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* Sample or Measurement Airborne Effluent Air Particulate Thermo luminescent Dosimetry Precipitation Milk. Soil Crops Surface Water Liquid Effluent James River Water Oysters and Clams Crab Silt Fish Liquid and/or Airborne Well Water Fowl TABLE II Environmental Measurement and Sample Analysis Program Frequency Analysis Bi-weekly Gros*s alpha and beta Quarterly Gamma Isotopic (2) Composite Quarterly Radiation Dose Monthly Gross beta (3) Tritium Quarterly Gross beta Composite Tritium Monthly Iodine-131 Sr-89,90 Gamma Isotopic Stable Calcium Annually Gamma Isotopic Annually Gamma Isotopic Sr-89,90 Semi-annually Gross alpha and beta *Tritium Bi-monthly . Gamma Isotopic Semi-annually Tritium Composite Bi-monthly Gamma .Isotopic (4) Three Summer . Gamma Isotopic Months Semi-annually Gamma Isotopic Semi-annually Gamma Isotopic Semi-annually Gross alpha and beta Semi-annually Gamma Isotopic (4) (1) 5
* Sample or Measurement Airborne Effluent Air Particulate Thermo luminescent Dosimetry Precipitation Milk. Soil Crops Surface Water Liquid Effluent James River Water Oysters and Clams Crab Silt Fish Liquid and/or Airborne Well Water Fowl TABLE II Environmental Measurement and Sample Analysis Program Frequency Analysis Bi-weekly Gros*s alpha and beta Quarterly Gamma Isotopic (2) Composite Quarterly Radiation Dose Monthly Gross beta (3) Tritium Quarterly Gross beta Composite Tritium Monthly Iodine-131 Sr-89,90 Gamma Isotopic Stable Calcium Annually Gamma Isotopic Annually Gamma Isotopic Sr-89,90 Semi-annually Gross alpha and beta *Tritium Bi-monthly . Gamma Isotopic Semi-annually Tritium Composite Bi-monthly Gamma .Isotopic (4) Three Summer . Gamma Isotopic Months Semi-annually Gamma Isotopic Semi-annually Gamma Isotopic Semi-annually Gross alpha and beta Semi-annually Gamma Isotopic (4) (1) 5
* NOTES TO TABLE II (1) Gamma isotopic analysis if gross beta exceeds 10 pCi/n 3* (2) Quarterly composites of bi-weekly air particulate samples will be analyzed for gamma emitters in three groups as follows: Stations 1 and 2 analyzed as one sample. Stations 3,5,6,9 and 10 analyzed as one sample. Station 11 analyzed as one sample. Strontium-90 determined radiochemically if significant amounts of fission products attributable to the Station are detected by the gamma isotopic analysis.  
* NOTES TO TABLE II (1) Gamma isotopic analysis if gross beta exceeds 10 pCi/n 3* (2) Quarterly composites of bi-weekly air particulate samples will be analyzed for gamma emitters in three groups as follows: Stations 1 and 2 analyzed as one sample. Stations 3,5,6,9 and 10 analyzed as one sample. Station 11 analyzed as one sample. Strontium-90 determined radiochemically if significant amounts of fission products attributable to the Station are detected by the gamma isotopic analysis.
(3) Perform gamma isotopic analysis if gross beta exceeds 15 nCi/m 2* (4) Entire sample analyzed for gamma emitters.
(3) Perform gamma isotopic analysis if gross beta exceeds 15 nCi/m 2* (4) Entire sample analyzed for gamma emitters.
Sr-90 to be determined if a significant amount of fission products attributable to the Station are noted in the gamma analysis .. 6 Medium or Pathway Sampled (Unit of Measurement)
Sr-90 to be determined if a significant amount of fission products attributable to the Station are noted in the gamma analysis .. 6 Medium or Pathway Sampled (Unit of Measurement)
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Name of Facility Surry Power Plant Docket No. ---------------
Name of Facility Surry Power Plant Docket No. ---------------
50-280 50-281 Location of Facility __ s_u_r_ry'-'-, _V_i_r..::g;...i_n_i_a
50-280 50-281 Location of Facility __ s_u_r_ry'-'-, _V_i_r..::g;...i_n_i_a
______ Reporting Period 01 January through 31 December 1978 (Coun~y, State) Type and Lower Limit -Total Number of All Indicator Locations Location with Hiahest Annual Mean Control Locations of Analyses Detection Mean (f)b Name Mean (f)11 Mean (f)b Performed  
______ Reporting Period 01 January through 31 December 1978 (Coun~y, State) Type and Lower Limit -Total Number of All Indicator Locations Location with Hiahest Annual Mean Control Locations of Analyses Detection Mean (f)b Name Mean (f)11 Mean (f)b Performed
{LL_D) Ranr,e Distance *& Direction Range Range . Cs-137 58 15 19 (4/35) Bacon's Castle 21 (2/11) 17 (3/23) 16 -23 Judkins 18 -23 13 -21 lln-l.n-140 58 15 1\11 LLD Not Applicable All LLD Sr-89 3 5 All LLD Not Applicable 1\11 LLD Sr-90 3 2 II II II II II II H-3 8 330 2500 (4/4) Station Discharge 2500 (4/4) All LLD 300 *-8400 300 -8400 lla-La-140 34 15 AlJ u.n Not -App lien bl c All 1.1.D Cs-134 34 15 " II II II " II Cs-137 34 15 " II II II II II Zr-Nb-95 34 10 II II 'II II II II Co-58 34 15 " " II II II II Mn-54 34 15 " II II II II II Zn-65 34 ! 15 " " II II II II .. Fe-59 34 30 II " II II II II Mn-54 30 130 II II II II " II Fe-59 30 260 II II " II " II Number of Nonroutine Reported Measurements 0 0 0 0 0 0 0 0 0 0 0 0 0 0 bMean and range based upon detectable  
{LL_D) Ranr,e Distance *& Direction Range Range . Cs-137 58 15 19 (4/35) Bacon's Castle 21 (2/11) 17 (3/23) 16 -23 Judkins 18 -23 13 -21 lln-l.n-140 58 15 1\11 LLD Not Applicable All LLD Sr-89 3 5 All LLD Not Applicable 1\11 LLD Sr-90 3 2 II II II II II II H-3 8 330 2500 (4/4) Station Discharge 2500 (4/4) All LLD 300 *-8400 300 -8400 lla-La-140 34 15 AlJ u.n Not -App lien bl c All 1.1.D Cs-134 34 15 " II II II " II Cs-137 34 15 " II II II II II Zr-Nb-95 34 10 II II 'II II II II Co-58 34 15 " " II II II II Mn-54 34 15 " II II II II II Zn-65 34 ! 15 " " II II II II .. Fe-59 34 30 II " II II II II Mn-54 30 130 II II II II " II Fe-59 30 260 II II " II " II Number of Nonroutine Reported Measurements 0 0 0 0 0 0 0 0 0 0 0 0 0 0 bMean and range based upon detectable  
*measurements bnly, Fraction of detectable measurements at specified locations is indicated in parentheses. (f) I
*measurements bnly, Fraction of detectable measurements at specified locations is indicated in parentheses. (f) I
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*
*
* Some of the collections from Newport News are designated State Split samples. Data presented on page 4-6 of Appendix I show that concentrations of gamma emitters were below the LLD's of the program throughout the year. Fish Samples Fish are collected from the vicinity of the Station twice a year and analyzed for gamma emitters by gamma spectroscopy.
* Some of the collections from Newport News are designated State Split samples. Data presented on page 4-6 of Appendix I show that concentrations of gamma emitters were below the LLD's of the program throughout the year. Fish Samples Fish are collected from the vicinity of the Station twice a year and analyzed for gamma emitters by gamma spectroscopy.
A sample of catfish collected in February contained  
A sample of catfish collected in February contained
: 1. 9+/-1. 6 pCi/kg (wet we*ight) Cs-137. This concentration of Cs-137 is not considered to be especially unusual in bottom feeders. This and other gamma emitters were below the LLD's for the program in other samples of this and other species collected during the year. Data are presented on page 4-7 of Appendix I. Crab Samples Samples of crabs from the vicinity of Surry Station are collected in July, August and September.
: 1. 9+/-1. 6 pCi/kg (wet we*ight) Cs-137. This concentration of Cs-137 is not considered to be especially unusual in bottom feeders. This and other gamma emitters were below the LLD's for the program in other samples of this and other species collected during the year. Data are presented on page 4-7 of Appendix I. Crab Samples Samples of crabs from the vicinity of Surry Station are collected in July, August and September.
Results of analyses on each of the collections as given on page 4-7 of Appendix I indicate that gamma emitters were below the LLD's for the program in all samples. Soil Samples Soil samples are collected annually from six locations and analyzed by gamma spectrometry for gamma emitters.
Results of analyses on each of the collections as given on page 4-7 of Appendix I indicate that gamma emitters were below the LLD's for the program in all samples. Soil Samples Soil samples are collected annually from six locations and analyzed by gamma spectrometry for gamma emitters.
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Air Particulate Filters Gross Beta -Exposed air particulate filters are counted in low ground Geiger or proportional flow beta counters using anti-coincidence background suppression.
Air Particulate Filters Gross Beta -Exposed air particulate filters are counted in low ground Geiger or proportional flow beta counters using anti-coincidence background suppression.
Filters are counted long enough to ensure that the required sensitivity (LLD) will be met. Gamma Isotopic -quarterly composites of air particulate filters are counted in high resolution (GeLi) gamma spectrometers for periods of time long enough to ensure that the required program sensitivity (LLD) is met. (See also intro. to data tables, Appendix I). Water Samples (including surface, well, James River waters and precipitation).
Filters are counted long enough to ensure that the required sensitivity (LLD) will be met. Gamma Isotopic -quarterly composites of air particulate filters are counted in high resolution (GeLi) gamma spectrometers for periods of time long enough to ensure that the required program sensitivity (LLD) is met. (See also intro. to data tables, Appendix I). Water Samples (including surface, well, James River waters and precipitation).
Gross Beta -a measured aliquot of sample is digested, "wet-ashed", evaporated, transferred to a tared 47mm stainless steel planchet, dried and weighed. The planchetted sample is counted long enough in a low background beta counter to ensure that -the LLD of the program will *be met. (1) HASL Procedures Manual, edited by John H. Harley, Health and Safety Laboratory, U. S. Atomic Energy Commission, 1972 edition, revised annually.  
Gross Beta -a measured aliquot of sample is digested, "wet-ashed", evaporated, transferred to a tared 47mm stainless steel planchet, dried and weighed. The planchetted sample is counted long enough in a low background beta counter to ensure that -the LLD of the program will *be met. (1) HASL Procedures Manual, edited by John H. Harley, Health and Safety Laboratory, U. S. Atomic Energy Commission, 1972 edition, revised annually.
(2) National Environmental Research Center, Environmental Handbook of Radiochemical Analytical  
(2) National Environmental Research Center, Environmental Handbook of Radiochemical Analytical
:Methods.
:Methods.
Program Office of Research and Dev~lopment, Las Vegas, Nevada Protection Agency; Element lHA 325. 89114. 22
Program Office of Research and Dev~lopment, Las Vegas, Nevada Protection Agency; Element lHA 325. 89114. 22
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If higher sensitivity is r~quired (ie. <~500 pCi/1) the sample is isotopically enriched in tritium concentration prior to liquid scintillation counting.
If higher sensitivity is r~quired (ie. <~500 pCi/1) the sample is isotopically enriched in tritium concentration prior to liquid scintillation counting.
23
23
* Isotopic enrichment is done by the classical method of Ostlund which involves alkaline electrolysis of a purified aliquot of sample under controlled conditions of temperature and electrode current density. Milk Samples I-131 -measured amounts of carrier iodide are added to a known volume of milk and the iodine extracted on anion exchange resin. The iodine is recovered and uurified by classical iodine chemistry methods which are similar to those given in former Regulatory Guide 4.3. The yield or recovery of iodine is measured gravimetrically and the precipitated sample is mounted and counted in a low level beta detector for a long enough period to ensure that the required LLD is met. Gamma Isotopic -a measured aliquot of sample is evaporated and oven dried to a standard volume and counted in a fixed geometry in a high resolution (GeLi) gamma spectrometer for a long enough period to ensure that the required LLD's are reached (see also Introduction to data Tables). Sr-89 and Sr-90 -Stable strontium carrier is added to an aliquot of the sample which is then dried and ashed at high temperature  
* Isotopic enrichment is done by the classical method of Ostlund which involves alkaline electrolysis of a purified aliquot of sample under controlled conditions of temperature and electrode current density. Milk Samples I-131 -measured amounts of carrier iodide are added to a known volume of milk and the iodine extracted on anion exchange resin. The iodine is recovered and uurified by classical iodine chemistry methods which are similar to those given in former Regulatory Guide 4.3. The yield or recovery of iodine is measured gravimetrically and the precipitated sample is mounted and counted in a low level beta detector for a long enough period to ensure that the required LLD is met. Gamma Isotopic -a measured aliquot of sample is evaporated and oven dried to a standard volume and counted in a fixed geometry in a high resolution (GeLi) gamma spectrometer for a long enough period to ensure that the required LLD's are reached (see also Introduction to data Tables). Sr-89 and Sr-90 -Stable strontium carrier is added to an aliquot of the sample which is then dried and ashed at high temperature
(>700&deg;c).
(>700&deg;c).
The ash is dissolved and the solution treated from this point on in the same manner as are water samples (Q.y.). Organic Samples (including Clams, Oysters, Fish, Crabs, Food Crops arid Fowl). Gamma Isotopic Analysis -a measured aliquot of sample is oven dried or ashed as appropriate, placed in a controlled geometry and counted in a high resolution (GeLi) gamma spectrometer for a period long enough to ensure that the LLD's of the program will be met (see also intro. to Data Tables) . 24 _ __J In the case of samples such as fish and fowl, the edible flesh is rated from bones and entrails prior to drying. Sr-89 and Sr-90 -stable strontium carrier is added to a weighed aliquot of the sample and the sample is ashed at high te~perature  
The ash is dissolved and the solution treated from this point on in the same manner as are water samples (Q.y.). Organic Samples (including Clams, Oysters, Fish, Crabs, Food Crops arid Fowl). Gamma Isotopic Analysis -a measured aliquot of sample is oven dried or ashed as appropriate, placed in a controlled geometry and counted in a high resolution (GeLi) gamma spectrometer for a period long enough to ensure that the LLD's of the program will be met (see also intro. to Data Tables) . 24 _ __J In the case of samples such as fish and fowl, the edible flesh is rated from bones and entrails prior to drying. Sr-89 and Sr-90 -stable strontium carrier is added to a weighed aliquot of the sample and the sample is ashed at high te~perature
()700&deg;c)~
()700&deg;c)~
The ashed sample is then dissolved and processed in the same manner as are water or milk samples. Soil and Silt Samples Gamma Isotopic Analysis -the sample is oven dried to facilitate handling and then sieved to remove pieces of stone and/or other large pieces of material.
The ashed sample is then dissolved and processed in the same manner as are water or milk samples. Soil and Silt Samples Gamma Isotopic Analysis -the sample is oven dried to facilitate handling and then sieved to remove pieces of stone and/or other large pieces of material.
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* 1.0 Introduction_
* 1.0 Introduction_
to the Data Tables In this section are given itens of information helpful in standing the presentation of the data in the Tables. 1.
to the Data Tables In this section are given itens of information helpful in standing the presentation of the data in the Tables. 1.
* Error Term!=l Data preceded by the "less than" symbol (<) are at the 3cr (99% confidence) level. The error terms on other data are 2cr (95% confidence).  
* Error Term!=l Data preceded by the "less than" symbol (<) are at the 3cr (99% confidence) level. The error terms on other data are 2cr (95% confidence).
: 2. Sensitivities  
: 2. Sensitivities  
-LLD's Analytical sensitivities or LLD's (Lower Limits of Detection) are those given in the most recent NRC Branch Position on Regulatory Guide 4.8. (Table A) For analyses not required in RG. 4.8, Federal EPA, former requirements for similar programs, or other appropriate guides are used (Table B). The LLD's are calculated as per RG. 4.8 at the 3cr level. The Guide specifically states that t_he LLD's are~ priori not a posteriori; limits for a particular measurement.
-LLD's Analytical sensitivities or LLD's (Lower Limits of Detection) are those given in the most recent NRC Branch Position on Regulatory Guide 4.8. (Table A) For analyses not required in RG. 4.8, Federal EPA, former requirements for similar programs, or other appropriate guides are used (Table B). The LLD's are calculated as per RG. 4.8 at the 3cr level. The Guide specifically states that t_he LLD's are~ priori not a posteriori; limits for a particular measurement.
When, however, RG. 4.-S-Or other LLD's have not been achieved, a footnote giving a brief explanation has been inserted.  
When, however, RG. 4.-S-Or other LLD's have not been achieved, a footnote giving a brief explanation has been inserted.
: 3. Gamma Isotopic Analyses All samples to be analyzed for gamma emitters are assayed using high resolution gamma spectrometers. (Geli). The spectra are computer scanned using recognized programs.
: 3. Gamma Isotopic Analyses All samples to be analyzed for gamma emitters are assayed using high resolution gamma spectrometers. (Geli). The spectra are computer scanned using recognized programs.
The energy search programs specifically examine the peak areas of gamma energies for the expected effluents from nuclear power plants. Only the nuclides required by NRC Reg. Guide 4.8 are reported in the Data Tables. If other gamma emitters associated with either power station operation or worldwide fallout.from nucleaf weapons tests are detected, this information is either given in cussions of the data or entered as footnotes to the data tables. Naturally occurring gamma emitters are frequently detected in mental samples. Analyses of these nuclides is not required by the NRC and they are neither quantified when detected nor reported in the Data Tables. 4. Exponents Exponents necessary to prevent data tables from being cumbersome are handled in the conventional manner of including them in column headings . 1-1 i 2.0 Airborne Radioactivity  
The energy search programs specifically examine the peak areas of gamma energies for the expected effluents from nuclear power plants. Only the nuclides required by NRC Reg. Guide 4.8 are reported in the Data Tables. If other gamma emitters associated with either power station operation or worldwide fallout.from nucleaf weapons tests are detected, this information is either given in cussions of the data or entered as footnotes to the data tables. Naturally occurring gamma emitters are frequently detected in mental samples. Analyses of these nuclides is not required by the NRC and they are neither quantified when detected nor reported in the Data Tables. 4. Exponents Exponents necessary to prevent data tables from being cumbersome are handled in the conventional manner of including them in column headings . 1-1 i 2.0 Airborne Radioactivity  
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-16 18+/- 5 18+/- 1 16+/- 1 17+/-2 Dow -17 24+/- 6 21+/- 3 16+/- 1 18+/-2 Lee Hall -18 25+/- 3 21+/- 1 20+/- 2 22+/-4 Fort Eustis -19 19+/- 2 17+/- 1 15+/- 1 18+/-2 Newport News -20 21+/- 5 19+/- 2 17+/- 1 17+/-2 Smithfield(Subst.)  
-16 18+/- 5 18+/- 1 16+/- 1 17+/-2 Dow -17 24+/- 6 21+/- 3 16+/- 1 18+/-2 Lee Hall -18 25+/- 3 21+/- 1 20+/- 2 22+/-4 Fort Eustis -19 19+/- 2 17+/- 1 15+/- 1 18+/-2 Newport News -20 21+/- 5 19+/- 2 17+/- 1 17+/-2 Smithfield(Subst.)  
-21 22+/- 4 21+/- 1 18+/- 1 20+/-2 Smithfield(l0&258)  
-21 22+/- 4 21+/- 1 18+/- 1 20+/-2 Smithfield(l0&258)  
-22 19+/- 2 18+/- 1 15+/- 1 14+/-3 Rt 10 and 676 -23 16+/- 4 14+/- 1 13+/- 1 13+/-1 ' 0-, I I-'
-22 19+/- 2 18+/- 1 15+/- 1 14+/-3 Rt 10 and 676 -23 16+/- 4 14+/- 1 13+/- 1 13+/-1 ' 0-, I I-'
(J'\ I t...)
(J'\ I t...)
* Date lnstalledi Date R.emoved:
* Date lnstalledi Date R.emoved:

