ML17299B219

Annual Radiological Environ Operating Rept for 1985.

ML17299B219
Person / Time
Site:	Palo Verde
Issue date:	12/31/1985
From:	ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17299B218	List: ML17299B217 ML17299B219
References
NUDOCS 8604300060
Download: ML17299B219 (122)

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ARIZONA NUCLEAR POWER PROJECT PALO VERDE NUCLEAR GENERATING STATION OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REPORT FOR 1985 86043000b0 8b0423 PDR *DOCK 05000528 R

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CONTENTS Number Title ~Pa e Abstract 1.0 Introduction 2.0 Description of the b,lonitoring Program 3.0 Analytical Procedures 12 0.0 Sample Preparation 5,'.ethods 5.0 Nuclear instrumentation 6.0 Isotopic Detection Limits and Activity Determinations 20 7.0 Quality Control Program S.Q Data Interpretation and Conclusions 9.Q 5,'.iscellaneous Information 101 1Q.O References Appendix A EPA Cross-checl< Results 102 Appendix B 1985 Land Use Census 108

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TABLES Number Title ~Pa e Collection Locations 9 II Collection Schedule 10 III Aliquot Scanned for Detection Limit Calculation and Actual Analysis IV Sample Counting Times 25 Detection Limits by other than Gan;ma Spectrometry 26 VI Detection Limits by Gamma Spectrometry 27 VII Cross Beta in Air Particulate Data (Second Quarter)

VIII Gross Beta in Air Particulate Data (Third Quarter) 30 IX Cross Beta in Air Particulate Data (Fourth Quarter)

Cross Beta in Air Particulate Lata (Station Summary) 33 XI Cross Alpha in Air Particulate Data (Second Quarter) 00 XII Gross Alpha in Air Particulate Data (Third Quarter)

XIII Cross Alpha in Air Particulate Data (Fourth Quarter)

XIV Airborne Padioiodine Data (Second Quarter) 60 XV Airborne Radioiodine Data (Third Quarter) 62 XVI Airborne Radioiodine Data (Fourth Quarter)

XVII Quarterly Thermoluminescent Dosimetry (Second Quarter) 67 XVIII Quarterly Thermoluminescent Dosimetry (Third Quarter) 69 xv C,'varterly Thermoluminescent Dosimetry (Fourth Quarter) 71 XX Vegetation XXI Vegetation (Leafy), Camma Spectrometry 79 XXII Vegetation (Produce R Citrus Fruits), Car .ma Spectrometry SO XXIII Drinking '6,'ater v2

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TABLES (Cont.)

Number Title ~Pa e XXIV Drinking Water, Gamma Spectrometry 83 XXV Croundwater 85 XXVI Groundwater, Gamma Spectrometry 86 XXVII Surface Water, PVNGS Reservoir 89 X X VIII Surface Water, PVNGS Evaporation Pond 90 XXIX Surface Water (Composite)

PVNGS Evaporation Pond and Reservoir 91 XXX Surface Water (Composite), Gamma Spectrometry PVNGS Evaporation Pond and Reservoir 92 XXXI Alilk (Fresh) Ph XXXII AIilk (Fresh), Gamma Spectrometry 90 XXYIII Env ironmenta I Radiological A'onitoring Program-Annual Summary - l985

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FIGURES Number Title ~Pa e I Area Collection Locations - Map 7 2 Site Collection Locations - Map 8 3 Gross Beta in Air Particulate (Station I) 06 Gross Beta in Air Particulate (Station 0) 07 Cross Beta in Air Particulate (Station 6) 08 6 Cross Beta in Air Particulate (Station 7A) Q9 7 Cross Beta in Air Particulate (Station ISA) 50 8 Cross Beta in Air Particulate (Station 15) 51 9 Cross Beta in Air Particulate (Station 17A) 52 10 Cross Beta in Air Particulate (Station 21) 53 11 Gross Beta in Air Particulate (Station 29) 50 12 Cross Beta in Air Particulate (Station 35) 55 13 Gross Beta in Air Particulate (Station 00) 56 10 Cross Beta in Air Particulate (Station 00) 57 15 Gross Beta in Air Particulate (X!ean V.'eekiy Activity) 58 16 t uarterly Them:oluminescent Dosimetry (Second Quarter) 73 17 Quarterly Thermoluminescent Dosimetry (Third Quarter) 70 18 Quarterly Thermoluminescent Dosimetry (Fourth Quarter) 75 19 ihlean Quarterly Thermoluminescent Dosimetry 76

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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.

Analytical results are presented and discussed along with other pertinent information.

Possible trends and anomalous results, as interpreted by CEP are also discussed.

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ARIZONA NUCLEAR PO%'ER PRO3ECT PALO VERDE NUCLEAR GENERATING STATION OPERATIONAL RADIOLOGICALMONITORING 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

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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 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 one half mile north of the old sampling location. I'pproximately 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 1.1.7 1983, fourth quarter - CEP purchased a Berthold (LB770) 10-Channel Low Level Planchet Counting'ystem. This system is capable of

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simultaneously counting l0 planchets for gross alpha. and gross beta

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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.l2).

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 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.

1.1.21 1981, fourth quarter - Sampling for airborne particulate and airborne radioiodine began.

1.1.22 3uly, 198l - The TLD (Thermoluminescent Dosimetry) dose measurement pr'ogram began.

1.1.23 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.

1.1.20 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.

1.1.25 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).

1.1.26 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.

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TABLE I COLLECTION LOCATIONS Sample Location Site /7 Sam leT e Location Descri tion Air E30 APS Coodyear Office Air E20 APS Buckeye Office 6 Air (Control) SSE35 APS Gila Bend Substation 7A Air SE8 Arlington School ISA Air NNE2 Buckeye-Salome P.d. 8'71st Ave.

15 Air NE2 YE Site Boundary 17A Air 351st Ave., 1 mi. S of B-S Rd.

21 Air S3 S Site Boundary 35 Air NNW9 Tonopah, Palo Verde Inn Fire Station 00 Air I'l3 Trailer Park at 9'intersburg Air ENE35 APS El N'!rage Office (Sun City) 06 IVater, Veg. NNW9 A!cArthur's Farm, Tonopah 07 Vegeta tion EI'I E3 Adam's Residence, 355th Avenue b:

Buckeye - Salome Road 08 Water SW5 7,'ell 19bbb - Desert Farms 09 Water ESEO Wedgeworth Residence, 351st Ave. R Dobbins Rd.

50 b,'ilk C'ordell Baisley t.airy, 331st Ave.

Van Buren 51 Milk, Veg. El 1 Butler Fairy, Palo Verde Pd.

Southern 52 Vegetation E15 C'amb ron Farm, Miller Rd.

• Broadway 53 Milk E26 Kerr L a iry, Dean 8 Buckeye Rds.

50 5! Ilk E27 Skousen Dairy, Airport ~~ Dobbins Rds.

55 Milk E28 Al Lueck Dairy 3r., 3ackrabbit Hazen Rds.

56 Milk (Control) E?5 Ham stra L a iry 0 2, N'.c Queen 2 P yan Rd s.

Water Cnsi te 9'e II 2?ddc 58 Water Cnsite ~

9'ell 30abb 59 Surface Water ~ Onsite PVNCS Evaporation Pond 60 Surface Water Onsite PVYCS Reservoir 61 Vegetation (Control) E80 Cooley Farm, A'cQueen 8: Cuadalupe Road 62 Vegetation (Control) E60 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 Air Airborne Domestic Fresh Drinking Suf face Collection Site Particulates Radioiodine Meats Milk ~Ve etatton Ground at r Water lpga ter iII, APS Goodyear Office il4, APS Buckeye Office W if6, APS Gila Dend Substation Lu II7A, Arlington School II I4A, Buckeye-Salome Rd.

h 37lst Ave. W 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 W 840, Trailer Park at Wintcrsburg W II44, APS El hlirage Oflice W I/46, htcArthur's Farm hl II47f Adam's Residence AA II48, Desert Farms hl II49, Wedgeworth Residence hl f150, Cordell Daisley Dairy Ii>l, Dutler Dairy ht II52, Cambron Farm ii53, Kerr Dairy M II54, Skousen Dairy hl III', Al Lueck, 3r. Dairy hl

ThOLE II (Cont.)

f985 COLLECTION SCl IEDlILE Air Airborne Domestic Fresh Drinking Surface Collection Site Particulates Radioiodine Meats Milk ~Ve elation Craunderaier Water  %'ater II 56, Ilanistra II2 Iaairy 857, Well 27ddc 1158, Well 30abb 859 PVNGS I;v )pofation Pond W Il60, PVN(iS fleshy rvuir IIGI, Cooley Farm AA II62, A3M I'an<<s, Inc. AA 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.

