ML18151A426
| ML18151A426 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/31/1989 |
| From: | Blount P, Erickson D, Garber B VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 90-199, NUDOCS 9005030346 | |
| Download: ML18151A426 (134) | |
Text
,-
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 30, 1990 United States Nuclear Regulatory Commission Serial No.90-199 Attention: Document Control Desk NURPC Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Attached is the 1989 Radiological Environmental Monitoring Program Report for Surry Power Station which fulfills the requirement for the Annual Radiological Environmental Operating Report per Technical Specification 6.6.B.2.
Very truly yours, W. L. Stewart Senior Vice President - Nuclear Attachment cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219
VIRGINIA ELECTRIC AND POWFJB/Jtm1g ANY SURRY POWER STAJ:,({)N, RADIOLOGICAL ENVIRONMENTAL MONIT0RING P;~~~
- , .. . ~-..... , *. ., ..
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FOR 1989 Prepared by VIRGINIA ELECTRIC AND POWERC.OMPANY and TELEDYNE ISOTOPE$:
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- ANNUAL RADIOLOGICAL ENYIROMENTAL OPERATING REPORT.
- SURRY POWER STATION JANUARY 1,1989 to DECEMBER 31,1989
- I Prepared by:
Peter F. Blount Supervisor Radiological Analysis Reviewed by: ~,. ,."K' 4 ,d__L__
. Barry J\.. Garber *
. Health Physics Supervisor Technical Services C
Superintendent Radiological Protection
TABLE OF CONTENTS SECTION TITLE PAGE I. IN'IRODUCTION ........................................................................... 1 II. SAMPLING AND ANALYSIS PROGRAM .. : .......................................... 4 III. PROGRAM EXCEPTIONS ............................................................... 16 IV.
SUMMARY
AND DISCUSSION OF 1989 ANALYTICAL RESULTS ............ 21 A. AIRBORNE EXPOSURE PATHWAY ........................................... 22
- 1. Air Iodine/Air Particulates .................................................... 22 B. WATERBORNE EXPOSURE PATHWAY ...................................... 27
- 1. River Water .....................................................................27
- 2. Well Water ...................................................................... 29 C. AQUATICEXPOSUREPATHWAY ............................................. 33
- 1. Silt ............................................................................... 33
- 2. Shoreline Sediment ............................................................ 35 D. INGESTION EXPOSURE PATHWAY .......................................... 36
- 1. Milk .............................................................................. 36
- 2. Aquatic Biota ................................................................... 41
- 3. Food Products ............................... .- .................................. 42 E. DIRECT RADIATION EXPOSURE PATHWAY .............................. .46
- 1. TLD Dosimeters ................................................................ 46 V. CONCLUSION ......................................................... .- ................... 48 VI. REFERENCES .............................................................................. 53 i
TABLE OF CONTENTS (Cont)
SECTION TITLE PAGE VII. APPENDICES ............................................................................... 55 APPENDIX A - Radiological Environmental Monitoring .............................. 55 Program Summary - 1989 APPENDIX B - Data Tables ....... ." ....................................................... 63 APPENDIX C - Land Use Census - 1989 .......................... : .................... 94 APPENDIX D - Synopsis of Analytical Procedures .................................... 98 APPENDIX E-EPA Interlaboratory Comparison Program ......................... 112 LIST OF FIGURES
- 1. Land Based Environmental Sampling Locations ........................................... 10
- 2. River Based Environmental Sampling Locations ................................... ~ ...... 11
- 3. Site Boundary 1LD Locations ............................................................... 12
- 4. Land Use Census Map* ........................................................................ 97 LIST OF TRENDING GRAPHS
- 1. Gross Beta in Air Particulates ................................................................ 23
- 2. Tritium in River Water ........... .-............................................................ 30
- 3. Tritium in Well Water ......................................................................... 34
- 4. Cobalt-58 in Silt ............................................................................... 37
- 5. Cobalt-6() in Silt ............................................................................... 38
- 6. Cesium-134 in Silt ............................................................................. 39
- 7. Cesium-137 in Silt ............................................................................. 40
- 8. Cobalt-58 in *clams ............................................................................ 43
- 9. Cobalt-60 in Clams ............................................................................ 44
- 10. Cesium-137 in Clams ......................................................................... 45 e 11.
12.
Direct Radiation Measurements-1LD Results ............................................. .47 US EPA Cross Check Program ............................................................ 114 ii
-- TABLE LIST OF TABLES PAGE B-1 Concentrations of Iodine-131 in Filtered Air..................................................... 64 B-2 Concentrations of Gross Beta in Air Particulates ................................................ 68 B-3 Concentrations of Ganuna Emitters in Quarterly Air Particulates .............................. 72 B-4 Concentrations of Gamma Emitters and Tritium in* River Water............................... 74 B-5 Concentrations of Gamma Emitters and Tritium in State Split River Water ..................77 B-6 Concentrations of Gamma Emitters and Tritium in Well Water................................78 B-7 Concentrations of Gamma Emitters in Silt ......................... : ............................. 79 B-8 Concentrations of Gamma Emitters in Shoreline Sediment .................................... 81 B-9 Concentrations of Strontium 89/90 and Gamma Emitters in Mille ........................... .. 82 B-10 Concentrations of Gamma Emitters in Clams .................................................... 85 B-11 Concentrations of Gamma Emitters in Oysters .................................................. 86 B-12 Concentrations of Gamma Emitters in Crabs .................................................... 87 B-13 Concentrations of Gamma Emitters in Fish ...................................................... 88 B-14 Concentrations of Gamma Emitters in Vegetation .......... : .................................... 89 B-15 Direct Radiation Measurements - Quarterly TLD Results Set 1................................ 90 B-16 Direct Radiation Measurements - Quarterly TLD Results Set 2 ................................ 92 .
iii
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.
iv
I. INTRODUCTION 1
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- 1. IN1RODUCTION The operational radiological environmental monitoring program conducted for the year 1989 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, 1989 through December 31, 1989 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 l, 1973.
B. The United States Nuclear Regulatory Commission (USNRC) regulations (10CFR50.34a) require that nuclear power plants be designed, constructed, 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 address the release of radioactive effluents. Inplant monitoring is used to ensure that these release limits are not exceeded. As a precaution against unexpected or undefined environmental processes which might allow undue accumulation of radioactivity in the environment, a program for monitoring the plant environs is also included in Surry Power Station Technical Specifications.
C. Virginia Electric and Power Company is responsible for collecting the various indicator and control environmental samples. Teledyne Isotopes is responsible for sample analysis and submitting 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 control levels, which vary with time due to such external events as cosmic ray bombardment, weapons test fallout, and seasonal 2
variations of naturally occurring isotopes. Data collected prior to the plant operation is used to indicate the degree of natural variation to be expected. This preoperational data is compared with data collected during the operational phase to assist in evaluating the radiological impact of the plant operation.
D. Occasional samples of environmental media show the presence of man-made isotopes.
As a method of referencing the measured radionuclide concentrations in the sample media to a dose consequence to man, the* data is compared to the reporting level concentrations listed in the USNRC Regulatory Guide 4.8 and Table 4.9-4 of Surry Power Station's Technical Specifications. These concentrations are based upon the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion of "As Low As Is Reasonably Achievable".
E. This report documents the results of the Radiological Environmental Monitoring Program for 1989 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 effluents 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
II. SAMPLING AND ANALYSIS PROGRAM 4
II. SAMPLING AND ANALYSIS PROGRAM A. Samplin1 Proecam
- 1. Table 1 summarizes the sampling program for Surry Power Station during 1989.
The symbols on this table refer to the sample locations shown on Figures 1 through
- 3. Figure 1 indicates the locations of the land based samples while Figure 2 shows the locations of the river based samples. The small triangles in Figure 3 designate the position of environmental thermoluminescent dosimeters (TLDs) at the site boundary.
- 2. For routine TLD measurements, two dosimeters made of CaS04:Dy in a teflon card are deployed at each sampling location. Several TLDs are co-located with NRC and Commonwealth of Virginia direct radiation recording devices. These are indicted as "co-location" samples.
- 3. In addition to the Radiological Environmental Monitoring Program required by Surry Technical Specifications, Virginia Electric and Power Company splits samples with the Commonwealth 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 locations except those labeled "control".
B. Analysis Pro1ram
- 1. Table 2 summarizes the analysis program conducted by Teledyne Isotopes for Surry Power Station during 1989.
5
TABLE I (Pagel of 4)
SURRY - 1989 RADIOl.OOICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance Collection . il*
Sample Media Location Station MIies Direction Degrees Frequency Remarks Environmental Control (00) Quarterly Onsile*
(TLD's) West Nonh West (02) 0.17 WNW 'l!:J1." Quarterly Sile Boundary Surry Slalion Discharge (03) 0.6 NW 30IJ" Quarterly Sile Boundary 6 North North West (04) 0.4 NNW 33()0 Quarterly Sile Boundary North (05) 0.33 N 357° Quarterly Sile BoundlU}'
North North F.ut (06) 0.28 NNE. 'lJ:> Quarterly Sile BoundlU}'
North East (07) 0.31 NE 450 Quarterly Sile BoundlU}'
East North East (08) 0.43 ENE (;If> Quarterly Sile Boundary East (Exclusion) (09) 0.31 E SU' Quarterly . Onsile West (10) 0.40 w 270" Quarterly Sile Bmmdary Wcat South West (11) 0.45 WSW 250" Quarterly Sile Boundary '
South West (12) 0.30 SW 2250 Quarterly Si1e Boundary South SoUlh West (13) 0.43 SSW 2030 Quarterly Sile Bol;llldary South (14) 0.48 s 180" Quarterly Sile Bmmdary SoUlh South East (15) 0.74 SSE 157" Quarterly Sile Boundary
°' South East (16) 1.00 SE 135° Quarterly Sile Boundary East (17) 0.57 E SU' . Quarterly Sile Boundary Slalion lnlakc (18) 1.23 ESE 113° Quarterly Sile Boundary Hog Island Resavc (19) 1.94 NNE 'Jf,O Quarterly Near Resident, co-location BKIDIIS Cude (20) 4.45 SSW 1JJ1:' Quarterly Apx. 5 mile 11..D, co-location Rowc633 (21) 3.5 SW 2240 Quarterly Apx. 5 mile 11..D Alliance (22) 5.1 WSW 2A80 Quana-ly Apx. 5 mile 11..D co-location Suny (23) 8.0 WSW 250" Quartcdy . Population Center Roule 636 and 637 (24) 4.0 w 27(1' Quarterly Apx. 5 mile 11..D Scotland Wharf (25) 5.0 WNW 2350 Quarterly Apx. 5 mile 11..D, co-location Juncs&own (26) 6.3 NW 310" Quarterly Apx. 5 mile 11..D co-location Colonial Parkway (27) 3.7 NNW 33()0 Quarterly Apx. 5 mile 11..D RoutG617 and618 (28) S.2 NNW 340" Quarterly Apx. S mile 11..D Kingsmill (29) 4.8 N 1! Quarterly Apx. S mile TLD Williamsburg (30) 7.8 N CJ' Quanaiy .Population Centcr, co-location Kingsmill North (31) 5.6 NNE 14° Quarterly Apx. 5 mile TLD Budweiser (32) 5.1 NNE 27° Quarterly Population Center
- TI..D stored in a lead shield in environmental building.
TABLE I (Page2 of4)
SURRY-1989 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance Collection* i** '
Sample Media Location Station Miles Direction Degrees Frequency Remarks Environmental W&1erPlanl (33) 4.8 NE. 41° Quarterly Apx. 5 mile TLD TLD's(Cont.) Dow (34) 5.i . ENE 7f1> Quarterly Apx. 5 mile TLD LccHall (35) 7.1 ENE 73° Quarterly Population Center, . co-location D Goose Island FonEuslis Newport News Junca'Rivrz Bridge (36)
(31)
(38)
(39) 5.0
- 4.8
- 16.5 14.8 E
ESE.
ESE SSE 88" 107° 102° 147° Quarterly Quarterly Quarterly Quane.rly Apx. 5 mile TLD Apx. 5 mile, TLD Population Center Control Location oo-location Benn's Church (40) 14.5 s 175° Quarterly Control Location Smithfield (41) 1L5 s 176° Quanedy Population Center Rushmcn: (42) 5.2 SSE 156° Quarterly Apx. 5 mile TLD Rt.628 (43) 5.0 s *171° Quarterly Apx. 5 mile, TLD co-location Air Charcoal Suny Station (SS) .37 NNE 15" Weekly Site boW1dary location with
....... and Particulate HighestD/Q Hog Island Rcsave (lilR) 2.0 NNE 'JnO Weekly Co-location (BC) .. SSW 202° Weekly D 81COOS Castle Allimcc Colmial Parkway Dow Cicmica1 (AIL)
(CP)
(DOW) 4.5 5.1 3.7 5.1 .
WSW NNW ENE 2118° 330" 7f1>
Weekly Weekly Weekly Co-location FanEuslis (FE) 4.8
- ESE 107° Weekly Newport Newa (NN)
- 16.5 ESE 122" Weekly Control Location River Water Suny Discharge 0.17 NW 3250 Monthly State Split Scodanil Wharf . 5.0 WNW 2850 Monthly Control Location/State Split ESE 11°
- Bi-monthly Suny Slalioo lnlake 1.9 Hog Island Point 2.4 NB 5-r> Bi-monthly Newport News 12.0 SE 140° Bi-moothly Chicbhmniny River
- 11.2 WNW 300" Bi-monthly Control Location Suny Slalion Discharge
- 0.17 NW 3250 Moothly Scod1pd Wharf 5.0 WNW 2850 Moothly
TABLE 1 (Page 3 of 4)
SURRY-1989 RADIOU>GICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. l Distance Collection Sample Media Location Miles Direction Degrees Frequency Rem*rks Well Water Surry Station Quarterly Onsitc*
Hog hland Rcaavc 2.0 NNE II° Quarterly
!WWI Bacoos Casile JamCIIOwn 4.5 6.3 SSW NW 203° DJ' Quarterly Quarterly Sed Shoreline Hog' Island Rcscive Burwell's Bay 0.8 7.76 N
SSE 167° j> Semi-Annually Semi-Annually Semi-Annually Control Location Slit Chickahcminy River 11.2 WNW 300" Surry Statioo Intake 1.9 ESE 71° Semi-Annually 00 Hog Island Point Point of Shoals Newport News
.2.4 6.4 12.0 NE SSE SE NNW 5'1!'
157° 140" 341° Semi-Annually Semi-Annually Semi-Annually Semi-Annually Surry Station Discharge 0.5 Milk LccHall 7.1 ENE 640 Monlhly State Spli1 Epps 4.8 SSW 201° Monlhly State Split
- A Colooial Parkway Judkins WIiiiama 3.7 6.2 22.5 NNW SSW s
3'57° 211° 18'1!'
Moruhly Monlhly Moolhly Control Location Oy1ter1 Deep Water Shoals 3.9 ESE 1()50 Bi-Monthly Point of Shoals 6.4 SSE 157° Bi-Monthly
@ Hondlcad Shoals Rock Landing Shoals 4.2 7.8 12.0 ESE SE SE 1'57° 140" 140" Bi-Monthly Bi-Monthly Bi-Monthly State Split Newport Ncwa Clams Chickahcminy River 11.2 WNW 300" . Bi-Monthly Control Location Surry Swtion Discharge 1.3 NNW 341° Bi-Mondtly State Split
© Hog Island Point J11111cstown Lawnes Creek 2.4 5.1 2.4 NE WNW SE 5'1!'
300" 131° Bi-Monlhly
.Bi-Monlhly Bi-Monthly
- Well water sample taken onsitc al Surry Envirorunenlal Building.
TABLE 1 (Page 4 of 4)
SURRY-1989 RADIOLOGICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance Collection Sample Media Location MIies Direction Degrees Frequency Crabs Suny Sration Discharge 0.6 NW 312° Annually Fish 0 Suny Station Discharge 0.6 NW 312° Semi-Annually Crops Brock's Fann 3.8 s 188° Annually S1a1e Split (Com,Peanuu) Slade's Furn 2.4 s 171° Annually State Split SoybcUIS)
(Cabbage,Kalc) Pool's Garden 2.3 s 182° Annually State Split Cutct's Grove Gudcn 4.8 NE 560 Annually Slalc Split Ryan's Garden Annually State Splil/Control Loe.
(Chester, Va.)
Srone's Garden Annually State Split
j FIGURE 1 LAND BASED SAMPLES
\ J:,-'
r---~- -~-----,
! 10
FIGURE 2 RIVER BASED snm
= LES 11
HOG ISLAND RESERVE N.
~
SPOILS POND
£ _ _ _ __
11£.Io £ ======----1
TABLE 2 SURRY POWER STATION SAMPLE ANALYSIS PROORAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD{l} REPORT UNITS Thermoluminescent Quarterly Gamma Dose 1.5 mR/month Dosimetry (TLD)
Air Iodine Weekly 1-131 0.07 pCi/m3 Air Particulate Weekly Gross Beta 0.01 pCi/m3 Quarterly (2) Gamma Isotopic pCi/ni3 Cs-134 0.05 Cs-137 0.06 River Water Quarterly Tritium 2000 pCi/1 composite of monthly sample Monthly and Gamma Isotopic pCi/1 Bi-monthly Mn-54 15 Fe-59 30 e Co-58, 60 Zn-65 Zr-95 15 30 30 Nb-95 15 1-131 10 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Well Water Quarterly Tritium 2000 pCi/1 1-131 1 Gamma Isotopic 15 Mn-54 15 Fe-59 30 Co-58, 60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 e Footnotes located at end of table.
13
TABLE 2 (Cont.)
SURRY POWER STATION SAMPLE ANALYSIS PROORAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD(l) REPORT UNITS Shoreline Sediment Semi-Annual Gamma Isotopic pCi/kg-dry Cs-134 150 Cs-137 180 Silt Semi-Annual Gamma Isotopic pCi/kg-dry Cs-134 150 Cs-137 180 Milk Monthly 1-131 1 pCi/1 .
Gamma Isotopic Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Oyster Bi-Monthly Gamma Isotopic pCi/kg-wet Mn-54 130 e Fe-59 Co-58, 60 Zn-65 260
- 130 260 Cs-134 130 Cs-137 150 Clams Bi-Monthly Gamma Isotopic pCi/kg-wet Mn-54 130 Fe-59 260 Co-58, 60 130 Zn-65 260 Cs-134 130 Cs-137 150 Crabs Annually Gamma Isotopic pCi/kg-wet Mn-54 130 Fe-59 260 Co-58, 60 130 Zn-65 260 Cs-134 130 Cs-137 150
- Footnotes located at end of table.
14
TABLE 2 (Cont.)
SURRY POWER STATION SAMPLE ANALYSIS PROORAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD(l) REPORT UNITS Fish Semi-Annual Gamma Isotopic pCi/kg-wet Mn-54 130 Fe-59 260 Co-58, 60 130 Zn-65 260 Cs-134 130 Cs-137 150 Crops Annually Gamma Isotopic pCi/kg-wet 1-131 60 Cs-134 6()
Cs-137 80 Footnotes:
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.
