palo verde nuclear generating station, units 1, 2, and 3 ... · in the pvngs offsite dose...

66
liAMS Scott A. Bauer Tel. 623-393-5978 Mail Station 7636 Palo Verde Nuclear Department Leader, Fax 623-393-5442 PO Box 52034 Geneeating Station Regulatory Affairs e-mail: sbaueraapsc.com Phoenix, Arizona 85072-2034 102-05245-SAB/TNW/CJJ April 8, 2005 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dear Sir Subject: Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3 Docket Nos. STN 50-52815291530 Annual Radiological Environmental Operating Report 2004 In accordance with PVNGS Technical Specification (TS) 5.6.2, enclosed please find the Annual Radiological Environmental Operating Report for 2004. 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, SAB/TNW/CJJ/cla Enclosure cc: B. S. Mallett M. B. Fields G. G. Warnick A. V. Godwin member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway O Comanche Peak 0 Diablo Canyon 0 Palo Verde 0 South Texas Project 0 Wolf Creek

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Page 1: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ... · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1, 2.2 and 9.1. Additional

liAMSScott A. Bauer Tel. 623-393-5978 Mail Station 7636

Palo Verde Nuclear Department Leader, Fax 623-393-5442 PO Box 52034Geneeating Station Regulatory Affairs e-mail: sbaueraapsc.com Phoenix, Arizona 85072-2034

102-05245-SAB/TNW/CJJApril 8, 2005

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 50-52815291530Annual Radiological Environmental Operating Report 2004

In accordance with PVNGS Technical Specification (TS) 5.6.2, enclosed please find theAnnual Radiological Environmental Operating Report for 2004.

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,

SAB/TNW/CJJ/cla

Enclosure

cc: B. S. MallettM. B. FieldsG. G. WarnickA. V. Godwin

member of the STARS (Strategic Teaming and Resource Sharing) Alliance

Callaway O Comanche Peak 0 Diablo Canyon 0 Palo Verde 0 South Texas Project 0 Wolf Creek

Page 2: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ... · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1, 2.2 and 9.1. Additional

ENCLOSURE

Annual Radiological EnvironmentalOperating Report

2004

Page 3: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ... · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1, 2.2 and 9.1. Additional

NUCLEAR GENERATING STATION

ANNUAL RADIOLOGICAL ENVIRONMENTALOPERATING REPORT

2004(Reference: RCTSAI 1643, Legacy Item No. 036843.01)

Digitalty signed by: Drinovsky. Louis J(Z33699)Date: 020005 16:12.25Reason: I amn the author of this docurnentLocation: PVNGS / e

Prepared by:

Digitally signed by: Bungard, James P(Z1 801 2)Date: 02/03/2005 14:58:39Reason: I have reviewed this documentLocation: PVNGS '

Reviewed by:__

Digitally signed by, Gafiney, John P(Z36459)Date: 03116/2005 11:19:28 ^Reason: I am approving this documentLocation: PVNGS

Approvea Dy:.

Page 4: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ... · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1, 2.2 and 9.1. Additional

TABLE OF CONTENTS

1. INTRODUCTION ............................................................. 2

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

2.1. 2004 PVNGS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM .................................. 32.2. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CHANGES FOR 2004 ......................... 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 ............................................................ 0 I3.5. SLUDGE AND SEDIMENT ............................................................. 11

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

4.1. AIR PARTICULATE ............................................................. I 14.2. AIRBORNE RADIOIODINE ............................................................. 114.3. M ILK .......................................................................................................................................... . . I I14.4. VEGETATION.............................................................................................................................. 124.5. SLUDGE/SEDIMENT ............................................................ 124.6. WATER ............................................................. 124.7. SOIL ............................................................ 1 3

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

5.1. GAMMA SPECTROMETER ............................................................. 135.2. LIQUID SCINTILLATION SPECTROMETER..................................................................................... 1 35.3. GAS FLOW PROPORTIONAL COUNTER ............................................................. 13

6. ISOTOPIC DETECTION LIMITS AND REPORTING CRITERIA. . 14

6.1. LOWERLIMITSOFDETECTION ................................. ; 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 ....................................... 24

8.1. AIR PARTICULATES .......................................... 248.2.- AIRBORNE RADIOIODINE .......................................... 258.3. VEGETATION .258.4. MILK .258.5. DRINKING WATER .258.6. GROUNDWATER ......... 25

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2004ii

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TABLE OF CONTENTS

8.7. SURFACE WATER .......................................................... 258.8. SLUDGE AND SEDIMENT .......................................................... 268.9. DATA TRENDS ......................................................... 26

9. THERMOLUMINESCENT DOSIMETER (TLD) RESULTS AND DATA .............................. 46

10. LANDUSECENSUS .......................................................... 5210.1. INTRODUCTION .......................................................... 5210.2. CENSUS RESULTS ......................................................... 52

11. SUMMARY AND CONCLUSIONS ......................................................... 54

12. REFERENCES ......................................................... 59

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2004

iii

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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 PRIORI) ............................... 17

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

TABLE 6.3 TYPICAL MDA VALUES .......................................................... 1 9

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

TABLE 8.1 PARTICULATE GROSS BETA IN AIR 1ST - 2ND QUARTER ....................................... 27

TABLE 8.2 PARTICULATE GROSS BETA IN AIR 3RD - 4TH QUARTER ....................................... 28

TABLE 8.3 GAMMA IN AIR FILTER COMPOSITES .......................................................... 29

TABLE 8.4 RADIOIODINE IN AIR 1ST - 2ND QUARTER .......................................................... 30

TABLE 8.5 RADIOIODINE IN AIR 3RD - 4TH QUARTER .......................................................... 31

TABLE 8.6 VEGETATION ....................................... 32

TABLE 8.7 MILK ....................................... 33

TABLE 8.8 DRINKING WATER ....................................... 34

TABLE 8.9 GROUNDWATER ....................................... 36

TABLE 8.10 SURFACE WATER ....................................... 37

TABLE 8.11 SLUDGE/SEDIMENT ....................................... 40

TABLE 9.1 TLD SITE LOCATIONS ....................................... 47

TABLE 9.2 2004 ENVIRONMENTAL TLD RESULTS ....................................... 49

TABLE 10.1 2004 LAND USE CENSUS ....................................... 53

TABLE 11.1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUALSUMMARY ....................................... 55

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2004iv

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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) ............... 42

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

COMPARED TO PRE-OP ....................................................................... 43

FIGURE 8.3 GROSS BETA IN DRINKING WATER ...................................................................... 44

FIGURE 8.4 EVAPORATION POND TRITIUM ACTIVITY ............................................................ 45

FIGURE 9.1 NETWORK ENVIRONMENTAL TLD EXPOSURE RATES ............... ....................... 50

FIGURE 9.2 ENVIRONMENTAL TLD COMPARISON - PRE-OPERATIONAL VS 2004 ............ 51

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2004v

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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 plant relatedradionuclide concentrations.

During 2004, the following categories of samples were collected by APS:

* Broad leaf vegetationGroundwaterDrinking 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 2004.

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

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2004

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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 I, 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 2004. 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 thepublic; and 3) to determine radiological impacts on the environment caused by the operationof PVNGS.

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 1 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 - 20042

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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. 2004 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.

Background gamma radiation measurements were performed by APS using TLDs atforty-nine (49) 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 2004

x One (1) new garden replaced an existing garden location due to dose calculationresults.

x One (1) new milk animal (goats) location was added to the REMP.x One (I) TLD, site #41, was placed at a new school.

Refer to Table 2.1 for a description of all current sample locations (except TLDs).

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 20043

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2.3. REMiP Deviations/Abnormal Events Summary

During calendar year 2004, there were three (3) deviations/abnormal events withregard to the monitoring program. Refer to Table 2.3 for more detail and anycorrective actions taken.

* Air sample site #4 for the week of 2-3-04 through 2-10-04 was invalidated due toan anomalous result.

* Air sample site #29 was out of service from 10-19-04 through 10-26-04.* The WRF Influent I-131 concentration exceeded 100 pCi/liter on three (3)

occasions.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 20044

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Table 2.1 SAMPLE COLLECTION LOCATIONS

SAMPLE E 'SITE# SAMPLE TYPE LOCATION LOCATIOArDESCRIPTION

4 air E16 APS Office6A* air SSE13,.,, Old US 8014A air NNE2'- 371St Ave. and Buckeye-Salome Rd.15 air NE2 NE Site Boundary17A air E3, ' 3515 Ave.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 SWi Berryman residence49 drinking water N2 ' . Chowanec residence51': milk -NE4' . Painter residence-goats52 : vegetation NNE2 rb). , Branch residence53* milk ENE24 ' Barber residence-goats54 milk NNE2(bj. ' Branch residence-goats55, ' ' drinking water SW3 ,- : I Gavette residence

(supplemental)57 I 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, " - Evaporation Pond #2

NOTES:

* Designates a control site

(a) Distances and direction are from the center-line of Unit 2 containment and rounded to thenearest mile

(b) Denotes a change in location or a new sample 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)

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2004

5

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Table 2.2 SAMPLE COLLECTION SCHEDULE

SAMPLE AIR AIRBORNE GROUND DRINKING SURFACESITE # PARTICULATE MILK RADIIOWDINE VEGETATION IA TER IVA TER WA TER

4 W W

6A W W

14A W W

15 W W

17A W W

21 W W

29 W W

35 W WV

40 W WV

46 W

47 M/AA

48 W

49 .W

51 M/AA

52 M/AA

53 M/AA

54 M/AA

55 W

57 Q

58 Q

59- XV

60 _W

62 M/AA

63 .W

W = WEEKLY M/AA = MONTHLY AS AVAILABLE Q = QUARTERLY

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 20046

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TABLE 2.3 SUMMARIES OF REMP DEVIATIONS/ABNORMAL EVENTS

Deviation/Abnormal Event

1. Air sample site #4 for the week of 2-3-04through 2-10-04 was invalidated due to ananomalous result.

2. Air sample site #29 was out of servicefrom 10-19-04 through 10-26-04.

3. The WRF Influent I-131 concentrationexceeded 100 pCi/liter on three (3)occasions.

Actions taken

1. The problem was attributed to intermittentpower losses due to construction activities in thearea. Subsequent sample results were consideredacceptable, therefore no further actions wererequired.

