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This system has been designed for simultaneous Alpha and Beta counting and has a sample capacity of fifty samples.l982, third quarter-Surface water samples (PVNCS Evaporation Pond and Reservoir) were included in the sampling regimen.Samples were analyzed for Iodine-131 weekly and composited monthly for Cross Alpha, Gross Beta, Strontium-89, Strontium"-90, Tritium and Camma Spectral analysis.Anarch, 1982-the Hoffman anC Alineso-Boers Dairies were deleted from the sampling progra'm due to scheduling and relocation problems.At the same time, two net dairies were introduced into the sampling program, the.Paul Skousen Dairy located approximately 24 miles east of the PYNCS and the Dan Paxton Dairy located in Chandler, Arizona, approximately 75 miles east of the PVNGS.1982-The collection of l..airy Feed,>wildlife (jack rabbit)and Poultry Products (eggs)was deleted from the sampling regimen.1982, fourth quarter-A TLC'adge comparison was made.This was accomplished by introducing a different type of dosimeter (CaSOp), into the field which was placed next to the LiF dosimeter in order to evaluate performance of each type of badge with respect to each other. | This system has been designed for simultaneous Alpha and Beta counting and has a sample capacity of fifty samples.l982, third quarter-Surface water samples (PVNCS Evaporation Pond and Reservoir) were included in the sampling regimen.Samples were analyzed for Iodine-131 weekly and composited monthly for Cross Alpha, Gross Beta, Strontium-89, Strontium"-90, Tritium and Camma Spectral analysis.Anarch, 1982-the Hoffman anC Alineso-Boers Dairies were deleted from the sampling progra'm due to scheduling and relocation problems.At the same time, two net dairies were introduced into the sampling program, the.Paul Skousen Dairy located approximately 24 miles east of the PYNCS and the Dan Paxton Dairy located in Chandler, Arizona, approximately 75 miles east of the PVNGS.1982-The collection of l..airy Feed,>wildlife (jack rabbit)and Poultry Products (eggs)was deleted from the sampling regimen.1982, fourth quarter-A TLC'adge comparison was made.This was accomplished by introducing a different type of dosimeter (CaSOp), into the field which was placed next to the LiF dosimeter in order to evaluate performance of each type of badge with respect to each other. | ||
1.1.19 December 31, 1981-Sampling for airborne radioiodine was suspended I until February l983, six months prior to the then estimated fuel load date.1.1.20 1.1.21 1.1.22 1.1.23 1.1.20 1.1.25 1.1.26 1981-changes in the method of rep'orting non-detectable activity levels in the annual report were made.All samples that have non-detectable activity levels are reported as less than the detection limit (i.e., less than 5 pCi/1)instead of the previously used method of reporting, (i.e., 0+5 pCi/I).In addition, Tritium activities in groundwater reflect a l000 pCi/I detection limit.1981, fourth quarter-Sampling for airborne particulate and airborne radioiodine began.3uly, 198l-The TLD (Thermoluminescent Dosimetry) dose measurement pr'ogram began.1981-CEP acquired a new computer-based Gamma Spectrometry System.It consists of a Tracor Northern Scientific (Alodel 0500)0096 channel pulse height analyzer coupled to three intrinsic detectors and one CeLi detector.The new system has greater sensitivity and gives more detailed information about the spectrum.3anuary, 1980-Due to a fire which totally destroyed Nancy's Yellow Canary, Drinking Water samples were collected from the Red Quail, a general store located directly behind what is now called"The Local".The Red Quail water comes from a well at the trailer park behind the store.September, l980-The Ped Quail had an extensive filtering system installed. | 1.1.19 December 31, 1981-Sampling for airborne radioiodine was suspended I until February l983, six months prior to the then estimated fuel load date.1.1.20 1.1.21 1.1.22 1.1.23 1.1.20 1.1.25 1.1.26 1981-changes in the method of rep'orting non-detectable activity levels in the annual report were made.All samples that have non-detectable activity levels are reported as less than the detection limit (i.e., less than 5 pCi/1)instead of the previously used method of reporting, (i.e., 0+5 pCi/I).In addition, Tritium activities in groundwater reflect a l000 pCi/I detection limit.1981, fourth quarter-Sampling for airborne particulate and airborne radioiodine began.3uly, 198l-The TLD (Thermoluminescent Dosimetry) dose measurement pr'ogram began.1981-CEP acquired a new computer-based Gamma Spectrometry System.It consists of a Tracor Northern Scientific (Alodel 0500)0096 channel pulse height analyzer coupled to three intrinsic detectors and one CeLi detector.The new system has greater sensitivity and gives more detailed information about the spectrum.3anuary, 1980-Due to a fire which totally destroyed Nancy's Yellow Canary, Drinking Water samples were collected from the Red Quail, a general store located directly behind what is now called"The Local".The Red Quail water comes from a well at the trailer park behind the store.September, l980-The Ped Quail had an extensive filtering system installed. | ||
This made samples from Red Quail non-representative of the groundwater found in the Palo Verde area.For the C'ctober 24, 1980 sampling, the second sample was taken at a faucet cn the pipe, in order to obtain an unfiltered sample.All remaining samples in l980 and 1981 were taken from this point (faucet on the pipe).September, 1979-The Al Lueck, 3r.Dairy moved to a new location approximately 25 miles east of PVNGS. | This made samples from Red Quail non-representative of the groundwater found in the Palo Verde area.For the C'ctober 24, 1980 sampling, the second sample was taken at a faucet cn the pipe, in order to obtain an unfiltered sample.All remaining samples in l980 and 1981 were taken from this point (faucet on the pipe).September, 1979-The Al Lueck, 3r.Dairy moved to a new location approximately 25 miles east of PVNGS. | ||
2.0 Descri tion of the Monitorin Pro ram ANPP has contracted with CEP to determine the ambient radiation levels in the environment around PVNCS during its operation. | |||
===2.0 Descri=== | |||
tion of the Monitorin Pro ram ANPP has contracted with CEP to determine the ambient radiation levels in the environment around PVNCS during its operation. | |||
ANPP personnel collect the samples and ship them to CEP.The types of environmental samples collected include: vegetation (produce and citrus fruits), groundwater, drinking water, surface water, fresh milk, airborne particulates, and radioiodine. | ANPP personnel collect the samples and ship them to CEP.The types of environmental samples collected include: vegetation (produce and citrus fruits), groundwater, drinking water, surface water, fresh milk, airborne particulates, and radioiodine. | ||
The locations of the monitoring sites are shown in Figure I.The monitoring sites and the respective sample types collected are described in Table I.Table II describes the sample collection frequency. | The locations of the monitoring sites are shown in Figure I.The monitoring sites and the respective sample types collected are described in Table I.Table II describes the sample collection frequency. | ||
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+=Quarterly 3.0 Anal tical Procedures The analytical procedures discussed in this report are those routinely used by CEP to analyze samples.3.1 Fresh Milk 3.1.1 Iodine-131 Two liters of milk containing standardized Iodine carrier are stirred with Amberlite IRA-000 anion exchange resin for one hour.The Iodine is stripped from the resin with sodium perchlorate (NaCIO>)and precipitated with silver nitrate (AgNO3).The precipitate is filtered on a tared glass fiber filter.The dried precipitate is weighed for percent recovery and counted for Iodine-131 in a thin window, gas flow, proportional counter (Beckman Low Beta II or BerthoJd LB770).These instruments have a forty-one percent efficiency and a forty-five percent, respectively using Iodine-131 precipitated as silver iodide (Agl).3.1.2 Strontium-89 The Strontium is precipitated with concentrated fuming nitric acid, redissolved in water, made basic with dilute ammonium hydroxide and precipitated as the oxalate.The dried oxalate precipitate is counted in a low background proportional counter (Qeckman Low Beta II or Berthold LB770)having sixty percent and forty-five percent Strontium-Yttrium-90 efficiencies, respectively. | +=Quarterly 3.0 Anal tical Procedures The analytical procedures discussed in this report are those routinely used by CEP to analyze samples.3.1 Fresh Milk 3.1.1 Iodine-131 Two liters of milk containing standardized Iodine carrier are stirred with Amberlite IRA-000 anion exchange resin for one hour.The Iodine is stripped from the resin with sodium perchlorate (NaCIO>)and precipitated with silver nitrate (AgNO3).The precipitate is filtered on a tared glass fiber filter.The dried precipitate is weighed for percent recovery and counted for Iodine-131 in a thin window, gas flow, proportional counter (Beckman Low Beta II or BerthoJd LB770).These instruments have a forty-one percent efficiency and a forty-five percent, respectively using Iodine-131 precipitated as silver iodide (Agl).3.1.2 Strontium-89 The Strontium is precipitated with concentrated fuming nitric acid, redissolved in water, made basic with dilute ammonium hydroxide and precipitated as the oxalate.The dried oxalate precipitate is counted in a low background proportional counter (Qeckman Low Beta II or Berthold LB770)having sixty percent and forty-five percent Strontium-Yttrium-90 efficiencies, respectively. | ||
The Strontium-39 activity is determined by subtracting the previously measured Strontium-90 activity and its corresponding Yttrium-90 ingrowth from the measured gross Strontium activity.3.1.3 Strontium-90 An aliquot of milk containing standardized Strontium and Yttrium carriers, is stirred with I.,owex SOY/XS cation exchange resin at a pH of six for thirty minutes: All ruclides are stripped from the resin with strong acid.After the ingrowth period has been established, the Yttrium-90 is extracted with five percent di-2-ethylhexyl phosphoric acid (D2EHPA)in toluene, back extracted into an aqueous phase, precipitated as the oxalate and counted in a low backgrou,.d internal gas flow proportional counter (Beckman Low Beta II or Berthold LB770)to determine the Strontium-90 content of the sample.These systems.have Strontium-Yttrium-90 efficiency of sixty percent and forty-five percent,'espectively. | The Strontium-39 activity is determined by subtracting the previously measured Strontium-90 activity and its corresponding Yttrium-90 ingrowth from the measured gross Strontium activity.3.1.3 Strontium-90 An aliquot of milk containing standardized Strontium and Yttrium carriers, is stirred with I.,owex SOY/XS cation exchange resin at a pH of six for thirty minutes: All ruclides are stripped from the resin with strong acid.After the ingrowth period has been established, the Yttrium-90 is extracted with five percent di-2-ethylhexyl phosphoric acid (D2EHPA)in toluene, back extracted into an aqueous phase, precipitated as the oxalate and counted in a low backgrou,.d internal gas flow proportional counter (Beckman Low Beta II or Berthold LB770)to determine the Strontium-90 content of the sample.These systems.have Strontium-Yttrium-90 efficiency of sixty percent and forty-five percent,'espectively. | ||
3.1.0 Gamma S ectrometr A suitable aliquot of sample is placed in a Marinelli beaker and counted with a multi-channel analyzer equipped with an intrinsic Cermanium detector which is coupled~to a 0096 channel, computer based, multi-channel analyzer (Aorthern Scientific TN0500).The resulting spectrum is analyzed by the computer, and specific nuclides, if present, identified and quantified. | |||
====3.1.0 Gamma==== | |||
S ectrometr A suitable aliquot of sample is placed in a Marinelli beaker and counted with a multi-channel analyzer equipped with an intrinsic Cermanium detector which is coupled~to a 0096 channel, computer based, multi-channel analyzer (Aorthern Scientific TN0500).The resulting spectrum is analyzed by the computer, and specific nuclides, if present, identified and quantified. | |||
3.2~Ve etation 3.2.l Gamma S ectrometr Refer to hlilk Subsection 3.1.0.3.2.2 Iodine-131 Required on leafy vegetation only.After appropriate preparation of the sample, analysis is performed as discussed in Subsection 3.l.'.3.3 Groundwater and Drinkin 9'ater 3.3.1 Cross Al ha and Beta P A 1.0-liter aliquot of water is evaporated to dryness and transferred to a weighed planchet.The Gross Alpha and C:ross Beta radioactivity is measured by counting the pianchet in an internal gas flow, sin;ult"neous proportional, low background counter (Beckman giide Beta ll or Oerthold LB770), or by counting the planchet in a low bacl'ground simultaneous counter (Tennelec L B5100).3.3.2 Gamma S ectrometr Refer to hlilk Subsection 3.1.0.3.3.3 Strontium-90 A 1.0 liter aliquot of the sample containing standardized stable Strontium carrier is evaporated to dryness and wet ashed with concentrated nitric acid (HNO3)and hydrogen peroxide (H202).The Yttrium-90 is extracted with five percent Di-2-ethylhexyl phosphoric acid (D2EHPA)in toluene after the ingrowth period has been established, back extracted into an aqueous phase, precipitated as the oxalate and counted with an integral gas flow proportional counter (Beckman Low Beta ll or Berthold LB770)having a Strontium, Yttrium-90 efficiencies of sixty percent and forty-five percent, respectively. | 3.2~Ve etation 3.2.l Gamma S ectrometr Refer to hlilk Subsection 3.1.0.3.2.2 Iodine-131 Required on leafy vegetation only.After appropriate preparation of the sample, analysis is performed as discussed in Subsection 3.l.'.3.3 Groundwater and Drinkin 9'ater 3.3.1 Cross Al ha and Beta P A 1.0-liter aliquot of water is evaporated to dryness and transferred to a weighed planchet.The Gross Alpha and C:ross Beta radioactivity is measured by counting the pianchet in an internal gas flow, sin;ult"neous proportional, low background counter (Beckman giide Beta ll or Oerthold LB770), or by counting the planchet in a low bacl'ground simultaneous counter (Tennelec L B5100).3.3.2 Gamma S ectrometr Refer to hlilk Subsection 3.1.0.3.3.3 Strontium-90 A 1.0 liter aliquot of the sample containing standardized stable Strontium carrier is evaporated to dryness and wet ashed with concentrated nitric acid (HNO3)and hydrogen peroxide (H202).The Yttrium-90 is extracted with five percent Di-2-ethylhexyl phosphoric acid (D2EHPA)in toluene after the ingrowth period has been established, back extracted into an aqueous phase, precipitated as the oxalate and counted with an integral gas flow proportional counter (Beckman Low Beta ll or Berthold LB770)having a Strontium, Yttrium-90 efficiencies of sixty percent and forty-five percent, respectively. | ||
The counting results are back calculated to give Strontium-90 activity.3.3 tt Tritium Three milliliters of the water sample are mixed with NEF-930 Aquasol cocktail which is manufactured by New England Nuclear Corporation. | The counting results are back calculated to give Strontium-90 activity.3.3 tt Tritium Three milliliters of the water sample are mixed with NEF-930 Aquasol cocktail which is manufactured by New England Nuclear Corporation. | ||
The mixture used is nineteen percent sample in a clear gel type aquasol.This gives a Tritium counting efficiency of approximately thirty percent.The counting system used is a Beckman LS-100 Liquid Scintillation Spectro-meter.Six Tritium standards, certified by NBS, are counted before each set of water samples to check the counting system's efficiency. | The mixture used is nineteen percent sample in a clear gel type aquasol.This gives a Tritium counting efficiency of approximately thirty percent.The counting system used is a Beckman LS-100 Liquid Scintillation Spectro-meter.Six Tritium standards, certified by NBS, are counted before each set of water samples to check the counting system's efficiency. | ||
A counting efficiency is derived from these standards which are equal in activity but vary in the amount of quenching. | A counting efficiency is derived from these standards which are equal in activity but vary in the amount of quenching. | ||
3.0 Surface Water 3.0.1 Iodine-131 One liter of water containing standardized Iodine carrier is acidiiied iyith nitric acid (HNO3), then extracted with carbon tetrachloride | |||