The dry sample is ground to a fine powder anC homogenized.

5. 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 Efficienc 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.

6t = 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:

Activity as pCi per units sample mass or volume.

Sample count rate in counts per minute.

Background counts per minute.,

V Sample volume or mass analyzed.

Counter efficiency as cpm/dpm.

2.22 Numerical constant to convert disintegrations per minute to picocuries.

(e - A t) Decay factor to correct the activity to time of collection.

/

Counting time in minutes.

1.96 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 LIMITCALCULATION AND ACTUAL ANALYSIS Sam leT e Air Particulates 265 m3 265 m3 265 m3 Airborne Radioiodine 265 m3 Domestic Meats (Beef) 500 g Fresh Milk l000 mls 2000 mls 2000 mls 2000 mls Vegetation (Citrus Fruits) 500 g Vegeta t ion (Lea fy) 500 g 100 g Groundwater 1000 mls. 1000 mls 1000 mls 1000 mls 3ml Drinking Water 1000 mls 1000 mls 1000 mls 1000 mls 3 ml Surface Water 1000 mls 1000 mls 1000 mls 1000 mls 1000 mls 1000 mls 3 ml

I I I ee I 'I ~ ee ee ssveewa News eee ~ cone ~ ~ ~ )

TABLE IV SAMPLE COUNTING TIMES Gamma Sam leT e Gross Al ha Gross Beta ~Sec. Iodino-13i Strontium-89 Strontium-90 Tritium Air Particulates 100 min 100 min 8 hrs Airborne Radioiodine 8 hrs+

Domestic Meats (Beef) 8 hrs Fresh Milk S hrs 100 min 100 min 100 min Vegetation (Citrus Fruits) 8 hrs Vegetation (Leafy) 8 hrs 100 min Groundwater 100 min 100 nein 8 hrs 100 min 500 min Drinking EVater 100 8>>i>> 100 rni>> 8 hrs 100 min 500 min Surface EVa ter 100 noah> 100 mi>> ~

8 hrs 100 min 100 min 100 min 500 min

+Alkaline Leach Method Counted for 100 wins

TABLE V DETECTION Llh11TS GY OTHER TI-lAN Ghhlh]A SPECTROhIETRY Sam le T Strontium-90 Tritium Air Particulates 0.005 pCi/m3 0.002 pCi/m3 Airborne Radioiodine 0.007 pCI/m3+ +

Fresh Milk O.'5 pCI/I l.o pCi/I 0.5 pCi/I Vegetation (Leafy) 0.02 pCI/g>>

Groundwater l pCi/I 2 pCi/I 0.5 pCi/I IOOO pci/I Drinking Water I pCi/I 2 pCi/I. 0.5 pCi/I I 000 pCi/I Surface Water I pCi/I 2 pCi/I 0.5 pCi/I 1.0 pCi/I 0.5 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 Sensitivity pCI/I+

Groundwater, Sensitivity Sensitivity Drinking Water Sensitivity pCi/m3 Energy pCI/gm+ and pCI/I+ Air MeV Isoto e Ve etation Surface Water Fresh Milk Particulate 0.130 Cerium-100 0.121 IS Io 0.005 0.537 Barium-100 0.075 0.030 0.605 Cesium-130 0.029 10 10 0.023 0.622 PU ~ Rh-106 0.103 2 2 0.001 0.662 Cesium-137 0.056 2 2 0.001 0.?65 Zr, Nb-95 0.066 10 0.026 O.S35 b'anganese-50 0.021 / 2 O.COI 1.095 Iron-59 0.021 3 3 O.OO6 1.115 Zinc-65 0.060 16 16 0.005 1.173 Cobalt-60 0.063 5 5 0.019 1.596 Lanthanum-100 0.4 65 15 15 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 6 Power interupted during sampling period 08/07/85 Flow calibration failed 08/07/85 6 Flow calibration and redline criteria not available 09/18/85 29A Numerous insects on air particulate filter 10/02/85 0A Heavy dirt on air particulate filter Fourth uarter 1985 Date Collected Site II Reason lo/o9/ss 29A Insects on particulate filter Io/16/ss 15 5.'talfunctioning sampler Io/23/ss 15 Valfunctioning sampler 12/11/85 OA ,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 3 at Station 15A in the fourth quarter. Annual mean activities con;pare 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 0.027 + 0.005 Third Quarter 1985 0.020 + 0.000 Fourth C;uarter 1985 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 Station lh Station Oh Station 6A Station 7A Station lOA Station 15A Station 17A 05/22/85 - 05/29/85 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+0.002a 05/29/85 - 06/05/85 0.015+0.002 0.019+0.002 0.021+0.002 0.020+0.002 0.018+0.002 0.021+0.002 0.018+0.002 06/05/85 - 06/12/85 0.025+0.002 0.029+0.002 0.02740.002 0.020+0.002 0.029+0.002 0.029+0.002 0.027+0.002 06/12/85 - 06/19/85 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 0.031 ~0.002 06/19/85 - 06/26/85 0.028+0.002 0.020+0.002 0.041 i 0.002 0.027+0.002 0.028'.002 0.026 i0.002 0.025'.002 06/26/85 - 07/03/85 0.032+0.002 0.030 ~0.002 0.038<0.002 0.030+0.002 0.029+0.002 0.030+0.002 0.031+0.002 alnvalid sample.

TABLE VII (Cont.)

GROSS BETA IN AIR PARTICULATE DATA (pCl/m3)

SECOND lJARTER 1985 Weekly Mean Gross Beta Activities

+ Standard Deviation Collection Period Station 21A Station 29A Station 35A Station 00A Station 00A of the Mean 05/22/85 - 05/29/85 0.031+0.002 0.029+0.002 0.027+0.002 0.031+0.002 0.028+0.002 0.029+0.002 05/29/85 - 06/05/85 0.016+0.002 0.020+0.002 0.017+0.002 0.019+0.002 0.018+0.002 ,0.018+0.002 06/05/85 - 06/12/85 0.026+0.002 0.025+0.002 0.028+0.002 0.028+0.002 0.029+0.002 0.027+0.002 06/12/85 - 06/19/85 0.028+0.002 0.0 32+0.002 0.028+0.002 0.029+0.002 0.029 ~0.002 0.030~0.000 06/19/85 - 06/26/85 0.026~ 0.002 0.027+0.002 0.026@0.002 0.035+0.002 0.026+0.002 0.028+0.005 06/26/85 07/03/85 0.028'.002 0.032E 0.002 0.033%0.002 0.036+0.002 0.032+0.002 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 0.033+0.002 0.0'3~> >> 0.002 0.03ii >> 0.002 0.028+0;002 0.032>> 0.002 0.032+0.002 0.035+0.002 07/10/85 - 07/17/85 0.028>> 0.002 0.0 30>> 0.002 0.030+0.002 0.026+0.002 0.025+0.002 0.028+0.002 0.0 30+0.002 07/17/85 - 07/20/85 0.019+0.002 0.018>> 0.002 0.019>> 0.002 0.016>> 0.002 0.018+0.002 0.018+0.002 0.019+0.002 07/20/85 - 07/31/85 0.022>> 0.002 0.029+0.002 0.023+0.002 0.022+0.002 0.022+ 0.002 0.020+0.002 07/31/85 - 08/07/85 0.022+0.002 0.02ii+0.002+ 0.020+0.002" 0.021+0.002 0.023+0.002 0.020+0.002 0.020+0.002 08/07/85 - 08/IO/85 0.022>>.0.002 0.022 i 0.002 0.022+0.002 0.021+0.002 0.032>> 0.002 0.021+0.002 0.023+0.002 08/Iii/85 - 08/21/85 0.025>> 0.002 0.026+0.002 0.025+0.002 0.026+0.002 0.020>>.0.002 0.025+ 0.002 0.025+0.002 08/21/85 - 08/28/85 0.025+0.002 0.025+0.002 0.025>> 0.002 0.023+0.002 0.022>> 0.002 0.025>> 0.002 0.020+0.002 08/28/85 - 09/00/85 0.028+0.002 0.023>> 0.002 0.027 4 0.002 0.027+0.002 0.025>> 0.002 0.026>> 0.002 0.020+ 0.002 09/00/85 - 09/11/85 0.022+0.002 0.019>> 0.002 0.018+0.002 0.020+0.002 0.019+0.002 0.020+0.002 0.018>>.0.002 09/I I/85 - 09/18/85 0.020+0.002 0.021>> 0.002 0.023>> 0.002 0.025>> 0.002 0.025+0.002 0.023>> 0.002 0.025+0.002 09/18/85 - 09/25/85 0.022>> 0.002 0.020>> 0.00? 0.025 ~0.002 0.02ii+0.002 0.025>>-0.002 0.026+0.002 0.022+0.002 09/25/85 - 10/02/85 0.023+0.002 0.027>> 0.002 ~ 0.021>> 0.002 0,022+0.002 0.022+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 Weekly Mean Gross Beta Activities

