +/- 4.04 -1. 85 Cs-134 25.00 +/- 5.00 25.67 +/- 0.58 0.23 Cs-137 51.00 +/- 5.00 54.67 +/- 2.08 1. 27 10/16/87 11/12/87 12/14/87 Water H-3 4492.00 +/-449.20 4300.00 +/-100.00 -0.74 10/21/87 01/04/88 02/01/88 Lab Perf. Ra-226 4.80 +/- 0.72 4.77 +/- 0.15 -0.08 Ra-228 3.60 +/- 0.54 3.30 +/- 0.30 -0.96 Gr-Beta 72.00 +/- 5.00 72. 67 +/- 1. 53 -0.23 Sr-89 16.00 +/- 5.00 14.67 +/- 0.58 -0.46 I-'

Sr-90 10.00 +/- 1. 50 9.67 +/- 0.58 -0.38 N Co-60 16.00 +/- 5.00 19.32 +/- 2.52 1.15 CX> Cs-134 16.00 +/- 5.00 14.33 +/- 2.52 -0.58 Cs-137 24.00 +/- 5.00 25.00 :t 3.61 0.25 11/20/87 12/16/87 02/01/87 Water Gr-Beta 19.00 +/- 5.00 <l. 0 ( k) 12/04/87 01/12/88 02/08/88 Water I-131 26.00 +/- 6.00 26.33 +/- 1. 53 0 .10 Footnotes:

(a) Average+/- experimental sigma.

(b) Expected laboratory precision (1 sigma, 1 determination).

(c) The three results were 42, 50 and 52. The efficiency for Cs-137 ~as checked and no reason for the two high results could be ascertained. The I-131 results by gamma ray spectroscopy in the same sample were on average 1.5 standard deviations above the stated EPA result but in better agreement than the Cs-137 results. The K-40 results by gamma ray spectroscopy in the same sample was on average 0.78 standard deviation below the stated EPA result. Thus considering all three isotopes measured in this sample there doesn't appear to be a severe bias. The average Cs-137 result in the next EPA milk sample (prepared 06/26/87) was 1.03 standard deviation high, in better agreement.

(d) No reason for the high result could be determined. Previous tests showed a normalized deviation from the known of 0.58 (06/06/86) and -0.34 (10/10/86). Future results will be exam,ned for a trend in the Zn-65 results.

1 US EPA INTERLABORA~OMPARISON PROGRAM 1987 VEPCO - SURRY (Page 4 of 4)

EPA Date TI Mailed Date EPA EPA TI Norm Dev. ** Warning PREPARATION Results Issued Results Media Results(a) Results(b) (Known) *** Action Footnotes: (Cont.)

(e) The previous two EPA beta results are 6% low. and our in-house beta spikes are low by about the same percentage.

The radiochemistry manager will re-train the analysts in transferring all sample residue into the planchets.

(f) The reported high result was due to small .aliquot available for the Sr-90 analysis. Inadvertently a large aliquot was used for another analysis leaving 40% of the normal volume for Sr-90. Additionally, the narrow acceptance limits defined by EPA is particularly difficult to meet. For this analysis 63% of the participants were beyond the+/- 3 sigma limit.

( g) Teledyne Isotopes' radiochemical method for 1-131 analysis of milk (PR0-032-11) employs ion exchange resin to absorb iodide ion from the bulk sample. This approach is standard in the industry, but it is recognized that approximately 10% of radioiodine in milk is protein-bound and will not be absorbed by this method. For example, Kar-Chan To and Edward Rack (Anal.

Chem 57 (7). June 85, p 1490-92) say "Ion-exchange chromatography is generally employed to isolate 1-131 from milk. It is foundor assumed that 90% of the 1-131 exists in the iodide form."

In order to avoid the protein-bound error when processing EPA 1-131 spiked milk samples, we have sometimes in the past used a hydroxide digestion and ashing step to convert all iodine to the iodide form. We have discontinued that procedure beginning in 1987, however, because it is not identical to the method in routine use (PR0-032-11). ~e intend to continue using the regular ion exchange method for all milk samples. realizing that an error in the vicinity of 10% may occur. When milk samples contain

...... more than 20 pCi/£ 1-131, we may refer to gamma spectral analyses which do not exhibit the protein-bound error .

N I.O

( h) The Cs-137 results in EPA foods have typically been biased high. We are in the proiess of performing our annual calibrations. We are using a new Amersham mixed gamma standard rather than the most recently prepared NBS standard which is now several years old. Based on preliminary results the three Cs-137 values would be 52.1, 50.3, and 50.9 which average 51.1.

(i) Erroneously high electrode reading of stable iodide in sample (possibly because of interfering species such as divalent sulphur ion, leading to erroneously low chemical yields. After repeating the electrode reading. the calculated average 1-131 is 49.6 pCi/£. Technicians have been made aware to be suspicious of high electrode readings. When unusually high readings occur samples will be diluted and/or oxidized and remeasured.

(j) The data for the Cr-51 results were reviewed. The detector efficiencies appear to be correct. The other five isotopes measured in this sample were within two standard deviations indicating there is no systematic error. Chromium-51 is difficult to measure at this activity level because of the low branch-ing intensity of the gamma ray and being in the high background region of the spectrum since Cr-51 has a low energy gamma ray. No further corrective action is planned since there is no required Tech Spec LLD for Cr-51 and consequently no formal LLD has been established at Tl.

(k) The EPA sample was not analyzed. A newly trained technician minsinterpreted the Sample Receipt Form and proceeded to dilute and analyze instead an in-house blank of deionized water. In the future, all dilutions will be performed by the *laboratory supervisor or the laboratory manager to ensure accuracy.

IX. REFERENCES

130

IX. REFERENCES

1. United States Nuclear Regulatory Conmission, Regulatory Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants",

December, 1975.

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

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

4. United States Nuclear Regulatory Corrmission. Regulatory Guide 1.109, Rev. 1, "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, "Acceptable Radiological Environ-mental Mani tori ng Program", Rev. 1, November 1979.

131

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