{CClq)and sodium nitrite (NaNQ2)to remove the Iodine.The Iodine is back extracted from the carbon tetrachloride (CCIq)using a 0.2%hydrazine soluticn, which supplies more purification and an aqueous media for precipitatioe Iodine is precipitated with silver nitrate (AgNQ3)and filtered on a tared glass fiber filter as silver iodide (Agl).The Cried precipitate is weighed for recovery and counted for Iodine-131 in a thin window, gas flow,.proportional counter (Beckman Low Beta II or Berthold LB770)having forty-one percent arc forty-five percent ef ficienies, respectively for iodine-131 precipitatec as silver iodide (Agl).3.0.2 Gross Al ha and Beta An aliquot of the monthly composite is taken and analyzed according to Ground and Drinking Y.'ater Subsection 3.0.1.3.0.3 Gamma S ectrometr An aliquot of the monthly composite is taken and analyzed according to hlilk Subsection 3.1.0.3A.O Strontium-89 An aliquot of the monthly composite is taken and analvzed according to Milk Subsection 3.1.2.3A.S Strontium-90 An aliquot of the monthly composite is taken and analyzeC according to Croundwater and Drinking Water Subsection 3.0.3.".3.tt.6 Tritium An aliquot of the monthly composite is taken and analyzed ac<"rcing to Ground and Drinking Water Subsection 3.0.0.3 5 Air Particulate 3.5.1 Gross Al ha and Beta The Sartorius filter (cellulose nitrate filter with a 3 micron pore size), is placed in a 50 mm stainless steel planchet and counted for Gross Alpha and Gross Beta radioactivity using a low background internal gas flow, simultaneous proportional counter (Beckman Wide Beta II), or by using a low background simultaneous counter (Tennelec LB5100).3.5.2 Gamma S ectrometr The air filters are sealed in small, plastic Klarinelli beakers and counted utilizing the method described in Milk Subsection 3.1.0..3.6 Airborne Radioiodine Two analytical methods for airborne radioiodine are used by CEP depending upon the length of time between the sample collection date and the date of sample receipt at CEP.The sensitivity of the Camma Spectrometry i'.lethod decreases significantly after an iodine-131 decay of greater than one half-life (3.00 days).Therefore, if more than one week has elapsed between sample collection and analysis of the sample the Alkaline Leach Vethod provides a greater sensitivity and is thus the analytical method of choice.3.6.1 Alkaline Leach Method Radioiodine is removed from activated charcoal along with a standardized iodine carrier using concentrated ammonium hydroxide (NH4+H)hydrogen peroxide (H2C'2).The charcoal is filtereC and the remaining solution is acidified with nitric acid (HYC'3)and extracted with carbon tetrachloride (CClq).A 0.2;~hydrazine solution supplies further purification and an aqueous media for precipitation. | ===3.0 Surface=== | ||
Water 3.0.1 Iodine-131 One liter of water containing standardized Iodine carrier is acidiiied iyith nitric acid (HNO3), then extracted with carbon tetrachloride | |||
{CClq)and sodium nitrite (NaNQ2)to remove the Iodine.The Iodine is back extracted from the carbon tetrachloride (CCIq)using a 0.2%hydrazine soluticn, which supplies more purification and an aqueous media for precipitatioe Iodine is precipitated with silver nitrate (AgNQ3)and filtered on a tared glass fiber filter as silver iodide (Agl).The Cried precipitate is weighed for recovery and counted for Iodine-131 in a thin window, gas flow,.proportional counter (Beckman Low Beta II or Berthold LB770)having forty-one percent arc forty-five percent ef ficienies, respectively for iodine-131 precipitatec as silver iodide (Agl).3.0.2 Gross Al ha and Beta An aliquot of the monthly composite is taken and analyzed according to Ground and Drinking Y.'ater Subsection 3.0.1.3.0.3 Gamma S ectrometr An aliquot of the monthly composite is taken and analyzed according to hlilk Subsection 3.1.0.3A.O Strontium-89 An aliquot of the monthly composite is taken and analvzed according to Milk Subsection 3.1.2.3A.S Strontium-90 An aliquot of the monthly composite is taken and analyzeC according to Croundwater and Drinking Water Subsection 3.0.3.".3.tt.6 Tritium An aliquot of the monthly composite is taken and analyzed ac<"rcing to Ground and Drinking Water Subsection 3.0.0.3 5 Air Particulate | |||
====3.5.1 Gross==== | |||
Al ha and Beta The Sartorius filter (cellulose nitrate filter with a 3 micron pore size), is placed in a 50 mm stainless steel planchet and counted for Gross Alpha and Gross Beta radioactivity using a low background internal gas flow, simultaneous proportional counter (Beckman Wide Beta II), or by using a low background simultaneous counter (Tennelec LB5100).3.5.2 Gamma S ectrometr The air filters are sealed in small, plastic Klarinelli beakers and counted utilizing the method described in Milk Subsection 3.1.0..3.6 Airborne Radioiodine Two analytical methods for airborne radioiodine are used by CEP depending upon the length of time between the sample collection date and the date of sample receipt at CEP.The sensitivity of the Camma Spectrometry i'.lethod decreases significantly after an iodine-131 decay of greater than one half-life (3.00 days).Therefore, if more than one week has elapsed between sample collection and analysis of the sample the Alkaline Leach Vethod provides a greater sensitivity and is thus the analytical method of choice.3.6.1 Alkaline Leach Method Radioiodine is removed from activated charcoal along with a standardized iodine carrier using concentrated ammonium hydroxide (NH4+H)hydrogen peroxide (H2C'2).The charcoal is filtereC and the remaining solution is acidified with nitric acid (HYC'3)and extracted with carbon tetrachloride (CClq).A 0.2;~hydrazine solution supplies further purification and an aqueous media for precipitation. | |||
Iodine is precipitated with silver nitrate and filtered on a tared glass fiber filter as silver iodide (Agl).The dried precipitate is weighed for recovery and counted for Iodine-131 in a thin window, gas flow, proportional counter (Beckman Low Beta ll or Berthold LB770)having forty-one percent and forty-five percent efficiencies, respectively for iodine-131 precipitated as silver iodide (Agl).3.6.2 Gamma S ectrometr Method The direct gamma counting method for iodine-131 consists of placing the charcoal canister directly on an intrinsic germanium detector and analyzing the resulting spectrum for iodine-131 using the computer, based Northern Scientific TN 0500 System.The system is calibrated using charcoal filters which have been uniformly loaded (in the first 5 mm)with standardized isotopes traceable to NGS and calibration verification is performed by analyzing a charcoal filter which has been uniformly loaded (in the first 5 mm)with standardized iodine-131 traceab le to NBS.Deposition of activity in the first 5 mm of the filters is done to simulate actual sample loading and both standards and samples are placed on the detector so that the load gradient is decreasing with distance from the detector.0.0 Sam le Pre aration Methods The following sample preparation methods are routinely used by C EP.O.l Ve etation Sam le Pre aration The plastic bags are opened and the sample weighed immediately to obtain the wet weight.3.After weighing, the sample is transferred to a crying pan and placed in an oven at 110 C.5.The dry sample is ground to a fine powder anC homogenized. | Iodine is precipitated with silver nitrate and filtered on a tared glass fiber filter as silver iodide (Agl).The dried precipitate is weighed for recovery and counted for Iodine-131 in a thin window, gas flow, proportional counter (Beckman Low Beta ll or Berthold LB770)having forty-one percent and forty-five percent efficiencies, respectively for iodine-131 precipitated as silver iodide (Agl).3.6.2 Gamma S ectrometr Method The direct gamma counting method for iodine-131 consists of placing the charcoal canister directly on an intrinsic germanium detector and analyzing the resulting spectrum for iodine-131 using the computer, based Northern Scientific TN 0500 System.The system is calibrated using charcoal filters which have been uniformly loaded (in the first 5 mm)with standardized isotopes traceable to NGS and calibration verification is performed by analyzing a charcoal filter which has been uniformly loaded (in the first 5 mm)with standardized iodine-131 traceab le to NBS.Deposition of activity in the first 5 mm of the filters is done to simulate actual sample loading and both standards and samples are placed on the detector so that the load gradient is decreasing with distance from the detector.0.0 Sam le Pre aration Methods The following sample preparation methods are routinely used by C EP.O.l Ve etation Sam le Pre aration The plastic bags are opened and the sample weighed immediately to obtain the wet weight.3.After weighing, the sample is transferred to a crying pan and placed in an oven at 110 C.5.The dry sample is ground to a fine powder anC homogenized. | ||
The sample is then dissolved or ashed, whichever is required for further isotopic analysis. | The sample is then dissolved or ashed, whichever is required for further isotopic analysis. | ||
0.2 Milk Iodine carrier (Potassium loCide), formalin and sodium bisulfate are added when the milk is collected to stabilize the iodine-1'31 during shipment of samples to CEP.The procedure for Fresh,'.lilk is then followed as described in Section 3.1, of this report.5.0 Nuclear Instrumentation 5.l Tracor Northern Computer Based Gamma S ectrometer The Gamma Spectrometer consists of a Tracor Northern Ti'>-0500 K!ultichannei Analyzer equipped with: a)DEC LSI-ll/23 lI,!icroprocessor; b)DEC'T-il Version IV Operating System;c)Free Standing Console consisting of a full ASCII keyboard;d)Comprehensive 5!CA Control Section, and e)Two Solid State Ce(Li)Detectors and Three Intrinsic Detectors having 2.8 KeV, 3.0 KeV, 2.07 KeV, 1.35 KeV and 1.85 KeV resoluti'ons and respective efficiencies of 16.1,~, 3.9",~, 22.6".-, 30.6%and 25.1%.The Computer Based Tracor Northern Gamma Spectrometry Systerr;is used for all gamma counting.The system uses the latest software to search and identify, as well as quantize the peaks of interest.5.2 Beckman Wide Beta II Low Back round Cas Pro ortional S stem The Beckman Wide.Beta II Two-inch Detector Counting System has an average of 2.5 cpm Beta backgrounC and O.l cpm Alpha background. | 0.2 Milk Iodine carrier (Potassium loCide), formalin and sodium bisulfate are added when the milk is collected to stabilize the iodine-1'31 during shipment of samples to CEP.The procedure for Fresh,'.lilk is then followed as described in Section 3.1, of this report.5.0 Nuclear Instrumentation 5.l Tracor Northern Computer Based Gamma S ectrometer The Gamma Spectrometer consists of a Tracor Northern Ti'>-0500 K!ultichannei Analyzer equipped with: a)DEC LSI-ll/23 lI,!icroprocessor; b)DEC'T-il Version IV Operating System;c)Free Standing Console consisting of a full ASCII keyboard;d)Comprehensive 5!CA Control Section, and e)Two Solid State Ce(Li)Detectors and Three Intrinsic Detectors having 2.8 KeV, 3.0 KeV, 2.07 KeV, 1.35 KeV and 1.85 KeV resoluti'ons and respective efficiencies of 16.1,~, 3.9",~, 22.6".-, 30.6%and 25.1%.The Computer Based Tracor Northern Gamma Spectrometry Systerr;is used for all gamma counting.The system uses the latest software to search and identify, as well as quantize the peaks of interest.5.2 Beckman Wide Beta II Low Back round Cas Pro ortional S stem The Beckman Wide.Beta II Two-inch Detector Counting System has an average of 2.5 cpm Beta backgrounC and O.l cpm Alpha background. | ||
The system can also be set up for one-inch detector.The system capacity is one hundred samples.The I detector has an efficiency of 60": for Strontium-90 and 00;5 for Plutonium-239. | The system can also be set up for one-inch detector.The system capacity is one hundred samples.The I detector has an efficiency of 60": for Strontium-90 and 00;5 for Plutonium-239. | ||
5.3 Beckman 0/ide Beta II Low Back round Cas Pro ortional S stem (Simultaneous) | |||
===5.3 Beckman=== | |||
0/ide Beta II Low Back round Cas Pro ortional S stem (Simultaneous) | |||
The Beckman Wide Beta II Two-inch Planchet Counting System has an average of 2.5 cpm Beta background and O.l cpm Alpha background. | The Beckman Wide Beta II Two-inch Planchet Counting System has an average of 2.5 cpm Beta background and O.l cpm Alpha background. | ||
The detector has a 60%efficiency for Strontium-90 and 00%for Plutonium-239. | The detector has a 60%efficiency for Strontium-90 and 00%for Plutonium-239. | ||
This system has been designed for simultaneous Alpha and Beta counting.The system sample capacity is one hundred samples.5A Beckman Low Beta II Low Back round Beta S stem The Beckman Low Beta II Cas Proportional One-inch Detector Counting System has an average of 1.5 cpm Beta background and O.l cpm Alpha background and detector efficiency of 6006 for Strontium-90 and 00%for Plutonium-239. | This system has been designed for simultaneous Alpha and Beta counting.The system sample capacity is one hundred samples.5A Beckman Low Beta II Low Back round Beta S stem The Beckman Low Beta II Cas Proportional One-inch Detector Counting System has an average of 1.5 cpm Beta background and O.l cpm Alpha background and detector efficiency of 6006 for Strontium-90 and 00%for Plutonium-239. | ||
The system capacity is one hundred samples.The system can also be set up for two-inch detector having 2.5 cpm Beta background and O.l cpm Alpha background. | The system capacity is one hundred samples.The system can also be set up for two-inch detector having 2.5 cpm Beta background and O.l cpm Alpha background. | ||
5.5 Beckman Low Beta 11 Low Back round Beta S stem The Beckman Low Beta II Cas Proportional Two-inch Detector Counting System has an average of 3.0 cpm Beta background and 0.2 cpm Alpha background and detector efficiency of 60.o for Strontium-90 and 00'.6 for Plutonium-239. | |||
===5.5 Beckman=== | |||
Low Beta 11 Low Back round Beta S stem The Beckman Low Beta II Cas Proportional Two-inch Detector Counting System has an average of 3.0 cpm Beta background and 0.2 cpm Alpha background and detector efficiency of 60.o for Strontium-90 and 00'.6 for Plutonium-239. | |||
The system capacity is one hundred samples.This system can also be set up for cne-inch detector having 1.5 cpm Beta background and 0.1 cpm Alpha background. | The system capacity is one hundred samples.This system can also be set up for cne-inch detector having 1.5 cpm Beta background and 0.1 cpm Alpha background. | ||
5.6 Beckman Li uid Scintillation Countin S stems Two Beckman LS-100 Liquid Scintillation Counters will be used for all Tritium determinations, as well as C-IO, P-32, S-35 and other Beta emitters.5.7 Low Back round Al ha Gas Flow S stems The Cross Alpha Counting Systems consist of two windowless gas flow detectors manufactured by Nuclear Xleasurements Corporation with an Alpha efficiency of 55.6 with a background of less than O.l cpm.5.8 Low Back round Scintillation Counter The Low Background Scintillation Counter consists of a Zinc Sulfide screen.The system has an average Alpha of 0.1 cpm.5.9 Tennelec LB5100 S stem The Tennelec L$5100 System has a Two-inch Planchet Counting System and has an average of 2 cpm Beta background and O.l cpm Alpha background. | |||
===5.6 Beckman=== | |||
Li uid Scintillation Countin S stems Two Beckman LS-100 Liquid Scintillation Counters will be used for all Tritium determinations, as well as C-IO, P-32, S-35 and other Beta emitters.5.7 Low Back round Al ha Gas Flow S stems The Cross Alpha Counting Systems consist of two windowless gas flow detectors manufactured by Nuclear Xleasurements Corporation with an Alpha efficiency of 55.6 with a background of less than O.l cpm.5.8 Low Back round Scintillation Counter The Low Background Scintillation Counter consists of a Zinc Sulfide screen.The system has an average Alpha of 0.1 cpm.5.9 Tennelec LB5100 S stem The Tennelec L$5100 System has a Two-inch Planchet Counting System and has an average of 2 cpm Beta background and O.l cpm Alpha background. | |||
This system has been designed for simultaneous Alpha and Beta counting.The sample capacity is fifty samples.5.10 Low Level Planchet Countin S stems (2)Each Berthold 10-Channel Low Level Planchet Counting System (Yodel LB700)is capable of simultaneously counting 10 planchets for Cross Alpha and Cross Beta activities alternately with Proportional Cas Flow l.etectors. | This system has been designed for simultaneous Alpha and Beta counting.The sample capacity is fifty samples.5.10 Low Level Planchet Countin S stems (2)Each Berthold 10-Channel Low Level Planchet Counting System (Yodel LB700)is capable of simultaneously counting 10 planchets for Cross Alpha and Cross Beta activities alternately with Proportional Cas Flow l.etectors. | ||
The systems have an average background count rate of less than 1 count per minute.The instruments have an Alpha efficiency of 33%for Plutonium-239 and Beta efficiences of 05%for Strontium, Yttrium-90 and 03%for Cesium-137. | The systems have an average background count rate of less than 1 count per minute.The instruments have an Alpha efficiency of 33%for Plutonium-239 and Beta efficiences of 05%for Strontium, Yttrium-90 and 03%for Cesium-137. | ||
| Line 147: | Line 162: | ||
~4 4~~Hs w w=-8 kJ~~x i ri'"e 0~4~.10 Figure 13 GROSS BETA IH AIR PARTICULATES NEEKLY ACTIVITY-'I 985 STATION 40A O..05 0-I-22 I I~I t 32 gpC'4'~~4' I I~,~~~~~4l 4Q~~*~0')4 eu 4J i~'h A+l figure 14 GROSS BETA IN AIR PARTICULATES NEEKLY ACTIVIT'(-1985 STATION 44A (3 Q..05 0-22 32 | ~4 4~~Hs w w=-8 kJ~~x i ri'"e 0~4~.10 Figure 13 GROSS BETA IH AIR PARTICULATES NEEKLY ACTIVITY-'I 985 STATION 40A O..05 0-I-22 I I~I t 32 gpC'4'~~4' I I~,~~~~~4l 4Q~~*~0')4 eu 4J i~'h A+l figure 14 GROSS BETA IN AIR PARTICULATES NEEKLY ACTIVIT'(-1985 STATION 44A (3 Q..05 0-22 32 | ||
8.2 Airborne Radioiodine Samples for airborne radioiodine monitoring are collected concurrently with the air particulate samples.These samples are collected in charcoal cartridges and analyzed for 1-131.As can be seen in Table XIV no radioiodine'samples collected during the second h quarter of 1985 showed observable I-131 activity.Third quarter radioiodine data may be found in Table XV.i~!o samples indicated I-131 activity above the detection limit of 0.007 pCilm3.As can be seen in Table XVI no radioiodine samples collected during the fourth l quarter of 1985 showed, observable I-131 acitivty. | ===8.2 Airborne=== | ||
Radioiodine Samples for airborne radioiodine monitoring are collected concurrently with the air particulate samples.These samples are collected in charcoal cartridges and analyzed for 1-131.As can be seen in Table XIV no radioiodine'samples collected during the second h quarter of 1985 showed observable I-131 activity.Third quarter radioiodine data may be found in Table XV.i~!o samples indicated I-131 activity above the detection limit of 0.007 pCilm3.As can be seen in Table XVI no radioiodine samples collected during the fourth l quarter of 1985 showed, observable I-131 acitivty. | |||
