Text

1993 Annual Radiological Environ Operating Rept
	ML17310B249
Person / Time
Site:	Palo Verde
Issue date:	12/31/1993
From:	Conway W; ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	102-02927-WFC-R, 102-2927-WFC-R, NUDOCS 9405040147
	Download: ML17310B249 (134)
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ACCESSION NBR:9405040147 DOC.DATE: 93/12/31 NOTARIZED: NO DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH.NAME AUTHOR AFFILIATION CONWAY,W.F.

Arizona Public (Service Co.

(formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION gv~dV O9P I

SUBJECT:

Palo Verde Nuclear Generating Station Units 1,2

& 3 Annaul ~

D Radiological Emviromental Operating Rept for 1993. q/ly/qP 8

DISTRIBUTION CODE:

IE25D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Environmental Monitoring Rept (per Tech Specs)

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NOTES:STANDARDIZED PLANT Standardized plant.

Standardized plant.

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PHOENIX. ARIZONA85072-3999 102-02927-WFC/RAB/JRP April 24, 1994 WILLIAMF. CONWAY EXECUTIVEViCEPRESIDENT NUCLEAR U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2, and 3 Docket Nos. STN 50-628/529/630 Annual Radiological Environmental Operating Report File: 94-005-419.05 94-056-026 Enclosed please find a copy ofthe Annual Radiological Environmental Operating Report for PVNGS. This report covers the operation of PVNGS Units 1, 2, and 3 during 1993, and is being submitted pursuant to Technical Specification 6.9.1.7.

Should you have any questions, please contact Richard A.'Bernier of my staff at (602) 393-5882.

Sincerely, WFC/RAB/JRP/rv Enclosure cc:

L. J. Callan K. E. Perkins K. E. Johnston B. E. Holian A. V. Godwin (ARRA)

" "9405oooi<7 ENCLOSURE.

PALO VERDE NUCLEARGENERATING STATION 1993 ANNUALRADIOLOGICAL.ENVIRONMENTALOPERATING REPORT

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TABLEOF CONTEXTS 1 ~O.Illtroductioll I ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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2.0 Description of the Monitoring Program.................

3.0 Sample Collection i.ogram.....................................................

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~0 Alldlytic41Llocedures

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5.0 Nuclear Instrumentation...................................

6.0 Isotopic Detection Limits and Reporting Criteria............................

7.0 EPA Interlaboratory Comparison Program...............................

8.0 Data Interpretations and Conclusions.................................

9.0 "Thermoluminescent Dosimetry Results"and: Data"Interpretation...........

10.0 Land Use Census................................................................

1 1.0 Summary and Conclusions.........~.........................

12.0.References.......................................................................

Appendix A Corrections to 1992 ARBOR.........................................

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TABLES 5

12 13

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................. 15:

. 19

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.32 33

... 34 37

......... 43

...................................44

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.2.1 Sample, Collection Locations 2.2'Sample Collection Schedule 4.1'ypical Aliquot Sizes 4.2 Typical Times Between Sample Collection And Counting 4.3. Typical Counting Ef5ciencies and Radiochemical Yields......

4.4'Typical Sample Counting Times.

6.1 ODCMLLDsa priori.

6.2 ODCMReporting Levels.

6.3 Typical LLDValues..

7.1 U;S.,EPA Intercomparison Results..

8.1 Gross Beta In Air,1st.- 2nd Quarter.

8.2 Gross Beta In Air3rd - 4th Quarter.

8.3 Gamma In AirFilter Composites.

8.4 Radioiodine In Air 1st - 2nd Quarter......................

8.5 Radioiodine In Air3rd - 4th Quarter.

8.6 Vegetation..............

8.7 DrinkingWater 8.8 Groundwater 8.9'Surface Water....

.8.10 Sludge 8.11 Sewage Plant

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8.12 Milk..

9.1 TI.D Site Locations 9;2'.1993 Environmental TLDResults 10.1 1993 Land Use'Census.... ~..

11.1 Environmental Radiological MonitoringProgram Annual Summary 111

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FIGURES

'2.1 PVNGS REMP Sample'Sites - Map (0-10 Miles)................................6

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2.2 PVNGS REMP Sample, Sites -,Map (0-35 Miles)..........................7 2.3.PVNGS REMP Sample Sites - Map (35-75 Miles)............8 8.1 Gross Beta In A'ir 1985 - 1993

.....................~...........................................45 8.2'Gross Beta In AirComparison -Pre-Operational vs.1993..................................

46, 8.3'Gross Beta InDrinkingWater

...................................47 8.4 Comparison ofPre-Operational Soil Activity(Cs-137)-With Onsite Sediment........;48 9.1 PVNGS Network TLDExposure Rates.....................................;

.....53, 9.2 Environmental TLD Comparison -Pre-operational.vs

1993,

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Abstract The radiological environmental monitoring program is,an;ongoing study;conducted, by., Arizona:Public'Service Company (APS). APS contracted Controls forEnvironmental:Pollution, Inc.'(CEP) to perform sample analysis.

During 1993, samples. were,collected:by, the Palo -Verde Nuclear.,Generating, Station personnel..The, following categories ofsamples were collected:

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Broad leaf vegetation

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Fresh milk

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Groundwater

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Drinkingwater

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Surface water

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Airborne particulate and radioiodine

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Sludge and'sediment Thermoluminescent dosimeters were used to measure environmental gamma radiation.

~ ', Sample analysis was,performed by,. CEP.personnel," Thermoluminescent dosimeters were placed and processed by the Palo-Verde Nuclear Generating. Station. PVNGS staK collects and ships samples and reviews analysis results for.trends and anomalies for inclusion in this rcport.