2. This was a planned event and due toconstruction activities related to plant securityupgrades. To prevent excess dust loading due tochanges in plant entrance roadways, the airsample station was moved two (2) poles south ofits previous location. GPS readings indicate thatthe sample station is still in the west sector. Nofurther action is required.

3. Phoenix sewage effluent is the supply for thiswater and is know to contain radiopharmaceuticalI-13 1. The Arizona Radiation Regulatory Agencyis notified when this source of water exceeds anI-131 concentration of 100 pCi/liter. This wasconsidered an abnormal event since it was thefirst year this threshold was known to have beenexceeded. This is considered a courtesynotification (not regulatory) and no further actionis required.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 20047

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FIGURE 2.1

___Graphic Scale In Miles 'rn , _.

I I I I I I0 1 2 3 4 5

N

KEY TO MAP Palo Verde Nuclear Generating Station- Paved Road uw lepost

Unpaved Road Palo Verde Nuclear-~ z 4WD Road GeneatIng Station Radiological-41 a F--- as Pipeline .: Environmental Monitoring-10F---lol- Oil Pipeline TTherrmolunIlnescert PormSml ie

1-4t I Power Une DosImeters. rL.D) Program Sample Sites- Railroad Air Sample4 A p v VegetatlonSample 0- 10 Miles

w Water SampleSchool M MIlkSaimpl

* Siren 1) Sample Shes

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2004

8

Page 16: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ... · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1, 2.2 and 9.1. Additional

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KEY TO MAP Palo Verde Nuclear Generating Station

I I I I Railroad !! Palo Verde Nuclear RADIOLOGICAL ENVIRONMENTAL MONITORINGGenerating Station lPROGRAM SAMPLE SITES~. Airstrip!A lrport B u d r -3 ie

Schools Located T Thermoluminescent ( Sample Sites 035 Miles* Near Sample Sites Dosometer (I1D) V Vegetation

* Municipal Buildings A Air Sample hi MILK

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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 I-131.

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 I-131. Particulate filters were composited quarterly, by location, andanalyzed for gamma emitting radionuclides.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 200410

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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.

Scale was removed from cooling tower louvers and circulating water/plant coolingwater piping and 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 counted on a multichannel analyzer equipped withan HPGe detector. The resulting spectrum is analyzed by a computer forspecific 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 1-13 1.

4.3. Milk

4.3.1. Gamma Spectroscopy

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.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 20041 1

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4.4. Vegetation

4.4.1. Gamma Spectroscopy

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

4.5.1. Gamma Spectroscopy

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

4.6.1. Gamma Spectroscopy

The sample is placed in a one-liter plastic marinelli beaker, weighed, andcounted on a multichannel analyzer equipped with an HPGc 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.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 200412

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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

4.7.1. Gamma Spectroscopy

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

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

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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 the.PVNGS 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.

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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 + 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 are 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.

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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 Samplc 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 between 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.

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

AIRBORNEANALYSIS/ WATER PARTICULATE or MILK VEGETATIONNUCLIDE (pCi/litcr) 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.

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Table 6.2 ODCM REQUIRED REPORTING LEVELS

AIRBORNEANALYSIS/ NWNATER PARTICULATE MILK VEGETATIONNUCLIDE (pCi/liter) or GAS (pCi/m 3) (pCiIliter) (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.

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Table 6.3 TYPICAL MDA VALUES

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

(pCi/liter) (pCi/liter) GAS (pCi/m3 )Gross Beta 3 0.003

H-3 280Mn-54 12Fe-59 21Co-58 11Co-60 13Zn-65 26Zr-95 19Nb-95 11I-131 Oa 1 0.05 50

Cs-134 10 1 0.02 50Cs-137 12 1 0 .0 2 60Ba-140 38 3La-140 13 1

NOTES:

a - low level I-13 1 is not required since there is no drinking water pathwayb - Based on 433 m3 volume

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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 2004, APS analyzed the following sample types under the interlaboratorycomparison program;

* Beta/Gamma/ in Air Filter* I-131 in Air* Beta in Water* Gamma in Water* Tritium in Water

7.2. Intercomparison Results

APS participates in a crosscheck program using vendor supplied blind radionuclidesamples. Results for the interlaboratory comparison program are presented in Table 7.1.

All crosscheck results reported in 2004 were within the established acceptance criteria.

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TABLE 7.1 INTERLABORATORY COMPARISON RESULTS

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

Water |Iodine 1 I-131 | 27.7 28.2 [ 23.0 - 33.4 Accept(ERA RAD-55) tium I H-3 1 12927 | 14300 | 11800 - 16800 I| Accept

E Sample Analysis Nuclide PVNGS Certified PT Acceptance Accept/RejectType Type | Value Value 1 Limits 2 l

Water Tritium H-3 27000 30900 25600 - 36200 Accept(ERA RAD-57) Mixed I-131 | 26 25.1 J 19.9 - 30.3 Accept

Gamma Co-60 [ 43.3 | 41.6 || 32.9 - 50.3 | Accept

Zn-65 [80.1 75.2 62.2-88.2 l Acceptl Ba-133 100 l 101 83.5 - 118 1 AcceptlCs-134 j[ 47.9 | 50.5 JI 41.8 - 59.2 ][ Accept

l l | Cs-137 [ 88.5 l 82.5 ][ 73.8 - 91.2 l Accept

* I The certified values are verified to meet criteria as established by NIST NVLAP 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.

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TABLE 7.1 INTERLABORATORY COMPARISON RESULTS

Ii 1Sample Analysis Nuclide Known PVNGS sigma Resolution Ratio Accept/RejectType Type Value Value Error * _

~MixedlWater Gamma 1-131 70.8 73 7 10 1.03 Accept

E4236-111 Ce-141 250 254 13 20 1.02 AcceptCr-51 223 199 29 7 0.89 Accept

Cs-134 96.4 79 6 13 0.82 AcceptCs-137 215 217 13 17 1.01 AcceptCo-58 94.6 96 7 14 1.01 AcceptMn-54 181 175 10 18 0.96 AcceptFe-59 91.6 107 11 10 1.17 AcceptZn-65 178 186 15 12 1.04 AcceptCo-60 125 124 8 16 0.99 Accept

Tritium H-3 12000 10200 293 35 0.85 AcceptE4239-1 11

Gross Beta 225 283 31 9 1.26 AcceptE4235-111

Air Gross Beta 195 215 2.3 93 1.1 AcceptE4237-111

Iodine Cart I-131 77.2 81 4.7 17 1.05 AcceptE4234-111

MixedGamma Ce-141 180 202 10 20 1.13 Accept

E3992-111 Cr-51 161 177 13 14 1.1 AcceptCs-134 69.3 87 4 22 1.26 AcceptCs-137 154 177 10 18 1.15 AcceptCo-58 68 76 5 15 1.12 AcceptMn-54 130 156 10 16 1.2 AcceptFe-59 65.7 85 6 14 1.29 AcceptZn-65 128 160 10 16 1.25 AcceptCo-60 90 100 6 17 1.11 Accept

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TABLE 7.1 INTERLABORATORY COMPARISON RESULTS

Sample A s Nuclide Known sigma Accept/RejectType [ Type [ ____ VleValue Error * ____

MixedWater Gamma 1-131 91.5 83 9 9 0.91 Accept

E4439-111 Ce-141 149 149 9 17 1.0 AcceptCr-51 365 378 34 11 1.04 Accept

Cs-134 164 143 9 16 0.87 AcceptCs-137 121 128 8 16 1.06 AcceptCo-58 141 133 8 17 0.95 AcceptMn-54 131 136 8 17 1.04 AcceptFe-59 117 130 11 12 1.11 AcceptZn-65 189 192 13 15 1.02 AcceptCo-60 168 169 9 19 1.0 Accept

Tritium H-3 8060 7090 256 28 0.88 AcceptE4443-111

Gross Beta 195 242 3 81 1.24 AcceptE4438-111

| Air Gross Beta 200 249 1.8 138 1.24 AcceptE3440-111

Iodine Cart 1-131 85 86 5.5 16 1.01 AcceptE4441-111

Mixed

Gamma Ce-141 78 85 4 21 1.09 AcceptE4442-111 Cr-51 184 198 14 14 1.08 Accept

Cs-134 82.3 70 4 18 0.85 AcceptCs-137 61.1 69 4 17 1.13 AcceptCo-58 70.8 78 5 16 1.10 AcceptMn-54 65.8 78 5 16 1.19 AcceptFe-59 58.8 75 6 13 1.28 AcceptZn-65 94.9 112 7 16 1.18 Accept

. _ Co-60 84.7 93 5 19 1.10 Accept

* calculated from PVNGS value/l sigma error value

Acceptance Criteria 1

Resolution<4

Ratio

4-7 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

1From NRC Inspection Manual, Inspection Procedure 84750, "Radioactive Waste Treatment, And Effluent And Environmental Monitoring'

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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 2004 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 2004.

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 0.012 to 0.080 pCi/M3 . The associated counting error ranged from 0.001 to 0.004pCi/mr3 . 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 1994-2004 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.

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8.2. Airborne Radioiodine

Tables 8.4 and 8.5 present the quarterly radioiodine results. No airborne radioiodinewvas 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 data for the goat milk samples. No gamma emittingradionuclides 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 5.1 pCi/liter (McArthur residence, September 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. I-131 wasobserved in Evaporation Pond # 1 in one (1) monthly composite sample (21 pCi/liter)and two (2) of the Reservoir monthly composite samples (9 and 15 pCi/liter). I-131 isa result of radiopharmaceutical I- 131 in the Phoenix sewage effluent.

Tritium was routinely observed in Evaporation Ponds 1 and 2. The highestconcentration in Evaporation Pond #1 was 1266 pCi/liter and the highest concentrationin Evaporation Pond #2 was 1826 pCi/liter. Tritium was not identified in theReservoir. The tritium identified in the Evaporation Ponds has been attributed to plantgaseous effluent releases and secondary plant liquid releases.