TABLE XIY AIRI3ORHE RADIOIODINE SECOND OIJARTER l985 Collection Period 05/22/85-05/29/85 05/29/85-06/05/85 06/05/85-06/l2/85 06/12/85-06/19/85 06/l9/85-06/2C/85 06/26/85-07/03/85 Station I Station 0 Station 6 Station 7A Station 10A Station l5 Station l7A+Iodine-I 3l activity less than 0.007 pCi/m>. | TABLE XIY AIRI3ORHE RADIOIODINE SECOND OIJARTER l985 Collection Period 05/22/85-05/29/85 05/29/85-06/05/85 06/05/85-06/l2/85 06/12/85-06/19/85 06/l9/85-06/2C/85 06/26/85-07/03/85 Station I Station 0 Station 6 Station 7A Station 10A Station l5 Station l7A+Iodine-I 3l activity less than 0.007 pCi/m>. | ||
TABLE XIV (Cont.)AIRBORNE l(ADIOIODINE 1985 Collection Period 05/22/85-05/29/85 05/29/85-06/05/85 06/05/85-06/12/85 06/12/85-'6/19/85 06/19/85-06/26/85 06/26/85-07/03/85 Station 21 Station 29 Station 35 Station 00 Station 00'Iodine-131 activity less than 0.007 pCi/m3. | TABLE XIV (Cont.)AIRBORNE l(ADIOIODINE 1985 Collection Period 05/22/85-05/29/85 05/29/85-06/05/85 06/05/85-06/12/85 06/12/85-'6/19/85 06/19/85-06/26/85 06/26/85-07/03/85 Station 21 Station 29 Station 35 Station 00 Station 00'Iodine-131 activity less than 0.007 pCi/m3. | ||
| Line 173: | Line 189: | ||
No groundwater sample collected during I985 had detectable levels of Tritium or Strontium-90. | No groundwater sample collected during I985 had detectable levels of Tritium or Strontium-90. | ||
In addition, no isotopes of interest were.detecteC by gamma spectral analysis of the groundwater samples. | In addition, no isotopes of interest were.detecteC by gamma spectral analysis of the groundwater samples. | ||
TABLE XXV GROUNDWATER 1985 Collection Location Date Collected Gross Alpha 1.0>>Ci/l Cross beta Strontium-90 Tritium 2.0>>0;5>>1000>>5'e I I 27ddc 08/15/85 II/IO/85 2.2+1.0<<<<<I.O 2.1+0.5<<<<<2.0<0.5<0.5 I GOO<1000 6'el l 30abb 08/15/85 1.9+I.3<<<<<2.0 I I/IO/85<1.0<2.0<0.5<0.5<1000<IOOG<<Detection limit>><<Verified by reanalysis TABLE XXVI CiROljNDWATER GAh1h1A SPLCTROh!ETP Y l9SS Date Collection Location Collected Ci/l Ba-l00 Co-60 Mn-S0 Ru,Rb-l06 Zn-6S Zr,Nb-9S Cs-l37 Cs-l30 Cc 1 00 0" S" 2" lo" l6" lo" 2" lo" IS" (Veil 27ddc os/ls/ss>>/l0/ss 5'cll 30abb os/l s/ss l l/l 0/SS NONE DETECTED I"Detection Limit 8.7 Surface Water Surface water samples were'introduced into the monitoring program during the third quarter of 1982.Samples from PVi4CS Reservoir and PVNCS Evaporation Pond were collected weekly throughout 1985.These samples were anal:zed for Iodine-131 activity, then composited at the end of each month and analyzed for Gross Alpha, Cross Beta, Strontium-89, Strontium-90, Tritium and Gamma-emitting nuclides.Results of these analyses are presented in Tables..XVII, XXVIII, YXIY, and XXX.Iodine-131 was detected:.". | TABLE XXV GROUNDWATER 1985 Collection Location Date Collected Gross Alpha 1.0>>Ci/l Cross beta Strontium-90 Tritium 2.0>>0;5>>1000>>5'e I I 27ddc 08/15/85 II/IO/85 2.2+1.0<<<<<I.O 2.1+0.5<<<<<2.0<0.5<0.5 I GOO<1000 6'el l 30abb 08/15/85 1.9+I.3<<<<<2.0 I I/IO/85<1.0<2.0<0.5<0.5<1000<IOOG<<Detection limit>><<Verified by reanalysis TABLE XXVI CiROljNDWATER GAh1h1A SPLCTROh!ETP Y l9SS Date Collection Location Collected Ci/l Ba-l00 Co-60 Mn-S0 Ru,Rb-l06 Zn-6S Zr,Nb-9S Cs-l37 Cs-l30 Cc 1 00 0" S" 2" lo" l6" lo" 2" lo" IS" (Veil 27ddc os/ls/ss>>/l0/ss 5'cll 30abb os/l s/ss l l/l 0/SS NONE DETECTED I"Detection Limit | ||
===8.7 Surface=== | |||
Water Surface water samples were'introduced into the monitoring program during the third quarter of 1982.Samples from PVi4CS Reservoir and PVNCS Evaporation Pond were collected weekly throughout 1985.These samples were anal:zed for Iodine-131 activity, then composited at the end of each month and analyzed for Gross Alpha, Cross Beta, Strontium-89, Strontium-90, Tritium and Gamma-emitting nuclides.Results of these analyses are presented in Tables..XVII, XXVIII, YXIY, and XXX.Iodine-131 was detected:.". | |||
none of the 1985 surface water samples collected. | none of the 1985 surface water samples collected. | ||
Table YXIX presents cata obtained for analyses of Cross Alpha, Gross Beta, Strontium-89, Strontiu-...-90 and Tritium on the monthly composite samples.Cross Alpha activity".'as"etected in two of the monthly composite's one (november) from the PV.';CS Evaporation Pond (3.2+1.6 pCi/1)and one (november) from the P"."i S Reservoir (1.9+ID pGi/I).PVfiGS Reservoir corr."estates demonstrated Cross Beta activities ranging from less th n 2.0 pCi/I t'."..9 0.7 pC i/l (.",'ovember composite). | Table YXIX presents cata obtained for analyses of Cross Alpha, Gross Beta, Strontium-89, Strontiu-...-90 and Tritium on the monthly composite samples.Cross Alpha activity".'as"etected in two of the monthly composite's one (november) from the PV.';CS Evaporation Pond (3.2+1.6 pCi/1)and one (november) from the P"."i S Reservoir (1.9+ID pGi/I).PVfiGS Reservoir corr."estates demonstrated Cross Beta activities ranging from less th n 2.0 pCi/I t'."..9 0.7 pC i/l (.",'ovember composite). | ||
Revision as of 14:08, 18 October 2018
| ML17299B219 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/31/1985 |
| From: | ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
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| ML17299B218 | List: |
| References | |
| NUDOCS 8604300060 | |
| Download: ML17299B219 (122) | |
Text
ARIZONA NUCLEAR POWER PROJECT PALO VERDE NUCLEAR GENERATING STATION OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REPORT FOR 1985 86043000b0 8b0423 PDR*DOCK 05000528 R PDR
~"'V 4 gJ J~\i~I I A~I l i CONTENTS Number 1.0 2.0 3.0 0.0 5.0 6.0 7.0 S.Q 9.Q 1Q.O Appendix A Appendix B Title Abstract Introduction Description of the b,lonitoring Program Analytical Procedures Sample Preparation 5,'.ethods Nuclear instrumentation Isotopic Detection Limits and Activity Determinations Quality Control Program Data Interpretation and Conclusions 5,'.iscellaneous Information References EPA Cross-checl<
Results 1985 Land Use Census~Pa e 12 20 101 102 108 L 1'l.J 1 lg TABLES Number II III IV VI VII VIII IX XI XII XIII XIV XV XVI XVII XVIII xv XX XXI XXII XXIII Title Collection Locations Collection Schedule Aliquot Scanned for Detection Limit Calculation and Actual Analysis Sample Counting Times Detection Limits by other than Gan;ma Spectrometry Detection Limits by Gamma Spectrometry Cross Beta in Air Particulate Data (Second Quarter)Gross Beta in Air Particulate Data (Third Quarter)Cross Beta in Air Particulate Data (Fourth Quarter)Cross Beta in Air Particulate Lata (Station Summary)Cross Alpha in Air Particulate Data (Second Quarter)Gross Alpha in Air Particulate Data (Third Quarter)Cross Alpha in Air Particulate Data (Fourth Quarter)Airborne Padioiodine Data (Second Quarter)Airborne Radioiodine Data (Third Quarter)Airborne Radioiodine Data (Fourth Quarter)Quarterly Thermoluminescent Dosimetry (Second Quarter)Quarterly Thermoluminescent Dosimetry (Third Quarter)C,'varterly Thermoluminescent Dosimetry (Fourth Quarter)Vegetation Vegetation (Leafy), Camma Spectrometry Vegetation (Produce R Citrus Fruits), Car.ma Spectrometry Drinking'6,'ater~Pa e 9 10 25 26 27 30 33 00 60 62 67 69 71 79 SO v2 I C 4 C lj~1, 1 I l)t'~c 1p tj 1 e0 P I II~ji L I 3 TABLES (Cont.)Number XXIV XXV XXVI XXVII X X VIII XXIX XXX XXXI XXXII XXYIII Title Drinking Water, Gamma Spectrometry Croundwater Groundwater, Gamma Spectrometry Surface Water, PVNGS Reservoir Surface Water, PVNGS Evaporation Pond Surface Water (Composite)
PVNGS Evaporation Pond and Reservoir Surface Water (Composite), Gamma Spectrometry PVNGS Evaporation Pond and Reservoir Alilk (Fresh)AIilk (Fresh), Gamma Spectrometry Env ironmenta I Radiological A'onitoring Program-Annual Summary-l985~Pa e 83 85 86 89 90 91 92 Ph 90 V 0 f C 4 C~I Y FIGURES Number I 2 3 6 7 8 9 10 11 12 13 10 15 16 17 18 19 Title Area Collection Locations-Map Site Collection Locations-Map Gross Beta in Air Particulate (Station I)Gross Beta in Air Particulate (Station 0)Cross Beta in Air Particulate (Station 6)Cross Beta in Air Particulate (Station 7A)Cross Beta in Air Particulate (Station ISA)Cross Beta in Air Particulate (Station 15)Cross Beta in Air Particulate (Station 17A)Cross Beta in Air Particulate (Station 21)Gross Beta in Air Particulate (Station 29)Cross Beta in Air Particulate (Station 35)Gross Beta in Air Particulate (Station 00)Cross Beta in Air Particulate (Station 00)Gross Beta in Air Particulate (X!ean V.'eekiy Activity)t uarterly Them:oluminescent Dosimetry (Second Quarter)Quarterly Thermoluminescent Dosimetry (Third Quarter)Quarterly Thermoluminescent Dosimetry (Fourth Quarter)ihlean Quarterly Thermoluminescent Dosimetry~Pa e 7 8 06 07 08 Q9 50 51 52 53 50 55 56 57 58 73 70 75 76 I IL C l I I l 1 I Abstract This operational environmental radiological monitoring program is an ongoing study conducted by Controls for Environmental Pollution, Inc.(CEP)for Arizona Nuclear Power Project (ANPP), Palo Verde Nuclear Generating Station (PVNGS).The data presented in this report were obtained from samples collected by APS personnel and analyzed by CEF during l985, beginning May 25.In order to determine radiation levels in the environment around the PYNGS, the following types of samples were collected:
vegetation (including fruits and vegetables), fresh milk, groundwater, drinking water, surface water, airborne particulate and radioiodine.
1 l'3 4'I 4 I I I I Analytical results are presented and discussed along with other pertinent information.
Possible trends and anomalous results, as interpreted by CEP are also discussed.
ARIZONA NUCLEAR PO%'ER PRO3ECT PALO VERDE NUCLEAR GENERATING STATION OPERATIONAL RADIOLOGICAL MONITORING PROGRAM 1.0 Introduction This report presents results of the operational environmental radiological monitoring program conducted during 1985 by Controls for Environmental Pollution, Inc.(CEP)for Arizona Nuclear Power Project (ANPP), Palo Verde Nuclear Generating Station (r VNGS).In compliance with federal requirements to provide a complete environmental monitoring program for nuclear reactors, and in its concern for maintaining the quality of the local environment, ANPP began its pre-operational environmental monitoring
/program in 1979.The program complies with the requirements of the U.S.Nuclear Regulatory Commission in their Reactor Assessment Branch Technical Position, Revision 1, November, 1979.Cn Play 25, 1935 PViNGS Unit One became operational.
The objectives of the pre-operational radiological environmental monitoring program were as follows: (1)to provide information on the concentrations of radionuclides and levels of radiation in the environs prior to reactor operations, (2)to provide the experience from which to develop a meaningful operational program of radiological assessment, and (3)to develop trip notification levels (background levels)for operational evaluation.
Program modifications, should they prove necessary, will be described in each annual report.The objectives of the operational radiological environmental monitoring program are as follows: 1)to determine radiation levels in the environs during reactor operations; 2)to monitor potential critical pathways of radioeffluent to man;3)to determine radiological impact on the environment caused by the operation of PVNGS.
A number of techniques are used to distinguish power plant effects from other sources during the operational phase, including application of established background levels.Operational radiation levels measured in the vicinity of AiNPP are compared with the pre'-operational measurements at each of the sampling locations.
Results of the monitoring program help to evaluate sources of elevated levels of radiation in the environment, e.g., atmospheric nuclear detonation or abnormal plant releases.1.1 Pre-o erational Radiolo ical Alonitorin Pro ram Chan es 1~')*~To date, the following changes have been made in the pre-operational
/operational radiological environmental monitoring program: I.l.l August 1980-Desert Farms became the new designation for what was earlier known as l8bbb or 19bbb.The collection location changed slightly.1.1.2 February 1980-Meat samples were deleted from the sampling program.They may be collected again after PVNCS becomes operational.
11.3 Februaiy 1980-The Adams residence replaces the Roger's residence as a vegetation and citrus collection location.The Adams residence is I'pproximately one half mile north of the old sampling location.I.IA February 1980-A3~.'.Farming, Inc.in Chandler, Arizona was added to the sampling program as the new Vegetation control site.1.1.5 3anuary l980-PVYGS took over the TLO program.1.1.6 3anuary 19SV-The Hamstra//2 Dairy replaced the Dan Paxton I'airy as a milk sampling location.1.1.7 1983, fourth quarter-CEP purchased a Berthold (LB770)10-Channel Low Level Planchet Counting'ystem.
This system is capable of simultaneously counting l0 planchets for gross alpha.and gross beta activities alternately with proportional gas flow detectors.
The system has an average background count rate of less than l count per minute for Beta and less than 0.05 count per minute for Alpha.The system is connected to a computer to calculate samples as pCi/unit volume.1.1.8 1983, first quarter-Two new sample locations for ve etation were added to the sampling program, the Cooley Farm, located approximately 75 miles east of the PVNCS and the Rogers Residence, approximately 3 miles to the east of the PVNCS.
1983, first and second quarters-Domestic meat was collected at the Paxton Dairy during the first and second quarters of 1983.February 1983-IVeekly airborne radioiodine sampling was re-introduced into the sampling regimen (See Section I.l.l 2).December, l982-A Salt Drift A'onitoring Program was initiated and.continued throughout 1983 at monitoring locations 10, l5, l7A, Zl, 29, and 00.Since this program required air filter leachates for analysis, gamma spectral analysis was performed weekly for these sites rather than quarterly.
Vid 1982-Thermoluminescent Dosimeter collection location number 05 was moved from the APS Deer Yalley Office to PVNGS Lead Shielding.
1982-No Groundwater samples were collected from V'inter's.
9'ell or Ped Quail and these locations were dropped from the program.1982, fourth quarter-CEP purchased a Tennelec LB5100 System.This system has a two-inch detector (80 ug/cm2 window)with an average of 2 cpm Beta background and 0!I cpm Alpha background.
This system has been designed for simultaneous Alpha and Beta counting and has a sample capacity of fifty samples.l982, third quarter-Surface water samples (PVNCS Evaporation Pond and Reservoir) were included in the sampling regimen.Samples were analyzed for Iodine-131 weekly and composited monthly for Cross Alpha, Gross Beta, Strontium-89, Strontium"-90, Tritium and Camma Spectral analysis.Anarch, 1982-the Hoffman anC Alineso-Boers Dairies were deleted from the sampling progra'm due to scheduling and relocation problems.At the same time, two net dairies were introduced into the sampling program, the.Paul Skousen Dairy located approximately 24 miles east of the PYNCS and the Dan Paxton Dairy located in Chandler, Arizona, approximately 75 miles east of the PVNGS.1982-The collection of l..airy Feed,>wildlife (jack rabbit)and Poultry Products (eggs)was deleted from the sampling regimen.1982, fourth quarter-A TLC'adge comparison was made.This was accomplished by introducing a different type of dosimeter (CaSOp), into the field which was placed next to the LiF dosimeter in order to evaluate performance of each type of badge with respect to each other.
1.1.19 December 31, 1981-Sampling for airborne radioiodine was suspended I until February l983, six months prior to the then estimated fuel load date.1.1.20 1.1.21 1.1.22 1.1.23 1.1.20 1.1.25 1.1.26 1981-changes in the method of rep'orting non-detectable activity levels in the annual report were made.All samples that have non-detectable activity levels are reported as less than the detection limit (i.e., less than 5 pCi/1)instead of the previously used method of reporting, (i.e., 0+5 pCi/I).In addition, Tritium activities in groundwater reflect a l000 pCi/I detection limit.1981, fourth quarter-Sampling for airborne particulate and airborne radioiodine began.3uly, 198l-The TLD (Thermoluminescent Dosimetry) dose measurement pr'ogram began.1981-CEP acquired a new computer-based Gamma Spectrometry System.It consists of a Tracor Northern Scientific (Alodel 0500)0096 channel pulse height analyzer coupled to three intrinsic detectors and one CeLi detector.The new system has greater sensitivity and gives more detailed information about the spectrum.3anuary, 1980-Due to a fire which totally destroyed Nancy's Yellow Canary, Drinking Water samples were collected from the Red Quail, a general store located directly behind what is now called"The Local".The Red Quail water comes from a well at the trailer park behind the store.September, l980-The Ped Quail had an extensive filtering system installed.
This made samples from Red Quail non-representative of the groundwater found in the Palo Verde area.For the C'ctober 24, 1980 sampling, the second sample was taken at a faucet cn the pipe, in order to obtain an unfiltered sample.All remaining samples in l980 and 1981 were taken from this point (faucet on the pipe).September, 1979-The Al Lueck, 3r.Dairy moved to a new location approximately 25 miles east of PVNGS.
2.0 Descri
tion of the Monitorin Pro ram ANPP has contracted with CEP to determine the ambient radiation levels in the environment around PVNCS during its operation.
ANPP personnel collect the samples and ship them to CEP.The types of environmental samples collected include: vegetation (produce and citrus fruits), groundwater, drinking water, surface water, fresh milk, airborne particulates, and radioiodine.
The locations of the monitoring sites are shown in Figure I.The monitoring sites and the respective sample types collected are described in Table I.Table II describes the sample collection frequency.
Information, concerning new sample types, locations, and collection frequency are included in these tables where applicable.