+ Standard Deviation Collection Period Station 21A Station 29A Station 35A Station 00A Station 40A of the Mean 07/03/85 - 07/10/85 O.ozs>> O.onz 0.031+0.002 0.0 36+ 0.002 0.029+0.002 0.0 36+0.002 0.032+0.003 07/10/85 - 07/17/85 0.027 IO.OOZ 0.028 <<0.002 0.029>> 0.002 0.026 <<0.002 0.033 <<0.002 0.028+0.002 07/17/85 - 07/20/$ 5 0.017 <<0.002 0.016>> 0.00 0.018>> 0.002 0.018>>0.002 0.023+0.002 0.018+0.002 07/20/85 - G7/31/85 o.ozz.n.nnz 0.025 <<G.OG2 0.025>> 0.002 0.023 I 0.002 0.010 <<0.002 0.022>> 0.005 07/31/85 - OS/07/85 G.021 I 0.002 0.021+0.00? 0.025>> 0.002 0.023>> 0.002 0.020 <<0.002 0.023 <<0.001 OS/07/85 - Os/10/85 0 023>>n onz 0.0?0 I 0,.002 0.021+0.002 0.023<<0.002 0.027>> 0.002 0.023+0.003 08/10/85 - OS/21/85 0.025 I 0.002 0.025 I 0.002 0.026 <<O.n02 0.027+ 0.002 0.027+0.002 0.026>> 0.001 os/21 /85 - os/zsls5 0.023+0.G02 O.G23>>o.onz 0.023>> 0.002 0.020 0.002 0.025+0.002 0.020 <<0.001 08/zs/85 09/00/ 5 0.026 <<0.002 0.027 I 0.002 0.026 I 0.002 0.025+0.002 0.025+0.002 0.026+ 0.001 09/00/85 - 09/II/85 0.019+0.002 0.021>> 0.002 0.021>> 0.002 0.020 <<0.002 0.019+ 0.009 0.020+0.002 09/11/85 - 09/IS/85 0.023 I 0.002 0.021 >0.00? 0.023 I o.nnz 0.022 I 0.002 0.02S <<0.002 0.020+ 0.002 09/18/85 - 09/25/85 0.02:>> O.OG2 I O.no 2 '.0?il 0.027 I 0.002 0.025<<0.002 0.023>>0.002 0.020+0.001 09/25/85 - 10/02/85 O.oznI 0.002 G.nz'G.nnz 0.0? 2 <<0.002 0.023>> 0.002 0.022>>0.002 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 0.030+0.002 0.030+0.002 0.030~0.002 0.03 I+0.002 0.032+0.002 0.030+0.002 0.032'+0.002 10/09/85 - 10/16/85 0.022+0.002 0.021+0.002 0.019+0.002 0.020+0.002 0.018+0.002 0.018+0.002 JO/J6/85 - 10/23/85 .0.027+0.002 0.025+0.002 0.023+0.002 0.022+0.002 0.020+0;002 0.022+0.002 10/23/85 - JO/30/85 0.030+0.002 0.038+0.002 0.038 ~0.002 0.00 2+0.002 0.037+0.002 0.000+0.002 0.035+0.002 10/30/85 - I I /06/85 0.036+0.002 0.036+0.002 i 0.030 0.002 0.036+0.002 0.030+0.002 0.038+0.002 0.033+0.002 I I/06/85 I I/13/85 0.031+0.002 0.029'.002 0.023~0.002 0.023+0.002 0.027+0.002 0.026+0.002 0.020+0.002 J I /13/85 - I I/20/85 0.0 30+0.002 0.0 30+0.002 0.027~ 0.002 0.028+0.002 0.031+0.002 0.0 32+0.002 0.027+0.002 I I /20/85 11/27/85 0.027+0.002 0.030+0.002 0.025+0.002 0.029+0.002 0.026+0.002 0.025+ 0.002 0.027+0.002 11/27/85 - 12/00/85 0.0 I 0~0.002 0.010+ 0.002 0.010+0.002 0.015+0.002 0.011+0.002 0.0 I 3+0.002 0.010+0.003 12/00/85 - 12/11/85 0.031+0.002 0.029+0.002" 0.027 %0.002 0.032+0.002 0.027'.002 0.028+0.002. 0.029+0.002 12/I I /85 - 12/18/85 0.032+0.002 0.030+0.002 0.035+0.002 0.036+0.002 0.037+0.002 0.036+0.002 0.032+0.002 I 2/18/85 - 12/26/85 0.038+0.002 0.00 3+0.002 0.007+ 0.002 0.000+0.002 0.033+0.002 0.036+0.002 0.033+0.002 12/26/85 - 01/02/86 0.050+ 0.002 0.05 I+0.003 0.057+0.002 0.055+0.002 0.008+0.006 0.0 55+ 0.002 0.009+0.002

<<Invalid sample.

TABLE IX (Cont.).

1 CROSS BETA IN AIR PARTICULATE DATA (pCi/m3)

FOURTH UARTER 1985 Weekly humean Cross Beta Activities t + Standard Deviation Collection Period Station 2IA Station 29A Station 35A Station 40A Station 44A of the Mean 10/02/85 10/09/85 0.032~0.002 0.034+0.002+ 0.033+0.002 0.034+0.002 0.032+0.002 0.032+0.001 10/09/85 - 10/16/85 0.019+0.002 0.023+0.002 0.017+0.002 0.019+0.002 0.018+0.002 0.020+0.002 10/16/85 - 10/23/85 0.024+0.002 0.024+0.002 0.022+0.002 0.025+0.002 0.022+0.002 0.024+0.002 10/23/85 - 10/30/85 0.036~0.002 0.037+0.002 0.034+0.002 0.039+0.002 0.034+0.002 0.037+0.003 10/30/85 - I I/06/85 0.032+0.002 0.033+0.002 0.032+0.002 0.038+0.002 0.032+0.002 0.034+0.002 II/06/85 - IJ/13/85 0.029+0.002 0.023'.002 0.021+0.002 0.024+0.002 0.026+0.002 0.026+0.003

.I I/I 3/85 - I I/20/85 0.026+0.002 0.030+0.002 0.027+ 0.002 0.031+0.002 0.020+0.002 0.028+0.003 11/20/85 - Il/27/85 0.029'.002 0.0254 0.002 0.024+0.002 0.027+ 0.002 0.022'.002 0.026+0.002 11/27/85 - 12/04/85 0.014+0.002 0.014+0.002 0.010+0.002 0.013'.002 0.010+0.002 0.013~0.002 I 2/04/85 - 12/I I/85 0.027'-0.002 0.028'.002 0.027+0.002 0.027 ~ 0.002 0.025'.002 0.028+0.002 I 2/I I/85 - 12/18/85 0.030 ~0.002 0.039+0.002 0.034~0.002 0.0 37 ~ 0.002 0.027i0.002 0.034+0.003 12/18/85 - 12/26/85 0.038+0.002 0.0 35 ~ 0.002 0.0 35~ 0.002 0.0 34 i 0.002 0.029 ~ 0.002 0.037+0.005 12/26/85 - Ol/02/86 0.053+0.002 0.040+0.002 0.047+0.002 0.040 i 0.002 0.044'.002 0.046+0.013 "Invalid sample.