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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 was193 pCi/liter (week of December 7th). The results indicate an increase inradiopharmaceutical 1-131 usage in the Phoenix area. The Arizona RadiationRegulatory Agency was contacted each week that this concentration exceeded 100pCi/liter (three times in 2004). None of the samples analyzed indicated the presence oftritium.

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 from278 to 482 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. WRF Centrifuge waste sludge

Sludge samples were obtained from the WRF centrifuge and analyzed bygamma spectroscopy. I-131 in the WRF waste centrifuge sludge is consistentwith historical values and, as previously discussed, is due toradiopharmaccuticals in the WRF influent. 1-131 was present in all fifty (50)samples ranging from 203 to 1431 pCi/kg.

In-I 11 was also identified in the sludge in eight (8) samples. The highestconcentration was 53 pCi/liter. It was previously established that In-i 11 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 nine (9) Evaporation Pond sediment samples indicated low levels ofI-131 and Cs-137 in Evaporation Ponds 1 and 2. The concentrations wereconsistent with historical values. Sample results can be found in Table 8.11.

8.8.3. Cooling Tower sludge

Sludge originating from the Unit cooling towers and/or circulating watercanals was not disposed of in the WRF sludge landfill during 2004. However,scale removed from cooling tower louvers and circulating water/plant coolingwater piping was disposed of in the landfill. Sample results of the scale can befound in Table 8.11.

8.9. Data Trends

Figures 8.1-8.4 present data in graphical format. Historical data are displayed forcomparison where practical.

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TABLE 8.1 PARTICULATE GROSS BETA IN AIR 1st - 2nd QUARTER

ODCM required samples denoted by *units are pCir 3

(control)

STARTDATE

STOPDATE

Site Site Site Site

4 6A* 14A* 15*

Site17A

Site

21

Site Site Site

29* 35 40* Mean RSD (%)Week #

12345678910111213

29-Dec-03 6-Jan-04 0.027 0.027 0.023 0.025 0.027 0.0246-Jan-04 13-Jan-04 0.054 0.053 0.048 0.048 0.049 0.05113-Jan-04 20-Jan-04 0.075 0.079 0.075 0.074 0.080 0.07420-Jan-04 27-Jan-04 0.036 0.037 0.036 0.042 0.036 0.03727-Jan-04 3-Feb-04 0.031 0.032 0.029 0.032 0.032 0.0313-Feb-04 10-Feb-04 Invalid ' 0.020 0.017 0.018 0.019 0.01810-Feb-04 17-Feb-04 0.042 0.036 0.037 0.038 0.037 0.03117-Feb-04 24-Feb-04 0.023 0.021 0.020 0.020 0.019 0.01924-Feb-04 1-Mar-04 0.012 0.013 0.014 0.014 0.015 0.0131-Mar-04 9-Mar-04 0.021 0.021 0.022 0.023 0.019 0.0189-Mar-04 16-Mar-04 0.041 0.040 0.040 0.042 0.039 0.03716-Mar-04 23-Mar-04 0.036 0.036 0.034 0.035 0.037 0.029

23-Mar-04 29-Mar-04 0.032 0.029 0.029 0.033 0.028 0.029

0.0270.0510.0780.0400.0310.0190.0360.0210.0140.0210.0370.0370.030

0.021 0.024 0.0250.044 0.053 0.0500.068 0.073 0.0750.037 0.040 0.0380.025 0.027 0.0300.017 0.018 0.0180.027 0.029 0.0350.018 0.020 0.0200.012 0.013 0.0130.021 0.021 0.0210.032 0.032 0.0380.029 0.032 0.0340.029 0.027 0.030

8.76.34.85.88.35.713.87.27.57.19.79.46.4

Mean 0.036 0.034 0.033 0.034 0.034 0.032 0.034 0.029 0.031 0.033 5.92nd Quarter

(control)START STOPDATE DATE

Site4

Site Site Site6A* 14A* 15*

Site17A

Site21

Site29*

Site Site35 40* Mean RSD (%)Week #

-

14151617181920

212223242526

29-Mar-04 6-Apr-04 0.0236-Apr-04 13-Apr-04 0.03013-Apr-04 20-Apr-04 0.03120-Apr-04 27-Apr-04 0.02927-Apr-04 4-May-04 0.0304-May-04 11-May-04 0.0401 1-May-04 18-May-04 0.032

18-May-04 25-May-04 0.02925-May-04 1-Jun-04 0.030

1-Jun-04 7-Jun-04 0.0367-Jun-04 15-Jun-04 0.03015-Jun-04 22-Jun-04 0.03022-Jun-04 29-Jun-04 0.024

0.021 0.023 0.025 0.020 0.0190.028 0.026 0.030 0.030 0.0270.030 0.030 0.033 0.031 0.0310.027 0.030 0.032 0.025 0.0260.034 0.033 0.039 0.030 0.0310.041 0.039 0.041 0.039 0.040

0.030 0.032 0.032 0.034 0.028

0.031 0.028 0.031 0.031 0.0290.029 0.029 0.032 0.031 0.0290.032 0.034 0.038 0.035 0.0310.028 0.030 0.026 0.028 0.0250.027 0.026 0.035 0.030 0.0280.029 0.030 0.033 0.028 0.023

0.0240.0290.0320.0250.0330.038

0.029

0.0270.0290.0360.0280.0250.028

0.023 0.023 0.0220.025 0.025 0.0280.029 0.030 0.0310.023 0.024 0.0270.033 0.033 0.0330.038 0.035 0.039

0.031 0.033 0.031

0.027 0.026 0.0290.029 0.031 0.0300.034 0.030 0.0340.029 0.030 0.0280.029 0.024 0.0280.030 0.027 0.028

8.77.63.911.28.24.8

6.26.73.97.66.311.711.0

Mean 0.030 0.030 0.030 0.033 0.030 0.028 0.029 0.029 0.029 0.030 4.5' Sample result invalidated due to anomalous result of 0.032 (contributing factor was ETM problems due to power outages)

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

units are pCi/rn 3

3rd Quarter.(control)

START

DATE

STOPDATE

Site Site Site Site Site Site Site Site Site4 6A* 14A* 15* 17A 21 29* 35 40* Mean RSD (%)Week I#

27282930313233343536373839

-I29-Jun-046-Jul-0413-Jul-0420-Jul-0427-Jul-043-Aug-0410-Aug-0417-Aug-0424-Aug-043 1-Aug-047-Sep-0414-Sep-0421 -Sen-04

6-Jul-0413-Jul-0420-Jul-0427-Jul-043-Aug-0410-Aug-0417-Aug-0424-Aug-043 1-Aug-047-Sep-0414-Sep-0421-Sep-0428-Sen-04

0.0300.0260.0280.0270.0370.0340.0320.0320.0300.0350.0440.0330.031

0.0260.0270.0220.0270.0300.0330.0260.0350.0250.0340.0440.0280.032

0.0300.0280.0270.0290.0320.0360.0290.0310.0280.0360.0390.0310.032

0.0320.0320.0290.0300.0370.0370.0320.0290.0280.0360.0490.0340.032

0.0280.0290.0250.0270.0340.0320.0310.0310.0280.0320.0430.0310.029

0.0270.0320.0240.0290.0360.0330.0270.0290.0250.0240.0410.0290.028

0.026 0.0260.030 0.0320.024 0.0240.028 0.0280.038 0.0300.033 0.03 60.033 0.0310.03 0 0.0320.028 0.0270.035 0.0350.043 0.0440.031 0.0310.03 1 0.028

0.0220.0300.0240.0270.0300.0330.0260.0300.0240.0340.0380.0280.027

0.0270.0300.0250.0280.0340.0340.0300.0310.0270.0330.0430.0310.030

10.87.69.04.09.95.29.26.07.2

11.27.66.76.7

Meat 0.032 0.030 0.03 1 0.034 0.031 0.030 0.032 0.031 0.029 0.031 4.8

(control)

START STOP Site Site Site Site Site Site Site Site SiteWeek# DATE DATE 4 6A* 14A* 15* 17A 21 29* 35 40* Mean RSD(%

40414243444546474849505152

28-Sep-045-Oct-0412-Oct-0419-Oct-0426-Oct-042-Nov-048-Nov-0416-Nov-0422-Nov-0430-Nov-047-Dec-0414-Dec-0420-Dec-04

5-Oct-0412-Oct-0419-Oct-0426-Oct-042-Nov-048-Nov-0416-Nov-0422-Nov-0430-Nov-047-Dec-0414-Dec-0420-Dec-0427-Dec-04

0.0340.0480.0380.0210.0180.0310.0230.0460.0380.0430.0290.0360.038

0.0340.0490.0390.0240.0200.0410.0240.0460.0400.0410.0320.0390.045

0.0340.0400.0350.0240.0180.0330.0240.0400.0380.0370.0280.0370.036

0.0360.0480.0380.0240.0210.0370.0250.0480.0340.0410.0300.0360.038

0.0330.0480.0390.0230.0190.0400.0240.0470.0400.03 80.0230.0360.031

0.0320.0430.0340.0190.0160.0330.0240.0410.0370.0400.0290.0350.041

0.0360.0400.037005 a

0.0200.04 10.0230.0430.0380.0420.0290.0400.035

0.0340.0450.0390.0210.0180.0330.0250.0420.0420.0390.0250.0380.034

0.0340.0400.0360.0210.0 180.0330.0210.0400.0390.0410.0260.0320.035

0.0340.0450.0370.0220.0 190.0360.0240.0440.0380.0400.0280.0370.037

3.78.75.08.58.011.25.27.25.84.89.96.4

11.1Mean

Annual Average0.034 0.036 0.033 0.035 0.034 0.033 0.035 0.033 0.032 0.034 4.3

0.033 0.033 0.032 0.034 0.032 0.031 0.033 0.031 0.030 0.032 3.9' Out of service due to road construction activities for plant security upgrades (planncd)