~Irrvrrn r 5.r i I IICDDI INIX--~-ll~wgq,ken erg.".~'w r'P\(IF~a SII I l NIINAGf'un C1ty.l, ,a 4g~~f 1I I tf ON I A'p SNLt Nlvfn INDIAN Nf Sf N vlf IDn.f It,s I.~1K II~tAN AD I VAllf Y 42~:.T I'>, , 4S 36~A..IC.P I'SDnof?o15+
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~~I t~.ttt<<--~~r t t tttl t-t~1, r t('-','~t r'I'II(ttt~I 0(2 I OL I~wJ'l,!'I I I 2I6..i, 2I I h<tA~'.~50:)*tt.t h.,I I t,l~~tr.I It n~))I~Pl II inlerIbur<<>ttir ta I Iv>~t~~4.".IIII~(l.!,'tlltvt.i t42~I PALO I(IRDr tt)HUCLLAR I tGIHIRAIIHG i~)I.r I lt 4 3I I 00~~'ilt I~rt<<t t 2 0 ttt'I'li tt ll I 4 gQ41*L t~ll)~I I LQIA..-I Qf I I.I i Q00, L I'I~'v~~r tt*t rt rt Ot Wrtt'0I hltr(~~t'r~<<tt I~~O~i~r.It t~r<<t~~5 I AT I OIL II.'0 tt r r.p rtv vt-l AI I 4C I I-:.I<I t~~I*,}rt<<IIO<<lt<<f t tl I'Pigure 2 I~."L~Wl'tl I~t Palo Verde Nuclear GeneratiLL~
Station v Radiological Environmental Monltori'ng Program Sample Sites tv<<tv<<1 TABLE I COLLECTION LOCATIONS Sample Site/7 6 7A ISA 15 17A 21 35 00 06 07 08 09 50 51 52 53 50 55 56 Sam leT e Air Air Air (Control)Air Air Air Air Air Air Air Air IVater, Veg.Vegeta tion Water Water b,'ilk Milk, Veg.Vegetation Milk 5!Ilk Milk Milk (Control)Location E30 E20 SSE35 SE8 NNE2 NE2 S3 NNW9 I'l3 ENE35 NNW9 EI'I E3 SW5 ESEO El 1 E15 E26 E27 E28 E?5 Location Descri tion APS Coodyear Office APS Buckeye Office APS Gila Bend Substation Arlington School Buckeye-Salome P.d.8'71st Ave.YE Site Boundary 351st Ave., 1 mi.S of B-S Rd.S Site Boundary Tonopah, Palo Verde Inn Fire Station Trailer Park at 9'intersburg APS El N'!rage Office (Sun City)A!cArthur's Farm, Tonopah Adam's Residence, 355th Avenue b: Buckeye-Salome Road 7,'ell 19bbb-Desert Farms Wedgeworth Residence, 351st Ave.R Dobbins Rd.C'ordell Baisley t.airy, 331st Ave.Van Buren Butler Fairy, Palo Verde Pd.Southern C'amb ron Farm, Miller Rd.*Broadway Kerr L a iry, Dean 8 Buckeye Rds.Skousen Dairy, Airport~~Dobbins Rds.Al Lueck Dairy 3r., 3ackrabbit Hazen Rds.Ham stra L a iry 0 2, N'.c Queen 2 P yan Rd s.58 59 60 61 62 Water Water Surface Water Surface Water Cnsi te Cnsite~Onsite Onsite Vegetation (Control)E80 Vegetation (Control)E60 9'e II 2?ddc~9'ell 30abb PVNCS Evaporation Pond PVYCS Reservoir Cooley Farm, A'cQueen 8: Cuadalupe Road A3A!Farms Inc., Chandler Industrial Park (a)Based on Table 3-I, NVREC-0650'istances are from centerline of Unit 2 containment in miles.
TABLE II l 985 COLLECTION SCI IEDULE Collection Site iII, APS Goodyear Office il4, APS Buckeye Office if6, APS Gila Dend Substation II7A, Arlington School II I4A, Buckeye-Salome Rd.h 37lst Ave.II I', NE Site Boundary fl l7A, 351st.Ave., I mi.S ol D-S Rd.112I, 5 Site Doundary II29, W Site Doundary II35, Tonopah, Palo Yerdc inn Fire Station Air Particulates W Airborne Radioiodine W Lu W Domestic Meats Fresh Milk Drinking~Ve etatton Ground at r Water Suf face lpga ter 840, Trailer Park at Wintcrsburg II44, APS El hlirage Oflice I/46, htcArthur's Farm II47f Adam's Residence II48, Desert Farms II49, Wedgeworth Residence f150, Cordell Daisley Dairy Ii>l, Dutler Dairy II52, Cambron Farm ii53, Kerr Dairy II54, Skousen Dairy III', Al Lueck, 3r.Dairy W W ht M hl hl AA hl hl hl ThOLE II (Cont.)f985 COLLECTION SCl IEDlILE Collection Site II 56, Ilanistra II2 Iaairy 857, Well 27ddc 1158, Well 30abb 859 PVNGS I;v)pofation Pond Il60, PVN(iS fleshy rvuir IIGI, Cooley Farm II62, A3M I'an<<s, Inc.Air Particulates Airborne Radioiodine Domestic Meats Fresh Milk Drinking~Ve elation Craunderaier Water AA AA Surface%'ater W W=Weekly M=Monthly Ah=Asavailableduringgrowingseason
+=Quarterly 3.0 Anal tical Procedures The analytical procedures discussed in this report are those routinely used by CEP to analyze samples.3.1 Fresh Milk 3.1.1 Iodine-131 Two liters of milk containing standardized Iodine carrier are stirred with Amberlite IRA-000 anion exchange resin for one hour.The Iodine is stripped from the resin with sodium perchlorate (NaCIO>)and precipitated with silver nitrate (AgNO3).The precipitate is filtered on a tared glass fiber filter.The dried precipitate is weighed for percent recovery and counted for Iodine-131 in a thin window, gas flow, proportional counter (Beckman Low Beta II or BerthoJd LB770).These instruments have a forty-one percent efficiency and a forty-five percent, respectively using Iodine-131 precipitated as silver iodide (Agl).3.1.2 Strontium-89 The Strontium is precipitated with concentrated fuming nitric acid, redissolved in water, made basic with dilute ammonium hydroxide and precipitated as the oxalate.The dried oxalate precipitate is counted in a low background proportional counter (Qeckman Low Beta II or Berthold LB770)having sixty percent and forty-five percent Strontium-Yttrium-90 efficiencies, respectively.
The Strontium-39 activity is determined by subtracting the previously measured Strontium-90 activity and its corresponding Yttrium-90 ingrowth from the measured gross Strontium activity.3.1.3 Strontium-90 An aliquot of milk containing standardized Strontium and Yttrium carriers, is stirred with I.,owex SOY/XS cation exchange resin at a pH of six for thirty minutes: All ruclides are stripped from the resin with strong acid.After the ingrowth period has been established, the Yttrium-90 is extracted with five percent di-2-ethylhexyl phosphoric acid (D2EHPA)in toluene, back extracted into an aqueous phase, precipitated as the oxalate and counted in a low backgrou,.d internal gas flow proportional counter (Beckman Low Beta II or Berthold LB770)to determine the Strontium-90 content of the sample.These systems.have Strontium-Yttrium-90 efficiency of sixty percent and forty-five percent,'espectively.
3.1.0 Gamma
S ectrometr A suitable aliquot of sample is placed in a Marinelli beaker and counted with a multi-channel analyzer equipped with an intrinsic Cermanium detector which is coupled~to a 0096 channel, computer based, multi-channel analyzer (Aorthern Scientific TN0500).The resulting spectrum is analyzed by the computer, and specific nuclides, if present, identified and quantified.
3.2~Ve etation 3.2.l Gamma S ectrometr Refer to hlilk Subsection 3.1.0.3.2.2 Iodine-131 Required on leafy vegetation only.After appropriate preparation of the sample, analysis is performed as discussed in Subsection 3.l.'.3.3 Groundwater and Drinkin 9'ater 3.3.1 Cross Al ha and Beta P A 1.0-liter aliquot of water is evaporated to dryness and transferred to a weighed planchet.The Gross Alpha and C:ross Beta radioactivity is measured by counting the pianchet in an internal gas flow, sin;ult"neous proportional, low background counter (Beckman giide Beta ll or Oerthold LB770), or by counting the planchet in a low bacl'ground simultaneous counter (Tennelec L B5100).3.3.2 Gamma S ectrometr Refer to hlilk Subsection 3.1.0.3.3.3 Strontium-90 A 1.0 liter aliquot of the sample containing standardized stable Strontium carrier is evaporated to dryness and wet ashed with concentrated nitric acid (HNO3)and hydrogen peroxide (H202).The Yttrium-90 is extracted with five percent Di-2-ethylhexyl phosphoric acid (D2EHPA)in toluene after the ingrowth period has been established, back extracted into an aqueous phase, precipitated as the oxalate and counted with an integral gas flow proportional counter (Beckman Low Beta ll or Berthold LB770)having a Strontium, Yttrium-90 efficiencies of sixty percent and forty-five percent, respectively.
The counting results are back calculated to give Strontium-90 activity.3.3 tt Tritium Three milliliters of the water sample are mixed with NEF-930 Aquasol cocktail which is manufactured by New England Nuclear Corporation.
The mixture used is nineteen percent sample in a clear gel type aquasol.This gives a Tritium counting efficiency of approximately thirty percent.The counting system used is a Beckman LS-100 Liquid Scintillation Spectro-meter.Six Tritium standards, certified by NBS, are counted before each set of water samples to check the counting system's efficiency.
A counting efficiency is derived from these standards which are equal in activity but vary in the amount of quenching.
3.0 Surface
Water 3.0.1 Iodine-131 One liter of water containing standardized Iodine carrier is acidiiied iyith nitric acid (HNO3), then extracted with carbon tetrachloride
{CClq)and sodium nitrite (NaNQ2)to remove the Iodine.The Iodine is back extracted from the carbon tetrachloride (CCIq)using a 0.2%hydrazine soluticn, which supplies more purification and an aqueous media for precipitatioe Iodine is precipitated with silver nitrate (AgNQ3)and filtered on a tared glass fiber filter as silver iodide (Agl).The Cried precipitate is weighed for recovery and counted for Iodine-131 in a thin window, gas flow,.proportional counter (Beckman Low Beta II or Berthold LB770)having forty-one percent arc forty-five percent ef ficienies, respectively for iodine-131 precipitatec as silver iodide (Agl).3.0.2 Gross Al ha and Beta An aliquot of the monthly composite is taken and analyzed according to Ground and Drinking Y.'ater Subsection 3.0.1.3.0.3 Gamma S ectrometr An aliquot of the monthly composite is taken and analyzed according to hlilk Subsection 3.1.0.3A.O Strontium-89 An aliquot of the monthly composite is taken and analvzed according to Milk Subsection 3.1.2.3A.S Strontium-90 An aliquot of the monthly composite is taken and analyzeC according to Croundwater and Drinking Water Subsection 3.0.3.".3.tt.6 Tritium An aliquot of the monthly composite is taken and analyzed ac<"rcing to Ground and Drinking Water Subsection 3.0.0.3 5 Air Particulate
3.5.1 Gross
Al ha and Beta The Sartorius filter (cellulose nitrate filter with a 3 micron pore size), is placed in a 50 mm stainless steel planchet and counted for Gross Alpha and Gross Beta radioactivity using a low background internal gas flow, simultaneous proportional counter (Beckman Wide Beta II), or by using a low background simultaneous counter (Tennelec LB5100).3.5.2 Gamma S ectrometr The air filters are sealed in small, plastic Klarinelli beakers and counted utilizing the method described in Milk Subsection 3.1.0..3.6 Airborne Radioiodine Two analytical methods for airborne radioiodine are used by CEP depending upon the length of time between the sample collection date and the date of sample receipt at CEP.The sensitivity of the Camma Spectrometry i'.lethod decreases significantly after an iodine-131 decay of greater than one half-life (3.00 days).Therefore, if more than one week has elapsed between sample collection and analysis of the sample the Alkaline Leach Vethod provides a greater sensitivity and is thus the analytical method of choice.3.6.1 Alkaline Leach Method Radioiodine is removed from activated charcoal along with a standardized iodine carrier using concentrated ammonium hydroxide (NH4+H)hydrogen peroxide (H2C'2).The charcoal is filtereC and the remaining solution is acidified with nitric acid (HYC'3)and extracted with carbon tetrachloride (CClq).A 0.2;~hydrazine solution supplies further purification and an aqueous media for precipitation.
Iodine is precipitated with silver nitrate and filtered on a tared glass fiber filter as silver iodide (Agl).The dried precipitate is weighed for recovery and counted for Iodine-131 in a thin window, gas flow, proportional counter (Beckman Low Beta ll or Berthold LB770)having forty-one percent and forty-five percent efficiencies, respectively for iodine-131 precipitated as silver iodide (Agl).3.6.2 Gamma S ectrometr Method The direct gamma counting method for iodine-131 consists of placing the charcoal canister directly on an intrinsic germanium detector and analyzing the resulting spectrum for iodine-131 using the computer, based Northern Scientific TN 0500 System.The system is calibrated using charcoal filters which have been uniformly loaded (in the first 5 mm)with standardized isotopes traceable to NGS and calibration verification is performed by analyzing a charcoal filter which has been uniformly loaded (in the first 5 mm)with standardized iodine-131 traceab le to NBS.Deposition of activity in the first 5 mm of the filters is done to simulate actual sample loading and both standards and samples are placed on the detector so that the load gradient is decreasing with distance from the detector.0.0 Sam le Pre aration Methods The following sample preparation methods are routinely used by C EP.O.l Ve etation Sam le Pre aration The plastic bags are opened and the sample weighed immediately to obtain the wet weight.3.After weighing, the sample is transferred to a crying pan and placed in an oven at 110 C.5.The dry sample is ground to a fine powder anC homogenized.
The sample is then dissolved or ashed, whichever is required for further isotopic analysis.
0.2 Milk Iodine carrier (Potassium loCide), formalin and sodium bisulfate are added when the milk is collected to stabilize the iodine-1'31 during shipment of samples to CEP.The procedure for Fresh,'.lilk is then followed as described in Section 3.1, of this report.5.0 Nuclear Instrumentation 5.l Tracor Northern Computer Based Gamma S ectrometer The Gamma Spectrometer consists of a Tracor Northern Ti'>-0500 K!ultichannei Analyzer equipped with: a)DEC LSI-ll/23 lI,!icroprocessor; b)DEC'T-il Version IV Operating System;c)Free Standing Console consisting of a full ASCII keyboard;d)Comprehensive 5!CA Control Section, and e)Two Solid State Ce(Li)Detectors and Three Intrinsic Detectors having 2.8 KeV, 3.0 KeV, 2.07 KeV, 1.35 KeV and 1.85 KeV resoluti'ons and respective efficiencies of 16.1,~, 3.9",~, 22.6".-, 30.6%and 25.1%.The Computer Based Tracor Northern Gamma Spectrometry Systerr;is used for all gamma counting.The system uses the latest software to search and identify, as well as quantize the peaks of interest.5.2 Beckman Wide Beta II Low Back round Cas Pro ortional S stem The Beckman Wide.Beta II Two-inch Detector Counting System has an average of 2.5 cpm Beta backgrounC and O.l cpm Alpha background.
The system can also be set up for one-inch detector.The system capacity is one hundred samples.The I detector has an efficiency of 60": for Strontium-90 and 00;5 for Plutonium-239.
5.3 Beckman
0/ide Beta II Low Back round Cas Pro ortional S stem (Simultaneous)
The Beckman Wide Beta II Two-inch Planchet Counting System has an average of 2.5 cpm Beta background and O.l cpm Alpha background.
The detector has a 60%efficiency for Strontium-90 and 00%for Plutonium-239.
This system has been designed for simultaneous Alpha and Beta counting.The system sample capacity is one hundred samples.5A Beckman Low Beta II Low Back round Beta S stem The Beckman Low Beta II Cas Proportional One-inch Detector Counting System has an average of 1.5 cpm Beta background and O.l cpm Alpha background and detector efficiency of 6006 for Strontium-90 and 00%for Plutonium-239.
The system capacity is one hundred samples.The system can also be set up for two-inch detector having 2.5 cpm Beta background and O.l cpm Alpha background.
5.5 Beckman
Low Beta 11 Low Back round Beta S stem The Beckman Low Beta II Cas Proportional Two-inch Detector Counting System has an average of 3.0 cpm Beta background and 0.2 cpm Alpha background and detector efficiency of 60.o for Strontium-90 and 00'.6 for Plutonium-239.
The system capacity is one hundred samples.This system can also be set up for cne-inch detector having 1.5 cpm Beta background and 0.1 cpm Alpha background.
5.6 Beckman
Li uid Scintillation Countin S stems Two Beckman LS-100 Liquid Scintillation Counters will be used for all Tritium determinations, as well as C-IO, P-32, S-35 and other Beta emitters.5.7 Low Back round Al ha Gas Flow S stems The Cross Alpha Counting Systems consist of two windowless gas flow detectors manufactured by Nuclear Xleasurements Corporation with an Alpha efficiency of 55.6 with a background of less than O.l cpm.5.8 Low Back round Scintillation Counter The Low Background Scintillation Counter consists of a Zinc Sulfide screen.The system has an average Alpha of 0.1 cpm.5.9 Tennelec LB5100 S stem The Tennelec L$5100 System has a Two-inch Planchet Counting System and has an average of 2 cpm Beta background and O.l cpm Alpha background.
This system has been designed for simultaneous Alpha and Beta counting.The sample capacity is fifty samples.5.10 Low Level Planchet Countin S stems (2)Each Berthold 10-Channel Low Level Planchet Counting System (Yodel LB700)is capable of simultaneously counting 10 planchets for Cross Alpha and Cross Beta activities alternately with Proportional Cas Flow l.etectors.
The systems have an average background count rate of less than 1 count per minute.The instruments have an Alpha efficiency of 33%for Plutonium-239 and Beta efficiences of 05%for Strontium, Yttrium-90 and 03%for Cesium-137.
5.11 Beckman Li uid Scintillation Countin S stem A Beckman LS-5801 Liquid Scintillation System will be used for all Tritium determinations.
The system has a tritium counting efficiency of sixty percent in a wide open window.6.0 Isoto ic Detection Limits and Activi Determinations Analytical detection limits are governed by a number of factors including:
The sample size taken is based on the numerical data one wishes to obtain which can describe a particular situation and can be interpreted as a basis for possible action.The sample size has to be representative and provide for accurate analysis or the entire process is invalid (Table 111).6.2 Countin Ef ficienc 1 The fundamental quality in the measurement of a radioactive substance is the number of disintegrations per unit time.As with most physical measurements in analytical chemistry, it is seldom possible to make an absolute measurement of the disintegration rate but rather it is necessary to compare the sample with one or more standards.
The standards determine the counter efficiency which may then be used to convert sample counts per minute (cpm)to disintegrations per minute (dpm), 6.3 Back round Count Rate'ny counter will show a certain counting rate without a sample in position.This background counting rate comes from several sources: I)natural environmental radiation from the.surroundings; 2)cosmic radiation; and 3)the natural radioactivity in the counter material itself.The background counting rate will depend on the amount of these types of radiation and the sensitivity of the counter to the radiation.
6.0 Back round and Sam le Countin Time The amount of time devoted to counting background depends on the level of activity being measured.In general, with low level samples, this time should be about equal to that devoted to counting a sample (Table IY).6.5 Time Interval Between Sam le Collection and Countin I ecay measurements are useful in identifying certain short-lived isotopes.The disintegration constant, or its related quantity, the l.al'-life, is one of the basic characteristics of a specific radionuclide and is readily determined if the half-life is sufficiently short.6.6 Chemical Recover of the Anal tical Procedures
.'.lost radiochemical analyses are carried out in such a way that losses occur during the separations.
These losses occur due to a large number of contaminants that may be present and interfere during chemical separations.
Thus it is necessary to include a technique for estimating these losses in the development of the analytical procedure.
The Lower Limits of detection are calculated using the following formula: LLD=0.66 sb E~V~2.22~Y~exp (-DAt)%HERE: LLD="A priori" lower limit of detection as defined above (as pCi per unit mass or volume).sb=Standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute).E=Counting efficieny (as counts per disintegration).
