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Radiological Environ Monitoring Program for 1988.
	ML18151A491
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Site:	Surry
Issue date:	12/31/1988
From:	BLOUT P F; TELEDYNE ISOTOPES MIDWEST LABORATORY
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', I ~b~-ADOCK 05000280 R PDC I I I I I ii I I I I I I I I I I VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FOR 1988 Prepared by -VIRGINIA ELECTRIC AND POWER COMPANY and TELEDYNE ISOTOPES *~-- I I I I I I I I I I -1 I I I I I I ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SURRY POWER STATION JANUARY 1, 1988 to DECEMBER 31, 1988 Prep a red by: Reviewed by: Approved by: Assistant Supervisor Health Physics Count Room/Environmental Supervisor Health Physics Technical Services Superintendent Health Physics I I I I I I I I .. I I I I I I I I SECTION I. I I. I I I. IV. V. VI. VI I. VI I I. IX. TABLE OF CONTENTS TITLE PAGE INTRODUCTION ................................................. 1 SAMPLING AND ANALYSIS PROGRAM ................................ 4 PROGRAM EXCEPTIONS .......................................... 16

SUMMARY

AND DISCUSSION OF 1988 ANALYTICAL RESULTS ........... 20 A. AIRBORNE EXPOSURE PATHWAY ............................... 21 1. Air Iodine/Particulates ............................. 21 B. WATERBORNE EXPOSURE PATHWAY ............................. 39 1. River Water ......................................... 39 2. Well Water .......................................... 50 C. AQUATIC EXPOSURE PATHWAY ................................ 54 1. Silt ................................................ 54 2. Shoreline Sediment .................................. 63 D. INGESTION EXPOSURE PATHWAY .............................. 66 1. Milk ................................................ 66 2. Aquatic Biota ....................................... 72 3. Food Products ....................................... 83 E. DIRECT RADIATION EXPOSURE PATHWAY ....................... 86 1. TLD Dosimeters ....................................... 86 CON CL US I ON .................................................. 93 1988 LAND USE CENSUS ........................................ 98 SYNOPSIS OF ANALYTICAL PROCEDURES .......................... 102 EPA INTERLABORATORY COMPARISON PROGRAM ..................... 114 REFERENCES ................................................. 133 I I I I I I I I I I I I I I I I 1. 2. 3. 4. TABLE OF CONTENTS (Cont) LIST OF FIGURES LAND BASED ENVIRONMENTAL SAMPLING LOCATIONS ................. 10 RIVER BASED ENVIRONMENTAL SAMPLING LOCATIONS ................ 11 TLD LOCATIONS ............................................... 12 LAND USE CENSUS MAP ........................................ 101 ii I I I I I I I I I I I I I I I \) FORWARD This report is submitted as required by Technical Specification 6.6.B.2, Annual Radiological Environmental Operating Report for Surry, Units 1 and 2, Virginia Electric and Power Company Docket Nos. 50-280 and 50-281. i ii I I I I I I I I I I I I I I I I I. INTRODUCTION VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The operational radiological environmental monitoring program conducted for the year 1988 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, 1988 through December 31, 1988 is summarized. A. The Surry Power Station of Virginia Electric and Power Company is located on the Gravel Neck peninsula adjacent to the James River, approximately 25 miles upstream of the Chesapeake Bay. The site consists of two units, each with pressurized water reactor (PWR) nuclear steam supply system and turbine generator furnished by Westinghouse Electric Corporation. Each unit is designed with a gross electrical output of 822.6 megawatts electric (MWe). Unit 1 achieved commercial operation on December 22, 1972, and Unit 2 on May 1, 1973. B. The United States Nuclear Regulatory Commission (USNRC) regulations (10CFR50.34a) require that nuclear power plants be designed, structed, and operated to keep levels of radioactive material in effluents to unrestricted areas as low as reasonably achievable (ALARA). To ensure these criteria are met, the operating license for Surry Power Station includes Technical Specifications which govern the release of radioactive effluents. Inplant monitoring is used to determine that these predetermined release limits are not exceeded. As a precaution against unexpected or undefined -1 I I I I I I I I I I I I I I I . I environmental processes which might allow undue accumulation of radi6activity in the environment, a progr~ for monitoring the plant environs is also included in Surry Power Station Technical Specifications. C. V~rginia 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 i-s 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 s~ples of environmental media show the presence of man-made isotopes. As a method of referencing the measured 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 1 s Technical Specifications. These concentrations are based upon the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion of "As Low As Is Reasonably Achievable" . 2 I I I I I I I I I I I I I I I I E. This report documents the results of the Radiological Environmental Monitoring Program for 1988 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 in the environment.

4. To verify that the plant operations have no detrimental effect on the health and safety of the public. 3 I I I I I I I I I I I I I I I I II. SAMPLING AND ANALYSIS PROGRAM A. Sampling Program 1. Table 1 summarizes the sampling program for Surry Power Station during 1988. The symbols on this table refer to the sample locations shown on Figures 1 through 3. Figure 1 indicates the locations of the land based s_amples 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 wealth of Virginia direct radiation recording devices. These are indicated as 11 co-location 11 samples. 3. In addition to the Radiological Environmental Monitoring Program required by Surry Technical Specifications, Virginia Electric and Power Company splits samples with the 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 tions except those labeled 11 control 11* 4 I I I I I I I I I I I I I I I I B. Analysis Program 1. Table 2 summarizes the analysis program conducted by Teledyne Isotopes for Surry Power Station during 1988. 5 ---SAMPLE MEDIA Environmental ( TLD' s)

TLD stored ----LOCATION STATION Control (00) West North West (02) Surry Station Discharge mi i North North West North (05) North North East rn~i North East East North East (08) East (Exclusion)

~nl West West South West ( 11 ) South West (12~ South South West (13 South ( 14) South South East H~l South East East ( 17} Station Intake g;j Hog Island Reserve Bacons Castle (20) Route 633 rnB Alliance Surry Hll Route 636 and 637 Scotland Wharf ( 2 5) Jamestown (26) Co 1 on i a 1 Parkway rn~i Route 617 and 618 Kingsmill (29) Williamsburg ( 30) Kingsmill North ( 31 l Budweiser (32 ----TABLE 1 VIRGINIA POWER -SURRY -1988 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 DISTANCE MILES DIRECTION DEGREES 0.17 WNW 292° 0.6 NW 309° 0.4 NNW 330° 0.33 N 357* 0.28 NNE 22* 0.31 NE 45 ° 0.43 ENE 68° 0.31 E 90° 0.40 w 270° 0.45 WSW 250° 0.30 SW 225" 0.43 SSW 203° 0.48 s 180° 0.74 SSE 157" 1. 00 SE 135" 0.57 E 90° 1. 23 ESE 113" 1. 94 NNE 26° 4.45 SSW 202* 3. 5 SW 224" 5. 1 WSW 248° 8.0 WSW 250° 4.0 w 270" 5.0 WNW 285° 6.3 NW 310° 3.7 NNW 330° 5.2 NNW 340° 4.8 N 2* 7.8 N o* 5.6 NNE 14° 5. 7 NNE 2 7° in a lead shield in environmental building.

COLLECTION FREQUENCY REMARKS Quarterly On site* Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundray Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly On site Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly

Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Site Boundary Quarterly Near Resident, co-location Quarterly Apx. 5 mile TLD, co-location Quarterly Apx. 5 mile TLD Quarterly Apx. 5 mile TLD, co-location Quarterly Population Center Quarterly Apx. 5 mile TLD Quarterly Apx. 5 mile TLD, co-location Quarterly Apx. 5 mi le TLD, co-location Quarterly Apx. 5 mile TLD Quarterly Apx. 5 mile TLD Quarterly Apx. 5 mile TLD Quarterly Population Center, co-location Quarterly Apx. 5 mile TLD Quarterly Population Center

SAMPLE MED IA LOCATION STATION Environmental Water Plant ( 3 3) TLD Is (Cont.) Dow ( 3 4) Lee Hall ( 3 5) Goose Island (36) Fa rt Eustis ( 37) Newport News ( 38) James River Bridge (39) Benn's Church ( 40) Smithfield (41) Rushmere ( 42) Rt. 628 ( 43) Air Charcoal Surry Station (SS) and Particulate Hog Isl and Reserve (HIR) Bacons Castle (BC) Alliance (ALL) Colonial Parkway ( CP) Dow Chemical (DOW) Fort Eustis (FE) Newport News ( NN) River Water Surry Discharge Scotland Wharf Surry Station Intake Hog Isl and Point Newport News Chickahominy River Surry Station Di sch arge Scotland Wharf -----TABLE 1 (Cont.) VIRGINIA POWER -SURRY -1988 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 DISTANCE MILES DIRECTION DEGREES 4.8 NE 41° 5 .1 ENE 70° 7. 1 ENE 73° 5.0 E 88° 4.8 ESE 107° 16. 5 ESE 102° 14.8 SSE 14 7° 14. 5 s 175° 11. 5 s 176° 5. 2 SSE 156° 5.0 s 177° .37 NNE 15 ° 2.0 NNE 26° 4. 5 SSW 202° 5. 1 WSW 248° 3. 7 NNW 330° 5. 1 ENE 70° 4.8 ESE 107° 16. 5 ESE 122* 0. 17 NW 325° 5. 0 WNW 285° 1. 9 ESE 77* 2. 4 NE 52° 12.0 SE 140° 11. 2 WNW 300° 0.17 NW 325° 5.0 WNW 285° -------,* COLLECTION FREQUENCY REMARKS Quarterly Apx. 5 mile TLD Quarterly APX. 5 mile TLD Quarterly Population Center, co-location Quarterly Apx. 5 mile TLD Quarterly Apx. 5 mile, TLU co-location Quarterly Population Center Quarterly Control Location Quarterly Control Location Quarterly Population Center Quarterly Apx. 5 mile TLD Quarterly Apx. 5 mile, TLD co-location Weekly Site boundary location with Highest D/Q Weekly Co-location Weekly Weekly Co-location Weekly Weekly Weekly Weekly Control Location Mo nth l y State Split Monthly Control Location/State Split Bi-monthly Bi-monthly Bi-monthly Bi-monthly Control Location Monthly Monthly

-co SAMPLE MEDIA -Well Water Shoreline Sediment Silt Mi 1 k Oysters Clams ---LOCATION Surry Station Hog Island Reserve Bacons Castle Jamestown Hog Island Reserve Burwell's Bay Chickahominy River Surry Station Intake Hog Island Point Point of Shoals Newport News -Surry Station Discharge Lee Hall Epps Colonial Parkway Judkins Wi 11 i ams Deep Water Shoals Point of Shoals Newport News Chickahominy River Surry Station Discharge Hog Island Point Jamestown Lawnes Creek ------TABLE 1 (Cont.) VIRGINIA POWER -SURRY -1988 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 DISTANCE MILES 2. 0 4.5 6.3 O.B 7.76 11. 2 1. 9 2.4 6. 4 12. 0 0.5 7. 1 4.8 3. 7 6. 2 2 2. 5 3.9 6.4 12.0 11. 2 1. 3 2. 4 5. 1 2. 4 DIRECTION NNE SSW NW N SSE WNW ESE NE SSE SE NNW ENE SSW NNW SSW s ESE SSE SE WNW NNW NE WNW SE DEGREES 27° 203° 309° 5* 167° 300° 77 0 52° 157° 140° 341° 64° 201° 337* 211 ° 182° 105° 157° 140° 300° 341° 52° 300° 131°

Well water sample taken onsite at Surry Environmental Building.

--COLLECT ION FREQUENCY Quarterly Quarterly Quarterly Quarterly Semi-Annually Semi-Annually Semi-Annually Semi-Annually Semi-Annually Semi-Annually Semi-Annually Semi-Annually Month 1 y Monthly Monthly Monthly Monthly Bi-Monthly Bi-Monthly Bi-Monthly Bi-Monthly Bi-Monthly Bi-Monthly Bi-Monthly Bi-Monthly ---REMARKS On site* Control Location State Split State Split Control Location State Split Control Location State Split

SAMPLE MED IA LOCATION Crabs Surry Station Di sch arge Fish Surry Station Discharge Crops Brock's Farm (Corn,Peanuts, Slade's Farm Soybeans) (Cabbage,Kale)

Pool's Garden Carter's Grove Garden Ryan's Garden Stone's Garden ----TABLE 1 (Cont.) VIRGINIA POWER -SURRY -1988 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 DISTANCE MILES DIRECTION DEGREES 0.6 NW 312° 0.6 NW 312" 3.8 s 188° 2. 4 s 177° 2.3 s 182° 4.8 NE 56° ----, --COLLECT ION FREQUENCY REMARKS Annually Semi-Annually Annually St ate Split Annually St ate Split Annually St ate Split Annually State Split Annually State Split/Control Loe. (Chester, Va.) Annually St ate Split ........ 0 --------- 2 RIVER BASED SAMPLES I 11 FIGURE 3 SITE BOUNDRY TLD's i ' + T 1 --r -t N r--i \~ __:. + *I-+ ;---~-----------*-*--

I TABLE 2 I SURRY POWER STATION ae SAMPLE ANALYSIS PROGRAM I SAMPLE MED IA FREQUENCY ANALYSIS LLD* REPORT UN ITS I Thermo luminescent Dosimetry (TLD) Quarterly Gamma Dose mR/month I Air Iodine Weekly I-131 0.07 pCi/m3 Air Particulate Weekly Gross Beta 0.01 pCi/m3 I Quarterly (1) Gamma Isotopic pCi/m3 Cs-134 0.05 I Cs-137 0.06 River Water Quarterly Tritium 2000 pCi / £ I composite of monthly sample Monthly and Gamma Isotopic pCi / £ Bi-monthly Mn-54 15 Fe-59 30 Co-58, 60 15 I Zn-65 30 Zr-95 30 Nb-95 15 I-131 10 I Cs-134 15 Cs-137 18 Ba-140 60 I La-140 15 Quarterly pCi / £ Well Water Tritium 2000 I Gamma Isotopic pCi/£ Mn-54 15 Fe-59 30 I Co-58,60 15 Zn-65 30 Zr-95 30 I Nb-95 15 I-131 1 Cs-134 15 I Cs-137 18 Ba-140 60 La-140 15 (1) Quarterly composites of each locations's weekly air particulate samples will be analysed for Gamma Emitters.

I 13 I I TABLE 2 (Cont.) SURRY POWER STATION SAMPLE ANALYSIS PROGRAM I I SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS I Shoreline Sediment Semi-Annual Gamma Isotopic pCi/kg-dry Cs-134 150 Cs-137 180 I Silt Semi-Annual Gamma Isotopic pCi/kg-dry Cs-134 150 I I Cs-137 180 I Milk Monthly I-131 1 pCi / £ Gamma Isotopic pCi/£ Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 I Oyster Bi-Monthly Gamma Isotopic pCi /kg-wet Mn-54 130 Fe-59 260 I Co-58, 60 130 Zn-65 260 Cs-134 130 I Cs-137 150 I Clams Annually Gamma Isotopic pCi /kg-wet Mn-54 130 Fe-59 260 Co-58, 60 130 I Zn-65 260 Cs-134 130 Cs-137 150 I Crabs Annually Gamma Isotopic pCi/kg-wet Mn-54 130 I Fe-59 260 Co-58, 60 130 Zn-65 260 Cs-134 130 Cs-137 150 I 14 I I I .. I I I I I I I I I I I I I I TABLE 2 (Cont.) SURRY POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Fi sh Crops Note:

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 Annually Gamma Isotopic pCi/kg-wet 1-131 60 Cs-134 60 Cs-137 80 This table is not a complete listing of nuclides which can be detected and reported.

Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported. LLD 1 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 I I I I I I I I ,1 I I I I I I I III. EXCEPTIONS 16 I I II I ,1 I I I .. I I I I I I I I ------------------------- III. 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 recurrence. Three TLD samples were lost from sampling stations during 1988. The TLDs were discovered missing while performing monthly vi sua 1 ch eeks of TLDs at each TLD station. The loss is attributed to vandalism. When TLDs are found missing they are normally replaced. Such was the case with the missing TLDs in the first quarter. Replacement TLDs were not requested for the second quarter TLDs found missing in June because the third quarter TLDs were already in transit to the station. Upon arrival at the station, third quarter TLDs were installed at the missing TLD stations. Compared to the large number of TLD stations in the field the loss rate is low and not considered a problem. No corrective action is considered necessary. One air iodine sample did not meet the station Technical Specification LLD requirement due to low sample volume. The fuse had blown on the power pole where the air sampler is located. Sample volume was calculated to be only 79 cubic meters as compared to a typical sample volume of 530 cubic meters. A minimum sample volume of 125 cubic meters is needed to meet the air iodine LLD. 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 17 I I I I I I I I I I I I I I *I I samples because of the delay in receipt of the samples from the State of Virginia. These samples are not used to comply with the requirements of the station's Technical Specifications. The monthly river water samples collected by Vepco personnel meet Technical Specification LLD requirements. Station Technical Specifications require three samples of oysters bi-monthly. For the month of January only two samples were collected. Due to a microorganism infestation in the lower James River (MSX/Dermo), oyster shellstock has been virtually depleted at the Newport News (Naseway Shoal) sample location. Sampling has terminated at this location and will recommence when the oyster beds revitalize as determined by the Commonwealth of Virginia. An alternative sampling location was selected. This location, Rock Landing Shoals, is downstream of the power station as was the Newport News location. Sampling began in March and will continue until the Newport News location is approved for sampling. The exceptions to the 1988 Radiological Environmental Monitoring Program are not indicative of programmatic weaknesses. Corrective actions were taken as appropriate and changes to the administration of the program are not deemed necessary. 18 I I I I I I I I I I 'I I I I I I I Location 04 03/08 NN SD, SW (State Split) ALL REMP EXCEPTIONS FOR SCHEDULED SAMPLING AND ANALYSIS DURING 1988 Description Direct Radiation Direct Radiation Oysters River Water I-131 Ba/La-140 Air Iodine 19 Date of Sampling First Quart er ( Sets 1/2) Second Quart er (Sets 1/2) January Reason(s) for Loss/ Exception TLD Vandalized TLD Vandalized Sample not collected due to shell stock depletion at sampling location. LLD's not met due to 05/15/88 late receipt from Ol/15/88-12/15/88 State of Virginia. 06/14/88-06/21/88 LLD not met due to loss of power at sampling location. I I I I I I I I I I IV.

SUMMARY

AND DISCUSSION OF 1988 I ANALYTICAL RESULTS I I I I ,I I I 20 I I I I I I I I I I I I I I I I IV.