(1) LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the Surry Radiological Environmental Program. Actual analysis of the samples by Teledyne Isotopes may be lower than those listed.
(2) Quarterly composites of each location's weekly air particulate samples are analyzed for gamma emitters.
e 15
III. PROGRAM EXCEPTIONS
- 16
III. PROGRAM EXCEPTIONS REMP deviations for 1989 are listed in this chapter. Where possible, the causes of the deviations have been corrected to prevent recurrence.
The station Technical Specification Lill for air iodine was not met for the sampling period 6/20/89 through 6/26/89 at the Colonial Parkway (CP) sampling location. The fuse had blown on the power pole where the air sampler is located. The timer on the sampler indicated a run time of only 0.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. A minimum sample volume of 125 cubic meters is needed to meet the air iodine LLD. A sample run time of 0.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is equivalent to a sample volume of 0.34 cubic meter. The fuse on the pole was replaced as well as the sampler.
River water samples are collected and composited at the Surry Discharge Canal (downstream location) and at Scotland Wharf (upstream control location) by the Commonwealth of Virginia. These samples are split with VEPCO on a monthly basis. The analysis of these samples for barium/lanthanium-140 and iodine-131 failed to meet the required Lower Limit of Detection (LLD) in many of these samples because of the delay in receipt of the samples from the Commonwealth of Virginia. These samples are not used to e comply with the requirements of the station's Technical Specifications. The monthly river water samples collected by VEPCO personnel meet Technical Specification LLD requirements.
Two TLDs were missing from TLD station #14 in the first quarter of 1989. The TLDs were discovered missing while performing monthly visual checks of TLDs at each TLD station during April. When TLDs are found missing they are normally replaced. In this case, replacement TLDs were not requested because second quarter TLDs were already in transit to the power station. Upon arrival at the power station the second quarter TLDs were installed at TLD station #14. The TLDs were found to be missing due to a gas turbine construction project. The construction project removed and replaced the power line pole on which the TLDs were placed.
One of two TLDs from TLD station #7 for the fourth quarter of 1989 was not available for analysis. Although shipping documents and monthly visual inspections of Till stations document that a TLD was not lost and that both TLDs from station #7 were shipped, the Teledyne Isotopes laboratory acknowledged receipt of only one Till. Interviews with power station and Teledyne Isotopes personnel have not determined a cause for the missing TLD.
17
The data reported for stations #7 and #14 in 1989 compares favorably with previous years data and no unusual influence is evident from the loss of these TLDs.
mR/STANDARD MONTH* AVERAGE STATION #7 STATION #14 Year Set 1 Set 2 Set 1 Set 2 1989 6.2 6.4 7.3 7.7 1988 6.5 6.4 6.8 6.5 1987 6.9 6.7 7.0 7.1 1986 6.9 6.9 7.1 7.4 The State Split vegetation sample collected August 20, 1989 was lost in transit to the Teledyne Isotopes laboratory. A resample of vegetation was obtained August 27, 1989 to meet the requirements of the State Split sampling program.
Due to a microorganism infestation in the lower James River (MSX/Dermo), oyster shellstock has been virtually depleted at the Newport News (Noseway Shoal) sample location. Sampling terminated at this location in 1988 and will recommence when the oyster beds revitalize as determined by the Commonwealth of Virginia. An alternative sampling location, Rock Landing Shoals, was selected. This location is downstream of the power station as was the Newport News location. The Commonwealth of Virginia also added Horsehead Shoals to the State Split sampling program for oysters. Horsehead Shoals is located between Deep Water Shoals and Rock Landing Shoals downstream of the power station. These samplings will continue until the Newport News location is approved for sampling again.
The fourth quarter 1989 Surry Station and Jamestown well water sample analyses for tritium are not included in this report. The original analyses reported from Teledyne Isotopes were 5,000 and 7,900 pCi/liter for the sample locations Surry Station and Jamestown respectively. A reanalysis confirmed these unusually high values. Further investigation at the analytical laboratory determined that the two samples were inadvertently contaminated prior to the tritium analysis. Corrective measures as taken by the Vice President -Technical of Teledyne Isotopes should prevent recurrence of this problem.
18
In addition to the quarterly samples, monthly samples were obtained. Although not required by the sampling program, these monthly samples were obtained for information only. The tritium analyses for the October and November samples were less than LLD (100 pCi/liter).
19
REMP EXCEPTIONS FOR SCHEDULED SAMPLING AND ANALYSIS DURING 1989 -SURRY e
Date of Location Description Sampling Reason(s) for Loss/Exception CP Air Iodine 06/20/89-06/28/89 LLD not met due to blown fuse causing power outage.
SW River Water 03/15/89 LLD not met due to late receipt of State Split 05/15/89-12/15/89 sample from State of Virginia.
SD River Water 02/15/89-12/15/89 LLD not met due to late receipt of State Split sample from State of Virginia.
14 Direct Radiation First Quarter 1LD lost due to construction.
11D Sets 1/2 7 Direct Radiation Fourth Quarter 1LD not received.
11D Set 1 Turner's Vegetation/ 08/20/89 Sample lost in transit.
Garden Cabbage LeeHall Milk 10/03/89 TI was unable to locate the sample at the time the composite was made.
ss Well Water 12/19/89 Tritium not determinable; sample contaminated at TI.
JMTN Well Water 12/19/89 Tritium not detenninable; sample contaminated at TI.
20
IV.
SUMMARY
AND DISCUSSION OF 1989 ANALYTICAL RESULTS 21
IV.
SUMMARY
AND DISCUSSION OF 1989 ANALYTICAL RESULTS Data from the radiological analyses of environmental media collected during the report period are provided in this section. The procedures and specifications followed in the laboratory are in accordance with the Teledyne Isotopes Quality Assurance Manual and are explained in the Teledyne Isotopes Analytical Procedures. A synopsis of analytical procedures used for the environmental samples are provided in Appendix D. 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 lnterlaboratory Comparison are provided in Appendix E.
Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurements 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 l, November 1979.
The following is a discussion and summary of the results of the environmental measurements taken during the reporting period.
A. Airborne Exposure Pathway
- 1. Air Iodine/Air Particulates 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 B-1. All results were below the lower level of detection with no positive activity detected.
Results of gross beta activities are presented in Table B-2. A review of the data tab~es indicate that all sample locations, including the control location in Newport News, show comparable results. Control and indicator locations differ by expected statistical and seasonal variations. Quarterly averages for each location are listed on the data tables and show good comparison in the first three quarters. All locations show slightly elevated results in the fourth quarter indicating seasonal variations. The required lower level of detection for this sample is 0.010 pCi/m3. The measurement of the gross beta activity on the weekly particulate filters is a
.good indication of the levels of natural and/or man made radioactivity in the environment. If 22
TRENDING GRAPH - 1 GROSS BETA IN AIR PARTICULATES
>o fl) 0 u
A.
II
~*. \ ,
,*. \
~ ' "
r \
N
~ i \-~-~
(")
- IE 0
A.
... - ~ ...... ....
"iii..o*
\*/-****** - -, ...:*
li1 - / \-:A ~A.r.rii"
10* 3 +------------------.-,---------.---------~,--------r--------,,..--------....-.---------,..------------------t 1969 1970 1 971 1972 1973 1 974
- ----a---- Indicator
- -****** Control
TRENDING GRAPH - 1 (Cont.)
GROSS BETA IN AIR PARTICULATES
. ~*
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IL II ,
- I (I)
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- ................................................................................................. ... ...._... *~*** ......................................................................................................................................
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.Ir 10*3 I I I I 1974 1975 1976 1977 1978 1979
--a-- Indicator Control
TRENDING GRAPH - 1 (Cont.)
GROSS BETA IN AIR PARTICULATES 10° i:=====================================================================i r., _ . . . .
U) 10* 1 .
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............................................................................................................................................................................................................. .......................... *~**********
- e 0
a.
10*2 10* 3 -t--~~...,-~~--.-.~~---......-~~,-,~~---~~~..--.~~......--~~---T",~~--.~~~
1979 1980 1981 1982 1983 1984
- ----************ Indicator
........... Control
TRENDING GRAPH - 1 (Cont.)
GROSS BETA IN AIR PARTICULATES
- s (a) rn 10* 1
- ;J
!I 0
C)
- a. l N >* _,,
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A *
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- L. ...._. ""
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..w,. ......... ~l~
.. &Ill 10*2
~ ** ti 10* 3 1984 1985 1986 I I 1987 1988 I . I 1989 1990 (a) Chernobyl Accident ----*G----* Indicator
........... Control
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 0.018 pCiJm3 with a range of 0.007 to 0.036 pCiJm3. The average measurement for the indicator locations is 0.017 pCi/m3 with a range of 0.003 to 0.042 pCiJm3. The required lower level of detection for the analysis is 0.010 pCi/m3.
The monthly averages of the gross beta concentrations for the seven indicator and one control location are plotted for 1969 through 1989. The gross beta levels observed are comparable to the levels detected during the 1982-1988 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 these analyses are listed in Table B-3. Beryllium-7, 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 0.064 pCiJm3 and a range between 0.041 to 0.124.
Naturally occurring potassium-40 was detected in five samples with an average activity of 0.004 pCi/m3 and a range of 0.003 to 0.005 pCi/m3. The results indicate that no other gamma emitting radioactivity was detected.
B. Waterborne Exposure Pathway
- 1. River Water The James River is an estuary near Surry Power Station and undergoes tidal exchange with the Chesapeake Bay. River water samples thus represent saline bay water. Samples of James River water are collected as both monthly grab samples at the Surry Discharge and Scotland Wharf stations and bi-monthly grab samples at the Hog Island Point, Newport News, Chickahominy River, and Surry Intake stations. All the samples were analyzed 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 B-4. Naturally occurring potassium-40 was measured in six of the samples with an e
27
average concentration of 84.7 pCi/liter and a range of 44.6 to 140 pCi/liter. 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 eighteen out of the twenty-four quarterly composite samples.
The average tritium activity for all the indicator stations was 512 pCi/liter with a range of 180 to 2700 pCi/liter. The average tritium activity of Surry Discharge was 985 pCi/liter with a range of 230 to 2700 pCi/liter. For the control stations (Chickahominy and Scotland Wharf) the average concentration was 328 pCi/liter with a range of 290 to 420 pCi/liter.
Except for the one high sample (2700 pCi/liter) from the Surry Discharge station, 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/liter).
As part of the State Split Program, samples are collected from Scotland Wharf (control) and Surry Discharge (indicator) locations. Scotland Wharf is taken as a weekly grab sample.
Surry Discharge is sampled by a composite sampler and collected weekly. Monthly composites are prepared for gamma analysis and iodine-131 by a radiochemical procedure.
Quarterly composites are prepared for tritium analysis. The results are presented in Table-B-5.
Naturally occurri_ng potassium-40 was measured in three samples with an average concentration of 65.5 pCi/liter and a range of 55.5 to 80.0 pCi/liter. Only one sample detected any other gamma emitters. The February sample of Surry Discharge detected cobalt-60 with an activity of 10.9 pCi/liter. This value was confirmed by reanalysis.
Tritium was measured in all eight of the quarterly composite samples. The average activity for Surry Discharge was 885 pCi/liter with a range of 210 to 1600 pCi/liter. The
- average for the control location was 322 pCi/liter with a range of 200 to 500 pCi/liter.
- In addition to the weekly grab sample and the State Split composite sampler a VEPCO Surry Discharge composite sampler was placed in service in May 1989. A tritium composite from this sampler was analyzed monthly and then composited for quarterly analysis. The average tritium activity for the last three quarters was 520 pCi/liter with a range of 420 to 690 pCi/liter.
The attached trend graphs provide a comparison of tritium activity measured in the downstream sample (Surry Discharge) and in the upstream control location (Scotland Wharf).
28
Also provided for comparison, is the average concentration of tritium in plant effluent samples obtained prior to release from the station.
As expected, the Surry Discharge samples indicated higher levels of tritium than the control location. Due to the low level of activity discharged and the variation of tritium in the control sample (background), good comparative analysis and trending is difficult. Sampling methodology (grab sample vs. composite) and the frequency may also cause problems in comparing results. The Station Discharge composite sample taken by VEPCO personnel, however does compare well with the station effluents. The trend for the last three quarters, although elevated by mixture of background tri~um, follows the projected activity from samples taken prior to release. The comparison of these two data points is due to the increased frequency of sampling (hourly for the VEPCO samples vs. once per six hours for the state sampler). The water in the discharge canal is further diluted by the river water beyond the discharge structure. The average tritium concentration in grab samples taken downstream of the station indicate normal background concentration.
- 2. Well Water Well water is collected from the four indicator locations during the months of March, June, September and December. Well 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 presented in Table B-6. The samples were analyzed by gamma spectroscopy and indicated that no man made or naturally occurring radionuclides were present. All samples were analyzed to well below the required lower level of detection for gamma emitting radionuclides.
Tritium was measured in five of the sixteen samples with an average activity of 330 pCi/liter and a range of 180 to 490 pCi/liter as indicated by the trend graph. The Surry Station and Jamestown samples collected in December could not be measured for tritium because of sample contamination at the analytical laboratory. However, monthly samples were also obtained from the four indicator locations in October and November. The analysis for these eight samples were all less than 100 pCi/liter.
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 29
e TRENDING GRAPH - 2 TRITIUM IN RIVER WATER u, \.
0 u
- a. 104-t---1------------------------------------1
~
0 >*
ua.
........~******i~~~
103 ____ ~!~-~
........... . . . .~. . . ~ . . . .~** *.**~*. . . .~. . . _,__-___-~:,-~. . . .~. . . .~. . . ~. . . .~. . . .~. . . ~. . . .~. . . .~. . . .~. . . -. .-.,. rt---1
................... ...., ........ t.,............................................................. , .......... , ................... N~r""r~ ....................... ;,.'""\. ............ / ...........
~
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.. **.."* ------- *--~---
102 I
- I I
- I I I I I 68 70 72 74 76 78 80 82 84 86 88 90 Years -----e----* Surry Discharge
........... Scotland Wharf
TRENDING GRAPH - 2 (Cont.)
TRITIUM IN RIVER WATER - 1989 VEPCO VS. STATION EFFLUENT
.....** ]
iI vi l
~
I 1000
~ ..
q --~---*************O....
I }'**************** ""'- #.. :".. ::". - :_*:*- Aar;"' - :-. :"'. :"'.:"'.:-. ~. :". :-. :-. :-. :'°. :-. :-.:-:0: - - - - ,.,*'
___ .....~---*
- ~ ***************-*- *.,,.*" **-*-*-*-*-***-*-*-.":.1 .........- . . . *-*-***-
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....____------..................__.:.::.a....'C't!...--...-*
100 +-----------------.. . .--------....---.......----.i----------------t 1st Qtr. 2ndQtr. 3rd Qtr. 4th Qtr.
- -[J** Station Discharge -*-**- Scotland Wharf --o-- Station Eflluent - -A- - Station Discharge Grab Sample Grab Sample Vepco Composite Sample
e TRENDING GRAPH - 2 (Cont.)
TRITIUM IN RIVER WATER - 1989 STATE SPLIT VS. STATION EFFLUENT i .... l
't'- ..
1000 .,__*;::..,*
~-*** " '_-.............,._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _,..,.. . ; .-***
..**-------1
.. ............. *------------------~r-~~--a---- .. ................ .
lT **
11*-*-* ........ . ..............- -.-.-.-.-.-::.::.::.~..........-.................-*
100-4---------.------.------""T"""--......,...-----,.--------------..------1 ~ ~
lstQtr. 2ndQtr. 3rd Qtr. 4thQtr.
- D** StationDlscharge -*-**- Scotland Wharf ...... ,o..... Station Effluent - -tr - Station Discharge Composite Sample Grab Sample VEPCO Composite Sample
results from the locations other than the Surry Site indicate very little influence of tritium contamination of ground water.
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. The samples are individually bagged and analyzed by gamma spectroscopy. The results are presented in Table B-7.
A number of man-made and natural radionuclides were measured. The man-made radionuclides included cobalt-58, cobalt-60, cesium-134 and cesium-137.
Cobalt-58 and cesium-134 were measured in only one of the twelve samples taken in 1989. Since 1986, this represents a decrease in the number of samples in which cobalt-58 and .
cesium-134 have been detected from five to one and nine to one respectively. As expected, these two radionuclides were only detected at the Surry Station Discharge sample location.
The cobalt-58 activity was 83.4 pCi/kg (dry weight) and the cesium-134 activity was 184 pCi/kg (dry weight).
Cobalt-60 and cesium-137 were measured in all silt samples. Due to the longer half life of these two radionuclides their presence was expected. Also, as suspected, the Surry Station Discharge sample location provided the highest activity. Samples from the downstream sample locations of Hog Island Point, Surry Intake, Point of Shoals and Newport News generally indicate the dilution provided by the James River.
33
- TRENDING GRAPH - 3 TRITIUM IN WELL WATER 10000 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ,
I 1000
~.,.,
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....... ~~-.,,..- ..0.::. ***. *************'\.i.........................................; ~
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......... 0........ Station-BC
>t----* Station-HIR
0---* Station-JMTN
- -ts- -
- Station-SS
The average cesium-137 activity at the Surry Station Discharge was 1040 pCi/kg (dry 4I weight) and a range of 630 to 1450 pCi/kg (dry weight). The average from the ten indicator samples was 549 pCi/kg (dry weight) and a range of 240 to 1450 pCi/kg (dry weight). The average from the control (Chickahominy) was 611 pCi/kg (dry weight) and a range of 556 to 666 pCi/kg (dry weight).
The average cobalt-60 activity at the Surry Station Discharge was 947 pCi/kg (dry weight) and a range of 394 to 1500 pCi/kg (dry weight). The average from the indicator sample location was 391 pCi/kg (dry weight) and a range of 62 to 1500 pCi/kg (dry weight).
The average from the control (Chickahominy) was 250 pCi/kg (dry weight) and a range of 218 to 281 pCi/kg (dry weight).
As presented in the trend graphs, the sample analysis results indicate a decrease in man-made radionuclides since 1986. However, during 1989 an increase in activity was evident for the Surry Station Discharge sample location. This corresponds with the data from the semiannual Radioactive Effluent Report as the activity in the 1989 liquid effluent increased approximately 33% over the 1988 liquid effluent activity. At the same time, dilution water available to the power station was reduced due to intake canal level instrumentation modification. For a nine month period beginning with the fourth quarter of 1988 and extending through the second quarter of 1989 dilution water available to the power station was reduced by a factor of seven as compared to the dilution water available in 1986, 1987 and the second half of 1989.
The increased activity in silt is not projected to be long term. Surry Power Station currently has under construction a Radwaste Treatment Facility which will employ state of the art technologies to reduce the volume and activity of liquid effluents and thus the impact on the environment.