V=Sample size (in units of mass or volume).2.22=Number of disintegrations per minute per picocurie.
Y=Fractional radiochemical yield (when applicable).
Radioactive decay constant for the particular radioisotope.
6 t=Elapsed time between sample collection (or end'of the sample collection period)and time of counting.The value of sb used in the calculation of the LLP.for a particular measurement system is based on the actual observed variance of the background counting rate, or, of the counting rate of the blank sample, (as appropriate), rather than on an unverified theoretically predicated variance.In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background included the typical contributions of other nuclides normally present in the samples.The activities per unit sample mass or volume are determined using the following formula: C+B T2 C-S+1.96 (2.22)(V)(R)(E)(e"~t)(2 22)(V)(R)(E)(e A t)
V/HERE: V 2.22 (e-A t)1.96 Activity as pCi per units sample mass or volume.Sample count rate in counts per minute.Background counts per minute., Sample volume or mass analyzed.Counter efficiency as cpm/dpm.Numerical constant to convert disintegrations per minute to picocuries.
Decay factor to correct the activity to time of collection.
/Counting time in minutes.Statistical constant for the 95K confidence level.Chemical recovery or photon yield.7.0 ualit Control Pro ram CEP employs a mutli-.faceted Quality Control Program designed to maintain high performance of its laboratory.
The overall objectives of the program are to: I.Yerify that work procedures are adequate to meet specifications of ANPP.2.Coordinate an in-house quality control program indepen(ent of external programs, to assure that CEP is operating at maximum efficiency.
Objectives are met by a variety of procedures that oversee areas of sample receipt.and handling, analysis and data review.These procedures include standard operating procedures, known and unknown spike analysis, blank analysis, reagent, carrier and nuclide standardization as well as participation in the U.S.Environmental Protection Agency's Interlaboratory Cross-check Program.(See Appendix A for EP."i Radiological Cross-check results).
TABLE III ALI VOT SCANNED FOR DETECTION LIMIT CALCULATION AND ACTUAL ANALYSIS Sam leT e Air Particulates Airborne Radioiodine Domestic Meats (Beef)Fresh Milk Vegetation (Citrus Fruits)265 m3 265 m3 265 m3 500 g l000 mls 500 g 265 m3 2000 mls 2000 mls 2000 mls Vegeta t ion (Lea f y)Groundwater Drinking Water Surface Water 1000 mls.1000 mls 1000 mls 1000 mls 1000 mls 1000 mls 500 g 1000 mls 1000 mls 1000 mls 100 g 1000 mls 1000 mls 1000 mls 1000 mls 1000 mls 3ml 3 ml 3 ml I I ee I~ee e e ssveewa News eee~cone~~~)I'I TABLE IV SAMPLE COUNTING TIMES Sam leT e Air Particulates Airborne Radioiodine Gross Al ha 100 min Gross Beta 100 min Gamma~Sec.Iodino-13i Strontium-89 Strontium-90 Tritium 8 hrs 8 hrs+Domestic Meats (Beef)Fresh Milk Vegetation (Citrus Fruits)Vegetation (Leafy)Groundwater Drinking EVater Surface EVa ter 100 min 100 8>>i>>100 noah>100 nein 100 rni>>100 mi>>8 hrs S hrs 8 hrs 8 hrs 8 hrs 8 hrs~8 hrs 100 min 100 min 100 min 100 min 100 min 100 min 100 min 100 min 100 min 500 min 500 min 500 min+Alkaline Leach Method Counted for 100 wins TABLE V DETECTION Llh11TS GY OTHER TI-lAN Ghhlh]A SPECTROhIETRY Sam le T Air Particulates Airborne Radioiodine Fresh Milk Vegetation (Leafy)Groundwater Drinking Water Surface Water 0.005 pCi/m3 l pCi/I I pCi/I I pCi/I 0.002 pCi/m3 2 pCi/I 2 pCi/I.2 pCi/I 0.007 pCI/m3++O.'5 pCI/I 0.02 pCI/g>>0.5 pCi/I l.o pCi/I 1.0 pCi/I Strontium-90 0.5 pCi/I 0.5 pCi/I 0.5 pCi/I 0.5 pCi/I Tritium IOOO pci/I I 000 pCi/I IOOO pri/I"As Wet Weight<<~Alkaline Leach Method.I-I31 Detection Limit by Gamma Spectrometry 0.020 pCi/m3 TABLE VI DETECTION LIMITS BY GAMMA SPECTROMETRY Energy MeV Isoto e Sensitivity pCI/gm+Ve etation Sensitivity pCI/I+Groundwater, Drinking Water and Surface Water Sensitivity pCI/I+Fresh Milk Sensitivity pCi/m3 Air Particulate 0.130 0.537 Cerium-100 Barium-100 0.622 0.662 0.?65 O.S35 1.095 1.115 1.173 1.596 PU~Rh-106 Cesium-137 Zr, Nb-95 b'anganese-50 Iron-59 Zinc-65 Cobalt-60 Lanthanum-100 0.605 Cesium-130 0.121 0.075 0.029 0.103 0.056 0.066 0.021 0.021 0.060 0.063 0.4 65 IS 10 2 2 10/2 3 16 5 15 Io 10 2 2 3 16 5 15 0.005 0.030 0.023 0.001 0.001 0.026 O.COI O.OO6 0.005 0.019 0.030+See Table III for aliquots used in the calculation of these sensitivities.
-2?-
8,0 Data Inter retation and Conclusions Interpretations and conclusions regarding all types of samples analyzed during 1985 are discussed in the following sections.Assessment of pre-operational and operational data revealed no significant changes to environmental radiation levels.There was no observed impact on the environment due to PViVGS operations.
For the calculation of means, a value of one half the detection limit is used for all samples with activities below the detection limit.8.1 Air Particulates Air particulate samples were collected from each of the twelve monitoring sites on a weekly basis during 1985.Air filters were analyzed for gross alpha and gross beta activities.
Camma Spectral analysis of the air filters was done on the individual filters for Stations 14A, 15, 17A, 21, 29 and 00 due to the Salt Drift~1onitoring Program.Camma Spectral analysis for the other stations was performed on quarterly composites by station.Ten air particulate samples were marked as possibly invalid upon arrival at CEP.The samples and the reason for the questionable statuses are listed below: Second uarter 1985 Date Collected Site//P.eason 05/29/85 17A i')alfunction of pressure relief valve Date Collected Site/f Reason 07/31/85 08/07/85 08/07/85 09/18/85 10/02/85 6 6 29A 0A Power interupted during sampling period Flow calibration failed Flow calibration and redline criteria not available Numerous insects on air particulate filter Heavy dirt on air particulate filter Fourth uarter 1985 Date Collected lo/o9/ss Io/16/ss Io/23/ss 12/11/85 Site II 29A 15 15 OA Reason Insects on particulate filter 5.'talfunctioning sampler Valfunctioning sampler ,5'et air particulate filter Table VII presents second quarter Cross Beta results.Station 6A showed the highest activity during the quarter (0.001+0.002 pCi/m3 collected 06/19/85-06/26/85).
The Station IA sample collected 05/29/85-06/05/85 showed the E lowest level at 0.015+0.002 pCi/m3..9'eekly mean activities ranged from a low of 0.018+0.002 pCi/m during the period of 05/29/85-06l05l85 to a high of 0.032+0.003 pCi/m in the week of 06/26/85-07/03/S5.
The range of results are/comparable to previous quarterly data and do not indicate'any anomalies.
Table VIII presents the Ciross Beta levels during the third quarter of 1985.maximum value of 0.036+0.002 pCI/m3 was observed at Stations 35A and'A (collected 07/03/85-07/10/S5).
The lowest level of activity was 0.010+0.002 pCi/m3 at Station 04A during the collection period of 07/2~/85-,G7/31/85.
5'eekly mean activities ranged from a minimum of 0.018+0.002 pCi/m 3 (07/17/85-07/20/SS), to a maxirnurn of 0.032+0.G03 pCi/m3 in the period of 07/03/85-07/10/Ss.
The range of results are comparable to previous quarterly data and do not indicate any anomalies.
Table IX presents the Cross Beta activities seen in the fourth quarter.Cbserved levels varied from 0.008+0.006 pCilm3 at Station IOA (collected 12/26/S5-Ol/G2/86), to 0.057+0.G02 pCi/m3 at Station 6A (collected 12/26/85-Ql/Q2/86).
6'eekiy mean activities ranged from 0.013+0.002 pCi/m3 during the collection period of 11/27/85-12/00/85 to 0.037+0.003 pCi/m3 collected lo/23/85-10/30/85 and 0.037+0.005 pCi/g collected 12/18/85-12/26/85.
Based on data from other nuclear reactor.environmental monitoring programs, the trend for Cross Beta in air particulates for the PVNCS during the fourth quarter of 1985 is similar to those for other reactor sites located west of the lI,lississippi Piver.Table X contains the mean Cross Beta activities by station.i"..ean quarterly and mean annual activities are calculated using all weekly activities except those marked invalid.h!ean activities for each quarter ranged from a low of Q.023+0.006 at Station 21A during the third quarter, to a high of 0.033+0.010 pCi/m at Station 15A in the fourth quarter.Annual mean activities con;pare 3 very well and fall between 0.026+0.006 pCi/m3 (Stations 17A, 21A and 35A)and 0.029+0.007 pCi/m (Station 15A);6!ean activities seen during 1985 are consistent with past results.The average gross beta activity for each quarter is as follows: Ci/m3 Second Quarter 1985 Third Quarter 1985 Fourth C;uarter 1985 0.027+0.005 0.020+0.000 0.030+0.009 Gross Beta levels determined during 1985 are slightly higher than those during 1982, 1983, and 1980.l".o n;an-made Camma-emitting Nuclides were detected in any of the air filter samples collected during 1985.
Tables YI thru XIII show the Cross Alpha activity for each.veek curing 19S5.L"o air particulate samples collected in 1985 had activity above detection limit.The data showed that fewer air filters in 19S5 contained Cross Alpha=ctivity above 0.005 pCi/m3 than in 19SV.
1,.'j.'i=g>,de's,"~%, ir i.~.*,is~'l~>~iaido~.,.q~",.a~~TABLE Yll GROSS BETA IN hlR PARTICEJLATE DATA (pci/m3)1985 Collection Period 05/22/85-05/29/85 05/29/85-06/05/85 06/05/85-06/12/85 06/12/85-06/19/85 06/19/85-06/26/85 06/26/85-07/03/85 0.025+0.002 0.029+0.002 0.026+0.002 0.031+0.002 0.027+0.002 0.031+0.002 0.015+0.002 0.019+0.002 0.021+0.002 0.025+0.002 0.029+0.002 0.02740.002 0.020+0.002 0.020+0.002 0.018+0.002 0.021+0.002 0.029+0.002 0.029+0.002 0.023+0.002 0.029i0.002 0.029 i 0.002 0.031+0.002 0.029 i-0.002 0.039+0.002 0.028+0.002 0.020+0.002 0.041 i 0.002 0.027+0.002 0.028'.002 0.026 i0.002 0.032+0.002 0.030~0.002 0.038<0.002 0.030+0.002 0.029+0.002 0.030+0.002 Station lh Station Oh Station 6A Station 7A Station lOA Station 15A Station 17A 0,015+0.002a 0.018+0.002 0.027+0.002 0.031~0.002 0.025'.002 0.031+0.002 alnvalid sample.
TABLE VII (Cont.)GROSS BETA IN AIR PARTICULATE DATA (pCl/m3)SECOND lJARTER 1985 Collection Period Station 21A 06/12/85-06/19/85 06/19/85-06/26/85 0.028+0.002 0.026~0.002 06/26/85-07/03/85 0.028'.002 05/22/85-05/29/85 0.031+0.002 05/29/85-06/05/85 0.016+0.002 06/05/85-06/12/85 0.026+0.002 Station 29A 0.029+0.002 0.020+0.002 0.025+0.002 0.0 32+0.002 0.027+0.002 0.032E 0.002 Station 35A 0.027+0.002 0.017+0.002 0.028+0.002 0.028+0.002 0.026@0.002 0.033%0.002 Station 00A 0.031+0.002 0.019+0.002 0.028+0.002 0.029+0.002 0.035+0.002 0.036+0.002 Station 00A 0.028+0.002 0.018+0.002 0.029+0.002 0.029~0.002 0.026+0.002 0.032+0.002 Weekly Mean Gross Beta Activities
+Standard Deviation of the Mean 0.029+0.002
,0.018+0.002 0.027+0.002 0.030~0.000 0.028+0.005 0.032+0.003 TABLE Vill GROSS BETA IN AIR PARTlcuLATE DATA (pCI/m)Tl I I R D UA RTER 1985 Collection Period Station IA Station OA Station 6A Station 7A Station 10A Station 15A Station 17A 07/03/85-07/10/85 07/10/85-07/17/85 07/17/85-07/20/85 07/20/85-07/31/85 07/31/85-08/07/85 08/07/85-08/IO/85 08/Iii/85-08/21/85 08/21/85-08/28/85 08/28/85-09/00/85 09/00/85-09/11/85 09/I I/85-09/18/85 09/18/85-09/25/85 09/25/85-10/02/85 0.033+0.002 0.028>>0.002 0.019+0.002 0.022>>0.002 0.022+0.002 0.022>>.0.002 0.025>>0.002 0.025+0.002 0.028+0.002 0.022+0.002 0.020+0.002 0.022>>0.002 0.023+0.002 0.0'3~>>>0.002 0.0 30>>0.002 0.018>>0.002 0.029+0.002 0.02ii+0.002+
0.022 i 0.002 0.026+0.002 0.025+0.002 0.023>>0.002 0.019>>0.002 0.021>>0.002 0.020>>0.00?0.027>>0.002~0.03ii>>0.002 0.030+0.002 0.019>>0.002 0.020+0.002" 0.022+0.002 0.025+0.002 0.025>>0.002 0.027 4 0.002 0.018+0.002 0.023>>0.002 0.025~0.002 0.021>>0.002 0.028+0;002 0.026+0.002 0.016>>0.002 0.023+0.002 0.021+0.002 0.021+0.002 0.026+0.002 0.023+0.002 0.027+0.002 0.020+0.002 0.025>>0.002 0.02ii+0.002 0,022+0.002 0.032>>0.002 0.025+0.002 0.018+0.002 0.022+0.002 0.023+0.002 0.032>>0.002 0.020>>.0.002 0.022>>0.002 0.025>>0.002 0.019+0.002 0.025+0.002 0.025>>-0.002 0.022+0.002 0.032+0.002 0.028+0.002 0.018+0.002 0.022+0.002 0.020+0.002 0.021+0.002 0.025+0.002 0.025>>0.002 0.026>>0.002 0.020+0.002 0.023>>0.002 0.026+0.002 0.022>>0.002 0.035+0.002 0.0 30+0.002 0.019+0.002 0.020+0.002 0.020+0.002 0.023+0.002 0.025+0.002 0.020+0.002 0.020+0.002 0.018>>.0.002 0.025+0.002 0.022+0.002 0.022+0.002
>>Invalid sainple.
TABLE VIII (Cont.)CROSS BETA IN AIR PARTICULATE DATA (pCi/m3)Tl IIRD UARTER 1985 Collection Period Station 21A Station 29A Station 35A Station 00A Station 40A Weekly Mean Gross Beta Activities
+Standard Deviation of the Mean 07/03/85-07/10/85 07/10/85-07/17/85 07/17/85-07/20/$5 07/20/85-G7/31/85 07/31/85-OS/07/85 OS/07/85-Os/10/85 08/10/85-OS/21/85 os/21/85-os/zsls5 08/zs/85-09/00/5 09/00/85-09/II/85 09/11/85-09/IS/85 09/18/85-09/25/85 09/25/85-10/02/85 O.ozs>>O.onz 0.027 IO.OOZ 0.017<<0.002 o.ozz.n.nnz G.021 I 0.002 0 023>>n onz 0.025 I 0.002 0.023+0.G02 0.026<<0.002 0.019+0.002 0.023 I 0.002 0.02:>>O.OG2 O.oznI 0.002 0.031+0.002 0.028<<0.002 0.016>>0.00 0.025<<G.OG2 0.021+0.00?
0.0?0 I 0,.002 0.025 I 0.002 O.G23>>o.onz 0.027 I 0.002 0.021>>0.002 0.021>0.00?'.0?il I O.no 2 G.nz'G.nnz 0.0 36+0.002 0.029>>0.002 0.018>>0.002 0.025>>0.002 0.025>>0.002 0.021+0.002 0.026<<O.n02 0.023>>0.002 0.026 I 0.002 0.021>>0.002 0.023 I o.nnz 0.027 I 0.002 0.0?2<<0.002 0.029+0.002 0.026<<0.002 0.018>>0.002 0.023 I 0.002 0.023>>0.002 0.023<<0.002 0.027+0.002 0.020 0.002 0.025+0.002 0.020<<0.002 0.022 I 0.002 0.025<<0.002 0.023>>0.002 0.0 36+0.002 0.033<<0.002 0.023+0.002 0.010<<0.002 0.020<<0.002 0.027>>0.002 0.027+0.002 0.025+0.002 0.025+0.002 0.019+0.009 0.02S<<0.002 0.023>>0.002 0.022>>0.002 0.032+0.003 0.028+0.002 0.018+0.002 0.022>>0.005 0.023<<0.001 0.023+0.003 0.026>>0.001 0.020<<0.001 0.026+0.001 0.020+0.002 0.020+0.002 0.020+0.001 0.022+0.001~Invalid sample-TABLE IX GROSS BETA JN AIR PARTICULATE DATA (pCI/m3)FOURTH UARTER 1985 Collection Period Station IA Station OA Station 6A Station 7A Station JOA Station 15A Station 17A 10/02/85-10/09/85 10/09/85-10/16/85 JO/J6/85-10/23/85 10/23/85-JO/30/85 10/30/85-I I/06/85 I I/06/85-I I/13/85 J I/13/85-I I/20/85 I I/20/85-11/27/85 11/27/85-12/00/85 12/00/85-12/11/85 12/I I/85-12/18/85 I 2/18/85-12/26/85 12/26/85-01/02/86 0.030+0.002 0.022+0.002
.0.027+0.002 0.030+0.002 0.036+0.002 0.031+0.002 0.0 30+0.002 0.027+0.002 0.0 I 0~0.002 0.031+0.002 0.032+0.002 0.038+0.002 0.050+0.002 0.030+0.002 0.021+0.002 0.025+0.002 0.038+0.002 0.036+0.002 0.029'.002 0.0 30+0.002 0.030+0.002 0.010+0.002 0.029+0.002" 0.030+0.002 0.00 3+0.002 0.05 I+0.003 0.030~0.002 0.019+0.002 0.023+0.002 0.038~0.002 0.030 i 0.002 0.023~0.002 0.027~0.002 0.025+0.002 0.010+0.002 0.027%0.002 0.035+0.002 0.007+0.002 0.057+0.002 0.03 I+0.002 0.020+0.002 0.022+0.002 0.00 2+0.002 0.036+0.002 0.023+0.002 0.028+0.002 0.029+0.002 0.015+0.002 0.032+0.002 0.036+0.002 0.000+0.002 0.055+0.002 0.032+0.002 0.018+0.002 0.020+0;002 0.037+0.002 0.030+0.002 0.027+0.002 0.031+0.002 0.026+0.002 0.011+0.002 0.027'.002 0.037+0.002 0.033+0.002 0.008+0.006 0.030+0.002 0.000+0.002 0.038+0.002 0.026+0.002 0.0 32+0.002 0.025+0.002 0.0 I 3+0.002 0.028+0.002.