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 200428

Page 36: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ... · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1, 2.2 and 9.1. Additional

TABLE 8.3 GAMMA IN AIR FILTER COMPOSITES

ODCM required samples denoted by *units are pCi/m 3

(control)QUARTERENDPOINT

Site4

Site

6A*Site14A*

Site

15*Site17A

Site21

Site29*

Site35

Site40*NUCLIDE

.6

29-Mar-04

29-Jun-04

28-Sep-04

27-Dec-04

Cs-134Cs-137Cs-134Cs-137Cs-134Cs-137Cs-134Cs-137

<0.0043 <0.0035 <0.0035 <0.0034 <0.0027 <0.0034 <0.0028 <0.0033 <0.0029<0.0034 <0.0030 <0.0042 <0.0036 <0.0017 <0.0030 <0.0021 <0.0028 <0.0024<0.0044 <0.0013 <0.0044 <0.0035 <0.0021 <0.0043 <0.0013 <0.0036 <0.0034<0.0042 <0.0035 <0.0043 <0.0029 <0.0031 <0.0031 <0.0044 <0.0010 <0.0031<0.0023 <0.0034 <0.0044 <0.0020 <0.0030 <0.0024 <0.0034 <0.0025 <0.0040<0.0026 <0.0029 <0.0047 <0.0026 <0.0029 <0.0031 <0.0011 <0.0035 <0.0036<0.0024 <0.0038 <0.0024 <0.0022 <0.0034 <0.0023 <0.0052 <0.0022 <0.0020<0.0025 <0.0042 <0.0036 <0.0023 <0.0011 <0.0025 <0.0031 <0.0025 <0.0021

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

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 200429

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TABLE 8.4 RADIOTODINE IN AIR 1st - 2nd QUARTER

ODCM required samples denoted by *units arc pCi/M3

- 1st Quarter -

(control) required LLD <0.070

Wecek #STARTDATE

STOPDATE

Site4

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

Site21

Site29*

Site Site35 40*

2345678910111213

29-Dec-03 6-Jan-046-Jan-04 13-Jan-0413-Jan-04 20-Jan-0420-Jan-04 27-Jan-0427-Jan-04 3-Feb-043-Feb-04 10-Feb-0410-Feb-04 17-Feb-0417-Feb-04 24-Feb-0424-Feb-04 1-Mar-04I-Mar-04 9-Mar-049-Mar-04 16-Mar-0416-Mar-04 23-Mar-0423-Mar-04 29-Mar-04

<0.043 <0.031 <0.037 <0.022 <0.067 <0.030 <0.029 <0.043 <0.026<0.035 <0.056 <0.057 <0.040 <0.061 <0.035 <0.034 <0.040 <0.050<0.034 <0.030 <0.056 <0.039 <0.012 <0.041 <0.033 <0.029 <0.033<0.028 <0.053 <0.067 <0.033 <0.032 <0.042 <0.035 <0.041 <0.032<0.030 <0.042 <0.050 <0.038 <0.034 <0.024 <0.035 <0.026 <0.032Invalid ' <0.041 <0.059 <0.034 <0.032 <0.027 <0.047 <0.032 <0.048<0.037 <0.033 <0.044 <0.042 <0.055 <0.033 <0.049 <0.031 <0.043<0.036 <0.040 <0.047 <0.034 <0.012 <0.022 <0.040 <0.032 <0.029<0.063 <0.057 <0.049 <0.059 <0.057 <0.057 <0.050 <0.065 <0.064<0.061 <0.031 <0.030 <0.030 <0.043 <0.025 <0.044 <0.025 <0.043<0.035 <0.042 <0.039 <0.043 <0.049 <0.032 <0.041 <0.025 <0.048<0.035 <0.050 <0.052 <0.036 <0.051 <0.035 <0.050 <0.028 <0.037<0.037 <0.056 <0.059 <0.045 <0.049 <0.042 <0.038 <0.042 <0.037

2nd Quarter -(control)

START STOP Site Site Site Site Site Site Site Site SiteWeek # DATE DATE 4 6A* 14A* 15* 17A 21 29* 35 40*

14 29-Mar-04 6-Apr-04 <0.029 <0.047 <0.047 <0.030 <0.043 <0.017 <0.037 <0.024 <0.04415 6-Apr-04 13-Apr-04 <0.031 <0.048 <0.034 <0.032 <0.033 <0.034 <0.054 <0.034 <0.03316 13-Apr-04 20-Apr-04 <0.035 <0.062 <0.060 <0.034 <0.052 <0.031 <0.059 <0.028 <0.01317 20-Apr-04 27-Apr-04 <0.034 <0.032 <0.043 <0.033 <0.035 <0.024 <0.040 <0.030 <0.03718 27-Apr-04 4-May-04 <0.039 <0.042 <0.052 <0.040 <0.050 <0.031 <0.034 <0.043 <0.03619 4-May-04 11-May-04 <0.039 <0.042 <0.013 <0.023 <0.037 <0.065 <0.042 <0.031 <0.03620 11-May-04 18-May-04 <0.035 <0.031 <0.052 <0.045 <0.018 <0.034 <0.041 <0.034 <0.06021 18-May-04 25-May-04 <0.035 <0.034 <0.061 <0.041 <0.042 <0.031 <0.049 <0.031 <0.02622 25-May-04 1-Jun-04 <0.036 <0.061 <0.036 <0.039 <0.044 <0.048 <0.037 <0.038 <0.03023 1-Jun-04 7-Jun-04 <0.039 <0.048 <0.058 <0.039 <0.058 <0.045 <0.050 <0.040 <0.05024 7-Jun-04 15-Jun-04 <0.033 <0.057 <0.051 <0.033 <0.061 <0.032 <0.039 <0.041 <0.03025 15-Jun-04 22-Jun-04 <0.039 <0.057 <0.068 <0.027 <0.033 <0.036 <0.049 <0.032 <0.02226 22-Jun-04 29-Jun-04 <0.029 <0.055 <0.038 <0.044 <0.054 <0.041 <0.037 <0.039 <0.037

a Sample result invalidated due to anomalous gross beta result (contributing factor was ETM problems due to power outages)

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2004

30

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TABLE 8.5 RADIOTODINE IN AIR 3rd - 4th QUARTER

ODCM required samples denoted by *units are pCi/mr3

- 3rd Quartcr * *

(control) required LLD <0.070

START STOP Site Site Site Site Site Site Site Site SiteWeek # DATE DATE 4 6A* 14A* 15* 17A 21 29* 35 40*

27282930313233343536373839

29-Jun-046-Jul-0413-Jul-0420-Jul-0427-Jul-043-Aug-0410-Aug-0417-Aug-0424-Aug-0431 -Aug-047-Sep-0414-Sep-0421-Sep-04

6-Jul-04 <0.033 <0.03813-Jul-04 <0.029 <0.02720-Jul-04 <0.034 <0.05327-Jul-04 <0.042 <0.0453-Aug-04 <0.013 <0.03210-Aug-04 <0.044 <0.04917-Aug-04 <0.046 <0.06224-Aug-04 <0.054 <0.03831-Aug-04 <0.030 <0.0417-Sep-04 <0.037 <0.06014-Sep-04 <0.032 <0.06021-Sep-04 <0.032 <0.03528-Sep-04 <0.041 <0.043

<0.037 <0.039 <0.060 <0.042 <0.014 <0.041 <0.054<0.049 <0.049 <0.029 <0.034 <0.035 <0.056 <0.030<0.053 <0.037 <0.051 <0.013 <0.035 <0.045 <0.037<0.044 <0.068 <0.041 <0.046 <0.040 <0.045 <0.031<0.058 <0.032 <0.049 <0.032 <0.053 <0.036 <0.038<0.054 <0.050 <0.043 <0.034 <0.050 <0.036 <0.034<0.035 <0.035 <0.049 <0.037 <0.068 <0.033 <0.044<0.035 <0.036 <0.064 <0.033 <0.031 <0.042 <0.032<0.039 <0.040 <0.037 <0.032 <0.035 <0.035 <0.040<0.067 <0.047 <0.064 <0.042 <0.062 <0.043 <0.061<0.061 <0.032 <0.060 <0.040 <0.046 <0.040 <0.038<0.064 <0.027 <0.058 <0.035 <0.035 <0.063 <0.058<0.036 <0.058 <0.038 <0.060 <0.040 <0.051 <0.039

4th Quarter . ..

(control) required LLD <0.070

START STOP Site Site Site Site Site Site Site Site SiteWVeek t DATE DATE 4 6A* 14A* 15* 17A 21 29* 35 40*

40414243444546474849505152

28-Sep-045-Oct-0412-Oct-0419-Oct-0426-Oct-042-Nov-048-Nov-0416-Nov-0422-Nov-0430-Nov-047-Dec-0414-Dec-0420-Dec-04

5-Oct-04 <0.035 <0.04312-Oct-04 <0.053 <0.05519-Oct-04 <0.044 <0.06426-Oct-04 <0.033 <0.0122-Nov-04 <0.034 <0.0338-Nov-04 <0.064 <0.05816-Nov-04 <0.028 <0.04422-Nov-04 <0.044 <0.02930-Nov-04 <0.029 <0.0377-Dec-04 <0.042 <0.04214-Dec-04 <0.033 <0.07020-Dec-04 <0.045 <0.04727-Dec-04 <0.061 <0.064

<0.035 <0.032 <0.053 <0.053 <0.039 <0.052 <0.038<0.043 <0.055 <0.036 <0.042 <0.033 <0.013 <0.024<0.045 <0.044 <0.045 <0.058 <0.0 15 <0.035 <0.059<0.042 <0.056 <0.031 <0.049 OOS S <0.030 <0.031<0.033 <0.030 <0.058 <0.029 <0.059 <0.034 <0.041<0.053 <0.015 <0.017 <0.053 <0.042 <0.042 <0.063<0.049 <0.032 <0.044 <0.032 <0.030 <0.032 <0.036<0.053 <0.046 <0.033 <0.045 <0.042 <0.045 <0.038<0.030 <0.030 <0.040 <0.037 <0.032 <0.031 <0.034<0.013 <0.013 <0.045 <0.045 <0.059 <0.059 <0.036<0.046 <0.033 <0.036 <0.036 <0.060 <0.033 <0.053<0.036 <0.040 <0.040 <0.050 <0.042 <0.049 <0.038<0.033 <0.048 <0.041 <0.040 <0.057 <0.048 <0.033