SUMMARY

AND DISCUSSION OF 1988 ANALYTICAL RESULTS Data from the radiologi~al 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 synopsi~ 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 Program. Participation in this program ensures that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples are performed. The results of the EPA Interlaboratory Comparison are provided in Section VIII. Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods. Teledyne Isotopes analytical methods meet or exceed the Lower Limit of Detection (LLD) requirements given in Table 2 of the USNRC Branch Technical Position of Radiological Monitoring, Revision I, November 1979. The following is a discussion and summary of the results of the environmenta.l 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 ment of the gross beta activity on the weekly particulate filters is a good 21 I I I I I I I I ,1 I I I I I I I indication of the levels of natural and/or manmade radioactivity in the environment. If sample results indicate normal levels of radioactivity, the filters are composited and analyzed for gamma emitting radioactivity. The gamma analysis will identify the type and origin of the radioactivity. If the beta analysis indicates results above the normal levels, gamma analysis may be done immediately to. identify the cause. The average concentration for the control location (Newport News) is 0.019 pCi/m3 with a range of 0.010 to 0.033 pCi/m3. The average ment for the indicator locations is 0.018 pCi/m3 with a range of 0.005 to 0.042 *pCi/m3. The required lower level of detection for the analysis is 0.010 pCi/m3. The maximum permissible concentrations of radioactivity in air above natural background radioactivity in unrestricted areas is limited by the Code of Federal Regulations Title 10, Part 20, Table II, for gross beta, to less than 100.000 pCi/m3. The monthly averages of the gross beta concentrations for the seven indicator and one control location are plotted for 1969 through 1988. The gross beta levels observed are comparable to the levels detected during the 1982-1987 period. Prior to this period the gross beta activities found during preoperational and the following operational period were higher due to atmospheric atomic weapons testing. As mentioned previously, air particulate filters were composited by location on a quarterly basis and were analyzed by gamma ray spectroscopy. The results of this analysis are listed in Table 6. Beryllium-?, which is produced continuously in the upper atmosphere by cosmic radiation, was measured in all 32 composite samples (control and indicator locations) with an average activity of 0.063 pCi/m3 and a range between 0.037 to 0.087 pCi/m3. Naturally occurring potassium-40 was detected in five samples with 22 I I I I I I I I I ! I I I I I I I an average activity of 0.005 pCi/m3 and a range of 0.004 to 0.007 pCi/m3. The results indicate that no other gamma emitting radioactivity was detected. Charcoal cartridges are installed downstream of the particulate filters and are used to collect airborne radioiodine. The results of the weekly analysis of the charcoal cartridges,are presented in Table 4. All results were below the lower level of detection with no positive activity detected. 23 ->-... ... ::::, u, 0 u C. Q) N > +::, (") == --0 C. -------------GROSS BETA IN AIR PARTICULATES 10

1 I 10*3 1984 a. JI I .Jtr3i' >V * -1985 (a) Chernobyl Accident 14.. -* vi l~1 1986 I .. "'---& ---~ ,ultf.~-\v'-~* .aa.ao -r (a) 1.987 1988 1989 0 * --Indicator Control

->-.. .. :I en 0 u C. G) > N u, M :l: ::::: 0 C. ---*----------10'-1 -----, 10-3 1979 b GROSS BETA IN AIR PARTICULATES -,..A I'\ ,r"( \ ,...,--, I\ I. r \ \ J V) 0 \\ j -. --. --I L -.I ' ' I I \. -I \ ---., * -f\-. I, \I\.~ "-d I\. JI J j>--ref\ -A. J>"'>"d .. -\r\l\_

I '""'\ V V vv u -'tf " V" ! v-/Y 1980 1981 1982 1983 1984 --o Indicator
Control

-N °' ---->-... ... ::I u, I 0 () . CL G) > I C') -0 CL 10° J 10-1 l --"7 2 10-3 1974 ---------GROSS BETA IN AIR PARTICULATES Q. ,-,"i I\\ I I~ I , l 0 I ** -I -V ,_llllt... ,U ' ,-, ,, ... -0 I 1,1 -u

I' / -.... " ' "" "' r o. ) .,.. b 6 C),. ~. * ~. * ,1 I 1975 1976 1977 1978 --* * ' l j -I ) -~ 0
1979 -Indicator Control -

->-... ... ::, en 0 u C. G) N > '-J C") == -.. 0 C. -------------10-1 ' .~ '----10-3 1969 --~, -' . 1970 GROSS BETA IN AIR PARTICULATES ....Ct A II r \ I ' I \ I \1' r \ j u ... ,--a -..Ill/ ............ .,... .......... -* ' V "'I] ~1 \ -,-y--, * \I , IL. JI .In a II _,\ .... w "6 0 Y" . . 1971 1972 1973 1974 0 * --Indicator Control -N co -------------ANALYSIS AND MEDIUM OR PATHWAY TOTAL NUMBER SAMPLED OF ANALYSES (UNIT OF MEASUREMENT) PERFORMED Air Iodine 1-131 424 (pCi/m3) Airborne Gross Beta 424 Particulates (lE-03 pCi/m3) Gamma Spec 32 Quarterly Be-7 32 K-40 32 TABLE 3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION SURRY COUNTY. VIRGINIA LOWER LIMIT OF ALL INDICATOR LOCATIONS DETECTION MEAN (LLD) (1) RANGE 0.07 -(0/371) 10 18.4(371/371) (5.2-42) 62.4(28/28) (36.8-86.5) 5.34(3/28) (4.04-6.59) DOCKET NO. 5-280-281 JANUARY 1, to DECEMBER 31, 1988 LOCATION WITH HIGHEST MEAN NAME MEAN DISTANCE AND DIRECTION RANGE N/A N/A BC 20.1(53/53) (12-41) FE 68.9(4/4) (55.7-86.5) CP 5.40(1/4) (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. NUMBER OF CONTROL LOCATION NONROUTINE MEAN REPORTED RANG!! MEASUREMENTS -(0/53) 0 19.3(53/53) 0 (10-33) 67.9(4/4) 0 (54.4-84.5) 4.90(2/4) (4.65-5.14) 0 --

TABLE 4 (Page 1 of 4) VIRGINIA POWER -SURRY -1988 CONCENTRATIONS OF IODINE-131 IN FILTERED AIR pCi/m3 +/- 2 Sigma STAT IONS ss HIR BC COLLECTION DATE ALL CP DOW FE NN JANUARY 12/29/87-01/05/88

<.02 <.02 <. 02 <. 02 <.02 <. 02 <.02 <.02 Ol/05/88-01/12/88 <.01 <.01 <.01 <.01 <.02 <.02 <.02 <. 02 Ol/12/88-01/19/88 <. 02 <.02 <. 02 <.02 <.01 <.01 <.01 <.01 01/19/88-01/26/88 <.02 <. 02 <. 02 <.02 <. 02 <. 02 <. 02 <.02 Ol/26/88-02/02/88 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 <.02 <. 02 N I.D FEBRUARY 02/02/88-02/09/88 <.02 <. 02 <.02 <. 02 <.02 <.02 <.02 <.02 02/09/88-02/16/88 <.02 <. 02 <.02 <.02 <. 02 <.02 <.02 <.02 02/16/88-02/23/88 <.02 <. 02 <.02 <.02 <.02 <.02 <. 02 <.02 02/23/88-03/01/88 <.02 <. 02 <. 02 <.02 <. 02 <.02 <. 02 <. 02 MARCH 03/01/88-03/08/88 <. 02 <. 02 <. 02 <.02 <.02 <.02 <.02 <.02 03/08/88-03/15/88 <.01 <.01 <.01 <.01 <.01 <.01 <. 01 <.01 03/15/88-03/22/88 <.02 <. 02 <. 02 <.02 <.02 <. 02 <.02 <.02 03/22/88-03/29/88 <.01 <.01 <.01 <.01 <. 02 <.02 <.02 <.02

STATIONS ss COLLECTION DATE APRIL 03/29/88-04/05/88

<.02 04/05/88-04/12/88 <. 02 04/12/88-04/19/88 <.02 04/19/88-04/26/88 <.009 w 04/26/88-05/03/88 <.01 0 MAY 05/03/88-05/10/88

<. 03 05/10/88-05/17/88

<.02 05/17/88-05/24/88 <.02 05/24/88-05/31/88 <. 02 JUNE 05/31/88-06/07/88 <.01 06/07/88-06/14/88 <. 02 06/14/88-06/21/88 <.02 06/21/88-06/28/88 <. 02 (a) LLD not met due to power outage; ( b) P~wer outage; low volume. ------TABLE 4 (Page 2 of 4) VIRGINIA POWER -SURRY -1988 CONCENTRATIONS OF IODINE-131 IN FILTERED AIR pCi/m3 +/- 2 Sigma HIR BC ALL CP <.02 <.02 <.02 <.02 <. 02 <. 02 <.02 <.02 <. 02 <.02 <. 02 <.02 <.01 <.01 <.01 <. 02 <.01 <.01 <.01 <.01 <.03 <.03 <.03 <.01 <. 02 <. 02 <.02 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 <.01 <.02 . <. 02 <. 02 <. 02 <. 02 <.02 < .1 (a) <.05 ( b) <.03 <. 02 <. 02 <. 02 low volume. -----DOW FE NN <.02 <.02 <.02 <. 02 <.02 <.02 <. 02 <.02 <. 02 <. 02 <. 02 <. 02 <.01 <.01 <.01 <.01 <.01 <.01 <.02 <.02 <. 02 <. 02 <.02 <. 02 <. 02 <. 02 <.02 <.01 <.01 <.01 <.02 <. 02 <.02 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02

STATIONS ss COLLECTION DATE JULY 06/28/88-07/05/88

<.02 07/05/88-07/12/88 <.02 07/12/88-07/19/88 <.01 w 07/19/88-07/26/88 <.02 I-' 07/26/88-08/02/88 <.01 AUGUST 08/02/88-08/09/88 <.02 08/09/88-08/16/88 <. 02 08/16/88-08/23/88 <. 02 08/23/88-08/29/88 <. 02 SEPTEMBER 08/29/88-09/06/88 <.02 09/06/88-09/13/88 <.01 09/13/88-09/20/88 <.02 09/20/88-09/27/88 <.02 ------TABLE 4 (Page 3 of 4) VIRGINIA POWER -SURRY -1988 CONCENTRATIONS OF IODINE-131 IN FILTERED AIR pCi/m3 +/- 2 Sigma H IR BC All CP <.02 <. 02 <.02 <.01 <. 02 <.02 <.02 <. 02 <. 02 <.01 <. 02 <.01 <. 02 <.02 <.02 <.02 <.Ol <.01 <. 02 <.02 <. 02 <. 02 <. 02 <.02 <.02 <. 02 <.03 <.02 <. 02 <. 02 <. 02 <. 02 <. 02 <.02 <.02 <. 02 <. 02 <.02 <. 02 <.02 <.01 <.01 <.01 <.02 <.02 <. 02 <. 02 <.02 <. 02 <. 02 <. 02 <. 02 -----DOW FE NN <.01 <.01 <.01 <. 02 <. 02 <. 02 <.01 <.01 <.01 <. 02 <. 02 <.02 <.02 <.02 <. 02 <. 02 <.02 <.02 <. 02 <.02 <. 02 <. 02 <. 02 <.01 *<.02 <. 02 <.02 <.02 <. 02 <.02 <.02 <. 02 <.02 <. 02 <.02 <. 02 <.02 <. 02 <. 02 J

STATIONS ss COLLECTION DATE OCTOBER 09/27/88-10/04/88

<. 02 10/04/88-10/11/88 <.02 10/11/88-10/18/88 <.01 10/18/88-10/25/88 <.01 10/25/88-11/02/88 <.02 w N NOVEMBER ll/02/88-11/08/88 <. 02 ll/08/88-11/15/88 <. 02 11/15/88-11/22/88 <.05 ll/22/88-11/29/88 <. 02 DECEMBER ll/29/88-12/06/88 <.01 12/06/88-12/13/88 <.02 12/13/88-12/20/88 <.02 12/20/88-12/27/88 <.01 12/27/88-01/03/89 <.02 ------TABLE 4 (Page 4 of 4) VIRGINIA POWER -.SURRY -1988 CONCENTRATIONS OF IOOINE-131 IN FILTERED AIR pCi/m3 +/- 2 Sigma H IR BC ALL CP <. 02 <. 02 <.02 <. 02 <. 02 <.02 <.03 <. 02 <.01 <.01 <.01 <.01 <. 02 <.01 <.01 <.02 <. 02 <.02 <. 02 <.01 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 <. 02 <.03 <.02 <. 02 <.03 <.03 <. 02 <.02 <.01 <.01 <.01 <.01 <. 01 <. 02 <. 02 <.02 <.02 <.03 <.03 <.02 <.02 <. 02 <.02 <.02 <.01 <. 02 <. 02 <.02 <.009 -----DOW FE NN <. 02 <. 02 <.02 <. 02 <. 02 <. 02 <.01 <.01 <.01 <. 02 <. 02 <.02 <.01 <.01 <.01 <. 02 <.02 <. 02 <. 02 <. 02 <. 02 <.03 <.03 <. 03 <.01 <.01 <.01 <.01 <.03 <.01 <.02 <.02 <. 02 <. 02 <.02 <. 02 <.01 <.01 <.01 <.009 <.009 <.009 -**--------------l -I TABLE 5 (Page 1 of 4) VIRGIN IA POWER -SURRY 1988 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES lo-3 pCi/m3 +/- 2 Sigma STATION Average COLLECTION DATE ss H IR BC ALL CP DOW FE NN +/- 2 s.d JANUARY 12/29/87-01/05/88 16 +/- 2 16 +/- 2 22 +/- 2 24 +/- 2 19 +/- 2 20 +/- 2 19 +/- 2 19 +/- 2 19 +/- 5 Ol/05/88-01/12/88 25 +/- 2 29 +/- 2 22 +/- 2 26 +/- 2 27 +/- 2 22 +/- 2 22 +/- 2 25 +/- 2 25 +/- 5 01/12/88-01/19/88 15 +/- 2 16 +/- 2 20 +/- 2 20 +/- .2 17 +/- 2 17 +/- 2 19 +/- 2 17 +/- 2 18 +/- 4 Ol/19/88-0l/26/B8 14 +/- 2 14 +/- 2 18 +/- 2 16 +/- 2 15 +/- 2 16 +/- 2 16 +/- 2 16 +/- 2 16 +/- 3 Ol/26/88-02/02/88 20 +/- 2 20 +/- 2 24 +/- 2 24 +/- 2 21 +/- 2 24 +/- 2 20 +/- 2 23 +/- 2 22 +/- 4 w FEBRUARY w 02/02/88-02/09/88 14 +/- 2 17 +/- 2 21 +/- 2 15 +/- 2 20 +/- 2 18 +/- 2 18 +/- 2 18 +/- 2 18 +/- 5 02/09/88-02/16/88 18 +/- 2 21 +/- 2 27 +/- 2 23 +/- 2 18 +/- 2 25 +/- 2 26 +/- 2 24 +/- 2 23 +/- 7 02/16/88-02/23jBB 16 +/- 2 20 +/- 2 22 +/- 2 17 +/- 2 20 +/- 2 17 +/- 2 25 +/- 2 20 +/- 2 20 +/- 6 02/23/88-03/0l/88 16 +/- 2 16 +/- 2 21 +/- 2 15 +/- 2 16 +/- 2 15 +/- 2 16 +/- 2 20 +/- 2 17 +/- 5 MARCH 03/01/88-03/08/88 18 +/- 2 20 +/- 2 21 +/- 2 17 +/- 2 16 +/- 2 19 +/- 2 20 +/- 2 17 +/- 2 19 +/- 4 03/08/88-03/15/88 11 +/- 2 13 +/- 2 18 +/- 2 16 +/- 2 15 +/- 2 12 +/- 2 10 +/- 2 19 +/- 2 14 +/- 7 03/15/88-03/22/88 11 +/- 2 15 +/- 2 14 +/- 2 12 +/- 2 15 +/- 2 15 +/- 2 17 +/- 2 11 +/- 2 14 +/- 4 03/22/88-03/29/88 10 +/- 1 18 +/- 2 18 +/- 2 15 +/- 2 18 +/- 2 20 +/- 2 19 +/- 2 18 +/- 2 17 +/- 6 Quarter Average 16 +/- 8 18 +/- 8 21 +/- 6 18 +/- 9 18 +/- 7 18 +/- 7 19 +/- 8 19 +/- 7 18 +/- 3 +/- 2 s. d. -w -+"> -STATION COLLECTION DATE APRIL 03/29/88-04/05/88 04/05/88-04/12/88 04/12/88-04/19/88 04/19/88-04/26/88 04/26/88-05/03/88 MAY 05/03/88-05/10/88 05/10/88-05/17/88 05/17/88-05/24/88 05/24/88-05/31/88 JUNE 05/31/88-06/07/88 06/07/88-06/14/88 06/14/88-06/21/88 06/21/88-06/28/88 Quarter Average +/- 2 s. d. --ss 11 +/- 2 10 +/- 1 8.6 +/- 1. 6 13 +/- 2 10 +/- 2 10 +/- 2 12 +/- 2 13 +/- 2 12 +/- 2 12 +/- 2 12 +/- 2 25 +/- 2 15 +/- 2 13 +/- 8 (a) Power outage; low volume. ----------------TABLE 5 (Page 2 of 4) VIRGINIA POWER -SURRY 1988 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES 10-3 pCi/m3 +/- 2 Sigma H IR BC ALL CP DOW 14 +/- 2 21 +/- 2 21 +/- 2 18 +/- 2 17 +/- 2 13 +/- 2 13 +/- 2 13 +/- 2 13 +/- 2 11 +/- 2 12 +/- 2 15 +/- 2 12 +/- 2 13 +/- 2 13 +/- 2 15 +/- 2 21 +/- 2 17 +/- 2 15 +/- 2 10 +/- 1 12 +/- 2 15 :I: 2 13 +/- 2 12 +/- 2 12 +/- 2 14 +/- 2 14 +/- 2 16 +/- 2 15 +/- 2 14 +/- 2 17 +/- 2 15 +/- 2 16 +/- 2 17 +/- 2 19 +/- 2 13 +/- 2 17 +/- 2 14 +/- 2 12 +/- 2 16 +/- 2 12 +/- 2 15 +/- 2 16 +/- 2 11 +/- 2 14 +/- 2 17 +/- 2 20 +/- 2 18 +/- 2 17 +/- 2 18 +/- 2 11 +/- 2 24 +/- 2. 21 +/- 2 17 +/- 2 20 +/- 2 13 +/- 2 22 +/- 2 42 +/- 9 ( a) 24 +/- 3 (a) 25 +/- 2 11 +/- 2 19 +/- 2 21 +/- 2 14 +/- 2 17 +/- 2 13 +/- 4 18 +/- 7 19 +/- 15 15 +/- 7 16 +/- 8 -----Average FE NN +/- 2 s.d 21 +/- 2 18 +/- 2 18 +/- 7 14 +/- 2 14 +/- 2 13 +/- 3 14 .I: 2 15 +/- 2 13 +/- 4 20 +/- 2 17 +/- 2 16 +/- 7 14 +/- 2 14 +/- 2 13 +/- 3 14 +/- 2 17 +/- 2 14 +/- 4 13 +/- 2 18 +/- 2 16 +/- 5 15 +/- 2 15 +/- 2 14 +/- 3 15 +/- 2 14 +/- 2 14 +/- 4 20 +/- 2 19 +/- 2 18 +/- 5 21 +/- 2 14 +/- 2 18 +/- 10 24 +/- 2 22 +/- 2 25 +/- 16 18 +/- 2 18 +/- 2 17 +/- 6 17 +/- 7 17 +/- 5 16 +/- 4

TABLE 5 (Page 3 of 4) VIRGINIA POWER -SURRY 1988 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES lo-3 pCi/m3 +/- 2 Sigma STATION Average COLLECTION DATE ss HIR BC All CP DOW FE NN +/- 2 s.d JULY 06/28/88-07/05/88 12 +/- 2 7.3 +/- 1.4 12 +/- 2 14 +/- 2 9.3 +/- 1.5 12 +/- 2 14 +/- 2 11 +/- 2 12 +/- 5 07/05/88-07/12/88 27 +/- 2 11 +/- 2 17 +/- 2 26 +/- 2 26 +/- 2 24 +/- 2 22 +/- 2 25 +/- 2 22 +/- 11 07/12/88-07/19/88 22 +/- 2 9.0 +/- 1.6 18 +/- 2 20 +/- 2 23 +/- 2 19 +/- 2 20 t 2 21 +/- 2 19 +/- 9. 07/19/88-07/26/88 5.2 +/- 1.3 12 +/- 2 13 +/- 2 9.6 +/- 1.5 9.5 +/- 1.5 12 +/- 2 14 +/- 2 10 :t 2 11 +/- 6 07/26/88-08/02/88 24 +/- 2 21 +/- 2 25 +/- 2 24 +/- 2 20 +/- 2 15 +/- 2 24 +/- 2 23 +/- 2 22 +/- 7 w AUGUST u, 08/02/88-08/09/88 11 +/- 2 11 +/- 2 12 +/- 2 12 +/- 2 11 +/- 2 9.9 +/- 1.4 8.0 +/- 1.4 11 +/- 2 11 +/- 3 08/09/88-08/16/88 11 +/- 2 11 +/- 2 12 +/- 2 10 +/- 2 12 +/- 2 9.8 +/- 1.5 11 +/- 2 10 +/- 2 11 +/- 2 08/16/88-08/23/88 16 +/- 2 26 +/- 2 20 +/- 2 22 +/- 2 22 +/- 2 19 +/- 2 20 +/- 2 18 +/- 2 20 +/- 6 08/23/88-08/29/88 24 +/- 2 21 +/- 2 23 +/- 2 26 +/- 2 25 +/- 2 21 +/- 2 26 +/- 2 23 +/- 2 24 +/- 4 SEPTEMBER 08/29/88-09/06/88 17 +/- 2 14 +/- 2 16 +/- 2 18 +/- 2 24 +/- 2 10 +/- 2 18 +/- 2 14 +/- 2 16 +/- 8 09/06/88-09/13/88 13 +/- 2 18 +/- 2 18 +/- 2 19 +/- 2 17 +/- 2 18 +/- 2 18 +/- 2 18 +/- 2 17 +/- 4 09/13/88-09/20/88 11 +/- 2 18 +/- 2 16 +/- 2 12 +/- 2 17 +/- 2 18 +/- 2 18 +/- 2 23 +/- 2 17 +/- 8 09/20/88-09/27/88 15 +/- 2 19 +/- 2 15 +/- *2 20 +/- 2 15 +/- 2 20 +/- 2 22 +/- 2 20 +/- 2 18 +/- 6 Quarter Average 16 +/- 13 15 +/- 11 17 +/- 8 18 +/- 12 18 +/- 12 16 +/- 10 18 +/- 10 18 +/- 11 17 +/- 2 +/- 2 s. d.