0.036+0.002 0.036+0.002 0.0 55+0.002 0.032'+0.002 0.018+0.002 0.022+0.002 0.035+0.002 0.033+0.002 0.020+0.002 0.027+0.002 0.027+0.002 0.010+0.003 0.029+0.002 0.032+0.002 0.033+0.002 0.009+0.002
<<Invalid sample.
TABLE IX (Cont.).1 CROSS BETA IN AIR PARTICULATE DATA (pCi/m3)FOURTH UARTER 1985 Collection Period Station 2IA Station 29A t Station 35A Station 40A Station 44A Weekly humean Cross Beta Activities
+Standard Deviation of the Mean 10/02/85-10/09/85 10/09/85-10/16/85 10/16/85-10/23/85 10/23/85-10/30/85 10/30/85-I I/06/85 II/06/85-IJ/13/85.I I/I 3/85-I I/20/85 11/20/85-Il/27/85 11/27/85-12/04/85 I 2/04/85-12/I I/85 I 2/I I/85-12/18/85 12/18/85-12/26/85 12/26/85-Ol/02/86 0.032~0.002 0.019+0.002 0.024+0.002 0.036~0.002 0.032+0.002 0.029+0.002 0.026+0.002 0.029'.002 0.014+0.002 0.027'-0.002 0.030~0.002 0.038+0.002 0.053+0.002 0.034+0.002+
0.023+0.002 0.024+0.002 0.037+0.002 0.033+0.002 0.023'.002 0.030+0.002 0.0254 0.002 0.014+0.002 0.028'.002 0.039+0.002 0.0 35~0.002 0.040+0.002 0.033+0.002 0.017+0.002 0.022+0.002 0.034+0.002 0.032+0.002 0.021+0.002 0.027+0.002 0.024+0.002 0.010+0.002 0.027+0.002 0.034~0.002 0.0 35~0.002 0.047+0.002 0.034+0.002 0.019+0.002 0.025+0.002 0.039+0.002 0.038+0.002 0.024+0.002 0.031+0.002 0.027+0.002 0.013'.002 0.027~0.002 0.0 37~0.002 0.0 34 i 0.002 0.040 i 0.002 0.032+0.002 0.018+0.002 0.022+0.002 0.034+0.002 0.032+0.002 0.026+0.002 0.020+0.002 0.022'.002 0.010+0.002 0.025'.002 0.027i0.002 0.029~0.002 0.044'.002 0.032+0.001 0.020+0.002 0.024+0.002 0.037+0.003 0.034+0.002 0.026+0.003 0.028+0.003 0.026+0.002 0.013~0.002 0.028+0.002 0.034+0.003 0.037+0.005 0.046+0.013"Invalid sample.
TABLE X GROSS BETA IN AIR PARTICULATE (pCi/m3)STATION SVhlMARY l985 I 47 00 I Mean Gross Beta Activities
+Standard Deviation of the Mean Second Quarter Third Quarter Fourth Quarter Annual Station I A 0.025+0.006 0.020+0.000 0.03 l+0.008 0.027+0.006 Station OA 0.027+0.005 0.025+0.005 0.032+0.010 0.028+0.007 Station 6A 0.030+0.008 0.020+0.005 0.03 I+0.012 0.028+0.008 Station 7A 0.028+0.005 0.023~0.003 0.032+0.0 I 0 0.028+0.006 Station IOA 0.027+0.000 0.020~0.000 0.026+0.009 0.027+0.006 Station I5A 0.029+0.006 0.020+0.000 0.033+0.010 0.029+0.007
~~'I~M TABLE X (Cont.)CROSS BETA 1N AIR PART1CULATE (pCi/m3)STAT1ON
SUMMARY
l985 Mean Cross Beta Activities
+Standard Deviation of the hlean Second Quarter Third t.uarter Fourth Quarter Annual Station l7A O.G26)0.005 0.024i0.004 0.029+0.009 0.026 s 0.006 Station 2lA 0.026+0.005 0.023+0.003 0.030+0.009 0.026+0.006 Station 29A 0.028+0.005 0.024+0.004 O.G29+0.008 0.027+0.QQ6 Station 35A 0.026+0.005
'.025+0.004 0.028~0.009 0.026+0.006 Station 4OA 0.030+0.006 0.024+0.003 0.030t0.008 0.028+Q.006 Station 44A 0.027+0.005 0.025+0.006 0.026>0.008 0.026+0.006 TABLE XI GROSS ALPI IA IN AIR PARTICULATE DATA (pCi/m3)"*" 1985 Collection Period Station IA Station OA Station 6A Station 7A Station 10A Station 15A 05/22/85-05/29/85 05(29/85-06/05/85 06/05/85-06/12/85 06/12/85-06/19/85 06/19/85-06/26/85 06/26/85-07/03/85 Station 17A<<Less than dectection limit;0.005 pCI/m3.
TABLE XI (Cont.)CROSS ALPHA IN AIR PARTICtJLATE DATA (pCi/m3)"*" l985 Collection Period 05/22/85-05/29/85 05/29/85-06/05/85 06/05/85-06/l2/85 06/l2/85-06/l9/85 06/l9/85-06/26/85 06/26/85-07/03/85 Station 21A.Station 29A Station 35A Station rJOA Station 00A Weekly Mean Cross Alpha Activities
+Standard Deviation of the Mean"Less than dectection limit;0.005 pCi/rn-TABLE Xll GROSS ALPHA IN AIR PAICTICULATE DATA (pCI/m3)1985 Collection Period 07/03/85-07/10/85 07/10/85-07/17/85 07/17/85-07/24/85 07/24/85-07/31/85 07/31/85-08/07/85 08/07/85-08/14/85 08/14/85-08/21/85 08/21/85-08/28/85 08/28/85-09/04/85 09/04/85-09/Il/85 09/11/85-09/18/85 09/18/85-09/25/85 09/25/85-10/02/85 Station IA Station 4A Station 6A Station 7A.Station 14A Station 15A Station 17A"Less than dectection limit;0.005 pCI%n."~Invalid sample.
TABLE XII (Cont-)CROSS ALPHA IN AIR PARTIClJLATE DATA (pCi/m3}1985 Collection Period Station 21A Station 29A.Station 35A Station 00A Station 00A Weekly Mean Cross Alpha Activities
+Standard Deviation of the Mean 07/03/85 07/1 0/85 07/17/85 07/20/85 07/31/85 08/07/85 0$/10/85 08/21/85 08/28/85 09/oc/8s 09/11/85 09/18/85 09/25/85-07/lo/85-O7/17/8S-07/20/85-07/31/85-08/07/85-08/Io/85-08/21/85-08/28/85-09/oo/85-09/1 1/85-09/18/85-09/25/85 10/02/85"Less than dectection limit;0.005 pCi/in.<<'Invalid sample.
TABLE XIII GROSS ALPHA IN AIR PARTICULATE DATA (pCJ/m3)1985 Collection Period 10/02/85-I 0/09/85 10/09/85-10/16/85 10/16/85-10/23/85 10/23/85-10/30/85 10/30/85-II/06/85 11/06/85-11/13/85 I I/I 3/85-I I/20/85 JI/20/85-II/27/85 11/27/85-J2/00/85 J2/00/95-I 2/11/85 I 2/JI/85-12/18/85 I 2/18/85-12/26/85 I 2/26/85-01/02/86 Station lh Station OA Station 6A Station 7A Station JOA Station 15A Station 17A<<Less than dectcction limit;0.005 pCi/m3."<<Invalid'sample.
TABLE Xlll (Cont.)GROSS ALPHA lN AIR PARTICULATE DATA (pCi/m3)FOURTH UARTER 1985 Collection Period 10/02/85-10/09/85 10/09/85-10/16/85 10/16/85-10/23/85 10/23/85-10/30/85 10/30/85-I I/06/85 11/06/85-11/13/85 11/13/85-11/20/85 I I/20/85-I I/27/85 IJ/27/85-I 2/00/85 J2/OIj/95-12/11/85 12/11/85-12/IS/85 I 2/IS/85-I 2/26/S5 12/26/85-01/02/86 Station 2IA Station 29A Station 35A Station OOA Station 00A Weekly humean Cross Alpha Activities
+Standard Deviation of the humean<<Less than dectection limit;0.005 pCi/<n3.'invalid sample.
Fjgora 5 GROSS BETA It)AIR PARTICULATES NEEK1Y ACTIVITY-1985 STATION 1A 42 NE~~I t I
.10 Figure 4 GROSS BETA IH AIR PARTICULATES NEEKLY At.TIVITY-1985 STATION 4A C3 Q..05 I-I-u 22%F Ff.'
i J..h~~y~~i g.'g~~~-'g~4)ma,g-.pe~i~ii.w'n~t, wl'.esse~~..~ij(ii'yi.A%;....c,".i.i~'Hiwv Figure 5 GROSS BETA Ill AIR PARTICULATES V/EEKLY ACTfVlTY-1985 STATION 6A.10 I~C3 O...05 I-I-22 Figure 6 GROSS BETA IN AIR PARTICULATES
'ItslEEKLY ACTIVITY-1985 STATION 7A 22 32 a~Lr~~c Figure 7, GROSS BETA IN AIR PARTICULATES NEEKLY ACTIVITY-)985 STATION 14A 32 42 Ftgura 8 GROSS BETA IH AIR PARTICULATES V/EEKLY ACTIVITY-1985 STATION 15A 3'7 42 Figure 9 GROSS BETA It)AIR PARTICUI ATES V/EEKLY ACTIVITY-1985 STATION 17A I CL.05 I-I-u 42 pic'~~
~~~~~~it@$i i.10 Figure 10 GROSS BETA IH AIR PARTICULATES 0/EEKLY ACTIVlTY-1985 STATION 214 I-~u Q..G5 0-l-I-22 Vf EF.K
.10 Flgote 11.GROSS BETA IH AIR PARTICULATES 0/EEKLY ACTIVJTY-1985 STATION 29A I u 0.05 0-I-32 42
~~~I'I e~.10 Figure 12 GROSS BETA IN AIR PARTICULATES V/EEKLY AeTIVITY-1985 STATION 35A
~4 4~~Hs w w=-8 kJ~~x i ri'"e 0~4~.10 Figure 13 GROSS BETA IH AIR PARTICULATES NEEKLY ACTIVITY-'I 985 STATION 40A O..05 0-I-22 I I~I t 32 gpC'4'~~4' I I~,~~~~~4l 4Q~~*~0')4 eu 4J i~'h A+l figure 14 GROSS BETA IN AIR PARTICULATES NEEKLY ACTIVIT'(-1985 STATION 44A (3 Q..05 0-22 32
8.2 Airborne
Radioiodine Samples for airborne radioiodine monitoring are collected concurrently with the air particulate samples.These samples are collected in charcoal cartridges and analyzed for 1-131.As can be seen in Table XIV no radioiodine'samples collected during the second h quarter of 1985 showed observable I-131 activity.Third quarter radioiodine data may be found in Table XV.i~!o samples indicated I-131 activity above the detection limit of 0.007 pCilm3.As can be seen in Table XVI no radioiodine samples collected during the fourth l quarter of 1985 showed, observable I-131 acitivty.
TABLE XIY AIRI3ORHE RADIOIODINE SECOND OIJARTER l985 Collection Period 05/22/85-05/29/85 05/29/85-06/05/85 06/05/85-06/l2/85 06/12/85-06/19/85 06/l9/85-06/2C/85 06/26/85-07/03/85 Station I Station 0 Station 6 Station 7A Station 10A Station l5 Station l7A+Iodine-I 3l activity less than 0.007 pCi/m>.
TABLE XIV (Cont.)AIRBORNE l(ADIOIODINE 1985 Collection Period 05/22/85-05/29/85 05/29/85-06/05/85 06/05/85-06/12/85 06/12/85-'6/19/85 06/19/85-06/26/85 06/26/85-07/03/85 Station 21 Station 29 Station 35 Station 00 Station 00'Iodine-131 activity less than 0.007 pCi/m3.
~,'~.~1 TAmF XV AIRBORNE RADIOIODINE Tl I I RD VARTER 1985 Collection Period 07/03/85-07/10/85 07/10/85-07/17/85 07/17/85-07/20/85 07/20/85-07/31/85 07/31/85-08/07/85 08/07/85-08/IO/85 08/10/85-08/21/85 08/21/85-08/28/85 08/28/85-09/00/85 09/0O/85-09/11/85 09/ll/85-09/18/85 09/18/85-09/25/85 09/25/85-10/02/85 Station I Station 0 Station 6 Station 7A Station IOA Station 15 Station 17A"Iodine-131 activity less than 0.007 pCi/m3."~<<Invalid sample.
TABLE XV (Cont.)AIRBORNE RADIOIODINE TI.IIRD lJARTER 1985 Collection Period 07/03/S5-07/10/85 07/10/85-07/17/85 07/17/85-07/24/85 07/24/85-07/31/85 07/31/85-OS/07/85 OS/O7/SS-OS/14/SS 08/14/85-08/21/85 OS/21/85-08/28/S5 OS/2S/85-09/04/Ss O9/O4/SS-O9/il/SS O9/li/SS-O9/18/SS 09/18/85-09/25/Ss 09/25/85-10/02/Ss Station 21 k Station 29 , Station 35 Station 40 Station 44"Iodine-131 activity less than 0.007 pCi/m.
~='-':w~s=~-..'.L'~'.'tr.i>a.,"rows A TABLE XVI AIRBORNE RAnipipnINE FOURTI I UARTER 1985 Collection Period 10/02/85-10/09/85 10/09/85-10/16/85 10/16/85-10/23/85 10/23/85-10/30/85 10/30/85-11/06/85 II/06/85-II/13/85 11/13/85-11/20/85 I I/20/85-I I/27/85 11/27/85-12/00/85 I2/00/95-12/11/85 12/II/85-12/18/85 12/18/85-12/26/85 12/26/85-01/02/86 Station I Station 0 Station 6 Station 7A Station IOA Station 15'Station 17A<<iodine-13I activity less than 0.007 pCi/in3.""Invalid sample.
TABLE XVI (Cont.)AJRBORr'.E RAnipipnINE FO(JRTJJ l JARTER 1985 Collection Period 10/02/85-10/09/85 10/09/85.-I 0/16/85 JO/16/85-IO/23/85 10/23/85-10/30/85 10/30/85-11/06/85 II/06/85-II/13/85 11/13/85-11/20/85 II/20/85-11/27/85 II/27/85-I2/00/85 12/00/95-12/11/85 12/11/85-12/18/85 12/18/85-12/26/85 12/26/85-Ol/02/86 Station 21 Station 29 Station 35 Station 00 Station 00"Iodine-I31 activity less than 0.007 pCi/m3.
8.3 Thermoluminescent
Dosimetr Thermoluminescent dosimeters were placed in fifty locations ranging from one to forty-five miles from the Palo Verde Nuclear Generating Station.Beginning in 1980 the Panasonic l"lodel 812 Dosimeter replaced all other TLD's in use.The 812 is a multi-element dosimeter combining 2 elements of Lithium Borate and 2 Calcium Sulfate elements.Tables XVII to XIX present the results of the C'uarterly exposures for 1985.Quarterly data obtained from TLD's are graphically presented in Figures 16 to 18.Differences in individual station mean values represent statistical variation more so than actual fluctuations in the background radiation around the Palo Verde Nuclear Gsenerating Station and tend to vary about an approximate mean of 2V mRem/quarter.
Operational data for 1985 compare very closely with pre-o perationa1 data.I is I ,'s I s t s Figure 19 illustrates the mean TLD activity from 1981 through 1985.These values were obtained by averaging all TLD's in the field during the quarter.(The control TLD was not included).
Figure 19 illustrates the mean exposure with high and love standard deviations of the mean for each quarter.