The results of analysis of the samples as presented in the trend graphs, indicate that all the man-made radionuclides indicate a decreasing trend except for the Surry Discharge location.
- 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
- e. using the shoreline for commercial or recreational purposes. Samples were 35
taken in March and August at Hog Island Reserve and Burwell's Bay. The samples were
- analyzed by gamma spectroscopy. The results are presented in Table 8.
The analytical results indicated the predominance of three naturally occurring radioisotopes:-- Potassium-40 was measured in all samples at an average concentration of 3648 pCi/kg (dry weight) and a range of 1530 to 6580 pCi/kg (dry weight). Radium-226 was measured in two of the four samples with an average concentration of 383 pCi/kg (dry weight)
- i and a range of 330 to 435 pCi/kg (dry weight). Thorium-228 was also measured in two samples with an average of 128 pCi/kg (dry weight) and a range of 94.9 to 161 pCi/kg (dry weight). No radionuclides attributable to the operation of the power station were detected in 1989. This is in line with the decreasing trend in activity as seen over the previous years.
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 deposited 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 B-
- 9. 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; a lower limit of detection 0.5
- pCi/liter or better was achieved in all samples.
Naturally occurring potassium-40 was detected in all samples. The average for the control location (WMS) was 1408 pCi/liter and the range was 1150 to 1920 pCi/liter. The average measurement for the 48 indicator samples was 1372 pCi/liter with a range of 1070 to 1560 pCi/liter.
- 36
TRENDING GRAPH - 4 COBALT-58 IN SILT A
\
\
I .\
I \
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,, , \
1
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1000 * .............................................................................. A .......................................................................................f*******L ............... , .................................',.......................................
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I 10-t--t.r--,,r--T""""..--,'T.--Y1--,.r--,r-T"""".,--,~-.,r--,r--T"""",,--T,--,.-...,--r-r-,,-- ....,--,..--,,...-.r-..--,"T.--Y1--,--r-,,--T1....,....,,--r-- * ..--,-r.--,.,--,.---t 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90
- N-NO--- Hog Island Years
0---* Station Intake
- - ~-
- Station Discharge
TRENDING GRAPH - 5 COBALT-60 IN SILT 100000 10000 *
\
- I 0 I
.A ,- A\ -. .,* '.
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/j 100*:i::::::::::::'~~=:J..~:::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::~
' ,111, .
D 10 ............--.,,--..-~,,--..-~,.--..-~*.--....-~*.--...--,.....~-,--...-,~-....-.~...........................~.--....-.~..--~.,--...-~,--.-.~............~,.--...--~,.------.-.~.----,......-t 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90
........ O ..***** Hog Island Years ----O---* Station Intake
- - fr -
- Station Discharge
e TRENDING GRAPH - 6 CESIUM-134 IN SILT 10000
,A---A,
- , 1000 - .~,,.. . '
en .
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. I I . I I I I I 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90
........o ...,. . Hog Island Years ----O---* Station Intake
---tr-* Station Discharge
TRENDING GRAPH - 7 CESIUM-137 IN SILT 10000 -:i:::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::i Cl) 1000 *
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70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90
- O******* Hog Island
- * *
- O * * ** Station Intake Years ----ls--* Station Discharge
- - ... -* CHIC
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/liter. The data from 1989 identified only one sample with an activity of 8.25 pCi/liter. These results are very close to the lower level of detection and are well below the required detection level of 18 pCi/liter. 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 all twelve indicator samples with an average activity of 2.44 pCi/liter and a range of 1.1 to 6.2 pCi/liter. 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/liter.
- 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 B-10 for clams and Table B-11 for oysters. As expected, naturally occurring potassium-40 was the nuclide most frequently detected.
For the clam samples the average potassium-40 activity was 495 pCi/kg (wet weight) and .
a range from 119 to 872 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 38.1 pCi/kg (wet weight) and a range of 28.7 to 47.4 pCi/kg. The activity measured in the 1983 through 1988 clam samples taken at the same locations is comparable with the 1989 results.
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.
For oyster samples the average potassium-40 activity for 17 of the 23 samples was 517 pCi/kg (wet weight) with a range of 326 to 851 pCi/kg (wet weight). This was lower than 41
\
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 2540 pCi/kg (wet weight) as presented in Table B-12. 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 April and October from the same Surry Discharge location (SD). Potassium-40. was measured in all four samples with an average activity of 1332 pCi/kg (wet weight) and a range of 986 to 1470 pCi/kg (wet weight). The results of gamma spectrometry on these samples are presented in Table B-13.
Cesium-137 was observed in one of the fish samples with an activity of 17.5 pCi/kg (wet weight). The results from the 1989 fish samples indicated good agreement with the one measured cesium-137 result of 17.7 pCi/kg (wet weight) in 1988. 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). Thus, the levels of cesium-137 continue to decrease. All other gamma emitters were well below the LLDs required in Table 2 with no positive activity detected.
- 3. Food ProductsNegetation
- l Four food samples were collected from four locations and analyzed by gamma spectrometry. The results are presented in Table B-14. The samples consisted of kale, b!occoli and cabbage. 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 4908 pCi/kg (wet weight) and a range of 2180 to 6060 pCi/kg (wet weight). Cosmogenic beryllium-7 was measured in two samples with an average activity of 177 pCi/kg (wet weight) and a range of 72.7 to 281 pCi/kg (wet weight). These results compare favorably with previous years.
42
TRENDING GRAPH - 8 COBALT-58 IN CLAMS
\
i I \
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I I
1~..- .. \
.0
.,"' ' ,P--.,*-0---0---0---q'
. ......-~\. /,' '
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.............................................. ~ ............................................................................................. ~ - - o.- - --q\ . . . . . . '\\. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
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-...~-, \
- v .* ,,'.,
0--.;.,0 10 I I " I I " I I I " I
- I I
- I I I I I "
1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990
**O***** Chickahomtny
---a-- Suny Discharge
- Hog Island
e TRENDING GRAPH - 9 COBALT-60 IN CLAMS 1000 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
i I
II l
~I I \
n-\--u-i/ I
.,., /
I '+
't., -------*-....
\
\ /
' 'cl \Jr-----*----- -
,,.. ,, ...... 0---0\. .
\
\ ... ,.u
'* ti/
10
- I I I ' I I I ' I I . I I " I I I I
- 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990
- ----o--* Chickahomlny
---m-- Surry Discharge
- Hog Island
TRENDING GRAPH - 10 CESIUM-137 IN CLAMS 1000 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ,
i I
.n
~
en l '
~
I I 100 1-
~
\ ,.
\
- r 1~,. .
\ \
//I \ .,0
\\ti;~,, ....*;/........................................................................................,~:--..... \-1(,,*.........................................................................................
~,
M'
, '\ , ,,
Ii
,,,, ,....u., ~',' ,.\.
,'--_ ...... -~ ,,
,_ - --~
\ ..\J ......
h ', -a
-.... ~o..' , ..
10
- I I I
- I
- I I I
- I I
- I I
- I I
- I
- I
- 1974 1975 1976 1977 1978 1979 1980 198_1 1982 1983 1984 1985 1986 1987 1988 1989 1990
......o ..*** Chlckahomlny
Surry Discharge
- -a-* - Hog Island
D. Direct Radiation Exposure Pathway
- 1. Thermoluminescent 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 residences. 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 process~d 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 B-15 and B-16.
A statistical summary of the four quarters 1989 data is provided in Appendix A.
Individual measurements of external radiation levels in the environs of the Surry site for stations 02 through 43 had an average dose of 6.2 mR/standard month period. The average dose for the control stations (39,40) was 5.5 mR/standard month and the average dose for the indicator stations was 6.3 mR/standard month. The range for the control locations was 4.0 to 7 .0 mR/standard month and for the indicator locations was 3.9 to 8. 7 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.
46
TRENDING GRAPH-II DIRECT RADIATION MEASUREMENTS-TLD RESULTS 100~---------------------------------
u, 0
u Q.
-..J
.c C
0
- E 10
~
ca "O
C ca u,
a:
E I
, i
, I 1----.----.....---.-----.----.---.---.---.--..----.----.---..----.--.--..---.--
1900 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990
.........9........ Site Boundary
- - ..... -
- 5 Mile Boundary
V. CONCLUSIONS 48
V. CONCLUSIONS The results of the 1989 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 a few 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 1989 appear to e 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-7 and potassium-40). No man-made activity was found in the particulate media during 1989. No iodine-131 was detected in charcoal filters in 1989.
Many river water samples were collected and analyzed for radioactivity. Only one sample from the Station Discharge location detected any gamma emitters that were attributable to the power station. The activity was within the projected activity for periodic discharge and was 1% of the reporting level concentrations.
Tritium activity was measured in many river water samples with the highest activity, as expected, at the Surry Discharge location. In the discussion section of this report several samples were compared with planned station effluents. The VEPCO composite samples collected and analyzed during the last three quarters compared well with the planned effluents. The average activity in the VEPCO composite was 520 pCi/liter while the planned activity for the last three e
49
quarters was 300 pCi/liter. The variance between planned releases and actual measurements is due e to the background tritium in the river water.
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 fish by man. The concentration of tritium in the VEPCO composite sample _of the Station Discharge represents 1.7% of the reporting level concentration. The discharge is further diluted when mixed with the upstream river water.
Tritium was also detected in well water samples taken from the vicinity of the power station. Five of the sixteen well water samples for 1989 had measurable concentrations of tritium.
Ground water is not normally considered to be affected by station operations since there are no discharges to this supply. The samples taken in the first half of 1989 at Surry Station, however, indicate a slightly higher level of tritium than the other three indicator locations.
As rp.entioned in the 1988 Environmental Report, an increased frequency of sampling was initiated to determine the cause for the variation in the tritium activity. Two samples taken in the fourth quarter for Jamestown and Surry sites were cross-contaminated at the vendor lab and the data replaced with a composite of monthly samples taken at the same location. These samples e detected no tritium activity. Monthly samples collected during the first two quarters indicated no tritium activity present at the Surry site.
The average tritium activity from the Surry Station samples taken during the first and second quarters represents 2.3% of the reporting level concentration for drinking water. Monthly sampling will continue to be collected to determine if cross contamination problems at the vendor lab still exists.
Although silt itself does not constitute a direct dose pathway for humans, silt does provide a sensitive indicator of potential discharges from nuclear power stations. Silt samples were collected semiannually from each of six locations and analyzed for gamma emitting radionuclides.
Cobalt-60 and cesium-137 were measured in all silt samples with the highest concentrations measured, as expected at the Surry Station Discharge.
The preoperational
- program analyzed silt samples but found no gamma emittmg radionuclides above the sensitivity of the analysis (<5000 pCi/kg dry weight). The current sensitivity is approximately 180 pCi/kg (dry weight). The low sensitivity of the preoperational e
so
sample analysis eliminates the ability to make direct comparisons to operational data. A review of the trend graphs indicate that all of the contaminants show a continued decline in levels except for the Surry Discharge location. A review of the data table indicates that the sample taken in the first quarter detected higher activity while the sample taken in the third quarter indicates the near normal activity. The averages of these two samples is displayed in the trend graphs. The highest activity seen during the first quarter may be expected because of the higher activity discharged and the lower dilution water used during that period.
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 collected_semiannually at two locations and analyzed for gamma emitting radionuclides. Only the naturally occurring isotopes, potassium-40, radium-226, and thorium-228 were detected and the concentrations were at normal background activities. There is no evidence of radioactivity released from station effluents. Therefore, there was no evidence of impact from station operation on this dose pathway..
Milk samples are an important indicator for measuring the affect of radioactive iodine-131 in particular, and other radionuclides in airborne releases from a power station. Sixty milk samples were collected from five locations and analyzed for iodine-131 and for gamma emitting radionuclides.
Iodine-131 was not measured in any of the sixty milk samples. Naturally occurring potassium-40 was detected in all the samples at normal concentrations. 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 1989 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.
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 the 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 m~m. Clam samples from 1989 indicate the presence of low level man-made co_balt-60 in two of the 30 51
samples. This activity was determined at levels well below the required sensitivity. Comparison of the 1989 data to 1983-1988 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), therefore these cannot be compared to the low level activity found in the 1983-1989 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 1989 was 0.38% of the reporting level concentrations for cobalt-60 for the two results above the detection limit 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, therefore the data is not comparable to the gamma analysis. The concentration of cesium-137 in this one positive result represents 0.88% of the reporting level concentrations. Since 1984, detectable levels of cesium-137 has steadily decreased from 87.1 to 17.5 pCi/kg.
A broad leaf vegetable sample was collected at each of five gardens during the harvest season and was analyzed for gamma emitting radionuclides. Potassium-40 was measured at background levels in all samples. Beryllium-?, also naturally occurring, was measured in two of the samples. No other gamma emitting radionuclides were detected, thus there was no affect from the nuclear station on the vegetable samples.
The direct exposure pathway as measured in the environment of the Surry site by thermoluminescent dosimetry has remained essentially the same at 6 milliroentgens per month or 0.2 milliroentgen per day. The average dose levels monitored have shown a normal fluctuation about these levels which are less than the estimated whole body dose due to natural terrestrial and cosmic radiation and the internal dosage from natural radionuclides.
Based upon the evidence of the environmental monitoring program the Surry Power Station appears to be operating within regulatory limits. Where possible, good correlations existed between planned 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.
52
VI. REFERENCES 53
VI. REFERENCES
- 1. United States Nuclear Regulatory Commission, Regulatory Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants", December, 1975.
- 2. Virginia Electric and Power Company, Surry Power Station Technical Specifications, Units 1 and 2.
- 3. NUREG 0472, "Radiological Effluent Technical Specifications for PWRs", Rev. 3, March 1982.
- 4. United States Nuclear Regulatory Commission Regulatory Guide 1.109, Rev. 1, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I", October, 1977.
- 5. USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979.
54
APPENDIX A RADIOLOGICAL ENVIRONMENT AL MONITORING PROGRAM
SUMMARY
55
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1989 ANALYSIS AND LOWER LIMIT NUMBER OF MEDIUMORPATIIWAY TOTAL NUMBER OF AIL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSF.S DETECTION MEAN NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENl) PERFORMED (U.D)(l) RANGE DISTANCE AND DIREcnON RANGE RANGE MEASUREMENTS Air Iodine 1-131 416 0.07 -(0/364) NIA NIA -(0152) 0 (pCi/m3)
Airborne Gross Beta 416 10 17.4(364/364)) All. 5.1 mi WSW 18.4(52152) 17 .8(52152) 0 Particulates (2.5-42) (6.3-42) (6.5-36)
(lE-03 pCiJm3)
Gamma 32 01 0\ Be-7 32 63.6(28/28) CP 3.7mi NNW 70.3(414) 66.3(414) 0 (40.7-124) (42.8-124) (49.5-93.1)
K-40 32 130 3.93(4/28) NN 16.5 mi ESE 5.96(114) 5.96(114) 0 (3.32-4.53)
(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.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRYCOUNTY,VIRGINIA JANUARY 1 to DECEMBER 31, 1989 ANALYSIS AND LOWER LIMIT NUMBER OF MEDIUMORPATIIWAY TOTAL NUMBER OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (U.D)(I) RANGE DISTANCE AND DIRECl10N RANGE RANGE MEASUREMENTS River Water (a) Gamma 48 (pCi/liter)
K-40 48 84.7(6142) NN 12.0mi SE 118.9(216) -(016) 0 (44.6-140) (97.7-140)
Tritiwn 24 2000 486(16/20) SD 0.17mi NW 985(414) 260(214) 0 (Quarterly) (180-2700) (230-2700) (230-290)
U1
-...i River Water (b) Gamma 24 (pCi/liter - State Split)
K-40 24 0 65.5(3112) SD 0.17 mi NW 65.5(3112) -(0112) 0 (55.5-80.0) (55.5-80.0)
Tritiwn 24 2000 885(414) SD 0.17mi NW 885(414) 323(414) 0 (Quarterly) (210-1600 (210-1600) (200-500)
Well Water Gamma 16 (pCi/liter)
K-40 16 -(0116) NIA NIA NONE 0 Tritiwn 16 2000 330(5116) SS Onsite 470(214) NONE 0 (Quarterly) (180-490) (440-490)
(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. *
(a) Analyses for monthly and bi-monthly samples listed in Table B-4 (b) Monthly State Split analyses presented in Table B-5.
e RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY I to DECEMBER 31, 1989 ANALYSIS AND LOWER LIMIT NUMBER OF MEDIUM OR PATHWAY TOfAL NUMBER OF Al,L 11::!DICATOB. l,OCAIIQ~S LQCATION WIIH IIIQHF.ST MEAi::! CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN NAME MEAN MEAN REPORTED (UNIT OF MEASUREMEN1) PERFORMED (LLD)(!) RANGE DISTANCE AND DIRECl'ION RANGE RANGE MEASUREMENTS Slit Gamma 12 pCi/kg (dry)
Be-7 12 1190(1/10) POS 6.4 mi SSE 1190(1/2) -(0/2) 0 K-40 12 12180(10/10) POS 6.4 mi SSE 14200(2/2) 13400(2/2 0 (7710-16100) (13800-14600) (12300-14500)
Co-58 12 83.4(1/10) SD 0.5miNNW 83.4(1/2) -(0/2) 0 U1 00 Co-60 12 391(10/10) SD 0.5miNNW 947(2/2) 250(2/2) 0 (62-1500) (394-1500) (218-281)
Cs-134 12 150 184(1/10) SD 0.5miNNW 184(1/2) -(0/2) 0 Cs-137 12 180 549(10/10) SD 0.5miNNW 1040(2/2) 611(2/2) 0 (240-1450) (630-1450) (556-666)
Ra-226 12 1479(10/10) CHIC 11.2 mi NNW 2275(2/2) 2275(2/2) 0 (891-1910) (2110-2440) (2110-2440)
Th-228 12 896(10/10) CHIC 11.2 miNNW 1100(2/2) 1110(2/2) 0 (615-1330) (990-1220) (990-1220)
(1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision I, November 1979.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUN1Y, VIRGINIA JANUARY 1 to DECEMBER 31. 1989 ANALYSIS AND LOWER LIMIT NUMBEROF MEDIUM OR PATIIWA Y TOfAL NUMBER OF AIJ, INDICATOR LOCATIONS LOCATION WITH HIGHF.ST MEAN CONTROL LOCATION NONROUflNE SAMPLED OF ANALYSES DETECl10N MEAN NAME MEAN MEAN REPORTED (UNIT OF MEASUREMEN1) PERFORMED (UD)(I) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Shoreline Sediment Gamma Spec 4 (pCi/kg dry)
K-40 4 3648(4/4) HIR 0.8 miN 5105(2/l) NONE 0 (1530-6580) (3630-6580)
CJ1 Ra-226 4 382(2/4) Burwell's 7.76 mi SSE 435(1/l) NONE 0 U) (330-435)
To-228 4 128(2/4) Burwell's 7.76 mi SSE 161(1/l) NONE 0 (94.9-161)
(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.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1989 ANALYSIS AND LOWER.LIMIT NUMBBlOF MEDIUMORPATIIWAY TOTAL NUMBBl OF AU, INDICATOR LOCATIONS LOCATION WWI HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PBlFORMED (LLD)(l) RANGE DISTANCEANDDIREcrION RANGE RANGE MEASUREMENTS Milk Gamma 60 (pCi/litcr)
K-40 60 1372(48148) WMS 22.5mi S 1408(12112) 1408(12112) 0 (1070-1560) (1150-1920) (1150-1920) 1-131 60 l -(0148) NIA NIA -(0112) 0 C]\
0 Cs-137 60 10 8.25(1148) JDKS 6.2 mi SSW 8.25(1/12) -(0112) 0 Sr-89 12 -(0112) NIA NIA -(010) 0 Sr-90 12 2.44(12112) CP 3.7mi NNW 3.88(414) -(0/0) 0 (l.1-6.2) (1.8-6.2)
(1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision I, November 1979.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRYCOUNTY,VIRGINIA JANUARY 1 to DECEMBER 31, 1989 ANALYSIS AND LOWER LIMIT NUMBER OF MEDIUM OR PATIIWA Y TOTAL NUMBER OF ALL l!SOl!::AIQB. LOCAIIQ!SS I..Q!::AIION WITH HJ!;z~I MBA!S CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DE'IBCfION MEAN NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENl) PERFORMED (UD)(l) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Clams GammaSpec 30 (pCi/kg wet)
K-40 499(20/25) SD l.3miNNW 573(5/6) 474(4/6) 0 (119-872) (416-872) (330-550)
Co-60 130 38.1(2/25) SD l.3miNNW 47.4(1/6) -(0/0) 0 (28.7-47.4 CJ\
I-'
Oysters Gamma Spec 23 (pCi/kg wet)
K-40 517(17/23) POS 6.4 mi SSE 619(3/6) NONE 0 (326-851) (502-851)
Crabs GammaSpec 1 (pCi/kg wet)
K-40 2540(1/1) SD l.3mi NNW 2540(1/1) NONE 0 Fish GammaSpec 4 (pCi/kg wet)
K-40 1332(4/4) SD 1.3 mi NNW 1332(4/4) NONE 0 (986-1470) (986-1470)
Cs-137 150 17.5(1/4) SD 1.3 miNNW 17.5(1/4) -(0/0) 0 (1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision l, November 1979.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31. 1989 ANALYSIS AND LOWER LIMIT NUMBEROF MEDIUMORPAlHWAY TOTAL NUMBEll OF ALL INDICATOR LOCATIONS LOCATION wrrn HIGHEST MEAN CONTROL LOCATION NONROUflNE SAMPLED OF ANALYSES DETECTlON MEAN NAME MEAN MEAN REPORTED (UNIT OF MEASUREMEN1) PERFORMED {llD)(l) RANGE DISTANCE AND DIREcrION RANGE RANGE MEASUREMENTS Direct Radiation Gamma 333 2 6.3(317/317) 38 16.5 mi ESE 7.9(8/8) 5.5(16/16) 0 n..Ds (3.9-8.7) (6.9-8.7) (4.0-7.0)
(mR/std. month)
Vegetation Gamma 4 (pCiJkg wet)
°'
N K-40 4 4908(4/4) Chesterfield's Garden 6060(1/1) NONE 0 (2180-6060)
Be-7 4 177(2/4) Chesterfield's Garden 281(1/1) NONE 0 (72.7-281)
(I) 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.
APPENDIX B DATA TABLES 63
e e TABLE B-1 (Page 1 of4)
SURRY-1989 CONCENTRATIONS OF IODINE-131 IN FILTERED AIR pCi/m3 +/- 2 Sigma STATIONS COLLEC'IlON DATE ss HIR BC ALL CP DOW FE NN
,JANUARY 01/03/89-01/10/89 < .02 <.02 < .01 < .01 < .02 < .02 <.02 <.02 Ol/10/89-01/17/89 < .01 < .02 < .01 < .01 < .01 < .01 < .01 < .01 01/17/89-01/24/89 < .02 < .02 < .02 < .02 < .01 < .01 <.02 < .02 01/24/89-01/31/89 < .02 < .02 <.02 < .02 < .02 < .02 <.02 <.02
°'
~
FEBRUARY Ol/31/89-02/07/89 < .02 < .02 < .02 < .02 < .01 < .01 < .01 < .01 02/ffl/89-02/14/89 < .02 <.02 <.02 < .02 <.02 <.02 < .02 < .02 02/14/89-02/21/89 < .02 < .02 <.02 < .02 < .02 < .02 <.02 < .02 01/21/89-03~1/89 < .02 <.02 <.02 < .02 < .01 < .01 < .01 < .01 MARCH 03/0l/89-03J1)6189 < .03 < .03 < .03 < .02 <.02 < .02 <.02 < .02 03/06/89-03/14/89 < .01 < .01 < .01 < .01 < .01 < .01 < .01 < .01 03/14/89-03!21/89 < .02 < .02 <.02 <.02 <.03 < .03 < .03 < .03 03122/89-03!28/89 <.02 < .02 < .02 < .02 < .02 < .02 <.02 < .02 03!28/89-04,01/89 < .01 < .01 < .01 < .01 < .01 < .01 < .01 < .01
e e TABLE B-1 (Page 2 of4)
SURRY - 1989 CONCENTRATIONS OF IODINE-.131 IN FILTERED AIR pCi/m3 +/- 2 Sigma STATIONS COLLEC110N DATE ss HIR BC ALL CP DOW FE NN AelUL 04/04/89-04/l l/89 < .01 < .01 < .01 < .01 < .02 < .02 < .02 < .02 04/l l/89-04/18/89 < .02 < .02 < .02 < .02 < .02 <.02 <.02 <.02 04/18/89-04/25/89 < .02 <.02 < .02 < .02 < .02 < .01 < .01 <.01 04/25/89-05/00l89 < .02 < .02 < .02 < .02 < .02 < .02 < .02 < .02
°'
V'I MAY 05/CYl./89-05/00/89 < .02 < .02 < .02 < .02 < .01 < .01 < .01 < .02 05/09/89-05/16/89 < .02 < .02 < .02 <.02 <.02 < .02 < .02 < .02 05/16is9-05/23/89 < .01 < .01 < .01 < .01 < .02 < .02 < .02 < .02 05/23/89-05/30/89 < .01 < .01 < .01 < .01 < .01 < .01 < .01 < .01
.l1llS.E 05/30/89-06,o6/89 < .02 <.02 < .02 < .03 < .01 < .01 < .01 <.02 06/06/89-06/13/89 < .02 < .02 < .02 <.02 < .02 < .02 < .02 <.02 06/13/89-06/20/89 < .02 < .02 < .02 <.02 < .01 < .01 < .01 < .02 06f}l}/89-06/28/89 < .02 < .02 < .02 < .02' < IO (a) < .02 < .02 < .02 (a) Blown fuse; results in total pCi.
e e e TABLE B-1 (Page 3 of 4)
SURRY-1989 CONCENTRATIONS OF IODINE-131 IN FILTERED AIR pCi/m3 +/- 2 Sigma STATIONS COLLECTION DA1E ss HIR BC ALL CP DOW Jt'E NN
~
06/2Jj/89--07/05/89 < .02 <.02 < .02 < .02 <.02 < .02 <.02 < .02 07/05/89--07/l l/89 < .02 < .02 < .01 < .01 < .03 <.03 < .03 < .03 07/l 1/89--07/18/89 < .01 < .02 < .01 < .01 < .02 < .02 < .02 < .02 07/18/89--07/25/89 < .02 < .02 < .02 < .02 < .01 < .01 < .01 < .01 07/25/89--08/01/89 < .02 < .02 < .02 < .02 < .01 < .01 < .01 < .01 C]\
C]\
AUGUST 08/01/89--08/08/89 < .01 < .01 < .01 < .01 < .02 < .02 < .02 < .02 08/08/89--08/15/89 < .01 < .01 < .01 < .01 < .02 < .01 < .01 < .01 08/15/89--08/22/89 < .02 < .02 < .02 <.02 <.02 < .02 < .02 < .02 08/22/89-08/29/89 < .01 < .01 < .01 < .01 <.02 < .02 <.02 <.02 SEPTEMBER 08/29/89--09/05/89 < .02 <.02 < .02 < .02 <.02 <.02 < .02 < .02 09/05/89--09/12/89 < .01 < .01 < .01 < .02 < .01 < .01 < .01 < .01 09/12/89--09/19/89 < .01 < .01 < .01 < .01 <.02 < .02 < .02 < .02
/19/89--09/26/89 < .02 < .02 <.02 < .02 < .01 < .01 < .01 < .01
/26/89-10/03/89 < .02 <.02 < .02 <.02 <.02 < .02 < .02 < .02
e e TABLE B-1 (Page4 of 4)
SURRY -1989 CONCENTRATIONS OF IODINE-131 IN FILTERED AIR pCi/m3 +/- 2 Sigma STATIONS COUF..C'IlON DATE ss BIR BC ALL CP DOW FE NN OCTOBER 10/03/89-10/10/89 < .01 < .01 < .01 < .01 < .02 < .02 < .02 < .02 10/10/89-10/17/89 < .02 < .02 < .03 <.02 <.03 <.02 < .02 < .02 10/17/89-10/24/89 < .01 < .01 < .01 < .01 < .01 < .01 < .01 < .01 10/24/89-10/31/89 < .02 <.02 < .02 < .02 < .02 < .02 < .02 < .02 0\
~
NOVEMBER 10/31/89-11/07/89 < .02 <.02 < .01 < .01 < .01 < .01 < .01 < .01 11/07/89-11/14/89 < .02 < .02 <.02 <.02 < .01 < .01 < .01 < .01 l l/14/89-11/21/89 < .02 < .02 < .02 < .02 < .02 <.02 < .02 < .02 ll/21/89-11/28/89 < .01 < .01 < .01 < .01 < .01 < .02 < .02 < .02 DECEMBER ll/28/89-12/05/89 < .o3 < .03 <.03 < .03 < .01 <.01 < .01 < .01 12/05/89-12/12/89 < .02 < .02 < .02 < .02 < .02 <.02 < .02 < .02 12/12/89-12/19/89 < .02 < .02 < .02 <.02 < .01 < .01 < .01 < .01 12/19/89-12/26/89 < .01 < .01 < .01 < .02 < .01 < .01 < .01 < .01 12/26/89-0 l,{)2/90 < .02 < .02 < .02 <.02 < .02 < .02 < .02 < .02
e e TABLE 8-2 (Page 1 of 4)
SURRY-1989 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES 10-3 pCi/m3 +/- 2 Sigma STATIONS Average COLLECTION DA1E ss HIR BC ALL CP DOW FE NN +/- 2 s.d.
JANUARY Ol/03/89-01/10/89 15+/-2 25+/-2 24+/-2 23+/-2 18 +/- 2 21 +/-2 22+/-2 23+/-2 21 +/-7 Ol/10/89-01/17/89 21 +/-2 22+/-2 20+/-2 21 +/-2 19+/-2 22+/-2 20+/-2 22+/-2 21 +/-2 01/17/89-01124/89 20+/-2 17+/-2 19+/-2 20+/-2 16+/- 2 15 +/-2 18 +/- 2 18 +/- 2 18 +/-4 01/24/89-01/31/89 19+/-2 20+/-2 25+/-2 17+/-2 23+/-2 26+/-2 22+/-2 22+/-2 22+/-6 FEBRUARY
°'
00 01/31/89-02/07/89 18 +/- 2 15+/-2 21 +/-2 19+/-2 13+/- 2 18 +/- 2 16 +/- 2 15 +/- 2 17 +/- 5 02J07/89-02/14/89 13 +/- 2 19+/-2 23+/-2 20+/-2 15 +/- 2 13 +/- 2 17 +/- 2 17+/- 2 17+/-7 02Jl4/89-02!21/89 14+/-2 17 +/-2 21 +/-2 17 +/- 2 17 +/- 2 16+/-2 14+/-2 20+/-2 17+/- 5 02J21/89-03'1>1/89 17 +/-2 15 +/-2 19+/-2 17 +/- 2 15 +/- 2 11 +/- 1 15 +/- 2 17+/-2 16+/- 5 MARCH 03/01/89-03'1)6/89 14+/-2 17+/-2 13+/-2 16+/-2 15 +/- 2 15 +/- 2 14+/-2 14+/- 2 15 +/- 3 03/06/89-03/14/89 15+/-2 15 +/-2 15 +/- 2 13 +/- 2 16+/-2 16+/-2 16 +/- 2 17+/-2 15 +/- 2 03/14/89-03!22J89 17+/-2 18 +/-2 17+/-2 18 +/-2 16+/- 2 18 +/-2 16+/-2 17+/-2 17 +/- 2 03/22/89-03!28/89 12+/-2 11 +/-2 12+/-2 12+/-2 13+/- 2 11 +/-2 13 +/- 2 11 +/-2 12+/- 2 Quarter Average 16 +/- 6 18 +/- 7 19 +/- 8 18 +/- 6 16 +/- 5 17 +/- 9 17 +/- 6 18 +/- 7 17 +/- 2
+/- 2 s.d.
~
TABLE 8-2 (Page 2 of 4)
SURRY -1989 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES 10-3 pCi/m3 +/- 2 Sigma STATIONS Average COll.ECTION DA1E ss HIR BC ALL CP DOW FE NN +/- 2 s.d.
AfRlL 03/28/89-04/04/89 13+/- 2 14+/-2 15 +/- 2 13 +/-2 12+/- 2 9.7 +/- 1.5 16 +/- 2 13+/-2 13 +/-4 04/04/89-04/11/89 12+/-2 12+/-2 14+/-2 12+/-2 13+/-2 12+/-2 13 +/- 2 13 +/- 2 13+/-2 04/l l/89-04/18/89 18 +/-2 13+/-2 19+/-2 19+/-2 19+/- 2 17 +/-2 20+/-2 17 +/- 2 18 +/-4 04/18/89-04/25/89 22+/-2 19+/-2 17 +/- 2 21 +/-2 23+/-2 19+/-2 16 +/- 2 20+/-2 20+/-5 04/25/89-05,{}2/89 11 +/-6 16+/-2 16+/- 2 14+/-2 15 +/- 2 15 +/-2 16 +/- 2 14+/- 2 15 +/- 3 0\
~ Mil 05/02/89-05/09/89 9.8 +/- 1.5 12+/-2 14 +/- 2 11 +/- 2 9.5 +/- 1.5 12+/-2 13 +/-2 16+/- 2 12 +/-4 05/09/89-05/16/89 14+/-2 14+/-2 15 +/- 2 14+/-2 13+/-2 15 +/- 2 14 +/- 2 14+/- 2 14+/- 1 05/16/89-05/23/89 14+/-2 14 +/-2 15 +/- 2 14+/-2 16 +/- 2 16 +/- 2 15 +/- 2 17 +/- 2 15 +/- 2 05/23/89-05/30/89 16+/- 2 13+/-2 15 +/- 2 15 +/- 2 14 +/- 2 14+/-2 14 +/-2 16+/- 2 15+/-2
.ll1n 05/30/89-06,{)6189 18 +/- 2 17+/-2 18 +/- 2 26+/- 3 (a) 16+/- 2 10+/-2 18 +/- 2 21 +/- 2 18 +/- 9 06/06/89-06/13/89 11 +/-2 12+/-2 13+/-2 12+/-2 10+/-2 12+/-2 12 +/- 2 13+/- 2 12+/- 2 06/13/89-06/20/89 16+/-2 13+/-2 16 +/- 2 17 +/-2 13+/-2 13+/-2 19 +/- 2 18 +/- 2 16+/- 5 06/20/89-06/28/89 14+/-2 10+/- 1 14+/- 2 13 +/- 1 2.5 +/- 0.6 (b) 12 +/- 1 14 +/- 2 16+/- 2 12+/- 8 Quarter Average 15 +/- 7 14 +/- 5 15 +/- 3 15 +/- 9 14 +/- 8 14 +/- 6 15 +/- 5 16 +/- 5 15 +/- 1
+/- 2 s.d.
(a) Elevaled result due to low air volwne. Timer and sampler appeared to be operating normally, however, the timer registered less than the usual nwnber of hours recorded for a sampling week. The nwnber of hours as indicated on the timer was used for sample volwne calculation.
(b) Blown fuse; results in total pCi. Not included in averages.
e -TABLE B-2 e
(Page 3 of 4)
SURRY-1989 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES 10-3 pCi/m3 +/- 2 Sigma STATIONS Average COLI..ECTION DA1E ss HIR BC ALL CP DOW FE NN +/- 2 s.d.
J..J.!.ll 06/28/89--07/05/89 15+/-2 14+/-2 17 +/- 2 13+/-2 16+/- 2 14 +/-2 16+/- 2 16+/-2 15 +/- 3 07/05/89--07/l l/89 20+/-2 18 +/-2 21 +/-2 21 +/-2 19+/-2 20+/-2 23+/-2 19+/- 2 20+/-3 07/11/89--07/18/89 14+/-2 17+/-2 15+/-2 16+/-2 15 +/- 2 14+/-2 15 +/-2 17 +/- 2 15 +/- 2 07/18/89--07/l5/89 13 +/-2 12+/-2 12+/-2 13+/-2 11 +/-2 12 +/-2 13 +/- 2 12+/- 2 12+/- 1 07/l5/89-08/0l/89 16+/-2 18 +/-2 16+/-2 14+/-2 15 +/-2 17 +/-2 16+/-2 16+/- 2 16+/-2
~
0 AUGUST 08/01/89--08/08/89 19+/-2 21 +/-2 24+/-2 21 +/-2 20+/-2 21 +/-2 22+/-2 21 +/- 2 21 +/- 3 08/08/89--08/15/89 9.0 +/- 1.5 7.5 +/- 1.4 9.6 +/- 1.5 10+/-2 11 +/-2 7.9 +/- 1.4 7.9 +/- 1.4 9.5 +/- 1.5 9+/-2 08/15/89--08/22/89 14+/-2 12+/-2 16+/-2 15 +/- 2 13+/- 2 13 +/- 2 13+/-2 13+/-2 14+/- 3 08/Zl/89--08/29/89 21 +/-2 21 +/-2 16+/-2 19+/-2 21 +/-2 19+/-2 18 +/-2 13+/- 2 19+/- 6 SEPTEMBER 08/29/89--09/05/89 15+/-2 18 +/-2 19+/-2 18+/-2 18 +/-2 19+/-2 19+/-2 18 +/- 2 18 +/- 3 09/05/89--09/12/89 20+/-2 19+/-2 22+/-2 22+/-2 18+/-2 22+/-2 24+/-2 26+/-2 22+/-5 09/12/89--09/19/89 13+/-2 13+/-2 14+/-2 16+/-2 12+/-2 15 +/-2 11 +/-2 12+/- 2 13+/- 3 09/19/89--09/26/89 7.1 +/- 1.4 7.9 +/- 1.5 7.3 +/- 1.4 6.3 +/- 1.4 8.1 +/- 1.5 8.0 +/- 1.5 6.8 +/- 1.4 6.5 +/- 1.4 7+/-1 09/26/89-10/03/89 13+/-2 16+/-2 16+/-2 18 +/-2 17+/-2 18 +/-2 19+/-2 17+/- 2 17+/-4 Quarterly Average 15 +/- 8 15 +/- 9 16 +/- 9 16 +/- 9 15 +/- 8 16 +/- 9 16 +/- 11 15 +/- 10 l6 +/- 1
+/- 2 s.d.
e e e TABLE B-2 (Page4 of 4)
SURRY-1989 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES 10-3 pCi/m3 +/- 2 Sigma STATIONS Average COll..EC110N DA1E ss HIR BC ALL CP DOW FE NN +/- 2 s.d.