TABLE 5 (Page 4 of 4) VIRGINIA POWER -SURRY 1988 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES lo-3 pCi/m3 +/- 2 Sigma STAT JON Average COLLECTION DATE ss H IR BC ALL CP DOW FE NN +/- 2 s.d OCTOBER 09/27/88-10/04/88 15 +/- 2 23 +/- 2 26 +/- 2 14 +/- 2 22 +/- 2 20 +/- 2 22 +/- 2 24 +/- 2 21 +/- 9 10/04/88-10/11/88 15 +/- 2 16 +/- 2 19 +/- 2 17 +/- 2 13 +/- 2 19 +/- 2 17 +/- 2 18 +/- 2 17 +/- 4 10/11/88-10/18/88 12 +/- 2 13 +/- 2 21 +/- 2 20 +/- 2 17 +/- 2 20 +/- 2 18 +/- 2 19 +/- 2 18 +/- 7 10/18/88-10/25/88 12 +/- 2 18 +/- 2 17 +/- 2 18 +/- 2 16 +/- 2 17 +/- 2 15 +/- 2 17 +/- 2 16 +/- 4 10/25/88-11/02/88 14 +/- 1 21 +/- 2 23 +/- 2 23 +/- 2 23 +/- 2 23 +/- 2 22 +/- 2 23 +/- 2 22 +/- 6 NOVEMBER w CJ) 11/02/88-11/08/88 16 +/- 2 19 +/- 2 26 +/- 3 24 +/- 2 22 +/- 2 25 +/- 3 22 +/- 2 26 +/- 3 23 +/- 7 . 11/08/88-11/15/88 14 +/- 2 21 +/- 2 23 +/- 2 25 +/- 2 22 +/- 2 24 +/- 2 24 +/- 2 23 +/- 2 22 +/- 7 11/15/88-11/22/88 12 +/- 2 20 +/- 2 21 +/- 2 22 +/- 2 19 +/- 2 21 +/- 2 22 +/- 2 21 +/- 2 20 +/- 7 ll/22/88-11/29/88 14 +/- 2 23 +/- 2 23 +/- 2 24 +/- 2 18 +/- 2 25 +/- 2 21 +/- 2 23 +/- 2 21 +/- 7 DECEMBER ll/29/88-12/06/88 13 +/- 2 19 +/- 2 24 +/- 2 25 +/- 2 19 +/- 2 20 +/- 2 28 +/- 4 24 +/- 2 22 +/- 9 12/06/88-12/13/88 20 +/- 2 31 +/- 3 35 +/- 3 32 +/- 2 29 +/- 2 32 +/- 2 33 +/- 3 33 +/- 3 31 +/- 9 12/13/88-12/20/88 16 +/- 2 28 +/- 3 41 +/- 3 32 +/- 2 28 +/- 2 31 +/- 2 22 +/- 2 22 +/- 2 28 +/-15 12/20/88-12/27/88 24 +/- 2 25 +/- 2 28 +/- 2 21 +/- 2 22 +/- 2 26 +/- 2 26 +/- 2 30 +/- 2 25 +/- 6 12/27/88-01/03/89 29 +/- 2 32 +/- 3 31 +/- 2 28 +/- 2 25 +/- 2 27 +/- 2 28 +/- 2 29 +/- 2 29 +/- 4 Quarter Average 16 +/- 10 22 +/- 11 26 +/- 13 23 +/- 10 21 +/- 9 24 +/- 9 23 +/- 10 24 +/- 9 22 +/- 6 +/- 2 s .d. Annual Average 15 +/- 10 17 +/- 11 20 +/- 11 20 +/- 12 18 +/- 10 19 +/- 11 19 +/- 10 19 +/- 10 18 +/- 3 +/- 2 s .d.

-,, -STATION ss H IR w ....... BC ALL

All other L --------TABLE 6 (Page 1 of 2) VIRGINIA POWER -SURRY -1988 --CONCENTRATIONS OF GAMMA EMITTERS*

IN QUARTERLY AIR PARTICULATES 10-3 pCi/m3 +/- 2 sigma FIRST QUARTER SECOND QUARTER THIRD QARTER --~ -FOURTH QUARTER AVERAGE NUCLIDE 12/29/87-03/29/88 03/29/88-06/28/88 06/28/88-09/27/88 09/27/88-01/03/89 +/- 2. s. d. Be-7 45.3 +/- 4.5 67.7 +/- 6.8 51.3 +/- 5.1 36.8 +/- 3.7 50.3 +/- 26.l K-40 <5 <5 <5 <4 Co-60 <0.3 <0.3 <0.3 <0.3 Cs-134 <0.3 <O. 2 <0.2 <0.2 Cs-137 <0.3 <0.3 <0.2 <0.2 Th-228 <0.4 <0.4 <0.4 <0.4 Be-7 65.0 +/- 6.5 63.0 +/- 6.3 61.4 +/- 6.1 54.8 +/- 5.5 61. l +/- 8.8 K-40 <5 <4 4.04 +/- 2.30 6.59 +/- 2.36 5.32 +/- 3.61 Co-60 <0.2 <0.2 <0.3 <0.2 Cs-134 <0.2 <0.2 <0.3 <0.2 Cs-137 <0.2 <0.2 <0.3 <0.2 Th-228 <0.3 <0.3 <0.4 <0.3 Be-7 68.6 +/- 6.9 80.7 +/- 8.1 62.5 +/- 6.3 54.4 +/- 5.4 66.6 +/- 22. 2 K-40 <6 <6 <4 <6 Co-60 <0.4 <0.3 <0.2 <0.3 Cs-134 <0.3 <0.3 <0.2 <0.3 Cs-137 <0.3 <0.3 <0.2 <0.3 Th-228 <0.5 <0.5 <0.3 <0.5 Be-7 58.4 +/- 5.8 74.6 +/- 7.5 56.7 +/- 5.7 52.9 +/- 5.3 60.7 +/- 19.2 K-40 <8 <8 <6 <6 Co-60 <0.4 <0.3 <0.3 <0.2 Cs-134 <0.3 <0.3 <0.3 <0.2 Cs-137 <0.3 <0.3 <0.3 <0.2 Th-228 <0.5 <0.4 <0.5 <0.3 gamma emitters were <LLD. ) - -STATION CP w DOW OJ FE NN

All -------------~ -NUCLIDE Be-7 K-40 Co-60 Cs-134 Cs-137 Th-228 Be-7 K-40 Co-60 Cs-134 Cs-137 Th-228 Be-7 K-40 Co-60 Cs-134 Cs-137 Th-228 Be-7 K-40 Co-60 Cs-134 Cs-137 Th-228 other gamma emitters TABLE 6 (Page 2 of 2) VIRGINIA POWER -SURRY -1988 ' CONCENTRATIONS OF GAMMA EMITTERS*

IN QUARTERLY AIR PARTICULATES 10-3 pCi/m3 +/- 2 sigma FIRST QUARTER SECOND QUARTER THIRD QARTER FOURTH QUARTER 12/29/87-03/29/88 03/29/88-06/28/88 06/28/88-09/27/88 09/27/88-01/03/89 68.3 +/- 6.8 71.9 +/- 7.2 59.5 +/- 5.9 51.2 +/- 5.1 <3 <4 5.40 +/- 2.40 <4 <0.2 <0.2 <0.3 <0.2 <0.2 <0.2 <0.3 <0.2 <0.2 <0.2 <0.3 <0.2 <0.3 <0.3 <0.4 <0.3 67.1 +/- 6.7 79.7 +/- 8.0 62.9 +/- 6.3 56.4 +/- 5.6 <4 <5 <4 <5 <0.3 <0.2 <0.2 <0.2 <0.2 <0.2 <0.2 <0.2 <0.2 <0.2 <0.2 <0.2 <0.3 <O. 4 <0.3 <0.4 64.4 +/- 6.4 86.5 +/- 8.7 68.8 +/- 6.9 55.7 +/- 5.6 <4 <4 <10 <5 <0.2 <0.2 <0.4 <0.2 <0.2 <0.2 <0.4 <0.2 <0.2 <0.2 <0.4 <0.2 <0.3 <0.3 <0.5 <0.3 54.4 +/- 5.4 84.5 +/- 8.5 69.9 +/- 7.0 62.9 +/- 6.3 5.14 +/- 2.16 4.65 +/- 2.22 <5 <4 <0.2 <0.2 <0.3 <0.2 <0.2 <0.2 <0.3 <0.2 <0.2 <0.2 <0.2 <0.2 <0.4 <0.4 <0.4 <0.3 were <LLD. AVERAGE +/- 2.s.d. 62.7 +/- 18.6 5.40 +/- 2.40 66.5 +/- 19.6 68.9 +/- 25.9 67.9 +/- 25.5 4.90 +/- 0.7 - I I I I I I I I I I I I I I I I B. 1. Waterborne Exposure Pathway River Water The James River is an estuary near Surry Power Station and undergoes tidal exchange with the Chesapeake Bay. River water samples thus represent saline bay water. Samples of James River water are collected as both monthly grab samples at the Surry Discharge and Scotland Wharf stations and bi-monthly grab samples at the Hog Island Point, Newport News, hominy 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 composited and analyzed for tritium on a quarterly basis. The results are presented in Table 8. Naturally occurring potassium-40 was measured in sixteen of the samples with an average concentration of 106 pCi/£ and a range of 65.1 to 234 pCi/£. No other gamma emitters were detected. Radiochemical analysis of the samples detected no iodine-131 when analyzed to levels well below the required sensitivity (LLD). Tritium was measured in sixteen out of the twenty-four quarterly composite samples. The average tritium activity for all the indicator stations was 411 pCi/£ with a range of 150 to 820 pCi/£. The 820 pCi/£ sample (Station Intake) was confirmed by reanalysis. The average tritium activity of Surry Discharge was 450 pCi/£ with a range of 420 to 490 pCi/£. For the control stations (Chickahominy and Scotland Wharf) the average concentration was 280 pCi/£ with a range of 140 to 440 pCi/£. Except for the one high sample (820 pCi/£) from the Surry Station Intake location, the tritium activity of the indicator locations compared well with the control locations. All of the samples were analyzed to activity levels well below the required lower level of detection (2000 pCi/£). 39 I I I I I I I I .. I I I I I I I I Monthly samples of river water are also collected by the Commonwealth of Virginia for the state split sampling program. Results of the gamma spectrometry and tritium analysis on these samples are presented in Table 9. Except for naturally occurring potassium-40, all gamma emitting radionuclides were below their respective lower level of detection. Potassium-40 was measured twelve times with an average activity of 79 pCi/£ and a range of 45 to 106 pCi/£. The average tritium activity for the four quarterly samples collected at Surry Discharge location was 613 pCi/£ and a range from 120 to 1100 pCi/£. The attached trend graphs provides a comparison of tritium activity measured in the downstream sample (Surry Discharge) and in the upstream control location (Scotland Wharf). As expected, the grab samples taken from the Surry Discharge Canal by VEPCO personnel measured the discharge of tritium from the station. The average concentration of tritium activity in samples taken from liquid prior to release from the station was 500 pCi/£. This compares well with the average of 613 pCi/£ from the state split samples and 450 pCi/£ from the VEPCO grab samples of the discharge canal. Two additional graphs are provided which draw comparisons with the quarterly tritium results of the state split and VEPCO environmental samples of the Station Discharge and samples taken prior to release. The results from the VEPCO grab samples compare well with the levels of tritium projected from in plant samples except for the fourth quarter results. The state samples which are taken several times during the day and then composited for a quarterly analysis, compared well with the elevated releases made during the fourth quarter. Variations between the samples may be due to the sampling methodology. The frequency of the composite sampling done for the state split environmental 40 I I 19 I I I I I I .. I I I I I I I I program should result in a .more accurate sample of the environmental discharge of radioactive liquids. Variations may also be the result of the low activity level of the samples. The required lower level of detection for tritium is 2000 pCi/£. The water in the discharge canal is further diluted by the river water beyond the discharge structure. Excluding the one high sample from the Station Intake location the average tritium concentration in the samples taken downstream of the station (265 pCi/£) compare well with samples taken at the upstream control location (280 pCi/£). 41

TRITIUM IN RIVER WATER 100000

Scotland Wharf .... ---o--Surry Discharge 1 ... >, ... ... \t~ ::::, en 10000 \ 0 N () 11 C. a, > ' I ' 0 ' -,, ... a, -*---*-0 1000 I 7' ' ' I " I \ a I \ I \ , C. . I .. . -I , I \ .---u-u_ " ' I I -I \ , I \ "-I 1/ .\ ' ' , I ' -... c, \ . *~ * . 11 1\ I \ _t\ o-..., J
0 ',\ \_ I'\ o* -7 \ V ... '-, ----,. , ~v ... , v' -V ' r-\ I 'O '\./
I 6 . ---100 I I I I I I
I I I I I I I I I I I I I I 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 Years

-.+::, w -------------10000 >, .... .... ::::, en 0 () a. Q) > .... Q) = 1000 :::: 0 a. 100 RIVER WATER TRITIUM-1988 STATE SPLIT VS. STATION EFFLUENT ' Station Discharoe ... ... -.... a.,-... Scotland Wharf Station Effluent -i----a--___. a --1' / I 1' / / I / / / / , I I ~/ II-~-----7 ...... ], ................. ,!' .. .. **-****-....... -..... .._ ....* , ----1 ........ / ......... / ........ ... .. / ............. / .,...,, .... __ I/ ... _ ?*-**-*-**-***. --~ 7 ,* -... 1 .......... . . . . -1st Qtr. 2nd Qtr. 3rd Qtr. 4th Otr. --

10000 >,. .... .... ::::, en 0 u CL G) > .... G) -1000 ::::: 0 CL 100

RIVER WATER TRITIUM-1988 VEPCO VS. STATION EFFLUENT Station Discharoe . _ .........

C .. ***-Scotland Wharf Station Effluent -""" ---a--** .' , ,,' , . , , , ./" , , L.L.... .,,' ./ , .. _...,*r.---

- -.. _ .........

---i / ....... .......... ~-****** .......... -J ************* 1******~ .................................. 1 -1st Qtr. 2nd Qtr. 3rd Otr. 4th Otr. -- ------------TABLE 7 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION SURRY COUNTY, VIRGINIA DOCKET NO. 5-280-281 JANUARY 1 to DECEMBER 31, 1988 ANALYSIS AND LOWER LIMIT MEDIUM OR PATHWAY TOTAL NUMBER OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN SAMPLED OF ANALYSES DETECTION MEAN NAME (UNIT OF MEASUREMENT) PERFORMED (LLD) (1) RANGE DISTANCE AND DIRECTION River Water (a) Gamma 48 (pCi/£) K-40 48 107(14/36) NN (65.1-234) Tritium 24 2000 370(12/20) SD (Quarterly) (140-820) River Water (b) Gamma 24 pCi/£ -State Split K-40 24 79.2(7/12) SD (60.0-106) Tritium 8 2000 613(4/4) SD (120-.1100) (1) ( a) ( b) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979. Analyses for monthly and bi-monthly samples listed in Table B. Monthly State Split analyses presented in Table 9. MEAN RANGE 158(5/6) (70.8-234) 450(3/4) (420-490) 79.2(7/12) (60.0-106) 613(4/4) (120-1100) NUMBER OF CONTROL LOCATION NONROUTINE MEAN REPORTED RANGE MEASUREMENTS 96.0(2/12) 0 (87.0-105) 288(4/4) 0 (220-440) 79.1(5/12) 0 (45.1-103) 267(3/4) 0 (130-360) -- -+:> O'\ ---------~ -VIRGINIA CONCENTRATIONS OF GAMMA STATION DATE Be-7 K-40 JANUARY CHIC 01/27/88 <30 71. 0 +/- 35.6 HIP 01/27/88 <30 <40 NN 01/27/88 <30 (60 SD 01/27/88 <30 <60 SI 01/27/88 <30 <50 SW 01/27/88 <30 <50 FEBRUARY so 02/16/88 <30 <60 SW 02/16/88 <50 <100 MARCH CHIC 03/24/88 <40 <100 HIP 03/17/88 <20 <50 NN 03/17/88 <30 156 +/- 44 SD SI SW APR IL SD SW * ( a) 03/17 /88 <40 <70 03/17/88 <40 <100 03/24/88 <40 <90 04/19/88 <30 65.1 +/- 04/19/88 <30 All other gamma emitters were <LLD. Confirmed by recount. <60 26.6 TABLE 8 (Page 1 of 3) POWER -SURRY -1988 EMITTERS* AND TRITIUM pCi/£ +/- 2 Sigma 1-131 Cs-137 <0.5 <3 <0.4 <3 <0.4 <4 <0.4 <4 <0.6 <3 <0.3 <3 <0.2 <3 <0.2 <5 <0.2 <5 <0.3 <3 <0.4 <3 <0.3 <4 <0.4 <4 <0.2 <5 <0.3 <3 <0.2 <4 -------IN RIVER WATER Ba-140 La-140 TH-228 H-3 <20 <7 <7 440 +/- 90 <20 <7 <6 480 +/- 120 <20 <8 <6 350 +/- 120 <20 <7 <7 440 +/- 90 <20 <8 <6 820 +/- 120 ( a) <20 <7 <7 390 +/- 120 <10 <6 <7 <20 <8 <9 <20 <6 <9 <10 <5 <5 <10 <7 <7 <20 <6 <9 <20 <7 <7 <20 <6 <10 <10 <5 <6 <10 <6 <7

TABLE 8 (Page 2 of 3) VIRGINIA POWER -SURRY -1988. 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 MAY CHIC 05/12/88 <30 <50 <0.4 <3 <10 <6 <6 220 +/- 110 HIP 05/11/88 <30 <60 <0.4 <4 <20 <7 <7 <100 NN 05/11/88 <40 70.8 +/- 33.9 <0.4 <4 <20 <6 <10 <100 SD 05/11/88 <30 <50 <0.3 <3 <10 <6 <5 420 +/- 110 SI 05/11/88 <30 55.2 +/- 24.4 <0.4 <3 <10 <5 <5 150 +/- 110 SW 05/12/88 <20 <40 <0.2 <3 <10 <5 <5 140 +/- 70 ........ JUNE SD 06/21/88 <30 <60 <0.4 <4 <10 <7 <6 SW 06/21/88 <30 <50 <0.2 <3 <10 <5 <6 JULY CHIC 07/07/88 <40 <90 <0.4 <4 <20 <6 <7 270 +/- 80 HIP 07 /06/88 <60 <200 <0.4 <7 <20 <10 <10 280 +/- 100 NN 07/06/88 <40 135 +/- 46 <0.4 <6 <20 <8 <10 <100 SD 07/07/88 <30 <60 <0.4 <3 <10 <6 <6 <200 SI 07 /06/88 <70 <200 <0.4 <8 <30 <10 <20 <200 SW 07/07/88 <30 <60 <0.4 <4 <20 <6 <7. <200 AUGUST SD 08/16/88 <40 <100 <0.2 <4 <10 <6 <8 SW 08/16/88 <30 <50 <0.3 <3 <9 <5 <5

All other gamma emitters were <LLD.

TABLE 8 (Page 3 of 3) VIRGINIA POWER -SURRY -1988 CONCENTRATIONS OF GAMMA EMITTERS*

AND TRITIUM IN RIVER WATER pCi/£ +/- 2 Sigma STAT ION DATE Be-7 K-40 1-131 Cs-137 Ba-140 La-140 TH-228 H-3 SEPTEMBER CHIC 09/08/88 <30 <60 <0.3 <4 <10 <5 <7 HIP 09/07/88 <60 <200 <0.2 <6 <30 <10 <10 NN 09/07/88 <30 194 +/- 37 <0.3 <3 <10 <7 <6 SD 09/08/88 <30 65.4 +/- 33.4 <0.3 <4 <10 <5 <7 +'> SI 09/07 /88 <30 80.1 +/- 34.8 <0.3 <3 <10 <7 <7 CX> SW 09/08/88 <40 <100 <0.3 <5 <20 <8 <8 OCTOBER SD 10/18/88 <30 116 +/- 33 <0.4 <4 <9 <5 <6 SW 10/18/88 <20 105 +/- 27 <0.3 <3 <IO <5 <5 NOVEMBER CHIC 11/10/88 <40 <80 <0.4 <5 <20 <7 *. <IO 220 +/- 80 HIP 11/09/88 <30 88.0 +/- 30.9 <0.4 <3 <10 <7 <6 220 +/- 120 NN 11/09/88 <30 234 +/- 33 <0.5 <3 <10 <5 <5 <200 SD 11/10/88 <30 85.3 +/- 30.0 <0.3 <3 <10 <5 <6 490 +/- 80 SI 11/09/88 <40 <100 <0.4 <4 <20 <7 <7 260 +/- 80 SW 11/10/88 <50 <200 <0.4 <6 <20 <10 <10 <200 DECEMBER SD 12/20/88 <20 87.0 +/- 29.8 <0.5 <3 <9 <4 <6 SW 12/20/88 <30 87.0 +/- 29.7 <0.3 <4 <10 <4 <6

All other gamma emitters were <LLD.