TABLE XVII UARTERLY THERMOLUMINESCENT DOSIMETRY SECOND UARTER 1985 Map Location 9 10 12 13 15 16 17 IS 19 20 21 22 23 20 25 26 Collection Location APS Goodyear, E 30 Office EflE 20 Scott-Libby School E 25, Liberty School E 20, APS Buckeye School ESE 15, Palo Verde SSE 35, APS Gila Bend Sub-station SE 8, Arlington School SSE, Corner of 363rd Ave.and SPP Rd.S5, Corner of 371st Ave.andPPP Rd.SE 5, Corner of 355th Ave.and V.'ard Rd.ESE 5, Corner of 339th Ave.arid Dobbins Rd.E5, Corner of 339th Ave., and B-S Rd.N Ii N Site Boundary I'!NE 2, NNE Site Boundary NE 2, Site Boundary ENE 2, ENE Site Boundary E", E Site Boundary ESE 2, ESE Site Boundary SE 2, SE Site Boundary SSL 2, SSE Site Boundary 5 3, S Site Boundary SSV 3, SS6'ite Boundary i'.', Benchmark at Baseline SW 5, EVard Rd.at 9'eli ISbbb V.'SV', V.'ard Rd.at DF 7'ell 2 Rd.SSUell 21 Cbb2 Total Exposure (m rem)23.0 23.5 23.0 26.0 21.0 29.0 29.0 23.0 30.C 25.5 26.5 26.0 25.5 27.0 25 0 20.0 27.0 2Q,5 0 26.0 27.0 2S.O 24.5 24.5 5'issing"Missing data TABLE XVII (Cont.)UARTERLY THERMOLUMINESCENT DOSIMETRY SECOND UARTER 1985.Map Location 27 28 29 30 31 32 33 30~35 36 37 38 39 00 01 02 05 06 07 08 09 50 Collection Location SW 2, ShV Site Boundary VISW 1, O'ShV Site Boundary 6', 9!Site Boundary O'NW 1, O'NC'ite Boundary I'!5', NN'ite Boundary NNAV 1, NNV!Site Boundary N'6', Yuma Rd., Vi mile 9!of Belmont Rd.NNC', Corner of Belmont Rd.and Van Buren Rd.NNIV 9, Tonopah, Palo Verde lnn Fire Station N 5, Corner of 6'intersburg Rd.and Van Buren Rd.NNE 5, Corner of 363rd Ave.and Van Buren Rd.Corner of 355th Ave.and Yuma Rd.ENE 5, 303rd Ave., Yi mile S of L.Buckeye N 3, Trailer Park at l"'intersburg
%:N5'0, Harquahala Valley School N 8, Ruth Fisher School N 05, Vulture~',ine Rd.School, Wickenburg ENE 35, APS El"irage Office, Sun City ENE 50, APS Deer Valley Office Litchfield Park School Littleton School, Cashion Perryville Hopeville C'linski Rd., 5 mile, PNV!Sector Total Exposure (m rem)27.0 27.0 26.0 27.0 23.0 26.0 29.0 29.0 30.0 26.0 24.0 28.0 24.0 25.0 27.0 lsslng 23.0 7.0 29.0 26.0 20.0 21.0+Missing data TABLE XVIII UARTERLY THERMOLUMINESCENT DOSIMETRY THIRD UARTER 1985 Map Location 5 6 7 8 9 10 II 12 13 IV 15 16 17 18 19 20 21 22 23 20 25 26 Collection Location APS Goodyear, E 30 Office ENE 20 Scott-Libby School E 25, Liberty School E 20, APS Buckeye School ESE 15, Palo Verde SSE 35, APS Gila Bend Sub-station SE 8, Arlington School SSE, Corner of 363rd Ave.and SPP Rd.S5, Corner of 371st Ave.and SPP Rd.SE 5, Corner of 355th Ave.and 6'ard Rd.ESE 5, Corner of 339th Ave.and Dobbins Rd.E5, Corner of 339th Ave., and B-S Rd.N I, N Site Boundary NNE 2,'NNE Site Boundary NE 2, Site Boundary ENE 2, ENE Site Boundary E 2, E Site Boundary ESE 2, ESE Site Boundary SE 2, SE Site Boundary SSE 2, SSE Site Boundary S 3, S Site Boundary SS'iV 3, SSS'ite Boundary I hV 5, Benchmark at Oaseline6','iVard Pd.at V'e!1 18bbb V.'S'6', V'ard Rd.at DF (Veil 2 Rd.SS'iV V'ell 21 Cbb2 Total Expo'sure (mrem)20.0 26.0 25.0 27.0 2 I.O 30.0 3ci 0 26.'3 358 27m i 29.C 27+4 29 0)9'l7 0 2Q 0~800 0 28.0 28.0 30.0 30.0 28.0 25.0 26.0 29.0 TABLE XVIII (Cont.)UARTERLY THERMOLUM INESCENT DOSIMETRY THIRD UARTER 1985 Map Location 27 28 29 30 31 32 33 3Q 35 36 37 38 39 00 01 02 03 05 06 07 08 09 50 Collection Location SC', SW Site Boundary O'ShV 1, WSU'ite Boundary 7/1,'9!Site Boundary O'N%', V!NhV Site Boundary N%', N%'ite Boundary NNEV 1, NNU'ite Boundary NN', Yuma Rd., Yi mile 9!of Belmont Rd.NNV!5, Corner of Belmont Rd.and Van Buren Rd.NNC<9, Tonopah, Palo Verde Inn Fire Station N 5, Corner of 6'intersburg Rd.and Van Buren Rd.NNE 5, Corner of 363rd Ave.and Van Buren Rd.Corner of 355th Ave.and Yuma P.d.ENE 5, 303rd Ave., Yi mile S of L.Buckeye N 3, Trailer Park at 7!intersburg V!NEW 20, Harquahala Valley School l" 8, Ruth Fisher School N 05, Vulture 5!ine Rd.School, 6'ickenburg ENE 35, APS El I'irage Office, Sun City ENE 50, APS Deer Valley Office Litchfield Park School Littleton School, Cashion Perryville Hopev il le Olinski Rd., 5 mile, O'NV.'ector Total Exposure (m rem)29.0 29.0 29.0 29.0 28.0 2S.O 32.0 31.0 30.0 2S.O 30.0 31.0 27.0 27.0 31.0 29.0 31.0 25.0 S.5-25.0 30.0 26.0 25.0 22.0 TABLE XIX UARTERLY THERMOLUMINESCENT DOSIMETRY FOURTH UARTER 1985 Map Location~7 10 12 13 15 16 17 19 20 21 22 23 20 25 26 Collection Location APS Goodyear, E 30 Office ENE 20 Scott-Libby School E 25, Liberty School E 20, APS Buckeye School ESE 15, Palo Verde SSE 35, APS Gila Bend Sub-station SE 8, Arlington School SSE, Corner of 363rd Ave.and SPP Rd.S5, Corner of 371st Ave.and SPP P.d.SE 5, Corner of 355th Ave.and Edward Rd.ESE 5, Corner of 339th Ave.and Dobbins Rd.E5, Corner of 339th Ave., and B-S Rd.N 1, l" Site Boundary NiNE 2, i~!4!E Site Boundary'E 2, Site Boundary ENE 2, EKE Site Boundary E 2, E Site Boundary ESE 2, ESE Site Boundary SE 2, SE Site Bouncary SSE 2, SSE Site Boundary S 3;S Site Boundary SSW 3, SSW Site Boundary W 5, Benchmark at Baseline SS',"..'ard Rd.at 9'ell ISbbb lVSW 5, 9'ard Rd.at DF~5'ell 2 Rd.SS%ell 21 Cbb2 Total Exposure (mrem)23.0 20.2 21.3 25.2 20.6 29.1 gc 3, 24,'25~3 26.0 25.4"6.2 26.9 25.S p 26.2 25.0 27.2 16.3 27.2 2 rov 23.8 24.S 29.2 TABLE XIX (Cont.)UARTERLY THERMOLUMINESCENT DOSIMETRY FOL'RTIE UARTER 19S5 Map Location 27 2S 29 30 31 32 33 30 35 36 37 3S 39 00 Ol 02 03 50 Collection Location S6', SW Site Boundary O'SUI 1, V'S9'ite Boundary V.', U~Site Boundary O'NLK', O'N'P Site Boundary N%', NV,'ite Boundary NNEV 1, NNVl Site Boundary Nnl 5, Yuma Rd., Y~mile 6'f Belmont Rd.NNV!5, Corner of Belmont Pd.and Van Buren Rd.NN~V 9, Tonopah, Palo Verde lnn Fire Station-i<<45, Corner of Pintersburg Rd.and Van Buren Rd.NiNE 5, Corner of 363rd Ave.and Van Buren Rd.Corner of 355th Ave.and Yuma Rd..ENE 5, 303rd Ave., Yi mile S of L.Buckeye N 3, Trailer Park at<<'t'intersburg
'WNU'0, Harquahala Valley School l'!S, Puth Fisher School N 45, Vulture<<:ine Rd.School, V'ickenburg ENE 35, APS El<<.'.irage Office, Sun City ENE 50, APS Deer Valley Office Litchfield School Littleton School, Cashion Perry ville Hopev i lie Olinski Rd., 5 mile, WM".Sector Total Exposure (m rem)29.6 27.6 27.1 2$.7 25.0 27.2 30.3 29.9 33.7 26.7 25.3 29.0 25.7 26.0 27.9 26.5 29.0 23.0 7.5 20.9 30.1 20.1 20.3 21.2 Figure 16 QUARTERLY THERMOLUMIHESCENT DOSIMETRY SECOND QUARTER 1985 30 E LLJ~20 10 10 15 20 25 S<<ATIOB 30 55 40 45 50 Figure 17 QUARTERLY THERMOLUMINESCENT DOSIMETRY THIRD QUARTER 1985 o 20>C 0 5 10 15 20 So S5 IO 45 5O Figure 18 QUARTERLY THERMOLUMIHESCENT DOSIMETRY FOURTH QUARTER 1985 l+++10 15 20 25 STATION 30-55 40 45 50 f g4 411"p'Sf'" i~w~Figure 19 MEAN QUARTERLY THERMOLUMINESCENT DOSIMETRY 1981-i985 Pre-Operational Operational 83 82%f PQ E.I I I 1~IV~~
8A~Ve etation Vegetation samples were collected from five local farms since no comn:ercial companies are located in the area.The leafy vegetation samples collected during 1985 included: mustard greens, cabbage, swiss chard, turnip greens, and lettuce.The citrus samples included grapefruits, and oranges.Table XX presents iodine-131 data for the vegetation samples collected Curing 1985.No observable activity was detected in any of the samples.The results of the gamma spectral analyses for all vegetation samples is presenteC in Tables XXI and XXII.i~lo man-made Gamma emitting nuclides were detected in any of the'samples.
TABLE XX VEGETATION 1985 Collection Location Date Collected Iodine-131 Ci/m (Wet)~Leaf: Cambron Garden Lettuce Cabbage II/Ie/SS Ii/IO/S5<0.02<0.02 A3M Farms Inc.Leafy 11/15/85<0.02 De Shazo Leafy 12/14/85<0.02 Thomas Leafy 12/17/85<o.oz Adams Swiss Chard 06/i~/85<0.02 Citrus: Butler Dair Grapefruits I I/14/85<0.02 Adams Grapefruits Lemons Oranges II/IO/85<</I e/SS<</IO/SS<0.02<0.02<0.02 TABLE XX1 VEGETATION (Leaf)GAMMA SPECTROMETRY l 985 Col lee tion Location Cambron Garden Lettuce Cabbage Ci/m (wet)Date Ba-l00 Co-60 Mn-50 Ru,Rh-l06 Zn-65 Zr,Nb-95 Cs-l37 Cs-l 30 Ce-140 Fe-59 Collected 0.073>>0.063>>0.02l~O.lt>>3>>0.060>>0.066>>0.036>>0.023>>0:12I>>0.02I>>ii/i4/S5 II/14/85 h3M Farms Inc Leafy De Shazo Leafy Thomas Leafy ii/i5/.'5 i 2/i 4/$5 I2/17/85 NONE nETECTE D Adams Swiss Chard"Detection Limit G6/i 0/85 TABLE XXII VEGETATION (Citrus Fruits)CAMhlA SPECTROhIETRY l985 Ci/m(wet)Date Ba-100 Co-60 bin-50 Ru,Rh-l 06 Zn-65 Zr,Nb-95 Cs-I 37,Cs-l 30 Ce.-l 00 Fe-59 Collection Location Collected 0.073>>0.063>>0.02l>>O.le3>>0.060>>0.066" 0.036>>0.029>>0.121" 0.02l>>Butler Dair Grape fruits Adams Gsrape fruits Lemons Oranges"Detection Limit>>/l0/85 I I/I0/85 ii/l0/85>>/l0/85 NONE DETECTED~nnnttn>>
Drinking water samples were taken monthly from Desert Farms,.'.lcArthur Farm, and begining in April, the 6'edgeworth Fa'rm.All of the samples were analyzed for Cross Alpha, Cross Beta, Strontium-90, Tritium and for Camma-emitting nuclides.Results of these analyses are summarized in Tables XXlll and XXIY'I Nine of the samples showed Cross Alpha activity above the detection limit of 1.0 pCi/I.The range of gross alpha activity in Drinking water samples collected during 1985 was from less than 1.0 pCi/I to 3.8+1.6 pCi/I (Desert Farms collected 08/15/85).
Cross Beta activity ranged from less than 2.0 pCi/I to a high of 6.1+1.5 pCi/I I (Desert Farms collected 09/19/85).
Results do not appear to be anomalous and may be attributed to naturally occurring nucliCes present in water (i.e.Potassium-00, etc.).Strontium-90 was detected in none'of the drinking water samples collected during 1985.Tritium results, for all drinking water samples collected during 1985, were less than 1000 pCi/I.In addition, no Gamma-emitting nuclices of man-made origin were detected in any of the samples.
TABLE XXIII DRINKING WATER 1985 Collection Location Date Gross Alpha Collected 1.0>>Gross Beta 2.0>>Ci/I Strontium-90 0.5>>Tf itium 1000>>Desert Farms 06/13/S5a O6/i3/S5b 07/18/85 OS/15/85 09/19/85 10/17/85 il/Ie/85 12/19/85 1.1+0.6 2.0+1.2 3>>>>0.2+0.6 3,Q+Q,5<2.0~<I.O 3.6+1.9<1.0 2.2+1.3 6.1+1.5>>>>5A+0.6<2.0 0.7+0.6 3.8+1.6>>>>0.5+0.6>>>><0.5<0.5'0.5<0.5<0.5<0.5<0.5<Q.5<IOQO<1000<1000<1000<1000<1000<1000<1000'.IcArthur Farm O6/i3/85a 06/13/85b o7/ls/85 os/i5/85 09/19/S5 io/>>/s5 Ii/IO/85 12/19/85<1.0<I.O<1.0<I.O<1.0<1.0<1.0 1.3+I.I 0.0+0.6<2.0<2.0 2.6+0.5<2.0 2.5+0.5<2.0 2.3+0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<1000<1000<1000<1000<1000<1000<1000<1000 Wed eworth O6/i~/85a 06/13/85b o7/is/s5 08/15/S5 09/19/85 IO/17/85 II/I</85 12/19/85<1.0 1.5+1.2<1.0<1.0<1.0 2.1+I.S<1.0<1.0<2.0 2.0+0.9 2.1+0.5 2.3+0.5 2.0+0.7 3.2+I.s<2.0<2.0<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<loco<1000<1000<1000<1000<1000<1000<1000>>Detection Limit>>>>Verified by reanalysis aComposite Sample bCrab Sample TABLE XX1Y BRINKlNG O'ATER GAMktA SPECTROMETRY 1985 Collection Location Desert Farms b1chrtl>ur Farm 1Yet!1;em;or tlr<<Detection Limit aConrposite Sample bGrab Sample Date Collected 06/13/Ssa O6/i3/Ssb 07/is/85 08/is/ss 09/19/85 io/i7/Ss ii/14/:s 12/19/85 06/13/85a 06/13/Ssb 07/1$/ss 08/is/ss 0)/19/S5 io/i7/85 ii/i4/85 12/19/85 06/1 3/8 sb 06/l 4/" sa o7/18/ss os/ls/85 o9/i 9/.s 10/17/85 ii/lrr/SS 12/19/85 Ci/1 Ba-140 Co-60 Mn-54 Ru,Rh-106 Zn-65 Zr,Nb-95 Cs-137 Cs-134 Ce-144 4"'" 2>>10" 16>>10>>2>>10<<18>>NONE DETECTED
8.6 Groundwater
Quarterly groundwater samples were collected from the on-site wells (V.'ell 27ddc and 6'ell 34abb).All groundwater samples were analyzed for Gross Alpha, Ciross Beta, Strontium-90, Tritium anC for Camma-emitting nuclides.Results.obtained from the analysis of the samples is presented in Tables XXV and XXVI.Two groundwater samples collected during l985 exhibited Cross Alpha activity.Gross Alpha activity ranged from less than I.O pCI/I to 2."+I@pCi/I.Gross Beta activity of 2.1+0.5 was detected in one of the groundwater samples collected during 1985 (6'eII 27ddc-08/I5/85).
No groundwater sample collected during I985 had detectable levels of Tritium or Strontium-90.
In addition, no isotopes of interest were.detecteC by gamma spectral analysis of the groundwater samples.
TABLE XXV GROUNDWATER 1985 Collection Location Date Collected Gross Alpha 1.0>>Ci/l Cross beta Strontium-90 Tritium 2.0>>0;5>>1000>>5'e I I 27ddc 08/15/85 II/IO/85 2.2+1.0<<<<<I.O 2.1+0.5<<<<<2.0<0.5<0.5 I GOO<1000 6'el l 30abb 08/15/85 1.9+I.3<<<<<2.0 I I/IO/85<1.0<2.0<0.5<0.5<1000<IOOG<<Detection limit>><<Verified by reanalysis TABLE XXVI CiROljNDWATER GAh1h1A SPLCTROh!ETP Y l9SS Date Collection Location Collected Ci/l Ba-l00 Co-60 Mn-S0 Ru,Rb-l06 Zn-6S Zr,Nb-9S Cs-l37 Cs-l30 Cc 1 00 0" S" 2" lo" l6" lo" 2" lo" IS" (Veil 27ddc os/ls/ss>>/l0/ss 5'cll 30abb os/l s/ss l l/l 0/SS NONE DETECTED I"Detection Limit
8.7 Surface
Water Surface water samples were'introduced into the monitoring program during the third quarter of 1982.Samples from PVi4CS Reservoir and PVNCS Evaporation Pond were collected weekly throughout 1985.These samples were anal:zed for Iodine-131 activity, then composited at the end of each month and analyzed for Gross Alpha, Cross Beta, Strontium-89, Strontium-90, Tritium and Gamma-emitting nuclides.Results of these analyses are presented in Tables..XVII, XXVIII, YXIY, and XXX.Iodine-131 was detected:.".
none of the 1985 surface water samples collected.
Table YXIX presents cata obtained for analyses of Cross Alpha, Gross Beta, Strontium-89, Strontiu-...-90 and Tritium on the monthly composite samples.Cross Alpha activity".'as"etected in two of the monthly composite's one (november) from the PV.';CS Evaporation Pond (3.2+1.6 pCi/1)and one (november) from the P"."i S Reservoir (1.9+ID pGi/I).PVfiGS Reservoir corr."estates demonstrated Cross Beta activities ranging from less th n 2.0 pCi/I t'."..9 0.7 pC i/l (.",'ovember composite).
The composite samples from the PVYGS Evaporation Pond showed Cross Beta activities ranging'rom less than.0 pC'I'I: 12.9+-".0 p(i/I (3une composite).
As can be seen from Table XXIY, none of the monthly composite samples exhibited any observabie activity for STrontium-89, Strontium-90, or Tritium above the detection liinits of I." pCi/I, and IQQQ pCi/I respectively.
Camma Spectral analysis of the monthly composites (PVNCS Reservoir and Evaporation Pond)showed no detectable activity for any of the nuclides of interest.(See Table XXX).