OCTOBER 10/03/89-10/10/89 18 +/- 2 18 +/-2 22+/-2 22+/-2 19+/-2 22+/-2 21 +/-2 20+/-2 20+/-4 10/10/89-10/17/89 34+/-3 42+/-3 31 +/-2 42+/-3 34+/-3 39+/-3 38 +/- 3 36+/- 3 37 +/- 8 10/17/89-10/24/89 11 +/-2 14+/-2 14+/-2 13+/-2 12+/- 2 12+/-2 12+/-2 12+/- 2 13+/-2 10/24/89-10/31/89 31 +/- 3 30+/-3 35+/- 3 40+/-3 30+/-3 36+/-3 35 +/- 3 36+/-3 34+/-7
-....i NOVEMBER 10/31/89-11/07/89 22+/-2 21 +/-2 20+/-2 21 +/-2 23+/-2 28+/-2 22+/-2 21 +/- 2 22+/-5 11/07/89-11/14/89 23+/-2 17 +/-2 21 +/-2 17+/-2 19+/-2 22+/-2 21 +/-2 21+/-2 20+/-5 ll/14/89-11/21/89 23+/-2 22+/-2 25+/-2 26+/-2 21 +/- 2 29+/-2 23+/-2 24+/-2 24+/-5 ll/21/89-11/28/89 14+/-2 15 +/-2 16+/-2 17 +/- 2 16+/- 2 16+/-2 15 +/- 2 15 +/-2 16+/-2 DECEMBER ll/28/89-12/05/89 19+/-2 21 +/-2 21 +/-2 20+/-2 21 +/-2 24+/-2 20+/-2 22+/-2 21 +/- 3 12/05/89-12/12/89 18 +/- 2 16+/-2 20+/-2 22+/-2 17+/-2 19+/-2 18 +/- 2 16+/- 2 18 +/- 4 12/12189-12/19/89 26+/-2 26+/-2 25+/-2 29+/-2 26+/-2 29+/-2 28+/-2 27+/-2 27+/-3 l 2/19/89-12/26/89 19+/-2 22+/-2 27+/-2 29+/-3 19+/-2 22+/-2 23+/-2 24+/-2 23+/-7 l 2/26/89-01/02/90 16+/-2 17 +/-2 18+/-2 20+/-.2 15 +/- 2 17 +/-2 18 +/- 2 16+/-2 17+/-3 Quarter Average 21 +/- 13 21 +/- 14 23 +/- 12 24 +/- 17 21 +/- 12 24 +/- 16 23 +/- 15 22 +/- 15 22 +/- 3
+/- 2 s.d.
Annual Average 17 +/- 10 17 +/- 11 18 +/- 10 18 +/- 13 17 +/- 10 18 +/- 13 18 +/- 11 18 +/- 11 18 +/- 1
+/- 2 s.d.
TABLE B-3 (Page 1 of2)
SURRY-1989 CONCENTRATIONS OF GAMMA EMITIERS* IN QUARTERLY AIR PARTICULA1ES 10-3 pCi/m3 +/- 2 Sigma FIRST QUARTER SECOND QUAR1ER THIRD QUARTER FOURTH QUARTER AVERAGE STATION NUCLIDE 01/03-04/04 04/04-06/28 06/28-10/03 10/03-01/02 +/- 2 s.d.
STA-SS Be-7 58.9 +/- 5.9 53.3 +/- 5.3 49.4 +/- 4.9 88.6 +/- 8.9 62.6 +/- 35.6 K-40 <5 4.06 +/- 2.21 <4 <5 4.06 +/- 2.21 Co-60 < 0.2 < 0.3 < 0.2 < 0.3 Cs-134 <0.3 < 0.2 < 0.2 < 0.2 Cs-137 <0.2 < 0.3 < 0.2 < 0.2 Th-228 < 0.4 < 0.4 < 0.4 < 0.4 STA-HIR Be-7 56.1 +/- 5.6 53.7 +/- 5.4 42.5 +/- 4.6 80.5 +/- 8.1 58.2 +/- 32.0 K-40 <5 <5 <6 <4 Co-60 < 0.3 <0.3 < 0.3 < 0.2
'1 Cs-134 < 0.2 < 0.2 < 0.2 < 0.2 N Cs-137 < 0.2 < 0.2 < 0.3 < 0.2 Th-228 < 0.4 < 0.3 <0.5 < 0.4.
STA-BC Be-7 46.7 +/- 4.7 63.6 +/- 6.4 48.1 +/- 4.8 90.4 +/- 9.0 62.2 +/- 40.6 K-40 <4 <5 <5 3.71 +/- 1.73 3.71 +/- 1.73 Co-60 <0.2 < 0.2 < 0.3 < 0.3 Cs-134 < 0.2 < 0.3 < 0.3 < 0.2 Cs-137 <0.2 < 0.2 < 0.3 < 0.2 Th-228 < 0.4 < 0.4 < 0.5 < 0.4 STA-ALL Be-7 40.7 +/- 4.1 67.0 +/- 6.7 54.5 +/- 5.4 98.0 +/- 9.8 65.1 +/- 48.9 K-40 3.32 +/- 1.78 <5 < 10 <4 3.32 +/- 1.78 Co-60 <0.2 < 0.3 < 0.4 < 0.2 Cs-134 < 0.2 < 0.2 < 0.3 < 0.2 Cs-137 <().2 < 0.2 < 0.3 < 0.2 Th-228 < 0.2 < 0.4 <0.5 < 0.3
- All other gamma emitters were < LLD.
e TABLE B-3 (Page2of2)
SURRY-1989 CONCENTRATIONS OF GAMMA EMIITERS* IN QUARTERLY AIR PARTICULATES 10-3 pCi/m3 +/- 2 Sigma FIRST QUARTER SECOND QUAR1ER THIRD QUAR1ER FOURTH QUARTER AVERAGE STATION NUCLIDE 01/03-04/04 04/04-06/28 06/28-10/03 10/03-01/02 +/- 2 s.d.
STA-CP Be-7 62.3 +/- 6.2 52.2 +/- 5.2 42.8 +/- 4.3 124 +/- 12 70.3 +/- 73.3 K-40 < 10 <5 < IO <6 Co-60 < 0.4 < 0.2 < 0.3 < 0.3 Cs-134 <0.4 < 0.3 < 0.3 < 0.3 Cs-137 < 0.4 < 0.2 < 0.3 < 0.3 Th-228 < 0.5 <0.4 < 0.4 < 0.4 STA-DOW Be-7 60.9 +/- 6.1 53.8 +/- 5.4 48.6 +/- 4.9 87.4 +/- 8.7 62.7 +/- 34.5 K-40 <5 < IO <5 4.53 +/- 1.71 4.53 +/- 1.71 Co-60 < 0.2 < 0.4 < 0.2 < 0.2
....... Cs-134 < 0.2 < 0.3 < 0.2 < 0.2
~
Cs-137 < 0.2 < 0.3 < 0.2 < 0.2 Th-228 < 0.5 < 0.4 < 0.4 < 0.4 STA-FE Be-7 52.1 +/- 5.2 65.7 +/- 6.6 54.1 +/- 5.4 84.2 +/- 8.4 64.0 +/- 29.5 K-40 <5 <5 <6 <4 Co-60 < 0.2 * < 0.2* < 0.3 < 0.3 Cs-134 < 0.2 < 0.3 < 0.3 < 0.2 Cs-137 < 0.2 <0.3 < 0.3 < 0.2 Th-228 < 0.4 <0.4 < 0.5 < 0.4 STA-NN Be-7 49.6 +/- 5.0 72.9 +/- 7.3 495 +/- 5.0 93.1 +/- 9.3 66.3 +/- 42.0 K-40 <4 5.96 +/- 2.65 < IO <3 5.96 +/- 2.65 Co-60 <2 < 0.3 < 0.3 < 0.3 Cs-134 < 0.2 < 0.2 < 0.3 < 0.2 Cs-137 <0.2 <0.3 < 0.3 < 0.2 Th-228 <0.3 < 0.4 < 0.4 < 0.3
- All other gamma emitters were< LLD.
T ABLE B-4 (Page 1 of 3)
SURRY-1989 CONCENTRATIONS OF GAMMA EMITIERS* AND TRITIUM IN RIVER WATER pCi/1 +/- 2 Sigma STATION DATE Be-7 K-40 1-131 Cs-137 Ba-140 La-140 Th-228 H-3 JANUARY CHIC 01/12/89 <40 <90 < 0.3 <5 <20 <7 < 10 HIP 01/11/89 <30 76.8 +/- 32.3 < 0.2 <3 < 10 <6 <6 NN 01/11/89 <30 97.7 +/- 32.2 < 0.2 <4 < 10 <4 <7 SD 01/12/89 <30 <70 < 0.2 <4 < 10 <6 <6 SI 01/11/89 <30 77.2 +/- 35.5 < 0.2 <3 <8 <3 <6 SW 01/12/89 <30 <70 < 0.3 <4 < 10 <5 <7
-...J FEBRUARY
"'" SD 01/21/89 <30 <70 < 0.2 <4 < 10 <5 <7 SW 01/21/89 <30 <70 < 0.2 <4 < 10 <6 <7 MARCH CHIC 03/16/89 <20 <50 <5 <3 < 10 <5 <5 < 110 HIP 03/16/89 <30 <50 <6 <3 < 10 <6 <6 < llO NN 03/15/89 <30 <80 <8 <4 < 10 <6 <6 < 110 SD 03/16/89 <30 <50 <6 <3 < 10 <5 <5 450+/- 90 SI 03/15/89 <30 44.6 +/- 25.7 <6 <3 < 10 <5 <5 < 170 SW 03/16/89 <40 <80 <9 <5 <20 <7 < 10 < 160 AtlUL SD 04/18/89 <40 <90 < 0.2 <4 <20 <7 <7 SW 04/18/89 <30 <50 < 0.2 <3 <10 <6 <6
- All other gwnma emiuers wen: <LLD .
e e e TABLE 8-4 (Page 2 of 3)
SURRY -1989 CONCENTRATIONS OF GAMMA EMITIERS* AND 1RITIUM IN RIVER WATER pCi/1 +/- 2 Sigma STATION DATE Be-7 K-40 1-131 Cs-137 Ba-140 La-140 Th-228 H-3 MAY cmc 05/10/89 <30 <60 < 0.2 <3 <9 <5 <6 290 +/- 80 HIP 05/0')/89 < 30 <70 < 0.3 <5 < 10 <7 < 10 240 +/- 80 NN 05/0')/89 < 30 <60 < 0.4 <4 < 10 <5 <7 350 +/-80 SD 05/0')/89 <30 <50 < 0.5 <3 <9 <5 <6 SI 05/0')/89 < 30 <50 < 0.2 <4 < 10 <5 <6 270 +/-80 SW 05/0')/89 <30 <60 < 0.2 <4 < 10 <5 <6
.Ill.NE
'-I U1 SD 06/20/89 <50 <90 < 0.2 <5 <20 <8 < 10 560+/- 150 SW 06/20/89 < 30 <60 < 0.2 <4 < 10 <7 <7 410+/- 80 J.l!LI CHIC 07/11/89 <40 <80 < 0.2 <4 <20 <1 <6 HIP 07/11/89 < 30 <50 < 0.2 <3 < 10 <1 <6 NN 07/11/89 <30 <60 < 0.3 <4 <20 <1 <6 SD 07/11/89 < 30 <60 < 0.2 <3 < 10 <1 <6 SI 07/11/89 <30 <70 < 0.3 <4 <20 <8 <1 SW 07/11/89 <30 <60 < 0.2 <3 <20 <6 <6 AlHHlSI SD 08/22/89 <30 <60 < 0.2 <3 < 10 <7 <6 SW 08/22/89 < 30 < 100 < 0.2 <4 <20 <1 <6
- All other gamma emitters were <LLD.
e e e TABLE B-4 (Page 3 of 3)
SURRY -1989 CONCENTRATIONS OF GAMMA EMITIERS* AND 1RITIUM IN RIVER WATER pCi/1 +/- 2 Sigma STATION DATE Be-7 K-40 1-131 Cs-137 Ba-140 La-140 Th-228 H-3 SEPTEMBER CHIC 09/08/89 <30 <50 < 0.3 <4 <20 <9 <6 < 100 HIP 09/07/89 <40 <70 < 0.4 <4 <20 < 10 <7 180+/- 90 NN 09/07/89 <40 < 100 < 0.4 <5 <30 < 10 <7 400+/-90 SD 09/07/89 <30 <50 < 0.4 <3 <20 <9 <6 230+/- 90 SI 09/07/89 <30 <60 < 0.5 <3 < 10 <9 <6 460+/- 90 SW 09/08/89 <30 <50 <0.3 <3 <20 <8 <6 420+/-90
'-I C]\
QS::IQDEB SD 10/17/89 <30 71.7 +/- 35.8 < 0.2 <3 <20 <8 <5 SW 10/17/89 <30 <50 <0.2 <3 <20 <7 <6 NOVEMBER CHIC 11/02/89 <30 <60 <0.3 <3 <20 <9 <6 230 +/- 90 HIP ll/02J89 <40 < 100 < 0.4 <4 <20 < 10 <7 380+/-90 NN 11/02/89 <30 140+/-32 < 0.4 <3 <20 <8 <5 210+/-90 SD 11/02J89 <30 <60 < 0.3 <3 <20 <7 <5 SI 11/02/89 <30 <50 < 0.3 <3 <20 < 10 <6 230+/-90 SW 11/02J89 <30 <50 < 0.2 <3 <20 <9 <6 DECEMBER SD 12/19/89 <30 <60 < 0.2 <4 < 10 <5 <6 2700+/- 100 SW 12/19/89 <30 <60 < 0.2 <4 < 10 <6 <7 290+/-90
- All other gamma emitters were <LLD.
e e e TABLE B-5 SURRY-1989 CONCENTRATIONS OF GAMMA EMITIERS* AND TRITIUM IN RIVER WATER pCi/1 +/- 2 Sigma STATE SPLIT MONTH COLL. DATES Be-7 K-40 1-131 Cs-137 Ba-140 La-140 Th-228 H-3 SCOTLAND WH, <SW}
JanWIJ)' 01/15/89 <50 < 100 <3 Femwy <4 <60 < 20 (a) <7 02/15/89 <50 <60 <2 <4 March <50 < 20 (a) <7 03/15/89 <70 <90 <2 <6 April <80 (a) <40 (a) < 10 340+/- 80 04/15/89 <40 <60 <2 <4 <50 May 05/15/89 < 20 (a) <7
<40 <60 <2 <4 <80 (a)
Jwie 06/15/89 <40 (a) <7
<40 <70 <5 <3 < 80 (a)
July 07/15/89 <40 (a) <7 200+/-90
<40 <50 <4 <3 <70 (a)
August 08/15/89 < 30 (a) <6
<60 <90 <2 <4 < 100 (a) < 50 (a)
September 09/15/89 <60 <90 <8
<2 <4 < 100 (a) <50 (a) <8 250+/- 90 October 10/15/89 <80 <200 <4 <6 November < 200 (a) < 70 (a) <9 11/15/89 <50 <70 <2 <4 (a)
December <90 < 50 (a) <8
--.I 12/15/89 <50 <60 <3 <4 <70 (a)
--.I < 30 (a) <7 500+/- 90 Average
+/- 2 s.d.
SllBBX l!IS, CSD}
- JanWIJ)' 01/15/89 <40 80.0 +/- 26.0 <3 Fcbruary(b) <3 <40 < 20 (a) <6 02/15/89 <50 <80 <2 <5 March <60 < 20 (a) <7 03/15/89 <50 <70 <2 <4 April <60 < 20 (a) <7 1200 +/- 100 04/15/89 <50 <90 <2 <6 < 60 May . 05/15/89 <50 < 20 (a) < 10
<60 <2 <4 <80 (a) < 30 (a)
Jwie 06/15/89 <50 <7
<60 <5 <4 <80 (a) <40 (a) <7 210+/- 100 July 07/15/89 <40 61.0 +/- 26.3 <5 August <3 <70 (a) < 30 (a) <5 08/15/89 <70 <90 <3 <6 < 100 (a)
Seprcmber 09/15/89 <50 < 60 (a) < 10
<70 <2 <4 < 100 (a) < 50 (a)
October 10/15/89 <60 55.5 +/- 29.2 <7 530+/- 90
<3 <4 < 100 (a) < 60 (a) <8 November 11/15/89 <50 <60 <2 <4 <90 (a) <40 (a) <7 Deccmbcr 12/15/89 <50 <60 <3 <4 <70 (a) < 30 (a) <6 1600+/- 100 Average 65.5 +/- 25.7
+/- 2 s.d.
(a)
All other gamma emitters were <LLD.
LLD not met because of late receipt of sample from the State of Virginia.
(b) Cobalt-60 gave positive result of 10.9 +/- 4.5 pCi/liter. This value was confirmed by reanalysis.
e e e TABLE 8-6 SURRY -1989 CONCENTRATIONS OF GAMMA EMITIERS* AND.1RITIUM IN WELL WATER pCi/1 +/- 2 Sigma DATE STATION Be-7 K-40 1-131 Cs-137 Ba-140 La-140 Th-228 H-3 FIRST QUARTER 03/21/89 BC <50 < 100 < 0.2 <6 03/22/89 HIR <20 <9 < 10 <200
< 30 <70 < 0.3 <4 < IO <6 03/}.2/89 JMTN <40 <7 <200
< 100 < 0.3 <5 <20 <6 <7 03/ll/89 ss <30 <60 < 0.2 <4 < IO <7 <6
<200 440+/- 120 SE!;;;Ql!lll QUARTER 06{}.0/89 BC <40 <80 < 0.2 <4
--.i <20 <9 < IO 230+/- 80 (X) 06/20/89 HIR <20 <50 < 0.2 <3 < 10 06/20/89 JMTN* <6 <5 <200
< 30 <80 < 0.2 <4 <20 <7 06/20/89 ss <40 <70 <6 300+/- 80
< 0.2 <4 <20 <9 <9 490+/- 80 THIRD QUARTER 09/19/89 BC <40 <80 < 0.2 <4 <20 09/19/89 HIR <30 <8 < 10 < 100
<50 < 0.2 <3 < IO <6 <5 09/19/89 JMTN <30 <80 < 100
<0.2 <4 <:20 <7 <6 09/19/89 ss <30 <50 < 0.2 <3 < IO <7 <5
< 100
< 100 FOURTH QUARTER 12/19/89 BC <50 <90 < 0.2 <5 12/19/89 <20 <8 < IO 180 +/- 80 HIR <30 <60 < 0.3 <4 < 10 12/19/89 JMTN <6 <7 < 100
<40 <90 < 0.2 <4 <20 <6 12/19/89 ss <30 <7 (a)
<60 < 0.2 <4 < 10 <7 <6 (a)
- All other ganuna emitters were <LLD.