' Out of service due to road construction activities for plant security upgrades (planncd)

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2004

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TABLE 8.6 VEGETATION

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

<60 <60 <80LOCATION TYPE DATE 1-131 Cs-134 Cs-137

COLLECTED

BRANCH Turnip Greens 10-Jun-04 <49 <45 <63RESIDENCE Collard greens 23-Jul-04 <49 <58 <42

(Site #52)*

Green cabbage 16-Jan-04 <40 <55 <63Red cabbage 16-Jan-04 <39 <58 <50

DUNCAN Lettuce 16-Jan-04 <54 <53 <61FAMILY Green cabbage 13-Feb-04 <49 <56 <23FARMS Red cabbage 13-Feb-04 <35 <56 <63

(Site #62)* Lettuce 13-Feb-04 <37 <44 <55Green cabbage 10-Mar-04 <42 <35 <69Red cabbage 10-Mar-04 <41 <29 <42

Lettuce 10-Mar-04 <46 <43 <55Green cabbage 15-Apr-04 <43 <58 <69Red cabbage 15-Apr-04 <46 <38 <57

Savoy cabbage 15-Apr-04 <57 <41 <49Savoy cabbage 13-May-04 <59 <49 <76Red cabbage 13-May-04 <58 <38 <70

Green cabbage 13-May-04 <44 <58 <55Green cabbage 22-Oct-04 <44 <58 <66Green cabbage 19-Nov-04 <39 <43 <36Red cabbage 19-Nov-04 <43 <52 <52

Savoy cabbage 17-Dec-04 <39 <56 <48Red cabbage 17-Dec-04 <45 <60 <74

Green cabbage 17-Dec-04 <55 <41 <79

MCCOYRESIDENCE NO SAMPLES AVAILABLE

(Site #47)*

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2004

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TABLE 8.7 MILK

ODCMI required samples denoted by *units are pCi/liter

SAMPLELOCATION

DATECOLLECTED

<1 <15 <18 <60 <15

1-131 Cs-134 Cs-137 Ba-140 La-140

22-Apr-04 <1 <2 <1 <3 <118-May-04 <1 <1 <1 <3 <1

PAINTER 17-Jun-04 <1 <1 <1 <3 <1GOATS 23-Jul-04 <1 <1 <1 <3 <1

(Site #51)* 20-Aug-04 <1 <1 <1 <3 <123-Sep-04 <1 <1 <1 <3 <122-Oct-04 <1 <1 <1 <3 <110-Nov-04 <1 <1 <1 <3 <1

22-Apr-04 <1 <1 <1 <4 <118-May-04 <1 <1 <1 <4 <11 1-Jun-04 <1 <1 <1 <3 <1

BARBER 16-Jul-04 <1 <1 <1 <3 <1GOATS 13-Aug-04 <1 <1 <1 <3 <1

(Site #53)* 17-Sep-04 <1 <1 <1 <3 <115-Oct-04 <1 <1 <1 <3 <1

10-Nov-04 <1 <1 <1 <3 <117-Dec-04 <1 <1 <1 <3 <1

BRANCHGOATS

(Site #54)

NO SAMPLES AVAILABLE

Notes: IBranch goats added to monitoring program in May.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 200433

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TABLE 8.8 DRINKING WATER

ODCM required samples denoted by *units arc pCi/liter

<2000

SAMPLE j MONTH <15 <15 <30 <15 <30 <15 <30 <15 <15 <18 <60 <15 QTRLY <4.0LOCATION IENDPOINT Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 11-3 Gross Beta

BERRYMANRESIDENCE(SITE #48)*

27-Jan-04 <11 <10 <21 <12 <30 <11 <20 <11 <13 <1324-Feb-04 <9 <9 <18 <10 <22 <10 <17 <9 <8 <929-Mar-04 <14 <14 <27 <15 <27 <10 <23 <12 <12 <1327-Apr-04 <9 <10 <17 <14 <24 <10 <18 <10 <11 <1325-May-04 <12 <11 <22 <14 <28 <15 <19 <12 <11 <1329-Jun-04 <12 <11 <23 <11 <30 <13 <23 <11 <11 <1327-Jul-04 <13 <14 <29 <14 <29 <15 <22 <13 <13 <1531-Aug-04 <11 <11 <20 <12 <27 <13 <18 <10 <10 <1028-Sep-04 <13 <12 <23 <13 <30 <14 <19 <11 <11 <1326-Oct-04 <10 <10 <20 <11 <22 <9 <16 <8 <8 <1030-Nov-04 <13 <10 <21 <9 <19 <11 <21 <11 <10 <1127-Dec-04 <13 <12 <26 <13 <30 <11 <18 <10 <10 <12

<41 <11 <3.1<30 <14 L <3.3<50 <12 <275 <3.2<33 <14 3.2 ± 1.8<37 <14 <3.2<41 <14 <265 <3.0<38 <15 [ <3.1<31 <9 _ <3.2<44 <14 <271 4.7± 1.8<32 <10 [,7.T 3.1 ± 1.7<43 <13 L 4.8 ± 1.7<38 <12 <276 <3.0

GAVETTERESIDENCE

(SITE #55)

27-Jan-04 <12 <11 <26 <15 <27 <10 <22 <11 <9 <924-Feb-04 <14 <12 <25 <15 <29 <15 <21 <12 <12 <1329-Mar-04 <11 <10 <16 <12 <17 <11 <17 <10 <10 <1127-Apr-04 <14 <14 <27 <14 <30 <15 <25 <12 <12 <1225-May-04 <12 <12 <23 <13 <29 <14 <19 <11 <10 <1329-Jun-04 <9 <8 <23 <9 <21 <11 <17 <9 <8 <927-Jul-04 <13 <12 <29 <15 <26 <12 <21 <12 <12 <13

31-Aug-04 <15 <15 <23 <14 <25 <13 <26 <12 <13 <1428-Sep-04 <14 <11 <23 <12 <30 <13 <19 <12 <11 <1226-Oct-04 <15 <13 <26 <15 <27 <13 <24 <13 <12 <1330-Nov-04 <13 <12 <23 <12 <29 <12 <20 <12 <11 <1227-Dec-04 <13 <13 <27 <14 <30 <14 <24 <11 <12 <13

<37 <11 1 4.1±1.6<43 <13 1.: <2.4<31 <15 <272 3.0± 1.7<49 <14 [7 2.941.5<39 <15 L_ <2.7<33 <15 <263 3.8± 1.6<43 <13 <2.4<48 <14 __: 3.6 + 1.7<38 <12 <272 4.9± 1.5<44 <14 5.0 ± 1.5<38 <11 .- 4.5 1.5<48 <14 <279 3.3 2.5

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 200434

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TABLE 8.8 DRINKING WATER

ODCMI required samples denoted by *units are pCi/liter

<2000

SAMPLE MONTII <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 11-3 Gross Beta

McARTHURRESIDENCE(SITE #46)*

27-Jan-04 <13 <12 <23 <12 <24 <13 <18 <11

24-Feb-04 <13 <12 <30 <15 <28 <13 <23 <13

29-Mar-04 <11 <12 <24 <13 <30 <14 <20 <12

27-Apr-04 <13 <11 <21 <7 <21 <12 <16 <9

25-May-04 <12 <12 <24 <15 <26 <13 <18 <10

29-Jun-04 <13 <14 <25 <14 <30 <14 <18 <11

27-Jul-04 <10 <10 <16 <8 <18 <9 <14 <8

31 -Aug-04 <14 <15 <27 <13 <29 <14 <26 <13

28-Sep-04 <11 <10 <27 <14 <25 <12 <18 <10

26-Oct-04 <13 <13 <26 <13 <28 <15 <23 <13

30-Nov-04 <10 <9 <17 <8 <22 <9 <12 <7

27-Dec-04 <10 <9 <20 <11 <23 <9 <19 <8

<11 <14 <36 <15 2.7 ± 1.5<10 <14 <46 <13 <2.5<11 <13 <41 <14 <275 <2.5

<9 <9 <32 <15 3.3 + 1.4

<10 <11 <41 <12 L <2.6

<12 <14 <44 <14 <265 <2.3

<8 <10 <29 <15 F <2.4

<13 <14 <44 <10 E J-'^_ <2.4<11 <12 <33 <9 <262 5.1 + 1.4

<13 <13 <42 <13 - 3.3 ± 1.4<10 <8 <32 <15 L. 4.1 ± 1.4

<7 <12 <32 <13 <278 2.5 ± 1.5I.

CIIOWANECRESIDENCE(SITE #49) *

27-Jan-04 <12 <10 <21 <15 <26 <12 <22 <1024-Feb-04 <13 <12 <27 <15 <29 <12 <21 <1329-Mar-04 <12 <10 <19 <12 <30 <13 <22 <1027-Apr-04 <14 <12 <25 <14 <29 <15 <20 <1225-May-04 <10 <10 <20 <12 <30 <11 <16 <1029-Jun-04 <14 <12 <29 <14 <28 <14 <26 <1327-Jul-04 <12 <12 <20 <13 <30 <13 <23 <13

31-Aug-04 <12 <13 <22 <14 <29 <15 <21 <1128-Scp-04 <13 <11 <27 <11 <30 <12 <22 <1126-Oct-04 <10 <13 <26 <12 <28 <14 <17 <1130-Nov-04 <11 <13 <27 <14 <30 <14 <18 <1127-Dcc-04 <12 <14 <29 <14 <30 <12 <21 <12

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

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

<39 <11<43 <15 L I<46 <14 <271<43 <12<36 <15 sL:: -<39 <15 <260<40 <14<44 <14 LF-7<40 <9 <274<39 <13

<39 <11<41 <11 <280

<2.3<2.6<2.4<2.1<2.6<2.3<2.4<2.4<1.9<2.0<1.9<2.3

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2004

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Page 43: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ... · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1, 2.2 and 9.1. Additional

TABLE 8.9 GROUNDWATER

ODCM required samples denoted by *units are pCi/liter

SAMPLE DATE <15 <15 <30 <15 <30 <15 <0 <15 <15 <18 <60 <15 <2000

LOCATION COLLECTED Mn-54 Co-58 Fc-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 11-3

WELL27ddc

(Site #57)*

27-Jan-04 <9 <11 <23 <14 <23 <13 <15 <10 <9 <10 <36 <15 <27327-Apr-04 <11 <10 <21 <13 <24 <12 <17 <10 <10 <11 <32 <15 <27827-Jul-04 <9 <10 <21 <9 <20 <12 <16 <9 <9 <10 <31 <13 <26826-Oct-04 <11 <11 <21 <11 <26 <14 <19 <11 <11 <11 <42 <15 <273

I.