Revision as of 13:52, 25 April 2019

Environ Monitoring Rept,1978.
ML18113A892
Person / Time
Site: Surry  Dominion icon.png
Issue date: 12/31/1978
From: CHANDRASEKARAN, TRAUTMAN M
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18113A887 List:
References
NUDOCS 7903070381
Download: ML18113A892 (57)
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Text

  • ** Reviewed By: / ENVIRONMENTAL MONITORING REPORT JANUARY 1 -DECEMBER 31, 1978 SURRY POWER STATION VIRGINIA ELECTRIC AND POWER COMPANY MIDWESTERN FACILI1Y EBERLINE INSTRUMENT CORPORATION WEST CHICAGO; ILLINOIS Approved By: !, '1 r-, ' ~~.µ*::>*
  • {~ ,-('

s., PhD p~ -~----=: .:l~Trautman, Manager ~lidwestern Facility Laboratory Manager V ,\ * '_) Dose Range (mrem) VIRGINIA ELECTRIC Ai.'1D POWER COMPANY SURRY POWER STATION LICENSE NOS. DPR-32 and DPR-37 RECORDED Ai.'1NUAL WHOLE BODY EXPOSURES CALENDAR YEAR 1978 Number of Individuals No measureable exposure 1301 1-99 100-249 250-499 500-749 750-999 1000-1999 2000-2999 3000-3999 4000-4999 5000-5999 6000-6999 7000-7999 8000-8999 9000-9999 10000-10999 11000-11999 12000-plus Total Number of Individuals reported 1077 215 111 76 77 341 147 75 40 24 14 6 0 0 0 0 0 3504 The above information is submitted for the total number of individuals for whom individual monitoring was provided during the calendar year. ***---*-----~--*****--*-*

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

    • ---.. -***--**--*-

....... --** -

' I I ;*. ,* r Station Employees Job Numbei**of

'Function Individuals Routine " Surveillance 366 Refueling 5 Steam Generator 17 Tube Eddy Cur-rent, Removal and !?lugging Primary System 24 Maintenance Liquid Waste 10 r.x. i Resin Transfer 4 Rad Waste B (Solid)

  • 1:~rn..11rn;:m::qn~rn;=~...::=c:a:~m

!Total Dose *. Rem 502.363 15.022 .. 51,495 101,232 10.264 5,938 5,243 :,. VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION LICENSE NOS, DPR-32 AND DPR-37 MAN JUIM EXPOSURE -.10B FUNCTION JANUARY TO DECEMBER 1978 TECHNICAL SPECIFICATION 6.6b (3) Utility Employees

.. Job Number Total Dose Function Individuals Rem Routine Surveillance 21 5;928 ' .. Refueling , . 8 5. 31~ Steam Generator 3.3 59. 728 Tube Eddy Cur-rent, Removal and Plugging Primary System 0 0 Maintenance Liquid Waste o* 0 I.x. Resin Transfer 0 0 Rad Waste 0 0 (Solid) I --= ::d::::::r:::===r

.;a:.

  • j ,, .. ( Sub-Contractural Employees Job Number of Total Dose Function Individuals Rem Routine Surveillance 150 177,456 Refueing 6 1.941 Steam Generato1 385 676.818 Tube Eddy Cur-rent, Removal and Plugging Primary System 51 *83.376 Maintenance Liquid Waste 0 0 r.x. Resin T.ransfer 0 0 Rad Wast~ 38 32.009 (Solid) .. -*=*=~~

, . . INTRODUCTION

  • The Surry Power Station of Virginia Electric and Power Company consists of two Westinghouse pressurized water reactors each with a generating capacity of 788 MWE. The station is located on a peninsula in the James River mately 25 miles upstream of the Chesapeake Bay. Cooling water is taken in stream of the site and discharged

5.7 miles

upstream of the intake. The Surry Power Station has been designed to minimize radioactive releases and insure that radiation doses attributed to the operation of the station will be "as low as reasonably-achievable".

Various environmental samples are collected at indicator and control or background iocations and analyzed to determine if changes in radioactivity levels may be attributable to the operation of the station. This environmental logical monitoring program provides surveillance to assure compliance with the NRC Regulations and the Surry Power Station Technical Specifications.

The program outlined in Tables I and II has in some cases more frequent collection and analysis of certain samples than called for in the Technical Specifications.

The accompanying map shows the plant environs.

Table III summar_~ izes the results of the radiological environmental surveillance measurements during calendar year 1978. 1 N, * *TABLE I Monitoring or Sampling Locations and Frequencies Surry Station Hog Island Reserve Bacon's Castle Chippokes Creek Alliance Colonial Parkway Williamsburg Jamestown Dow Fort Eustis Newport News Scotland Wharf Lee Hall Routes 10 and 676 Smithfield Guard Booth Station Intake Kings Mill Budweiser Station Discharge Air Particulate BW BW BW BW BW BW BW BW Ambient Radiation Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Bi-weekly M -Monthly Bi-monthly Q -Quarterly Semi-annually A -Annually -Annually corn, peanuts, and soybeans Precipitation M M BW -BM -SA -A(3) SM -Summer Months (two Samplings:

July -September)

Milk M(2 ea.) M M ~1 Well Water SA SA SA SA Surface Water SA SA SA SA Soil A A A A A A TABLE I (continued)

Bacon's Castle Hog Island Reserve Jamestown Newport News Chickahominy Station Discharge Hog Island Point Station Intake

  • Lawnes Creek Deep Water Shoals Point of Shoals BW -Bi-weekly BM -Bi-monthly SA-Semi-annually Crops A(3) James River Fowl Water SA BM BM BM BM BM* M -Monthly Q -Quarterly A -Annually A(3) -Annually corn, peanuts, and soybeans Silt Oyster SA BM SA SA SA SA BM SA BM SM -Summer Months (three Samplings:

July -August -September)

Clams Fish Crab BM BM BM BM SA SM BM

' l

  • CHARLES CITY COU_NTY A SURRY STATION B HOG ISLAND C CHIPPOKES STATE PARK D BACONS CASTLE* E TOWN OF SURRY . ./' F HERON ROOKERY /' / G FERRY ( SCOTLAND GI -JAMESTOWN G2 l H JAMESTOWN ISLAND . I WILLIAMSBURG J BUSCH GARDENS K YORKTOWN BATTLEFIELD L COLONIAL PARKWAY M FORT EUSTIS
  • N JAMES RIVER BRIDGE P TUNNEL R COBHAMBAY 0 5 MILEAGE Environs of Surry Power Station
  • 4

. i *

  • Sample or Measurement Airborne Effluent Air Particulate Thermo luminescent Dosimetry Precipitation Milk. Soil Crops Surface Water Liquid Effluent James River Water Oysters and Clams Crab Silt Fish Liquid and/or Airborne Well Water Fowl TABLE II Environmental Measurement and Sample Analysis Program Frequency Analysis Bi-weekly Gros*s alpha and beta Quarterly Gamma Isotopic (2) Composite Quarterly Radiation Dose Monthly Gross beta (3) Tritium Quarterly Gross beta Composite Tritium Monthly Iodine-131 Sr-89,90 Gamma Isotopic Stable Calcium Annually Gamma Isotopic Annually Gamma Isotopic Sr-89,90 Semi-annually Gross alpha and beta *Tritium Bi-monthly . Gamma Isotopic Semi-annually Tritium Composite Bi-monthly Gamma .Isotopic (4) Three Summer . Gamma Isotopic Months Semi-annually Gamma Isotopic Semi-annually Gamma Isotopic Semi-annually Gross alpha and beta Semi-annually Gamma Isotopic (4) (1) 5
  • NOTES TO TABLE II (1) Gamma isotopic analysis if gross beta exceeds 10 pCi/n 3* (2) Quarterly composites of bi-weekly air particulate samples will be analyzed for gamma emitters in three groups as follows: Stations 1 and 2 analyzed as one sample. Stations 3,5,6,9 and 10 analyzed as one sample. Station 11 analyzed as one sample. Strontium-90 determined radiochemically if significant amounts of fission products attributable to the Station are detected by the gamma isotopic analysis.