TABLE X GROSS BETA IN AIR PARTICULATE (pCi/m3)

STATION SVhlMARY l985 Mean Gross Beta Activities +

Standard Deviation of the Mean Station I A Station OA Station 6A Station 7A Station IOA Station I5A Second Quarter 0.025+0.006 0.027+0.005 0.030+0.008 0.028+0.005 0.027+0.000 0.029+0.006 Third Quarter 0.020+0.000 0.025+0.005 0.020+0.005 0.023~0.003 0.020 ~0.000 0.020+0.000 Fourth Quarter 0.03 l+0.008 0.032+0.010 0.03 I +0.012 0.032+0.0 I 0 0.026+0.009 0.033+0.010 I

Annual 0.027+0.006 0.028+0.007 0.028+0.008 0.028+0.006 0.027+0.006 0.029+0.007 47 00 I

I

~~ '

~ M

TABLE X (Cont.)

CROSS BETA 1N AIR PART1CULATE (pCi/m3)

STAT1ON

SUMMARY

l985 Mean Cross Beta Activities +

Standard Deviation of the hlean Station l7A Station 2lA Station 29A Station 35A Station 4OA Station 44A Second Quarter O.G26 ) 0.005 0.026+0.005 0.028+0.005 0.026+0.005 0.030+0.006 0.027+0.005 Third t.uarter 0.024i0.004 0.023+0.003 0.024+0.004 '.025+0.004 0.024+0.003 0.025+0.006 Fourth Quarter 0.029+0.009 0.030+0.009 O.G29+0.008 0.028~ 0.009 0.030t0.008 0.026> 0.008 Annual 0.026 s 0.006 0.026+0.006 0.027+ 0.QQ6 0.026+0.006 0.028+ Q.006 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 Station 17A 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

<<Less than dectection limit; 0.005 pCI/m3.

TABLE XI (Cont.)

CROSS ALPHA IN AIR PARTICtJLATE DATA (pCi/m3) l985 Weekly Mean Cross Alpha Activities

+ Standard Deviation Collection Period Station 21A . Station 29A Station 35A Station rJOA Station 00A of the Mean 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 "Less than dectection limit; 0.005 pCi/rn-

TABLE Xll GROSS ALPHA IN AIR PAICTICULATE DATA (pCI/m3) 1985 Collection Period Station IA Station 4A Station 6A Station 7A . Station 14A Station 15A Station 17A 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 "Less than dectection limit; 0.005 pCI%n .

"~Invalid sample.

TABLE XII (Cont-)

CROSS ALPHA IN AIR PARTIClJLATE DATA (pCi/m3}

1985 Weekly Mean Cross Alpha Activities

+ Standard Deviation Collection Period Station 21A Station 29A . Station 35A Station 00A Station 00A of the Mean 07/03/85 07/lo/85 07/1 0/85 - O7/17/8S 07/17/85 - 07/20/85 07/20/85 - 07/31/85 07/31/85 - 08/07/85 08/07/85 - 08/Io/85 0$ /10/85 - 08/21/85 08/21/85 - 08/28/85 08/28/85 - 09/oo/85 09/oc/8s 09/1 1/85 09/11/85 - 09/18/85 09/18/85 - 09/25/85 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 Station lh Station OA Station 6A Station 7A Station JOA Station 15A Station 17A 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/I3/85 - 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

<<Less than dectcction limit; 0.005 pCi/m3.

" <<Invalid'sample.

TABLE Xlll(Cont.)

GROSS ALPHA lN AIR PARTICULATE DATA (pCi/m3)

FOURTH UARTER 1985 Weekly humean Cross Alpha Activities

+ Standard Deviation Collection Period Station 2IA Station 29A Station 35A Station OOA Station 00A of the humean 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

<<Less than dectection limit; 0.005 pCi/<n3.

'invalid sample.

Fjgora 5 GROSS BETA It) AIR PARTICULATES NEEK1Y ACTIVITY1985 STATION 1A 42 NE~~ I I t

Figure 4 GROSS BETA IH AIR PARTICULATES NEEKLY At.TIVITY1985 STATION 4A

.10 C3 Q.

.05 I-I-

u 22

%F Ff.'

..h ~~

y ~ ~ i g. 'g~ ~ ~ -' g ~ 4 )ma,g-. pe ~ ~

i i ii.J w' n ~t, wl'.esse~ ~ ..~ij(i i' yi.A%;....c, ".i.i~'Hiwv Figure 5 GROSS BETA Ill AIR PARTICULATES V/EEKLY ACTfVlTY1985 STATION 6A

.10 I

~

C3 O.

..05 I

I-22

Figure 6 GROSS BETA IN AIR PARTICULATES

'ItslEEKLY ACTIVITY1985 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 ACTIVITY1985 STATION 15A 3'7 42

Figure 9 GROSS BETA It) AIR PARTICUI ATES V/EEKLY ACTIVITY1985 STATION 17A I

CL

.05 I

I u

42 pic' ~ ~

~ ~ ~ ~ ~ ~it@

$ i i

Figure 10 GROSS BETA IH AIR PARTICULATES 0/EEKLY ACTIVlTY1985 STATION 214

.10 I-~

uQ.

.G5 0-l I

22 VfEF.K

Flgote 11

.GROSS BETA IH AIR PARTICULATES 0/EEKLY ACTIVJTY1985 STATION 29A

.10 I

u0

.05 0-I 32 42

e~

'I I

~ ~ ~

Figure 12 GROSS BETA IN AIR PARTICULATES V/EEKLY AeTIVITY-1985 STATION 35A

.10

~ 4 4 ~ ~ Hs w w =-8 kJ ~ ~ x i ri' "e 0 ~ 4 ~

Figure 13 GROSS BETA IH AIR PARTICULATES NEEKLY ACTIVITY'I 985 STATION 40A

.10 O.

.05 0-I 22 32 I

I ~ I t gpC'4'

~ ~ 4'

~, ~ ~ ~ ~ ~ 4l 4Q ~ ~ * ~ 0')4 eu 4J i ~ 'h A+l I I 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 Station I Station 0 Station 6 Station 7A Station 10A Station l5 Station l7A 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

+Iodine-I 3l activity less than 0.007 pCi/m>.

TABLE XIV (Cont.)

AIRBORNE l(ADIOIODINE 1985 Collection Period Station 21 Station 29 Station 35 Station 00 Station 00 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

'Iodine-131 activity less than 0.007 pCi/m3.

~, ' ~ . ~1 TAmF XV AIRBORNE RADIOIODINE Tl I I RD VARTER 1985 Collection Period Station I Station 0 Station 6 Station 7A Station IOA Station 15 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 08/10/85 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 "Iodine-131 activity less than 0.007 pCi/m3. "

~ <<Invalid sample.

TABLE XV (Cont.)

AIRBORNE RADIOIODINE TI.IIRD lJARTER 1985 Collection Period Station 21 Station 29 , Station 35 Station 40 Station 44 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 k O9/O4/SS - O9/il/SS O9/li/SS - O9/18/SS 09/18/85 - 09/25/Ss 09/25/85 - 10/02/Ss "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 Station I Station 0 Station 6 Station 7A Station IOA Station 15 'Station 17A 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

<<iodine-13I activity less than 0.007 pCi/in3.

""Invalid sample.

TABLE XVI (Cont.)

