Palo Verde, Units 1, 2 and 3 - Annual Radiological Environmental … · 2012-11-19 · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1,

~L AMR Scott A. BauerDepartment LeaderRegulatory AffairsPalo Verde NuclearGenerating Station

Tel: 6231393-5978Fax: 623/393-5442e-mail: sbauer~apsc.com

Mail Station 7636P.O. Box 52034Phoenix, AZ 85072-2034

102-05096-SAB/TNW/CJJApril 23, 2004

U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001

Dear Sir:

Subject: Palo Verde Nuclear Generating Station (PVNGS)Units 1, 2, and 3Docket Nos. STN 50-528/5291530Annual Radiological Environmental Operating Report 2003

In accordance with PVNGS Technical Specification (TS) 5.6.2, enclosed please find theAnnual Radiological Environmental Operating Report for 2003.

No commitments are being made to the NRC in this letter. If you have any questions,please contact Thomas N. Weber at (623) 393-5764.

Sincerely,

IUW L53 6L .I C

SAB/TNW/CJJ/kg SA SQerEnclosure

cc: B. S. MallettM. B. FieldsN. L. SalgadoA. V. Godwin

A member of the STARS (strategic Teaming and Resource sharing) Alliance

Callaway * Comanche Peak * Diablo Canyon * Palo Verde * South Texas Project * wolf creek

ENCLOSURE

Annual Radiological EnvironmentalOperating Report

2003

NUCLEAR GENERATING STATION

ANNUAL RADIOLOGICAL ENVIRONMENTALOPERATING REPORT

2003

Prepared by:

Reviewed by:._

Digitally signed by: Drinovsky, Louis J(Z33699)Date: 04/09/2004 08:13:15 ;Reason: I am the author of this documentLocation: PVNGS /~6'

a

Digitally signed by-. Gray, Thomas S(Z99610)Date: 04/09/2004 09:42:25 XReason: I have reviewed this documentLocation: PVNGS ' -

Digitally signed by: Gaffney, John P(Z36459)Date: 04/16/2004 17:09:44 XXReason: I am approving this documentLocation: PVNGS

1,Approved by:I

TABLE OF CONTENTS

I. INTRODUCTION ............................................................. 2

2. DESCRIPTION OF THE MONITORING PROGRAM ............................................................ 3

2.1. 2003 PVNGS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM .................................. 32.2. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CHANGES FOR 2003 ......................... 32.3. REMP DEVIATIONS/ABNORMAL EVENTS SUMMARY ............................................................. 4

3. SAMPLE COLLECTION PROGRAM ............................................................ 10

3.1. WATER ............................................................ 103.2. VEGETATION ............................................................ 103.3. MILK ............................................................ 103.4. AIR ............................................................ 103.5. SLUDGE AND SEDIMENT ............................................................ 11

4. ANALYTICAL PROCEDURES.................................................................................................. I I

4.1. AIR PARTICULATE ............................................................ 114.2. AIRBORNE RADIOIODINE ............................................................ 114.3. M ILK1.......................................................................................................................................... . . I I14.4. VEGETATION ............................................................ 124.5. SLUDGE/SEDIMENT ............................................................ 124.6. WATER ............................................................ 124.7. SOIL ............................................................ 13

5. NUCLEAR INSTRUMENTATION .................................................... 13

5. I. GAMMA SPECTROMETER .................................................... 135.2. LIQUID SCINTILLATION SPECTROMETER..................................................................................... 135.3. GAS FLOW PROPORTIONAL COUNTER .................................................... 13

6. ISOTOPIC DETECTION LIMITS AND REPORTING CRITERIA . ......................................... 14

6.1. LOWER LIMITS OF DETECTION ................................................... 146.2. DATA REPORTING CRITERIA ................................................... 146.3. LLD AND REPORTING CRITERIA OVERVIEW .................................................... 15

7. INTERLABORATORY COMPARISON PROGRAM ....................................... 20

7.1. QUALITY CONTROL PROGRAM ................................................... 207.2. INTERCOMPARISON RESULTS ................................................... 20

8. DATA INTERPRETATIONS AND CONCLUSIONS ....................................... 25

8.1. AIR PARTICULATES .258.2. AIRBORNE RADIOIODINE .268.3. VEGETATION .268.4. MILK .268.5. DRINKING WATER .268.6. GROUNDWATER .26

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT. 2003ii

TABLE OF CONTENTS

8.7. S URFACE WATER ................... ; 268.8. SLUDGE AND SEDIMENT .278.9. DATA TRENDS .28

9. THERMOLUMINESCENT DOSIMETER (TLD) RESULTS AND DATA . .49

10. LAND USECENSUS .55

10.1. INTRODUCTION .5510.2. CENSUS RESULTS .55

11. SUMMARY AND CONCLUSIONS .. 57

12. REFERENCES .62

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2003iii

LIST OF TABLES

TABLE 2.1 SAMPLE COLLECTION LOCATIONS .................................................................... 5

TABLE 2.2 SAMPLE COLLECTION SCHEDULE .................................................................... 6

TABLE 2.3 SUMMARY OF REMP DEVIATIONS/ABNORMAL EVENTS ......................................... 7

TABLE 6.1 ODCM REQUIRED LOWER LIMITS OF DETECTION (A PRIORP) ............................... 17

TABLE 6.2 ODCM REQUIRED REPORTING LEVELS ................................................................... 18

TABLE 6.3 TYPICAL MDA VALUES ................................................................... 19

TABLE 7.1 INTERLABORATORY COMPARISON RESULTS ........................................................... 21

TABLE 8.1 PARTICULATE GROSS BETA IN AIR IST - 2ND QUARTER ....................................... 29

TABLE 8.2 PARTICULATE GROSS BETA IN AIR 3RD - 4TH QUARTER ....................................... 30

TABLE 8.3 GAMMA IN AIR FILTER COMPOSITES ................................................................... 31

TABLE 8.4 RADIOIODINE IN AIR IST - 2ND QUARTER ................................................................. 32

TABLE 8.5 RADIOIODINE IN AIR 3RD - 4TH QUARTER ................................................................. 33

TABLE 8.6 VEGETATION ................................................................... 34

TABLE 8.7 MILK .................................................................... 35

TABLE 8.8 DRINKING WATER ................................................................... 36

TABLE 8.9 GROUNDWATER .................................................................... 38

TABLE 8.10 SURFACE WATER .................................................................... 39

TABLE 8.11 SLUDGE/SEDIMENT ................................................................... 42

TABLE 9.1 TLD SITE LOCATIONS .................................................................... 50

TABLE 9.2 2003 ENVIRONMENTAL TLD RESULTS .................................................................... 52

TABLE 10.1 2003 LAND USE CENSUS ................................................................... 56

TABLE 11.1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUALSUMMARY ................................................................... 58

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2003iv

LIST OF FIGURES

FIGURE 2.1 REMP SAMPLE SITES - MAP (0-10 miles) ................................................................... 8

FIGURE 2.2 REMP SAMPLE SITES - MAP (0-35 miles) ................................................................... 9

FIGURE 8.1 HISTORICAL GROSS BETA IN AIR (WEEKLY SYSTEM AVERAGES) ............... 44

FIGURE 8.2 HISTORICAL GROSS BETA IN AIR (ANNUAL SITE TO SITE COMPARISONS)

COMPARED TO PRE-OP ...................................................................... 45

FIGURE 8.3 GROSS BETA IN DRINKING WATER ...................................................................... 46

FIGURE 8.4 SOIL Cs-] 37 COMPARED TO ONSITE SEDIMENT BASIN #2 . . 47

FIGURE 8.5 EVAPORATION POND TRITIUM ACTIVITY ............................................................ 48

FIGURE 9.1 NETWORK ENVIRONMENTAL TLD EXPOSURE RATES ............... ....................... 53

FIGURE 9.2 ENVIRONMENTAL TLD COMPARISON - PRE-OPERATIONAL VS 2003 ... 54

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2003v

ABSTRACT

The Radiological Environmental Monitoring Program (REMP) is an ongoing program conducted byArizona Public Service Company (APS) for the Palo Verde Nuclear Generating Station (PVNGS).Various types of environmental samples are collected near PVNGS and analyzed for radionuclideconcentrations.

During 2003, the following categories of samples were collected by APS:

* Broad leaf vegetation. Groundwater• Drinking water* Surface water* Airborne particulate and radioiodine* Goat milk* Sludge and sediment

Thermoluminescent dosimeters (TLDs) were used to measure environmental gamma radiation. TheEnvironmental TLD program is also conducted by APS.

The Arizona Radiation Regulatory Agency (ARRA) performs radiochemistry analyses on variousduplicate samples provided to them by APS. Samples analyzed by ARRA include onsite samples fromthe Reservoir, two (2) Evaporation Ponds, and two (2) deep wells. Offsite samples analyzed by ARRAinclude two (2) local resident wells. ARRA also performs air sampling at seven (7) offsite locationsidentical to APS and maintains approximately fifty (50) environmental TLD monitoring locations,eighteen (18) of which are duplicates of APS locations.

A comparison of pre-operational and operational data indicates no changes to environmentalradiation levels. There were no measurable radiological impacts on the environment due toPVNGS operations in 2003.

(NOTE: Reference to APS throughout this report refers to PVNGS personnel)

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 20031

OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORINGPROGRAM

1. Introduction

This report presents the results of the operational radiological environmental monitoringprogram conducted by Arizona Public Service Company (APS). The RadiologicalEnvironmental Monitoring Program (REMP) was established for the Palo Verde NuclearGenerating Station (PVNGS) by APS in 1979. The REMP is performed in accordance with thefederal requirements to provide a complete environmental monitoring program for nuclearreactors, and with concern for maintaining the quality of the local environment. The programcomplies with the requirements of 10 CFR50, Appendix 1, PVNGS Technical Specifications,and with the guidance provided by the US Nuclear Regulatory Commission (USNRC) in theirRadiological Assessment Branch Technical Position on Environmental Monitoring, Revision1, November 1979.

This report contains the measurements and findings for 2003. All references are specificallyidentified in Section 12.

The objectives of the REMP are as follows: 1) to determine baseline radiation levels in theenvirons prior to plant operation and to compare the findings with measurements obtainedduring reactor operations; 2) to monitor potential critical pathways of radio-effluent to man;and 3) to determine radiological impacts on the environment caused by the operation ofPVNGS.

Results from the REMP help to evaluate sources of elevated levels of radioactivity in theenvironment (e.g., atmospheric nuclear detonations or abnormal plant releases).

Results of the PVNGS pre-operational environmental monitoring program are presented inReference 1.

The initial criticality of Unit I occurred May 25, 1985. Initial criticality for Units 2 and 3 wereApril 18, 1986, and October 25, 1987, respectively. PVNGS operational findings (historical)are presented in Reference 2.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 20032

2. Description of the Monitoring Program

APS and vendor organizations performed the pre-operational radiological environmentalmonitoring program, which began in 1979. APS and vendors continued the program into theoperational phase.

2.1. 2003 PVNGS Radiological Environmental Monitoring Program

The assessment program consists of routine measurements of background gammaradiation and of radionuclide concentrations in media such as air, groundwater,drinking water, surface water, vegetation, milk, sludge, and sediment.

Samples were collected by APS at the monitoring sites shown in Figures 2.1 and 2.2.The specific sample types, sampling locations, and sampling frequencies, as set forthin the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presentedin Tables 2.1, 2.2 and 9.1. Additional onsite sampling (outside the scope of the ODCM)is performed to supplement the REMP. All results are included in this report. Sampleanalyses were performed by APS at the PVNGS Central Chemistry Laboratory andEberline Services (goat milk only).

Background gamma radiation measurements were performed by APS using TLDs atforty-eight (48) locations near PVNGS.

In addition to monitoring environmental media, a land use census is performedannually to identify the nearest milk animals, residents, and gardens. This informationis used to evaluate the potential dose to members of the public for those exposurepathways that are indicated.

2.2. Radiological Environmental Monitoring Program Changes for 2003

* Air sample location 7A, Arlington School (SE8), was deleted as of 12-31-02.The school was closed so air sample monitoring at this location wasdiscontinued.

Refer to Table 2.1 for a description of all current sample locations.


2.3. REMP Deviations/Abnormal Events Summary

During calendar year 2003, there were two (2) deviations/abnormal events withregard to the monitoring program. Refer to Table 2.3 for more detail and anycorrective actions taken.

* TLD site #26 was moved approximately 0.25 miles east of its previous locationdue to property inaccessibility.

* The I-131 required LLD of 1.0 pCi/liter was not achieved for the goat milksample on 9-17-03.