(3) Perform gamma isotopic analysis if gross beta exceeds 15 nCi/m 2* (4) Entire sample analyzed for gamma emitters.

Sr-90 to be determined if a significant amount of fission products attributable to the Station are noted in the gamma analysis .. 6 Medium or Pathway Sampled (Unit of Measurement)

Air Particulates (pCi/m 3) 1 Gamma Dose (mR/wk) Precipitation (pCi/1) H-3 (nCi/rn 2) B Milk (pCi/l)

  • TABLE III ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Docket No. 50..,,280 50-281 ---------'----"'~=------

  • Name of Facility Surry Power Plant Location of Facility Surry, Virginia (County, State) Reporting Period 01 January through 31 December 1978 Type and Lower Limit -Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations of Analyses Detection Mean (f)b Name Mean (f)D Mean (f)b Performed (LLD) Range Distance & Direction Ran2e Ran2e Gross B 221 .01 0.11 (187 /193) Surry Station . 0.12 (27 /28) 0.13 (28/28) .01 -.61 -.02 -.61 .01 -.66 Gross a 213 .01 .01 (1/194) Ft. Eustis .01 (1/27) .01 (1/27) .01 4.8 ML N, .01 .01 y T:;otoplr 12 .01 Ce-.Lt,t 1
  • Qt, (3/4) Composi.tc-Surry

.04 0/4) .08 (li/8) .02 -. 07 Stll., lion In, He,icrvli

.02 -,07 .Oli -.16 Ru-106 .01 (1/4) Sta., Hog Ts. Reserve .01 (1/ lf) .02 (1/8) Cs-1 Jt, All LLD Not Applicable All LLD Cs-137 All LLD Not Appl icahle All LU> Dose 96 0.5 1.8 (76/76) Surry Station 17 .4 .(4/4) 1.0 (12/12) 0.6 -17.4 On Site 13.4 -21.0

  • 0.8 -1.2 Gross B 28 5 1.1 (15/15) Surry Station 1.1 (15/15) 0.8 (15/15) .03 -3.4 On Site .03 -3.4 0.4 -2.,, Tritium 30 300 780 (12/16) Surry Station 780 (12/15) 730 (12/16) 400 -2200 On Site 400 -2200 360 -1700 I-131 58 0.5 1.1 (1/35) llncon' s Cnstle 1.1 (1/11) 0.9 (2/23) 1.1 (J,,<lklns) 1.1 0.6 -1.2 Sr-89 58 5 All LLD Not Applicable All LLD Sr-90 58 2 5 (43/46) Bacon's Castle 8 (9/10) 5 (11/11) 1 -17 (Judkins) 4 -16 2 -12 Number of Non routine Reported Measurements 0 0 0 0 0 0 0 0 0 0 bMean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses. (f) ..... _j (X) Medium or Pathway Sampled (Unit of Measurement)

Milk (cont'd) River Water (pCi/1) Clams (pCi/kg) TA~LE III (continued)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Surry Power Plant Docket No. ---------------

50-280 50-281 Location of Facility __ s_u_r_ry'-'-, _V_i_r..::g;...i_n_i_a

______ Reporting Period 01 January through 31 December 1978 (Coun~y, State) Type and Lower Limit -Total Number of All Indicator Locations Location with Hiahest Annual Mean Control Locations of Analyses Detection Mean (f)b Name Mean (f)11 Mean (f)b Performed

{LL_D) Ranr,e Distance *& Direction Range Range . Cs-137 58 15 19 (4/35) Bacon's Castle 21 (2/11) 17 (3/23) 16 -23 Judkins 18 -23 13 -21 lln-l.n-140 58 15 1\11 LLD Not Applicable All LLD Sr-89 3 5 All LLD Not Applicable 1\11 LLD Sr-90 3 2 II II II II II II H-3 8 330 2500 (4/4) Station Discharge 2500 (4/4) All LLD 300 *-8400 300 -8400 lla-La-140 34 15 AlJ u.n Not -App lien bl c All 1.1.D Cs-134 34 15 " II II II " II Cs-137 34 15 " II II II II II Zr-Nb-95 34 10 II II 'II II II II Co-58 34 15 " " II II II II Mn-54 34 15 " II II II II II Zn-65 34 ! 15 " " II II II II .. Fe-59 34 30 II " II II II II Mn-54 30 130 II II II II " II Fe-59 30 260 II II " II " II Number of Nonroutine Reported Measurements 0 0 0 0 0 0 0 0 0 0 0 0 0 0 bMean and range based upon detectable

  • measurements bnly, Fraction of detectable measurements at specified locations is indicated in parentheses. (f) I
  • Medium or Pathway Sampled (Unit of Measurement)

Clams (cont'd) Oysters (pCi/kg).

Fish (pCi/kg) TABLE III (continued)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL S~Y Name of Facility Surry Power Plant Docket. No

  • __ 5_0_-_2_8_0

__ 5_0_-_2_8_1

___ _ Location of Facility~~S~u~r~r~y~*~V~i_r~g~i~n~ia;;;....~..,...~~~-

Reporting Period 01 January through 31 December 1978 (County, State) Type and Lower Limit Total Number of All Indicator Locations Location with Highest Annual*Mean Control Locations of Analyses Detection

-Mean (f)b *Name Mean (f)D Mean (f)h Performed (LLD) Range Distance & Direction Range Range Co-58 30 130 All LLD Not Appiicable All LLD Co-60 30 130 II II II II II II 'Zn-65 30 260 II II II II " II Cs-134 30 130 II II II II II II Cs-137 30 130 All LLD Not Applicable All LLD Sr-90 3 10 10 (1/3) Station Dischiirr,e 10 (1/3) Analysis not 10 10. Required Sr-89 3 10 All LLD Not Applicable Analysis not Required Mn-54 16 130 II II, II II All LLD Fe-59 16 260 II II II II II II Co-58 16

  • 130 II II II II II II Co-60 16 130 II II " II II II Zn-65 16 260 II II II II II II Cs-134 16 130 II II II II II II Cs-137 16 130 All LLD Not Applicable All LLD Cs-137 4 130 190 (1/4) Surry Station 190 (1/4) Not Required 190 Vicinity 190 Mn-54 4 130 All LLD Not Applicable Not Required Fe-59 4 260 II II II II II " Co-58 4 130 II II II II " II Co-60 4 130 II II II II II II Number of Nonroutine Reported Measurements 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
  • bMean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses. (f)

..... 0

  • Medium or Pathway Sampled (Unit of Measurement)

Fish (cont'd) Crnbs (pCi/kg) Silt (pCl/kg) Soil (pCi/kg) Fowl (pCi/kg) TABLE II! (continued)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL SUMMhRY Docket No

  • ___ 5_0_-_2_8_0

__ 5_0_-_2_8_1

__ N11mc of F'ncility Surry Power Plant Location of Facility Surry, Virginia (County, State) ReportJng Period 01 January through 31 December 1978 Type and Lower Limit -Total Number of All Indicator Locations Location with Hiehest Annual Mean Control Locations of Analyses Detection*

Mean (f)b Name Mean (f)0 Mean (f)b Performed (LLD) Ranl!e Distance & Direction Ran2e Ranee Zn-65 4 260 All LLD Not Applicable Not Required Cs-134 4 130 " " " II II II Mn-54 3 130 II II II II II II *Fe-59 3 260 II II II II* " II Co-58 3 130 II II II " 11-* " Co-60 3 130 II II " II II II Zn-65 3 260 II " II II " " Cs-134 3 130 " II II II " II Cs-137 3 130 All LLD Not Applicable Not Required Cs-134 12 150 620 (1/10) Station Discharge 620 (1/10) All LLD 620 620 Cs-137 12 150 910 (8/10) Station Disc*harge 2000 (1/2) 400 (2/2) 300 -2000 2000 400 Co-58 12 150 All LLD Not Applicabl~

Co-60 12 150 700 (3/10) Station Discharge 1900 (1/2) All LLD 300 -1400 1400 Mn-54 12 150 All LLD Not Applicable Zn-65 12 260 AP LLD Not Applicable Cs-134 12 150 All LLD Not Applicable All LLD Cs-137 12 150 1600 (9/12) Ft. Eustis 1750 (2/2) Not Applicable 300 -2300 1700 -1800 Cs-134 2 80 All LDD Not Applicable Not Applicable Cs-137 2 80 " II . II II II II Number of Nonroutine Reported Measurements 0 0 () 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ' bMean and range based upon detectable_measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses, (f)

  • Medium or Pathway Sampled (Unit of Measurement)

Food Crops (pCi/kg) \fo.l l Water (pC:1/1) Surface Water (pCi/1} TAB~E III (continued)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Docket No ._5-"'Q_ .... ;:..;..28=0_...;;..5~0-~;;;;:.28"'"1=------

  • Name of Facility Surry Power Plant Location of Facility Surry, Virginia (County, State) Reporting Period 01 January through 31 December 1978 *Type and Lower Limit
  • Total Number *of All Indicator Locations Location with Hi2hest Annual Mean Control Locations of Analyses Detection Mean (f)b Name Mean (f)15 Mean (f)b Performed (LLD) Range Distance & Direction Ran2e Range Cs-134 6 80 All LLD Not Applicable' Not Applicable Cs-137 6 80 II II II II II II Sr..;89 "6 10 All LLD Not Applicable Not Applicable Sr-90 6 10 150 (1/6) Slade 150 (1/3} Not Applicable 150 150 . Gross n 8 l 3.5 (2/6) Hog Is. Reserve 5 (1/2) 2 . (1/2) 1 -5 l. 9 Mi. 5 2 C:rOHH (\ 8 1 ,, . 2 (5/6) llog Ts. (lcscrvc 5.5(2/2) J.5(2/2) 2 -5 3 -8 3 -4 Tritium 8 330 300 (1/1) Surry Station JOO (1/1) 500 (1/2) 300 500 Gross a 8 l 2.8 (2/4) Williamsburg 2.5(2/2) 3 (2.4) 2 -3 Reserve 2 -3 3 Gross fl 8 1 3 (3/4) Williamsburg 2.5(2/2) 4.5(4/4) 2 -3 2 -9 Tritium 8 500 600 (2/4) Williamsburg 600 (2/4) 800 (2/4) 600 Chippokes Creek 600 700 -900 Number of Nonroutine Reported Measurements 0 0 0 0 0 0 0 0 0 0 bMcan and range based upon detectable measurements only, Fraction of detectable measurements at specified locations is indicated in parentheses. (f) l
  • Sl:r-!ARY Environmental monitoring results showed that the radiation dose to a member of the general population did not exceed Technical Specifications of 1% of the 10 CFR 20 limit during 1978. Radionuclides released to the air and water from Surry Station may tribute to the radiation background through both external and internal ex-posure. The most significant environmental dose pathways are direct dose from the gaseous effluent and thyroid dose due to ingestion of milk. The area contains only a very small milk shed.which limits general population dose potential from this source and since James River water is not used for drinking, dose potential from this source is *also minimal .
  • A nuclear explosive was detonated in the atmosphere in the People's*

Republic of China in mid-March of 1978. Radioactive debris (fallout) from this event was detected throughout the continental United States in the later part of March chiefly as I-131 in milk samples and elevated concentrations of beta and gamma emitters in air. particulate filters collected during the lowing several months. Effects on other media were generally minimal or masked by the usual ambient levels encountered in those media. A second nuclear device was exploded in mid-December at the Lop Nor test site. Fallout from this event was apparently too diffused to be detected in routine environmental monitoring progr*a!!ls.