AJRBORr'. E RAnipipnINE FO(JRTJJ l JARTER 1985 Collection Period Station 21 Station 29 Station 35 Station 00 Station 00 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 "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 Figure 19 illustrates the mean TLD activity from 1981 through 1985. These is I

,'s values were obtained by averaging all TLD's in the field during the quarter. (The I control TLD was not included). Figure 19 illustrates the mean exposure with high and love standard deviations of the mean for each quarter.

s t

s

TABLE XVII UARTERLY THERMOLUMINESCENT DOSIMETRY SECOND UARTER 1985 Total Map Exposure Location Collection Location (m rem)

APS Goodyear, E 30 Office 23.0 EflE 20 Scott-Libby School 23.5 E 25, Liberty School 23.0 E 20, APS Buckeye School 26.0 ESE 15, Palo Verde 21.0 SSE 35, APS Gila Bend Sub-station 29.0 SE 8, Arlington School 29.0 SSE, Corner of 363rd Ave. and SPP Rd. 23.0 9 S5, Corner of 371st Ave. andPPP Rd. 30.C 10 SE 5, Corner of 355th Ave. and V.'ard Rd. 25.5 ESE 5, Corner of 339th Ave. arid Dobbins Rd. 26.5 12 E5, Corner of 339th Ave., and B-S Rd. 26.0 13 N Ii N Site Boundary 25.5 I'!NE 2, NNE Site Boundary 27.0 15 NE 2, Site Boundary 25 0 16 ENE 2, ENE Site Boundary 20.0 17 E ", E Site Boundary 27.0 IS ESE 2, ESE Site Boundary 2Q,5 19 SE 2, SE Site Boundary 0 20 SSL 2, SSE Site Boundary 26.0 21 5 3, S Site Boundary 27.0 22 SSV 3, SS6'ite Boundary 2S.O 23 i'.', Benchmark at Baseline 24.5 20 SW 5, EVard Rd. at 9'eli ISbbb 24.5 25 V.'SV', V.'ard Rd. at DF 7'ell 2 Rd.

26 SSUell 21 Cbb2 5'issing "Missing data TABLE XVII (Cont.)

UARTERLY THERMOLUMINESCENT DOSIMETRY SECOND UARTER 1985 Total

. Map Exposure Location Collection Location (m rem) 27 SW 2, ShV Site Boundary 27.0 28 VISW 1, O'ShV Site Boundary 27.0 29 6', 9! Site Boundary 26.0 30 O'NW 1, O'NC'ite Boundary 27.0 31 I'!5', NN'ite Boundary 23.0 32 NNAV 1, NNV! Site Boundary 26.0 33 N'6', Yuma Rd., Vi mile 9! of Belmont Rd. 29.0 30 NNC', Corner of Belmont Rd. and Van Buren Rd. 29.0

~ 35 NNIV 9, Tonopah, Palo Verde lnn Fire Station 30.0 36 N 5, Corner of 6'intersburg Rd. and Van Buren Rd. 26.0 37 NNE 5, Corner of 363rd Ave. and Van Buren Rd. 24.0 38 Corner of 355th Ave. and Yuma Rd. 28.0 39 ENE 5, 303rd Ave., Yi mile S of L. Buckeye 24.0 00 N 3, Trailer Park at l"'intersburg 25.0 01  %:N5'0, Harquahala Valley School 27.0 02 N 8, Ruth Fisher School N 05, Vulture ~',ine Rd. School, Wickenburg lsslng ENE 35, APS El "irage Office, Sun City 23.0 05 ENE 50, APS Deer Valley Office 7.0 06 Litchfield Park School 07 Littleton School, Cashion 29.0 08 Perryville 26.0 09 Hopeville 20.0 50 C'linski Rd., 5 mile, PNV! Sector 21.0

+Missing data

TABLE XVIII UARTERLY THERMOLUMINESCENT DOSIMETRY THIRD UARTER 1985 Total Map Expo'sure Location Collection Location (mrem)

APS Goodyear, E 30 Office 20.0 ENE 20 Scott-Libby School 26.0 E 25, Liberty School 25.0 E 20, APS Buckeye School 27.0 5 ESE 15, Palo Verde 2 I.O 6 SSE 35, APS Gila Bend Sub-station 30.0 7 SE 8, Arlington School 3ci 0 8 SSE, Corner of 363rd Ave. and SPP Rd. 26.'3 9 S5, Corner of 371st Ave. and SPP Rd. 358 10 SE 5, Corner of 355th Ave. and 6'ard Rd. 27m i II ESE 5, Corner of 339th Ave. and Dobbins Rd. 29.C 12 E5, Corner of 339th Ave., and B-S Rd. 27+4 13 N I, N Site Boundary 29 0 IV NNE 2,'NNE Site Boundary )9 15 NE 2, Site Boundary 'l7 0 16 ENE 2, ENE Site Boundary 2Q 0 17 E 2, E Site Boundary ~ 800 18 ESE 2, ESE Site Boundary 0 19 SE 2, SE Site Boundary 28.0 20 SSE 2, SSE Site Boundary 28.0 21 S 3, S Site Boundary 30.0 22 SS'iV 3, SSS'ite Boundary I 30.0 23 hV 5, Benchmark at Oaseline 28.0 20 'iVard Pd. at V'e!1 18bbb 6',

25.0 25 V.'S'6', V'ard Rd. at DF (Veil 2 Rd. 26.0 26 SS'iV V'ell 21 Cbb2 29.0 TABLE XVIII(Cont.)

UARTERLY THERMOLUMINESCENT DOSIMETRY THIRD UARTER 1985 Total Map Exposure Location Collection Location (m rem) 27 SC', SW Site Boundary 29.0 28 O'ShV 1, WSU'ite Boundary 29.0 29 7/ 1, '9! Site Boundary 29.0 30 O'N%', V!NhV Site Boundary 29.0 31 N%', N%'ite Boundary 28.0 32 NNEV 1, NNU'ite Boundary 2S.O 33 NN', Yuma Rd., Yi mile 9! of Belmont Rd. 32.0 3Q NNV! 5, Corner of Belmont Rd. and Van Buren Rd. 31.0 35 NNC< 9, Tonopah, Palo Verde Inn Fire Station 30.0 36 N 5, Corner of 6'intersburg Rd. and Van Buren Rd. 2S.O 37 NNE 5, Corner of 363rd Ave. and Van Buren Rd. 30.0 38 Corner of 355th Ave. and Yuma P.d. 31.0 39 ENE 5, 303rd Ave., Yi mile S of L. Buckeye 27.0 00 N 3, Trailer Park at 7!intersburg 27.0 01 V!NEW 20, Harquahala Valley School 31.0 02 l" 8, Ruth Fisher School 29.0 03 N 05, Vulture 5!ine Rd. School, 6'ickenburg 31.0 ENE 35, APS El I'irage Office, Sun City 25.0 05 ENE 50, APS Deer Valley Office S.5-06 Litchfield Park School 25.0 07 Littleton School, Cashion 30.0 08 Perryville 26.0 09 Hopev ille 25.0 50 Olinski Rd., 5 mile, O'NV.'ector 22.0 TABLE XIX UARTERLY THERMOLUMINESCENT DOSIMETRY FOURTH UARTER 1985 Total Map Exposure Location Collection Location (mrem)

APS Goodyear, E 30 Office 23.0 ENE 20 Scott-Libby School 20.2 E 25, Liberty School 21.3 E 20, APS Buckeye School 25.2 ESE 15, Palo Verde 20.6 SSE 35, APS Gila Bend Sub-station 29.1

~

7 SE 8, Arlington School gc 3, SSE, Corner of 363rd Ave. and SPP Rd. 24,'

S5, Corner of 371st Ave. and SPP P.d.

10 SE 5, Corner of 355th Ave. and Edward Rd. 25 ~ 3 ESE 5, Corner of 339th Ave. and Dobbins Rd. 26.0 12 E5, Corner of 339th Ave., and B-S Rd. 25.4 13 N 1, l" Site Boundary "6.2 NiNE 2, i~! 4!E Site Boundary'E 26.9 15 2, Site Boundary 25.S 16 ENE 2, EKE Site Boundary p 17 E 2, E Site Boundary 26.2 ESE 2, ESE Site Boundary 25.0 19 SE 2, SE Site Bouncary 27.2 20 SSE 2, SSE Site Boundary 16.3 21 S 3; S Site Boundary 27.2 22 SSW 3, SSW Site Boundary 23 W 5, Benchmark at Baseline 2 rov 20 SS', "..'ard Rd. at 9'ell ISbbb 23.8 25 lVSW 5, 9'ard Rd. at DF ~5'ell 2 Rd. 24.S 26 SS%ell 21 Cbb2 29.2 TABLE XIX (Cont.)