Table 2.1 SAMPLE COLLECTION LOCATIONS

SAMPLE ISITE # SAMPLE TYPE LOCATION; LOCATIONDESCRIPTION

4 air E16 ' APS Office6A* - air SSEl3 Old US 8014A , air -NNE2-' 3715 Ave. and Buckeye-Salome Rd.15 air NE2 - NE Site Boundary17A air E3' 3515Ave.21 air S3 ,, S Site Boundary29 air WI W Site Boundary35 air NNW8 Tonopah40 air -N2' ' Transmission Rd46;, drinking water NW9, McArthur residence47 vegetation ESE4 - McCoy residence48 drinking water SW I Berryman residence49'. drinking water N2 Chowanec residence51 milk NE4 ,: Painter residence-goats52 : vegetation N2 Chowanec residence53* milk ENE24 - Barber residence-goats55 drinking water SW3 , Gavette residence

(supplemental)57 - groundwater ONSITE Well 27ddc58 - groundwater ONSITE,' Well 34abb59 ,' , surface water ONSITE -- Evaporation Pond #160 ' ' surface water ONSITE' - Reservoir62* ' vegetation ENE26 Duncan Family Farms63 J-surface water ONSITE 1 Evaporation Pond #2

NOTES:

* Designates a control site

(a) Distances and directionnearest mile

are from the center-line of Unit 2 containment and rounded to the

(b) Denotes a change in location

Air sample sites designated with the letter 'A' are sites that have the same site number as a TLDlocation, but are not in the same location (e.g. site #6 TLD location is different from site #6A airsample location; site #4 TLD location is the same as site #4 air sample location)


Table 2.2 SAMPLE COLLECTION SCHEDULE

SAMPLE AIR AIRBORNE GROUND DRINCKING SURFACESITE # PARTICULATE MILK RADIOlODIANE VEGETA TION I WA TER I IA TER I WA TER

4 W W

6A W W

14A V X

15 W W

17A _ V

21 W W

29 W WX

35 W XV

40 W XV

46 XW

47 M/AA

48 XV

49 .W

51 M/AA

52 M/AA

53 M/AA

55 XV

57 Q

58 Q

5 9 XV

60 W

62 MJAA

63 W

W = WEEKLY MIAA = MONTHLY AS AVAILABLE Q = QUARTERLY


TABLE 2.3 SUMMARIES OF REMP DEVIATIONS/ABNORMAL EVENTS

Deviation/Abnormal Event

1. TLD site #26 was moved.

2. The required LLD for I-131 of 1.0pCi/liter was not achieved for a goat milksample on 9-17-03.

Actions taken

The previous location became inaccessible due tothe property selling. The TLD field holder wasmoved approximately 0.25 miles east of itsprevious location. This TLD location is to meetthe ODCM outer ring (4-5 miles) criterion. GPSreadings indicate that the new position still fallswithin the ODCM required sector and distancecriteria for this location. No further actions arerequired.

The onsite Central Lab initiated analysis of lowlevel 1-13 1 in milk in September 2003. Prior tothis date samples were counted by a vendor lab.'A priori' LLD counting parameters were set upfor the instrumentation to be used to analyzesamples. Due to differences in detectorefficiencies, one of the samples (control location)was not counted long enough to achieve the 1.0pCi/liter required sensitivity (actual MDA was1.2 pCi/liter). The indicator milk sample locationwas counted on a different detector and achievedthe required sensitivity of <1 pCi/liter for I-13 1.The corrective action was to set the 'count toLLD' feature on all instruments used to countmilk samples to the most restrictive count time(in this case they were set to 7 days). Subsequentsamples have met the 1.0 pCi/liter LLD value.This was documented in the corrective actionprogram as CRDR No. 2646728. No furtheractions are required.


FIGURE 2.1REMP SAMPLE SITES

(0-10 MILES)

Graphic Scale In Miles

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w Water Sample* School M Mllk Sample

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KEY TO MAP Palo Verde Nuclear Generating Station

RADIOLOGICAL ENVIRONMENTAL MONITORING-+4- --- Railroad Palo Verde Nuclear P O R M S M L I E

Airstrip!Airport Generating StationBoundary

Schools Located T Thnermlumineseent OSampleSites 0-35 Miles,*Near Sample Sites DosmImeteu(D) V Vegeladen

* Municipal Buildings A AlrSample MI MILK

3. Sample Collection Program

APS personnel using PVNGS procedures collected all samples.

3.1. Water

Weekly samples were collected from the Reservoir, Evaporation Pond #1, EvaporationPond #2, and four (4) residence wells. Samples were collected in one-gallon containersand 500 ml glass bottles. One liter from each weekly one-gallon sample was added to amonthly composite, which is preserved with nitric acid (HNO3 ). The compositesamples were then analyzed for gamma emitting radionuclides. Residence wells werealso analyzed for gross beta activity. Weekly grab samples in glass bottles werecomposited quarterly and analyzed for tritium.

Quarterly grab samples were collected from onsite wells 34abb and 27ddc. Sampleswere collected in one-gallon containers and 500 ml glass bottles. Samples wereanalyzed for gamma emitting radionuclides and tritium.

Treated sewage effluent from the City of Phoenix was sampled as a weekly compositeat the onsite Water Reclamation Facility (WRF), and analyzed for gamma emittingradionuclides. A monthly composite was analyzed for tritium.

3.2. Vegetation

Vegetation samples were collected monthly, as available, and were analyzed for gammaemitting radionuclides.

3.3. Milk

Goat milk samples were collected monthly, as available, and were analyzed for gammaemitting radionuclides, including low level 1-13 1.

3.4. Air

Air particulate filters and charcoal cartridges were collected at nine (9) sites on aweekly basis. Particulate filters were analyzed for gross beta. Charcoal cartridges wereanalyzed for 1-131. Particulate filters were composited quarterly, by location, andanalyzed for gamma emitting radionuclides.


3.5. Sludge and Sediment

Sludge samples were obtained weekly from the WRF waste centrifuge (whenever theplant was operational) and analyzed for gamma emitting radionuclides. Samples werecollected using 1000 ml plastic bottles.

Cooling tower sludge from Unit 3 was disposed of in the WRF Landfill in 2003.Samples were analyzed for gamma emitting radionuclides.

Bottom sediment/sludge samples were obtained from Evaporation Pond #1 and #2 andanalyzed for gamma emitting radionuclides.

4. Analytical Procedures

The procedures described in this report are those used by APS to routinely analyze samples.

4.1. Air Particulate

4.1.1. Gross Beta

A glass fiber filter sample is placed in a stainless steel planchet and countedfor gross beta activity utilizing a low background gas flow proportionalcounter.

4.1.2. Gamma Spectroscopy

The glass fiber filters are placed in a standard geometry container andcounted on a multichannel analyzer equipped with an HPGe detector. Theresulting spectrum is analyzed by a computer for specific radionuclides.

4.2. Airborne Radioiodine

The charcoal cartridge is counted on a multichannel analyzer equipped with an HPGedetector. The resulting spectrum is analyzed by a computer for 1-131.

4.3. Milk


The sample is placed in a plastic marinelli beaker, weighed, and counted on amultichannel analyzer equipped with an HPGe detector. The resultingspectrum is analyzed by a computer for specific radionuclides.


11

4.3.2. 1-131 (Eberline only)

The sample is reduced with sodium bisulfite and iodine is absorbed by anionresin. The iodine is eluted from the resin, extracted from the sample, and thenback extracted and precipitated onto a filter. The precipitate is counted and the1-131 is quantified.

4.4. Vegetation


The sample is pureed in a food processor, placed in a one liter plastic marinellibeaker, weighed, and counted on a multichannel analyzer equipped with anHPGe detector. The resulting spectrum is analyzed by a computer for specificradionuclides.

4.5. Sludge/Sediment


The wet/dry sample is placed in a one-liter plastic marinelli beaker, weighed,and counted on a multichannel analyzer equipped with an HPGe detector. Theresulting spectrum is analyzed by a computer for specific radionuclides.

4.6. Water


The sample is placed in a one-liter plastic marinelli beaker, weighed, andcounted on a multichannel analyzer equipped with an HPGe detector. Theresulting spectrum is analyzed by a computer for specific radionuclides.

4.6.2. Tritium

The sample is evaluated to determine the appropriate method of preparationprior to counting. If the sample contains suspended solids or is turbid, it maybe filtered, distilled, and/or de-ionized, as appropriate. Eight (8) milliliters ofsample are mixed with fifteen (15) milliliters of liquid scintillation cocktail.The mixture is dark adapted and counted for tritium activity using a liquidscintillation counting system.


4.6.3. Gross Beta

A 200-250 milliliter sample is placed in a beaker. Five (5) milliliters ofconcentrated nitric (HNO3) acid is added and the sample is evaporated downto about twenty (20) milliliters. The remaining sample is transferred to astainless steel planchet. The sample is heated to dryness and counted for grossbeta in a gas flow proportional counter.

4.7. Soil


The samples are sieved, placed in a one-liter plastic marinelli beaker, andweighed. The samples are then counted on a multichannel analyzer equippedwith an HPGe detector. The resulting spectrum is analyzed by a computer forspecific radionuclides.

5. Nuclear Instrumentation

5.1. Gamma Spectrometer

The Canberra Gamma Spectrometer consists of a Canberra System equipped withHPGe detectors having resolutions of 1.73 keV and 1.88 keV (as determined by fullwidth half max with an energy of 0.5 keV per channel) and respective efficiencies of21.5% and 38.4% (as determined by the manufacturer with Co-60). The CanberraSystem is used for all gamma counting. The system uses Canberra developed softwareto search, identify, and quantify the peaks of interest.

5.2. Liquid Scintillation Spectrometer

A Beckman LS-6500 Liquid Scintillation Counter is used for tritium determinations.The system background averages approximately 15-17 cpm with a counting efficiencyof approximately 40% using a quenched standard.

5.3. Gas Flow Proportional Counter

5.3.1. The Tennelec LB5 100 is a low background gas flow proportional counter forgross beta analysis. The system contains an automatic sample changer capable ofcounting 50 samples in succession. Average beta background count rate is about 1-2cpm with a beta efficiency of approximately 30% for Cs-137.

5.3.2. The Tennelec S5E is a low background gas flow proportional counter for grossbeta analysis. The system contains an automatic sample changer capable of counting 50samples in succession. Average beta background count rate is about 1-2 cpm with a betaefficiency of approximately 30% for Cs-137.


6. Isotopic Detection Limits and Reporting Criteria

6.1. Lower Limits of Detection

The lower limits of detection (LLD) and the method for calculation are specified in thePVNGS ODCM, Reference 4. The ODCM required a priori LLDs are presented inTable 6.1. For reference, a priori LLDs are indicated at the top of data tables forsamples having required LLD values.

6.2. Data Reporting Criteria

All results that are greater than the Minimum Detectable Activity (MDA) (a posterioriLLD) are reported as positive activity with its associated 2a counting error. All resultsthat are less than the MDA are reported as less than values at the associated MDA. Forexample, if the MDA is 12 pCi/liter, the value is reported as <12.

Typical MDA values are presented in Table 6.3.

Occasionally, the PVNGS ODCM a priori LLDs may not be achieved as a result of:

. Background fluctuations* Unavoidably small sample sizes* The presence of interfering radionuclides

Self absorption corrections* Decay corrections for short half-life radionuclides* Other uncontrollable circumstances

In these instances, the contributing factors will be noted in the table where the data arepresented. A summary of deviations/abnormal events is presented in Table 2.3 andincludes a description of any sample results that did not meet a priori LLDrequirements.


6.3. LLD and Reporting Criteria Overview

Making a reasonable estimate of the limits of detection for a counting procedure or aradiochemical method is usually complicated by the presence of significantbackground. It must be considered that the background or blank is not a fixed valuebut that a series of replicates would be normally distributed. The desired net activity isthe difference between the gross and background activity distributions. Theinterpretation of this difference becomes a problem if the two distributions intersect asindicated in the diagram.

BACKGROUND GROSS

If a sufficient number of replicate analyses are run, it is expected that the results wouldfall in a normal Gaussian distribution. Standard statistics allow an estimate of theprobability of any particular deviation from the mean value. It is common practice toreport the mean b one or two standard deviations as the result. In routine analysis,such replication is not carried out, and it is not possible to report a Gaussian standarddeviation. With counting procedures, however, it is possible to estimate a Poissonstandard deviation directly from the count. Data is commonly reported as themeasured value + one or two Poisson standard deviations. The reported values are thenconsidered to give some indication of the range in which the true value might beexpected to occur.

A LLD is the smallest amount of sample activity that will yield a net count for whichthere is confidence at a predetermined level that activity is present. LLDs arecalculated values for individual radionuclides based on a number of different factorsincluding sample size, counting efficiency and background count rate of theinstrument, the background and sample counting time, the decay time, and thechemical recovery of the analytical procedures. A minimum detectable activity value(MDA) is the smallest amount of activity that can be detected in an actual sample anduses the values obtained from the instrument and outcome of the analytical process.Therefore, the MDA values may differ from the calculated LLD values if the samplesize and chemical recovery, decay values, or the instrument efficiency, background, orcount time differed from those used in the LLD calculation.


The factors governing the calculation of the LLD and MDA values are discussedbelow:

1. Sample Size

2. Counting Efficiency

The fundamental quantity in the measurement of a radioactive substance is the numberof disintegrations per unit time. As with most physical measurements in analyticalchemistry, an absolute measurement of the disintegration rate is seldom possible,rather it is necessary to compare the sample with one or more standards. The standardsdetermine the counter efficiency that may then be used to convert sample counts perminute (cpm) to disintegrations per minute (dpm).

3. Background Count Rate

Any counter will show a certain counting rate without a sample in position. Thisbackground counting rate comes from several sources: 1) natural environmentalradiation from the surrounding materials, 2) cosmic radiation, and 3) the naturalradioactivity in the counter material itself. The background counting rate will dependon the amounts of these types of radiation and the sensitivity of the counter to theradiation.

4. Background and Sample Counting Time

The amount of time devoted to the counting of the background depends on the level ofactivity being measured. In general, with low level samples, this time should be aboutequal to that devoted to counting a sample.

5. Time Interval betwveen Sample Collection and Counting

Decay measurements are useful in identifying certain short-lived nuclides. Thedisintegration constant is one of the basic characteristics of a specific radionuclide andis readily determined, if the half-life is sufficiently short. To ensure the required LLDsare achieved, appropriate decay correction values are used to account for radioactivedecay during transit time and sample processing.