Table III summarizes the range and average concentrations for ments at the indicator and control locations, and the location with the ~st annual mean. Complete information is given in the Sample Data Tables. (Appendix I) Specific findings for various environmental media are discussed below: 12

  • Air Particulate Samples Air particulate samples collected in late March showed the arrival of fallout associated with the nuclear test conducted by the People's Republic of China. All sampling locations showed increased gross beta concentration, with elevated levels persisting until late July. The average concentration for the year for all indicator stations was 0.11 pCi/m 3* and for the control location was 0.13 pCi/m 3* The single highes*t concentration, 0.66+/-.09 pCi/m 3 , was noted at Newport News on 04/11/78, and is attributable to fallout and not operation of nuclear power plants. The presence of significant and variable amounts of radionuclides due to fallout in this and previous years' samples does not permit meaningful trend analysis or comparison of average concentrations in the samples. Data for analyses of individual filters are given on pages 2-1 through 2-3 of Appendix I. Gamma spectrometry of quarterly composites of air particulate filters indicated that concentrations of Cs-134 and Cs-137 were below 0.01 pCi/m 3 throughout the year. Small amounts of Ce-144 and occasionally Ru-106 were detected in first and second quarter composites from all locations.

These nuclides were found to be present in similar collections throughout the continental U. S. and are attributed to fallout from the Spring Chinese nuclear test. By the third quarter of the year, concentrations of all gamma emitters had fallen below LLD's for the most part. None of the radioactivity detected is attributable to operation of Surry Station, since effects of the station, if any, are masked by the more abundant fallout. Analytical data are given on page 2-4 of Appendix I. 13

  • i \ * *
  • Environmental Dosimetry Measurements of environmental dose rates were made at twenty-three locations plus a control (shielded) location on a quarterly basis using thermoluminescent dosimeters (TLD's). Data are summarized below and in tables on pages 6-1 of Appendix I. ENVIRONMENTAL DOSIMETRY BY THERMOLill1INESCENT DOSIMETRY Average mR/week Location 1st Q 2nd Q 3rd g 4th Q Year Control -00 0.5+/-0.1 0.8+/-0.1 0. 7+/-0.1 0.7+/-0.2 0.7 Surry Station -01 13.4+/-2. 8 19.4+/-1. 9 15.9+/-1.6 21. 0+/-2. 0 17.4 Guard Booth -02 1. 3+/-0. 2 1. 6+/-0. 2 1. 5+/-0. 2 1. 6+/-0. 2 1.5 Surry East -03 1.1+/-0. 2 1.4+/-0 .1 1. 2+/-0.1 1.2+/-0.1 1.2 Surry North -04 0.9+/-0.2 1.2+/-0.1 0.9+/-0.1 1. 2+/-0. 2
  • 1.1 Hog Island Reserve -05 0.7+/-0.1 1.1+/-0.1 0.9+/-0.1 1.0+/-0.1 0.9 Surry West -06 0.6+/-0.1 1. 0+/-0. 2 0.8+/-0.1 0.9+/-0.1 0.8 Station Discharge

-07 0.6+/-0.1 o. 8+/-0 .1 0.6+/-0.1 0.5+/-0.1 0.6 Station Intake -08 0.7+/-0.1 o. 8+/-0.1 0.6+/-0.1 0. 7+/-0.1 0.7 Surry South -09 0.9+/-0.1 1.1+/-0.1 0.9+/-0.1 1.1+/-0.1 1.0 Bacons Castle -10 0.7+/-0.1 0.9+/-0.1 0.8+/-0.1 0.9+/-0.1 0.8 Alliance -11 1.0+/-0.1 0.9+/-0.1 0.7+/-0.1 0.8+/-0.1 0.9 Scotland Wharf -12 0.7+/-0.1 1.0+/-0.1 0.9+/-0.1 0.9+/-0.1 0.9 Jamestown

-13 0.8+/-0.1 0.9+/-0.1 0.8+/-0.1 0.9+/-0.2 0.9 Colonial Parkway -14 0.8+/-0.2 0.9+/-0.1 o. 8+/-0.1 0.9+/-0.1 0.9 Kings Mill -15 0.6+/-0.2 0.9+/-0.1 0.8+/-0.1 o. 9+/-0.1 0.8 Budweiser

-16 1. 0+/-0. 3 1.1+/-0.1 1. 0+/-0.1 1. 0+/-0.1 1.0 Dow -17 1. 3+/-0. 3 1. 2+/-0. 2 1.0+/-0.1 1.1+/-0.1 1.2 Lee Hall :...13 1.4+/-0. 2 1. 2+/-0.1 1. 2+/-0.1 1.4+/-0. 3 1.3 Fort Eustis -19 1.1:!:0. 2 1.0+/-0.1 0.9+/-0.1 1.1+/-0.1 1.0 Newport News -20 1. 2+/-0. 3 1.1+/-0.1 1.0+/-0.1 1.1+/-0.1 1.1 Smithfield(Subst.)

-21 1. 2+/-0. 3

  • 1.2+/-0.1 1.1+/-0.1 1. 2:!:0.1 1.2 Smithfield(l0&258)

-22 1.1+/-0.2 1.1+/-0. 2 0.9+/-0.1 0.9+/-0.2 1.0 Rt 10 and 676 -23 0.9+/-0.2 0. 8+/-0.1 0.8+/-0.1 0.8+/-0.1 0.8 As observed in previous years, the Surry Station location displays clearly elevated dose rates throughout the year . .. 14

  • Other on-site locations appear to be only very slightly above nearby locations and the badges located near the station intake and discharges consistently give some of the lowest readings observed.

The major fraction of the dose at the Surry Station location is undoubtedly due to operation of the station. The doses at other on-site locations may be partially due to the station, but only by a few tenths of a millirem per week at most. Doses due to the plant at locations away from the site, if they exist, are masked by doses from the usual natural environmental sources such as uranium, thorium and their ters, and possibly worldwide fallout . . Precipitation Samples Precipitation samples collected at the Surry Station and at Newport News. The samples are collected and analyzed on a monthly basis and as quarterly composties

  • for gross beta deposition and tritium concentrations.

Data which are summarized in Table III and on page 2-5 of Appendix I. Some samples collected at the Surry Station displayed gross beta deposition slightly higher than the Newport News location especially during the first half of the year. Gross beta measurements, the only measurements other than tritium required on these samples are not capable of indicating whether the differences are due to station operations or not. Some if not most of the activity during the first half of the year is due to worldwide fallout from both the well-known "Spring Peak" which is due to injection of long term radioactive debris from the stratosphere into the troposphere during early part of the year, and the Chinese nuclear test previously referred to. Tritium concentrations in precipitation were comparable at both tions throughout the year, and were generally in the range to be expected from measurements of this nuclide in this medium. 15

  • ' *, The cause of the somewhat elevated concentrations in the February sample is unknown to us, but the increase was observed at both locations suggesting that it is due to large scale meteorological processes and not releases from Surry Station. Milk Samples Radionuclides attributable to worldwide fallout are found in milk samples throughout the country. The most prevalent nuclides are Cs-137 and Sr-90, which were detected in the usual low and variable concentrations to be expected in most of the milk samples collected during the year. sio~ally, I-131 is detected in milk samples collected for a few weeks after intrusion of debris for an atmospheric nuclear explosion.

Such was the case with samples from Judkins, Gwaltney and Smith farms during March, shortly after the April nuclear detonation in the People'~ Republic of.China (see also air particulates).

All other milk samples collected during the year were below the de'tection limit (O. 5 pCi/1) for I-131. Strontium-89.

and Ba-La-140 were below the detection limits in all samples collected during the year. Radioactivity attributable to operation of Surry Station was not tected in any milk samples collected during the year. What activity was detected, is due to worldwide fallout and effects of the station, if any, were masked by the more abundant debris from that source. Comparisons of average concentrations for all nuclides assayed and other statistical information are given in Table III and data for analyses on each sample are given on pages 3-1 and 3-2 of Appendix I. Well Water Samples Samples of water were collected from each of four wells once during the Spring and once in the Fall.* 16 Gross alpha and gross beta activity were detected in most of the samples at the usual low levels encountered in environmental media. There was no statistically significant difference in *concentration:s, which were lar to those measured previously, between indicator and background tions and the activity is attributable to naturally occurring nuclides.

Tritium was detected above minimum detection limit of 330 pCi/1 in only one sample (Jamestown, 04/11/78, 530+/-110 pCi/1). This concentration is within the range to be expected in environmental samples and is not due to operation of the Surry Plant. The Fall sample from the Jamestown location was below MDL. Analytical data are given on page 5-1 (Appendix I) and summarized in Table III. Surface Water Samples Surface water samples were collected in the Spring and Fall from each of four locations.

Gross alpha and gross beta concentrations were all at the low concentrations usually expected to be found in environmental face water, with no significant differences between indicator and back-. ground stations or concentrations measured during 1977. Tritium at typical environmental levels was detected in Spring samples, but was below the minimum detection levels in Fall samples. The tritium in the spring samples is attributable to either normal environmental level fluctuations or fallout from recent atmospheric nuclear explosions and not operation at nuclear power stations.

Average concentrations for indicator and background stations are given in Table III, and analytical data for all samples are given on page 5-1 of Appendix I. 17

James River Water Samples Samples of water from the James River are collected bi-monthly from five locations including the station inlet and dishcharge and are analyzed for gamma emitters.

Semi-annual composites of the collections from the Chickahominy and Newport News locations are also analyzed for tritium. Quarterly samples are collected from the discharge.

These samples are split with a State agency and are analyzed for tritium, Sr-89 and Sr-90 in addition to gamma emitters.

Analytical data are presented on pages 4~1 through 4-3 of Appendix I and are summarized in Table III of this report. Gamma emitters were below the detection requirements of this program in all samples collected as were Sr-89 and Sr-90 in those samples requiring analyses ~or these latter nuclides.

Tritium was detected in all of the Station Discharge (State Split.) samples. The April and October samples were in the range frequently tered in environmental surface water. The January and July samples displayed concentrations somewhat higher than usually expected in the environment.

It is possible that these measurements represent releases from the Station. Tritium in the semi-annual composites from Chickahominy and Newport News was below the detection limit of 300 pCi/1 for both halves of the year. Silt Samples Silt Samples are collected semi-annually from six locations and lyzed for gamma emitters.

18

  • Silt is one of the few environmental media in which radioactive effluents from nuclear power stations are usually detected.

Most of the samples lected contained measurable concentrations of Cs-137, several contained Co-60 above the MDL's, and the Fall sample from the Station Discharge tained Cs-134. The Spring sample from the same location was anomalous in that no radioactivity was detected in a sample which is expected to be one of the highest areas. This probably represents a sampling problem rather than an actual "absence" of activity in the area. The levels of activity measured are generally comparable with those encountered in previous years. Precise comparison cannot be made because of the variability of tions at a given location and the relatively infrequent collections.

Data are summarized in Table III and detailed in Appendix I, page 4-8. Clam Samples Clam samples are collected bi-monthly from five locations near the station including the Station Discharge and are analyzed for gamma emitters.

Samples from this location are frequently designated "State Split Samples" and such samples are analyzed for Sr-89 and Sr-90 as well as gamma emitters.

Gamma emitters were below the LLD's of the program in* all samples collected during the year. Analysis of State Split clam samples for radiostrontium revealed the presence of only _Sr-90 at levels attributable to worldwide out in one sample (May). Analytical data are presented on page 4-5 of Appendix I and summarized in Table III. Oyster Samples* Samples of oysters are collected from Deep Water Shoal, Point of Shoal, and Newport News on a bi-monthly basis and analyzed for gamma emitters . 19

  • Some of the collections from Newport News are designated State Split samples. Data presented on page 4-6 of Appendix I show that concentrations of gamma emitters were below the LLD's of the program throughout the year. Fish Samples Fish are collected from the vicinity of the Station twice a year and analyzed for gamma emitters by gamma spectroscopy.

A sample of catfish collected in February contained

1. 9+/-1. 6 pCi/kg (wet we*ight) Cs-137. This concentration of Cs-137 is not considered to be especially unusual in bottom feeders. This and other gamma emitters were below the LLD's for the program in other samples of this and other species collected during the year. Data are presented on page 4-7 of Appendix I. Crab Samples Samples of crabs from the vicinity of Surry Station are collected in July, August and September.

Results of analyses on each of the collections as given on page 4-7 of Appendix I indicate that gamma emitters were below the LLD's for the program in all samples. Soil Samples Soil samples are collected annually from six locations and analyzed by gamma spectrometry for gamma emitters.

The only nuclide detected at trations greater than the LLD's for the program was Cs-137. Because the ples collected during the scheduled collection yielded unexpected trations of Cs-137, a second series of samples .were obtained and analyzed.