-..i:,, \.0 ---MONTH COLL. DATES 1988 SCOTLAND WH. (SW} January 01/15/88 February 02/15/88 March 03/15/88 April 04/15/88 May 05/15/88 June 06/15/88 July 07/15/88 August 08/15/88 September 09/15/88 October 10/15/88 November 11/15/88 December 12/15/88 Average+/- 2 s. d. ----------Be-7 <50 <40 (40 <50 <70 (50 <70 <50 <50 (40 <50 <30 VIRGINIA POWER -SURRY -1988 CONCENTRATIONS OF GAMMA EMITTERS* AND TRITIUM IN RIVER WATER pCi/£ +/- 2 Sigma -STATE SPLIT K-40 I-131 Cs-137 Ba-140 La-140 45.1 +/- 24.6 <10 <3 <200 (a) <60 ( a) <50 <5 <3 <60 ( a) <20 (a) <40 (9 <3 <70 f: I <30 i: J <60 <7 <3 <100 <40 <100 (20 ( a) <5 <200 ( a <90 (a) <60 <5 <4 <80 i: l <40 f: 97.5 +/- 45.0 (4 (6 <100 <40 60.4 +/- 31.6 <3 <4 <60 ( a) <30 (a) 1 03 +/- 3 3 <7 <4 <90 ! : i <40 ! : i 89.3 +/- 32.9 <2 <4 <30 <20 <50 <4 <4 <60 ( a) <30 (a) (60 <4 (3 <40 ( a) <20 (a) 79.1 +/- 50.2 Th-228 (6 <6 <5 <7 <8 (8 <9 <8 <7 <6 (6 <6 SURRY DIS. (SD) January 01/15/88 (50 63.4 +/- 26.1 <10 <3 <100 ( a) <60 ( a) <5 February 02/15/88 <40 <50 <5 <3 <50 ( a) <30 ( a) <5 March 03/15/88 <60 <90 <9 <4 <100 ( a) <50 ( a J <B April 04/15/88 <40 65.8 +/- 26.1 <B <3 <100 ( a) <50 ( a <6 May 05/15/88 (60 <60 <20 (a) <4 <200 f: l <70 f: l <7 June 06/15/88 (50 77.6 +/- 35. 0 <5 <4 <90 <40 <B July 07/15/88 (50 93.3 +/- 35.8 <4 <4 <70 ( a) <20 (a) <8 August 08/15/88 (40 60.0 +/- 28.4 (2 <3 (50 (a~ <20 t: I <7 September 09/15/88 <70 <200 <8 <5 <100 ( a <50 (9 October 10/15/88 <40 106 +/- 43 <2 <4 <40 ( a) <20 (a <7 November 11/15/88 <60 <200 <5 <5 <90 (a) <30 (a~ <8 December 12/15/88 <40 88.1 +/- 26.4 <4 (4 <50 ( a) <20 ( a <6 Average+/- 79.2 +/- 34.6 2 s. d.

All other gamma emitters were <LLD. (a) LLD not met because of late receipt of sample from the State of Virginia.

--H-3 130 +/- 70 <120 360 +/- 130 310 +/- 120 267 +/- 242 420 +/- 80 120 +/- 90 810 +/- 130 1100 +/- 100 613 +/- 861 I I I I I I I I I I I I I I I I I 2. Well Water Well water is collected from the four indicator locations during the months of March, June, September and December. Ground water is not considered to be affected by station operations since there are no discharges made to this pathway. The results of the analysis of well water samples are preseted in Table 11. The samples were analyzed by gamma spectroscopy and indicated that no gamma emitting radionuclides were present. Also, the analysis indicated that no naturally occurring gamma emitting radioisotopes were present. All samples were analyzed to well below the required lower level of detection for gamma emitting radionuclides. Tritium was measured in ten of the sixteen samples with an average activity of 328 pCi/£ and a range of 180 pCi/£ to 910 pCi/£. As indicated by the trend graph, the Surry Station sample continues to indicate a higher tritium concentration than the other indicator locations. Large variations between the quarterly samples from the Surry Station indicate higher than normal positive results one quarter, then no positive indication of tritium from the next quarterly sample. Samples from the other indicator locations indicate results either below the lower limit of detection or positive results above the detection level with a high degree of analysis error. The results from the locations other than the Surry Site indicate very little influence of tritium contamination of ground water. 50 ->,. ... ... ::::, en 0 u, C, t-' C. Q) > ... Q) -::::; u C. -------------TRITIUM IN GROUND/WELL WATER* 10000 [] Station-BC -* Station-HI A a Station-JMTN --0-Station-SS 1000 -........... ., \. ., \. A , ,, \ n / \ 7 \ I\ / \. / \ / .. \ L \ 7 A\ /~ 100 't ..... / ~(x)~ --------=--. ......... -:.:::0 ----v-... -(x) __ (x) (x) -(x) -(x) == (x) -(x) (x) (X) -10 1986 . 1987 * (x) Less than lower limit of detection (LLD) . 1988 1989 ----__J

TABLE 10 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION SURRY COUNTY, VIRGINIA ANALYSIS AND LOWER LIMIT MEDIUM OR PATHWAY TOTAL NUMBER OF SAMPLED OF ANALYSES DETECTION (UNIT OF MEASUREMENT) PERFORMED . (LLD) (1) Well Water (pCi/£) Tritium K-40 16 2000 16 r ALL INDICATOR LOCATIONS MEAN RANGE 328(10/16) (180-910) -(0/16) DOCKET NO. 5-280-281 JANUARY 1 to DECEMBER 31, 1988 LOCATION WITH HIGHEST MEAN NAME MEAN DISTANCE AND DIRECTION RANGE ss N/A 715(2/4) (520-910) N/A (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. CONTROL LOCATION MEAN RANGE NONE NONE NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 --

TABLE 11 VIRGINIA POWER -SURRY-1988 CONCENTRATIONS OF TRITIUM AND GAMMA EMITTERS*

IN WELL WATER pCi/£ +/- 2 Sigma DATE STATION Be-7 K-40 I-131 Cs-137 Ba-140 La-140 Th-228 H-3 FIRST QUARTER 03/22/88 BC <40 <100 <0.2 <5 <20 <7 <9 260 +/- 80 03/22/88 HIR <50 <90 <0.2 <5 <20 <6 <10 200 +/- 110 03/22/88 JMTN <30 <50 <0.2 <3 <10 <6 <6 180 +/- 110 03/22/88 ss <30 <60 <0.2 <4 <10 <5 <7 910 +/- 80 SECOND QUARTER 06/21/88 BC <30 <60 <0.2 <3 <20 <8 <7 <110 (.Tl 06/21/88 HIR <40 <100 <0.2 <5 <20 <8 <8 <110 w 06/21/88 JMTN <50 <80 <0.2 <5 <20 <9 <10 <110 06/21/88 ss <30 <50 <0.2 <3 <10 <6 <6 <110 THIRD QUARTER 09/20/88 BC <50 <100 <0.2 <6 <20 <9 <10 280 +/- 80 09/20/88 HIR <60 <200 <0.2 <7 <20 <8 <10 220 +/- 120 09/20/88 JMTN <40 <100 <0.2 <5 <20 <6 <9 320 +/- 130 09/20/88 ss <30 <50 <0.3 <4 <10 <6 <6 520 +/- 80 FOURTH QUARTER 12/20/88 BC <40 <80 <0.2 <4 <10 <6 '<10 180 +/- 80 12/20/88 H IR <30 <50 <0.2 <4 <10 <4 <6 <100 12/20/88 JMTN <30 <80 <0.2 <4 <10 <4 <7 210 +/- 80 12/21/88 ss <30 <50 <0.2 <3 <9 <4 <6 <100 ~;

All other gamma emitters were <LLD.

I I I I I I I I I I I I I I I I C. Aquatic Exposure Pathway 1. Silt Silt samples or river sediment were taken to determine the build up of radionuclides in the environment due to the operation of the power station. The activity in the silt comes from the precipitation of radionuclides in the waste discharges and the subsequent dispersion of material by the current. Although the silt itself does not constitute a direct dose pathway for humans, the concentration of radionuclides on the river bottom provides a good indication of the dispersion effects of discharge to the river. Buildup of radionuclides in silt may indirectly lead to increasing activity levels in clams, oysters and fish. Silt samples were collected semiannually during March and September from each of six locations. A dredge is used to collect each sample from approximately the same location and is washed thoroughly after each use. copy. The samples are individually bagged and analyzed by gamma The results are presented in Table 13. A number of man-made and naturally occurring radioisotopes were measured. At the indicator sample locations cobalt-58 was measured with an average activity of 62.4 pCi/kg (dry weight) and a range of 46.1 to 78.6 pCi/kg (dry weight). There was no cobalt-58 measured at the control location (Chickahominy). Cobalt-60 was measured in the two samples at the control station, Chickahominy, with an average activity of 244 pCi/kg (dry weight) and a range of 218 to 269 pCi/kg (dry weight). The indicator locations measured cobalt-60 at an average of 349 pCi/kg (dry weight) and a range of 81.6 to 728 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. 54 I I I I I I I I I I I I I I I I Cesium-134 was measured in all locations except Newport News with the highest location at Surry Intake. Cesium-134 was measured in one sample at Surry Intake with an activity of 134 pCi/kg (dry weight). Cesium-137 was measured in all samples, with the highest activity at Surry Intake. The average at this location was 827 pCi/kg (dry weight) and a range of 707 to 946 pCi/kg (dry weight). The average from the ten indicator samples was 461 pCi/kg (dry weight) and a range of 88.9 to 946 pCi/kg (dry weight). The average from the control location (CHIC) was 776 pCi/kg (dry weight) with a range of 743 to 808 pCi/kg (dry weight). The results of analysis of the samples as presented in the trend graphs, indicate that all the man made radionuclides show a decreasing trend. The decrease was most notable in the Surry Discharge samples. This correlates well with the declining radionuclide activity in the station effluent samples. Data from the semiannual Radioactive Effluent Report indicates that the activity in the 1988 liquid effluent was approximately half the activity of the 1987 liquid effluent. 55 ->, .. .. :::, rn c..n 0 CJ) u CL G) > a .._ 0 CL -------------1000 . . . . .. : . ..... JJ. ~\ .. . . * . . .. *'/;' ') ... .... * '\ *-COBALT-58 IN SILT ! I . .

I : . . . . . . : . . . . ! . . . . . . . . . . . . . . I . . * * * . . }-----] \ : * -. I .. _ ,,.*** _.---11, . . * * * . . * . * . I . r , . * . . . * . . * . . .
I l .
I . * .
r--1*---i ~---*-4 ~--*-*~ J, ' T l ...... ' (x) (x) JxL (x) J~t_ ***-.... .-,.~ -..._,,_ ' I .. (x) '~; +--+---t---+--+--+---ir----t--+---+---t---+--+---1---

-(x) -(x) -"'i!ld.~,-1

t *'-(x) --0--Hog Island ,_ -.............

Station Intake I~ ****D**

Station Dis. 10-t--r,--i,---r--i--,..--+,---r--+,--r--i--r--t--..--+--r--+--r--+---. .--1--..--+-"T,--l---..---1~..--~....-4--

........ -i--.--+---.--I 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 Years -- -~-------------I --COBALT-60 IN SILT 100000 . --o--Hog Island ................ Station Intake ------* Station Discharge 10000 ) ... . .... >-. ... , ... :ll en , -_, , I ' I 0 )*, , ... , J I , I Ul () --.J a. Cl) > 1000 ,, ' ,* I I -...... "11 , l > I , ' ,, ' , I , ' ,.I .... ' '

J -I ' I ' I , ' ' I ' I , '* ,, I ! '. I .' ' I , , I . . . . . -. . . . , ., ' I ' I .. I .... -~ I a .:w:: .. *' ' -. *~ . ,, ... .... ,* I.' ,,, ./ ,I \ I I ....... I I Ji ' I ' ; .._ 0 a. , fl '~ I/ ,* I' \ 1 ; ; ;. *, ., 1, ' ! i' "\ I .............

I \\\ i / ) J .. \ ' !I J . . . I \ .-*~' J I \\' II , -,~, II I ' *' I _.,,.~ ' I '~ ' ' 100 I F ,.,, ... ' ,, ., { "IJ, I~ /)' > *---h .. ,, 70 '"' . -\~ I F -.;,,

I ,~ "1 I 10 . . . . . . . . 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 Years

->,.* .. .. ::I u, 0 u, C,) co a. Cl) > Cl .:ii: :::::: 0 a. --10000 1000 100 10 71 . -------------CESIUM-134 IN SILT l I I l . ---o--Hog Island -.. _ .......... , Station Intake ,... -------* Station Dis. .... t

p\ ,J 1-----1 *,. i, \', ' .. ,. .. ,. . * -. ,. h ' '* 1;' I \\ ' ,. Ii,' ,.,._ .. .... .... ' .-----1 Ji \\ ...... _,, ;. ; .....-l , ... ' . ,' Ii \\ '"u' T I ....... , ... ,," ... . )~ .. '* I '* ,* ., ~;*~--j) I I ** , ... 0 ,,, X \ /, ' I ' \ I ..* I ' . , .... ' ' i ) . ,.,. , ... ,~ t( \ \ ' /, ') ' ' :,c*' , ' ' *' /I a. '* '* ,' ,,J I ' , ..... ' \ / ;; '-{' ** ' ,;. ..... '1 i ,~, \ ' ' 4 ..---i .........

,~ *-4 ' I I ' , .. ' *1 I I . . 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 Years

CESIUM-137 IN SILT 10000 I ' / \ I ) / \ V ~. I .~ .,\., ,0 \ I l"i / 1 / y I I ) \. , \ \ j / \ Ii \" J I *L " /. , \. / ' ' .... \ \ ' I I :-,.... \ I I \A I\ I "" ' / I ' I' " , ...... , \ \' ....)r"j I ,~ I ){ \/ /* I I' \ \ \ V I 'I-... I \ A I \ I \ \\ I\ I/ I ' / \ I \ I \ 5 rn u, I I.D 0 C,) 1000 11 ...... 0 , H* I ' ,J , ,l * ,, *J m Hog Island --Station Intake -a Station Dis. -CHIC 100 . . . I 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989

-CJ) 0 -------------- TABLE 12 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1988 ANALYSIS AND LOWER LIMIT MEDIUM OR PATHWAY TOTAL NUMBER OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION SAMPLED OF ANALYSES DETECTION MEAN NAME MEAN MEAN (UNIT OF MEASUREMENT) PERFORMED (LLD) (1) RANGE DISTANCE AND DIRECTION RANGE RANGE Silt Gamma Spec 12 (pCi/kg dry) Be-7 12 1139(5/10~ (463-2260 SI 1491(2/2) (722-2260) 549(1/2) K-40 12 SI 11927(10/10~ (4730-16400 15100(2/2) (14800-15400) 14850(2/2) (14100-15600) Co-58 12 62.4(2/10) SI (46.1-78.6) Co-60 12 349(10/10) (81.6-728) SI Cs-134 12 150 121(4/10) SI (110-134) Cs-137 12 180 461(10/10) SI (88.9-946) Ra-226 12 1669(10/10) CHIC (1110-2380) Th-228 12 905(10/10~ CHIC (658-1170 (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. 78.6(1/2) -(0/2) 604(2/2) 244(2/2) (480-728) (218-269) 134(1/2) 97.9(1/2) 827(2/2) 776(2/2) (707-946) (743-808) 2460(2/2) 2460(2/2) (2400-2520) (2400-2520) 1260(2/2) (1080-1440) 1260(2/2) (1080-1440) --NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 -en ...... -------------STATION CHIC HIP COLLECTION DATE 03/24/88 03/17/88 Be-7 549 +/- 194 811 +/- 199 K-40 15600 +/- 1600 13000 +/- 1300 Mn-54 <20 <20 Co-58 <20 46.1 +/- 20.4 Co-60 218 +/- 27 586 +/- 59 Cs-134 97.9 +/- 24.2 119 +/- 24 Cs-137 808 +/- Bl 686 +/- 69 Ra-226 2400 +/- 340 1510 +/- 360 Th-228 1440 +/- 140 887 +/- 89

All other gamma emitters were <LLD. TABLE 13 (Page 1 of 2) VIRGINIA POWER -SURRY-1988 CONCENTRATIONS OF GAMMA* EMITTERS IN SILT pCi/kg (dry)+/- 2 Sigma NN POS 03/17/88 03/17/88 <200 1440 +/- 270 11700 +/- 1200 16400 +/- 1600 <20 <30 <20 <30 81.6 +/- 19.5 617 +/- 62 <30 119 +/- 27 204 +/- 26 801 +/- 80 1300 +/- 370 2260 +/- 440 658 +/- 66 1150 +/- 110 SD SI 03/17/88 03/17/88 <200 2260 +/- 300 4730 +/- 470 15400 +/- 1500 <20 <30 <20 78.6 +/- 25.4 106 +/- 21 728 +/- 73 <20 134 +/- 25 88.9 +/- 10.4 946 +/- 95 1270 +/- 280 2380 +/- 460 906 +/- 91 1170 +/- 120 --

STATION CHIC HIP COLLECTION DATE 09/08/88 09/08/88 Be-7 <500 <400 K-40 14100 +/- 1400 10400 +/- 1600 0) N Mn-54 <40 <40 Co-58 <50 <50 Co-60 269 +/- 43 145 +/- 40 Cs-134 (50 <40 Cs-137 743 +/- 74 165 +/- 36 Ra-226 2520 +/- 630 1110 +/- 460 Th-228 1080 +/- 110 728 +/- 73

All other gamma emitters were <LLO. -----TABLE 13 (Page 2 of 2) VIRGINIA POWER -SURRV-1988 CONCENTRATIONS OF GAMMA* EMITTERS IN SILT pCi/kg (dry)+/- 2 Sigma NN POS 09/09/88 09/09/88 <300 (400 13300 +/- 1300 11500 +/- 1200 <30 <30 <30 <40 104 +/- 29 98.9 +/- 28.8 <30 <40 356 +/- 39 137 +/- 33 1390 +/- 370 1380 +/- 510 694 +/- 69 842 +/- 84 -----SD SI Average 09/08/88 09/09/88 +/- 2 s.d 463 +/- 235 722 +/- 326 1041 +/- 1379 8040 +/- 800 14800 +/- 1500 12414 +/- 6828 <30 <40 <30 <40 62.4 +/- 46 547 +/- 55 480 +/- 48 332 +/- 483 110 +/- 27 <50 116 +/- 27 522 +/- 52 707 +/- 71 514 +/- 615 1850 +/- 410 2240 +/- 530 1801 +/- 1055 995 +/- 100 1020 +/- 100 964 +/- 454 I I I I I I I I I I I I I I I I -----------------------------------

2. Shoreline Sediment Unlike river bottom silt, the shoreline sediment can provide a direct dose to humans. Buildup of radionuclides along the shoreline may provide a source of direct exposure for those using the shoreline for commercial or recreational purposes.