Table 6.1 ODCM REQUIRED LOWER LIMITS OF DETECTION (a priori)

AIRBORNEANALYSIS/ WATER PARTICULATE or MILK VEGETATIONNUCLIDE (pCi/liter) GAS (pCi/m3 ) (pCi/liter) (pCi/kg, wet)Gross Beta 4 0.01

H-3 2000*Mn-54 15Fe-59 30

Co-58, 60 15Zn-65 30Zr-95 30Nb-95 151-131 1** 0.07 1 60

Cs-134 15 0.05 15 60Cs-137 18 0.06 18 80Ba-140 60 60La-140 15 15

NOTES:

* If no drinking water pathway exists, a value of 3000 pCi/liter may be used.** If no drinking water pathway exists, a value of 15 pCi/liter may be used.

This list does not mean that only these nuclides are to be detected and reported. Other peaks that aremeasurable and identifiable, together with the above nuclides, shall also be identified and reported.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT. 200317

Table 6.2 ODCM REQUIRED REPORTING LEVELS

AIRBORNEANALYSIS/ WATER PARTICULATE MILK VEGETATIONNUCLIDE (pCi/liter) or GAS (pCi/m3 ) (pCifliter) (pCi/kg, wet)

H-3 20,000*Mn-54 1,000Fe-59 400Co-58 1,000Co-60 300Zn-65 300

Zr/Nb-95 4001-131 2** 0.9 3 100

Cs-134 30 10 60 1,000Cs-137 50 20 70 2,000

Ba/La-140 200 300

NOTES:

* For drinking water samples. This is a 40CFR141 value. If no drinking water pathway exists, avalue of 30,000 pCi/liter may be used.

** If no drinking water pathway exists, a reporting level of 20 pCi/liter may be used.

The values in this table are (calendar) quarterly average values, as stated in the ODCM.


Table 6.3 TYPICAL MDA VALUES

ANALYSIS/ AIRBORNE VEGETATIONNUCLIDE WATER MILK PARTICULATE or (pCi/kg, wet)

(pCi/liter) (pCifliter) GAS (pCi/m 3 )Gross Beta 3 0.003

H-3 300Mn-54 11Fe-59 23Co-58 12Co-60 14Zn-65 25Zr-95 21Nb-95 13I-131 12 1 0.0 450

Cs-134 12 1 0.02 45Cs-137 12 1 0.2b60Ba-140 37 3La-140 13 1

NOTES:

a - low level 1-131 is not required since there is no drinking water pathwayb - Based on 433 m3 volume


19

7. Interlaboratory Comparison Program

7.1. Quality Control Program

APS maintains .an extensive QA/QC Program to provide assurance that samples arecollected, handled, tracked, and analyzed to specified requirements. This programincludes appropriate elements of USNRC Regulatory Guide 4.15, Quality Assurancefor Radiological Monitoring Programs (Normal Operations) - Effluent Streams and theEnvironment, Rev. 1. Included in the program are procedures for sample collection,preparation and tracking, sample analysis, equipment calibration and checks, andongoing participation in an interlaboratory comparison program. Duplicate/replicatesamples are analyzed to verify analytical precision and sample methodology.Comprehensive data reviews are performed including trending of data whereappropriate.

During 2003, APS and/or Eberline Services analyzed the following sample types underthe interlaboratory comparison program;

* Beta/Gamma/ in Air Filter* 1-131 in Air* Beta in Water* Gamma in Water* Tritium in Water* 1-131 in Milk* Gamma in Milk

7.2. Intercomparison Results

APS participates in a crosscheck program using vendor supplied blind radionuclidesamples. Eberline Services participates in several crosscheck programs. Results for theinterlaboratory comparison programs relevant to REMP sample media are presented inTable 7.1.

It was identified in February 2003 that Eberline Services did not performinterlaboratory cross-checks for I-131 in milk in 2002. This discrepancy wasdocumented in the corrective action program as CRDR No. 2585801 (this was reportedin the 2002 AREOR). Part of the corrective action was for Eberline to analyze a blindintercomparison milk sample with I-131. The performance of the corrective action wasverified for 2003.

All crosscheck results reported in 2003 were within the established acceptance criteria.


TABLE 7.1 INTERLABORATORY COMPARISON RESULTS

Sample Analysis Nuclide PVNGS Certified PT Acceptance Accept/RejectType Type Value Value 1 Umits 2

Water Iodine 1-131 22.0 20.8 17.3 - 24.3 Accept(ERA RAD-53) - .

Tritium H-3 ] 1170 [ 1250 J 678- 1820 Accept

Sample Analysis |Nudide PVNGS Certified 1 PT Acceptance Accept/RejectType Type Value value Umits 2

Water Mixed |[Co-60 40.1 37.4 1 28.7 - 46.1 | Accept(ERA RAD-52) Gamma Zn-65 J 63.2 60.3 j 49.9 - 70.7 Accept

Ba-133 l 20.3 19.5 j 10.8 - 28.2 | AcceptCs-134 16.5 17.8 j 9.14 - 26.5 AcceptCs-137 48.1 44.2 j 35.5 - 52.9 Accept

I The certified values are verified to meet criteria as established by NISTNVLAP in Handbooks 150 and 150-19 and the USEPA in

National Standards for Water Proficiency Testing Studies Criteria Document (December 30, 1998).

2 "Acceptance limits' have been calculated per the requirements of the USEPA in National Standards for Water Proficiency Testing

Studies Criteria Document (December 30, 1998). The 'PT limits are calculated at the 3 standard deviation limit.



Sample Analysis Nudide Known PVNGS sigma Resolution Ratio Accept/RejectType Type Value Value Error =

| MixedWater Gamma I-131 70 64 5.0 13 0.91 Accept

E3541-111 Ce-141 168 168 8.0 21 1.00 AcceptCr-51 238 203 20.0 10 0.85 Accept

Cs-134 88 75 5.0 15 0.85 AcceptCs-137 195 188 10.0 19 0.96 AcceptCo-58 42 50 4.0 13 1.19 AcceptMn-54 63 59 4.0 15 0.94 AcceptFe-59 46 49 11.0 4 1.07 AcceptZn-65 90 98 7.0 14 1.09 AcceptCo-60 157 159 8.0 20 1.01 Accept

Tritium H-3 4463 3810 111.0 34 0.85 AcceptE3545-111

Gross Beta 186 230 3.0 77 1.24 AcceptE3540-111

Air Gross Beta 187 214 2.0 107 1.14 AcceptE3542-111

Iodine Cart I-131 77 80 4.0 20 1.04 AcceptE3543-111

MixedGamma Ce-141 154 158 7.0 23 1.03 Accept

E3544-111 Cr-51 219 213 21.0 10 0.97 AcceptCs-134 80 77 6.0 13 0.96 AcceptCs-137 178 196 12.0 16 1.10 AcceptCo-58 42 50 4.0 13 1.19 AcceptMn-54 57 63 5.0 13 1.11 AcceptFe-59 42 49 6.0 8 1.17 AcceptZn-65 83 100 7.0 14 1.20 Accept

| Co-60 | 144 152 7.0 22 1.06 Accept



Sample Analysis Nuclide Known PVNGS | sigma Resolution Ratio 'Accept/RejectTy eTyeype__ aue V luTrrrype_________Value_______ _______Value _______ ________ErrorI__________

MixedWater Gamma I-131 61 55 6 9 0.90 Accept

E3989-111 Ce-141 189 200 10 20 1.06 AcceptCr-51 262 237 20 12 0.90 Accept

Cs-134 127 110 7 16 0.87 AcceptCs-137 121 118 7 17 0.98 AcceptCo-58 104 105 7 15 1.01 AcceptMn-54 162 173 11 16 1.07 AcceptFe-59 96 104 8 13 1.08 AcceptZn-65 184 192 11 17 1.04 AcceptCo-60 145 148 8 19 1.02 Accept

Tritium H-3 2290 1805 194 9 0.79 AcceptE3993-111

Gross Beta 141 204 15 14 1.45 AcceptE3988-111

Air Gross Beta 52 66 2 33 1.27 AcceptE3990-111

Iodine Cart I-131 76 85 10 9 1.12 AcceptE3991-111

MixedGamma Ce-141 108 125 8 16 1.16 Accept

E3992-111 Cr-51 150 137 28 5 0.91 AcceptCs-134 73 67 5 13 0.92 AcceptCs-137 69 77 5 15 1.12 AcceptCo-58 59 62 5 12 1.05 AcceptMn-54 93 107 7 15 1.15 AcceptFe-59 55 70 9 8 1.27 AcceptZn-65 105 125 9 14 1.19 AcceptCo-60 83 89 5 18 1.07 Accept



Sample Analysis Nuclide Known Eberline sigma Resolution Ratio Accept/RejectType Type Value Value ErrorMilk Mixed

Gamma 1-131 84 84 2 42 1.00 AcceptE3661-207 Ce-141 416 412 32 13 0.99 Accept

Cs-1 34 88 77 9 9 0.88 AcceptCs-137 191 184 15 12 0.96 AcceptCo-58 100 100 9 11 1.00 AcceptMn-54 163 160 13 12 0.98 AcceptFe-59 125 130 17 8 1.04 AcceptZn-65 162 152 18 8 0.94 AcceptCo-60 111 104 10 10 0.94 Accept

Sapl Analysis Nudide Known PVNGS sigma Resolution Ratio Accept/RejectType TApe Value Value Error *

Milk MixedGamma 1-131 45 46 2.6 18 1.02 AcceptE3806 Ce-141 38 35 1.4 25 0.92 Accept

Cs-134 30 31 1.7 18 1.03 AcceptCs-I 37 22 24 1.5 16 1.09 AcceptCo-58 32 30 1.7 18 0.94 AcceptCr-51 114 106 7.5 14 0.93 AcceptMn-54 24 22 1 22 0.92 AcceptFe-59 30 31 1.8 17 1.03 AcceptZn-65 46 50 2.2 23 1.09 Accept

l Co-60 30 31 1.5 21 1.03 Accept

* calculated from PVNGS value/l sigma error value

Acceptance Criteria 1

Resolution Ratio<44-7 0.5-2.08-15 0.6-1.6616-50 0.75-1.33

51-200 0.80-1.25>200 0.85-1.18

From NRC Inspection Manual, Inspection Procedure 84750, "Radioactive Waste Treatment, And Effluent And Environmental Monitoring'


8. Data Interpretations and Conclusions

Associated with the analytical process are potential random and systematic errors. Systematicerrors can be caused by instrument malfunctions, incomplete precipitation, back scattering,and self-absorption. Random errors are beyond the control of the analyst.

Efforts are made to minimize both systematic and random errors in the data reported.Systematic errors are minimized by performing reviews throughout the analysis. For example,instruments are checked routinely with radioactive sources, and recovery and self-absorptionfactors based on individual sample analyses are incorporated into the calculation equationswhere necessary. Random errors are reduced by comparing all data to historical data for thesame site and performing comparisons between analytical results when available. In addition,when data do not appear to match historical results, analyses may be rerun on a separatealiquot of the sample to verify the presence of the activity. The acceptance of data isdependent upon the results of quality control samples and is part of the data review processfor all analytical results.

The "plus or minus value" reported with each analytical result represents the counting errorassociated with the result and gives the 95% confidence (2a) interval around the data.

Most samples contain radioactivity associated with natural background/cosmic radioactivity(e.g. K-40, Th-234, and Be-7). Gross beta results for drinking water and air are due to naturalbackground. Gamma emitting radionuclides. which can be attributed to natural backgroundsources, are not indicated in this report.

Results and interpretation of the data for all of the samples analyzed during 2003 arepresented in the following sections. Assessment of pre-operational and operational datarevealed no changes to environmental radiation levels. There were no measurable radiologicalimpacts on the environment due to PVNGS operations in 2003.

8.1. Air Particulates

Weekly gross beta results, in quarterly format, are presented in Tables 8.1 and 8.2.Historical trend graphs are depicted in Figures 8.1 and 8.2. Gross beta activity rangedfrom 0.011 to 0.071 pCi/M3 . The associated counting error ranged from 0.001 to 0.003pCi/M3. Mean quarterly activity is calculated using weekly activity over a thirteen (13)week period. Also presented in the tables are the weekly mean values of all the sites aswell as the percent relative standard deviation (RSD %) for the data. The findings areconsistent with pre-operational baseline and previous operational results. Figure 8.2shows the results of the gross beta in air from the pre-operational phase compared tothe 1993-2003 gross beta in air results. As can be seen, the indicator sites trendconsistently with the control site. The results are summarized in Table 11.1.

Table 8.3 displays the results of gamma spectroscopy on the quarterly composites. NoCs-134 or Cs-137 was observed.


8.2. Airborne Radioiodine

Tables 8.4 and 8.5 present the quarterly radioiodine results. No airborne radioiodinewas observed in any of the samples.

8.3. Vegetation

Table 8.6 presents gamma isotopic data for the vegetation samples. No gammaemitting radionuclides were observed in any of the samples.

8.4. Milk

Table 8.7 presents gamma isotopic and low level 1-131 data for the goat milk samples.No 1-131 or other gamma emitting radionuclides were observed in any of the samples.

8.5. Drinking Water

Samples were analyzed for gross beta, tritium, and gamma emitting radionuclides.Results of these analyses are presented in Table 8.8. No tritium or gamma emittingradionuclides were detected in any samples. Gross beta activity ranged from less thandetectable to a high of 6.1 pCi/liter ( Chowanec residence, May composite).

8.6. Groundwater

Groundwater samples were analyzed for tritium and gamma emitting radionuclides.Results obtained from the analysis of the samples are presented in Table 8.9.