The concentrations of Cs-137 have been quite var~able throughout the years as is illustrated in the table below. This is probably due to the well ognized difficulty of obtaining truly representative samples of soil. There are no c~ear trends and the origin of the cesium is unclear . 20

  • Long and short term worldwide fallout are probably the major factors and contributions to the total by the station can not be ruled out. If, however, the major fraction were due to the station, significant amounts of Cs-134 and Co-60 might be expected in the samples, but this was not the case. tailed analytical data for the current year's samples are found on page 5-2 of Appendix I. Cs-137 Concentrations in Soil Samples 10 2 pCi/kg* 1975 1976 1977 1978(Aug) 1978 (Sept) Surry Station 35 1 17 <2 4 Ft. Eustis 18 10 17 18 Dow 10 2 2 <2 3 Bacon's Castle 8 24 2 23 9 Alliance 2 3 2 <2 3 Colonial Parkway
  • 15 12 22 7 *Data rounded to nearest whole unit, statistical errors omitted. Crop Samples Samples of food crops (corn, peanuts) are collected from two farms in the area annually and analyzed for gamma emitters, Sr-89 and Sr-90. No activity was detected _in any of the samples at the LLD' s applicable to this program. Data may be found on page 5-2 of Appendix I. Fowl Samples A Canadian Goose from the Hog Island Reserve was collected in }1arch and a'h American Egret was obtained on Hog Island Point in September.

The fowl were analyzed by spectrometry for gamma emi-tters, specifically Cs-134 and Cs-137. Concentrations of these nuclides were below the LLD of 80 pCi/kg for both ples. Data are given on page 5-2 of Appendix I . 21

  • ANALYTICAL PROCEDURES Samples received at the laboratory are analyzed for the various active components by standard radiochemical methods. These methods are equal to, and in most cases identical with, those of the U. S. DOE (1) or those of h (2) t e Federal -E. P.A. . Brief descriptions of analytical procedures are available in the atory Procedures Manual available at Surry Station and in the radioanalytical contractor's laboratory.

Air Particulate Filters Gross Beta -Exposed air particulate filters are counted in low ground Geiger or proportional flow beta counters using anti-coincidence background suppression.

Filters are counted long enough to ensure that the required sensitivity (LLD) will be met. Gamma Isotopic -quarterly composites of air particulate filters are counted in high resolution (GeLi) gamma spectrometers for periods of time long enough to ensure that the required program sensitivity (LLD) is met. (See also intro. to data tables, Appendix I). Water Samples (including surface, well, James River waters and precipitation).

Gross Beta -a measured aliquot of sample is digested, "wet-ashed", evaporated, transferred to a tared 47mm stainless steel planchet, dried and weighed. The planchetted sample is counted long enough in a low background beta counter to ensure that -the LLD of the program will *be met. (1) HASL Procedures Manual, edited by John H. Harley, Health and Safety Laboratory, U. S. Atomic Energy Commission, 1972 edition, revised annually.

(2) National Environmental Research Center, Environmental Handbook of Radiochemical Analytical

Methods.

Program Office of Research and Dev~lopment, Las Vegas, Nevada Protection Agency; Element lHA 325. 89114. 22

  • Gamma Isotopic -a measured aliquot of the sample is evaporated to a small controlled volume and counted in a standard geometry in a high resolution (Geli) gamma spectrometer long enoungh to ensur.e meeting the sensitivity requirements of the program. See also the Introduction to Data Tables. Strontium-89 and Strontium-90

-carrier strontium is added to a measured aliquot of sample. The strontium is then separated

.. and purified by either ion exchange chromatography (EPA method) or straight wet chemistry (HASL method). The chemical yield for strontium is determined by atomic tion spectrometry or grav_imetric methods. After a suitable period (usually 14 days) to allow for ingrowth of Y-90 the sample is counted in a low background beta counter (equilibrim or total Sr count). The strontium is next put_ into solution, carrier yttrium added, and the strontium and yttrium fractions separated.

The yttrium is counted and from the Y~90 (Sr-90 daughter) count, the Sr-90 concentration can be.determined.

The difference between the total strontium concentration as determined by the equilibrium

_count and the Sr-90 concentration as determined from the Y-90 count is the Sr-89 concentration.

Equations are available to permit calculation of Sr-89 and Sr-90 by counting the purified Sr fraction at two points during ingrowth of the Sr-90 daughter Y-90. While either method is acceptable, we find the former method to provide more consistent results. Tritium -tritium as tritiated water is analyzed by liquid scintillation counting after distillation.

If high sensitivity is not required (ie. LLD ~soo pCi/1) the sample is distilled, mixed with the appropriate counting phosphors*

and counted with no further treatment.

If higher sensitivity is r~quired (ie. <~500 pCi/1) the sample is isotopically enriched in tritium concentration prior to liquid scintillation counting.

23

  • Isotopic enrichment is done by the classical method of Ostlund which involves alkaline electrolysis of a purified aliquot of sample under controlled conditions of temperature and electrode current density. Milk Samples I-131 -measured amounts of carrier iodide are added to a known volume of milk and the iodine extracted on anion exchange resin. The iodine is recovered and uurified by classical iodine chemistry methods which are similar to those given in former Regulatory Guide 4.3. The yield or recovery of iodine is measured gravimetrically and the precipitated sample is mounted and counted in a low level beta detector for a long enough period to ensure that the required LLD is met. Gamma Isotopic -a measured aliquot of sample is evaporated and oven dried to a standard volume and counted in a fixed geometry in a high resolution (GeLi) gamma spectrometer for a long enough period to ensure that the required LLD's are reached (see also Introduction to data Tables). Sr-89 and Sr-90 -Stable strontium carrier is added to an aliquot of the sample which is then dried and ashed at high temperature

(>700°c).

The ash is dissolved and the solution treated from this point on in the same manner as are water samples (Q.y.). Organic Samples (including Clams, Oysters, Fish, Crabs, Food Crops arid Fowl). Gamma Isotopic Analysis -a measured aliquot of sample is oven dried or ashed as appropriate, placed in a controlled geometry and counted in a high resolution (GeLi) gamma spectrometer for a period long enough to ensure that the LLD's of the program will be met (see also intro. to Data Tables) . 24 _ __J In the case of samples such as fish and fowl, the edible flesh is rated from bones and entrails prior to drying. Sr-89 and Sr-90 -stable strontium carrier is added to a weighed aliquot of the sample and the sample is ashed at high te~perature

()700°c)~

The ashed sample is then dissolved and processed in the same manner as are water or milk samples. Soil and Silt Samples Gamma Isotopic Analysis -the sample is oven dried to facilitate handling and then sieved to remove pieces of stone and/or other large pieces of material.

An appropriate sized, weighed aliquot of the sample is then transferred into a standard geometry container and counted for a period long enough to ensure that the LLD of the program will be met. (See also Introduction to Data Tables). Thermoluminescent Dosimeters (TLD) Environmental radiation doses are measured using badges comprizing five, chips sealed in plastic protective holders having a density of 50 mg/cm 2* The TLD chips are l/8 11 x 1/8" x 1/32 LiF (thallium activated) known commercially as Harshaw-100.

The chips are all selected to provide uniform response to in 5% of the mean for the batch. Prior *to installation, the chips are annealed by a standard cycle of 60 minutes at 400°c and immediate cooling to ambient temperature by placing the tray containing the annealed chips on an aluminum block 12" x 12" x 1". After exposure the chips are read on an Eberline Instrument Corporation Model TLR-5 reader. The system employs a preheat cycle which removes low temperature peaks and integrates and digitizes only the light output in a selected temperature range. 25

  • The dose is calculated from the average light output for the five chips and the statistical uncertainty is the standard deviation of the five readings.

Control badges are used to detect any unusual exposure to the badge which might occur during shipment

  • 26
  • TABLE A Detection Capabilities for Environmental Sample Analysis Lower Limit of O~te6tion (LLD) Airborne Particulate Water or Gas Fish Milk Food Products Sediment Anaysis (pCi/1) (pCi/m3) (pCi/kg,wet) ( pCi/1) (pCi/kg. wet) (pCi/kg, dry) gross beta 2 1 X 10;..2 3H .330 54Mn 15 130 59Fe 30 260 58,60co 15 130 65zn 30 260 95 zr-Nb 10 131 I l 7 X 10-2 l 25 134,137Cs 15 1 X 10-2 130 15 80 150 *. 140 aa-La 15 15
  • TABLE B Lower Limits of Detection (LLD) for Analyses Not Required in Regulatory Guide 4.8 Media Analysis LLD Water Grosso. 1 pCi/1 Sr-89 5 pCi/1 Sr-90 2 pCi/1 Precipitation Gross 13 5 pCi/1 Tritium 330 pCi/1 Air Particulates Gross a 0.01 pCi/rn3 Fowl Gamrna Isotopic (1) Food Crops Sr-89 20 pCi/kg Sr-90 10 pCi/kg Oysters Gamma Isotopic (2) Clam Gamma Isotopic (2) Sr-89 20 pCi/kg Sr-90 10 pCi/kg Crab Gamma Isotopic (2) Milk Sr-89 5 pCi/1 Sr-90 2 pCi/1 Soil Gamma Isotopic (3) (1) Same as RG. 4.8 for Food Crops. * (2) *Same as RG. 4.8 for Fish. (3) Same as RG. 4.8 for Sediment .

APPENDIX I Data Tables 1.0 Introduction 1-1 Error Terms Sensitivity

-LLD's Garmna Isotopic Analysis Exponents

2.0 Airborne

Radioactivity 2-0 Air Particulates Precipitation 3.0 Milk* 3-0 4.0 Samples from the Aquatic Environment 4-0 James River Water Clams Oysters Fish Crab Silt 5.0 Samples from the Terrestrial Environment 5-0 Well Water 6.1 TLD Data 6-0

  • 1-0
  • 1.0 Introduction_

to the Data Tables In this section are given itens of information helpful in standing the presentation of the data in the Tables. 1.

  • Error Term!=l Data preceded by the "less than" symbol (<) are at the 3cr (99% confidence) level. The error terms on other data are 2cr (95% confidence).
2. Sensitivities

-LLD's Analytical sensitivities or LLD's (Lower Limits of Detection) are those given in the most recent NRC Branch Position on Regulatory Guide 4.8. (Table A) For analyses not required in RG. 4.8, Federal EPA, former requirements for similar programs, or other appropriate guides are used (Table B). The LLD's are calculated as per RG. 4.8 at the 3cr level. The Guide specifically states that t_he LLD's are~ priori not a posteriori; limits for a particular measurement.

When, however, RG. 4.-S-Or other LLD's have not been achieved, a footnote giving a brief explanation has been inserted.

3. Gamma Isotopic Analyses All samples to be analyzed for gamma emitters are assayed using high resolution gamma spectrometers. (Geli). The spectra are computer scanned using recognized programs.

The energy search programs specifically examine the peak areas of gamma energies for the expected effluents from nuclear power plants. Only the nuclides required by NRC Reg. Guide 4.8 are reported in the Data Tables. If other gamma emitters associated with either power station operation or worldwide fallout.from nucleaf weapons tests are detected, this information is either given in cussions of the data or entered as footnotes to the data tables. Naturally occurring gamma emitters are frequently detected in mental samples. Analyses of these nuclides is not required by the NRC and they are neither quantified when detected nor reported in the Data Tables. 4. Exponents Exponents necessary to prevent data tables from being cumbersome are handled in the conventional manner of including them in column headings . 1-1 i 2.0 Airborne Radioactivity

2.1 Particulate

Filters 2.1.1 2.1.2 Gross Alpha and Gross Beta Concentrations Gamma Isotopic Analyses 2.2 Precipitation

2.2.1 Gross

Beta and Tritium Analyses of Monthly Collections

2.2.2 Gross

Beta and Tritium Analyses of Quarterly Composites Page 2-1 2-4 2-5 2-5 2-0 Collection Date 01/10/78 01/24/78 02/07/78 02/22/78 03/07/78 03/21/78 04/11/78 04/18/78 05/02/78 05/21/78 05/30/78 06/13/78 . 06/27/78 07 /11/78 07 /25/78 08/04/78 08/22/78 09/05/78 09/19/78 10/03/78 10/17/78 10/31/78 11/14/78 11/29/78 12/13/78 12/17 /78 1 I 12/19/78 I. 12/21/78, I VEPCO GROSS ALPHA AND BETA CONCENTRATIONS IN AIR PARTICULATES (ai-Weekly Collections)

___ SS -S ll.E.9'. Stat 1 __

  • o_n __ _ LiIR Hog Islnnd Reserve Volume _ 10-2 pCi.-'--/t_n3

__ Volume 10-2 pCi/m3 :_ __ _ (m 3) Gross a _Gros_s~B-

__iE!.:l_

Gross et _Gros~ 330 < 1 8 +/- 1 295 < 1 2 +/- 1 330 C 1 2 +/- 1 290 < 1 3 +/- 1 335 < 1 10 +/- 1 295 < 1 8 +/- 1 355 < 1 5 +/- 1 315 < 1 9 +/- 1 325 < 1 8 +/- 1 270 < 1 10 +/- 1 330 < 1 13 +/- 1 270 < 1 11 +/- 1 495 < 1 61 +/- 9 455 < 1 48 +/- 7 160 < 1 31 +/- 3 140 < 1 25 +/- 3 330 < 1 21 +/- 3 160 < 1 6 +/-