Samples were taken in February and August at Hog Island Reserve and Burwell's Bay. The samples were analyzed by gamma spectroscopy. The results are presented in Table 15. The analytical results indicated the predominance of three naturally occurring radioisotopes. Potassium-40 was measured in all samples at an average concentration of 4170 pCi/kg (dry weight) and a range of 2450 to 5900 pCi/kg (dry weight). Radium-226 was measured in two of the four samples with an average concentration of 426 pCi/kg (dry weight) and a range of 394 to 458 pCi/kg (dry weight). Thorium-228 was also measured in two samples with an average of 80.0 pCi/kg (dry weight) and a range of 75.4 to 84.6 pCi/kg (dry weight). Cesium-137 was the only manmade isotope found and was measured in one sample from Burwell's Bay. The activity of the sample was 16.3 pCi/kg (dry weight). The sample results for cesium-137 are lower than in previous years and indicate a downward trend in activity. The lower values in the shoreline samples correlates well with the decreasing trends in the river bottom silt and in the activity released in the station effluents. 63 -O'I .p. -------------TABLE 14 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION SURRY COUNTY, VIRGINIA ANALYSIS AND LOWER LIMIT MEDIUM OR PATHWAY TOTAL NUMBER OF SAMPLED OF ANALYSES DETECTION (UNIT OF MEASUREMENT) PERFORMED (LLD) (1) Shoreline Sediment Gamma Spec 4 (pCi/kg dry) K-40 4 Cs-137 4 180 Ra-226 4 Th-228 4 ALL INDICATOR LOCATIONS MEAN RANGE 4170(4/4) (2450-5900) 16.3(1/4) 426(2/4) (394-458) 80.0(2/4) (75.4-84.6) DOCKET NO. 5-280-281 JANUARY 1 to DECEMBER 31, 1988 LOCATION WITH HIGHEST MEAN NAME MEAN DISTANCE AND DIRECTION RANGE HIR 5535(2/2) (5170-5900) BURNELL'S 16.3(1/2) BURWELL'S 426(2/2) (394-458) HIR 84.6(1/2) (1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision l, November 1979. CONTROL LOCATION MEAN RANGE NONE NONE NONE NONE NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 -- -m (.J1 ----STATION HIR COLLECT ION DATE 02/23/88 Be-7 <100 K-40 5170 +/- 520 Co-60 <10 Cs-134 <10 Cs-'137 <10 Ra-226 <200 Th-228 <2 0 -------TABLE 15 VIRGINIA POWER -SURRY-1988 CONCENTRATIONS OF GAMMA EMITTERS* IN SHORELINE SEDIMENT pCi/kg (dry) +/- 2 Sigma BURWELL'S HIR BU RWE LL Is 02/23/88 08/23/88 08/23/88 <70 <100 <100 3160 +/- 320 5900 +/- 590 2450 +/- 240 <8 <10 <20 <8 <10 <10 16.3 +/- 8.0 <10 <20 394 +/- 147 <200 458 +/- 224 75.4 +/- 7.7 84.6 +/- 8.5 <30

All other gamma emitters searched for were <LLD. ----AVERAGE +/- 2.s.d. 4170 +/- 3260 16.3 +/- 8.0 426 +/- 91 80.0 +/- 13.0 I I 19 I I I I I I I I I I I I I I D Ingestion Exposure Pathway 1. Milk Milk samples are an important indicator for measuring the affect of radioactive iodine in particular, and other radionuclides in airborne releases from the power station. The dose consequence to man is from both a direct and indirect exposure pathway. The direct exposure pathway is from the inhalation of radioactive material.

The indirect exposure pathway is from the grass-cow-milk pathway. In this pathway radioactive material is desposited on the plants consumed by the dairy animals. The radioactive material is in turn passed on to man via the 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 sixty 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 1300 pCi/£ and the range was 1140 to 1460 pCi/£. The average measurement for the 48 indicator samples was 1347 pCi/£ with a range of 1020 to 1570 pCi/£. Cesium-137 continues to be detected on an occasional, infrequent basis. This is very consistent with historical data and does not indicate a positive trend. Cesium-137 has typically been detected since 1983, in one to four out of sixty samples obtained and found to be in the range of 5.2 to 9.8 pCi/£. The data from 1988 identified two samples with an average activity of 7.5 pCi/£ and a range of 6.3 to 8.8 66 I I -I I I I I I I I I I I I I I pCi/£. These results are very close to the lower level of detection and are well below the required detection level of 18 pCi/£. This occasional detection of cesium-137 may be attributable to past atmospheric atomic weapons testing (global fallout) rather than station operation. The twelve milk samples collected in participation with the state split sampling program, Lee Hall, Epps and Colonial Parkway were also analyzed for strontium-89 and strontium-90. Strontium-89 was not detected in any of the samples. Strontium-90 was observed in ten of the twelve indicator milk samples with an average activity of 2.45 pCi/£ and a range of 0.71 to 4.5 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/£. 67 -°' co -----------TABLE 16 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION SURRY COUNTY, VIRGINIA ANALYSIS AND LOWER LIMIT MEDIUM OR PATHWAY TOTAL NUMBER OF SAMPLED OF ANALYSES DETECTION (UNIT OF MEASUREMENT) PERFORMED (LLD) (1) Milk Gamma Spec 60 (pCi/£) K-40 60 1-131 60 1 Cs-137 60 10 Sr-89 12 Sr-90 12 ALL INDICATOR LOCATIONS MEAN RANGE 1347(48/48) (1020-1570) -(0/48) 7.53(2/48) (6.30-8.76) -(0/12) 2.50(10/12) (0.71-4.5) DOCKET NO. 5-280-281 JANUARY 1 to DECEMBER 31, 1988 LOCATION WITH HIGHEST MEAN NAME MEAN DISTANCE AND DIRECTION RANGE CP 1403(12/12) (1270-1570) N/A N/A CP 8.76(1/12) N/ A N/A LEE HALL 2.5(3/4) (0.64-4.5) (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. ----CONTROL LOCATION MEAN RANGE 1300(12/12) ( 1140-1460) -(0/12) -(0/12) -(0/0) -(0/0) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 - ---MONTH JANUARY FEBRUARY MARCH APRIL State split -NUCLIDE Sr-89 Sr-90 K-40 Cs-137 I-131 Sr-89 Sr-90 K-40 Cs-137 I-131 Sr-89 Sr-90 K-40 Cs-137 I-131 Sr-89 Sr-90 K-40 Cs-137 I-131 ------TABLE 17 (Page 1 of 3) VIRGINIA POWER -SURRY -1988 ----CONCENTRATIONS OF STRONTIUM-89 AND -90 AND GAMMA EMITTERS** IN MILK pCi/£ +/- 2 sigma LEE HALL* <2 (a) 0.64 +/- 0.36 (a) 1290 +/- 130 <4 <0.2 1370 +/- 140 <6 <0.2 1020 +/- 100 <7 <0.2 <6 ( a) <2 (a) 1340 +/- 130 <4 <0.3 EPPS* <2 ( a) 2.4 +/- 0.6 (a) 1060 +/- 110 <5 <0.3 1200 +/- 120 <4 <0.3 1350 +/- 140 <4 <0.3 <5 (a) 0.73 +/- 0.51 (a) 1500 +/- 150 <4 <0.3 CP <2 (a) 2.9 +/- 0.6 (a) 1320 +/- 130 <4 <0.2 1290 +/- 130 <4 <0.2 1370 +/- 140 <4 <0.3 <3 (a) <O. 9 ( a) 1330 +/- 130 <4 <0.3 WMS 1230 +/- 120 <6 <0.3 1250 +/- 120 <4 <0.2 1250 +/- 130 <4 <0.3 1260 +/- 130 <4 <0.2 * ** (a) All other gamma emitters were LLD. Strontium-89 and 90 sample analysis done on a quarterly composite of state split samples and Colonial Parkway(CP) sample at the request of the State of Virginia. --JDKS 1310 +/- 130 6.30 +/- 3.14 <0.2 1350 +/- 130 <4 <0.3 1170 +/- 120 <6 <0.3 1310 +/- 130 <4 <0.2 --....J 0 ---------TABLE 17 (Page 2 of 3) VIRGINIA POWER -SURRY -1988 ---CONCENTRATIONS OF STRONTIUM-89 AND -90 AND GAMMA EMITTERS** IN MILK pCi/£ +/- 2 sigma -MONTH NUCLIDE LEE HALL* EPPS* CP WMS MAY JUNE JULY Sr-89 Sr:-90 K-40 Cs-137 1-131 Sr-89 Sr-90 K-40 Cs-137 1-131 Sr-89 Sr-90 K-40 Cs-137 1-131 1350 +/- 140 <4 <0.3 1430 +/- 140 <4 <0.3 <10 ( a) 2.2 +/- 1.3 1450 +/- 150 <6 <0.3 (a) 1110 +/- 110 <4 <0.3 1510 +/- 150 <4 <0.3 <1 ( a) 0. 71 +/- 0:-40 1460 +/- 150 (6 <0.3 ( a) 1280 +/- 130 <4 <0.3 1570 +/- 160 <4 <0.3 <2 ( a) 2.3 +/- 1. 0 1570 +/- 160 <4 <0.3 (a) 1140 +/- 110 <4 <0.3 1360 +/- 140 <4 <0.2 1280 +/- 130 <6 <0.3 AUGUST Sr-89 Sr-90 K-40 Cs-137 1-131 * ** ( a) State split 1480 +/- 150 <5 <0.3 All other gamma emitters were LLD. 1350 +/- 140 <5 <0.3 13-70 +/- 140 <5 <0.3 1350 +/- 130 <4 <0.3 Strontium-89 and 90 sample analysis done on a quarterly composite of state split samples and Colonial Parkway(CP) sample at the request of the State of Virginia. -JDKS 1230 +/- 120 <6 <0.3 1330 +/- 130 <4 <0.3 1320 +/- 130 <5 <0.3 1330 +/- 130 <4 <0.4 - -......., ...... --MONTH SEPTEMBER OCTOBER NOVEMBER DECEMBER State split -NUCLIDE Sr-89 Sr-90 K-40 Cs-137 1-131 Sr-89 Sr-90 K-40 Cs-137 1-131 Sr-89 Sr-90 K-40 Cs-137 1-131 Sr-89 Sr-90 K-40 Cs-137 1-131 ------TABLE 17 (Page 3 of 3) VIRGINIA POWER -SURRY -1988 ----CONCENTRATIONS OF STRONTIUM-89 AND -90 AND GAMMA EMITTERS** IN MILK pCi/£ +/- 2 sigma LEE HALL* 1290 +/- 130 <6 <0.3 <5 (a) 4.5 +/- 1. 8 1430 +/- 140 <4 <0.2 1530 +/- 150 <5 <0.3 1440 +/- 140 <5 <0.3 ( a) EPPS* 1240 +/- 120 <4 <0.3 <2 (a) 0.95 +/- 0.69 1400 +/- 140 <4 <0.2 1390 +/- 140 <5 <0.2 1310 +/- 130 (5 <0.3 ( a) CP 1270 +/- 130 <4 <0.2 <2 (a) 1. 4 +/- 0.6 1460 +/- 150 <6 <0.3 1450 +/- 140 <4 <0.3 1550 +/- 160 8.76 +/- 3.92 <0.3 (a) WMS 1330 +/- 130 <5 <0.3 1460 +/- 150 <4 <0.2 1270 +/- 130 <4 <0.2 1420 +/- 140 <6 <0.3 * ** All other gamma emitters were LLD. Strontium-89 and 90 sample analysis done on a quarterly composite of state split samples and Colonial Parkway(CP) sample at the request of the State of Virginia. ( a) --JDKS 1080 +/- 110 (8 <0.3 1420 +/- 140 <5 <0.2 1420 +/- 140 <5 <0.2 1270 +/- 130 <5 <0.3 I I I I I I I I I I I I I I I .. I 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. As expected, naturally occurring potassium-40 was the nuclide most frequently detected. For the clam samples the average potassium-40 activity was 583 pCi/kg (wet weight) and a range from 255 to 1060 pCi/kg (wet weight). Cobalt-60 was measured in two samples (one from Surry Discharge and one from Hog Island Point) with an average activity of 39.l pCi/kg (wet weight) and a range of 21.1 to 57.1 pCi/kg (wet weight). The activity measured in the 1983 through 1987 clam samples taken at the same locations is comparable with the 1988 results. Cesium-137 was measured in one sample from Surry Discharge with an activity of 14.2 pCi/kg (wet weight). This positive result was 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. No other gamma emitting isotopes, attributable to plant discharges, were detected in any of the samples. An overall decreasing trend of activity in the clam population is evident from the trend graphs provided. 72 I I I I I I I I I I I 'I I I I I For oyster samples the average potassium-40 activity for 15 of the 17 samples was 666 pCi/kg (wet weight) with a range of 400 to 916 pCi/kg (wet weight). This was lower than activity measured in 1987. All other gamma emitters were well below the required LLDs listed in Table 2 with no positive activity detected. One crab sample was collected in June from the Surry Discharge (SD) location and analyzed by gamma spectrometry. Naturally occurring potassium-40 was measured with an activity of 2480 pCi/kg (wet weight) as presented in Table 21. All other gamma emitters were well below the LLDs required in Table 2 with no positive activity detected. Four fish samples (catfish and white perch) were collected during May and October from the same Surry Discharge location (SD). Potassium-40 was measured in all four samples with an average activity of 1575 pCi/kg (wet weight) and a range of 1380 to 1770 pCi/kg (wet weight). The results of gamma spectrometry on these samples are presented in Table 23. Cesium-137 was observed in one of the fish samples with an activ*ity of 17.7 pCi/kg (wet weight). The results from the 1988 fish samples indicated lower cesium-137 activity in comparison to results from recent years. The 1987 samples averaged 24 pCi/kg (wet weight) while in 1986 the samples averaged 45.5 pCi/kg (wet weight). During 1985 cesium-137 was measured in the fish samples at an average of 87.1 pCi/kg (wet weight). All other gamma emitters were well below the.LLDs required in Table 2 with no positive activity detected. 73

COBALT-58 IN CLAM SAMPLES 1000 ,... --o--CHICKAHOMINY

*---*

SURRY DISCHARGE I-........ 0 ....... HOG ISLAND ..... >,. ... Q ... ::I \ en \ \ \ \ 0 \ u C. '.J a, > 100 C, :::: * \ *--.~~ X X X X X \*. .,---~---o---~----Q \ .* ---,i \ I, .I \. LI . , \*. ~"' I .... \ ,.' \' .I I \.\ .-. ts \*I , .. x . .. . * *-(.) C. \ I *1..*------**

- )..( b .............

a ............ Q * . . * -X \ . ' . ' . . *, \ . * ' . . '-* -\ ~;~. x\ ' _, -:.~ .. "** ....... ' " o-' X ... . *, "'O.. a ' .. X ,. X X '-g 10 . I I I . I I . I I . I I I I I . I I I 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 X:LLD

COBALT-60 IN CLAM SAMPLES 1000 i I I R I t I---o--CHICKAHOMINY

-********* SURRY DISCHARGE ........ 0 ....... HOG ISLAND .... >, ... ... :::, U) * *

0 . . u -...J C. CJ1 a, > 100 0, -.
X X X
X X *
o-,--o-,--.P--* 1--0--,-.-a--~a--'--Q I *'1 \ 0 . *. I .* I . I--. -** I . *. ..** ... \ *~ ,* I I '
0 C. I ~--u* ........ I " --**-. _. . ., j ---* I l:l 'a----*--** \ I ...... -' I x'~ ...... o ... ,, ...... q '* I r,, ..... .* -. . *w* / \ \ I \ h b \ ' \ X ' \ -a ' ... -.. o--* X .. 'O X '~ X X ' 'o 10 I I I I I I I I -r I I I I I I 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 X:LLD

CESIUM-137 IN CLAM SAMPLES 1000 ... --o--CHICKAHOMINY

*-***

SURRY DISCHARGE

-.. *D--**~ HOG ISLAND ... >, ... ... :I rn n 0 ......, () 0) C. a, > 100 C, .. /" r-~---~--~ \ 1.,.1 3 ' \ j1 ' :::: \ .:f \ 0 C. *"'(*** *~ ;,7 \ J.a \ . .. ~1 \_...,-.... x\ . . l""I u, *\t.o~ .~, -\ x'* '~ \'* 'e,-7\ .. .... \ .. \ \ .. \ . \ "*-......... . . X ¥ . -_ ..........

! .. --x \ X **ij***** \ .......... °' o, ... ..n. *** X-~~---.. .... 'O ...... **. ' b . ' *---~". 0 X 10 I . I I I I I --. I I . I I I I . I I 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 X:LLD -"-J "-J -------------TABLE 18 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION SURRY COUNTY, VIRGINIA ANALYSIS ANO LOWER LIMIT MEDIUM OR PATHWAY TOTAL NUMBER OF SAMPLED OF ANALYSES DETECTION (UNIT OF MEASUREMENT) PERFORMED* (LLD) (1) Clams (pCi/kg wet) Oysters (pCi/kg wet) Crabs (pCikg wet) Gamma Spec 30 K-40 Co-60 Cs-137 Gamma Spec 17 K-40 Gamma Spec 1 K-40 130 150 ALL INDICATOR LOCATIONS MEAN RANGE 614(22/24! (255-1060 39.1(2/24) (21.1-57 .1) 14.2(1/24) 666(15/17) (400-916) 2480(1/1) DOCKET NO. 5-280-281 JANUARY 1 to DECEMBER 31, 1988 LOCATION WITH HIGHEST MEAN NAME MEAN DISTANCE. ANO DIRECTION RANGE SD SD SD NN SD 679(6/6) (378-1060) 57.1(1/6) 14.2(1/6) 750(4/5) (625-916) 2480(1/1) (1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Progrilll, Revision 1, November 1979. CONTROL LOCATION MEAN RANGE 471(6/6) (298-583) -(0/6) -(0/6) NONE NONE NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 -- --.-------~ ---------TABLE 19 VIRGINIA POWER -SURRY -1988 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 01/27/88 Clams <100 298 +/- 103 <10 <10 <10 <200 <20 03/24/88 Clams <100 428 +/- 107 <10 <10 <10 <300 <20 05/12/88 Clams <100 430 +/- 113 <10 <10 <10 <200 <20 07/07/88 Clams <100 583 +/- 116 <10 <10 <10 <300 <20 09/08/88 Clams <200 502 +/- 136 <20 <20 <20 <300 <40 11/10/88 Clams <200 582 +/- 148 <20 <20 <20 <300 <40 JMTN 01/2 7 /88 Cl ams <200 474 +/- '140 <20 <20 <20 <400 <30 03/17/88 Clams <100 <500 <20 <20 <20 <300 <30 05/11/88 Clams <200 652 +/- 146 <20 <20 <20 <300 <30 07/06/88 Clams <100 574 +/- 95 <10 <10 <10 <200 <20 09/07 /88 Clams <200 279 +/- 141 <20 <20 <20 <300 <30 ....... 11/09/88 Clams <100 535 +/- 141 <20 <10 <10 <300 <30 CX) SD 01/27/88** Clams <200 378 +/- 161 <20 57.1 +/- 12.4 14.2 +/- 7.8 <300 <30 03/02/88** Clams <100 454 +/- 146 <10 <10 <10 <200 <20 05/09/88** Clams <100 526 +/- 128 <10 <10 <10 <300 <30 07/07/88** Clams <90 841 +/- 105 <10 <10 <10 <100 <10 09/26/88** Clams <100 1060 +/- 150 <10 <10 <10 <200 <20 11/07/88** Clams <100 816 +/- 134 <10 <10 <10 <200 <20 HIP 01/27/88 Clams <200 564 +/- 116 <10 <20 <10 <300 <20 03/17/88 Clams <200 <800 <20 <30 <30 <400 <40 05/11/88 Clams <200 554 +/- 147 <2 0 <20 <20 <300 <40 07/06/88 Clams <200 255 +/- 149 <20 <20 <20 <300 <20 09/07/88 Clams <100 925 +/- 150 <10 21.1 +/- 7.9 <10 <300 <20 11/09/88 Clams <200 905 +/- 150 <20 <20 <10 <300 <30 LC 01/27/88 Clams <200 514 +/- 153 <2 0 <20 <20 <300 <40 03/17/88 Clams <100 726 +/- 131 <10 <20 <10 <300 <30 05/11/88 Clams <200 674 +/- 200 <20 <20 <20 <400 <40 07/06/88 Clams <100 574 +/- 106 <10 <10 <10 <200 <20 09/07/88 Clams <200 522 +/- 118 <10 <20 <20 <300 <30 11/09/88 Cl ams <200 703 +/- 151 <10 <10 <20 <300 <30 Average 583 +/- 392 39.1 +/- 50.9 14.2 +/- 7.8 +/- 2 s. d.