No tritium or gamma emitting radionuclides were observed in any of the samples.

8.7. Surface Water

Surface water samples from the Reservoir and Evaporation Ponds were analyzed fortritium and gamma emitting radionuclides. The Reservoir contains processed sewagewater from the City of Phoenix and is approximately 80 acres in size. The twoEvaporation Ponds receive mostly circulating water from main turbine condensercooling and are about 250 acres each. Results are presented in Table 8.10. 1-131 wasobserved in Evaporation Pond # I and #2 in each of three (3) monthly compositesamples (10-14 pCi/liter) and five (5) of the Reservoir monthly composite samples (8-19 pCi/liter). 1-131 is a result of radiopharmaceutical 1-131 in the Phoenix sewageeffluent. Low levels of Cs-137 (9-15 pCi/liter) were observed in Evaporation Pond #2in two (2) of the monthly composite samples. These concentrations were consistentwith previous results.

Tritium was routinely observed in Evaporation Ponds I and 2. The highestconcentration in Evaporation Pond #1 was 1619 pCi/liter and the highest concentrationin Evaporation Pond #2 was 1704 pCi/liter. Tritium was not identified in the


Reservoir. The tritium identified in the Evaporation Ponds has been attributed to plantgaseous effluent releases and secondary plant liquid releases.

WRF influent (Phoenix sewage effluent) samples collected by the WRF were analyzedfor gamma emitting radionuclides and tritium. The results, presented in Table 8.10,demonstrate that I-131 was observed routinely. The highest I-131 concentration was88 pCi/liter (week of March 18th). The results are consistent with assays from theprevious years. None of the samples analyzed indicated the presence of tritium.

Table 8.10 also presents gamma spectroscopy and tritium measurements of samplescollected from Sedimentation Basin #2. This basin collects rain waters from site runoffand was dry for most of the year. Tritium was detected in six (6) samples ranging from479 to 1137 pCi/liter. The tritium in this basin has been attributed to plant gaseouseffluent releases and secondary plant liquid releases.

8.8. Sludge and Sediment

8.8.1. WORF Centrifuge waste sludge

Sludge samples were obtained from the WRF centrifuge and analyzed bygamma spectroscopy. 1-131 in the WRF waste centrifuge sludge is consistentwith historical values and, as previously discussed, is due toradiopharmaceuticals in the WRF influent. 1-131 was present in all fifty (50)samples ranging from 452 to 1935 pCi/kg.

In-i 1 1 was also identified in the sludge in thirteen (13) samples. The highestconcentration was 72 pCi/liter. It was previously established that In-I I I is inuse in the Phoenix area as a radiopharmaceutical. Results for WRF centrifugewaste sludge can be found in Table 8.11.

8.8.2. Evaporation Ponds #1 and #2 sediment

A set of ten (10) Evaporation Pond samples, five (5) from each pond,indicated low levels of Co-60 and Cs-137 in Evaporation Ponds I and 2. Theconcentrations were consistent with historical values. Sample results can befound in Table 8.11.


8.8.3. Cooling Tower sludge

Sludge originating from the Units 3 cooling towers and/or circulating watercanal was disposed of in the WRF sludge landfill during 2003. Sample resultscan be found in Table 8.11.

8.9. Data Trends

Figures 8.1-8.5 present data in graphical format. Historical data are displayed forcomparison where practical.


TABLE 8.1 PARTICULATE GROSS BETA IN AIR 1st - 2nd QUARTERODCM required samples denoted by *

units arc pCi/m3

;1st Quarter(control)

START STOP Site Site Site Site Site Site Site Site Site

Week# DATE DATE 4 6A* 14A* 15* 17A 21 29* 35 40* Mean RSD (%)

I 31-Dec-02 6-Jan-03 0.033 0.030 0.029 0.026 0.025 0.031 0.029 0.026 0.026 0.028 9.72 6-Jan-03 13-Jan-03 0.053 0.054 0.054 0.044 0.047 0.051 0.055 0.050 0.052 0.051 7.1

3 13-Jan-03 21-Jan-03 0.041 0.041 0.039 0.037 0.036 0.039 0.039 0.038 0.037 0.039 4.54 21-Jan-03 27-Jan-03 0.040 0.045 0.042 0.044 0.039 0.041 0.043 0.045 0.042 0.042 5.0

5 27-Jan-03 3-Feb-03 0.042 0.047 0.041 0.040 0.042 0.038 0.035 0.038 0.037 0.040 8.8

6 3-Feb-03 10-Feb-03 0.032 0.029 0.028 0.027 0.025 0.028 0.028 0.028 0.029 0.028 6.67 10-Feb-03 18-Feb-03 0.026 0.026 0.027 0.027 0.026 0.028 0.027 0.024 0.024 0.026 5.28 18-Feb-03 24-Feb-03 0.031 0.032 0.031 0.031 0.029 0.032 0.031 0.037 0.030 0.032 7.1

9 24-Feb-03 3-Mar-03 0.013 0.012 0.011 0.012 0.011 0.014 0.012 0.012 0.012 0.012 7.710 3-Mar-03 10-Mar-03 0.027 0.027 0.028 0.026 0.024 0.026 0.028 0.025 0.025 0.026 5.3

1 1 10-Mar-03 18-Mar-03 0.037 0.035 0.036 0.033 0.030 0.035 0.034 0.032 0.032 0.034 6.612 18-Mar-03 24-Mar-03 0.025 0.025 0.027 0.024 0.023 0.027 0.024 0.025 0.025 0.025 5.3

13 24-Mar-03 31-Mar-03 0.025 0.024 0.024 0.025 0.021 0.034 0.023 0.023 0.023 0.025 15.0

Mean 0.033 0.033 0.032 0.030 0.029 0.033 0.031 0.031 0.030 0.031 4.12ndQ = u-rter.

(control)


Week DATE DATE 4 6A* 14A* 15* 17A 21 29* 35 40* Mean RSD (%)

14151617181920

212223242526

31 -Mar-03 7-Apr-03 0.0247-Apr-03 14-Apr-03 0.03014-Apr-03 21-Apr-03 0.01821-Apr-03 28-Apr-03 0.02228-Apr-03 5-May-03 0.0265-May-03 13-May-03 0.02813-May-03 20-May-03 0.041

0.022 0.022 0.020 0.022 0.0280.025 0.025 0.027 0.027 0.0350.019 0.020 0.019 0.017 0.0230.023 0.023 0.024 0.022 0.0280.023 0.022 0.024 0.025 0.0290.025 0.025 0.024 0.024 0.0270.038 0.042 0.036 0.039 0.044

0.0220.0280.0190.0240.0240.0240.040

0.0440.0370.0380.0340.0280.035

0.024 0.022 0.0230.027 0.027 0.0280.022 0.018 0.0190.024 0.022 0.0240.025 0.024 0.0250.028 0.025 0.0260.040 0.036 0.040

0.046 0.041 0.044

0.040 0;038 0.0390.036 0.035 0.0350.032 0.031 0.0330.028 0 026 0.0270.035 0.035 0.034

9.911.010.08.08.16.56.7

5.96.24.712.012.44.4

20-May-03 27-May-03 0.047 0.042 0.045 0.041 0.048 0.046

27-May-03 2-Jun-03 0.041 0.039 0.036 0.043 0.037 0.0422-Jun-03 9-Jun-03 0.034 0.035 0.033 0.035 0.035 0.0389-Jun-03 16-Jun-03 0.034 0.030 0.030 0.030 0.030 0.04216-Jun-03 23-Jun-03 0.030 0.024 0.026 0.025 0.025 0.03523-Jun-03 30-Jun-03 0.034 0.032 0.035 0.034 0.033 0.031

Mean 0.031 0.029 0.030 0.029 0.030 0.034 0.031 0.031 0.029 0.030 5.7


29

TABLE 8.2 PARTICULATE GROSS BETA IN AIR 3rd - 4th QUARTERODCM required samples denoted by *

units are pCUm3

,- 3rd Quarter(control)


Week # DATE DATE 4 6A* 14A* 15* 17A 21 29* 35 40* Mean RSD (%)27 30-Jun-03 7-Jul-03 0.034 0.034 0.036 0.035 0.034 0.036 0.038 0.033 0.029 0.034 7.328 7-Jul-03 14-Jul-03 0.038 0.037 0.040 0.041 0.039 0.034 0.038 0.037 0.036 0.038 5.629 14-Jul-03 21-Jul-03 0.046 0.044 0.045 0.047 0.047 0.045 0.045 0.043 0.041 0.045 4.330 21-Jul-03 28-Jul-03 0.043 0.044 0.044 0.042 0.043 0.042 0.041 0.043 0.044 0.043 2.531 28-Jul-03 4-Aug-03 0.036 0.036 0.034 0.034 0.033 0.033 0.034 0.034 0.033 0.034 3.432 4-Aug-03 12-Aug-03 0.038 0.039 0.038 0.038 0.038 0.036 0.041 0.040 0.039 0.039 3.733 12-Aug-03 19-Aug-03 0.045 0.043 0.044 0.046 0.040 0.041 0.043 0.042 0.039 0.043 5.434 19-Aug-03 26-Aug-03 0.029 0.029 0.032 0.034 0.031 0.032 0.034 0.032 0.031 0.032 5.735 26-Aug-03 2-Sep-03 0.031 0.031 0.030 0.031 0.030 0.031 0.031 0.033 0.030 0.031 3.036 2-Sep-03 9-Sep-03 0.038 0.037 0.034 0.036 0.036 0.032 0.036 0.040 0.035 0.036 6.437 9-Sep-03 16-Sep-03 0.036 0.035 0.033 0.037 0.036 0.037 0.035 0.035 0.030 0.035 6.338 16-Sep-03 23-Sep-03 0.040 0.044 0.041 0.041 0.041 0.039 0.039 0.039 0.037 0.040 4.939 23-Sep-03 30-Sep-03 0.040 0.040 0.039 0.041 0.039 0.042 0.041 0.040 0.038 0.040 3.1

Mean 0.038 0.038 0.038 0.039 0.037 0.037 0.038 0.038 0.036 0.038 2.4-- - 4th Quarter.,

(control)


Week # DATE DATE 4 6A* 14A* 15* 17A 21 29* 35 40* Mean RSD (%)40 30-Sep-03 7-Oct-03 0.047 0.047 0.042 0.047 0.044 0.044 0.047 0.047 0.043 0.045 4.541 7-Oct-03 14-Oct-03 0.036 0.039 0.036 0.037 0.036 0.032 0.039 0.036 0.034 0.036 6.142 14-Oct-03 21-Oct-03 0.054 0.061 0.052 0.058 0.054 0.047 0.057 0.057 0.051 0.055 7.743 21-Oct-03 28-Oct-03 0.057 0.059 0.055 0.054 0.057 0.051 0.056 0.050 0.033 0.052 15.044 28-Oct-03 4-Nov-03 0.036 0.037 0.037 0.036 0.036 0.035 0.039 0.033 0.036 0.036 4.545 4-Nov-03 10-Nov-03 0.039 0.042 0.034 0.034 0.035 0.033 0.035 0.034 0.035 0.036 8.246 10-Nov-03 17-Nov-03 0.032 0.032 0.031 0.032 0.032 0.031 0.034 0.028 0.033 0.032 5.247 17-Nov-03 24-Nov-03 0.033 0.037 0.030 0.034 0.032 0.030 0.033 0.027 0.031 0.032 8.948 24-Nov-03 2-Dec-03 0.048 0.048 0.042 0.046 0.046 0.043 0.045 0.034 0.043 0.044 9.849 2-Dec-03 9-Dcc-03 0.065 0.071 0.058 0.062 0.066 0.058 0.059 0.045 0.054 0.060 12.650 9-Dec-03 16-Dec-03 0.022 0.022 0.020 0.024 0.021 0.018 0.021 0.017 0.020 0.021 10.451 16-Dec-03 22-Dec-03 0.042 0.038 0.039 0.033 0.041 0.038 0.040 0.032 0.035 0.038 9.352 22-Dec-03 29-Dec-03 0.027 0.028 0.023 0.024 0.023 0.022 0.025 0.020 0.023 0.024 10.3

Mean 0.041 0.043 0.038 0.040 0.040 0.037 0.041 0.035 0.036 0.039 6.6AnnualAverage 0.036 0.036 0.034 0.035 0.034 0.035 0.035 0.034 0.033 0.035 2.8


30

TABLE 8.3 GAMMA IN AIR FILTER COMPOSITES

ODCM required samples denoted by *units are pCi/m3

(control)QUARTER Site Site Site Site Site Site Site Site SiteENDPOINT NUCLIDE 4 6A* 14A* 15* 17A 21 29* 35 40*

31-Mar-03 Cs-134 <0.0031 <0.0039 <0.0060 <0.0031 <0.0047 <0.0025 <0.0043 <0.0033 <0.0059

Cs-137 <0.0021 <0.0031 <0.0031 <0.0033 <0.0039 <0.0027 <0.0032 <0.0005 <0.003230-Jun-03 Cs-134 <0.0040 <0.0014 <0.0036 <0.0067 <0.0021 <0.0015 <0.0026 <0.0050 <0.0016

Cs-137 <0.0030 <0.0043 <0.0031 <0.0031 <0.0029 <0.0049 <0.0030 <0.0048 <0.002430-Sep-03 Cs-134 <0.0049 <0.0037 <0.0047 <0.0062 <0.0055 <0.0014 <0.0048 <0.0048 <0.0047

Cs-137 <0.0047 <0.0039 <0.0051 <0.0032 <0.0031 <0.0053 <0.0046 <0.0046 <0.004229-Dec-03 Cs-134 <0.0047 <0.0032 <0.0044 <0.0033 <0.0013 <0.0032 <0.0057 <0.0032 <0.0049

Cs-137 <0.0035 <0.0026 <0.0023 <0.0034 <0.0037 <0.0031 <0.0017 <0.0029 <0.0029

Quarterly sample results include all samples except those determined to be invalid.