UARTERLY THERMOLUMINESCENT DOSIMETRY FOL'RTIE UARTER 19S5 Total Map Exposure Location Collection Location (m rem) 27 S6', SW Site Boundary 29.6 2S O'SUI 1, V'S9'ite Boundary 27.6 29 V.', U~ Site Boundary 27.1 30 O'NLK', O'N'P Site Boundary 2$ .7 31 N%', NV,'ite Boundary 25.0 32 NNEV 1, NNVl Site Boundary 27.2 33 Nnl 5, Yuma Rd., Y~ mile 6'f Belmont Rd. 30.3 30 NNV! 5, Corner of Belmont Pd. and Van Buren Rd. 29.9 35 NN~V 9, Tonopah, Palo Verde lnn Fire Station 33.7 36 - i<<45, Corner of Pintersburg Rd. and Van Buren Rd. 26.7 37 NiNE 5, Corner of 363rd Ave. and Van Buren Rd. 25.3 3S Corner of 355th Ave. and Yuma Rd. 29.0 39 .ENE 5, 303rd Ave., Yi mile S of L. Buckeye 25.7 00 N 3, Trailer Park at <<'t'intersburg 26.0 Ol 'WNU'0, Harquahala Valley School 27.9 02 l'! S, Puth Fisher School 26.5 03 N 45, Vulture <<:ine Rd. School, V'ickenburg 29.0 ENE 35, APS El <<.'.irage Office, Sun City 23.0 ENE 50, APS Deer Valley Office 7.5 Litchfield School 20.9 Littleton School, Cashion 30.1 Perry ville 20.1 Hopev i lie 20.3 50 Olinski Rd., 5 mile, WM" .Sector 21.2 Figure 16 QUARTERLY THERMOLUMIHESCENT DOSIMETRY SECOND QUARTER 1985 E

30 LLJ

~ 20 10 10 15 20 25 30 55 40 45 50 S <<ATIOB

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 30 -

55 40 45 50 STATION

f g4 411 "p'Sf'" i ~

w ~

Figure 19 MEAN QUARTERLY THERMOLUMINESCENT DOSIMETRY 1981-i985 Pre-Operational Operational 83 82

%f E.PQ I 1~ I IV I ~ ~

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 Iodine-131 Collection Location Date Collected Ci/ m (Wet)

~Leaf:

Cambron Garden Lettuce II/Ie/SS < 0.02 Cabbage Ii/IO/S5 < 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 II/IO/85 < 0.02 Lemons <</I e/SS < 0.02 Oranges <</IO/SS < 0.02

TABLE XX1 VEGETATION (Leaf )

GAMMASPECTROMETRY l 985 Ci/ m (wet)

Col lee tion Date Ba-l00 Co-60 Mn-50 Ru,Rh-l06 Zn-65 Zr,Nb-95 Cs-l37 Cs-l 30 Ce-140 Fe-59 Location Collected 0.073>> 0.063>> 0.02l ~ O.lt>>3>> 0.060>> 0.066>> 0.036>> 0.023>> 0:12I>> 0.02I >>

Cambron Garden Lettuce ii/i4/S5 Cabbage II/14/85 h3M Farms Inc Leafy ii/i5/.'5 De Shazo Leafy i 2/i 4/$ 5 NONE nETECTE D Thomas Leafy I2/17/85 Adams Swiss Chard G6/i 0/85 "Detection Limit

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 >>/l0/85 Adams Gsrape fruits I I/I0/85 NONE DETECTED Lemons ii/l0/85 Oranges >>/l0/85 "Detection Limit

~ 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 XXllland 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 Iless than 2.0 pCi/I to a high of 6.1+1.5 pCi/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 Ci/I Collection Date Gross Alpha Gross Beta Strontium-90 Tfitium Location Collected 1.0>> 2.0>> 0.5>> 1000>>

Desert Farms 06/13/S5a 1.1 + 0.6 0.2 + 0.6 < 0.5 < IOQO O6/i3/S5b 2.0 + 1.2 3,Q + Q,5 < 0.5' < 1000 07/18/85 3>>>> < 2.0 ~

0.5 < 1000 OS/15/85 3.8 + 1.6>>>> 0.5 + 0.6>>>> < 0.5 < 1000 09/19/85 < I.O 6.1 + 1.5>>>> < 0.5 < 1000 10/17/85 3.6 + 1.9 5A + 0.6 < 0.5 < 1000 il/Ie/85 < 1.0 < 2.0 < 0.5 < 1000 12/19/85 2.2 + 1.3 0.7 + 0.6 < Q.5 < 1000

'.IcArthur Farm O6/i3/85a <1.0 0.0 + 0.6 < 0.5 < 1000 06/13/85b < I.O < 2.0 <0.5 < 1000 o7/ls/85 < 1.0 < 2.0 < 0.5 < 1000 os/i5/85 < I.O 2.6 + 0.5 <0.5 < 1000 09/19/S5 <1.0 < 2.0 <0.5 < 1000 io/>>/s5 < 1.0 2.5 + 0.5 <0.5 < 1000 Ii/IO/85 < 1.0 < 2.0 <0.5 < 1000 12/19/85 1.3 + I.I 2.3 + 0.5 <0.5 < 1000 Wed eworth O6/i~/85a < 1.0 < 2.0 <0.5 < loco 06/13/85b 1.5 + 1.2 2.0 + 0.9 < 0.5 < 1000 o7/is/s5 <1.0 2.1 + 0.5 < 0.5 < 1000 08/15/S5 < 1.0 2.3 + 0.5 <0.5 < 1000 09/19/85 < 1.0 2.0 + 0.7 < 0.5 < 1000 IO/17/85 2.1 + I.S 3.2 + I.s < 0.5 < 1000 II/I</85 < 1.0 < 2.0 <0.5 < 1000 12/19/85 <1.0 < 2.0 < 0.5 < 1000

>>Detection Limit

>>>>Verified by reanalysis aComposite Sample bCrab Sample

TABLE XX1Y BRINKlNG O'ATER GAMktA SPECTROMETRY 1985 Collection Location Desert Farms Date Collected 06/13/Ssa Ba-140 4" '"

Co-60 Mn-54 2>>

Ru,Rh-106 10" 16>>

Ci/1 Zn-65 Zr,Nb-95 Cs-137 Cs-134 10>> 2>> 10<<

Ce-144 18>>

O6/i3/Ssb 07/is/85 08/is/ss 09/19/85 io/i7/Ss ii/14/:s 12/19/85 b1chrtl>ur Farm 06/13/85a 06/13/Ssb NONE DETECTED 07/1$ /ss 08/is/ss 0)/19/S5 io/i7/85 ii/i4/85 12/19/85 1Yet!1;em;or tlr 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

<<Detection Limit aConrposite Sample bGrab Sample

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 Ci/l Collection Date Gross Alpha Cross beta Strontium-90 Tritium Location Collected 1.0>> 2.0>> 0;5>> 1000>>

5'e I I 27ddc 08/15/85 2.2+ 1.0<<<< 2.1 + 0.5<<<< < 0.5 I GOO II/IO/85 < I.O < 2.0 < 0.5 < 1000 6'el l 30abb 08/15/85 1.9 + I.3<<<<< 2.0 < 0.5 < 1000 I I/IO/85 < 1.0 < 2.0 < 0.5 < IOOG

<<Detection limit

>><<Verified by reanalysis TABLE XXVI CiROljNDWATER GAh1h1A SPLCTROh! ETP Y l9SS Ci/l Date Ba-l00 Co-60 Mn-S0 Ru,Rb-l06 Zn-6S Zr,Nb-9S Cs-l37 Cs-l30 Cc 1 00 Collection Location Collected 0" S" 2" lo" l6" lo" 2" lo" IS" (Veil 27ddc os/ls/ss

>>/l0/ss 5'cll 30abb os/l s/ss NONE DETECTED l l /l 0/SS 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 I-I31 (pci/I)

Collection Location Collection Date 0.5+

PVNCS Reservoir 05/30/85 < 0.5 06/06/85 < 0.5 06/13/85 < 0.5 06/20/85 < 0.5 06/27/85 < 0.5 07/oo/ss < 0.5 07/11/85 < 0.5 o7/Is/85 < 0.5 07/25/S5 < 0.5 os/oi/ss < 0.5 os/os/ss < 0.5 os/is/ss < 0.5 08/22/85 < 0.5 08/29/85 < 0.5 09/05/85 < 0.5 09/12/Ss < 0.5 o9/i9/ss < n.s 09/26/85 <0 5 10/03/Ss < 0.5 io/Io/ss ,< n.s Io/17/ss < '3.5 Io/20/85 ( Jos Io/31/85 < 0.5 I I/07/85 < 0.5 ii/io/ss < O.s 11/21/85 < 0.5 II/27/85 < 0.5 12/05/85 < rJ.5 12/12/Ss < 0.5 12/19/85 <0 5 12/26/85 < G.s