All other gamma emitters were <LLD. ** State Split

--....J I.O ---------TABLE 20 VIRGINIA POWER -SURRY -1988 SAMPLE STAT ION DATE TYPE Be-7 NN 01/27/88** Oysters f bl 03/17 /88** Oysteq <100 05/11/88** Oysters' ( b) <100 07/06/88** Oysters f l <200 09/07 /88** Oysters <100 11/09/88** Oysters ( b) <200 DWS 01/27/88 Oysters <100 03/17/88 Oysters <200 05/11/88 Oysters <100 07/06/88 Oysters <100 09/07/88 Oysters <100 11/09/88 Oysters <200 POS 01/27/88 Oysters <200 03/17/88 Oysters <100 05/11/88 Oysters <100 07/06/88 Oysters <100 09/07/88 Oysters <100 11/09/88 Oysters <200 Average +/- 2 s. d. * ** All other gamma emitters were <LLD. State Split CONCENTRATIONS OF GAMMA EMITTERS* pCi/kg (wet)+/- 2 Sigma K-40 Co-58 <200 <10 625 +/- 139 <10 697 +/- 125 <10 762 +/- 131 <10 916 +/- 136 <20 400 +/- 137 <10 <800 <20 527 +/- 140 <10 791 +/- 127 <10 747 +/- 186 <IO 764-+/- 129 <2 0 537 +/- 130 <20 557 +/- 118 <10 556 +/- 151 <20 788 +/- 121 <10 541 +/- 17 9. <10 788 +/- 17,2 <20 666 +/- 284 ( a) ( b) Sample not available due to shell stock depletion at sample location. Substitute sample from RLS. OYSTERS Co-60 <20 <10 <10 <10 <10 <10 <20 <10 <10 <IO <10 <10 <10 <10 <10 <20 <20 ------Cs-137 Ra-226 Th-228 <10 <200 <20 <10 <300 <20 <10 <300 <20 <10 <300 <30 <20 <300 <30 <10 <300 <30 <20 <400 <40 <10 <300 <30 <I 0 <200 <20 <I 0 <300 <20 <10 <300 <20 <20 <300 <30 <10 <200 <20 <20 <300 <30 <10 <200 <20 <20 <300 <30 <20 <300 <40 -00 0 --STATION DATE SD 06/23/88 -SAMPLE TYPE Cr abs --Be-7 <200

All other gamma emitters were <LLD -----TABLE 21 VIRGINIA POWER -SURRY -1988 CONCENTRATIONS OF GAMMA EMITTERS*

IN CRABS pCi/kg (wet) +/- 2 Sigma K-40 Co-58 Co-60 2480 +/- 250 <10 <20 -----Cs-137 Ra-226 Th-228 <10 <300 <30 -co ...... --------------ANALYSIS AND MEDIUM OR PATHWAY TOTAL NUMBER SAMPLED OF ANALYSES (UNIT OF MEASUREMENT) PERFORMED Fi sh Gamma Spec 4 (pCi/kg wet) K-40 4 Cs-137 4 TABLE 22 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION SURRY COUNTY, VIRGINIA LOWER LIMIT OF ALL INDICATOR LOCATIONS DETECTION MEAN (LLD) (1) RANGE 1575(4/4) ( 1380-1770) 150 17.7(1/4) DOCKET NO. 5-280-281 JANUARY 1 to DECEMBER 31, 1988 LOCATION WITH HIGHEST MEAN NAME MEAN DISTANCE AND DIRECTION RANGE SD 1575(4/4) (1380-1770) SD 17. 7(1/4) (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. NUMBER OF CONTROL LOCATION NONROUTINE MEAN REPORTED RANGE MEASUREMENTS NONE 0 NONE 0 -- -OJ N ----COLLECTION

DATE STATION 05/12/88 SD 05 /2 4/88 SD 10/11/88 SD 10/11/88 SD Average+/- 2 S. D. -----TABLE 23 VIRGINIA POWER -SURRY -1988 CONCENTRATIONS OF GAMMA* EMITTERS IN FISH pCi/kg (wet)+/- 2 sigma SAMPLE TYPE K-40 Co-58 CATFISH 1380 +/- 140 <10 WH !TE PERCH 1600 +/- 350 <30 WHITE PERCH 1550 +/- 190 <20 CATFISH 1770 +/- 2 50 <30 1575 +/- 321
All other gamma emitters were below <LLD. ------Cs-134 Cs-137 <10 17.7 +/- 7.8 <30 <40 <2 0 <20 <20 <20 17.7 +/- 7.8 I I I I I I I I I I I I I I I I 3. Food Products Ten food samples were collected from six locations and analyzed by gamma spectrometry.

The samples consisted of kale, brocolli, cabbage, corn, soybeans and peanuts. No man made isotopes attributable to station discharges were detected in any of these samples. Naturally occurring potassium-40 was observed in all samples with an average activity of .6663 pCi/kg (wet weight) and a range of 2180 to 15700 pCi/kg (wet weight). Cosmogenic beryllium-? was measured in one sample from Stone's garden with an activity of 314 pCi/kg (wet weight). These results are comparable with previous years. 83

TABLE 24 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SURRY NUCLEAR POWER STATION SURRY COUNTY, VIRGINIA ANALYSIS AND LOWER LIMIT MEDIUM OR PATHWAY TOTAL NUMBER OF SAMPLED OF ANALYSES DETECTION (UNIT OF MEASUREMENT) PERFORMED (LLD) (1) Vegetation (pCi/kg wet) Gamma Spec K-40 Be-7 10 10 ALL INDICATOR LOCATIONS MEAN RANGE 6663(10/10) (2180-15700) 314(1/10) DOCKET NO. 5-280-281 JANUARY 1 to DECEMBER 31, 1988 LOCATION WITH HIGHEST MEAN NAME MEAN DISTANCE AND DIRECTION RANGE Brock's Stone's 7853(3/3) (2180-15700) 314(1/1) (1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Rad-iological Environmental Monitoring Program, Revision 1, November 1979. CONTROL LOCATION MEAN RANGE NONE NONE NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 -- -co u, ----SAMPLE STATION TYPE Poole's Garden ** Kale Ryan's Garden** Brocol l i Carter's Garden** Cabbage Stone's Garden ** Cabbage Brock's Garden Corn Brock's Garden ** Peanuts Slade's Garden Peanuts Slade's Garden ** Corn Brock's Garden Soybeans Slade's Garden ** Soybeans Average+/- 2 s. d. -------TABLE 25 VIRGINIA POWER -SURRY -1988 CONCENTRATIONS OF GAMMA* EMITTERS IN VEGETATION pCi/kg (wet) +/- 2 sigma COLLECTION DATE Be-7 K-40 1-131 06/21/88 <200 6130 +/- 610 <20 06/21/88 <200 4840 +/- 480 <20 07 /11/88 <200 5040 +/- 500 <20 07 /24/88 314 +/- 108 3530 +/- 350 <4 10/25/88 <70 2180 +/- 220 <10 10/2 5/88 <100 5680 +/- 570 <20 11/02/88 <100 5130 +/- 510 <20 11/02/88 <40 3200 +/- 320 <6 11/29/88 <60 15700 +/- 1600 <10 12/01/88 <60 15200 +/- 1500 <7 6663 +/- 9569

All other gamma emitters were <LLD. ** State Split ----Cs-134 Cs-137 <20 <20 <20 <20 <20 <20 <10 <10 <9 <8 <10 <20 <10 <10 <5 <5 <9 <9 <7 <8 I I I I I I I I I I I I I I I I E. DIRECT RADIATION EXPOSURE PATHWAY 1. TLD Dosimeters Thermoluminescent dosimeters (TLDs) are placed in two concentric rings around the station environs at the site boundary and approximately 5 miles in each of sixteen sectors. TLDs are also placed in special interest locations such as population areas and nearby residents.

Several TLDs also serve as controls. These dosimeters measure external radiation exposure from several sources including naturally occurring radionuclides in the air and soil, radiation from cosmic origin, fallout from atomic weapons testing, potential radioactive airborne releases from the power station and direct radiation from the power station. The TLDs record the exposure from all of these potential sources and then are processed on a quarterly basis. Two sets of TLD badges each with four readout areas are placed at each location. The average value of the four readings from each badge (calibrated individually for response to a known dose and for intransit exposure) are presented in Tables 27 and 28. Table 26 provides a statistical summary of the four quarters 1988 data. Individual measurements of external radiation levels in the environs of the Surry site for stations 02 through 43 had an average dose of 6.3 mR/standard month period. The average dose for the control stations (39,40) was 5.7 mR/standard month with a range of 5.1 to 6.6 mR/standard month. The indicator locations had an average activity of 6.3 mR/standard month with a range of 4.2 to 9.2 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. 86 ->, ... ... :::, Cl) 0 u C. G> > (X) -....J .c -C 0 :!E 'O ... as 'O C as -Cl) -a: E -------------100 10 1 1980 ~-DIRECT RADIATION MEASUREMENT-TLD RESULTS

Site Boundary ---0-5 Mile Boundary , ~* -* I 1 '-* l /~ I~\ 1-I -" , , ... ,.,.,._-, \ '\. .A\ * --., r l1 , ~/,~ lT --* """-J ---.,. u ~.* l:f '-I --¥ , ----V J 0 I . I . I "T .. . I I I I . I 1981 1982 1983 1984 1985 1986 1987 1988 1989 --

-co co -------------TABLE 26 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

ANALYSIS AND MEDIUM OR PATHWAY TOTAL NUMBER SAMPLED OF ANALYSES (UNIT OF MEASUREMENT) PERFORMED Direct Radiation Gamma 330 TLD's (mr/std. month) SURRY NUCLEAR POWER STATION SURRY COUNTY, VIRGINIA LOWER LIMIT OF ALL INDICATOR LOCATIONS DETECTION MEAN (LLD) (1) RANGE 2 6.3(314/314) (4.2-9.2) DOCKET NO. 5-280-281 JANUARY 1 to DECEMBER 31, 1988 LOCATION WITH HIGHEST MEAN NAME MEAN DISTANCE AND DIRECTION RANGE 38 8.1(8/8) (6.7-8.8) CONTROL LOCATION MEAN RANGE 5. 7(16/16) (5.1-6.6) --NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 -co I.O -------27--* ------of 2) VIRGINIA -1988 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 03 04 05 06 07 08 09 10 11 12 13 14 15 16 17 18 19 20 21 22 ( a) ( b) 7.8 +/- 0.3 6.0 +/- 1. 1 8.5 +/- 0.2 7.9 +/- 1.1 7.8 +/- 2. 2 4.6 +/- 0.2 ( b) 8.3 +/- 0.3 8.2 +/- 0.7 7.0 +/- 4.2 14.7 +/- 6.8 (a) 5.9 +/- 0.8 7.1 +/- 0.2 6.8 +/- 0.7 6.6 +/- 1. 2 6.5 +/- 0.3 5.9 +/- 0.6 7.4 +/- 0.1 6.3 +/- 0.2 6.5 +/- 1. 3 7.4 +/- 0.7 6.8 +/- 0.5 7. 5 +/- 0.2 7.0 +/- 0.5 7.2 +/- 0.7 6. 7 +/- 0.2 5.6 +/- 0.6 6.9 +/- 0.3 6.7 +/- 0.6 6.5 +/- 1. 2 6.9 +/- 0.2 ( b) 7.0 +/- 0.4 6.6 +/- 0.6 6.8 +/- 0.4 6.5 +/- 0.5 5.9 +/- 0.4 6.9 +/- 0.1 7.2 +/- 0.4 6.6 +/- 1. 1 6 .. 5 +/- 0.5 5.8 +/- 0.6 6.9 +/- 0.2 6.0 +/- 1. 7 6.3 +/- 1. 0 6.7 +/- 0.2 6.3 +/- 0.7 7.6 +/- 0.6 6.3 +/- 0.5 6.7 +/- 1. 2 6.6 +/- 0.6 5.9 +/- 0.9 7.0 +/- 0.3 6.8 +/- 0.3 6.6 +/- 1. 0 6. 7 +/- 0.3 6.0 +/- 0.5 7. 3 +/- 0.8 6.9 +/- 0.5 6.7 +/- 1. 1 6.8 +/- 0.5 6.3 +/- 0.6 7. 2 +/- 0.4 6.8 +/- 0.3 6.8 :I: 0. 7 6.3 +/- 0.3 4.6 +/- 1. 6 6.4 +/- 0.3 6.4 +/- 0.4 5.9 +/- 1. 8 6. 7 +/- 0.8 5.8 +/- 0.5 6.7 +/- 0.4 6.5 :I: 0.8 6.4 +/- 0.9 6.2 +/- 0.3 5.6 +/- 0.7 6.6 +/- 0.4 6.2 +/- 0.1 6.2 +/- 0.8 5. 3 +/- 0.4 4.8 +/- 0.3 5.6 +/- 0.3 5.6 :I: 0.2 5.3 +/- 0.8 6.2 +/- 0.4 5.4 +/- 0.4 6.0 +/- 0.4 6.4 +/- 0.8 6.0 +/- 0.9 5.6 +/- 0.4 5. 1 +/- 0.5 5.7 +/- 0.6 5.9 +/- 0.6 5.6 +/- 0.7 5.9 +/- 0. 1 4.4 +/- 0.5 6.2 :I: 0.5 6.2 +/- 0.1 5.7 +/- 1. 7 5.7 +/- 0.4 4.7 +/- 0.8 5.8 +/- 0.4 5.6 :1: 0.7 5.5 :1: 1.0 TLD found missing; replaced 03/09/88. The replacement TLDs for the period 03/09/88 through 04/04/88 appeared to have received a non-uniform dose concentrated in area 4 in particular and to a lesser extent in area 3. It appears the replacement TLD for station number 04, Set 1-098 was positioned such that it partially shielded the replacement TLD for station number 04, Set 2-099 and the associated control TLD. This possibly indicates that a spurious dose was received in transit or receipt at the station. The data for TLD station number 04 for this time period was not included in the averages. TLD vandalized; third quarter TLDs placed in field early as replacements.

(Page 2 of 2) VIRGINIA POWER -SURRY -1988 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. 23 6.6 +/- 0.4 6.6 +/- 0.5 6.8 +/- 0.1 6.8 +/- 0.3 6.7 +/- 0.2 24 6.2 +/- 0.5 5.2 +/- 0.5 6.4 +/- 0.3 5.9 +/- 0.9 5.9 +/- 1.1 25 6.6 +/- 0.3 6.3 +/- 0.7 6.7 +/- 0.3 7.0 +/- 0.7 6.7 +/- 0.6 26 6.4 +/- 0.2 5.4 +/- 1. 8 6.3 +/- 0.1 6.3 +/- 0.5 6.1 +/- 0.9 27* 5.6 +/- 0.4 5.0 +/- 0.6 6.0 +/- 0.3 5.7 +/- 0.9 5.6 +/- 0.8 28 6.5 +/- 0.4 5. 7 +/- 0.9 6.4 +/- 0.3 5.7 +/- 1. 5 6. 1 +/- 0.9 29 5.5 +/- 0.2 5. 1 +/- 0.8 6.3 +/- 0.6 5.4 +/- 0.7 5.6 +/- 1 0 30 6.2 +/- 0.4 4.7 +/- 0.6 6. 2 +/- 0.3 5.7 +/- 0.5 5. 7 +/- 1. 4 w 31 5.9 +/- 0.2 5. 1 +/- 0.3 5.6 +/- 0.5 5. 7 +/- 0.3 5.6 +/- 0.7 0 32 6.4 +/- 0.2 5.9 +/- 0.6 6.4 +/- 0.4 5.9 +/- 0.6 6.2 +/- 0.6 33 6.6 +/- 0.3 5.8 +/- 1. 9 6.8 +/- 0.6 6.7 +/- 0.3 6.5 +/- 0.9 34 6.8 +/- 0.8 6.8 +/- 0.7 6.8 +/- 0.1 6.6 +/- 0.7 6.8 +/- 0.2 35 7.3 +/- 0.4 6.4 +/- 0.8 7. 2 +/- 0.7 6.6 +/- 0.6 6.9 +/- 0.9 36 7.5 +/- 0.6 6.4 +/- 0.7 7.3 +/- 1. 3 7.5 +/- 0.8 7.2 +/- 1.1 37 6.8 +/- 0.1 6.0 +/- 1. 0 6.4 +/- 1. 0 6.4 +/- 0.4 6.4 +/- 0.7 38 8.2 +/- 0.6 7.5 +/- 0.9 8.8 +/- 0.4 7.9 +/- 0.7 8. 1 +/- 1.1 39 6.4 +/- 0.4 6. 2 +/- 0.3 6.2 +/- 0.2 6 .1 +/- 0.1 6.2 +/- 0.3 40 5.2 +/- 0.2 4.7 +/- 0.6 5. 5 +/- 0.4 5.3 +/- 0.2 5.2 +/- 0.7 41 6.8 +/- 0.4 6.2 +/- 0.5 7. 2 +/- 0.5 6.8 +/- 0.6 6.8 +/- 0.8 42 6.4 +/- 0.4 5.5 +/- 0.9 6.5 +/- 0.5 6.0 +/- 0.4 6. 1 +/- 0.9 43 5.0 +/- 0 .1 5.9 +/- 0.9 6.2 +/- 0.2 6.5 +/- 0.7 5.9 +/- 1. 3 Average 6.4 +/- 1. 4 5. 7 +/- 1. 4 6.7 +/- 1. 5 6.4 +/- 1. 3 6.3 +/- 0.8 +/- 2 s. d. -I.O ,__. ,.-STATION NUMBER 02 03 04 05 06 07 08 09 10 11 12 13 14 15 16 1 7 18 19 20 21 22 ---FIRST QUARTER 7.9 +/- 0.3 4.4 +/- 0.1 8.3 +/- 6. 3 (a) 7. 1 +/- 0.6 7.6 +/- 0.6 6.5 +/- 0.4 7.0 +/- 0.4 6.9 +/- 0.4 6.5 +/- 0. 1 6.8 +/- 0.2 7.0 +/- 0.3 6.9 +/- 0. 1 6.9 +/- 1. 0 6.6 +/- 0.4 6.6 +/- 0.3 6. 2 +/- 0.5 5.9 +/- 0.2 6. 1 +/- 0. 1 5.6 +/- 0.2 6. 2 +/- 0.5 5.6 +/- 0.2 ---TA 8 --(Pa. VIRGINIA POWER -SURRY -1988 DIRECT RADIATION MEASUREMENTS -QUARTERLY TLD mR/month +/- 2 Sigma -Set 2 -099 SECOND QUARTER THIRD QUARTER 6. 5 +/- 0.5 8.7 +/- 1. 4 ( b) 8.0 +/- 0.4 4.8 +/- 0.5 7.7 +/- 0.5 5. 1 +/- 0.6 7.5 +/- 0.7 5. 7 +/- 0.8 7.8 +/- 0.4 5.0 +/- 0.9 7. 2 +/- 0.4 ( b) 6. 3 +/- 0.5 5. 6 +/- 0.9 7.3 +/- 0.3 4.2 +/- 1. 9 6.9 +/- 0.4 4.9 +/- 1. 0 7. 1 +/- 0.3 4. 9 +/- 0.5 7. 1 +/- 0.5 6.4 +/- 0.8 7. 3 +/- 0.4 5.4 +/- 1. 2 7.5 +/- 0.6 4.6 +/- 0.4 6. 7 +/- 0.4 5.0 +/- 0.8 6.7 +/- 0.4 4.7 +/- 0.3 6.4 +/- 0.4 4. 5 +/- 0.2 5. 7 +/- 0.4 4.9 +/- 0.6 6. 5 +/- 1. 2 4. 2 +/- 0.5 6.0 +/- 0.3 4.8 +/- 1. 2 6.4 +/- 0.2 4.8 +/- 0.3 5.7 +/- 0.5 ------RESULTS AVERAGE FOURTH QUARTER +/- 2 s. d. 9.2 +/- 1. 5 8. 1 +/- 2.4 7.7 +/- 2. 1 6.7 +/- 4.0 6.8 +/- 0.5 6.4 +/- 3.0 6.7 +/- 0.5 6.6 +/- 2. I 7. 3 +/- 0.6 7. 1 +/- 1. 9 6.8 +/- 0.2 6.4 +/- 1. 9 6.8 +/- 0.6 6. 7 +/- 0.7 7.2 +/- 0.7 6.8 +/- 1. 6 6. 3 +/- l'. 3 6.0 +/- 2.4 6.6 +/- 0.6 6.4 +/- 2.0 6.7 +/- 0.7 6.4 +/- 2. 1 6.6 +/- 0.3 6.8 +/- 0.8 6.0 +/- 0.7 6.5 +/- 1. 9 6.4 +/- 0.6 6. 1 +/- 2.0 6.4 +/- 0.9 6.2 +/- 1. 6 6.3 +/- 0.7 5.9 +/- 1. 6 4.6 +/- 2 .1 5. 2 +/- 1. 5 5.8 +/- 0.7 5.8 +/- 1. 4 5. 2 +/- 1. 3 5. 3 +/- 1. 5 6.3 +/- 0.3 5.9 +/- 1. 5 5.4 +/- 0.7 5.4 +/- 0.8 (a) TLO found missing; replaced 03/09/88. T~e replacement TLOs for the period 03/09/88 through 04/04/88 appeared to have received a non-uniform dose concentrated in area 4 in particular and to a lesser extent in area 3. It appears the replacement TLO for station number 04, Set 1-098 was positioned such that it partially shielded the replacement TLO for station number 04, Set 2-099 and the associated control TLD. This possibly indicates that a spurious dose was received in transit or receipt at the station. The data for TLO station number 04 for this time period was not included in the averages (b) TLO vandalized; third quarter TLOs placed in the field early as replacements. -,.---------------E 28 of 2) VIRGINIA POWER -SURRY -1988 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 7.6 +/- 0.2 5. 3 +/- 0.7 6.9 +/- 0.5 6.8 +/- 0.7 6.7 +/- 1. 9 24 6.4 +/- 0.4 5. 7 +/- 0.5 6.6 +/- 0.7 6.1 +/- 0.8 6.2 +/- 0.8 25 6.0 +/- 0.4 5. 1 +/- 0.5 7. 1 +/- 0.5 6.3 +/- 1. 2 6 .1 +/- 1. 7 26 5.8 +/- 0.7 4.8 +/- 0.3 6.7 +/- 0.8 6.6 +/- 0.3 6.0 +/- 1. 8 27 5.6 +/- 0.6 4.2 +/- 0.6 6.3 +/- 0.5 5.8 +/- 0.3 5.5 +/- 1. 8 28 6.4 +/- 0.2 4.7 +/- 0.6 6.6 +/- 0.5 6.5 +/- 0.4 6. 1 +/- 1. 8 29 5.4 +/- 0.2 4.4 +/- 0.9 6.2 +/- 0.6 5.9 +/- 0.3 5.5 +/- 1. 6 30 5.8 +/- 0.3 4.2 +/- 0.6 6. 7 +/- 0.7 6.0 +/- 0.2 5. 7 +/- 2.1 31 5.6 +/- 0.2 4.2 +/- 0.8 5.7 +/- 0.2 5.8 +/- 0.7 5.3 +/- 1. 5 I.O 32 6.0 +/- 0.3 4.8 +/- 0.2 6.4 +/- 0.3 6 .1 +/- 0.3 5.8 +/- 1. 4 N 33 6.6 +/- 0.7 5. 2 +/- 0.6 7. 1 +/- 0.3 6.6 +/- 0.4 6.4 +/- 1. 6 34 6.3 +/- 0.3 5. 3 +/- 0.8 6.9 +/- 0.6 6.9 +/- 0.4 6.4 +/- 1. 5 35 7.4 +/- 0.7 5.5 +/- 0.4 7 .1 +/- 0.6 7.3 +/- 1.1 6.8 +/- 1. 8 36 7 .1 +/- 0.5 5. 2 +/- 1.1 7.2 +/- 0.4 7.3 +/- 0.6 6.7 +/- 2.0 37 6.4 +/- 0.4 5.4 +/- 0.5 6. 7 +/- 0.5 6.6 +/- 0. 4 6.3 +/- 1. 2 38 8.4 +/- 0.7 6.7 +/- 1. 3 8.6 +/- 1. 1 8.4 +/- 0.7 8.0 +/- 1. 8 39 6.0 +/- 0.4 5.2 +/- 0.4 6.6 +/- 0. 1 6.3 +/- 0.9 6.0 +/- 1. 2 40 5.3 +/- 0.1 5. 1 +/- 0.1 5.3 +/- 0.4 5. 1 +/- 0.5 5.2 +/- 0.2 41 6.6 +/- 0.5 5. 5 +/- 0.8 7. 2 +/- 0.5 7.0 +/- 0.3 6.6 +/- 1. 5 42 6.0 +/- 0.2 5. 5 +/- 0.2 7.1 +/- 1. 3 6.1 +/- 0.4 6.2 +/- 1. 3 43 6. 1 +/- 0. 2 5. 1 +/- 0.7 5.9 +/- 0.5 6.2 +/- 0.4 5.8 +/- 1. 0 Average 6.4 +/- 1. 5 5. 1 +/- 1. 2 6.8 +/- 1. 4 6.5 +/- 1. 6 6.2 +/- 1. 5 +/- 2 s. d. I I I I I I I I I I I I I I I I ,. I V. CONCLUSIONS I I I I I I I I I I I I I I I -I V. CONCLUSIONS The results of the 1988 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 1988 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 foµnd in the particulate media during 1988. No iodine-131 was detected in charcoal filters in 1988. 93 I I I I I I I I I I I I I I I I The tritium concentrations in the Surry Discharge Canal samples were similar to the predicted effluent tritium concentrations. The average tritium concentration from the VEPCO grab samples was 450 pCi/£. The average tritium concentration from the State Split samples from the canal was 613 pCi/£. Samples taken from liquid tanks in the plant prior to release mixed with the volume of cooling water from the plant indicates that the average concentration of tritium from the station should be 500 pCi/£. Considering the variability of the environmental sampling methodology the results of the environmental samples compared well to the predicted trations of tritium in liquid effluents. Since there is no supply of potable drinking water downstream of Surry and the river water is not used to irrigate crops for food production, the remaining pathway to man is uptake by fish and then consumption of the fish by man. The concentration of tritium in the State Split discharge canal sample represents 2.0% of the reporting level concentrations. The discharge canal water is further diluted when mixed with river water. No gamma emitting radionuclides were detected. Tritium was also detected in well water samples taken from the vicinity of the power station. Ten of the sixteen well water samples for 1988 had measurable concentrations of tritium. Ground water is not normally considered to be affected by station operations since there are no discharges. The sample taken at Surry Station, however, indicates a higher level of tritium than the other three indicator locations. Large variations between the quarterly well water tritium results from Surry Station indicates higher than normal levels one quarter, then less than detectable results the next quarter. An increased frequency of sampling may be warranted to determine the cause for the wide variations. 94 I I I I I I I I I I I I I I I I -----------~----------