31

TABLE 8.4 RADIOTODINE IN AIR 1st - 2nd QUARTER

ODCM required samples denoted by *units are pCi/M3

1st Quarter:. i -(control) required LLD <0.070

START STOPDATE DATE

Site4

Site Site Site Site6A* 14A* 15* 17A

Site21

Site29*

Site Site35 40*Week #

4I2345678910I11213

31 -Dec-026-Jan-0313-Jan-032 1-Jan-0327-Jan-033-Feb-0310-Feb-0318-Feb-0324-Feb-033-Mar-0310-Mar-0318-Mar-0324-Mar-03

6-Jan-0313-Jan-0321-Jan-0327-Jan-033-Feb-0310-Feb-0318-Feb-0324-Feb-033-Mar-0310-Mar-0318-Mar-0324-Mar-0331 -Mar-03

<0.045<0.029<0.057<0.054<0.059<0.048<0.021<0.045<0.034<0.035<0.049<0.033<0.044

<0.042 <0.037 <0.037 <0.047 <0.055<0.027 <0.021 <0.020 <0.027 <0.044<0.030 <0.041 <0.029 <0.039 <0.027<0.047 <0.067 <0.060 <0.067 <0.054<0.059 <0.036 <0.047 <0.052 <0.068<0.047 <0.058 <0.054 <0.036 <0.041<0.026 <0.049 <0.038 <0.012 <0.025<0.065 <0.067 <0.044 <0.069 <0.057<0.069 <0.054 <0.033 <0.045 <0.033<0.033 <0.043 <0.024 <0.037 <0.043<0.045 <0.032 <0.031 <0.063 <0.030<0.046 <0.016 <0.053 <0.065 <0.047<0.040 <0.052 <0.057 <0.039 <0.065

<0.025<0.026<0.055<0.061<0.046<0.043<0.057<0.064<0.047<0.046<0.055<0.066<0.035

<0.051 <0.039<0.040 <0.034<0.033 <0.035<0.043 <0.050<0.045 <0.059<0.054 <0.032<0.033 <0.020<0.042 <0.046<0.041 <0.064<0.037 <0.050<0.035 <0.037<0.045 <0.067<0.046 <0.035

2nd Quarter . - ;(control)

START STOPDATE DATE

Site4

Site Site Site Site Site6A* 14A* 15* 17A 21

Site29*

Site Site35 40*Week #

914151617181920212223242526

31-Mar-03 7-Apr-037-Apr-03 14-Apr-0314-Apr-03 21-Apr-0321-Apr-03 28-Apr-0328-Apr-03 5-May-035-May-03 13-May-0313-May-03 20-May-0320-May-1 3 27-May-0327-May-03 2-Jun-03

2-Jun-03 9-Jun-039-Jun-03 16-Jun-0316-Jun-03 23-Jun-0323-Jun-03 30-Jun-03

<0.034<0.061<0.022<0.044<0.056<0.022<0.031<0.060<0.065<0.046<0.040<0.024<0.036

<0.012 <0.049 <0.026 <0.064 <0.041<0.036 <0.045 <0.036 <0.062 <0.038<0.042 <0.040 <0.037 <0.048 <0.029<0.057 <0.049 <0.039 <0.065 <0.041<0.033 <0.048 <0.029 <0.049 <0.034<0.043 <0.023 <0.043 <0.037 <0.042<0.029 <0.039 <0.031 <0.039 <0.031<0.057 <0.044 <0.041 <0.043 <0.065<0.056 <0.059 <0.039 <0.034 <0.052<0.058 <0.054 <0.033 <0.060 <0.063<0.052 <0.0 13 <0.042 <0.056 <0.029<0.050 <0.037 <0.034 <0.053 <0.042<0.037 <0.025 <0.022 <0.031 <0.049

<0.059<0.052<0.034<0.055<0.054<0.023<0.044<0.050<0.037<0.041<0.069<0.032<0.050

<0.025 <0.029<0.033 <0.069<0.039 <0.034<0.014 <0.069<0.028 <0.042<0.020 <0.019<0.027 <0.036<0.055 <0.034<0.061 <0.058<0.048 <0.042<0.033 <0.038<0.035 <0.038<0.040 <0.035


32

TABLE 8.5 RADIOTODINE IN AIR 3rd - 4th QUARTER

ODCM required samples denoted by *units are pCi/rm3

t��-'='--t...'!=-x--tYO7,eRi,_ s-5--F.:. w_ = _--: s_==-r __ . .3rd Quarter .' - _ .

(control) required LLD <0.070


Week# DATE DATE 4 6A* 14A* 15* 17A 21 29* 35 40*

27282930313233343536373839

30-Jun-03 7-Jul-03 <0.0287-Jul-03 14-Jul-03 <0.04014-Jul-03 21-Jul-03 <0.03121-Jul-03 28-Jul-03 <0.03128-Jul-03 4-Aug-03 <0.0464-Aug-03 12-Aug-03 <0.02912-Aug-03 19-Aug-03 <0.04719-Aug-03 26-Aug-03 <0.05326-Aug-03 2-Sep-03 <0.0622-Sep-03 9-Sep-03 <0.0499-Sep-03 16-Sep-03 <0.03816-Sep-03 23-Sep-03 <0.04623-Sep-03 30-Sep-03 <0.047

<0.052<0.047<0.055<0.027<0.034<0.042<0.036<0.037<0.036<0.038<0.012<0.053<0.055

<0.047 <0.039 <0.036 <0.035 <0.040 <0.037 <0.034<0.047 <0.026 <0.053 <0.007 <0.062 <0.032 <0.013<0.047 <0.034 <0.055 <0.042 <0.055 <0.029 <0.046<0.032 <0.035 <0.049 <0.033 <0.033 <0.023 <0.012<0.056 <0.055 <0.048 <0.056 <0.059 <0.064 <0.054<0.046 <0.038 <0.046 <0.027 <0.053 <0.024 <0.029<0.046 <0.023 <0.047 <0.036 <0.032 <0.027 <0.066<0.049 <0.068 <0.044 <0.062 <0.069 <0.037 <0.054<0.037 <0.065 <0.053 <0.037 <0.061 <0.046 <0.048<0.049 <0.041 <0.062 <0.034 <0.053 <0.044 <0.053<0.046 <0.035 <0.042 <0.037 <0.059 <0.024 <0.045

<0.056 <0.036 <0.063 <0.036 <0.056 <0.031 <0.040<0.047 <0.055 <0.067 <0.067 <0.043 <0.070 <0.014

. , ' 4thQuarter- -Quar-er

(control) required LLD <0.070


Week # DATE DATE 4 6A* 14A* 15* 17A 21 29* 35 40*

404142434445464748495051

52

30-Sep-03 7-Oct-03 <0.0447-Oct-03 14-Oct-03 <0.02614-Oct-03 21-Oct-03 <0.04621-Oct-03 28-Oct-03 <0.03728-Oct-03 4-Nov-03 <0.0364-Nov-03 10-Nov-03 <0.06510-Nov-03 17-Nov-03 <0.03217-Nov-03 24-Nov-03 <0.04024-Nov-03 2-Dec-03 <0.0512-Dec-03 9-Dec-03 <0.0319-Dec-03 16-Dec-03 <0.02616-Dec-03 22-Dec-03 <0.05122-Dec-03 29-Dec-03 <0.040

<0.046 <0.053 <0.059 <0.033 <0.045 <0.060 <0.050 <0.055<0.037 <0.050 <0.031 <0.049 <0.039 <0.046 <0.037 <0.049<0.043 <0.045 <0.031 <0.046 <0.029 <0.046 <0.027 <0.055<0.051 <0.066 <0.035 <0.055 <0.036 <0.051 <0.036 <0.047

<0.048 <0.046 <0.013 <0.050 <0.029 <0.046 <0.064 <0.063<0.015 <0.056 <0.064 <0.031 <0.015 <0.046 <0.052 <0.039<0.042 <0.034 <0.034 <0.060 <0.033 <0.055 <0.031 <0.034<0.049 <0.039 <0.039 <0.049 <0.042 <0.070 <0.035 <0.043<0.030 <0.028 <0.038 <0.053 <0.033 <0.036 <0.043 <0.037<0.048 <0.034 <0.049 <0.032 <0.060 <0.031 <0.052 <0.054<0.033 <0.033 <0.033 <0.012 <0.032 <0.068 <0.025 <0.057<0.057 <0.034 <0.014 <0.050 <0.057 <0.034 <0.014 <0.037

<0.063 <0.045 <0.036 <0.052 <0.019 <0.062 <0.033 <0.013


33

TABLE 8.6 VEGETATION

ODCM required samples denoted by *units are pCi/kg, wet

<601-131LOCATION TYPE DATE

COLLECTED

<60Cs-134

<80Cs-137

*0

CHOWANECRESIDENCE

(Site #52)*No Samples Available

.9

DUNCANFAMILYFARMS

(Site #62)*

LettucePurple CabbageGreen CabbageGreen CabbagePurple CabbageEndive LettuceGreen CabbagePurple CabbageGreen CabbagePurple CabbageSavoy CabbageGreen CabbageGreen Cabbage

EscaroleRed Cabbage

Green CabbageEscarole

Endive LettuceRed Cabbage

17-Jan-0317-Jan-0317-Jan-0312-Feb-0312-Feb-0312-Feb-0312-Mar-0312-Mar-0317-Apr-0317-Apr-0317-Apr-0314-May-0317-Oct-0314-Nov-0314-Nov-0314-Nov-0312-Dec-0312-Dec-0312-Dec-03

<46<37<47<39<42<46<46<47<47<45<57<40<59<56<41<43<39<45<48

<53<35<42<42<47<47<51<30<33<54<47<32<52<31<30<59<51<37<33

<60<47<42<54<58<56<69<51<42<42<72<37<79<67<45<51<71<65<50

I.

MCCOYRESIDENCE

(Site #47)*

Lettuce 17-Apr-03 <49 <55 <61


TABLE 8.7 MILK

ODCM1 required samples denoted by *units are pCi/liter

SAMPLE DATE <1 <15 <18 <60 <15LOCATION COLLECTED 1-131 Cs-134 Cs-137 Ba-140 La-140

23-Apr-03 NO SAMPLES AVAILABLEPAINTER 21-May-03 <0.2 <12 <9 <23 <12

GOATS 19-Jun-03 <0.3 <8 <7 <22 <9(Site#51)* 24-Jul-03 <0.5 <11 <10 <27 <13

20-Aug-03 <0.6 <10 <10 <23 <1117-Sep-03 <1.0 <1 <1 <3 <122-Oct-03 <1.0 <1 <1 <3 <1

21-Nov-03 NO SAMPLES AVAILABLE

17-Dec-03 NO SAMPLES AVAILABLE23-Apr-03 <0.5 <13 <10 <28 <1321-May-03 <0.3 <9 <8 <20 <1019-Jun-03 <0.3 <10 <8 <25 <12

BARBER 24-Jul-03 <0.4 <6 <5 <13 <6GOATS 20-Aug-03 <0.4 <7 <6 <15 <8

(Site #53)* 17-Sep-03 <1.2' <1 <1 <4 <122-Oct-03 <1.0 <1 <1 < <1

21-Nov-03 <1.0 <1 <1 <3 <1

17-Dec-03 <1.0 <1 <1 <3 <I

Notes:' Required LLD of 1.0 pCi/liter was not achieved. CRDR No. 2646728 was initiatedto correct the deficiency.