WELL34abb

(Site #58)*

27-Jan-04 <12 <12 <24 <13 <26 <12 <19 <12 <10 <12 <43 <15 <27327-Apr-04 <11 <10 <19 <10 <21 <11 <18 <11 <10 <11 <37 <15 <27627-Jul-04 <13 <13 <23 <15 <28 <15 <21 <13 <12 <15 <43 <14 <27126-Oct-04 <13 <12 <21 <13 <24 <15 <21 <12 <12 <13 <42 <14 <272

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2004

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Page 44: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ... · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1, 2.2 and 9.1. Additional

TABLE 8.10 SURFACE WATER

ODCM required samples denoted by *units are pCi/liter

SAMPLELOCATION

MONTH •15 <15 <30 <15 <30 <15 <30ENDPOINT Mn-54 Co-58 Fc-59 Co-60 Zn-65 Nb-95 Zr-95

<15 <15 .<18 <60 <15 .1-131 Cs-134 Cs-137 Ba-140 La-140

<3000H-3

RESERVOIR(Site #60) *

27-Jan-04 <12 <15 <27 <14 <28 <14 <2224-Feb-04 <11 <10 <20 <11 <21 <11 <1729-Mar-04 <7 <7 <14 <8 <18 <7 <1227-Apr-04 <11 <11 <23 <13 <25 <14 <1825-May-04 <15 <15 <21 <14 <29 <15 <2229-Jun-04 <12 <11 <27 <13 <27 <13 <2127-Jul-04 <13 <14 <24 <15 <25 <13 <27

31-Aug-04 <12 <11 <28 <15 <27 <11 <1628-Sep-04 <10 <12 <28 <15 <18 <11 <1826-Oct-04 <13 <11 <25 <12 <23 <12 <2230-Nov-04 <11 <11 <25 <13 <29 <12 <2027-Dec-04 <13 <12 <26 <14 <24 <14 <20

<13<12<8

<15<14<12

15±8<119±9<12<12<13

<11<10<7

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

<12<11<8

<12<15<13<13<11<11<11<12<12

<42<36<27<44<51<40<47<34<37<41<43<42

<14 L _i<8 <280

<11 F- ^<13 L-.^<15 <267<14<10 _ _ _

<12 <275<15<12<15 <279

.. .. . . _ . _ _ .

EVAP POND 1(Site #59) *

27-Jan-04 <15 <11 <26 <14 <25 <15 <19 <1224-Feb-04 <11 <12 <24 <10 <30 <11 <19 <929-Mar-04 <13 <12 <23 <13 <29 <10 <20 <1027-Apr-04 <12 <11 <22 <15 <27 <12 <21 <1225-May-04 <9 <10 <26 <13 <30 <10 <14 <1029-Jun-04 <10 <8 <24 <15 <27 <10 <19 <827-Jul-04 <11 <13 <25 <13 <30 <12 <22 <10

31-Aug-04 <11 <10 <23 <13 <30 <12 <20 21 + 12a28-Sep-04 <12 <13 <30 <13 <30 <13 <25 <1226-Oct-04 <11 <10 <23 <13 <30 <12 <17 <930-Nov-04 <13 <13 <27 <14 <30 <14 <20 <1227-Dec-04 <11 <9 <26 <13 <25 <9 <15 <11

<12<11.<10<11<8

<10<11<9<10<9

<10<9

<14<11<10<12<11<12<12<12<13<11<11<10

<44<33<34<37<32<31<38<39<40<34<42<32

<13<12 -

<9 954 ± 181<13 fT TT<15<7 12664±184

<12<12<10 864 176<12.<150 67 17_<15 R674 17R

_ _ . _

EVAP POND 2(Site #63) *

27-Jan-04 <10 <10 <23 <11 <26 <10 <2024-Feb-04 <12 <11 <28 <15 <30 <11 <2129-Mar-04 <12 <14 <26 <13 <25 <11 <2227-Apr-04 <10 <11 <24 <12 <24 <10 <1725-May-04 <11 <11 <25 <12 <30 <11 <1929-Jun-04 <11 <12 <26 <13 <24 <14 <2127-Jul-04 <12 <11 <29 <14 <25 <13 <2331-Aug-04 <14 <11 <27 <13 <30 <11 <2228-Scp-04 <10 <12 <27 <13 <30 <12 <2226-Oct-04 <14 <12 <25 <15 <29 <14 <2030-Nov-04 <10 <10 <23 <14 <30 <11 <2027-Dec-04 <12 <12 <24 <14 <30 <12 <24

<12<12<15<11<12<13<15<12<13<14<11<12

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

<14<14<14<11<13<15<16<14<14<15<13<15

<37<42<42<32<39<38<45<46<42<44<36<44

<14 1 .-.<14 uL f-:<15 1284± 184<14 r<14<15 1826± 195<15 .<12 L<10 1558± 187<13 F f l<13 IL:.-<12 1294+ 186

a Sample recount rcsult was 18 + 7 pCi/litcr

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2004

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Page 45: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ... · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1, 2.2 and 9.1. Additional

TABLE 8.10 SURFACE WATER

ODCMI required samples denoted by *units are pCi/liter

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

I

WRFINFLUENT

6-Jan-0413-Jan-0420-Jan-0427-Jan-043-Feb-0410-Feb-0417-Feb-0424-Feb-04I-Mar-049-Mar-0416-Mar-0423-Mar-0430-Mar-046-Apr-0427-Apr-044-May-04I 1-May-0417-May-0425-May-04

I-Jun-048-Jun-0415-Jun-0422-Jun-0429-Jun-046-Jul-0413-Jul-0420-Jul-0427-Jul-043-Aug-0410-Aug-04

<10 <9 <17 <13 <24 <10 <14 11 i 8 <10<11 <9 <30 <13 <29 <11 <19 23 12 <10<11 <11 <21 <13 <19 <12 <17 20 10 <10<9 <9 <18 <15 <24 <10 <18 35 10 <10

<10 <11 <20 <8 <25 <10 <14 14 8 <9<9 <10 <25 <13 <30 <8 <23 46 12 <8

<13 <11 <26 <15 <23 <13 <21 41 12 <8

<15 <13 <24 <15 <24 <14 <20 72 15 <12<10 <10 <19 <11 <24 <10 <14 57i 13 <7<9 <10 <18 <10 <18 <10 <17 135 19 <8<9 <9 <11 <10 <21 <9 <15 47 10 <7<12 <11 <25 <14 <28 <15 <22 43 13 <9<11 <10 <20 <9 <20 <10 <20 63 ± 12 <9

<12 <15 <30 <10 <29 <14 <22 36 ± 13 <12<10 <9 <23 <14 <19 <11 <15 71 ± 13 <9<11 <11 <20 <14 <23 <10 <21 15 ±f 9 <9

<9 <11 <25 <13 <30 <13 <20 23 + 9 <11<12 <10 <22 <14 <24 <12 <22 <15 <11<9 <10 <23 <8 <20 <9 <17 27 + 11 <10

<13 <11 <18 <14 <28 <11 <18 24+ 13 <11<12 <11 <25 <15 <27 <14 <20 14 + 11 <11<12 <13 <24 <11 <30 <9 <16 24 8 <12<11 <11 <25 <13 <29 <11 <19 20 11 <11

<9 <12 <22 <11 <20 <11 <15 18 8 <9<11 <12 <26 <15 <28 <12 <24 27 10 <12<9 <9 <19 <11 <23 <8 <18 21 +8 <8<9 <9 <20 <10 <25 <9 <14 69+ 12 <8

<7 <10 <23 <12 <25 <10 <17 29 9 <9<12 <11 <21 <14 <26 <10 <19 26 9 <9

<12 <13 <28 <12 <27 <12 <25 18 10 <12

<12<13<9

<11<9

<11<13<15<11<9

<8<14<10<14<12<13<12<14<12<13<11<14<12<9

<10<10<7

<10<12<14

<30 <15<37 <12<31 <14<33 <14 <282<28 <15<36 <13<34 <8 .. .<48 <12 <288<32 <13.<28 <15<28 <12<41 <11 :.<36 <14 <283<46 <13 7 ,<34 <13 <284<31 <15 .<31 <15<46 <15 .<37 <15 <277<35 <13<42 <12<32 <12<34 <15<30 <14 <279<40 <13<32 <13<29 <13 _--<32 <15 <279<28 <15<43 <15 .

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2004

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Page 46: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ... · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1, 2.2 and 9.1. Additional

TABLE 8.10 SURFACE WATER

ODCM required samples denoted by *units are pCi/iiter

SAMPLELOCATION

DATECOLLECTED .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

WRFINFLUENT(continued)

17-Aug-0424-Aug-0431-Aug-047-Sep-0414-Sep-0421-Sep-0428-Sep-045-Oct-0412-Oct-0422-Oct-0426-Oct-042-Nov-048-Nov-0416-Nov-0422-Nov-0430-Nov-047-Dec-0414-Dec-0420-Dec-0427-Dec-04

<13 <14 <27 <15 <30 <14 <22<9 <11 <24 <13 <29 <10 <17

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

24 + 1014±9

18± 1441 I 1116± 1132 ± 1337 ± 1315±9

27 ± 1461 ± 1552 ± 1319± 1221 ± 11

<1534 ± 18

<13193 ± 2955 ± 14105 ± 1812±9

<11 <13<10 <10<11 <14<11 <12<11 <11<12 <15<13 <12<10 <14<13 <13<10 <11I<12 <14<10 <12<11 <12<11 <14<11 <13<11 <12<11 <13<12 <13<11 <13<11 <12

<40 <12 F- -_ 1<36 <15<44 <15 <276<31 <12<42 <15<43 <14 L'" _':.