The average concentration of tritium in well water from the Surry Station sample represents 3.6% of the reporting level concentration 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. CobaJt-60 and cesium-137 were detected in the samples from all locations. Cobalt-58 was detected in two of the eight downstream samples. Cesium-134 was detected in five samples at several locations upstream and downstream of the plant discharge. The preoperational program analyzed silt samples but found no gamma emitting radionuclides above the sensitivity of the analysis (<5000 pCi/kg). The current sensitivity is approximately 180 pCi/kg. The low sensitivity of the preoperational sample analysis eliminates the ability to make direct comparisons to operational data. As well, no reporting level concentrations have been assigned to this media because silt contamination does not provide a direct pathway to man. A review of the trend graphs indicates that all of the contaminates show a decline in the levels during 1988. This correlates well with the lower activity levels in station effluents. 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. However, the sample results for 1988 indicate the detection of cesium-137 in the frequency and activity ranges seen due to past nuclear weapons testing as opposed to the operation of the power station. 95 I I I I I I I I I I I I I I I I Twelve milk samples from three indicator stations were analyzed for strontium. No strontium-89 was detected in any of the milk samples. Strontium-90 was measured in ten of th~ twelve 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 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 1988 indicate the presence of low level man-made radioactivity. This activity was determined at levels well below the required sensitivity. Comparison of the 1988 data to 1983-1987 data and to data prior to 1978, does not indicate increasing trends. Samples taken during 1978-1982 were not analyzed below the required sensitivity level (<130 pCi/kg) and therefore cannot be compared to the low level activity found in the 1983-1988 samples. Preoperational clam samples were analyzed for gross beta and potassium-40 and are not directly comparable to operational data. The average concentration of activity in the Surry Discharge clam samples taken during 1988 was 0.57% of the reporting level concentrations for cobalt-60 and 0.71% for cesium-137. Cesium-137 was observed in 1 of the 4 fish samples. Trends in activity in the fish samples is difficult to establish because previous samples were analyzed only to the required sensitivity (130 pCi/kg). Preoperational samples were analyzed for gross beta and therefore the data is not comparable to the gamma analysis. The concentration of cesium-137 in this one positive 96 I I I I I I I I I I I I I I I I result represents 0.9% of the reporting level concentrations. Since 1984, detectable levels of cesium-137 has steadily decreased from 87.1 to 17.7 pCi/kg. Based upon the evidence of the environmental monitoring program the station appears to be operating within regulatory limits. Where possible, good correlations existed between predicted releases and actual environmental samples. There appears to be no buildup of activity and concurrent with declining effluent releases, environmental samples are indicating decreasing trends. 97 I I I I I I I I I I I I I I I I VI. 1988 LAND USE CENSUS RESULTS FOR SURRY POWER STATION 98 I I I I I I I I I I I I I I I .I 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 identifies, 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 1988 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. 99 I I I I I I I I I I I I I I I I TABLE 29 CENSUS FOR SURRY POWER STATION -1988 NEAREST NEAREST NEAREST NEARSET SECTOR RESIDENT GARDEN cow GOAT A-(N) 4.75@358°

*
B-(NNE) 1.95@34° * *
C-(NE)
4.90@56° *
D-(ENE) 4.90@63° * *
E-(E) * * *
F-(ESE) * * *
G-(SE) * * *
H-(SSE) 4.70@152°
*
J-(S) 1.60@182° 1.90@182°
K-(SSW) l.88@193° l.88@193° 4.75@201 °
L-(SW) 2.25@220° 3.67@224°
M-(WSW) 2.80@243° 3.42@2s8*
N-(W) 3.20@261 ° 4.33@262°
* , P-(WNW) 4.86@281 ° * *
Q-(NW) * * *
R-(NNW) 3.75@339° 4.38@336° 3.65@337°
None 100

.. I FIGURE 4 RESULTS OF LAND USE CENSUS FOR SURRY POWER STATION .. *

LAND USI CENSUS LOCATION MAP, ?UR /988 . 1
BAUS? RESIDENT 2* NEAREST GARDEN 3* NEAREST CU. 4* NEAREST GOAT ~---~----I 101 ... ' * * .

I I I I I I I I I I I I I I I ,, I VII. SYNOPSIS OF ANALYTICAL PROCEDURES 102 I I I I I I I I I I I I I I I I VII. ANALYTICAL PROCEDURES SYNOPSIS 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 ................... 104 Gross Beta Analysis of Water Samples .................................... 105 Analysis of Samples for Tritium ......................................... 106 Water .............................................................. 106 Analysis of Samples for Iodine-131 ...................................... 107 Milk or Water ...................................................... 107 Gamma Spectrometry of Samples ........................................... 108 Milk and Water ..................................................... 108 Dried Solids other than Soils and Sediment ......................... 108 Fish ............................................. ................. 108 Soi ls and Sediments ................................................ 108 Charcoal Cartridges (Air Iodine).,. ................................. 108 Air Particulates ................................................... 108 Environmental Dosimetry ................................................. 110 Analysis of Samples for Strontium-89 and -90 ............................ 111 Total Water ........................................................ 111 Milk ............................................................... 111 Soil and Sediment .................................................. 111 Organic Solids ..................................................... 112 Air Particulates ................................................... 112 103 I I I I I I I I I I I I I I I I 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) where: =((S/T) -(B/t))/(2.22 VE) =((S/T2) + (B/t2))1/2/(2.22 VE) =4.66 (Bl/2)/(2.22 VE t). 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) 104 I I I I I I I I I I I I I I I I GROSS BETA ANALYSIS OF WATER SAMPLES One liter of sample is evaporated to near dryness and the residue is ferred to a tared, 2 11 diameter planchet and final evaporation to dryness takes place under heat lamps. The planchet is weighed and then counted in a gas-flow proportional counter. Calculation of the results, the two sigma error and the lower limit of detection (LLD). RESULT (pCi/£) TWO SIGMA ERROR (pCi/£) LLD (pCi/£) where: =((S/T) -(B/t))/(2.22 VE) =((S/T2) + (B/t2))1/2/(2.22 VE) =4.66 (Bl/2)/(2.22 VE t) 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) 105 I I I I I I I I I I I I I I I I ANALYSIS OF SAMPLES FOR TRITIUM Water Approximately 2 ml of water are converted to hydrogen by passing the water, heated to its vapor state, over a granular zinc conversion column heated to 400° C. The hydrogen is loaded into a one liter proportional detector and the volume is determined by recording the pressure. The proportional detector is passively shielded by lead and steel and an electronic, anticoincidence system provides additional shielding from cosmic rays. Calculation of the results, the two sigma error and the lower limit tion (LLD) in pCi/£: RESULT TWO SIGMA ERROR LLD where: = 3.234 TN VN(C 6 -8)/(CN Vs) = 2((CG + B)6t)1/2 3.234 TN VN/((CN Vs)(C 6-B)) = 4.66 (3.234)TN VN(C 6)1/2/(6t CN Vs) TN = tritium units of the standard 3.234 = conversion factor changing tritium units to pCi/£ = volume of the standard used to calibrate the B 6t efficiency of the detector in psia = volume of the sample loaded into the detector in psia = the cpm activity of the standard of volume VN = the gross activity in cpm of the sample of volume Vs and the detector volume = the background of the detector in cpm = counting time for the sample 106 I I I I I I I I I I I I ANALYSIS OF SAMPLES FOR IODINE-131 Milk or Water Two liters of sample are first equilibrated with stable iodide carrier. A batch treatment with anion exchange resin is used to remove iodine from the sample. The iodine is then stripped from the resin with sodium hypochlorite solution, is reduced with hydroxylamine hydrochloride and is extracted into carbon tetrachloride as free iodine. It is then back-extracted as iodide into sodium bisulfite solution and is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting. The chemical yield is corrected by measuring the stable iodide content of the milk or the water with a specific ion electrode. Calculations of results, two sigma error and the lower limit of detection (LLD) in pCi/£: RESULT TWO SIGMA ERROR LLD where: N At B 2.22 V y OF E E = (N/At-8)/(2_.22 EVY OF) = 2((N/At+B)/At) 112 (2~22 EVY DF) = 4.66(B/At) 1/2/(2.22 EVY DF) = total counts from sample (counts) = counting time for sample (min). = background rate of counter (cpm) = dpm/pCi = volume or weight of sample analyzed = chemical yield of the mount or sample counted = decay factor from the mid-collection date to the counting date = efficiency of the counter for I-131, corrected for self absorption effects by the formula = Es(exp-0.0061M)/(exp-0.0061Ms) = efficiency of the counter determined from an I-131 standard mount = mass of PdI 2 on the standard mount, mg = mass of PdI 2 on the sample mount, mg 107 I I I I I I I I I I I I I I I I 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 l00°C. As much as possible (up to the total sample) is loaded into a tared 1-liter Marinelli and weighed. The sample is then counted for at least 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data tion system which performs pulse height analysis. Fi sh 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 l00°C. The soil or sediment is loaded fully into a tared, standard 300 cc container and weighed. The sample is then counted for at least six hours with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis. Charcoal Cartridges (Air Iodine) Charcoal cartridges are counted up to five at a time, with one positioned on the face of a Ge(Li) detector and up to four on the side of the Ge(Li) detector. Each Ge(Li) detector is calibrated for both positions. The detection limit for I-131 of each charcoal cartridge can be determined ing no positive I-131) uniquely from the volume of air which passed through it. In the event I-131 is observed in the initial counting of a set, each charcoal cartridge is then counted separately, positioned on the face of the detector. Air Particulate The four or five (depending on the calendar month) air particulate filters for a monthly composite for each field station are aligned one in front of another and then counted for at least six hours with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis. 108 I I I I I I I I I I I I I A mini-computer software program defines peaks by certain changes in the slope of the spectrum. The program also compares the energy of each peak with a library of peaks for isotope identification and then performs the activity calculation using the appropriate fractional gamma ray abundance, half life, detector efficiency, and net counts in the peak region. The calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/volume or pCi/mass: RESULT = (S-B)/(2.22 t EV F OF) TWO SIGMA ERROR = 2(S+B)1/2/(2.22 t EV F OF) LLD = 4.66(8)1 1 2/(2.22 t EV F OF) where: s B = Area, in counts, of sample peak and background (region of spectrum of interest) = Background area, in counts, under sample peak, 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 F grams) = fractional gamma abundance (specific for each emitted gamma) OF = decay factor from the collection to the counting date 109 I I I I I I I I I I I I I I I I ENVIRONMENTAL DOSIMETRY Teledyne Isotopes uses a CaS04:Dy thermoluminescent dosimeter (TLD) which the company manufactures. This material has a high light output, negligible thermally induced signal loss (fading), and negligible self dosing. The energy response curve (as well as all other features) satisfies NRC Reg. Guide 4.13. Transit doses are accounted for by use of separate TLDs. Following the field exposure period the TLDs are placed in a Teledyne Isotopes Model 8300. One fourth of the rectangular TLD is heated at a time and the measured light emission (luminescence) is recorded. The TLD is then annealed and exposed to a known Cs-137 dose; each area is then read again. This provides a calibration of each area of each TLD after every field use. The transit controls are read in the same manner. Calculations of results and the two sigma error in net milliRoetgen (mR): RESULT where 01 .Dl I1 K Rl A = the net mR of area 1 of the TLD, and similarly for o 2 , o 3 , and D 4 = I 1 K/R 1 -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 110 I I I I I I I I I I I I I ,. I ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 WATER Stable strontium carrier is added to 1 liter of sample and the volume is reduced by evaporation. Strontium is precipitated as Sr(N03)2 using nitric acid. A barium scavenge and an iron (ferric hydroxide) scavenge are performed followed by addition of stable yttrium carrier and a 5 to 7 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. MILK Stable strontium carrier is added to 1 liter of sample and trichloracetic acid (TCA) is added to produce a curd. The curd is separated by filtration and is discarded. An oxalate precipitation is performed on the filtrate and the precipitate is ashed in a muffle furnace. The ash is dissolved and strontium is precipitated as SrN03 using fuming (90%) nitric acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for 7 to 10 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 is determined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for low 1evel beta counting. SOIL AND SEDIMENT The sample is first dried under heat lamps and a 10 gram aliquot is taken. Stable strontium carrier is added and the sample is leached in nitric acid. The mixture is filtered and the liquid portion is reduced in volume by ration. Strontium is precipitated as Sr(N03)2 using fllTiing (90%) nitric acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for 7 to 10 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 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. 111 I I I I I I I I I I I I I I I I Organic Solids A 200g wet portion of the sample is dried and then ashed in a muffle furnace. Stable strontium carrier is added and the ash is leached in-nitric acid. The sample is filtered and the volume is reduced by evaporation. Strontium is precipitated as Sr(N03)2 using fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a 7 to 10 day period for yttrium ingrowth. Yttrium is then precipitatd as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is mined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. Air Particulates Stable strontium carrier is added to the sample and it is leached in nitric acid to bring deposits into solution. The mixture is then filtered and the filtrate is reduced in volume by evaporation. Strontium is precipitated as Sr(N03)2 using fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a 7 to 10 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mo~nted on a nylon planchet and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is determined by tating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with 80 mg/cm2 aluminum absorber for level beta counting. Calculations of the results, two sigma errors and lower limits of detection (LLD) are expressed in activity of pCi/volume or pCi/mass: RESULT Sr-89 = (N/6t-Bc-BA)/(2.22 V Ys DFsR-89 EsR-89) TWO SIGMA ERROR Sr-89 = 2((N/6t+BA+BA)/6t) 112/(2.22 V Ys DFSR-89 ESR-8 9) LLD Sr-89 = 4.66((Bc+BA)/6t) 112 1(2.22 V Ys DFsR-89 EsR-89) RESULT Sr-90 = (N/6t B)/(2,22 V Y 1 Y 2 DF IF E) TWM SIGMA ERROR Sr-90 = 2((N/8t+B)/6t) 1 1 2/(2.22 V Y 1 Y 2 DF E IF)) LLD Sr-90 = 4.64(B/8t) 1/2/(2.22 V Y 1 Y 2 IF DF E) 112 I I I I I I I I I I I I I I I I where: N = total counts from sample (counts) ~t = counting time for sample (min) Be = background rate of counter (cpm) using absorber configuration 2.22 V BA = dpm/pCi = volume or weight of sample analyzed = background addition from Sr-90 and ingrowth of Y-90 BA = 0.016 (K) + (K) Ev/abs) (IGy_go) Ys DFSR-89 K DFY-90 EY-90 IFY-90 IGY-90 0.016 Ey /abs B E IF = chemical yield of strontium = decay factor from the mid collection date to the counting date for SR-89 = efficiency of the counter for SR-89 with the 80 mg/cm.sq. aluminum absorber = (N/~t -Bc)y_gol(Ey_go Ify_go Dfy_90Y1) = the decay factor for Y-90 from the "mi 1 k 11 time to the mid count time = efficiency of the counter for Y-90 = ingrowth factor for Y-90 from scavenge time to milking time = the ingrowth factor for Y-90 into the strontium mount from the 11 milk 11 time to the mid count time. = the efficiency of measuring SR-90 through a No. 6 absorber = the efficiency of counting Y-90 through a No. 6 absorber = background rate of counter (cpm) = chemical yield of yttrium = chemical yield of strontium = decay factor of yttrium from the radiochemical milking time to the mid count time = efficiency of the counter for Y-90 = ingrowth factor for Y-90 fpom scavenge time to the chemical milking time 113 I I I I I I I I I I I I I I I I VIII. EPA INTERLABORATORY COMPARISON PROGRAM 114 I I I I I I I I I I I I I I I I 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 1988 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. 115 -...... ...... 0) -a-------US EPA CROSS ----ECK PROGRAM --GROSS BETA IN AIR PARTICULATES 100-,-------------------------------, 80 60 0 CL 40 20 0 +-~.......--~---------.---.r--r---.-.......--~-...-------.-----r---.----..-----4 1981 1982 1983 1984 1985 1986 1987 1988 1989 --* EPA+/-3 sigma 0 Tl +/-3 sigma -I-' I-' 0 '-I CL us EPA CROSS C ---* ---CK PROGRAM CS-137 IN AIR PARTICULATES 80 60