TABLE 8.8 DRINKING WATER

ODCNI required samples denoted by *units are pCi/liter

<2000

SAMPLE MONTH <15 <15 <30 <15 <30 <15 <30 <15 <15 <18 <60 <15 QTRLY <4.0LOCATION ENDPOINT Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 13a-140 La-140 H-3 Gross Beta

BERRYMANRESIDENCE(SITE #48)*

27-Jan-03 <12 <12 <25 <15 <29 <12 <22 <14 <12 <12 <45 <13 - : <2.824-Feb-03 <10 <10 <18 <13 <21 <11 <14 <8 <9 <11 <37 <14 L. <2.831-Mar-03 <14 <12 <24 <13 <30 <15 <21 <12 <13 <14 <39 <12 <268 <3.228-Apr-03 <10 <11 <29 <12 <28 <13 <21 <9 <12 <13 <37 <15 f-T] <2.827-May-03 <10 <11 <22 <11 <25 <12 <19 <11 <10 <11 <42 <15 L -u 2.8 ± 1.830-Jun-03 <12 <15 <24 <13 <29 <14 <13 <12 <15 <15 <39 <15 <260 3.6+ 1.928-Jul-03 <9 <10 <18 <11 <25 <9 <17 <9 <8 <10 <26 <13 f <3.6

26-Aug-03 <13 <13 <20 <15 <27 <13 <21 <12 <11 <12 <42 <13 E <3.230-Sep-03 <11 <9 <16 <10 <23 <13 <19 <9 <10 <12 <37 <15 <278 <3.028-Oct-03 <12 <11 <21 <12 <29 <14 <18 <12 <12 <13 <40 <10 F 3.2± 1.624-Nov-03 <12 <12 <20 <12 <29 <13 <19 <12 <11 <13 <43 <14 Lxig <2.729-Dec-03 <12 <12 <27 <15 <24 <14 <19 <11 <13 <13 <37, <12 <279 <2.8

GAVETTERESIDENCE

(SITE #55)

27-Jan-03 <9 <10 <19 <12 <21 <II <16 <10 <10 <10 <33 <15 3.3 + 1.524-Feb-03 <11 <11 <18 <15 <26 <13 <20 <11 <11 <12 <43 <12 3.3±1.531-Mar-03 <14 <12 <25 <15 <25 <14 <22 <11 <10 <12 <45 <13 <269 3.2+ 1.728-Apr-03 <13 <11 <27 <12 <27 <15 <20 <11 <13 <13 <49 <14 3.4+ 1.527-May-03 <9 <10 <18 <9 <22 <10 <16 <10 <8 <11 <32 <14 L j 3.8 ± 1.530-Jun-03 <11 <14 <29 <14 <30 <15 <22 <13 <12 <10 <42 <14 <260 5.2± 1.528-Jul-03 <12 <11 <20 <10 <24 <12 <19 <10 <12 <11 <34 <14 [ <2.9

26-Aug-03 <12 <11 <23 <11 <28 <13 <17 <10 <10 <11 <36 <15 L : <2.630-Sep-03 <11 <8 <29 <13 <24 <14 <20 <10 <9 <13 <39 <13 <278 <2.428-Oct-03 <9 <9 <19 <10 <24 <12 <16 <7 <9 <10 <32 <15 f',- 4.9±1.424-Nov-03 <10 <15 <23 <13 <30 <14 <23 <12 <11 <14 <48 <15L 1 3.7 ± 1.629-Dec-03 <11 <9 <20 <13 <22 <12 <17 <10 <8 <11 <30 <15 <280 4.7± 1.6


36

TABLE 8.8 DRINKING WATER

ODCNI required samples denoted by *units are pCi/liter

<2000

SAMPLE I MONT!! <15 <15 <30 <15 <30 <15 <30 <15 <15 <18 <60 <15 QTRLY <4.0LOCATION ENDPOINT Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 H-3 Gross Beta

McARTHURRESIDENCE(SITE #46)*

I.

27-Jan-0324-Feb-0331-Mar-0328-Apr-0327-May-0330-Jun-0328-Jul-03

26-Aug-0330-Sep-0328-Oct-0324-Nov-03

29-Dec-0327-Jan-0324-Feb-0331 -Mar-0328-Apr-0327-May-0330-Jun-0328-Jul-03

26-Aug-0330-Sep-0328-Oct-0324-Nov-0329-Dec-03

<13 <13 <29 <10 <29 <15 <23 <15<11 <12 <21 <12 <30 <12 <22 <13<11 <12 <23 <11 <27 <13 <21 <11<13 <11 <24 <11 <30 <14 <20 <11<9 <9 <20 <9 <19 <9 <15 <9<7 <9 <16 <11 <21 <10 <15 <9

<13 <13 <25 <15 <27 <13 <24 <12<13 <11 <25 <15 <25 <13 <23 <12<13 <11 <23 <14 <28 <12 <22 <13<13 <13 <24 <15 <30 <14 <22 <11<9 <9 <18 <10 <19 <10 <15 <8

<11 <13 <20 <14 <29 <12 <21 <12

<12 <13<11 <11<11 <13<11 <12<9 <9<8 <9<12 <13<12 <12<11 <14<12 <15<8 <8

<12 <14

<41 <15 4.5 ± 1.6<47 <14 3.3±1.5<40 <13 <268 <2.5<45 <13 [...T 2.8 + 1.5<29 <11 L 2.8±1.4<31 <13 <262 3.4± 1.4<43 <13 ' .71 <2.8<40 <14 L <2.5<44 <15 <274 <2.3<43 <14 : -1 3.7 + 1.3<29 <13 L _ 2.6± 1.6

<46 <15 <279 <2.2

CHOWANECRESIDENCE(SITE #49) *

<14 <13 <28 <15 <25 <14 <20 <13<12 <10 <24 <14 <24 <12 <21 <11<12 <11 <28 <14 <29 <13. <20 <11<11 <14 <21 <14 <26 <11 <18 <10<15 <13 <29 <12 <30 <14 <22 <13<11 <13 <22 <15 <27 <12 <22 <12<12 <12 <26 <15 <27 <11 <19 <11<12 <9 <23 <12 <22 <9 <15 <9<10 <11 <23 <12 <29 <12 <21 <11<13 <10 <29 <13 <30 <10 <19 <12<13 <10 <23 <10 <30 <14 <22 <12<12 <13 <27 <14 <29 <14 <24 <14

<11 <14<12 <12<12 <11<10 <14<12 <12<10 <12<11 <12<10 <12<9 <12<10 <13<11 <12<13 <17

<43 <15 2.7 + 1.4<35 <15 L - <2.2<48 <14 <268 <2.5<40 <14 r-: :1 <2.2<47 <12 L- 1 6.1 + 1.6<37 <15 <263 <2.1<47 <15 r-7- " i 2.8<32 <15 LL-J <2.4<26 <15 <277 <2.3<44 <11 2.8 ± 1.3<40 <13 <281 <2.3<47 <15 <281 c2.2


TABLE 8.9 GROUNDWATER

ODCM required samples denoted by *units are pCi/liter

SAMPLE DATE <15 <15 <30 <15 <30 <15 <30 <15 <15 <18

LOCATION COLLECTED Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137

<60 <15 <2000

Ba-140 La-140 H-3

WELL 27-Jan-03 <9 <10 <20 <11 <20 <12 <15 <10 <8 <10 <38 <15 <28527ddc 28-Apr-03 <13 <14 <26 <15 <30 <15 <22 <13 <12 <15 <48 <14 <283

(Site #57)* 28-Jul-03 <11 <12 <26 <10 <28 <13 <19 <12 <10 <14 <42 <15 <26328-Oct-03 <13 <10 <29 <12 <27 <14 <19 <12 <12 <12 <41 <15 <273

WELL34abb

(Site #58)*

27-Jan-03 <12 <11 <17 <12 <27 <14 <19 <12 <11 <1128-Apr-03 <12 <12 <24 <12 <23 <14 <21 <12 <8 <1228-Jul-03 <10 <11 <21 <14 <26 <15 <19 <11 <10 <1128-Oct-03 <12 <13 <30 <10 <28 <14 <25 <13 <13 <13

<42 <15 <284<40 <15 <282<39 <15 <263<51 <15 <276


38

TABLE 8.10 SURFACE WATER


SAMPLE I MONTH <15 <15 <30 <15 <30 <15 <30 <15 <15 <18 <60 <15LOCATION ENDPOINT Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 r-131 Cs-134 Cs-137 Ba-140 La-140

<3000H-3

4

RESERVOIR(Site #60) *

27-Jan-03 <11 <11 <22 <9 <17 <11 <17 12 + 1024-Feb-03 <13 <13 <23 <11 <27 <12 <24 17+ 1231-Mar-03 <13 <11 <25 <15 <28 <14 <21 19± 1128-Apr-03 <13 <11 <25 <11 <28 <11 <20 <1427-May-03 <12 <11 <23 <13 <23 <11 <17 8±h 730-Jun-03 <12 <12 <23 <14 <26 <12 <21 <1528-Jul-03 <10 <11 <28 <12 <26 <11 <19 <12

26-Aug-03 <12 <11 <21 <15 <25 <11 <18 11 + 1030-Sep-03 <12 <9 <23 <10 <27 <10 <21 <1328-Oct-03 <11 <10 <22 <9 <25 <12 <19 <1124-Nov-03 <14 <13 <25 <11 <30 <13 <20 <1429-Dec-03 <9 <10 <22 <10 <26 <11 <21 <10

<11<12<11<11<10<14<10<10<9<9<11<9

<12<13<13<12<12<13<12<10<13<11<13<10

<35<43<46<45<35<46<42<38<41<35<48<32

<14<14<14 <270<15 77

<10

<11 <263<15<11 L _<15 <282<15 L -

<15 <2804

EVAP POND 1(Site #59) *

27-Jan-03 <13 <11 <27 <12 <29 <15 <20 <1324-Feb-03 <15 <14 <28 <12 <26 <13 <21 104 1131-Mar-03 <11 <13 <23 <15 <29 <13 <19 14± 1028-Apr-03 <12 <12 <26 <15 <25 <10 <21 10± 1327-May-03 <13 <11 <27 <10 <30 <11 <21 <1330-Jun-03 <11 <11 <23 <13 <27 <12 <16 <1228-Jul-03 <14 <11 <29 <12 <29 <15 <26 <12

26-Aug-03 <12 <13 <30 <13 <27 <12 <22 <1230-Sep-03 <10 <11 <25 <9 <30 <13 <23 <1128-Oct-03 <11 <13 <26 <15 <27 <12 <21 <1124-Nov-03 <10 <11 <25 <11 <30 <11 <20 <1129-Dec-03 <13 <14 <24 <15 <29 <12 <23 <13

<11<10<9<11<10<9<12<11<10<11<10<12

<12<14<13<13<11<12<14<12<14<12<12<14

<41<40<44<39<41<37<41<37<39<39<38<41

<14 , , _, 1<13 - i.L<14 774± 177<11FT7<12<10 1263±: 177<12<12 V3<13 1093 + 185<14 .<12 .-. ;J<12 1619+ 169

4

EVAP POND 2(Site #63) *

27-Jan-03 <10 <10 <20 <15 <22 <11 <19 <924-Feb-03 <11 <12 <26 <10 <28 <13 <19 <1031-Mar-03 <13 <10 <24 <15 <30 <12 <22 <1328-Apr-03 <14 <13 <25 <11 <30 <11 <22 <1127-May-03 <13 <12 <26 <12 <30 <12 <22 <1030-Jun-03 <12 <12 <30 <12 <25 <11 <20 <1228-Jul-03 <12 <12 <26 <14 <30 <11 <20 <1226-Aug-03 <12 <13 <22 <12 <30 <11 <21 <930-Sep-03 <11 <9 <22 <13 <28 <9 <17 14±928-Oct-03 <10 <9 <24 <14 <27 <10 <18 12±924-Nov-03 <11 <11 <24 <10 <30 <10 <18 11 ± 829-Dec-03 <13 <12 <27 <12 <30 <12 <22 <12

<9<10<12<10<9<12<11<11<8<9<11<12

<89 + 10

<16<16<14<16<14

15+8<13<13<15<16

<36<39<42<39<40<43<40<35<31<34<40<30

<10 L i<15 WL z

<14 1129± 183<12 ......<15 ,.;<13 1200 177<13<14 -<12 1486± 190<9 r<13 ... .<9 1704 +164


TABLE 8.10 SURFACE WATER


SAMPLE DATELOCATION COLLECTED Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 H-3

4.

WRFINFLUENT

7-Jan-0314-Jan-0321 -Jan-0328-Jan-034-Feb-03I 1-Feb-0318-Feb-0325-Feb-034-Mar-03I 1-Mar-0318-Mar-0325-Mar-03I-Apr-038-Apr-0315-Apr-0329-Apr-036-May-0313-May-0320-May-0327-May-033-Jun-0310-Jun-0317-Jun-0324-Jun-0330-Jun-038-Jul-0315-Jul-0322-Jul-0329-Jul-0312-Aug-03

<12 <11 <24 <11 <27 <10 <21 <11 <11<11 <13 <24 <15 <29 <13 <20 26 + 13 <12<15 <13 <24 <12 <30 <12 <18 43 ± 11 <10<10 <11 <24 <15 <27 <13 <24 17± 10 <12<10 <12 <21 <13 <30 <13 <22 55 ± 14 <10<14 <13 <21 <13 <30 <13 <25 42+ 13 <13<10 <7 <19 <12 <25 <9 <14 34 + 9 <8<14 <15 <24 <13 <29 <12 <22 30± 12 <12<14 <11 <22 <13 <27 <13 <24 45 ± 13 <14<13 <10 <20 <15 <29 <14 <19 39 + 15 <11<10 <11 <21 <15 <30 <10 <20 88 + 17 <11<12 <10 <29 <15 <28 <12 <23 75± 17 <12<12 <12 <27 <15 <27 <14 <21 48 ± 14 <13<12 <12 <25 <13 <27 <12 <21 56± 17 <13<10 <12 <23 <14 <19 <11 <21 42 + 13 <11<14 <12 <23 <13 <30 <13 <22 53 ± 14 <12<13 <11 <26 <13 <23 <13 <23 22+ 13 <11<12 <12 <23 <11 <28 <14 <23 16± 11 <12<10 <12 <25 <11 <26 <11 <18 9 + 7 <9<14 <15 <29 <11 <30 <14 <21 24± 13 <14<10 <13 <26 <14 <23 <13 <23 23 + 14 <11<11 <14 <24 <15 <30 <13 <23 30+ 13 <13<12 <11 <20 <8 <26 <12 <16 25± 12 <10<11 <10 <23 <15 <26 <IS <21 38± 11 <11<12 <10 <18 <12 <18 <10 <18 39+ 12 <9<12 <10 <21 <12 <30 <11 <18 22± 10 <11<11 <10 <22 <13 <29 <10 <19 9± 10 <10<12 <11 <24 <14 <29 <13 <21 <12 <10<11 <11 <20 <15 <23 <14 <19 12± 10 <14<10 <13 <26 <13 <29 <12 <17 48 ± 14 <12

<12<15<12<14<12<15<11<14<14<13<12<12<13<14<14<13<14<14<12<16<15<14<11<10<11<12<11<12<16<14