<40 <11 <280<41 <12<44 <12<46 <12 L :- -<42 <12 <281<37 <15<41 <12<41 <13<46 <12 L -

<31 <13 <277<42 <15<37 <13<43 <15<42 <12

SEDIMENT.BASIN #2

24-Feb-049-Mar-046-Apr-0413-Apr-042-Nov-048-Nov-0416-Nov-0422-Nov-0430-Nov-047-Dec-0414-Dec-0420-Dec-0427-Dec-04

<12 <13 <28 <14 <29 <13 <23<12 <12 <24 <15 <27 <12 <21<10 <7 <17 <7 <21 <9 <15<8 <9 <17 <10 <21 <8 <17<15 <13 <22 <13 <29 <14 <27<13 <15 <27 <13 <30 <14 <25<12 <12 <23 <15 <24 <10 <21<11 <10 <22 <10 <20 <9 <17<14 <11 <29 <10 <29 <13 <21<13 <10 <21 <12 <26 <12 <19<13 <12 <24 <13 <25 <14 <21<13 <12 <24 <13 <30 <13 <22

<10 <10 <26 <13 <22 <12 <14

<11<12<8<8

<12<11<8<9

<12<9<11<11

<9

<11 <13<11 <12<8 <8<8 <9<14 <14<11 <14<10 <11<8 <11<12 <12<9 <13<13 <15<12 <13

<44 <13<44 <11<29 <11<31 <15<45 <9<45 <12<36 <13<30 <15<45 <13<34 <15<35 <15<38 <11

<294384 ± 173

<286<283

333 + 180482 + 172

<273<264

278 I 167<288

331 ± 174423 ± 174

<294<9 <13 <31 <11

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2004

39

Page 47: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ... · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1, 2.2 and 9.1. Additional

TABLE 8.11 SLUDGE/SEDIMENT

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

SAMPLELOCATION

DATECOLLECTED 1-131 Cs-134 Cs-137 In-111

WRFCENTRIFUGE

WASTE SLUDGE

6-Jan-0413-Jan-0420-Jan-0427-Jan-043-Feb-0410-Feb-0417-Feb-0424-Feb-04I-Mar-049-Mar-0416-Mar-0423-Mar-0430-Mar-046-Apr-04

20-Apr-0427-Apr-044-May-04I 1-May-0417-May-0425-May-04

I-Jun-048-Jun-0415-Jun-0422-Jun-0429-Jun-046-Jul-0413-Jul-0420-Jul-0429-Jul-043-Aug-0410-Aug-0417-Aug-0424-Aug-0431 -Aug-047-Sep-0414-Sep-0421-Sep-0428-Sep-045-Oct-0412-Oct-0426-Oct-042-Nov-048-Nov-0416-Nov-0422-Nov-0430-Nov-047-Dec-0414-Dec-0420-Dec-0427-Dec-04

849i 116417 i 71396i 72330i 62452 i 75402 i 69203 ± 44278 i 56571 ± 87643 ± 91356 i 68791 ± 101575i 89

787i± 111743 i 104466478525 ± 74215433286 :t 55493 + 71760 ±t 106720 1021116± 137432 74680± 87444 4± 738064 110955 ± 1251431 ± 1621288 ± 1491013 131951 ± 113590 ± 79

943±E 1251093 ± 1411146± 146880± 118773 ± 105897± 1081007 ± 130296 ± 52

10064 120629 ± 94316 ± 55499 ± 76413 ± 63376 ± 66473 ± 68

1050± 12810144 123

<24<23<31<24<21<25<24<39<12<28<39<20<24<30<34<32<23<12<29<16<57<27<27<9<19<20<26<26<25<23<29<21<20<31<19<6<23<30<19<23<22<14<24<21<25<24<27<25<29<24

<25<30<32<29<35<22<41<33<30<32<45<29<37<37<39<30<24<12<26<29<34<20<26<32<23<12<26<20<28<26<30<22<13<27<7<28<37<7<24<25<23<28<8<27<31<24<21<22<22<24

32 ± 3113 ± 8

50 4 25

39 ± 19

51 ± 26

53 ± 27

37± 2541 ± 24

51 ± 23

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2004

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Page 48: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ... · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1, 2.2 and 9.1. Additional

TABLE 8.11 SLUDGE/SEDIMENT

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

DATESAMPLE LOCATION COLLECTED 1-131 Cs-134 Cs-137

(N) 18-Nov-04 13+7 <7 <11(E) 18-Nov-04 7+7 <9 <11

EVAP POND I (S) 18-Nov-04 12±8 <9 <11(W) 18-Nov-04 <8 <11(C) No sediment obtainable(N) 18-Nov-04 <10 14±7(E) 18-Nov-04 <10 18±9

EVAP POND 2 (S) 18-Nov-04 <13 15 ± 11(W) 18-Nov-04 <9 12+ 11(C) 18-Nov-04 <12 18 ±10

COOLING TOWER LOUVER/PIPING SCALE

UNIT APPROXIMATE ISOTOPE ACTIVITY RANGE SAMPLE TYPE FRACTION OF SAMPLESCYCLE VOLUME (yd3) (pCi/liter) ABOVE MDA

lRIO 70 n/a <MDA CW(PW piping scale none

IRI 8.5 n/a <MDA CW/PW piping scale none

2R1 1 6 Co-60 3.41E-07 to 8.17E-07 CW/PW piping scale 8 of 8Cs-137 <MDA to 5.62E-08 3 of 8

2R1 1 150 Co-60 <MDA to 1.07E-06 Cooling tower louver scale 25 of 32

3R10 30 n/a <MDA Cooling tower louver scale none

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 200441

Page 49: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ... · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1, 2.2 and 9.1. Additional

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

Gross Beta in Air 1994-2004

1.000 -

I0.100 -

EI

0.010

0.001 I i i i I"I t.o o %Oa r- oc o. o, e o ,

0% 0% el 0 0% % 0% w 0 0 w 0cc cc cc Q U U U U Q cm U

-S < ) Q Q Sc

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 200442

Page 50: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ... · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1, 2.2 and 9.1. Additional

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

+ Gross Bcta in Air Particulates- pre-operational (1981-1985)1994199519961997

-1998control location 1999

0.100 2000

0.090 2001

0.080 - 20022003

0.070 x 2004

0.060

Q 0.050

0.040 __-_._.____

0.020 ,

0.010

0.000 IVioo l l% l0

o m -Lo ation* _- U _. _.

Sample Location

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2004

43

Page 51: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ... · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1, 2.2 and 9.1. Additional

FIGURE 8.3 GROSS BETA IN DRINKING WATER

10

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

- Berryman (site #48)- Chowanec (site #49)I-

0.

5 +

N

0 I I I I I

Jan Feb Mar Apr May JunI I I I I I

Jul Aug Sep Oct Nov Dec

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

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2004

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Page 52: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ... · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1, 2.2 and 9.1. Additional

FIGURE 8.4 EVAPORATION POND TRITIUM ACTIVITY

5000

4000

3000

2000

1000

0\0\0O cc c-ct t-0 ow a, a\ C 0 0 0 - - - " '1 q I'D t- 00 ON 0 - C4 m 'T00 0o oo w0 00 00 00 00 00 c 0 00 0% 0% 0\ 0% 0c - % 0% 0% 0% 0 0% % 0% T 9 9 9 9 0

, ,o S S~0 W p S to u S So S 4 So S = a C S C S S =

= li 0. 1 0 94 : 0 P. 0 = 0 - 0 3 : = 0 z = 0 = g g-b < < Q < C C " "S S" -" S,

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT.- 2004

45

Page 53: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ... · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1, 2.2 and 9.1. Additional

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.

TLDs were placed in forty-nine locations from one to thirty-five miles from the PVNGS.TLD locations are shown in Figures 2.1 and 2.2 and are described in Table 9.1. TLD resultsfor 2004 are presented in Table 9.2. Historical environmental gamma radiation results for1985 through 2004 are presented in graphical form on Figure 9.1 (excluding transit controlTLD #45).

Figure 9.2 depicts the environmental TLD results from 2004 as compared to the pre-operational TLD results (excluding sites #41, #43, and #46-50 as they were either deleted orhad no pre-op TLD at these locations for comparison). The site to site comparisons indicate adirect correlation with respect to pre-operational results. It is evident that the offsite dose, asmeasured by TLDs, has not changed since Palo Verde became operational.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 200446

Page 54: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ... · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1, 2.2 and 9.1. Additional

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

-

TLD SITEI23456*7891011121314151617i8192021222324252627282930313233343536373839404142

LOCATIONE30

ENE24E21E16

ESElISSE31

SE7SSE4

S5SE5

ESE5E5Nl

NNE2NE2

ENE2E2

ESE2SE2

SSE2S3

SSW3W5

SW4WSW5SSW4SWI

WSW1WI

WNW1NW1

NNW1NW4

NNW5NNW8

N5NNE5NE5

ENE5N3

ESE3N8

LOCATION DESCRIPTIONGoodyearScott-Libby SchoolLiberty SchoolBuckeyePalo Verde SchoolAPS Gila Bend substationOld US 80 and Arlington School RdSouthern Pacific Pipeline Rd.Southern Pacific Pipeline Rd.355h Ave. and Elliot Rd.339th Ave. and Dobbins Rd.339h 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 Rd395th Ave. and Van Buren St.TonopahWintersburg Rd. and Van Buren St.363"d Ave. and Van Buren St.355th Ave. and Buckeye Rd.343'd Ave. N of Broadway Rd.WintersburgArlington SchoolRuth Fisher School

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 200447

Page 55: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ... · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1, 2.2 and 9.1. Additional

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

-

TLD SITE44*

45**4647484950

LOCATIONENE35OnsiteENE30

E35E24

ENEI IWNW5

LOCATION DESCRIPTIONEl MirageCentral 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).