  • 1 307 < 1 10 +/- 1 166 < 1 15 +/- 2 342 < 1 6 +/- 1 319-< 1 8 +/- 1 330 < 1 18 +/- 3 295 < 1 10 +/- 2 . 315 < 1 16 +/- 2 300 < 1 17 +/- 2 310 < 1 14 +/- 1 295 < l 14 +/- 1 312 < 1 13 +/- 1 293 ( 1 13 +/- 1 345 <. 1 5 +/- 1 317 ( 1 3 +/- 1 303 < 1 7 +/- 1 275 < 1 5 +/- 1 201 < 1 9 +/- 1 278 < 1 10 +/- 2 330 < 1 < 1 285 <
  • 1 7 +/- 1 308 < 1 6 +/- 1 266 < 1 6 +/- 1 24 < 1 9 +/- 3 280 < 1 5 +/- l 180 < 1 4 +/- 1 280 < l* 3 +/- 1 150 < 1 9 +/- 2 280 < 1 12 +/- 2 178 < 1 8 +/- 1 299 < 1 5 +/- 1 215 < 1 4 +/- 1 . 245 < 1 1 +/- 1 125 < 1 6 +/- 2 100 < 1 4 +/- 2 49 < 1 3 +/- 1 40 < 1 2 +/- 2 43 < 1 7 +/- 1 39 < 1 5 +/- 1 (a) Not available

-out of order. N I I-' Volume (m3) 280 285 300 330 285 285 445 150 285 277 293 270 285 300 296 306 267 301 290 287 310 290 305 331 290 110 43 45 BC -Bacon's C~stlc 10-2 pCi/1;-3==== Grons a Gross B < 1 9 +/- 1 < 1 5 +/- 1 < 1 3 +/- 1 < 1 3 +/-'1 < 1 9 +/- 1 < 1 11 +/- 1 < 1 59 +/- 9 (' 1 28 +/- 3 < 1 17 +/- 3 < 1 9 +/- 1 <l 11+/-2 < 1 18 +/- 3 < 1 21 +/- 2 < 1 15 +/- 2 < 1 13 +/- 1 < 1 7 +/- 1 < 1 6 +/- 1 < l 6 +/- 1 < 1 < 1 < 1 1 +/- 1 < 1 1 +/- 1 < 1 8 +/- 1 < 1 4 +/- l < 1 4 +/- 1 < 1 4 +/- l < 1 1 +/- 1 < *l < 1 < *l < 1

  • VEPCO GROSS ALPHA AND BETA CONCENTRATIONS IN AIR PARTICULATES (Bi-Weekly Collections)

ALL -Allinnct'.

CP -Colonial Pnrkway Dow -j 0-2 pCi/m 3 Collection Volume 10-2 pCi/m 3 Volume 10-2 ECi/m 3 Volume Date (m3) Gross Cl. Gross s (m3) Gross a Gross s (m:l) Gt'oss a Gross B 01/10/78 310 < 1 6 +/- 1 30 <1 < 3 300 < 1 7 +/- 1 01/24/78 . 315 < 1 4 +/- 1 (a) 305 < 1 7 +/- 1 02/07/78 305 < 1 8 +/- 1 (a) 325 < 1 9 +/- 1 02/22/78 380 < 1 9 +/- 1 195 (1 7 +/- 1 360 < 1 9 +/- 1 03/07/78 295 < 1 7 +/- 1 190 <1 6 +/- 1 300 < 1 9 +/- 1 03/21/78 315 < 1 12 +/- 1 185 <l 11 +/- 1 315 < 1 11 +/- 1 04/11/78 505 < 1 60 +/- 9 320 . <l 48 +/- 7 470 < 1 59 +/- 8 04/18/78 165 < 1 11 +/- 2 90 <1 26 +/- 3 170 < 1 26 +/- 3 05/02/78 340 < 1 17 +/- 3 .90 <1 37 +/- 6 305 < 1 22 +/- 3 05/21/78 461 < 1 7 +/- 1 199 <l 7 +/- 1 279 < 1 14 +/- 1 05/30/78 216 < 1 11 +/- 2 217 <l 10 +/- 2 324 < 1 7 +/- 1 06/13/78 340 < 1 14 +/- 2 200 <1 12 +/- 2 300 < 1 15 +/- 2 06/27 /78 300 < 1 18 +/- 2 200 <l 21 +/- 2 300 < 1 13 +/- 1 07 /11/78 320 < 1 14 +/- 1 220 <l 14 +/- 2 300 < 1 6 +/- l 07/25/78 313 < L 11 +/- 1 218 <l 1.3 +/- 1 302 < 1 13 :! 1 08/04/78 329 (" 1 5 +/- 1 235 <l 5 +/- 1 313 < 1 5 +/- 1 08/22/78 297 < 1 5 +/- 1 205 <l 7 +/- 1 279 < 1 6 +/- 1 09/05/78 302 < 1 6 +/- 1 222 <l 10 +/- 2' 282 < 1 10 +/- 2 09/19/78 315 < 1 7 +/- 1 255 <1 8 +/- 2 290 < 1 7 +/- 1 10/03/78 302 < 1 5 +/- 1 215 (1 8 +/- 2. 276 < 1 5 +/- 1 10/17/78 280 < 1 5 +/- 1 (a) 290 < 1 3 +/- 1 10/31/78 285 < 1 6 +/- 1. 565 <1 6 +/- 1 295 < 1 7 +/- 1 11/14/78 290 < 1 16 +/- 2 290 <1 29 +/- 4 290 < 1 13 +/- 2 11/29/78 324 < 1 5 +/- 1 595 (1 4 +/- 1 301 < 1 6 +/- 1 12/13/78 300 < 1 3 +/- 1 565 <1 5 +/- 1 265 < 1 4 +/- 1 12/17/78 115 < 1 4 +/- 2 120 <1 5 +/- 2 105 < 1 5 +/- 2 12/19/78 45 < 1 3 +/- 1 38 <l 2 +/- 2 43 < 1 3 +/- 2 12/21/78 47 < 1 6 +/- 1 44 <1 5 +/- 1 53 < 1 4 +/- 1 (a) Not available

-out of order. N I N N I w Collection Date 01/10/78 01/24/78 02/07/78 02/22/78 03/07 /78 03/21/78 04/11/78 04/18/78 05/02/78 05/21/78 05/30/78 06/13/78 06/27/78 07/11/78 07/25/78 08/04/78 08/22/78 09/05/78 09/19/78 10/03/78 10/17/78 10/31/78 11/14/78 11/29/78 12/13/78 12/17/78 12/19/78 12/21/78

  • VEPCO GROSS A1PHA AND BETA CONCENTRATIONS IN AIR PARlICULATES (B:L.-Weekly Collections)

Volume ~m3L 320 225 65 145 325 335 475 160 300 412 322 300 300 2BO 299 220 279 298 295 286 290 295 160 234 134 90 36 36 FE -Fort Eustis 10-2 oCi/m'3 Gross Cl. Gro~ <l 2 +/- 1 <l 8 +/- 1 <1 8 +/- 2 <l 6 +/- 1 <l 9 +/- 1 <1 9 +/- 1 <1 50 +/- 7 <l

  • 29 +/- 3 <l 28 +/- 4 <1 9 +/- 1 <1 10 +/- 2 <l 11 +/- 2 <l 1 +/- 1 <l 4 .+/- 1 <l 3 +/- 1 <I 5 +/- 1 <l 6 +/- 1 <l 8 +/- 1 <I 8 +/- 2 <l 4 +/- 1 <1 5 +/- 1 <1 6 +/- 1 <l 9 +/- 2 <l 4 +/- 1 <l 2 +/- 1 <1 5 +/- 2 1+/-1 < 1. <l 3 +/- 1 Volume (m3) 280 325 285 255 275 295 455 150 305 283 329 300 310 305 .. 302 324 281 303 305 291 300 290 270 313 275 105 45 40 NN -Newport News J0-2 pCi/m 3 Gross ct Gross B < 1 10 +/- 1 < 1 8 +/- 1 < 1 11 +/- 1 <"l 10 +/- 1 < 1 10 +/- 1 < 1 12 +/- 1 < 1 66 +/- 9 < 1 31 +/- 3 < 1 21 +/- 3 < 1 12 +/- 1 < 1 9 +/- 2 < 1 17 +/- 3 < 1 16 +/- 2 < l 15 +/- 2 < 1 14 +/- 1 < 1 8 +/- 1 < 1 7 +/- 1 <l 10+/-2 (. 1 7 +/- 1 < 1 4 +/- 1 < 1 5 +/- 1 < 1 6 +/- 1 < 1 13 +/- 2 < 1 7 +/- 1 < 1 1 +/- 1 < 1 9 +/- 2 < 1 3 +/- 1 1 +/- 1 5 +/- 1
  • VEPCO -Surry GAMMA EMITTERS IN AIR PARTICULATE FILTER COMPOSITE (Quarterly Composites of Bi-we*ekly Collections)

Stations in composite:

ss, HIR Collection 10-2 ECi/m 3 Period Ce-144 Ru-106 Cs-137 1st Quarter 2+/-1 1'+/-1 <l 2nd Quarter 7+/-2 <2* <l 3rd Quarter 2+/-1 <l <l 4th Quarter <l <I <l Stations in composite:

BC, ALL, CP, DOW, FE Collection 10-2 pCi/m 3 Period Ce-144 Ru-106 Cs-137 1st Quarter 4+/-1 (1 <1 2nd Quarter 5+/-1 2+/-1 <l 3rd Quarter <1 <l <1 4th Quarter <I <l <l Stations in composite:

NN Collection 10-2 pCi/m 3 Period Ce-144 Ru-106 Cs-137 1st Quarter 5+/-1 <l <l 2nd Quarter 16+/-4 <4* <l 3rd Quarter <3* <2* <l 4th Quarter <I <l <l Cs-134 <1 <l <1 <1 Cs-134 <l <1 <l <I Cs-134 <1 <1 <1 <l *Higher LLD due to larger Compton and/or smaller sample composite volume. 2-4 Collection Period January february . March _.i\pril ~y .June .July August September October November December Collection Period 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter VEPCO -Surry _ . ___ GROS~_ )m1'A_ DEPOSITION AND TRITIUM CONCENTRATIONS IN PRECfP!TAtIO~CSAMPLES--

(:Monthly Collections)

Gross 13 pCi/1 21+/-6 60+/-8 25+/-6 57+/-6 24+/-2 11+/-2 10+/-2 8+/-2 14+/-2 12+/-2 11+/-2 3+/-2 Surry Station Gross S nCi/m 2 2.5+/-0.6 3.4+/-0.5 2.5+/-0.6 2.6+/-0.3 3.3+/-0.3 1.. 0+/-0. 2 o. 3+/-0. 1 0.5+/-0.1 0.2+/-0.1 0.2+/-0.1 0.2+/-0.1 0.2+/-0.1 Tritium pCi/1 360+/-100 2200+/-700 550+/-100 <500 600+/-100 <"500 500+/-300 500+/-300 400+/-300 560+/-340 1700+/-400 (500 Gross 13 pCi/1 31+/-6 50+/-7 15+/-6 43+/-4 15+/-2 7+/-2 11+/-2 11+/-2 3+/-2 4+/-1 7+/-2 8+/-2 Newport News Gross 13 nCi/m 2 2.2+/-0.4 1. 8+/-0. 3 0.9+/-0.3 2.4+/-0.2 1. 9+/-0. 2 0.4+/-0.1 0.3+/-0.1 o. 2+/-0.1 0.1+/-0.1 0.1+/-0,1 0.1+/-0.1 0.1+/-0.1 GROSS BETA DEPOSITION AND TRITIUM CONCENTRATIONS IN PRECIPITATION SA}IPLES (Quarterly

  • composites of Honthly*collections)

Surry Station Newport News Gross S Tritium Gross S Tritium nCi/m 2 pCi/1 nCi/m 2 oCi/1

  • 700+/-100
  • 700+/-100 0.38+/-0.04 810+/-130 0.11+/-0.02 800+/-130 0.13+/-0.03 400+/-300 0.05+/-0.02 800+/-300 0.03+/-0.01 690+/-100 0.04+/-0.02 1100+/-200 *Sample lost in transit. Tritium pCi/1 360+/-100 1700+/-700 (500 <5oo 600+/-100 <500 500+/-300 <soo 800+/-300 400+/-330 95.0+/-500 410+/-310 .. 2-5

3.0 Radioactivity

in Milk Page Bacon's Castle (EPPS) 3-1 Bacon's Castle (Judkins) 3-1 Lee Hall (Ross) 3-1 Smithfield (Gwaltney) 3-2 Colonial ParkW?Y (Smith) 3-2

  • 3-0 VEPCO -Surry RADIOACTIVITY IN MILK SAMPLES (Monthly Collections)

Bacon's Castle {~PPS)_ -State Split Samples Collection pCi/1 as of collection date g/1 Date I-131 Sr-89 Sr-90 Cs-137 Ba-La-140 Stable Ca 01/10/78 <O.S <S 3+/-1 <15 <15 1. 7 02/01/78 <O. 5. <S 3+/-1 <15 <15 1. 6 03/20/78 <O.S <S 3+/-1 <15 <15 1.6 04/18/78 <O.S <S 5+/-1 <15 <15 1.8 05/16/78 <0.5 <S 2+/-1 <15 <15 1.6 06/27/78 <O.S <S 6+/-1 <IS <15 *2.2 07/25/78 <O.S <S 4+/-1 <15 <15 1.8 08/22/78 <O.S <S 6+/-1 <15 <15 1. 6 09/05/78 <O.S <5 4+/-2 <15 <15 1.2 10/03/78 <0.5 <S . 17+/-2 <IS <15 1.6 11/28/78 <0.5 . <S 4+/-2 <15 <15 1.2 12/12/78 <O.S <S 4+/-2 <15 <15 1.1 Bacon's Castle (Judkins) pCi/1 as of collection date g/1 I-131 Sr-89 Sr-90 Cs-137 Ba-La-140 Stable Ca :. -----01/24/78 <O.S <S 5+/-2 . <15 <IS 2.2 02/22/78 <O.S <S 7+/-1 18+/-13 <15 1.8 03/07/78 <O.S <S 15+/-2 <15 <15 1. 7 04/ 11/78 i.1+/-0. 3 <S 7+/-3 <15 <15 0.9 05/02/78 <0.5 <S 11+/-2 23+/-6 <is 2.1 06/20/78 S a m p 1 e 1 0 s t d u r i n g s h i p m e n t 07/25/78 <0.5 <S 4+/-3 <15 <15 1. 9 08/09/78.