<36<47<40<47<38<36<32<39<44<42<38<45<45<43<42<42<46<38<40<45<40<45<34<43<32<37<38<34<44<38

<15<14<12L<15 <291<13<10

<lo 8<10 <289<15<13<11 L<14 <276<13<15<15 .<12 <275<15<15 . :

<12 <279<15<12<13<15<15 <270<10<15 .t.<9<11 <271<8 E'777


TABLE 8.10 SURFACE NVATER


SAMPLELOCATION

DATECOLLFCTFD Mn-54 Co-5R Fe-S9 Co-60 Zn-65 Nh-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 11-3

WRFINFLUENT(continued)

19-Aug-0326-Aug-032-Sep-039-Sep-0316-Sep-0323-Sep-0330-Sep-0314-Oct-0321 -Oct-0328-Oct-034-Nov-03I l-Nov-0318-Nov-0324-Nov-032-Dec-039-Dec-0316-Dec-0322-Dec-0329-Dec-03

<12 <12 <26 <11 <27 <15 <20<15 <15 <26 <13 <27 <15 <22<8 <9 <23 <11 <22 <12 <16

<11 <12 <25 <15 <20 <13 <18<13 <11 <22 <14 <30 <14 <20<13 <13 <24 <15 <29 <12 <23<13 <11 <26 <15 <30 <15 <25<11 <12 <28 <14 <29 <14 <23<11 <11 <19 <13 <20 <11 <20<13 <12 <25 <13 <21 <12 <22<12 <14 <25 <15 <30 <14 <21<11 <11 <25 <13 <30 <14 <16<12 <14 <26 <12 <26 <13 <23<9 <10 <22 <15 <28 <13 <21

<11 <11 <22 <9 <29 <12 <21<10 <9 <19 <9 <24 <9 <16<9 <8 <19 <14 <19 <10 <15

<12 <12 <21 <9 <26 <11 <18<11 <10 <24 <15 <28 <13 <22

70 ± 16 <1329+ 10 <1363 ± 14 <821 + 10 <1240 + 1233 + 1338 + 1340 + 12

<1315± 1118± 1025 + 15

<1576 ± 1540 ± 1257 ± 1240 4 1049 t1228 + 12

<11<12<12<10<13<10<11<11<11<11<10<8<9<9<10

<14<13<11<13<13<12<14<14<12<12<12<13<13<13<13<11<9

<11<11

<41 <13 t l<48 <11 <284<31 <15<41 <14<40 <13<45 <10<33 <4 <282<40 <12 - : -<39 <15 . ,-:;<39 <15 <284<41 <13<44 <13<39 <15<35 <15 <281<42 <12<31 <14<27 <12<39 <14 .__.<38 <10 286

a

SEDIMENT.BASIN #2

13-Jan-0321-Jan-0318-Feb-0324-Feb-033-Mar-0310-Mar-0318-Mar-0324-Mar-0331 -Mar-037-Apr-0314-Apr-0319-Aug-0326-Aug-03

<11 <11 dl1 <15 <27 <11 dl1<12 <8 <30 <12 <23 <10 <14<11 <10 <21 <10 <21 <10 <16<11 <11 <25 <11 <30 <11 <24<13 <14 <29 <13 <27 <13 <23<11 <12 <27 <13 <29 <14 <23<10 <9 <18 <11 <21 <9 <17<13 <12 <24 <12 <28 <15 <24<13 <11 <25 <14 <30 <14 <21<11 <11 <27 <12 <26 <12 <19<12 <12 <29 <12 <25 <15 <24<11 <12 <24 <15 <27 <11 <20<12 <10 <21 <14 <26 <11 <15

<11<9<9

<11<10<12<9

<14<11<10<11<11<8

<11*

<10<13<8<10<13<12<8

<13<13<10<12<11<10

<10<12<10<12<15<14<11<15<15<12<13<12<9

<41 <15<40 <15<30 <12<37 <11<49 <11<43 <15<30 <15<43 <14<49 <15<41 <15<38 <14<35 <11<35 <15

<287<295<306<299<295<302

1137± 195969 + 1841126± 1931054± 190921 +200

<284<300

<291

479 + 174

2-Sep-03 <11 <12 <28 <11 <26 <10 <24 <13 <13 <41 <14

9-Sep-03 <13 <9 <19 <15 <23 <10 <22 <11 <11 <11 <36 <14


41

TABLE 8.11 SLUDGE/SEDIMENT

ODCM required samples denoted by *units are pCi/kg, wet

SAMPLELOCATION

DATECOLLECTED 1-131 Cs-134 Cs-137 In-III

WRFCENTRIFUGE

WASTE SLUDGE

7-Jan-0314-Jan-0321-Jan-0328-Jan-034-Feb-03I 1-Feb-0318-Feb-0325-Feb-034-Mar-0311-Mar-0318-Mar-0325-Mar-03I-Apr-038-Apr-0315-Apr-0329-Apr-036-May-0313-May-0320-May-0327-May-03

3-Jun-0310-Jun-0317-Jun-0324-Jun-0330-Jun-038-Jul-0315-Jul-0322-Jul-0329-Jul-035-Aug-0312-Aug-0319-Aug-0326-Aug-032-Sep-039-Sep-0316-Sep-0323-Sep-0330-Sep-0314-Oct-0321 -Oct-0328-Oct-034-Nov-0311-Nov-0318-Nov-0324-Nov-032-Dec-039-Dec-0316-Dec-0322-Dec-0329-Dec-03

743 104757 108633 4 98

631 ± 104764* 108843 4 118628 : 90511 + 83

668 100844* 117646 * 88

1168* 1521449* 1761918 2251935 231935*h 1201040 * 1361209 * 156732* 1021054 141602 88722* 1011044* 124741 113812* 112636 95

763* 113512 83672 + 98568 * 77524 * 84827* 1031268* 160951 * 1271203 154814* 1111150 134833* 113461 75869 117559 * 83704 * 101559 85614* 91452* 72

1349* 169903* 1131126* 148652 * 86

708 101

<28<20<32<37<30<28<18<6

<35<21<25<32<23<28<24<23<26<25<21<19<26<20<27<34<6<31<29<23<27<20<16<20<26<17<24<30<27<26<24<20<16<32<24<25<25<25<22<33<22<29

<7<20<31<34<33<39<19<32<23<21<20<27<30<18<35<22<28<8

<30<9

<30<21<26<39<35<42<24<32<31<29<28<16<25<29<17<21<26<28<21<25<21<26<12<27<29<44<26<29<23<40

26 + 19

19 * 21

33 * 32

25* 16

20 * 2422 * 3540 * 22

33*25

36* 25

36* 30

22*13

72 * 2837* 25


42

TABLE 8.11 SLUDGE/SEDIMENT

ODCM required samples denoted by *Units are pCi/kg, wet

DATESAMPLE LOCATION COLLECTED Co-60 Cs-134 Cs-137

(N) 19-Nov-03 31 4 9 <6 <8(E) 23 ± 9 <7 <8

EVAP POND I (S) <8 <9(W) <8 <10(C) <11 <14(N) 19-Nov-03 <11 22+ 13(E) <10 19± 11

EVAP POND 2 (S) <9 23 ± 10(W) 23± 11 <9 20+ 12(C) <11 11± 14

(C)(N)

Sedimentation Basin #2 (E)

(W)

31-Dec-03 <56<53<46<59<48

<44<39<38<46<35

61 + 3570 ±4454 ±43

<7680 ± 33

COOLING TOWER SLUDGE

DATE UNIT APPROXIMATE ISOTOPE ACTIVITY RANGE FRACTION OF SAMPLESVOLUME (yd3 ) (pCi/liter) ABOVE MDA

4-Jun-03 3 356 Co-60 <MDA-328 29 of 32 samples

Cs-137 <MDA-55 14 of 32 samples


43

FIGURE 8.1 HISTORICAL GROSS BETA IN AIR (WEEKLY SYSTEM AVERAGES)

Gross Beta in Air 1993-2003

1.000

0.100

en._

0.010

0.001tn ' 0 '.0 t 00 a%

0a a % 0s C% 0% ON s 0% 0

e c c 0 tj 0 u u 0

- - 0 a 0 0

_ q cn

C> C)

0 0 00m 0 0


FIGURE 8.2 HISTORICAL GROSS BETA IN AIR (ANNUAL SITE TO SITE COMPARISONS) COMPARED TO PRE-OP

control location --- Gross Beta in Air Part iculates- nrc-orerational (1981-1985)0.100 X 1993

-*. 19940.090 -0- 1995

1 19960.080 - 1997

-1998

0.070 1-9- 199920002001

0.060 2002- a--- 2003

0.050

0.040 . _ _

0.030 1-- * - - __* l --

0.020 --

0.010

0.000-t*1W

*0 (#2

t-

Sm 2

Surniple Location

.ci

0s

at)

0%k00nC

(#2 (En

To


45

FIGURE 8.3 GROSS BETA IN DRINKING WATER

10

McArthur (site #46)- Gavette (site #55)

Berryman (site #48)

a) X___|-Chowanec (site #49)_|

C,

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec

NOTES: MDA values plotted as activity (e.g. <2.3 is plotted as 2.3)


46

FIGURE 8.4 SOIL Cs-137 COMPARED TO ONSITE SEDIMENT BASIN #2

250 -

209

200--

"l 150

:.5

U,

50 -

238

67 70 - 63 6 0 6

40 40

__ I0- LLIJ I<MDA [L Iu-T _--- I _ , _ _ , _ _ , _ - I--- - I I I , _

1976 1984 1990 1992 1993 1994 1995 1996 1997 1998 2001 2002 2003onsite onsite

soil avg. soil avg.-

1

(Sedirnentation Basin #2 accepts site storm runoff, no otherganma emitters present)


47

FIGURE 8.5 EVAPORATION POND TRITIUM ACTIVITY


48

9. Thermoluminescent Dosimeter (TLD) Results and Data

The environmental TLD used at PVNGS is the Panasonic Model 812 Dosimeter. The Model812 is a multi-element dosimeter combining two elements of lithium borate and twoelements of calcium sulfate under various filters.

Thermoluminescent dosimeters were placed in forty-eight locations from one to thirty-fivemiles from the PVNGS. TLD locations are shown in Figures 2.1 and 2.2. TLD locations aredescribed in Table 9.1. TLD results for 2003 are presented in Table 9.2. TLD results for 1985through 2003 are presented in graphical form on Figure 9.1 (excluding transit control TLD#45).

Figure 9.2 depicts the environmental TLD results from 2003 as compared to the pre-operational TLD results (excluding indicator location #41 and 43 that were deleted and #46-50 due to no pre-op TLD at these locations for comparison). The site to site comparisonsindicate a direct correlation with respect to pre-operational results. It is evident that theoffsite dose, as measured by TLDs, has not changed since Palo Verde became operational.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT .2003

49

TABLE 9.1 TLD SITE LOCATIONS(distances and directions are relative to Unit 2 in miles)

-

TLD SITE12345

6*789101112131415161718192021222324252627282930313233343536373839404244*

LOCATIONE30

ENE24E21E16

ESEI ISSE31

SE7SSE4

S5SE5

ESE5E5NI

NNE2NE2

ENE2E2

ESE2SE2

SSE2S3

SSW3W5SW4

WSW5SSW4SWI

WSWIWI

WMNWINW1

NNWINW4

NNW5NNW8

N5NNE5NE5

ENE5N3N8

ENE35

LOCATION DESCRIPTIONGoodyearScott-Libby SchoolLiberty SchoolBuckeyePalo Verde SchoolAPS Gila Bend substationOld US 80 and Arlington School RdSouthern Pacific Pipeline Rd.Southern Pacific Pipeline Rd.355th Ave. and Elliot Rd.3 39th Ave. and Dobbins Rd.339th Ave. and Buckeye-Salome Rd.N site boundaryNNE site boundaryNE site boundary, WRF access roadENE site boundaryE site boundaryESE site boundarySE site boundarySSE site boundaryS site boundarySSW site boundaryN of Elliot RdN of Elliot RdN of Elliot RdS of Elliot RdSW site boundaryWSW site boundaryW site boundaryWNW site boundaryNW site boundaryNNW site boundaryS of Buckeye Rd395 dh Ave. and Van Buren St.TonopahWintersburg Rd. and Van Buren St.363rd Ave. and Van Buren St.355th Ave. and Buckeye Rd.343rd Ave. N of Broadway Rd.WintersburgRuth Fisher SchoolEl Mirage


50

TABLE 9.1 TLD SITE LOCATIONS(distances and directions are relative to Unit 2 in miles)

-

TLD SITE45**

4647484950

LOCATIONOnsiteENE30

E35E24

ENEllWNW5

LOCATION DESCRIPTIONCentral Laboratory (lead pig)Litchfield Park SchoolLittleton SchoolJackrabbit TrailPalo Verde Rd.S of Buckeye-Salome Rd.

.

* Site #6 and site #44 are the control locations.** Site #45 is the transit control TLD (stored in lead pig).