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 200448

Page 56: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ... · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1, 2.2 and 9.1. Additional

TABLE 9.2 2004 ENVIRONMENTAL TLD RESULTSUnits are mrem/std qtr

TLD Site # Ist Quarter 2nd Quarter 3rd Quartcr 4th Quarter Average1 22.9 22.8 22.9 23.9 23.12 19.8 20.2 21.3 21.3 20.73 22.4 22.4 23.2 22.7 22.74 21.3 22.2 21.8 22.5 22.05 20.5 20.3 20.7 19.7 20.3

6(control) 24.4 25.1 25.4 25.9 25.27 23.9 24.2 23.1 23.7 23.78 22.3 22.5 21.3 22.9 22.39 26.2 25.7 26.1 26.9 26.2

10 22.2 22.7 22.2 22.5 22.411 24.1 23.5 23.5 23.4 23.612 21.4 21.6 21.7 21.5 21.613 24.2 23.2 24.3 23.7 23.914 22.5 24.1 23.9 24.2 23.715 22.3 22.4 23.1 22.8 22.716 20.8 20.2 21.2 20.2 20.617 23.8 23.4 24.0 23.5 23.718 22.6 21.8 22.8 21.9 22.319 23.1 23.5 23.7 24.2 23.620 22.9 22.5 22.2 22.7 22.621 23.9 24.5 24.2 23.9 24.122 24.3 23.8 24.9 24.5 24.423 21.3 21.8 21.4 22.2 21.724 21.6 20.9 21.1 21.3 21.225 22.4 21.9 22.5 21.4 22.126 26.1 25.5 27.1 26.3 26.327 27.0 26.3 27.2 25.6 26.528 24.4 24.0 24.9 24.1 24.429 24.1 24.1 24.3 23.2 23.930 24.6 24.3 25.3 25.3 24.931 22.0 21.8 22.2 22.5 22.132 24.7 23.6 24.5 24.0 24.233 24.2 24.2 24.8 23.9 24.334 26.9 26.2 25.9 26.6 26.435 29.5 29.0 29.6 29.5 29.436 23.8 23.6 23.8 24.0 23.837 22.7 21.6 23.4 22.0 22.438 26.9 25.6 27.3 26.1 26.539 22.5 22.5 22.6 23.4 22.840 24.4 23.4 24.5 23.4 23.941 22.8 21.7 23.0 22.6 22.542 25.6 24.8 25.4 25.0 25.2

44 (control) 17.9 19.0 19.0 19.5 18.945 (transit control) 4.8 5.7 5.6 5.5 5.4

46 24.9 25.6 26.4 25.4 25.647 22.0 21.4 22.3 23.5 22.348 22.6 22.4 22.5 23.4 22.749 21.2 21.1 22.2 21.7 21.6so 17.9 18.4 18.2 18.8 18.3

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -200449

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FIGURE 9.1 NETWORK ENVIRONMENTAL TLD EXPOSURE RATES

30.0

28.0

26.0

J

z 24.0

2

22.0

20.0

18.0

mR/std qtr

BBASELINE

- - - - IOYEARMEAN

o'n " %O O tN- t- 00 00 O C0 C 0 0- _ " M M ' t " '0 ' %0 N N 000 0% a a 0 0- - " M M7 ~tw000000000 0000000000w0% 0% 07% 0% c0% 0% 0% 07% 0% 0% 0% a, 0% 0% 0 0% 0% 0% 0% 0% 0000000000 4 C C C

>- ch; cd ;e En ;- ch 0- En D-Y ch ;- C5 ;A 05 °- C05 :Eth> h >- th °-:n :E rh :X tn :3 En ~E v) Cd m :c C) cE rEvt~~~~~~~~coS~~~. 0.vmc~zS ~~ov S ~ vt~Su ~~~tv

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 200450

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FIGURE 9.2 ENVIRONMENTAL TLD COMPARISON - PRE-OPERATIONAL VS 2004

35 T Control TLD

30

a,< 25U,

S 20

3 15Cn0

l05 10

.Is

0

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

TID Number

TLD #41 monitoring location was deleted in June, 2000 due to school closing (this TLD was placed at new school in 2004)TLD #43 monitoring location was deleted in 1994 due to school closingTLDs #46-50 are not included since they were not included in the pre-op monitoring program

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2004

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Page 59: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ... · in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2.1, 2.2 and 9.1. Additional

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 2004.

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 no changes in nearest resident status. Dose calculations indicated thehighest dose to be 0.177 mrem.

Milk Animal

There was one (1) change in nearest milk animal (goat) status. Dose calculationsindicated the highest dose to be 1.03 mrem. This new location was added to theREMP.

Vegetable Gardens

There were four (4) changes in nearest garden status. Dose calculations indicated thehighest dose to be 0.419 mrem. One new garden location replaced an existinglocation.

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

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 200452

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TABLE 10.1 2004 LAND USE CENSUS(Distances and directions are relative to Unit 2 in miles)

NEAREST NEAREST NEAREST CALCULATED DOSESECTOR RESIDENT GARDEN MILK ANIMAL (mrem) CHANGEl (COW/GOAT) FROM 2003

N 1.55 1.79 NONE Resident 6.34E-02Garden 2.88E-01

NNE 1.52 2.05 2.05 Resident 1.21E-01 GardenGarden 4.19E-01 Milk animal

l Milk 1.03E+00 _Milkanimal

NE 2.16 NONE 3.91 Resident 1.43E-01l Milk 6.31E-01

ENE 2.67 4.72 4.84 Resident 9.50E-02 GardenGarden 1.80E-01

l Milk 2.64E-01E 2.81 NONE NONE Resident 8.34E-02 Garden

ESE 3.17 3.85 NONE Resident 8.39E-02Garden 2.95E-01

SE 4.10 NONE NONE Resident 8.87E-02SSE NONE NONE NONE NA

S NONE NONE NONE NASSW NONE NONE NONE NASW 1.39 NONE NONE Resident 1.77E-01

|WSW 0.75 NONE NONE Resident 1.03E-01

| W 0.70 NONE NONE Resident 7.80E-02

WNW 2.67 NONE NONE Resident 1.96E-02NW 1.12 NONE NONE Resident 5.92E-02

NNW 1.30 3.86 NONE Resident 5.96E-02 Gardenl Garden 8.39E-02

COMMENTS:

Dose calculations were performed using the GASPAR code and 2003 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 - 200453

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11. Summary and Conclusions

The conclusions are based on a review of the radio assay results and background gammaradiation measurements for the 2004 calendar year. Where possible, the data were comparedto pre-operational sample data.

All sample results for 2004 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, WRFCentrifuge sludge, and Reservoir is the result of offsite sources and appears in the effluentsewage from Phoenix. The levels of I-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 ue'ere no measurable radiological impacts on the envirolnment dute to PVANGSoperations in 2004.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 200454

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TABLE I1.1

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL SUMMARY

Palo Verde Nuclear Generating Station Docket Nos. STN 50-528/529/530Maricopa County, Arizona Calendar Year 2004

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 (IV Nonroutine(Unit of Analyses (from Table Mean (f)' Distance and Range Mean (f)a Reported

Measurement) Performed 6.1) Range Direction Range Measurements

Direct Radiation TLD - 196 NA 23.4 (184/184) Site #35 29.4 (4/4) 22.0 (8/8) 0(mrem/std. qtr.) 17.9-29.6 8 miles 3350 29.0 -29.6 17.9-25.9

Air Particulates Gross Beta - 466 0.010 0.032 (414/414) Site #15 0.034 (52/52) 0.033 (52/52) 0(pCUn 3) 0.012 - 0.080 2 miles 45° 0.014 - 0.074 0.013 - 0.079

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. - 466(pCi/m3) 1-131 0.07 <LLD NA <LLD <LLD 0

Broadleaf Gamma Spec. - 23Vegetation I-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

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TABLE 11.1

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL SUMMARY

Palo Verde Nuclear Generating Station Docket Nos. STN 50-528/529/530Maricopa County, Arizona Calendar Year 2004

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 (fa Nonroutine(Unit of Analyses (from Table Mean (f) Distance and Range Mean (f) 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(pCiAiter) 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 3.8 (19/48) Site #55 4.0 (9/12) NA 02.5 -5.1 3 miles 2200 2.9-5.0

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

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 200456

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TABLE I 1.1

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL SUMMARY

Palo Verde Nuclear Generating Station Docket Nos. STN 50-528/529/530Maricopa County, Arizona Calendar Year 2004

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 (fl Nonroutine(Unit of Analyses (from Table Mean (f)' Distance and Range Mean (ft Reported

Measurement) Performed 6.1) Range Direction Rangc MeasurementsGamma Spec. - 17

1-131 1.0 <LLD NA <LLD <LLD 0Milk Cs-134 15 <LLD NA <LLD <LLD 0

(pCiAiter) Cs-137 18 <LLD NA <LLD <LLD 0Ba-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 1-131 15 15 (3/36) Site #59 21(1/12) NA 0(pCi/liter) 9 - 21 Onsite 180° 21 -21

Cs-134 15 <LLD NA <LLD NA 0

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

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 200457

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TABLE 11.1

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL SUMMARY

Palo Verde Nuclear Generating StationMaricopa County, Arizona

Docket Nos. STN 50-528/529/530Calendar Year 2004

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 (fW Nonroutine(Unit of Analyses (from Table Mean (f)8 Distance and Range Mean (a)t Reported

Measurement) Performed 6.1) Range Direction Range Measurements

Surface Water 11-3 - 12 3000 1239 (8/12) Site #63 1491 (4/4) NA 0(pCi/liter) 864- 1826 Onsite 1800 1284- 1826

-continued-

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

parentheses. (f)

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

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12. References

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

* 2. 1985-2003 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.

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