+Detection Limit TABLE XXVIII SURFACE WATER 1985 1-131 (pCI/I)

Collection Location Collection Date 0.5+

PVNGS Evaporation Pond 05/30/85 < 0.5 06/06/85 < 0.5 06/13/S5 ( 0.5 06/2G/85 < 0.5 06/27/85 < 0.5 07/00/85 < 0.5 07/11/85 < 0.5 07/18/S5 < 0.5 07/25/S5 < G-5 OS/01/S5 < 0.5 OS/OS/85 < 0.5 OS/15/85 < 0.5 08/22/85 < 0.5 OS/29/85 < 0.5 09/05/85 < 0.5 09/12/85 < 0.5 09/19/85 < 0.5 09/26/85 (05 10/03/85 < 0.5 10/10/85 ( 0.5 10/17/85 < 0.5 10/20/85 < 0.5 10/31/S5 < 0.5 11/07/85 < 0.5 11/10/85 < 0.5 Il/21/85 < 0.5 II/27/85 < 0.5 12/05/S5 < 0.5 12/12/S5 < 0.5 12/19/85 < 0.5 12/26/85 < 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 Ci/I Gross Alpha Cross Beta Strontium-89 Strontium-90 Tritium Collection Location Com osite Period 1.0" 2.0" 1.0" 0.5" 1000" PVNGS Reservoir Viay < 1.0 5.9 + 0.6 < 1.0 < 0.5 <1000 3rrne < J.Q 6.6 + 0.6 < 1.0 < 0.5 < 1000 3uly < 1.0 7.0 + 1.0 < 1.0 < 0.5 < 1000 August 1.0 8.3 + 0.7 < 1.0 < 0.5 < 1000 Sop te>>rber < 1.0 5.rr + 0.6 < 1.0 < 0.5 < 1000 October < 1.0 3.0 + 0.5 1.0 < 0.5 < IQOQ Novenrbr r 1.9 ~ 1.0 10.9 + 0.7 < 1.0 < 0.5 < 1000 Dr cerrrber 1.0 5:3 + 0.6 < 1.0 < 0.5 < 1000 PVI'!GS Pond J".ay < 1.0 9.1 + 0.7 < 1.0 < 0.5 < JPPQ 3une 1.0 12.9 + 2.0"" 1.0 < 0.5 < 1000 3rr ly < 1.0 12.0 + 1.0 < 1.0 < 0.5 < 1000 Arrgrrst 1.0 10.5 + 0.7 1.0 < 0.5 < 1000 Septenrbc r 1.0 6.8 + 0.6 < 1.0 < 0.5 < 1000 October < I.O 8.3 + 0.7 < 1.0 < 0.5 < 1000 Yovembef 3.2 + 1.6 6.7 + 0.6 < 1.0 < 0.5 < 1000 0( cernber I.p 7.9 + 0.6 < 1.0 < 0.5 < JOQO

'Detection Limit rr 'Verified by reanalysis

Thl)LE XXX SLRFACE 5'hTER (Com osite)

GA Mich SPl'CTROMETR Y l935 Cill Date Ba-!00 Co-60 Mn-50 Ru,Rb-l06 Zn-65 Zr,Nb-95 Cs-l37 Cs-130 Ce-l00 Fe-59 Collection Location Collected 6>> 5>> 2" IO" I6 ~ IO" 2>> IO" IO>> 3<<

PVNCIS Reservoir May 3une 3uly Aul>>ust September October November December NONE DETECTED I

I PVNGS Pond h,lay 3unc 3uly August September Octobrr Noven>bcr December

<<Detection Limit

8.8 Milk (Fresh)

Fresh milk samples were collected on a monthly basis during 1985 from the following locations:

Al Lueck, 3r. Dairy 20 Cordell Baisley Dairy 30 Butler Dairy 3ohn Kerr Dairy

5. Hamstra /I2 (designated operational control location)

6. 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 XXXIand 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 CI/I Collection Date Iodine-131 Strontium-89 Strontium-90 Location Collected 0.5+ 0+ 0.5+

3ohn Kerr Dairy 06/10/85 <05 I.O 0.5 07/19/85 < 0.5 1.0 0.5 Os/i6/85 < 0.5 1.0 0.5 09/20/85 < 0.5 1.0 0.5 io/is/ss < 0.5 1.0 0.5 li/15/S5 < 0.5 1.0 0.5 12/20/85 < 0.5 1,0 0.5 Al Lueck, 3r. Dairy 06/10/85 < 0.5 I.O < 0' 07/19/85 < 0.5 1.0 < 0.5 os/16/s5 < 0.5 1.0 < 0.5 09/20/85 < 0.5 1.0 < CD 5 10/18/S5 < 0.5 1.0 < 0.5 ll/15/S5 < 0.5 1.0 < 0.5 12/20/85 < 0.5 1.0 < 0 '

Paul Skousen Dairy o6/i~/85 < 0.5 1.0 < 0.5 07/19/85 < 0.5 1.0 < 0.5 OS/16/S5 < 0.5 1.0 < 0.5 09/20/85 <05 1.0 < 0' 10/IS/S5 < Oo5 1.0 < 0.5 ii/i5/S5 < 0.5 1.0 < 0.5 12/20/85 < 0.5 1.0 < 0.5 Hamstra I/2 Dairy 06/io/85 < 0.5 1.0 <0 5 07/19/85 < 0.5 I.O < 0.5 QS/16/S5 < 0.5 I.G < 0 '

09/20/85 < 0.5 I.o < 0.5 lo/ls/85 < 0.5 I.O < 0,5

>>/15/S5 <05 1.0 < 0.5 12/20/85 <05 I.O < 0.5 Cordell Baisley Dairy 06/I~/85 < 0.5 1.0 < 0.5 07/19/85 < 0.5 ' 1.0 < 0' os/i6/s5 <0.5 1.0 < 0.5 09/20/85 0.5 1.0 < 0.5 io/is/s5 < 0.5 I .'0 < 0.5 11/15/85 < 0.5 1.0 < 0.5 12/20/8 < 0.5 I.Q < 0.5

+Detection Limit

TABLE XXXI(Continued)

MILK (Fresh) 19S5 Ci/I Collection Date iodine-131 Strontium-89 Strontium-90 Location Collected 0.5+ 1.0+ 0.5+

'utler Dairy 06/ie/s5 < 0.5 < '1.0 < 0.5 07/19/S5 < 0.5 1.0 < 0.5 os/i6/ss < 0.5 <'.0 < 0.5 09/20/S5 < 0.5 1.0 < 0.5 io/is/s5 < 0.5 1.0 < 0.5 li/15/S5 < 0.5 1.0 < 0.5 12/20/S5 < 0.5 1.0 < 0.5

+Detection Limit Thl3LE XXXll MILK 0".RESl 1)

CihMMA SPECTROMETRY l985 Ci/i Collection Col lee tion Ba-i 40 Co-60 Mn-54 Pu,Rh-l06 Zn-65 Zr,Nb-95 Cs-l 37 Cs-l 34 Ce-l44 Location Period >>>> ~ $" 2>> IO ~ l6 ~ IO>> 2~ IO>> 12>>

Cordell Baisley Dairy O6/i4/85 07/i9/85 os/ic/85 09/20/85

-io/i8/85 ii/is/85 l2/20/85 Butler Dairy o6/i4/8s o7/i9/8s o8/i6/:s 09/20/85 io/i8/85 ii/is/8s NONE DETECTED l2/20/85 3otin Kerr Dairy 06/i 4/85 o7/i9/85 08/l6/85 09/20/85 io/is/8s ii/is/85 i2/2o/85 hl Lueck, 3r. Dairy o6/i4/8s 07/i9/85 08/i6/85 o9/2o/85 io/i8/85

>>/>>/85 i2/20/$ 5

~ >>>>>>>>>>>>>> I>>>>>>>>>>a>>>>

TAnLE XXXII(Cont.)