(a) No result detenninable; sample was contaminated in the analytical laboratory.
TABLE B-7 (Page 1 of2)
SURRY-1989 CONCENTRATIONS OF GAMMA EMITIERS* IN SILT pCi/kg (dry)+/- 2 Sigma STATION CHIC HIP NN POS SD SI COLLECTION DATE 03/16/89 03/16/89 03/15/89 03/15/89 03/16/89 03/15/89 Be-7 <300 <200 <300 <300 <300 <300 K-40 14500 +/- 1500 7710+/- 770 13000+/- 1300 14600+/- 1500 12700+/- 1300 10600 +/- 1100 Mn-54 <30 <20 <30 < 30 <30 <30
"'-I Co-58 <30 <20 <30 < 30 83.4 +/- 29.5 < 30
\0 Co-60 281 +/- 31 166+/- 21 62.0 +/- 24.6 222+/- 28 1500+/- 150 326 +/- 33 Cs-134 <40 <20 <30 < 30 . 184 +/- 31 < 30 Cs-137 666+/- 67 318 +/- 32 240+/- 31 402+/- 40 1450+/- 150 546+/- 55 Ra-226 2440+/- 420 891 +/- 215 1290+/- 440 1890+/- 380 1330+/- 380 1910+/- 390 Th-228 1220+/- 120 615+/- 62 156+/- 76 979+/- 98 956+/- 96 1080+/- uo
- All olher garruna emitters were <LLD.
TABLE 8-7 (Page 2 of2)
SURRY-1989 CONCENTRATIONS OF GAMMA EMITIERS* IN SILT pCi/kg (dry)+/- 2 Sigma STATION CHIC HIP NN POS SD SI Average COLLECTION DATE 09/08/89 09/07/89 09/07/89 09/07/89 09/07/89 09/07/89 +/- 2 Sigma Be-7 <400 <500 <500 1190+/- 330 <400 < 300 1190+/- 330 K-40 12300+/- 1200 16100+/- 1600 13500+/- 1400 13800+/- 1400 9690+/- 970 10100 +/- 1000 12383 +/- 4841 Mn-54 <30 <40 <30 < 30 < 30 <20 Co-58 <40 <50 <40 <40 <40 <20 83.4 +/- 29.5 00 0
Co-60 218 +/- 33 573+/- 57 102+/- 29 364 +/- 36 394+/- 42 197+/- 20 367+/- 766 Cs-134 <40 <50 <40 <40 <40 <20 184+/- 31 Cs-137 556+/- 56 692+/- 69 308+/- 36 599+/- 60 630+/- 63 301 +/- 30 559+/- 645 Ra-226 2110+/- 490 1730+/- 490 1340+/- 430 1870+/- 460 1340+/- 400 1200+/- 300 1612+/- 895 Th-228 999+/- 100 1330+/- 130 902+/- 90 866+/- 87 804+/- 80 667+/- 67 931 +/- 424
- All other gamma emillers were <LLD.
e TABLE B-8 SURRY-1989 CONCENTRATIONS OF GAMMA EMITIERS* IN SHORELINE SEDIMENT pCi/kg (dry)+/- 2 Sigma STATION HIR BURWELL'S HIR BURWELL'S AVERAGE COLLECTION DATE 03/01/89 03/01/89 08/29/89 08/29/89 +/- 2 s.d.
Be-7 < 100 < 100 <200 <300 K-40 3630+/- 360 1530+/- 170 6580+/- 660 2850+/- 420 3648 +/- 4277 Co-60 < 10 < IO <20 <20 Cs-134 < 10 < IO <20 <200
- Cs-137 < 10 <20 <20 <30 00 Ra-226 330+/- 172 435+/- 242 <300 <500 383 +/- 148 Th-228 94.9 +/- 19.9 161 +/- 16 <30 <60 128 +/- 93
- All other gamma emitters were <LLD.
TABLE 8-9 (Page 1 of 3)
SURRY-1989 CONCEN1RATIONS OF STRONTIUM-89 AND-90* AND GAMMA EMITfERS** IN MILK pCi/liter +/- 2 Sigma MONTH NUCLIDE LEE HALL EPPS CP WMS JDKS JANUARY Sr-89 Sr-90 K-40 1400+/- 140 1400+/- 140 1530+/- 150 1380 +/- 140 1460 +/- 150 Cs-137 <4 <4 <5 <4 <5 1-131 < 0.2 < 0.3 < 0.2 < 0.4 < 0.2 00 N
FEBRUARY Sr-89 Sr-90 K-40 1480 +/- 150 1340+/- 130 1300+/- 130 1390 +/- 140 1290+/- 130 Cs-137 <4 <4 <4 <4 <4 1-131 < 0.4 < 0.3 < 0.1 < 0.2 < 0.2 MARCH Sr-89 <3 <3 <4 Sr-90 1.4 +/- 0.8 1.9 +/- 0.8 3.7 +/- 1.1 K-40 1170+/- 120 1330+/- 130 1070+/- 110 1150 +/- 120 1380+/- 140 Cs-137 <6 <4 <6 <4 <5 1-131 <0.2 <0.2 < 0.2 < 0.2 < 0.3 APRIL Sr-89 Sr-90 K-40
- 1280 +/- 130 1360 +/- 140 1350+/- 140 1420 +/- 140 1350+/- 130 Cs-137 <4 <4 <4 <4 <4 1-131 <0.2 <0.2 < 0.2 < 0.4 < 0.3
(*) Strontium-89 and 90 sample analysis done on a quarterly composite of slate splil samples (Epps, Lee Hall) and Colonial Parkway(CP) sample al !he request of !he State of Virginia.
(**) All o!her gamma emitters were <LLD.
e TABLE B-9 (Page 2of3)
SURRY -1989 CONCENTRATIONS OF STRONTIUM-89 AND-90* AND GAMMA EMITI'ERS** IN MILK pCi/liter +/- 2 Sigma MONTH NUCLIDE LEE HALL EPPS CP WMS JDKS MAY Sr-89 Sr-90 K-40 1410+/- 140 1420+/- 140 1450+/- 150 1540 +/- 150 1350+/- 140 Cs-137 <4 <4 <4 <4 <5 1-131 < 0.3 <0.2 < 0.3 < 0.3 < 0.3 JUNE Sr-89 <4 <2 <4 00 Sr-90 2.3 +/- 0.7 1.9 +/- 0.4 3.8 +/- 0.9
<,I K-40 1560 +/- 160 1370 +/- 140 1490+/- 150 1260 +/- 130 1270+/- 130 Cs-137 <4 <4 <4 <4 <4 1-131 < 0.2 < 0.3 < 0.2 < 0.3 < 0.2 JULY Sr-89 Sr-90 K-40 1410+/- 140 1390 +/- 140 1470+/- 150 1390 +/- 140 1500 +/- 150 Cs-137 <4 <4 <4 <4 <4 1-131 < 0.2 < 0.2 < 0.3 < 0.2 < 0.2 AUGUST Sr-89 Sr-90 K-40 1560+/- 160 1490 +/- 150 1440+/- 140 1280+/- 130 1420 +/- 140 (a)
Cs-137 <5 <4 <4 <6 8.25 +/- 3.75 1-131 <0.2 < 0.2 < 0.2 < 0.2 < 0.2
(*) Strontium-89 and 90 sample analysis done on a quarterly composite of state split samples (Epps, Lee Hall) and Colonial Parkway(CP) sample at the request of the State of Virginia.
- All other gamma emitters were <LLD.
(a) Confirmed by reanalysis.
TABLE B-9 (Page 3 of 3)
SURRY- 1989 CONCEN1RATIONS OF STRONTIUM-89 AND-90* AND GAMMA EMITI'ERS** IN MILK pCi/liter +/- 2 Sigma MONTH NUCLIDE LEE HALL EPPS CP WMS JDKS SEPTEMBER Sr-89 <5 <4 <5 Sr-90 1.6 +/- 1.0 l.l +/- 0.5 1.8 +/- 0.8 K-40 1470 +/- 150 1370 +/- 140 1140+/- 110 1340 +/- 130 1220 +/- 120 Cs-137 <6 <4 <6 <4 <5 1-131 < 0.3 <0.2 < 0.3 < 0.3 < 0.2 00 OCTOBER Sr-89
.i,:.. Sr-90 K-40 1330+/- 130 1470 +/- 150 1420+/- 140 1390+/- 140 1260+/- 130 Cs-137 <6 <6 <4 <6 <5 1-131 < 0.3 < 0.3 < 0.2 < 0.2 < 0.3 NOVEMBER Sr-89 Sr-90 K-40 1340+/- 130 1370 +/- 140 1260+/- 130 1920 +/- 190 1350 +/- 130 Cs-137 <4 <6 <4 <5 <7 1-131 <0.3 < 0.3 < 0.3 < 0.2 < 0.2 DECEMBER Sr-89 <4 <5 <5 Sr-90 2.4 +/- 1.6 1.2 +/- 0.5 6.2 +/- 2.0 K-40 1250+/- 120 1340 +/- 130 1530+/- 150 1430 +/- 140 1230 +/- 120 Cs-137 <5 <6 <4 <4 <5 1-131 < 0.2 < 0.2 < 0.3 < 0.2 < 0.2
(*) Strontium-89 and 90 sample analysis done on a quarterly composite of state split samples (Epps, Lee Hall) and Colonial Parkway(CP) sample at the request of the State of Virginia.
- All other ganuna emitters were <LLD .
e e e TABLE B-10 SURRY-1989 CONCENTRATIONS OF GAMMA EMITIERS* IN CLAMS pCi/kg (wet) +/- 2 Sigma STATION DATE TYPE Be-7 K-40 Co-58 Co-60 Cs-137 Ra-226 Th-228 gfK 01/12/89 Clams < 100 495 +/- 140 < 10 < 10 <20 <300 < 30 03/16/89 Clams < 100 330 +/- 119 < 10 < 10 < 10 <300 <30 05/10/89 Clams <200 520+/- 199 <20 <20 <20 <400 <40 07/11/89 Clams < 100 550 +/- 107 < 10 < 10 < 10 <200 <20 09/08/89 Clams <300 <800 <30 <20 <20 <400 <40 11/02/89 Clams <300 <400 <30 <20 < 30 <400 <40
.IM.IN 01/11/89 Clams < 100 694+/- 126 < 10 <20 <20 < 300 <20 03/16/89 Clams < 100 242+/- 112 < 10 < 10 < 10 <200 <20 05/09/89 Clams <200 <600 <20 <20 <20 <400 < 30 07/11/89 Clams < 100 442+/- 110 < 10 < 10 < 10 <200 <20 09/08/89 Clams < 100 637 +/- 139 < 10 < 10 < 10 <300 <20 11/02/89 Clams <300 <700 <30 <20 <30 <400 <40 00 tn
£ll 01/12/89** Clams < 100 541 +/- 136 <20 47.4 +/- 16.4 <20 < 300 <30 03/01/89** Clams < 100 509+/- 130 < 10 < 10 < 10 <300 < 30 05/02./89** Clams <200 528 +/- 115 <20 < IO < 10 <300 <30 07/10/89** Clams <200 <500 <20 <20 <20 <300 <30 09/12/90** Clams < 100 416+/- 130 < 10 < 10 < 10 <300 <20 10/30/89** Clams <300 872+/- 196 <30 <20 <20 <400 <40 lll.f 01/11/89 Clams <200 418 +/- 127 <20 <20 <20 <400 <40 03/16/89 Clams < 100 325 +/- 113 < 10 28.7 +/- 14.4 < 10 <300 <30 05/09/89 Clams <200 <500 <20 <20 <20 <400 <40 07/11/89 Clams <300 119 +/- 12 <30 <20 <20 <300 <30 09/07/89 Clams <200 538 +/- 123 <20 <20 < 10 < 300 <30 11/02/89 Clams <200 499+/- 136 < 10 <20 < 10 <300 < 30
~ 01/11/89 Clams < 100 736 +/- 152 < 10 < 10 < 10 < 300 <20 03/15/89 Clams < 100 441 +/- 127 < 10 < 10 < 10 <300 <30 05/09/89 Clams <200 555 +/- 121 < 10 < 10 <20 < 300 <40 07/11/89 Clams <200 589+/- 119 < 10 < 10 < 10 < 300 <30 09/07/89 Clams <200 649+/- 130 < 10 < 10 < 10 <300 <30 11/02/89 Clams <200 237 +/- 136 <20 <20 < 10 <400 <30 Average 495 +/- 336 38.1 +/- 26.4
+/- 2 s.d *
- All other gamma emitters were <LLD .
- State Split
TABLE B-11 SURRY - 1989 CONCENTRATIONS OF GAMMA EMITI1;RS* IN OYSIBRS pCi/kg (wet)+/- 2 Sigma STATION DATE TYPE Be-7 K-40 Co-58 Co-60 Cs-137 Ra-226 Th-228 B.LS 01/11/89 Oysters < 100 644+/- 124 < IO < IO < IO <200 <20 03/15/89 Oysters < 100 513 +/- 138 < IO < IO < IO <300 < 30 05/09/89 Oysters <200 <400 < 30 <20 < 30 <400 <40 07/11/89 Oysters <200 511 +/- 133 <20 < IO < IO < 300 < 30 Cli/01/89 Oysters < 100 488 +/- lCli < IO < IO < IO <200 <20 11/02/89 Oysters <300 <400 < 20 <20 <20 <300 < 30 01/11/89 Oysters < 100 598 +/- 124 < IO < IO < IO <200 <20 03/15/89 Oysters < 100 415 +/- 159 < IO < IO < IO <300 <20 00 05/09/89 Oysters <200 <600 <20 <20 <20 <400 <40 07/11/89 Oysters < 100 578 +/- 106 < IO < 10 < IO <300 < 30
°' Cli/01/89 Oysters < 200 447 +/- 158 <20 <20 < 10 < 300 <30 11/02/89 Oysters <200 326+/- 117 <20 < IO <20 < 300 < 30 01/11/89 Oysters < 100 <500 < 20 < 20 <20 < 300 < 30 03/15/89 Oysters < 100 502 +/- 176 < IO < IO <20 <300 < 30 05/fl)/89 Oysters <200 <700 < 30 < 30 < 30 <400 <40 07/11/89 Oysters < 100 851 +/- 129 < IO < 10 < 10 <300 <20 Cli/01/89 Oysters <200 < 300 <20 <20 <20 < 300 <40 11/02/89 Oysters <200 505 +/- 138 < 10 < 10 < IO < 300 <30 0'2/27/89** Oysters < 100 650+/- 123 < 10 < 10 < 10 <200 <20 05/02/89** Oysters <200 442+/- 138 <20 <20 <20 < 300 <30 07/06/89** Oysters <200 348 +/- 141 <20 < 10 <20 < 300 <40 Cli/11/89** Oysters < 100 447 +/- 130 <20 < 10 <20 < 300 <30 10/31/89** Oysters <200 390+/- 188 <20 <20 <20 < 300 <30 Average 517 +/- 254
+/- 2 s.d.
All other garruna emitters were <LLD .
State Split
TABLE 8-12 SURRY -1989 CONCENTRATIONS OF GAMMA EMIITERS* IN CRABS pCi/k:g (wet)+/- 2 Sigma STATION DATE TYPE Be-7 K-40 Co-58 Co-60 Cs-137 Ra-226 Th-228 06/0.6/89 Crabs < 100 2540+/- 250 < 10 < 10 < 10 <200 <20
- All other gamma emiUers were <LLD.
e TABLE B-13 SURRY -1989 CONCENTRATIONS OF GAMMA EMITTERS* IN FISH pCiJkg (wet) +/- 2 Sigma COLL.DATE STATION SAMPLE TYPE K-40 Co-58 Cs-134 Cs-137 04/04/89 SD CATFISH 1470+/- 150 <6 <6 <6 04/04/89 SD WHITE PERCH 1420+/- 140 <8 <9 17.5 +/- 7.7 10{}.6/89 SD WHITE PERCH 986+/- 102 <7 <6 <9 00 10{}.6/89 SD CATFISH 1450+/- 150 < 10 <9 <9 00
- All other gamma emitters were below <LLD.
TABLE B-14 SURRY -1989 CONCENTRATIONS OF GAMMA EMfITERS* IN VEGEfATION pCi/kg (wet)+/- 2 Sigma SAMPLE COLLECTION STATION TYPE DATE Be-7 K-40 1-131 Cs-134 Cs-137 Poole's Garden** Kale 06/13/89 <80 5820+/- 580 <20 <8 <9 Ryan's Garden** Kale 06/13/89 <200 5570+/- 560 <40 <20 <20 Carter's Garden** Cabbage 07/03/89 72.7 +/- 37.4 2180+/- 220 < 30 <8 <9 Turner's Garden** Cabbage 08/20/89 (a) 00 Chersterfield's Garden** Brocolli 08/27/89 281 +/- 66 6060+/- 6160 <40 <8 <7
'° Average +/- 2 s.d. 177 +/- 29S 4908 +/- 36S9
- All other gamma emitters were below <LLD
- State Split (a) Sample lost in transit.
e TABLE B-15 (Page 1 of2)
SURRY - 1989 DIRECT RADIATION MEASUREMENTS - QUARTERLY 1LD RESULTS mR/month +/- 2 Sigma - Set 1 - 098 STATION AVERAGE NUMBER FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER +/- 2 s.d.