0 40 20 Q-+--T--Y---r-r---,.--,---.-__.,_~-..----y---r---'-,.---'r---,-......_-,.-~..,__- __ r--....--~

1981 1982 1983 1984 1985 1986 1987 1988 1989 --EPA +/-3 sioma Tl +/-3 sigma -...... 0 ...... C. 00 us EPA CROSS C CKPROGRAM SR-90 IN AIR PARTICULATES 40 30

0 20 i i 10 Q4------------------~---..-------.------.------.--

........... --.---....-------.-~ 1981 1982 1983 1984 1985 1986 1987 1988 1989 --EPA+/-3 Sioma Tl +/-3 sigma -... CD ....... -....... \.0 -0 C. -----*--US EPA CROSS ECKPROGRAM 1-131 IN MILK 120-,-----------------------------T"I"'--, 100 80 60 40 20 0 0 -+,,1-......--..-...--..-....------------.-....--......------.,............-----......._--,......._....--......-- ______ _ 1981 1982 1983 1984 1985 1986 1987 1988 1989 --* EPA+/-3 sigma 0 Tl +/-3 sigma -... Cl) -....... N -C) 0 C. USEPACROSS CKPROGRAM K-40INMILK 2400 2000 1600 1200 B00-+--,----.----.~-:.----- ......... ---.-------.----.----....-------.-__.---.__.-.-.-.---.---......------.---.---........--1 1981 1982 1983 1984 1985

1986 1987 1988 1989 --* EPA +/-3 siama 0 Tl +/-3 sigma

-... a, ,_. -N ,_. -0 a. us EPA CROSS C CKPROGRAM CS-137 IN MILK 80 60 40 20 0 -+---r---r--ir---.----r---r-r---.----.---r-,---.----.---,,------------.----.-....---1 1981 1982 1983 1984 1985 1986 1987 1988 1989 --* EPA +/-3 siama 0 Tl +/-3 sigma -... a, -...... N N -0 a. -------.. ---US EPA CROSS cW£cK PROGRAM SR-89 IN MILK --100-r------------------------------ 80 60 40 0 0 0 20 0 0 -+---r----r-,,,---.--1.....r-----,--,,-.......----r--r--,,,-~----------..--1-.......-------------1 1981 1982 1983 1984 1985 1986 1987 1988 1989 ---* EPA +/-3 siama 0 Tl +/-3 sigma -... a, -' N w -0 a. USEPACROSS ECKPROGRAM SR-90 IN MILK 100...------------------------------ 80 60 40 20 0 4--.....------.-------...---.....----r-----r-----r-r---r--.....------.-----r---...---__.L...-----r---.--.....----r---1 1981 1982 1983 1984 1985 1986 1987 1988 1989 --* EPA+/-3 siama 0 Tl +/-3 sigma -... I-' CD N --Po --._ -0 C. -------------80 60 40 20 0 1981 US EPA CROSS CHECK PROGRAM SR-89 IN WATER I; t 1982 1983 1984 1985 1986 1987 I I I 1988 1989 --* EPA+/-3sigma 0 Tl+/-3 sigma -.. CD --I-' -N -u, -0 a. -------------US EPA CROSS CHECK PROGRAM SR-90 IN WATER 100,---------------------------- 80 60 40 JiH 1 fa 0 -f---y--------..----,.--.-.-------.---+--------_...,_----------4---,I 20 f 1981 1982 1983 1984 1985 1986 1987 1988 1989 --* EPA+/-3 sigma 0 Tl+/-3sigma -... QI 1--' -N -0) ---0 C. -------------US EPA CROSS CHECK PROGRAM 1-131 IN WATER 120 -.--------------------------------. 100 80 I 60 40 20 ¥ t, I, ' 0 1981 1982 1983 1984 1985 1986 1987 1988 1989 --* EPA+/-3 sigma 0 Tl+/-3sigma -.. Cl) ....... -N -'-I ---0 C. -------------8000 6000 4000 2000 US EPA CROSS CHECK PROGRAM H-3INWATER Q-t---r----.-----.----~-~-r-----r----.---.------r------""T""--.--f 1980 1982 1984 1986 1988 1990 --* EPA+/-3 sigma 0 Tl+/-3 sigma

us EPA INTERLABOR COMPARISON PROGRAM 1988 VEPCO -SURRY (Page 1 of 5) EPA Date TI Mailed Date EPA EPA TI Norm Dev. ** Warning PREPARATION Results Issued Results Media Nuclide Results(a)

Results(b) (Known) *** Action 12/11/87 01/28/88 02/23/88 Water Ra-226 4.80 +/- 0.72 5.20 +/- 0.35 0.96 Ra-228 5.30 +/- 0.80 4.93 +/- 0.49 -0.79 01/08/88 02/29/88 04/11/88 Water Sr-89 30.00 +/- 5.00 27.33 +/- 0.58 -0.92 Sr-90 15.0D +/- 1. 50 16.00 +/- 1. 00 1.15 01/22/88 02/19/88 03/07/88 Water Gr-Alpha 4.00 +/- 5.00 3.67 +/- 0.58 -0.12 Gr-Beta 8.00 +/- 5.00 8.33 +/- 0.58 0.12 01/29/88 04/05/88 05/03/88 Food Sr-89 46.00 +/- 5.00 40.67 +/- 2.52 -1. 85 Sr-90 55.00 +/- 2.75 54.33 +/- 3.79 -0.42 1-131 102.00 +/- 10.20 85.67 +/- 5.13 -2. 77 ** ( C) Cs-137 91. 00 +/- *5. 00 98.67 t 7.64 2.66 ** ( d) K 1230.00 t 61. 50 1210.00 +/-151.00 -0.56 02/05/88 03/14/88 04/11/88 Water Co-60 69.00 t 5.00 65.00 t 2.65 -1. 39 Zn-65 94.00 t 9.40 91.00 t 4.36 -0.55 Ru-106 105.00 +/- 10.50 89.00 t 7.94 -2.64 ** (e) 1--' N Cs-134 64.00 t 5.00 55.00 t 5.29 -3.12 *** ( f) co Cs-137 94.00 t 5.00 91.00 t 3.61 -1. 04 02/12/88 03/18/88 04/04/88 Water H-3 3327.00 +/-362.00 3266.67 t 57.73 -0.29 02/26/88 03/18/88 04/29/88 Milk 1-131 4.00 +/- 0.40 4.33 +/- 0.58 1. 44 03/18/88 04/12/88 05/16/88 Water Gr-Alpha 6.00 +/- 5.00 4.00 +/- 0.00 -0.69 Gr-Beta 13.00 t 5.00 15.67 t 0.58 0.92 03/25/88 06/02/88 06/28/88 Air Filter Gr-Alpha 20.00 t 5.00 24.00 +/- 0.00 1. 39 Gr-Beta 50.00 +/- 5.00 46.33 +/- 1.15 -1. 27 Sr-90 17.00 +/- 1. 50 17.00 +/- 0.00 0.00 Cs-137 16.00 t 5.00 16.33 +/- 0.58 0.12 03/31/88 05/06/88 05/31/88 Water Ra-226 7.60 +/- 1.14 7.30 t 0.17 -0.46 Ra-228 7.70 +/- 1.16 12.00 +/- 0.00 6.42 *** ( g) 04/08/88 05/06/88 06/06/88 Water I-131 7.50 +/- 0.75 8.67 +/- 0.58 2.69 ** (h)

us EPA I NTERLABO f COMPARISON PROGRAM 1988 VEPCO -SURRY (Page 2 of 5) EPA Date TI Mailed Date EPA EPA TI Norm Dev. ** Warning PREPARATION Results Issued Results Media Nuclide Results( a) Results(b} (Known} *** Action 04/24/88 06/29/88 08/01/88 Lab Perf. Gr-Alpha 46.00 +/- 11.00 70.67 +/- 0.58 3.88 *** ( i ) (Sample A) Ra-226 6.40 +/- 0.96 6.63 +/- 0.12 0.42 Ra-228 5.60 +/- 0.84 6.10 +/- 0.20 1. 03 (Sample B) Gr-Beta 57.00 +/- 5.00 67.67 +/- 2.08 3.70 *** ( j ) Sr-89 5.00 +/- 5.00 4.67 +/- 0.58 -0 .12 Sr-90 5.00 +/- 1. 50 5.00 +/- 0.00 -0.00 Co-60 50.00 +/- 5.00 53.00 +/- 2.00 1.04 Cs-134 7. 00 +/- 5.00 8.33 +/- 1.15 0.46 Cs-137 7.00 +/- 5.00 9.00 +/- 1. 00 0.69 05/06/88 07/13/88 08/05/88 Water Sr-89 20.00 +/- 5.00 16.67 +/- 2.08 -1.15 Sr-90 20.00 +/- 1. 50 19.67 +/- 1. 15 -0.38 05/20/88 06/17/88 07/19/88 Water Gr-Alpha 11.00 +/- 5.00 4.67 +/- 0.58 -2.19 ** (k) Gr-Beta 11.00 +/- 5.00 13.67 +/- 0.58 0.92 06/03/88 07 /12/88 08/08/88 Water Cr-51 302.00 +/- 30.00 313.67 +/- 20.31 0.67 Co-60 15.00 +/- 5.00 18.00 +/- 2.00 1. 04 Zn-65 101.00 +/- 10.00 109.33 +/- 10.50 1. 44 I-' Ru-106 195.00 +/- 20.00 184.67 +/- 20.03 -0.89 N Cs-134 20.00 +/- 5.00 19.33 +/- 2.08 -0.23 I.O Cs-137 25.00 +/- 5.00 30.33 +/- 7. 55 1. 73 06/10/88 07 /08/88 08/01/88 Water H-3 5565.00 +/-557.00 5900.00 +/-199.99 1. 04 06/17/88 08/11/88 09/08/88 Water Ra-226 10.00 +/- 1. 51 10.60 +/- 0.40 0.69 Ra-228 12.40 +/- 1. 86 9.97 +/- 0.06 -2.27 ** ( 1) 06/24/88 09/02/88 09/26/88 Milk Sr-89 40.00 +/- 5.00 36.33 +/- 2.52 -1. 27 Sr-90 60.00 +/- 3.00 61.00 +/- 2.00 0.58 I-131 94.00 +/- 9.00 101. 67 +/- 7.64 1.48 Cs-137 51. 00 +/- 5.00 53.67 +/- 3.06 0.92 K 1600.00 +/- 80.00 1656.67 +/- 55.07 1. 23 07/22/88 08/19/88 09/08/88 Water Gr-Alpha 15.00 +/- 5.00 8.33 +/- 0.58 -2.31 ** ( m) Gr-Beta 4.00 +/- 5.00 6.00 +/- 0.00 0.69 07/29/88 10/07/88 11/10/88 Food 1-131 107.00 +/- 11. 00 103.33 +/- 11. 55 -0.58 Cs-137 49.00 +/- 5.00 51. 33 +/- 2.52 0.81 K 1240.00 +/- 62.00 1220.00 +/- 34.64 -0.56 08/05/88 09/07/88 10/12/88 Water 1-131 76.00 +/- 8.00 86.00 +/- 2.65 2.17 ** ( n)

us EPA I NTERLABO COMPARISON PROGRAM 1988 VEPCO -SURRY (Page 3 of 5) EPA Date TI Mailed Date EPA EPA TI Norm Dev. ** Warning PREPARATION Results Issued Results Media Nuclide Results(a)

Results(b) (Known) *** Action 08/26/88 11/04/88 12/02/88 Air Filter Gr-Alpha 8.00 +/- 5.00 9.33 +/- 0.58 0.46 Gr-Beta 29.00 +/- 5.00 25.67 +/- 1. 53 -1. 15 Sr-90 8.00 +/- 1. 50 7.67 +/- 0.58 -0.38 Cs-137 12.00 +/- 5.00 11. 00 +/- 1. 00 -0.35 09/16/88 11/10/88 12/02/88 Water Ra-226 8.40 +/- 1. 30 8.70 +/- 0.26 0.40 Ra-228 5.40 +/- 0.80 5.83 +/- 0.32 0.94 09/23/88 10/21/88 11/21/88 Water Gr-Alpha 8.00 +/- 5.00 9.00 +/- 0.00 0.35 Gr-Beta 10.00 +/- 5.00 11. 33 +/- 0.58 0.46 10/07/88 11/17/88 12/12/88 Water Cr-51 251. 00 +/- 25.00 236.00 +/- 29.21 -1. 04 Co-60 25.00 +/- 5.00 28.00 +/- 0.00 1. 04 Zn-65 151.00 +/- 15.00 165.67 +/- 5. 51 1. 69 Ru-106 152.00 +/- 15.00 169.67 +/- 12. 2 2 0.89 Cs-134 25.00 +/- 5.00 27.67 +/- 1. 53 0.92 I-' Cs-137 15.00 +/- 5.00 17. 33 +/- 3.06 0.81 w 0 10/14/88 11/10/88 12/01/88 Water H-3 2316.00 +/-350.00 2300.00 +/-100.00 -0.08 10/18/88 12/23/88 02/06/89 Lab Perf. Gr-Alpha 41.00 +/- 10.00 38.67 +/- 1.15 -0.40 (Sample A) Ra-226 5.00 +/- 0.80 5. 6 7 +/- 0.15 1. 44 Ra-228 5.20 +/- 0.80 5.27 +/- 0.06 0.14 (Sample B) Gr-Beta 54.00 +/- 5.00 53.33 +/- 2.52 -0.23 Sr-89 11. 00 +/- 5.00 8.67 +/- 0.58 -0.81 Sr-90 10.00 +/- 1. 50 9.00 +/- 0.00 -1. 15 Cs-134 15.00 +/- 5.00 15.67 +/- 1. 15 0.23 Cs-137 15.00 +/- 5.00 16.33 +/- 3. 21 0.46 11/25/88 12/23/88 01/23/89 Water Gr-Alpha 9.00 +/- 5.00 10.00 +/- 0.00 0.35 Gr-Beta 9.00 +/- 5.00 11. 00 +/- 1. 00 0.69 10/28/88 01/06/89 12/13/8 8 Milk Sr-89 40.00 +/- 5.00 28.33 +/- 0.58 -4.04 *** ( 0) Sr-90 60.00 +/- 3.00 52.00 +/- 3. 5 6 -4.62 *** ( o) 1-131 91. 00 +/- 9.00 87.67 +/- 1. 15 -0.64 Cs-137 50.00 +/- 5.00 51. 33 +/- 1. 53 0.46 K 1600.00 +/- 80.00 1578.33 +/- 23.63 -0.47 12/09/88 01/10/89 02/09/89 Water 1-131 115.00 +/- 12.00 106.67 +/- 5. 77 -1. 20 -I-' w 1-*, -----Footnotes: (a) Average+/- experimental sigma. -----US EPA INTERLABORATORY COMPARISON PROGRAM 1988 VEPCO -SURRY (Page 4 of 5) (b) Expected laboratory pr~cision (1 sigma, 1 determination).

(c) The average result of 86 pCi/kg was lowered by one analysis of 80 pCi/kg, in which 1-131 may have been lost in processing.

If this analysis is discarded and the higher results of the other 2 aliquots are taken, the average becomes 94 pCi/kg which is more favorable (-1.1 sigma for 2 determinations). Our investigations revealed no systemic reason for the low (-2.77) sigma for 3 determinations). Moreover, our previous performance for this analysis shows no systematic bias. (d) There is no apparent reason for the deviation. Although there is a bias high, the bias does not appear to be changing significantly. Starting with the 01/13/86 data, the ratio of the average TI results to the EPA result is 1.27, 1.10, 1.08 and 1.15. (e) The ruthenium-106 results (as well as other isotopes in the EPA sample) for the February 5, 1988 EPA sample were based ( f) ( g) on a new standard (Amersham) used in the December 1987 annual .calibrations. A calculation using the previous NBS standard efficiencies gave an average of 98.0 pCi/liter having a normalized deviation of -1.15. A second Amersham standard in a marinelli was prepared and agreed with the NBS standard. These efficiencies are in use currently. The cesium-134 results (as well as the other isotopes in the EPA sample) for February 5, 1988 EPA sample were based on a new standard (Amersham) used in the December 1987 annual calibrations. A calculation using the previous NBS standard efficiencies gave an average of 60.2 pCi/liter having a normalized deviation of -1.80. A second Amersham standard in a Marinelli was prepared and agreed with the NBS standard. These efficiencies are is use currently. The samples were analyzed for Ra-228 by PR0-032-67. A new procedure (PR0-032-97) has been formalized and is currently in use for all samples. The results using the new procedure gave 6.2 +/- 1.4 pCi/liter. (h) An investigation was _conducted and there is no apparent reason for the deviation. The samples contained an unusually high concentration of stable iodide (3.6 mg/liter) as determined by electrode readings which was verified at that time. The chemical yields were properly calculated taking these readings into account. No corrective action is necessary since these results fall within the EPA 3 sigma control limits and no trends on previous 1-131 intercomparison results are evident. ( i) Dr~ Frank Novielli of the EPA states that the EPA takes energy correction into account. He mailed us a document which indicates how this is achieved. Teledyne Isotopes has implemented the EPA method for energy correction. (j) High concentration of Co-60 in the sample (50 pCi/£) resulted in false beta counts on the Tennelec counters from Co-60 gamma. Dr. Frank Novielli of the EPA stated that the EPA will discontinue using Co-60 in Performance Evaluation samples (effective October 1988) because of this problem. (k) Low alpha caused by the presence of chlorides in the sample reside which increases self-absorption. Samples are now being evaporated with more nitric acid to convert chlorides to niturates. These reported results fall within the EPA 3 sigma control limits. (l) The investigation revealed no apparent reason for the reported low value; the result is within the EPA 3-sigma acceptance region. The new rapid extraction method for Ra-228 has provided acceptable results for all of the last 7 EPA tests. -I-' w N ---------US EPA INTERLABORATORY COMPARISON PROGRAM 1988 VEPCO -SURRY (Page 5 of 5) -----Footnotes: (Cont.) (m) ( n) ( 0) The deviation noted is due to unusually high self-absorption characteristics of EPA water spikes. Our results and the midwest laboratory, each independently calibrated with Am-241, obtained low results by the same margin. Corrective action involves applying the self-absorption curve derived by our analysis of EPA water in 1976 Collaborative Study (solid line) instead of the usual curve (dashed line) when calculating EPA cross-check samples. Faulty stable iodide yield correction, probably caused by a chemical in the sample which interferes with the iodide electrode. The high electrode reading was verified by repeating several times. Without yield correction our average result would have been 77pCi/l. This is in the EPA 3 sigma acceptance region. Possible loss of radiostrontium in the initial TCA separation step. Another possibility, the presence of calciu~ on the final strontium mount, has been ruled out by an experiment in which the strontium mounts were repurified and recounted, giving the same results as originally found. An experiement with direct ashing (EML method) and with ion exchange (EPA method) as alternatives to the TCA separation step is being explored. This study includes an experiment in which spiked milk samples are stored for several weeks before analysis in order to determine whether radiostrontium becomes bound to the protein or fat components of the milk. I C 0 . :; :! . ... >, I g .. u :;: ... .... I .u ... ... .., gra111s res~due .... --.. -... ... .I I I I I I I I I I I I I i I IX. REFERENCES 133 I I I I I I I I I I I I I IX. REFERENCES

1. United States Nuclear Regulatory Corrmission, 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 11 , Rev. 3, March 1982. 4. United States Nuclear Regulatory Co1T1T1ission.

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 1 11 , October, 1977. 5. USNRC Branch Technical Position, "Acceptable Radiological mental Mmnitmring Program", Rev. 1, November 1979. 134}}

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