MlLK (FRESI I)

CAMMASPECTROl'.IETRY 1985 Ci/I Collection Collection Ba-100 Co-60 Mn-50 Ru,Rh-106 - Zn-65 Zr,Nb-95 Cs-137 Cs-130 Ce-100 Location Period - '0" 5" 2" 10>> 16>> 10" 2" 10" IS>>

Paul Skousen Dairy 06/10/85 07/l9/85 08/l6/85 09/20/85

.10/18/85

>>/I 5/85 12/20/85 NONE DETECTED l larnstra I/2 Dairy 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

>> Ibetcction Limit

TAIILE XXXIII ENVIRONMENTALRADIOLOGICALMONITORINC PROGRAM ANNUAL

SUMMARY

NAME OF FACILITYt PALO VERDE NUCLEAR GENERATING STATION LOCATION OF FACILITVt MARICOVA COIINTY ARiZONA f

REPORTINC PEIIIOD: l985 (Ol RATIONAL)

Medium or Type and Total Lower Limit All Indicator Location with I I ighest Control Location No. ol nonroutinc Pathway sampled Number of of Detection Locations Annual Mean Mean (f) Range Repor ted (Unit of Measurement) Analyses (LLD) 8(ean (I) Range Name Mean (I) Measurements Performed I)lstancc 4 Range Direction Air Particulates (pCi/in3) Gross II (380) 0.002 0.027 (380/380) I5A 0.029 (32/32) 0.02S (32/32) 0 (0.008-0.037) 2 niilcs ~i 5o (0.013-0.055) (0.0 l0-0.057)

Cross n (380) 0.005 0 Y -spec (36) a 0 I-I3I (38II) 0.007 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 0 T-spec (IQ) a 0

~AII samples less than LLD aSee Table Vl for LLD

'I

~ ~

f ThfILE XXXlll(Cont.)

ENVIRONMENTALRADIOLOGICALMONITOIIINGPROGRAM ANNUALSUhlMARY NAME OF FACILITYt I'ALO VERDE NUCLEAR GENEltATING STATION LOCATION OF FACILITY: MARICOPA COI)NTY ARIZONA IIEPORTING PERIODt l985 (OPERATIONAL)

Medium or Type and Total Lower Limit All Indicator Location with flighest Control Location No. of nonroutine Pathway sampled Number of of Detection Locations Annual Mean Mean (f) Range Reported (Unit of Measurement) Analyses (I.LD) Mean (I) Range Name Mean (f) Measurements Performed Distance h Range Direction Drinl ing Kyater (pCi/l) Gross (24) I.O 2.i (9/24) Desert Farms 2 4 (6/8)

(I.I-3.8) 5 miles 229o (I.l-3.8)

Gross "(24) . 2.0 3.5 (I5/24) Desert Farms 4.7 (6/8)

(2.0-6.I) 5 mii<<s 229o (3 4-6.I)

Sr-90 (24) 0.5 0.

l!3 (24) I,OOO 0 T -spec (24) 0 Ground Water (pCi/I) Gross n(4) I.O 2.0 (2/4) Well 27tldc 2.2 (I/2) 0 (I.9-2.2) Onsitt (2.2)-

Gross E (4) 2.0 2.l (I/4) Well 27ddc 2. I (I/2)

(2.l) Onsitc (2.I)

Sr-90 (4)

I I 3 (4) I,OOO T -spec (4)

Surface kyat<<r (pCi/I) I-I3 I (62) 0.0 0

~ All samples less than LLD aSee Table Vl lor LLD

~ \'rk ~ 1, a

~ M0 TAIlLE XXXIII(Cont.)

ENVIRONMENTALRADIOLOGICALMONITORING PROGRAM ANNUAL

SUMMARY

NAhIE OF FACILITYz PALO Vf RDE NUCLEAR GENERATING STATION LOCATION OF FACILITY: MAltICOPA COUNTY ARIZONA REPORTING PERIOD: 1985 (OPERATIONAL)

Medium or Type and Total Lower Limit All indicator Location with llighest Control Location No. of nonroutine Pathway sampled Number of of Detection Locations Annual hlean Mean (I) Range Reported (Unit of Measuremcnt) Analyses (LLD) Mean (I) Itange Name htean (I) Measurements Performed Distance 6 Range Direction, Siirlacc Water Composites Gross n(I6) I.O 2.G (2/I6) PVNGS Pond 3.2 (I/8) 0 (pCI/i) (I.9-3.2) Onsitc (3.2)

Gross II(IG) 7.9 (I 6/I 6) I VNGS Pond 9.3 (8/8) 0 (3.0- I 2.9) Onsite (G.7- I 2.9)

Sr-89 (iG) l.0 0 Sr-90 (I 6) 0.5 I I 3 (I 6) I,000 0 y-spec (I 6) hlill'pCi/I) I- I 3I (42) 0.5 Sr-89 (42) 1.0 0 Sr-90 (42) 0.5 0 y-spec (42) 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 PRQCRAM

1985 Water EPA CEP Kno~ Value Reported Value Date Parameter Ci/1+ 3 Ci/filter 2/SS Chromium-51 OS + 8.7 3S+ 7 06+ 7 32+7 Cobalt-60 20 + S.7 20+ 3 25+ 3 20 3 inc-65 55+ S.7 51+ 3 50+ 3 55+ 3 Cesium-134 35+ S.7 33+2 29+ 2 32+2 Cesium-137 25 + S.7 23+3 25+ 3 2S+ 3 7/S5 Cobalt-60 10.0 + 5.0 19+ 2 15+ 2 16+ 2

inc-65 ~ r~

Ted e' ~ J 52+ 5 09+ 5 QQ+ Lt Ruthenium-106 62.0 + 5." 73+7 70+7 69+ 7 Cesium-134 35.0'+ 5.0 2S+ 3 29+ 3 26+ 3 Cesium-137 20.0 + 5e0 19+ 2 16+ 2 10+2

-103-

EPA CROSS-CHECK PROCRAM l985 Radionuclides in Air Filters'ate EPA C'Er Known Value Reported Value Parameter Ci/I+ 3 a Ci/filter 3/85 Cross Alpha IQ.Q 3.7 9+I 10+1 12+1 Cross Beta 36.0+S.7 40+0 01+0 39+0 Strontium-90 15.0+2.6 19+2 IS+2 17e 2 Cesium-137 6.0+8.7 7+ 2 6+2 5+2

EPA CROSS-CHECK PRCCRAM 1985 Water EPA CEP Known Value Reported Value Date Parameter Ci/filter

~l-'.5 e/S5 iodine-131 + 1.3 6 + 2 6 + 2 5 + 2

-105-

EPA CROSS-CHECK PROGRAM 1985 Water EPA CEP Known Value Reported Value Date Parameter Ci/I+ 3 Ci/filter I /85 Cross Alpha 5.0 + 5.0 6+2 7 +

7 + 2 Gross Beta 15.0 + 5.0 13+ 2 10+ 2 16+ 2 5/85 Gross Alpha 12.0 + 5.0 13+ 2 15+ 2 IO+ 2 Gross Beta I I.O + 5.0 12+ 2 13+ 2 16+ 2 7/85 Gross Alpha <<+5 9+2 8+2

<<+2 Gross Beta 8+5 9+2 13+ 2 12+ 2 9/85 Cross Alpha 10+ 3 9+3

<<+3 Gross Beta 0 + 5 6+3 5+3 8+3

<</85 Cross Alpha 10+ 5 9+3 8+3 IO+ 3 Gross Beta 13+ 5 IS+3

~

13+ 3 15+3

-106-

EPA CROSS-.CI IECK PROGRAM 1985 Water EPA CEP Known Value Reported Value Date Parameter Ci/I + 3 cr Ci/filter 2/85 Tritium 3796 + 630 3750 + 600 3610 + 600 3500 + 600 e/85 3559 + 630 3437 + 500 3265 + 500 3301 + 500 6/85 2016 + 351 3260 + 571 3191 + 576 2906 + '05 8/85 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 Radial Sector ~Hi1ea e N l. 50 1.50 2.00 1.75 3.00 ESE 3. 75 SE 4. 00 SSE 4. 50 S 4. 50 SSW No Residents SW 2. 75 WSW 1.75 (new)

No Residents WNW No Residents

4. 00 i'NW 2.50 (new)

1 I

f

~

I 1 1

i, l

J jl f

~

~

3