02 1.5 +/- 0.8 7.4 +/- 0.6 6.8 +/- 1.6 8.7 +/- 0.2 7.6 +/- 1.6 03 8.0 +/- 0.7 1.5 +/- 0.9 7.0 +/- 0.9 8.4 +/- 0.4 7.7 +/- 1.2 04 6.9 +/- 1.0 6.9 +/- 1.1 5.8 +/- 0.3 7.0 +/- 1.1 6.7 +/- 1.1 05 6.2 +/- 0.4 5.9 +/- 0.4 5.5 +/- 0.6 7.0 +/- 0.8 6.2 +/- 1.3 06 6.8 +/- 0.6 6.4 +/- 0.6 6.5 +/- 0.4 6.8 +/- 0.9 6.6 +/- 0.4 07 6.9 +/- 1.2 6.1 +/- 0.8 5.1 +/- 0.8 (b) 6.2 +/- 1.2 08 6.3 +/- 1.1 6.0 +/- 0.7 5.8 +/- 0.2 7.4 +/- 0.7 6.4 +/- 1.4
\0 0
()I) 6.4 +/- 0.4 5.2 +/- 1.0 6.3 +/- 0.9 7.6 +/- 0.6 6.4 +/- 2.0 10 6.3 +/- 0.9 5.9 +/- 0.5 5.5 +/- 0.2 6.6 +/- 0.4 6.1 +/- 1.0 11 6.5 +/- 0.4 . 5.9 +/- 0.3 5.7 +/- 0.7 7.0 +/- 0.4 6.3 +/- 1.2 12 6.0 +/- 0.5 6.9 +/- 1.7 5.9 +/- 1.0 6.8 +/- 0.1 6.4 +/- 1.0 13 6.6 +/- 0.5 6.9 +/- 0.3 6.2 +/- 0.4 7.2 +/- 0.7 6.7 +/- 0.9 14 (a) 7.6 +/- 0.6 6.6 +/- 1.0 7.7 +/- 0.5 7.3 +/- 1.2 15 6.5 +/- 1.0 6.2 +/- 0.8 5.5 +/- 0.3 6.6 +/- 0.4 6.2 +/- 1.0 16 5.1 +/- 1.7 5.2 +/- 1.6 5.1 +/- 0.6 6.9 +/- 1.0 5.9 +/- 1.4 17 5.8 +/- 0.2 4.0 +/- 0.9 5.4 +/- 0.3 6.3 +/- 0.4 5.4 +/- 2.0 18 5.2 +/- 0.5 5.1 +/- 0.8 4.5 +/- 0.2 5.1 +/- 0.2 5.1 +/- 1.0 19 4.9 +/- 0.2 5.5 +/- 0.6 5.3 +/- 0.4 6.9 +/- 0.2 5.1 +/- 1.1 20 6.6 +/- 0.9 5.4 +/- 0.1 4.8 +/- 0.5 6.6 +/- 0.6 5.9 +/- 1.8 21 5.7 +/- 0.5 5.5 +/- 0.9 5.6 +/- 1.1 6.6 +/- 0.4 5.9 +/- 1.0 22 5.8 +/- 0.3 5.5 +/- 0.2 5.5 +/- 0.3 6.2 +/- 0.3 5.8 +/- 0.7 (a) 1LD lost during construction of combustion turbines.
(b) Till lost after collection and before receipt at TI.
e TABLE B-15 (Page 2 of2)
SURRY-1989 DIRF.CT RADIATION MEASUREMENTS - QUARTERLY TLD RES ULTS mR/month +/- 2 Sigma - Set 1 - 098 STATION AVERAGE NUMBER FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER +/- 2 s.d.
23 6.5 +/- 0.7 6.3 +/- 0.8 6.5 +/- 0.4 7.4 +/- 0.0 6.7 +/- 1.0 24 5.9+/- 0.3 5.8 +/- 0.3 5.4 +/- 0.8 6.9 +/- 0.2 6.0 +/- 1.3 25 6.6+/- 0.6 5.9 +/- 0.3 6.1 +/- 0.5 6.9 +/- 1.1 6.4 +/- 0.8 26 4.9+/- 0.7 5.9 +/- 0.8 5.1 +/- 0.4 5.9 +/- 0.7 5.5 +/- 1.1 27 5.6 +/- 0.2 4.9 +/- 0.8 4.4 +/- 0.3 6.0 +/- 1.1 5.2 +/- 1.4 28 6.0+/- 0.3 5.5 +/- 1.1 5.8 +/- 0.6 6.7 +/- 0.5 6.0 +/- 1.0
'° I-' 29 5.3 +/- 0.7 5.4 +/- 0.7 4.6 +/- 0.8 6.1 +/- 0.8 5.4 +/- 1.2 30 6.0 +/- 0.6 5.5 +/- 0.4 5.1 +/- 0.5 6.5 +/- 0.6 5.8 +/- 1.2 31 5.1 +/- 0.3 5.3 +/- 0.3 4.7 +/- 0.3 6.2 +/- 0.6 5.3 +/- 1.3 32 6.0+/- 0.8 5.5 +/- 0.2 4.5 +/- 0.5 6.6 +/- 0.6 5.7 +/- 1.8 33 6.2 +/- 0.5 6.6 +/- 0.4 5.1 +/- 0.6 7.1 +/- 1.0 6.3 +/- 1.7 34 6.9+/- 0.9 6.1 +/- 0.7 6.2 +/- 1.3 7.9 +/- 1.4 6.8 +/- 1.7 35 6.7 +/- 0.4 6.5 +/- 0.6 5.8 +/- 0.4 7.3 +/- 0.7 6.6 +/- 1.2 36 7.2+/- 0.5 7.1 +/- 0.9 6.0 +/- 1.0 8.0 +/- 0.9 7.1 +/- 1.6 37 6.8 +/- 1.2 6.6 +/- 0.3 5.5 +/- 0.7 6.9 +/- 0.7 6.5 +/- 1.3 38 8.3 +/- 1.1 7.8 +/- 0.8 6.9 +/- 0.4 8.7 +/- 0.6 7.9 +/- 1.6 39 6.2+/- 0.4 6.0 +/- 0.5 5.3 +/- 0.5 7.0 +/- 0.4 6.1 +/- 1.4 40 4.9+/- 0.3 5.2 +/- 0.2 4.0 +/- 0.5 5.7 +/- 0.4 5.0 +/- 1.4 41 6.8 +/- 0.5 6.1 +/- 0.4 4.9 +/- 0.8 6.7 +/- 1.5 6.1 +/- 1.7 42 6.3 +/- 0.4 6.1 +/- 0.4 6.0+/- 0.9 6.8 +/- 0.6 6.3 +/- 0.7 43 5.8 +/- 0.4 5.8 +/- 0.2 5.0 +/- 0.9 6.8 +/- 1.3 5.9 +/- 1.5 Average 6.3 +/- 1.5 6.0 +/- 1.6
- 5.6 +/- 1.4 6.9 +/- 1.4 6.2 +/- 1.1
+/- 2 s.d.
-~--___J
TABLE B-16 (Page 1 of2)
SURRY -1989 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.
02 7.3 +/- 0.7 8.0 +/- 0.6 6.8 +/- 1.0 8.1 +/- 0.1 7.6 +/- 1.2 03 7.3 +/- 0.9 7.5 +/- 0.8 6.7 +/- 1.2 8.3 +/- 0.7 7.5 +/- 1.3 04 6.4 +/- 0.4 6.5 +/- 0.7 5.9 +/- 1.0 7.6 +/- 0.5 6.6 +/- 1.4 05 6.3 +/- 0.3 6.2 +/- 0.8 6.1 +/- 0.4 7.3 +/- 0.6 6.5 +/- 1.1 06 6.4 +/- 0.3 6.4 +/-0.6 6.3 +/- 0.7 1.7 +/- 0.5 6.7 +/- 1.3 07 5.1 +/- 0.8 6.2 +/- 0.4 6.4 +/- 0.5 7.3 +/- 0.4 6.4 +/- 1.3 I.O 08 6.0+/- 0.5 7.3 +/- 1.3 5.8 +/- 1.3 6.9 +/- 0.6 6.5 +/- 1.4 N
09 6.5 +/- 0.9 7.2 +/- 0.8 5.1 +/- 1.0 7.1 +/- 0.7 6.6 +/- 1.4 10 5.8 +/- 0.2 5.3 +/- 1.4 5.1 +/- 0.8 6.9 +/- 0.5 5.9 +/- 1.4 11 6.7 +/- 0.9 4.2 +/- 0.8 6.4 +/- 0.7 7.1 +/- 0.8 6.1 +/- 2.6 12 6.3 +/- 0.3 6.3 +/- 0.5 5.8 +/- 0.5 7.3 +/- 0.7 6.4 +/- 1.3 13 6.6+/- 0.4 6.4 +/- 0.7 6.1 +/- 0.7 1.5 +/- 0.3 6.7 +/- 1.2 14 (a) 7.9 +/- 0.6 7.2 +/- 0.5 7.9 +/- 0.3 7.7 +/- 0.8 15 6.1 +/- 0.5 6.0 +/- 0.7 5.2 +/- 0.7 7.4 +/- 0.2 6.2 +/- 1.2 16 6.1 +/- 0.4 6.6 +/- 0.3 5.9 +/- 0.3 7.2 +/- 0.4 6.5 +/- 1.2 17 5.6 +/- 0.6 5.7 +/- 0.7 5.6 +/- 0.5 6.8 +/- 0.3 5.9 +/- 1.2 18 5.5 +/- 0.4 5.6 +/- 0.8 4.7 +/- 0.3 6.3 +/- 0.6 5.5 +/- 1.3 19 5.7 +/- 0.3 5.2 +/- 2.2 4.9 +/- 0.8 6.5 +/- 0.7 5.6 +/- 1.4 20 5.3 +/- 0.4 6.3 +/- 0.7 4.9 +/- 0.3 6.2 +/- 0.2 5.7 +/- 1.4 21 5.8 +/- 1.1 6.0 +/- 1.0 5.3 +/- 0.9 7.1 +/- 0.5 6.1 +/- 1.5 22 5.3 +/- 0.8 5.7 +/- 0.4 5.3 +/- 0.3 6.3 +/- 0.7 5.7 +/- 0.9 (a) TLD lost during construction of combustion turbines.
~~I
e e TABLE B-16 (Page 2 of2)
SURRY-1989 DIRECT RADIATION MEASUREMENTS - QUARTERLY 1LD RESULTS mR/month +/- 2 Sigma - Set 2 - 099 STATION AVERAGE NUMBER FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER +/- 2 s.d.
23 6.3 +/- 0.8 6.6 +/- 0.8 6.2 +/- 0.5 7.1+/-0.7 6.6 +/- 0.8 24 5.5 +/- 0.4 5.5 +/- 0.8 5.4 +/- 0.2 6.6 +/- 0.7 5.8 +/- 1.1 25 5.6+/- 0.6 5.9 +/- 0.6 5.7 +/- 0.3 6.9 +/- 0.5 6.0 +/- 1.2 26 5.6+/- 0.3 6.4 +/- 1.0 5.4 +/- 0.4 5.8 +/- 0.7 5.8 +/- 0.9 27 5.1 +/- 0.5 3.9 +/- 1.4 5.2 +/- 0.6 5.8 +/- 1.0 5.0 +/- 1.6 28 5.4 +/- 0.4 4.9 +/- 1.4 5.5 +/- 0.3 6.5 +/- 0.8 5.6 +/- 1.3 29 5.2 +/- 0.3 5.6 +/- 0.5 4.6 +/- 1.0 5.5 +/- 0.5 5.2 +/- 0.9 ID 30 6.0 +/- 0.4 5.3 +/- 0.3 5.4 +/- 0.6 6.2 +/- 1.0 5.7 +/- 0.9
!.N 31 5.4 +/- 0.2 5.9 +/- 0.4 4.9 +/- 0.2 5.8 +/- 0.3 5.5 +/- 0.9 32 6.0 +/- 1.3 6.2 +/- 0.3 5.8 +/- 0.4 6.0 +/- 0.7 6.0 +/- 0.3 33 6.3 +/- 0.5 6.2 +/- 0.4 6.1 +/- 0.6 6.5 +/- 0.5 6.3 +/- 0.3 34 6.1 +/- 0.4 6.0 +/- 0.4 5.7 +/- 0.6 6.6 +/- 0.8 6.1 +/- 0.7 35 6.9+/- 0.6 6.6 +/- 0.6 6.3 +/- 0.6 6.9 +/- 1.3 6.7 +/- 0.6 36 7.1 +/- 0.9 7.0 +/- 0.6 6.9 +/- 0.9 7.4 +/- 1.0 7.1 +/- 0.4 37 6.2 +/- 0.8 6.4 +/- 0.3 5.8 +/- 0.5 6.7 +/- 0.8 6.3 +/- 0.8 38 7.8 +/- 0.5 7.9 +/- 1.8 7.8 +/- 0.9 8.1 +/- 0.5 7.9 +/- 0.3 39 6.4 +/- 0.8 5.6 +/- 1.3 5.5 +/- 0.6 6.4 +/- 0.4 6.0 +/- 1.0 40 5.2 +/- 0.7 5.2 +/- 0.3 4.5 +/- 0.5 5.6 +/- 0.1 5.1 +/- 0.9 41 6.6 +/- 0.7 5.8 +/- 1.1 5.9 +/- 1.2 6.8 +/- 0.5 6.3 +/- 1.0 42 6.0 +/- 0.5 5.9 +/- 0.7 5.6 +/- 1.5 6.3 +/- 0.5 6.0 +/- 0.6 43 5.5 +/- 0.9 5.4 +/- 1.2 5.6 +/- 0.4 6.2 +/- 0.4 5.7 +/- 0.7 Average 6.1 +/- 1.3 6.1 +/- 1.8 5.8 +/- 1.4 6.8 +/- 7.4 6.2 +/- 1.4
+/- 2 s.d.
APPENDIX C LAND USE CENSUS
- 1989 94
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 ga~eous 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 1989 Land Use Census, no change to the Monitoring Program nor calcul:,itional model is required.
95
CENSUS FOR SURRY POWER STATION - 1989 NEAREST NEAREST NEAREST NEARSET SECTOR RESIDENT GARDEN cow GOAT A-(N) 4.72@357° * *
- B-(NNE) 1.90@34° 1.90@34° *
- C-(NE)
- 4.91 @56° *
- 0-(ENE) 4.73@63° 4.91 @56° *
- E-(E)
F-(ESE)
- G-(SE)
H-(SSE) 4.75@152°
- e J-(S) 1.82@182° 2.01 @182° *
- K-(SSW) 1.87@193° 4.84@201 ° 1.87@193°
- L-(SW) 2.28@222° 3.65@224° *
- M-(WSW) 2.82@243° 3.43@258° *
- N-(W) 3.15@261° 4.33@262° *
- P-(WNW) 4.79@282° * *
- Q-(NW) * * *
- R-(NNW) 3.73@339° 4.89@340° 3.65@337° *
- None 96
LAND USE CENSUS SURRY POWER STATION e
I
(
~-~* .. ... r t
1989 LAND USE CENSUS LOCATION MAP 1 = NEAREST RESIDENT 2 = NEAREST GARDEN 3 = NEAREST COW 4 = NEAREST GOAT
(
i 97 l
APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES 98
ANALYTICAL PROCEDURES SYNOPSIS Appendix Dis a synopsis of the analytical procedures performed on samples collected for the Surry Power Station's Radiological Environmental Monitoring Program. All analyses have been mutually agreed upon by VEPCO and Teledyne Isotopes and include those recommended by the USNRC Branch Technical Position, Rev. 1, November 1979.
ANALYSIS TITLE PAGE 1
Gross Beta Analysis of Samples .......................... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 100 Precipitation .......................................................................................... 100 Airborne Particulates ........................................................................................ 102
_Analysis of Samples for Tritium ........................................................................... 103 Water ................................................................................................. 103 Analysis of Samples for Strontium-89 and -90 .......................................................... 104 Total Water .......................................................................................... 104 Milk .................................................................................................. 104 Soil and Sediment .................................................................................. I 04 Organic Solids ...................................................................................... 105 Air Particulates ...................................................................................... 105 Analysis of Samples for Iodine-131 ...................................................................... 108 Milk or Water ....................................................................................... 108 Gamma Spectrometry of Samples ......................................................................... 109 Milk and Water ...................................................... : .............................. 109 Dried Solids other than Soils and Sediment ..................................................... 109 Fish .................................................................................................. 109 Soils and Sediments ................................................................................ 109 Charcoal Cartridges (Air Iodine) ................................................................. 109 Airborne Particulates ............................................................................... 110 e Environmental Dosimetry .................................................................................. 111 99
DETERMINATION OF GROSS BETA ACTIVITY IN WATER SAMPLES
1.0 INTRODUCTION
The procedures described in.this section are used to measure the overall radioactivity of water samples without identifying the radioactive species present. No chemical separation techniques are involved.
One liter of the sample is evaporated on a hot plate. A smaller volume may be used if the sample has a significant salt content as measured by a conductivity meter. If requested by the customer, the sample is filtered through No. 54 filter paper before evaporation, removing particles greater than 30 microns in size.
After evaporating to a small volume in a beaker, the sample is rinsed into a 2-inch diameter stainless steel planchet which is stamped with a concentric ring pattern to distribute residue evenly. Final evaporation to dryness talces place under heat lamps.
Residue mass is determined by weighing the planchet before and after mounting the sample. The planchet is counted for beta activity on an automatic proportional counter.
Results are calculated using empirical self-absorption curves which allow for the change in effective counting efficiency caused by the residue mass.
100
2.0 DETECTION CAPABILITY Detection capability depends upon the sample volume actually represented on the planchet, the background and the efficiency of the counting instrument, and upon self-absorption of beta particles by the mounted sample. Because the radioactive species are not identified, no decay corrections are made and the reported activity refers to the counting time.
The minimum detectable level (MDL) for water samples is nominally 1.6 picocuries per liter for gross beta at the 4.66 sigma level (1.0 pCi/1 at the 2.83 sigma level), assuming that 1 k
liter of sample is used and that gram of sample residue is mounted on the planchet. These figures are based upon a counting time of 50 minutes and upon representative values of counting efficiency and background of 0.2 and 1.2 cpm, respectively.
The MDL becomes significantly lower as the mount weight decreases because of reduced self-absorption. At a zero mount weight, the 4.66 sigma MDL for gross beta is 0.9 picocuries per liter. These values reflect a beta counting efficiency of 0.38.
101
GROSS BETA ANALYSIS OF SAMPLES e Air Particulates 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. An unused air particulate filter, supplied by LILCO, is counted as the blank.
Calculations of the results, the two sigma error and the lower limit of detection (LLD):
RESULT (pCiJm3) = ((S/f) - (B/t))/(2.22 VE)
TWO SIGMA ERROR (pCi/m3) = 2((S!f2) + (B/t2))ll2/(2.22 VE)
LLD (pCiJm3) = 4.66 (B lfl.)/(2.22 V E t) where:
s = Gross counts of sample including blank B = Counts of blank E = Counting efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted V = Sample aliquot siz.e (cubic meters) 102
ANALYSIS OF SAMPLES FOR TRITIUM One of two methods is used. Each has the same measurement sensitivity. One method of tritium analysis is to count 8 ml of sample by liquid scintillation for 1000 minutes.