<0.5 <S 8+/-2 <15 <IS 1.5 09/19/78 <0.5 <S <2. <1s* <IS 1. 2 10/17 /78 . <O.S . <S 16+/-2 <15 <15 1.3 11/14/78 <0.5 <S 6+/-1 <15 <15 1.0 12il2/78 <0.5 <S 4+/-3 <15 <IS l.l+ Lee H~J.c.!____(Ross)

-State Split Samples ECi/1 as of collection date g/1 I-131 Sr-89 Sr-90 Cs-137 Ba-La-140 Stable Ca 01/10/78 <0.5 <S 2+/-2 16+/-14 <IS 1.8 02/01/78 <0.5 <S 1+/-1 <15 <15 1. 7 03/20/78 <0.5 <S 3+/-1 20+/-11 <15 1.6 04/18/78 <0.5 <S 9+/-4 <IS <15 1.4 05/16/78 <0.5 <S 2+/-1 <15 <IS 1. 7 06/27/78 <O.S <S 3+/-1 <15 <15 1. 6 07/25/78 <0.5 <S 3+/-2 <15 <15 1.1 08/22/78 <0.5 <S 7+/-3 <15 *<15 1. 2 09/05/78 <0.5 <S 5+/-2 <15 <15 1.2 10/03/78 <0.5 <S 5+/-2 <15 <15 1.4 11/27 /78 <0.5 <5 <2* <15 <15 1.1 12/12/78 <0.5 <S 2+/-2 <15 <15 1.3 *Low chemical yield. 3-1 VEPCO -Surry RADIOACTIV:fTY -IN Mltk SAMPLES---(Monthly Collections) "Smithfield (Gwaltney)

Collection ECi/1 as of collection date g/1 Date I-131 Sr-89 Sr-90 Cs-137 Ba-La-140 Stable Ca 02/07/78 <0.5 <s 3+/-1 <15 <15 1. 9 02/23/7S (0.5 (5 6+/-1 21+/-13 (15 1. 7 03/07 /78 (0.5 <s 5+/-2 GS <15 1. 7 04/18/78 1. 2+/-0. 3 (5 2_+/-1 (15 (15 1.6 05/30/78 <0.5 (5 6+/-2 (15 <15 1. 7 06/27/78 (0.5 (5 4+/-1 (15 (15 1.1 07/25/78 <0.5 <s 7+/-2 (15 <15 1.5 08/20/78 S a m p 1 e 1 0 s t i n s h i p m e n t 09/19/78 (0.5 (5 10+/-2 (15 (15 1.3 ')..0/17/78

<0.5 <s 4+/-1 <15 <15 1..4 11/29/78 (0.5 (5 4+/-4 <15 <15 12/21/78 <0.5 . (5 7+/-2 (15 <15 1.1 Colonial Parkway (Smith) 2Ci/l as of collection date g/1 I-131 Sr-89 Sr-90 Cs-137 Ba-La-140 Stable Ca 01/24/78 (0.5 (5 3+/-1 <15 (15 1. 7 02/07/78 . (0.5 (5 4+/-1

  • 16+/-12 <15 1.6 03/07 /78 (0.5. (5 2+/-1 (15 <15 1.8 04/11/78 0.6+/-0.2 (5 3+/-1 (15 <15 1.1 05/02/78 (0.5 (5 7+/-2 13~ 5 <15 1. 7 06/27/78 (0.5 (5 6+/-1 <15 <15 1.2 07/25/78 <0.5 (5 7+/-2 <15 <15 1.3 08/09/78 (0.5 (5 4+/-1 <15 (15 1.3 09/19/78 <0.5 (5 3+/-2 <15 (15 1.3 10/17/78 <0.5 (5 3+/-2 <15 <15 1.0 11/14/78 <0.5 (5 3+/-1 (15 (15 1.5 12/19/78 <0.5 (5 <2 (15 <15 0.9 3-2

4.0 Samples

from the Aquatic Environment

4.1 James

River Water 4.1.1 4.1.2 4.1.3 Gamma Isotopic Analyses State Split Sample Analyses Tritium Analysis 4.2 Clam Samples 4.2.1 4.2.2 Gamma Isotopic Analyses State Split Samples and Other Samples from Station Discharge

4.3 Ovster

Samples 4.2.1 Gamma Isotopic Analy~es 4.4 Fish Samples 4.4.1 Gamma Isotopic Analyses 4.5 Crab Samples 4.5.1 Gamma Isotopic Analysis 4.6 Sediment 4.6.1 Gamma Isotopic Analysis Page 4-1 4-3 4-3 4-4 4-5 4-6 4-7 4-7 4-8 4-0.

I I ..... Month Collected January March May July September November January March May July September November*

Ba-La-140

<15 (15 <15 <15 (15 <15 (15 <15 <15 <15 (15 (15 VEPCO -Surry GAMMA EMITTERS IN JAMES RIVER WATER SAMPLES (Bimonthly Collections)

Ci/1 Cs-134 Cs-137 Zr-Nb-95 Co-58 Mn-54 Zn-65 Co-60 Fe-59 STATION INTAKE (15 (15 (10 <15 (15 (30 <15 <30 <15 <15 <IO <15 <15 (30 <15 <30 <15 (15 <10 <15 <15 <30 <15 <30 (15 <15 (10 <15 (15 (30 <15 <30 (15 (15 <10 <15 <15 (30 <15 <30 <15 <15 <10 (15 <15 <30 <15 <30 STATION DISCHARGE

<15 <15 (10 (15 <15 <30 <15 <30 (15 <15 <IO <15 <15 <30 <15 <30 <15 <15 <10 <15 <15 (30 (15 <30 <15 (15 <10 (15 <15 <30 <15 <30 <15 <15 <10 <15 (15 <30 <15 <30 <15 <15 <10 <15 <15 (30 <15 <30

  • *
  • VEPCO -Surry GAMMA EMITTERS IN JAMES RIVER WATER SAMPLES (Bimonthly Collections)

Month Ci/1 Collected Ba-La-140 Cs-134 Cs-137 Zr-Nb-95 Co..;.58 Mn-54 Zn-65 Co-60 Fe-59 CHICKAHOMINY January <15 <15 <15 <10 <15 <15 <30 <15 <30 March <15 <15 <15 <10 <15 <15 <30 <15 <30 May <15 <15 <15 <10 <15 <15 <30 <15 <30 July <15 <15 <15 <10* <15 <15 <30 <15 <30 September

<15 *<15 <15 <10 <15 <15 <30 <15 <30 November <15 <15 <15 <10 <15 <15 <30 <15 <30 HOG ISLAND POINT January <15 <15 <15 <10 <15 <15 <30 <15 <30 March <15 <15 <15 <10 <15 <15 <30 <15 <30 May <15 <15 <15 <10 <15 <15 <30 <15 <30 July <15 <15 <15 <10 <15 <15 <30 <15 <30 September

<15 <15 <15 <10 <15 <15 <30 <15 <30 November <15 <15 <15 <10 <15 <15 <30 <15 00 NEWPORT NEWS January <15 <15 . <15 <10 <15 <15 <30 <15 <30 March <15 <15 <15 <10 <15 <15 <30 <15 <30 May <15 <15. <15 <10 <15 <15 <30 <15 <30 July <15 <15 <15 <10* <15 <15 <30 <15 <30 September

<15 <15 <is <10 <15 <15 <30 <15 <30 November . <15 <IS <15 <IO <15 <IS <30 <15 <30 ' I N Collection Date: Nuclide Sr-89 Sr-90 Tritium Ba-La-140 Cs-134 Cs-137 Zr-Nb-95 Co-58 Mn-54 Zn-65 Co-60 Fe-59 VEPCO -Surry RADIOACTIVITY IN JAMES RIVER WATER SAMPLES FROM THE STATION DISCHARGE -STATE SPLIT SAHPLES-(Quarterly Collections) 01/24/78 04/11/78 07 /11/78 10/03/78 Ci/1 Not Required <5 <5 *<S this sample <2 <2 <2 8400+/-800 470+/-110 1000+/-300 300+/-300 <15 <15 .(15 <15 <15 <15 <15 (15 <IS <15 <15. <15 (10 <IO (10 <IO <15 <15 <15 <IS <15 <15 <15 <15 <30 <30 <30 <30 <15 <15 <15 <15 <30 <30 <30 <30 TRITIUM IN JAMES RIVER WATER SAMPLES (Semia~nual Composites of Bimonthly Samples) pCi/1 Sample Location Chickahominy Newport News 1st half 1978 <330 <330 2nd half 197 8 <330 <330 4-3

  • Sample Month Site Collected CHICKAHOMINY January March May July September November U.WNES CREEK January March May 'July September November JAMESTOWN January March
  • May July September November*

HOG ISLAND POINT January March May July September November VEPCO -Surry GAMMA EMITTERS IN CLAM SAMPLES (Bi-Monthly Collections) 102 :eCi/kg Wet Weight Mn-54 Fe-59 Co-58 Co-60 Zn-65 --<1.3 <2.6 <1.3 <1.3 <2.6 <1.3 <2.6 <1.3 <1.3 *<2.6 <1.3 <2.6 <1.3 <1.3 <2.6 <1.3 <2.6 <1.3 <1.3 <2.6 <1.3 <2.6 <1.3 <1.3 <2.6 <1.3 <2.6 <1.3 <i.3 <2.6 q_,3 <2.6 <1.3 <1.3 <2.6 <1.3 <2.6 * <1.3 <1.3 <2.6 <1.3 <2.6 <L3 (1.3 * <2. 6 <1.3 <2.6 <1.3 <1.3 <2.6 <1.3 <2.6 <1.3 <1.3 <2.6 <L3 <2.6 <1.3 <1.3 <2.6 <1.3 <2.6 <1.3 <1.3 <2.6 .. <1.3 <2.6 <1.3 <1.3 <2.6 <1.3 <2.6 <1.3 <1.3 <2.6 .<1.3 <2.6 <1.3 <1.3 <2.6 <1.3 <2.6 <1.3 <1.3 <2.6 <i.3 <2.6 <1.3 <L3 <2.6. . <1.3 <2,6 <1.3 <1.3 <2.6 <1.3 *<2.6 <1.3 <1.3 .<2.6 <L3 <2.6 <L3 <1.3 <2.6 <L3 <2.6 <1.3 <1.3 <2.6 <1.3 <2.6 (1.3 <1.3 <2.6 (1.3 <2~6 <1.3 <1.3 <2.6 Cs-134 Cs-137 <1.3 <1.3 <1.3 <1.3 <1.3 <1.3 <1.3 <1.3 <1.3 <1.3 <1.3 . <1.3 <1.3 <1.3 <1.3 <1.3 <1.3 (1.3 <1.3 <1.3 <L 3 (1.3 <1.3 <1.3 <1.3 <1.3 <1.3 <1.3 : <L 3 <1.3 <1.3 <L3 <L 3 <1.3 <l.;) <1;3 <1.3 (1.3 <L 3 <1.3 <1.3 <1.3 <1.3 (1.3 <1.3 ** <1.3 <1.3 <L3 4-4

  • Month Collected Mn-54 January* <1. 6* March (1.3 May <1.3 July <1.3 September**

<1.3 November <1.3 VEPCO -Surry GAMHA EMITTERS IN CLAM SAMPLES State Split.Samples from Station Discharge 10 2 ECi/kg Wet Fe-59 Co-58 Co-60 Zn-65 <3. 2~-: <1. 6* <2.0* (3. 2* <2.6 <1.3 * <L 3 <2.6 <2.6 <1.3 (1.3 <2.6 <2.6 <1.3 <1.3 <2.6 <2.6 <1.3 <L 3 <2.6 <2.6 <L 3 <1.3 <2.6 Cs-134 Cs-137 (2.0* (1. 9* <1.3 <1.3 <1.3 <1.3 <1.3 (1.3 (1.3 <1.3 <1.3 <L 3

  • This sample is not a State Split. Instrument problems prevented achieving usual sensitivity.

~':* Not a State Split Sample. Strontium-89 and Strontium-90 in Clams (State Split Samples from Collection Date March May July November Station Discharge) pCi/kg Wet Weight Sr-89

< 10 *< 10 <200 sample for Analysis.