TABLE XXVII SURFACE WATER 1985 Collection Location PVNCS Reservoir+Detection Limit Collection Date 05/30/85 06/06/85 06/13/85 06/20/85 06/27/85 07/oo/ss 07/11/85 o7/Is/85 07/25/S5 os/oi/ss os/os/ss os/is/ss 08/22/85 08/29/85 09/05/85 09/12/Ss o9/i9/ss 09/26/85 10/03/Ss io/Io/ss Io/17/ss Io/20/85 Io/31/85 I I/07/85 ii/io/ss 11/21/85 II/27/85 12/05/85 12/12/Ss 12/19/85 12/26/85 I-I31 (pci/I)0.5+<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<n.s<0 5<0.5 ,<n.s<'3.5 (Jos<0.5<0.5<O.s<0.5<0.5<rJ.5<0.5<0 5<G.s TABLE XXVIII SURFACE WATER 1985 Collection Location PVNGS Evaporation Pond Collection Date 05/30/85 06/06/85 06/13/S5 06/2G/85 06/27/85 07/00/85 07/11/85 07/18/S5 07/25/S5 OS/01/S5 OS/OS/85 OS/15/85 08/22/85 OS/29/85 09/05/85 09/12/85 09/19/85 09/26/85 10/03/85 10/10/85 10/17/85 10/20/85 10/31/S5 11/07/85 11/10/85 Il/21/85 II/27/85 12/05/S5 12/12/S5 12/19/85 12/26/85 1-131 (pCI/I)0.5+<0.5<0.5 (0.5<0.5<0.5<0.5<0.5<0.5<G-5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5 (05<0.5 (0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5+Detection Limit ff 4+%0~qP~1~'8~1g ill K~1l~I t."~~~~~1 TABLE XXIX St)RFACE WATER (Com osite)1985 Collection Location PVNGS Reservoir Com osite Period Viay 3rrne 3uly August Sop te>>rber October Novenrbr r Dr cerrrber Gross Alpha 1.0"<1.0<J.Q<1.0 1.0<1.0<1.0 1.9~1.0 1.0 Cross Beta 2.0" 5.9+0.6 6.6+0.6 7.0+1.0 8.3+0.7 5.rr+0.6 3.0+0.5 10.9+0.7 5:3+0.6 Ci/I Strontium-89 1.0"<1.0<1.0<1.0<1.0<1.0 1.0<1.0<1.0 Strontium-90 0.5"<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5 Tritium 1000"<1000<1000<1000<1000<1000<IQOQ<1000<1000 PVI'!GS Pond J".ay 3une 3rr ly Arrgrrst Septenrbc r October Yovembef 0(cernber<1.0 1.0<1.0 1.0 1.0<I.O 3.2+1.6 I.p 9.1+0.7 12.9+2.0"" 12.0+1.0 10.5+0.7 6.8+0.6 8.3+0.7 6.7+0.6 7.9+0.6<1.0 1.0<1.0 1.0<1.0<1.0<1.0<1.0<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<JPPQ<1000<1000<1000<1000<1000<1000<JOQO'Detection Limit rr'Verified by reanalysis Thl)LE XXX SLRFACE 5'hTER (Com osite)GA Mich SPl'CTROMETR Y l935 Collection Location PVNCIS Reservoir I I PVNGS Pond<<Detection Limit Date Collected May 3une 3uly Aul>>ust September October November December h,lay 3unc 3uly August September Octobrr Noven>bcr December Cill Ba-!00 Co-60 Mn-50 Ru,Rb-l06 Zn-65 Zr,Nb-95 Cs-l37 Cs-130 Ce-l00 6>>5>>2" IO" I6~IO" 2>>IO" IO>>NONE DETECTED Fe-59 3<<
8.8 Milk (Fresh)Fresh milk samples were collected on a monthly basis during 1985 from the following locations:
20 30 5.6.Al Lueck, 3r.Dairy Cordell Baisley Dairy Butler Dairy 3ohn Kerr Dairy Hamstra/I2 (designated operational control location)Paul Skousen Dairy All milk samples were analyzed for iodine-131, Strontium-89, Strontium-90 and Gamma-emitting nuclides.Results of these analyses are presented in Tables XXXI and XXXII.iodine-131 analyses of the milk samples showed no results above the detection limit of 0.5 pCi/l.Strontium-90 analyses of the milk samples revealed no positive results bove the detection limit of 0.5 pCi/l.Results for all milk samples for Strontium-89 analyses were less than the detection lir.".it of 1.0 pCi/l.Gamma-emitting nuclides of interest remain below the level of detection for all milk samples analyzed in 1985.
TABLE XXXI MII K (Fresh)1985 Collection Location 3ohn Kerr Dairy Al Lueck, 3r.Dairy Paul Skousen Dairy Hamstra I/2 Dairy Cordell Baisley Dairy Date Collected 06/10/85 07/19/85 Os/i6/85 09/20/85 io/is/ss li/15/S5 12/20/85 06/10/85 07/19/85 os/16/s5 09/20/85 10/18/S5 ll/15/S5 12/20/85 o6/i~/85 07/19/85 OS/16/S5 09/20/85 10/IS/S5 ii/i5/S5 12/20/85 06/io/85 07/19/85 QS/16/S5 09/20/85 lo/ls/85>>/15/S5 12/20/85 06/I~/85 07/19/85 os/i6/s5 09/20/85 io/is/s5 11/15/85 12/20/8 Iodine-131 0.5+<05<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<05<Oo5<0.5<0.5<0.5<0.5<0.5<0.5<0.5<05<05<0.5<0.5<0.5'0.5<0.5<0.5<0.5 CI/I Strontium-89 0+I.O 1.0 1.0 1.0 1.0 1.0 1,0 I.O 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 I.O I.G I.o I.O 1.0 I.O 1.0 1.0 1.0 1.0 I.'0 1.0 I.Q Strontium-90 0.5+0.5 0.5 0.5 0.5 0.5 0.5 0.5<0'<0.5<0.5<CD 5<0.5<0.5<0'<0.5<0.5<0.5<0'<0.5<0.5<0.5<0 5<0.5<0'<0.5<0,5<0.5<0.5<0.5<0'<0.5<0.5<0.5<0.5<0.5+Detection Limit TABLE XXXI (Continued)
MILK (Fresh)19S5 Collection Location'utler Dairy Date Collected 06/ie/s5 07/19/S5 os/i6/ss 09/20/S5 io/is/s5 li/15/S5 12/20/S5 iodine-131 0.5+<0.5<0.5<0.5<0.5<0.5<0.5<0.5 Ci/I Strontium-89 1.0+<'1.0 1.0<'.0 1.0 1.0 1.0 1.0 Strontium-90 0.5+<0.5<0.5<0.5<0.5<0.5<0.5<0.5+Detection Limit Thl3LE XXX ll MILK 0".RESl 1)CihMMA SPECTROMETRY l985 Ci/i Collection Location Col lee tion Period Ba-i 40 Co-60 Mn-54 Pu,Rh-l06 Zn-65 Zr,Nb-95 Cs-l 37 Cs-l 34 Ce-l44>>>>~$" 2>>IO~l6~IO>>2~IO>>12>>Cordell Baisley Dairy Butler Dairy 3otin Kerr Dairy hl Lueck, 3r.Dairy O6/i4/85 07/i9/85 os/ic/85 09/20/85-io/i8/85 ii/is/85 l2/20/85 o6/i4/8s o7/i9/8s o8/i6/:s 09/20/85 io/i8/85 ii/is/8s l2/20/85 06/i 4/85 o7/i9/85 08/l6/85 09/20/85 io/is/8s ii/is/85 i2/2o/85 o6/i4/8s 07/i9/85 08/i6/85 o9/2o/85 io/i8/85>>/>>/85 i2/20/$5 NONE DETECTED~>>>>>>>>>>>>>>I>>>>>>>>>>a>>>>
TAnLE XXXII (Cont.)MlLK (FRESI I)CAMMA SPECTROl'.IETRY 1985 Ci/I Collection Location Collection Ba-100 Co-60 Mn-50 Ru,Rh-106-Zn-65 Zr,Nb-95 Cs-137 Cs-130 Period-'0" 5" 2" 10>>16>>10" 2" 10" Ce-100 IS>>Paul Skousen Dairy l larnstra I/2 Dairy>>Ibetcction Limit 06/10/85 07/l9/85 08/l6/85 09/20/85.10/18/85>>/I 5/85 12/20/85 06/10/85 07/19/85 OS/l 6/85 09/20/8 5 10/lS/S5 I 1/I 5/85 12/20/85 NONE DETECTED TAIILE XXXIII ENVIRONMENTAL RADIOLOGICAL MONITORINC PROGRAM ANNUAL
SUMMARY
NAME OF FACILITYt PALO VERDE NUCLEAR GENERATING STATION LOCATION OF FACILITVt MARICOVA COIINT Y ARiZONA REPORTINC PEIIIOD: l985 (Ol f RATIONAL)Medium or Pathway sampled (Unit of Measurement)
Type and Total Number of Analyses Performed Lower Limit All Indicator of Detection Locations (LLD)8(ean (I)Range Location with I I ighest Annual Mean Name I)lstancc 4 Direction Mean (I)Range Control Location No.ol nonroutinc Mean (f)Range Repor ted Measurements Air Particulates (pCi/in3)Gross II (380)0.002 Cross n (380)0.005 Y-spec (36)a I-I 3I (38II)0.007 0.027 (380/380)I5A (0.008-0.037) 2 niilcs~i 5o 0.029 (32/32)(0.013-0.055) 0.02S (32/32)0 (0.0 l0-0.057)0 0 I I TLD (mRem)Quarterly (50)N/A 25.8 (l50/I 50)37lst Avc.8 SPP Ihl.32.5 (3/3)7.7 (3/3)5 tniles l80o (30.0-35.0)
(7.0-8.5)Vegetation (pCi/g-wet)
I-I 3l (I 0)0.02 T-spec (IQ)a 0 0~AII samples less than LLD aSee Table Vl for LLD
'I~~f ThfILE XXXlll (Cont.)ENVIRONMENTAL RADIOLOGICAL MONITOIIING PROGRAM ANNUAL SUhlMARY NAME OF FACILITYt I'ALO VERDE NUCLEAR GENEltATING STATION LOCATION OF FACILITY: MARICOPA COI)NTY ARIZONA IIEPORTING PERIODt l985 (OPERATIONAL)
Medium or Pathway sampled (Unit of Measurement)
Type and Total Number of Analyses Performed Lower Limit All Indicator of Detection Locations (I.LD)Mean (I)Range Location with flighest Annual Mean Name Distance h Direction Mean (f)Range Control Location No.of nonroutine Mean (f)Range Reported Measurements Drinl ing Kyater (pCi/l)Gross (24)I.O Gross"(24).2.0 2.i (9/24)(I.I-3.8)3.5 (I5/24)(2.0-6.I)Desert Farms 5 miles 229o Desert Farms 5 mii<<s 229o 2 4 (6/8)(I.l-3.8)4.7 (6/8)(3 4-6.I)Ground Water (pCi/I)Sr-90 (24)l!3 (24)T-spec (24)Gross n(4)Gross E (4)Sr-90 (4)I I 3 (4)T-spec (4)0.5 I,OOO I.O 2.0 I,OOO 2.0 (2/4)(I.9-2.2)2.l (I/4)(2.l)Well 27tldc Onsitt Well 27ddc Onsitc 2.2 (I/2)(2.2)-2.I (I/2)(2.I)0.0 0 0 Surface kyat<<r (pCi/I)I-I 3 I (62)0.0 0~All samples less than LLD aSee Table Vl lor LLD
~\'rk~1, a~M 0 TAIlLE XX XIII (Cont.)ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL
SUMMARY
NAhIE OF FACILITYz PALO Vf RDE NUCLEAR GENERATING STATION LOCATION OF FACILITY: MAltICOPA COUNTY ARIZONA REPORTING PERIOD: 1985 (OPERATIONAL)
Medium or Pathway sampled (Unit of Measuremcnt)
Type and Total Number of Analyses Performed Lower Limit All indicator of Detection Locations (LLD)Mean (I)Itange Location with llighest Annual hlean Name Distance 6 Direction, htean (I)Range Control Location No.of nonroutine Mean (I)Range Reported Measurements Siirlacc Water Composites (pCI/i)Gross n(I6)I.O Gross II(IG)2.G (2/I6)(I.9-3.2)7.9 (I 6/I 6)(3.0-I 2.9)PVNGS Pond Onsitc I VNGS Pond Onsite 3.2 (I/8)(3.2)9.3 (8/8)(G.7-I 2.9)0 0 Sr-89 (iG)Sr-90 (I 6)I I 3 (I 6)y-spec (I 6)l.0 0.5 I,000 0 0 hlill'pCi/I)
I-I 3I (42)Sr-89 (42)Sr-90 (42)y-spec (42)0.5 1.0 0.5 0 0 0~All samples less than LLD aScc Table Vl for LLD I I I I~~
9.0 Miscellaneous
Information No miscellaneous information was obtained for the 1985 Annual Report.N 10.0 References 1.)1981 Annual Report, Palo Verde Nuclear Generating Station's Pre-Operational Radiological Monitoring Program.2.)1982 Annual Report, Palo Verde Nuclear Generating Station's Pre-Operational Radiological Monitoring Program.3.)1983 Annual Report, Palo Verde Nuclear Generating Station's Pre-Operational Monitoring Program.0.)1980 Annual Report,.alo Verde Nuclear Cenerating Station's Pre-Operational Monitroing Program.5.)Palo Verde Nuclear Generating Station's Pre-Operational Radiological Monitoring Program, Summary Report 1979-1985.
6.)Nuclear Regulatory Commission,"Quality Assurance Criteria for Nuclear Power Plants and Fuel Processing Plant", 10 CFR 50, Appendix 3 (1975).7.)Environmental Radiation Data, Quarterly Reports, U.S.Environmental Protection Agency, Office of Radiation Programs.8.)Nuclear Regulatory Commission, Branch Technical Position, Revision 1, 1979.-101-APPENQFX A EPA CROSS CFfECK RESULTS-102-EPA CROSS-CHECK PRQCRAM1985 Date 2/SS Parameter Chromium-51 Cobalt-60 Water EPA Kno~Value Ci/1+3 OS+8.7 20+S.7 CEP Reported Value Ci/filter 3S+7 06+7 32+7 20+3 25+3 20 3 inc-65 Cesium-134 55+S.7 35+S.7 51+3 50+3 55+3 33+2 29+2 32+2 7/S5 Cesium-137 Cobalt-60:inc-65 Ruthenium-106 25+S.7 10.0+5.0~r~Ted e'~J 62.0+5." 23+3 25+3 2S+3 19+2 15+2 16+2 52+5 09+5 QQ+Lt 73+7 70+7 69+7 Cesium-134 Cesium-137 35.0'+5.0 20.0+5e0 2S+3 29+3 26+3 19+2 16+2 10+2-103-EPA CROSS-CHECK PROCRAM l985 Radionuclides in Air Filters'ate 3/85 Parameter Cross Alpha EPA Known Value Ci/I+3 a IQ.Q 3.7 C'Er Reported Value Ci/filter 9+I 10+1 12+1 Cross Beta Strontium-90 36.0+S.7 15.0+2.6 40+0 01+0 39+0 19+2 IS+2 17e 2 Cesium-137 6.0+8.7 7+2 6+2 5+2 EPA CROSS-CHECK PRCCRAM 1985 Date e/S5 Parameter iodine-131 Water EPA Known Value~l-'.5+1.3 CEP Reported Value Ci/filter 6+2 6+2 5+2-105-EPA CROSS-CHECK PROGRAM 1985 Date I/85 5/85 7/85 Parameter Cross Alpha Gross Beta Gross Alpha Gross Beta Gross Alpha Gross Beta Water EPA Known Value Ci/I+3 5.0+5.0 15.0+5.0 12.0+5.0 I I.O+5.0<<+5 8+5 CEP Reported Value Ci/f ilter 6+2 7+7+2 13+2 10+2 16+2 13+2 15+2 IO+2 12+2 13+2 16+2 9+2 8+2<<+2 9+2 13+2 12+2 9/85<</85 Cross Alpha Gross Beta Cross Alpha 0+5 10+5 10+3 9+3<<+3 6+3 5+3 8+3 9+3 8+3 IO+3 Gross Beta 13+5 IS+3~13+3 15+3-106-EPA CROSS-.CI IECK PROGRAM 1985 Date 2/85 e/85 6/85 8/85 Parameter Tritium Water EPA Known Value Ci/I+3 cr 3796+630 3559+630 2016+351 CEP Reported Value Ci/filter 3750+600 3610+600 3500+600 3437+500 3265+500 3301+500 3260+571 3191+576 2906+'05 3893+'85 3904+476 3847+'77-107-APPENDIX B PALO VERDE YUCLEAR GEYERATING STATION LAND tJSE CENSUS l985-108-ANPP PVNGS 1985 LAND USE CENSUS DECEMBER, 1985 7146C/dg
1.0 INTRODUCTION
In accordance with PVNGS Technical Specification 12.2, t'e annual Use.Census within a five mile radius of mid line PVNGS Unit 2 containment was performed during December, 1985 by Ralph B.Ochoa and Tim Hodges.Observations were made in each of the 16 meteorological sectors of the nearest milking animals (cows and goats), nearest residence, and the nearest garden of greater than 500 ft2 producing broad leaf vegetation.
This census was completed by driving the roads within a five mile radius of PVNGS noting the location of the abovementioned items.The results of the Land Use Census are presented in Table 1 and discussed below.In the table, the radial direction and mileage from Unit 2 containment are presented for each location.The radial direction is one of the.16 different compass points.The mileage was estimated from map position from each location.2.0 CENSUS RESULTS 2.1 Nearest Resident Table 1 presents the location of the nearest resident to the PVNGS in each of the 16 meteorological sectors.There were two changes in the nearest resident noted in the 1985 census.These changes were in the NNW and WSW sectors.2.2 Milkin Animals There were no milking animals observed during the 1985 census.No changes to the REHP milk sampling locations were made as a result of this census.2.3 Ve etable Gardens No gardens greater than 500 square feet producing broad leaf vegetation were found during the 1985 Land Use Census.2.4 No changes were made to the REHP as a result of the 1985 Land Use Census.
Table 1 NEAREST RESIDENCE WITHIN FIVE lfILES OF PVNGS December, 1985 Heterological Sector N ESE SE SSE S SSW SW WSW WNW i'NW Radial~Hi1ea e l.50 1.50 2.00 1.75 3.00 3.75 4.00 4.50 4.50 No Residents 2.75 1.75 (new)No Residents No Residents 4.00 2.50 (new) 1 I f~1 I 1 i, l J jl f~~3