- The other method is to convert approximately 2 ml of water to hydrogen by passing the water, heated to its vapor state, over a granular z~c 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 detection (LLD) in pCi/1:
RESULT = 3.234 TN VN(CG - B)/(CN Vs) 1WO SIGMA ERROR = 2((CG + B)L\t)l/23.234 TN VN/((CN Vs) (CG-B))
UD = 4.66 (3.234)TN VN(Ca)l/2/(L\t CN Vs) where: TN = tritium units of the standard 3.234 = conversion factor changing tritium units to pCi/1 VN = volume of the standard used to calibrate the efficiency of the detector in psia Vs = volume of the sample loaded into the detector in psia CN = the cpm activity of the standard of volume VN CG = the gross activity in cpm of the sample of volume Vs and the detector volume B = the background of the detector in cpm L\t = counting time for the sample 103
ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 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 minimum of 5 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, 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.
Stable strontium carrier is added to 1 liter of sample and the sample is first evaporated, then ashed in a*muffle furnace. The ash is dissolved and strontium is precipitated as phosphate, then is dissolved and 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 a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 is determined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting.
Soil and Sediment The sample is first dried under heat lamps and an aliquot is taken. Stable strontium carrier is added and the sample is leached in hydrachloric acid. The mixture is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(N03)2 using fuming (90%) nitric acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, 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 104
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.
Organic Solids A 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 hydrochloric acid. The sample is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(N0 3) using fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addition of &table yttrium carrier and a minimum of 5 days period for yttrium ingrowth. Yttrium is then precipitated as hydroxide; dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer strontium-90 activity.
Strontium-89 activity is determined by ,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 e 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. A barium scavenge is used to remove some interfering species. An iron (ferric hydroxide) scavenge is performed, followed addition of stable yttrium carrier and a 7 to 10 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is determined by precipitating 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/Dt-Bc-BA)/(2.22 VYs DFsR-89 EsR-89)
TWO SIGMA ERROR Sr-89 = 2((N/Dt+Bc+BA)/.1t) 112/(2.22 VYs DFsR-89 EsR-89)
LLDSr-89 = 4.66((Bc+BA)/.1t)ll2/(2.22 V YS DFsR-89 EsR-89) 105
RESULT Sr-90 = (N/At - B)/(2.22 V Y 1 Y 2 OF IF E)
TWO SIGMA ERROR Sr-90 = 2((N/At+B)/At)ll2/(2.22 VY 1 Y2 OF E IF))
LLDSr-90 = 4.66(B/At)ll2/(2.22 V Y1 Y2 IF OF E) e 106
where: N = total counts from sample (counts)
LY = counting time for sample (min)
Be = background rate of counter (cpm) using absorber configuration 2.22 = dpm/pCi V = volume or weight of sample analyzed BA = background addition from Sr-90 and ingrowth of Y-90 BA = 0.016 (K) + (K) Ey/abs) (IGy_90)
Ys = chemical yield of strontium DF SR-89 = decay factor from the mid collection date to the counting date for SR-89 EsR-89 = efficiency of the counter for SR-89 with the 80 mg/cm.sq.
aluminum absorber K = (NL\t - BC)y_9Ql(Ey_901Fy_90 DFy_90Y 1)
DFy_90) = the decay factor for Y-90 from the "milk" time to the mid count time Ey_90 = efficiency of the counter for Y-90 1Fy_90 = ingrowth factor for Y-90 from scavenge time to milking time IGy_90 = the ingrowth factor for Y-90 into the strontium mount from the "milk" time to the mid count time 0.016 = the efficiency of measuring SR-90 through a No. 6 absorber EY/abs = the efficiency of counting Y-90 through a No. 6 absorber B = background rate *of counter (cpm)
Y1 = chemical yield of yttrium Y2 = chemical yield of strontium DF = decay factor of yttrium from the radiochemical milking time to the mid count time E = efficiency of the counter for Y-90 IF = ingrowth factor for Y-90 from scavenge time to the radio-chemical milking time 107
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, reduced with hydroxylamine hydrochloride and 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 sodium bisulfite solution 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/1:
RESULT = (N/L\t-B)/(2.22 EVY DF)
TWO SIGMA ERROR = 2((N/L\t+B)/L\t)ll2(2.22 EVY DF)
LLD = =4.66(B/L\t)lf2/(2.22 EVY DF) where: N = total counts from sample (counts)
M = counting time for sample (min)
B = background rate of counter (cpm) 2.22 = dpm/pCi V = volume or weight of sample analyzed y = chemical yield of the mount or sample counted DF = decay factor from the collection to the counting date E = efficiency of the counter for I-131, corrected. for self absorption effects by the formula
= Es(exp-0.006 lM)/(exp-0.006 lMs)
= efficiency of the counter determined from an I-131 standard mount Ms = mass of Pdl 2 on the standard mount, mg M = mass of Pdiz on the sample mount, mg 108
GAMMA SPECTROMETRY OF SAMPLES Mille and Water A 1.0 liter Marinelli beaker is filled with a representative aliquot of the sample. The sample is then counted for approximately 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 100°C. As much as possible (up to the total sample) is loaded into a tared I-liter Marinelli and weighed. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.
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 approximately 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 at a low temperature, less than 100°C. The soil or sediment is loaded fully into a tared, standard 300 cc container and weighed. The sample is then counted for approximately six hours with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height and 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 1-131 of each charcoal cartridge can be determined (assuming no positive 1-131) uniquely from the volume of air which passed through it. In the event 1-131 is observed in the initial counting of a set, each charcoal cartridge is' then counted separately, positioned on the face of the detector.
109
Air Particulate The thirteen airborne particulate filters for a quarterly 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.
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 radioactivity 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 of pCi/mass:
RESULT = (S-B)/2.22 t EV F DF) 1WO SIGMA ERROR = 2(S+B)l/2/(2.22 t EV F DF) lLD = 4.66(B)lf2/(2.22 t EV F DF) where: s = Area, in counts, of sample peak and background (region of spectrum of interest)
B = Background area, in counts, under sample peak, determined by a linear interpolation of the representative backgrounds on either side of the peak t = length of ti.me in minutes the sample was counted 2.22 = dpm/pCi E = detector efficiency for energy of interest and geometry of sample V = sample aliquot size (liters, cubic meters, kilograms, or grams)
F = fractional gamma abundance (specific for each emitted gamma)
DF = decay factor from the mid-collection date to the counting date 110
I I
I ENVIRONMENTAL DOSIMETRY Teledyne Isotope~ 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 1LDs.
Following the field exposure period the TLDs are placed in a Teledyne Isotopes Model 8300. One fourth of the rectangular 1LD 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 milliRoentgen (mR):
RESULT = D = (D 1+D2+D3+D,J/4 TWO SIGMA ERROR = 2((D1-D)2+(D2-D)2+(DrD)2+(D4-D)2)/3)1/2 WHERE: D1 = the net mR of area 1 of the TLD, and similarly for Dz, D3, and D4 DI = I1KIR1-A 11 = the instrument reading of the field dose in area 1 K = the known exposure by the Cs-137 source R1 = the instrument reading due to the Cs-137 dose on area 1 A = average dose in mR, calculated in similar manner as above, of the transit control lLDs D = the average net mR of all 4 areas of the 1LD.
111
APPENDIX E EPA INTERLABORATORY COMPARISON PROGRAM 112
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 1989 data summary tables are presented for isotopes in the various sample media applicable to the Surry Power Stations Radiological Environmental Monitoring Program. The footnotes of the table discuss investigations of problems encountered in a few cases.
113
. TRENDING GRAPH - 12 US EPA CROSS CHECK PROGRAM GROSS BETA IN AIR PARTICUIATES 100------------------------------
80
... 60
........ ~
+:>,
-i m Tl +/-3sigma
- EPA+/- 3 sigma 40 20 f
0 -t---r--.--....----.-----...---..-----....----,.---.---~--,.-----,---,.---~
1981 1982 1983 1984 1985 1986 1987 1988 1989 1990
- 08/25/89 EPA test invalid.
US EPA CROSS CHECK PROGRAM CESIUM-137 IN AIR PARTICUIATES 100-------------------------------,
80 60 I-'
I-'
V1 l~ l!I Tl +/-3 sigma
- EPA+/-3sigma 40 20 TI 0
f ,,
1981 1982 1983 1984 1985 1986 1987 1988 1989 1990
US EPA CROSS CHECK PROGRAM IODINE-131 IN MILK 120------------------------------.
100 80 Q\
t 60 m Tl+/-3sigma
- EPA +/-3 sigma 40 20
- ~ I ii 0
1980 1982 1984 1986 1988 1990
US EPA CROSS CHECK PROGRAM POTASSIUM-40 IN MILK 2400
... 2000
~ lq a Tl +/-3 sigma
- EPA +/-3 sigma 1600 1200 1J { f 800+---.~--------~~--~-.----,.~--~..---,.~--~..---,.--...;;.*_...~..-----.-~--~
1981 1982 1983 1984 1985 1986 1987 1988 1989 1990
US EPA CROSS CHECK PROGRAM CESIUM-137 IN MILK 80 l
Ii
!i 60 I-' m Tl+/- 3sigma
-I I-'
CX)
- EPA +/-3 sigma l
40 20 0
1981 1982 1983 1984 1985 I 1986 1987 1988 1989 1990
US EPA CROSS CHECK PROGRAM STRONTWM-89 IN MILK 80
........ JI
~
60 I
I ID a Tl+/- 3 sigma
- EPA +/-3 sigma 40 I
20 lj i 0
1981 1982 1983 1984 1985 I1986 1987 1988 1989 1990
US EPA CROSS CHECK PROGRAM STRONTIUM-90 IN MILK 80 -
.f.
I f
60 -
N ID Tl +/-3sigma 0
. 11
- EPA+/-3 sigma 40 -
ill i .*Hi ..
20 - ~
I' iI 1 0 I I I J I I I 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990
US EPA CROSS CHECK PROGRAM IODINE-131 IN WATER 160 Iq j.
120 N 111 Tl+/- 3 sigma
- EPA +/-3 sigma 80 I 40
~ li ~~ ~, 1 0
1981
~
1982 ai 1983 1984 d
1985
"' 1986 1987 j I.
1988 1989 1990
US EPA CROSS CHECK PROGRAM STRONTIUM-89 IN WATER (pg. 1) 80 N
N Ii 60 m Tl+/- 3 sigma
- EPA +/-3 sigma 40 20 i
0
(
1981 1982 1983 1984 1985
US EPA CROSS CHECK PROGRAM STRONTIUM-89 IN WATER (pg. 2) 80 N
(J;I Ii 60 m Tl+/- 3sigma
- EPA+/- 3 sigma 40 I
I I
20 B f 1
0 1984 1985
' 1986 1987 - 1988 I
1989 1990
US EPA CROSS CHECK PROGRAM STRONTIUM-90 IN WATER 80
... 60 N ! m Tl +/-3sigma
~
.i:,.
- EPA +/-3 sigma 40 i
20 . J~ ! iJH II 0
Ii Ji i fl ~ I i i *I *I ~
1981 1982 1983 1984 1985 1986 1987 1988 1989 1990
SURRY- 1989 US EPA INTERLABORAIDRY COMPARISON PROGRAM 1989 (Page 1 of 3)
EPA Date TI Malled Date EPA EPA TI Norm Dev. **warning Preparation Results Issued Results Media Nuclide Results(a) Results(b) (Known) ***Action 12/16/88 02/fl)/89 04/17/89 Water Ra-226 3.50 +/- 0.50 3.40 +/- 0.00 -0.35 Ra-228 10.30 +/- 1.50 8.83 +/- 0.81 -1.69 01/06/89 03/07/89 05/01/89 Water Sr-89 40.00 +/- 5.00 37.00 +/- 2.65 -1.04 Sr-90 25.00 +/- 1.50 26.00 +/- 2.00 1.15 Ol/20/89 CY2/17/89 04/28/89 Water Gr-Alpha 8.00 +/- 5.00 8.00 +/- 1.00 0.00 Gr-Beta 4.00+/- 5.00 6.00 +/- 0.00 0.69 CY}.Jl0/89 03/14/89 05/12/89 Water Cr-51 235.00 +/- 24.00 245.67 +/- 11.72 0.77 Co-60 10.00 +/- 5.00 12.67 +/- 1.53 0.92 Zn-65 159.00 +/- 16.00 181.33 +/- 5.51 2.42 **(c)
Ru-106 178.00 +/- 18.00 191.00 +/- 9.85 1.25 Cs-134 10.00 +/- 5.00 10.33 +/- 0.58 0.12 Cs-137 10.00 +/- 5.00 13.67 +/- 0.58 1.27 N
U1 CY2/17/89 03/22/89 05/12/89 Water 1-131 106.00 +/- 11.00 98.67 +/- 0.58 -1.15 02/24/89 03/22/89 05/01/89 Water H-3 2754.00 +/- 356.00 2866.67 +/- 251.66 0.55 03/10/89 05/26/89 06/16/89 Water Ra-226 4.90 +/- 0.70 5.07 +/- 0.29 0.41 Ra-228 1.70 +/- 0.30 1.47 +/- 0.29 -1.35 03/31/89 06/08/89 00/10/89 Air Filter Gr-Alpha 21.00 +/- 5.00 28.67 +/- 1.15 2.66 **(d)
Gr-Beta 62.00+/- 5.00 65;67 +/- 1.53 1.27 Sr-90 20.00 +/- 1.50 19.67 +/- 2.08 -0.38 Cs-137 20.00+/- 5.00 18.00 +/- 1.00 -0.69 04/18/89 06/21/89 00/28/89 LabPerf Gr-Alpha 29.00+/- 7.00 21.33 +/- 2.31 -1.90 Sample A Ra-226 3.50 +/- .0.50 3.47 +/- 0.23 -0.12 Ra-228 3.60+/- 0.50 3.60 +/- 0.10 0.00 SampleB Gr-Beta 57.00+/- 5.00 53.00 +/- 3.61 -1.39 Sr-89 8.00 +/- 5.00 8.00 +/- 0.00 0.00 Sr-90 8.00+/- 1.50 7.67 +/- 0.58 -0.38 Cs-134 20.00+/- 5.00 19.67 +/- 1.53 -0.12 Cs-137 20.00 +/- 5.00 20.00+/- 2.65 0.00
- Footnotes at end of table.
SURRY - 1989 US EPA INTERLABORATORY COMPARISON PROGRAM 1989 (Page 2 of3)
EPA Date TI Malled Date EPA EPA TI Norm Dev. **warning Preparation Results Issued Results Media Nuclide Results(a) Results(b) (Known) ***Action 04/28/89 06/21/89 08/07/89 Milk Sr-89 39.00 +/- 5.00 36.67+/- 1.15 -0.81 Sr-90 55.00 +/- 3.00 56.33 +/- 1.53 0.77 Cs-137 50.00 +/- 5.00 53.33 +/- 2.31 1.15 K 1600.00 +/- 80.00 1760.00 +/- 113.58 3.46 ***(e) 05/05/89 07/06/89 08/14/89 Water Sr-89 6.00 +/- 5.00 6.33 +/- 0.58 0.12 Sr-90 6.00 +/- 1.50 6.33 +/- 0.58 0.38 06/09/89 07/19/89 08/28/89 Water Ba-133 49.00 +/- 5.00 33.00 +/- 3.61 -5.54 ***(0 Co-60 31.00 +/- 5.00 30.00 +/- 2.65 -0.35 Zn-65 165.00 +/- 17.00 165.33 +/- 0.58 0.03 Ru-106 128.00 +/- 13.00 113.67 +/- 17.50 -1.91 Cs-134 39.00 +/- 5.00 34.00 +/- 2.65 -1.73 Cs-137 20.00 +/- 5.00 22.00 +/- 3.61 0.69 06/23/89 07/19/89 08/14/89 Water H-3 4503.00 +/- 450.00 4466.67 +/- 152.75 -0.14 I-'
N
°' 08125/89 12/19/89 Air Filter Gr-alpha 6.00 +/- 5.00 8.33 +/- 0.98 0.81 Cs-137 10.00 +/- 5.00 12.00 +/- 1.00 0.69 00/22/89 10/19/89 11/13/89 Water Gr-Alpha 4.00 +/- 5.00 5.00 +/- 0.00 0.35 Gr-Beta 6.00+/- 5.00 8.00 +/- 0.00 0.69 10/06/89 11/16/89 12/19/89 Wata Ba-133 59.00+/- 6.00 51.00 +/- 4.36 -2.31 **(g)
Co-60 30.00 +/- 5.00 30.67 +/- 2.08 0.23 Zn-65 129.00 +/- 13.00 128.33 +/- 2.89 -0.09 Ru-106 161.00 +/- 16.00 139.00 +/- 15.72 -2.38 **(g)
Cs-134 29.00+/- 5.00 23.67 +/- 1.15 -1.85 Cs-137 59.00+/- 5.00 61.67 +/- 1.53 0.92 10/20/89 11/16/89 12/19/89 Water H-3 3496.00+/- 364.00 3433.33 +/- 57.74 -0.30 11/10/89 01/05/90 01/30/90 Water Ra-226 8.70 +/- 1.30 8.47 +/- 0.49 -0.31 Ra-228 9.30 +/- 1.40 8.57 +/- 1.46 -0.91
- Foo!notes at end of table.
SURRY- 1989 US EPA INTERLABORATORY COMPARISON PROGRAM 1989 (Page30F 3)
Footnotes:
(a) Average+/- experimental sigma.
~) Expected laboratory precision (1 sigma, 1 determination).
(c) The lhree Zn-65 measurements were 184, 175 and 185 pCi/liter. These were measured on three detectors using the same aliquot. The other reported resulls (Cr-51, Co-60, Ru-106, Cs-134, Cs-137) were all within two standard deviations of the EPA results, This would indicate that the dilution made was correct (except that possibly the Zn-65 was not well mixed). Other parameters were investigated. The branching intensity, decay factor, and detection efficiencies were checked. Since one of the Co-60 gamma ray energies is only 60 KeV from Zn-65, the detector efficiencies must be correcL There is no obvious reason for the deviation. Another aliquot was counted yielding 165 pCi/1.
(d) The EPA deposits activity on the filter over a small diameter (nearly a point source) whereas our calibration is based on a deposit nearly 2 inches in diameter. In order to correct to point,so~ geometry our p-acticc has been to divide our results by 1.2. We neglected to do it on this test.
(e) There is no apparent r:cason why the potassium was high. Three separate detectors were used and the K-40 value for each was correctly divided by 0.86 to convert to potassium in mg/liter.
(f) There is no apparent reason why Ba-133 was low by 5.54 standanl deviation while the other isotopes were within +/- 2 standard deviations. The detector efficiencies and Ba-133 branching intensities were checked and found to be conccL On 10/31/89, 300 ml of the original, undiluted sample was counted giving 43.9 +/- 5.8 pCi/1 of Ba-133.
.,.. (g) This EPA samples was counted in two geometries; me in diluted stage, the ~ther undiluted. There was no significant difference. Comparing detector efficiencies betweeri two
~ 8JU1ual sets did not reveal any significant difference. Thus there is no apparent reason why our results differed as much as they did.