10 +/- 10 < 10 <200(a) (a) Insufficient sample for more sensitive analysis . 4-5

  • *-* *.
  • Location Deep Water Shoal Point of Shoal Newport News Month Collected January March May July September November January March May July September November February March* May* July* VEPCO -Surry GAMMA EMITTERS IN OYSTER SAMPLES (Bi-:t-lonthly Collections) 10 2 ECi/kg Wet Weight Mn-54 Fe-59 Co-58 Co-60 Zn-65 <1.3 <2.6 <L 3 (1.3 <2.6 Sample lost in shipment <1.3 <2.6 <1.3 <1.3 <2.6 <1.3 <2.6 <1.3 <1.3 <2.6 <1.3 <2.6 (1.3 <1.3-<2.6 <1.3 <2.6 <L-3 <1.3 <2.6 <1.3 <2.6 <1.3 <1.3 <2.6 Sample lost in shipment <1.3 <2.6 <1.3 <1.3 <2.6 <1.3 <2.6 <1.3 (1.3 <2.6 <1.3 <2.6 . <1.3 <1.3 <2.6 <1.3 <2.6 <1.3 <1.3 <2.6 <1.3 (2.6 (1.3 <1.3 (2.6 <1.3 (2.6 <1.3 (1.3 (2.6 <1.3 (2.6 <1.3 (1.3 <2.6 <l._3 * <2.6 <1.3 <1.3 <2.6 September*

<1.3 <2.6 <1.3 <1.3 * <2.6 <2.6 November*

<1.3 <2.6 <1.3 <1.3

  • State Split Sample . Cs-134 Cs-137 <1.3 (1.3 <1.3 <1.3 <1.3 <1.3 <L3 <1.3 <1.3 <1.3 <1.3 <1.3 <1.3 <1.3 <L :3 <1.3 <1.3 <1.3 <1.3 (1.3 (1.3 <r~3 (1.3 <1.3 <1.3 <1.3 <1.3 <1.3 <1.3 <1.3 <1.3 <1.3. 4-6 Collection Sample Date TIEe February '78 Catfish February '78 Perch 08/24/78 Catfish 08/24/78 Catfish VEPCO -Surry GAl!-1MA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF SURRY STATION (Semi-Annual Collection) 10 2 ECi/kg Wet Weight Mn-54 Fe-59 Co-58 Co-60 Zn-65 (1.3 (2.6 (1.3 (1.3 (2.6 (2.2* <4.5* <2.2* (2.8* <4.5* <1.3 <2. 6 .* <t.3 <1.3 (2.6 (1.3 <2.6 (1.3 <1.3 <2.6 *Insufficient sample available for more sensitive analysis . Month Collected Mn-54 July (1.3 August <1.3 September

<1.3 . GAMMA EMITTERS IN CRAB SAMPLES COLLECTED IN THE. VICINITY OF SURRY STATION (July, August, September Collection) 102 pCi/kg Wet Weight Fe-59 Co-58 Co-60 Zn-65 Cs-134 <2.6 (1.3 (1.3 <2.6 <1.3 (2.6 <1.3 <L 3 <2.6 <1.3 <2.6 <1.3 (1.3 <2.6 <1.3 Cs-134 Cs-137 * (1.3 1. 9+/-1. 6 <2.5* <:Z.8* (1.3 <1.3 <1.3 <1.3 Cs-137 (1.3 <1.3 .. <1.3

  • Collection Period: Collection Site Chickahominy Station Discharge Hog Island Point Station Intake Point of Shoals -Newport News Collection Period: Chickahominy Station Discharge
  • Hog Island Point Station Intake Point of Shoals Newport News * ----------

VEPCO -Surry GAMMA EMITTERS IN SILT SAMPLES (Semiannual Collections)

April 10 2 pCi/kg Dry Weight Cs-134 Cs-137 Co-58 Co-60 <LS i0.0+/-4.0 <LS <LS <LS <L 5 <L 5 <LS <LS 5.0+/-0.2 <LS <LS <L 5 --8.0+/-0.2 <L 5 4.0+/-0.2 <LS 3.0+/-0.1 <LS <L 5 <LS 4.0+/-0.1 <L 5 <LS September

<L5 9.0+/-2.0 <LS <LS 6.2+/-LS 20.0+/-3.0 <LS 14.0+/-3.0 <LS <LS <LS <LS <L 5 8.0+/-2.0 <LS <L 5 <LS 10.0+/-2.0 <LS 3. O+/-L 0 <LS 4.0+/-LO <LS <LS Mn-54 <LS <LS <LS <LS <LS <L5 <LS <LS <LS <L 5 <LS <LS Zn-65 <2.6 <2.6 <2.6 <2.6 <2.6 <2.6 <2.6 <2.6 <2.6 <2.6 <2.6 (2.6 4-8

  • 5.0 Radioactivity in the Terrestrial Environment 5 *. 1 Well Water Samples 5.1.1 Gross Alpha, Gross Beta and Tritium Analysis 5.2 Surface Water Samples 5.2.1 Gross Alpha, Gross Beta and Tritium Analyses 5.3 Soil Samples 5.3.1 Gamma Isotopic Analyses 5.4 Fowl Samples 5.3.1 Gamma Isotopic Analyses 5.3 Food Crops Page 5-1 5-1 5-2 5-2 5-0
    • Surry Station Hog Island Res. Bacon's Castle Jamestown VEPCO -Surry RADIOACTIVITY IN WELL WATER SAMPLES (Semi-Annual Collections) 1st Half Coll. 04/11/78 2nd Half Coll. ECi/1 :eC:i/1 Gross a Gross 8 Tritium* Gross a Gross <l <l 300+/-100 <l 3+/-2 <2** 3+/-2 <300 5+/-2 8+/-2 2+/-1 2+/-2 <300 <2~1:* 5+/-2 <l 4+/-2 530+/-110 2+/-1 3+/-2
  • Tritium Analyzed by enrichment method. ** Dissolved solids too high for more sensitive analys*is.

1st RADIOACTIVITY IN SURFACE WATER SAMPLES (Semi-Annual Collections)

Half Coll. 04/11/78 2nd Half Coll. ECi/1 pCi/1 10/03/78 8 Tritium* <300 <300 <300 <300 10/03/78 Gross a. Gross 8 Tritium* Gross a Gross 13 Tritium* Chippokes Creek <l (2 600+/-300 3+/-1 4+/-2 (500 Williamsburg Reserve 2+/-1 3+/-1 600+/-300 3+/-1 2+/-1 (500 Newport News Reserve <1 4+/-1 900+/-300 3+/-1 2+/-2 <5oo* Smithfield

<l 4+/-1 700+/-300 2+/-1 9+/-2 (500

  • Tritium Analyzed by direct L. S. Counting.

5-1

  • -*
  • Location Surry Station Fort Eustis Dow Bacon's Castle Alliance Colonial Parkway Collection
  • Area Hog Island Reserve Hog Island Point Date Collected 10/10/78 10/10/78 10/10/78 10/10/78 11/08/78 11/13/78 VEPCO -SU:rry GAMMA EHITTERS IN SOIL SAMPLES (Annual Collection)

Samples Collected

  • os/11/78 Samples Collected 09/19/78 10 2 pCi/kg 10 2 pCi/kg Cs-134 Cs-137 Cs-134 Cs-137 <LS <LS <L5 <L5 <L5 <L5 <LS <1.5 17+/-8. <L5 (L5 <L5 23+/-6 <L5 <1.5. (L5 22+/-6 <L5 GAMMA EHITTE...~S IN FOWL (Semi-Annual Co-llections) 4+/-1 18+/-2 3+/-1 9+/-1 3+/-1 7+/-1 Month Collected Sa.:i.ple Type 10 2 pCi/kg Cs-134 Cs-137 March .
  • September Canada Goose (0.8 Araerican Egret, <b.8 RADIOACTIVITY IN FOOD CROPS (Annual Collection)

State Split Samples 10 2 pCi/kg, Farm Type Cs-134 Cs-137 Slade Corn <0.8 <0.8 Brock Corn <0.8 <0.8 Slade Peanuts <0.8 <0.8 Brock Peanuts <0.8 <0.8 Brock Soybeans <0.8 <0.8 Slade Soybeans <0.8 <0.8 <0.8 <0.8 Wet Weight Sr-89 <O.l <0.1 <O.l <0.1 <O.l <0.3 Sr-90 <0.1 <0.1 <O.l <O.l <O.l 0.15+/-0.03 5-2

  • ' )J ' 6.0 Gamma Radiation Background as Measured With Thermoluminescent Dosimeters Page 6.1 Environmental Badges 6-1 6.2 Area Badges 6-2
  • 6-0
  • VEPCO -Surry GAMMA RADIATION TOTAL mR/QTR, USING THERMOLUMINESCENT DOSIMETERS VEPCO-ENVIRONMENTAL TLD'S 1978 1st Quarter 2nd Quart_e_£ 3rd Quarter 4th guarter Date Installed; 01/10/78 04/11/78 07/11/78 10/04/78 Date Removed: 04/11/78 07/11/78 10/04/78 01/03/79 Location rmR Control -00 9+/- 2 14+/- 1 11+/- 1 11+/-3 Surry Station -01 242+/-50 329+/-33 268+/-27 340+/-30 Guard Booth -02 23+/- 3 27+/- 4 25+/- 3 25+/-3 Surry East -03 19+/- 3 23+/- 2 21+/- 2 19+/-2 Surry North -04 17+/- 3 20+/- 2 16+/- 1 19+/-3 Hog Island Reserve -05 13+/- 2 19+/- 2 16+/- 1 16+/-2 Surry West -06 11+/- 1 17+/- 3 13+/- 1 14+/-1 Station Discharge

-07 11+/- 2 13+/- 1 10+/- 1 9+/-2 Station Intake -08 12+/- 1 13+/- 1 10+/- 1 12+/-1 Surry South -09 16+/- 2 19+/- 1 16+/- 1 14+/-2 Bacons Castle -10 12+/- 2 16+/- 2 14+/- 1 14+/-1 Alliance -11 18+/- 2 15+/- 2 12+/- 1 12+/-2 Scotland Wharf -12 13+/- 1 17+/- 1 15+/- 1 14+/-2 Jamestown

-13 15+/- 2 16+/- 2 14+/- 1 15+/-3 Colonial Parkway -14 14+/- 3 16+/- 1 13+/- 1 14+/-1 Kings Mill -15 11+/- 3 15+/- 1 13+/- 1 14+/-1 Budweiser

-16 18+/- 5 18+/- 1 16+/- 1 17+/-2 Dow -17 24+/- 6 21+/- 3 16+/- 1 18+/-2 Lee Hall -18 25+/- 3 21+/- 1 20+/- 2 22+/-4 Fort Eustis -19 19+/- 2 17+/- 1 15+/- 1 18+/-2 Newport News -20 21+/- 5 19+/- 2 17+/- 1 17+/-2 Smithfield(Subst.)

-21 22+/- 4 21+/- 1 18+/- 1 20+/-2 Smithfield(l0&258)

-22 19+/- 2 18+/- 1 15+/- 1 14+/-3 Rt 10 and 676 -23 16+/- 4 14+/- 1 13+/- 1 13+/-1 ' 0-, I I-'

(J'\ I t...)

  • Date lnstalledi Date R.emoved:

Location Control -00 Training Center -01 Admin Bldg Entrance-02 Admin Bldg Recep -03 Admin Bldg Kitchen -04 Admin Bldg (Men) -05 Admin Bldg Conf -06 Cafeteria

-07 Maintenance Shop -08 Storeroom East End -09 Storeroom West End -10 Control Room East -11 Control Room West -12 Intrument Shop -13 Clean Change Room -14 Security Bldg. -15 East Fence -16 North Fence .:..17 West Fence -18 South Fence -19 Electrical Shop -20 *-* !'" VEPCO -Surry . GAMMA RADIATION TOTAL mR/QTR. USING THERMOLUMINESCENT DOSIMETERS VEPCO-AREA TLD'S 1978 lst*guarter 2nd Quarter 3rd Quarter 4th Quarter 01/ 10/78 04/11/78 07 /11/78 10/04/78 04/11/78 07 /11/78 . 10/04/78 01/03/79 !:mR 10+/-3 13+/-2 11+/-1 11+/-1 12+/-2 14+/-1 12+/-1 13+/-1 24+/-4 23+/-1 22+/-2 21+/-2 30+/-2 31+/-2 34+/-1 33+/-3 24+/-3 22+/-1 23+/-1 21+/-2 27+/-5 29+/-3 30+/-1 30+/-3 20+/-2 21+/-4 20+/-2 20+/-2

  • 28+/-3 30+/-4 )1+/-1 28+/-3 22+/-3 22+/-2 19+/-2 20+/-2 21+/-5 24+/-1 33+/-3 32+/-3 28+/-5 29+/-3 34+/-3 29+/-3 11:!2 13+/-1 13+/-1 13+/-1 10+/-3 10+/-1 10+/-1
  • 9+/-1 870+/-70 780+/-40 550+/-60 430+/-40 90+/-10 96+/-7 74+/-7 54+/-5 New Station beginning 3rd. Qtr. 90+/-10 70+/-9 II II 400+/-40 380+/-40 " II 120+/-10 160+/-20 II II 270+/-30 210+/-20 " II 15+/-2 16+/-2 New Station beginning 4th Qtr. 120+/-10 '.
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