TABLE 9.2 2003 ENVIRONMENTAL TLD RESULTSUnits are mrem/std qtr

TLD Site # Ist Quarter 2nd Quarter 3rd Quarter 4th Quarter Average1 22.2 24.0 23.4 23.4 23.32 19.9 20.9 21.0 21.3 20.83 21.4 22.3 22.6 22.9 22.34 20.6 22.4 21.9 21.6 21.65 20.8 20.9 21.5 21.3 21.1

6(control) 24.1 24.9 25.5 25.3 25.07 23.1 24.4 24.0 24.7 24.18 22.4 22.9 22.2 22.4 22.59 26.3 26.0 25.8 26.2 26.110 22.0 22.4 22.7 22.7 22.511 23.2 23.9 24.1 24.4 23.912 22.2 21.8 22.4 22.1 22.113 23.9 23.4 24.0 23.5 23.714 23.0 23.3 23.7 23.8 23.515 22.4 22.4 22.7 22.9 22.616 20.2 20.8 21.3 20.9 20.817 23.8 23.1 23.6 24.5 23.818 22.3 22.2 22.4 22.8 22.419 23.4 23.8 24.4 23.7 23.820 22.4 22.4 23.0 23.1 22.721 24.2 24.2 24.1 24.2 24.222 24.9 25.1 25.5 25.4 25.223 21.2 21.5 21.9 22.2 21.724 21.7 21.3 21.1 22.1 21.625 22.4 22.1 22.7 22.9 22.526 24.6 27.2 25.9 27.3 26.327 25.2 26.5 26.4 27.0 26.328 23.8 25.4 24.4 25.9 24.929 22.9 24.8 24.6 24.7 24.330 24.1 24.9 24.7 24.8 24.631 22.0 22.8 22.4 23.0 22.632 23.2 24.8 24.3 24.0 24.133 24.1 26.0 24.3 25.7 25.034 26.3 27.5 27.0 26.0 26.735 27.8 30.5 29.2 29.1 29.236 24.5 24.0 24.2 23.8 24.137 22.5 22.8 22.4 22.5 22.638 26.0 27.6 25.7 26.6 26.539 22.5 23.6 22.6 22.9 22.940 22.6 24.4 24.3 24.4 23.942 24.9 26.0 25.3 25.6 25.5

44(control) 20.0 19.8 19.9 19.7 19.945 (transit control) 5.3 5.6 5.2 5.4 5.4

46 25.6 26.4 26.0 25.8 26.047 22.5 23.2 21.4 22.7 22.548 22.6 23.7 23.8 22.7 23.249 21.4 22.1 21.2 21.6 21.650 18.9 18.9 18.7 18.7 18.8


FIGURE 9.1 NETWORK ENVIRONMENTAL TLD EXPOSURE RATES

30.0-~ mRlstd qtr

BASELINE

---- 10OYEARMEAN

28.0 +

26.0 +I-

o2 A A A r RA A / = - ,A24.0

22.0

20.0

18.0

i- - - - - I- t I - - I rI - - i k - -I -II I r \ - l .

., u v kl- 'i v v V v \ v I

,. .I . . I I . . . . . . . . . . . . . I I I . . . . . . . . I I I . . . .kn- tn %0w t- t-o oo 00 0% o~ o - -n Cje en M �td "- " : %O % oo X- o- W f o O7 A - - N N M e

es x & i 6. 't 0 -L & , &X , , , V & fi &l .&S . g t 6. i0 oo a, !q 06:E x E vx :M cx "7c _:6E vS (x : vE cx SE cx, I%S vE 6i 2~ v%>_ 6E 6i S E JE CM S_ EXS :2 C


53

FIGURE 9.2 ENVIRONMENTAL TLD COMPARISON - PRE-OPERATIONAL VS 2003

35

30Z.

an 25

. 205

= 15en

0

x 10o)

5

0

1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 42 45

TJD Number

TLD #41 monitoring location was deleted in June, 2000.TLD #43 monitoring location was deleted in 1994.TLDs #46-50 are not included since they were not included in the pre-op monitoring program.


54

10. Land Use Census

10.1. Introduction

In accordance with the PVNGS ODCM, Section 6.2, the annual Land Use Census wasperformed within five miles of Unit 2 containment in May-June 2003.

Observations were made in each of the 16 meteorological sectors to determine thenearest milking animals, residences, and gardens of greater than 500 square feet. Thiscensus was completed by driving the roads and speaking with residents.

The results of the Land Use Census are presented in Table 10.1 and discussed below.The directions and distances listed are in sectors and miles from the Unit 2containment.

10.2. Census Results

Nearest Resident

There were three (3) changes in nearest resident status. Refer to Table 10.1 forspecific location changes. Dose calculations indicated the highest dose to be 0.118mrem.

Milk Animal

There was one (1) change in nearest milk animal (goat) status. Dose calculationsindicated the highest dose to be 0.483 mrem.

Veictable Gardens

There were three (3) changes in nearest garden status. Dose calculations indicated thehighest dose to be 0.296 mrem.

See Table 10.1 for a summary of the specific results and Table 2.1 for current samplelocations.


TABLE 10.1 2003 LAND USE CENSUS

(Distances and directions are relative to Unit 2 in miles)

NEAREST NEAREST NEAREST CALCULATED DOSESECTOR RESIDENT GARDEN MILK ANIMAL (mrem) CHANGE

(COW/GOAT) FROM 2002N 1.55 1.79 NONE Resident 3.18E-02

Garden 1.80E-01

NNE 1.52 NONE NONE Resident 5.70E-02 ResidentGarden

Milk animalNE 2.16 NONE 3.91 Resident 1.08E-01 Garden

Milk 4.83E-01ENE 2.67 NONE 4.84 Resident 6.53E-02 Resident

Milk 1.88E-01 Garden

E 2.81 4.79 NONE Resident 7.97E-02Garden 1.38E-O1 l

ESE 3.17 3.85 NONE Resident 8.62E-02Garden 2.96E-01

SE 4.10 NONE NONE Resident 7.46E-02 l

SSE NONE NONE NONE NAS NONE NONE NONE NA Resident

SSW NONE NONE NONE NASW 1.39 NONE NONE Resident 1.18E-01 _l

WSW 0.75 NONE NONE Resident 7.59E-02W 0.70 NONE NONE Resident 4.42E-02 l

WNW 2.67 NONE NONE Resident 7.1 1E-03NW 1.12 NONE NONE Resident 2.14E-02

NNW 1.30 3.49 NONE Resident 2.04E-02Garden 4.611E-02

COMMENTS:

Dose calculations were performed using the GASPAR code and 2002 meteorological data and sourceterm. Dose reported for each location is the total for all three PVNGS Units and is the highestindividual dose identified (organ, bone, total body, or skin).

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -200356

11. Summary and Conclusions

The conclusions are based on a review of the radio assay results and background gammaradiation measurements for the 2003 calendar year. Where possible, the data were comparedto pre-operational sample data.

All sample results for 2003 are presented in Tables 8.1-8.11 and do not include observationsof naturally occurring radionuclides, with the exception of gross beta in air and gross beta indrinking water. Table 11.1 summarizes the ODCM required samples and is in the formatrequired by the NRC BTP on Environmental Monitoring.

1-131 concentrations identified on occasion in the Evaporation Ponds, WRF Influent, WRECentrifuge sludge, and Reservoir is the result of offsite sources and appears in the effluentsewage from Phoenix. The levels of 1-131 detected in these locations are consistent withlevels identified in previous years.

Tritium concentrations identified in surface water onsite have been attributed to PVNGSgaseous effluent releases and secondary plant releases. These concentrations are consistentwith historical values.

Natural background radiation levels are consistent with measurements reported in previousPre-operational and Operational Radiological Environmental annual reports, References Iand 2.

There were ino measurable radiological impacts on the environment due to PVNGSoperations in 2003.


TABLE 1 1.1

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL SUMMARY

Palo Verde Nuclear Generating Station Docket Nos. STN 50-528/529/530Maricopa County, Arizona Calendar Year 2003

Medium or Lower Limit of All Indicator Location with Highest Annual Mean ControlPathway Type and Total Detection Locations Locations Number ofSampled Number of (LLD) Name Mean (Ma Nonroutine(Unit of Analyses (from Table Mean (f)a Distance and Range Mean(f) Reported

Measurement) Performed 6.1) Range Direction Range Measurements

Direct Radiation TLD - 192 NA 23.6 (180/180) Site 035 29.2 (4/4) 22.4 (8/8) 0(mrem/std. qtr.) 18.7-30.5 8 miles 3350 27.8 -30.5 19.7-25.5

Air Particulates Gross Beta -468 0.010 0.035 (416/416) Site #4 0.036 (52/52) 0.036 (52/52) 0(pCi/m3) 0.011 - 0.066 16 miles 90° 0.013 - 0.065 0.012 - 0.071

Gamma Spec.Composite- 36

Cs-134 0.05 <LLD NA <LLD <LLD 0Cs-137 0.06 <LLD NA <LLD <LLD 0

Air Radioiodine Gamma Spec. - 468(pCi/m) 1-131 0.07 <LLD NA <LLD <LLD 0

Broadleaf Gamma Spec. - 20Vegetation 1-131 60 <LLD NA <LLD <LLD 0

(pCi/Kg-wet) Cs-134 60 <LLD NA. <LLD <LLD 0Cs-137 80 <LLD NA <LLD <LLD 0

Groundwater 11-3 - 8 2000 <LLD NA <LLD NA 0(pCi/liter)

Gamma Spec. - 8Mn-54 15 <LLD NA <LLD NA 0Fe-59 30 <LLD NA <LLD NA 0Co-58 15 <LLD NA <LLD NA 0Co-60 15 <LLD NA <LLD NA 0Zn-65 30 <LLD NA <LLD NA 0Zr-95 30 <LLD NA <LLD NA 0


TABLE 11.1



Medium or Lower Limit of All Indicator Location with Highest Annual Mean ControlPathway Type and Total Detection Locations Locations Number ofSampled Number of (LLD) Name Mean (fM Nonroutine(Unit of Analyses (from Table Mean (f)' Distance and Range Mean (a) Reported

Measurement) Performed 6.1) Range Direction Range MeasurementsNb-95 15 <LLD NA <LLD NA 0

Groundwater 1-131 15 <LLD NA <LLD NA 0(pCi/liter) Cs-134 15 <LLD NA <LLD NA 0

-continued- Cs-137 18 <LLD NA <LLD NA 0Ba-140 60 <LLD NA <LLD NA 0La-140 15 <LLD NA <LLD NA 0

Gross Beta - 48 4.0 (22/48) Site #49 (3/12) NA 02.6-6.1 2miles 0° 2.7-6.1

H-3 - 16 2000 <LLD NA <LLD NA 0

Gamma Spec. - 48Drinking Water Mn-54 15 <LLD NA <LLD NA 0

(pCi/liter) Fe-59 30 <LLD NA <LLD NA 0Co-58 - 15 <LLD NA <LLD NA 0Co-60 15 <LLD NA <LLD NA 0Zn-65 30 <LLD NA <LLD NA 0Zr-95 30 <LLD NA <LLD NA 0Nb-95 15 <LLD NA <LLD NA 01-131 15 <LLD NA <LLD NA 0

Cs-134 15 <LLD NA <LLD NA 0Cs-137 18 <LLD NA <LLD NA 0Ba-140 60 <LLD NA <LLD NA 0La-140 15 <LLD NA <LLD NA 0


TABLE 11.1



Medium or Lower Limit of All Indicator Location with Highest Annual Mean ControlPathway Type and Total Detection Locations Locations Number ofSampled Number of (LLD) Name Mean (Ms Nonroutine(Unit of Analyses (from Table Mean (f) Distance and Range Mean (f) Reported


Gamma Spec. - 151-131 1.0 <LLD NA <LLD <LLD 0t

Milk Cs-134 15 <LLD NA <LLD <LLD 0,(pCi/liter) Cs-137 18 <LLD NA <LLD <LLD 0

Ba-140 60 <LLD NA <LLD <LLD 0La-140 15 <LLD NA <LLD <LLD 0

Gamma Spec. - 36Mn-54 15 <LLD NA <LLD NA 0Fe-59 30 <LLD NA <LLD NA 0Co-58 15 <LLD NA <LLD NA 0Co-60 15 <LLD NA <LLD NA 0Zn-65 30 <LLD NA <LLD NA 0Zr-95 30 <LLD NA <LLD NA 0Nb-95 15 <LLD NA <LLD NA 0

Surface Water T-131 15 13(11/36) Site #60 13(5/12) NA 0(pCiAiter) 8-19 Onsite 670 8-19

Cs-134 15 <LLD NA <LLD NA 0

Cs-137 18 12 (2/36) Site #63 12 (2/12) NA 09-15 Onsite 1800 9-15

Ba-140 60 <LLD NA <LLD NA 0La-140 15 <LLD NA <LLD NA 0

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2003

60

TABLE 1. 1



Medium or Lower Limit of All Indicator Location with Highest Annual Mean ControlPathway Type and Total Detection Locations Locations Number ofSampled Number of (LLD) Name Mean (fM Nonroutine(Unit of Analyses (from Table Mean (f)' Distance and Range Mean (f)M Reported


Surface Water H-3 - 12 3000 1284 (8/12) Site #63 1380(4/4) NA 0(pCiAiter) 774- 1704 Onsite 1800 1129- 1704

-continued-

(a) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated inparentheses. (1)

NOTE: Miscellaneous samples that are not listed on Tables 2.1 and 9.1 (not ODCM required) are not included on this table.


12. References

1. Pre-Operational Radiological Monitoring Program, Summary Report 1979-1985.

2. 1985-2002 Annual Radiological Environmental Operating Reports, Palo Verde Nuclear

Generating Station.

3. Palo Verde Nuclear Generating Station Technical Specifications and the Technical

Reference Manual (TRM).

4. Offsite Dose Calculation Manual, PVNGS Units 1, 2, and 3.

5. Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants.

6. NRC Radiological Assessment Branch Technical Position on Environmental Monitoring,

Revision 1, November 1979.

/


62

Documents

Palo Verde, Units 1, 2 and 3 - Annual Radiological Environmental … · 2012-11-19 · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1,