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OPERATIONALRADIOLOGICALENVIRONMENTALMONITORINGPROGRAM 1.0 Introduction This report presents the results ofthe operational environmental radiological. monitoring program conducted by Arizona Public. Service Co. (APS). In accordance..with federal, requirements to provide a complete environmental monitoring program for.nuclear, reactors and their, concern for,maintaining the quality ofthe "local environment, the Radiological Environmental Monitoring.Program (REMP) was established for the

. Palo Verde Nuclear Generating Station,(PVNGS);by, the'Arizona.Nuclear Power Project (ANPP),in 1979.

The program complies withthe requirements ofthe U;S. Nuclear Regulatory Commission (USNRC) in their Reactor Assessment Branch, Technical Position,.Revision 1, November 1979. This,.reporticontains the measurements and findings for 1993..All,bracketed, numbers refer.to references contained in,section.12..

The objectives of the radiological-environmental monitoring,program. are as. follows:,1) to determine baseline radiation levels in the environs prior to plant operation and to compare the findings with measurements obtained during reactor operations; 2) to monitor potential critical pathways of radio-efiluent to man; and 3) to determine radiological impacts on the environment caused by the operation ofPVNGS.

Results Rom the REMP help to evaluate sources of elevated levels of radiation, in the environment, e.g.,

atmospheric nuclear detonations or abnormal plant releases.

Results ofthe PVNGS prewperational environmental monitoring program are presented in reference [1].,

The'initial'criticalityofUnit.One:occurred May 25, 1985. Initial,criticalityfor Units. Two and Three were April 18, 1986, and October 25, 1987, respectively.

PVNGS operational findings are presented in reference

[2]. This report contains the measurements and findings for 1993.

2.0 Descri tion ofthe Monitorin Pro ram The pre-operational radiological environmental monitoring program,,which began in 1979, was performed by PVNGS and outside organizations.

These organizations continued the program into the operational phase ofPVNGS.

2.1 1993 PVNGS Radiolo cal Monitorin Pro am The assessment program consists of'routine measurements of background gamma radiation and of radionuclide concentrations in media such as air, groundwater, drinking water, sudace water, fresh milk,vegetation, sludge, and sediment.

Samples were collected by PVNGS personnel'at the monitoring sites shown inFigures 2.1, 2.2, and 2.3.

The specific sample types, sampling locations, and sampling frequencies as set forth in Palo Verde Nuclear Generating Station Offsite Dose Calculation Manual (ODCM) [4] are presented in Tables 2.1 and 2.2.

Sample analysis was performed at the CEP facilityin Santa Fe, New Mexico.

Background gamma radiation measurements are, performed using thermoluminescent,dosimetry at fifly locations by PVNGS.

PVNGS commenced on-site analyses of duplicate REMP samples during the fourth quarter of 1993 to compare with CEFs results, in order to demonstrate consistent and reliable results. In addition, PVNGS has been participating in the USEPA Interlaboratory Comparison Program to further demonstrate it' ability to perform environmental sample analyses.'On-site analyses willcommence on January 1, 1994 for those sample types which PVNGS has demonstrated quality results.

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2.2Radiolo 'calMonitorin Pro am Chan cs for1993 2.? 1 Effective April 1,1993 the drinking water sample at the Scott Residence(site ¹49) was replaced withthe Chowanec residence,due to it's proximityto PVNGS. In addition, this willprovide another sample site

,that is monitored by the Arizona Radiation Regulatory. Agency(ARRA).

2.2.2 Effective January 1,1993, the Tolleson Produce Company became the'control location for.vegetation, replacing J.A. Woods ofScottsdale 2.2.3 Airsample site ¹6 was moved the week ofDecember 14, 1993. from SSE31 to SSEl1. Table 2.1 ofthe 1994 AREORwillbe changed to reflect the new location.

2.3 Changes to Descriptions ofSample Locations Areview, ofexisting. sample locations was performed. The followingdescriptions.were'corrected to more accurately identifylocations:

~ Site ¹35 - Changed location fromNNW9 to NNWS.

~ Site ¹46 - Changed location fromNNW9 to NW9.

~ Site ¹53 - Changed location fromE20 to E19.

~ Site ¹52,-, Changed from Site ¹55; due to ODCMchange. which added garden at this location.

~ Site ¹56 - Changed location fromE75 to E60.

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TABLE2.1 SAMPLE COLLECTIONLOCATIONS [4]

Sample Site ¹ 1

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7A 14A 25 17A'1

'29 35

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57 58 59 60 62>>

63 yp'ir Air

Air, Air Air Air'ir Air Air Air Air Water Vegetation Water

.Water Milk

Milk, Water, Vegetation Milk Milk Milk Water Water Surface Water Surface Water Vegetation Surface Water Location(a)

E30 E16 SSE31 SES NNE2 NE2

,E4 S3 Wl NNWS N3 NW9 ENE3 S5

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ENE12, Ell SW3'19 E17 E60 on-site on-site on-site on-site E35 on-site Location Description APS Goodyear CM5ce APS Buckeye OQice, 615 N. 4th St, Buckeye

.APS,Gila Bend Substation,:Service Road West of,Town Arlington School, 16351 S. ArlingtonSchool Rd..

Buckeye-Salome Road dh 371st Ave.,

North East Site Boundary

.351st Ave., l.mile South ofBuckeye4alome Road, South Site Boundary West Site Boundary Tonopah, Fire Station, 40901 W. Osborn RxL Wintersburg, End ofTransmission Road McArthux's Farm, Tonopah Adams's Residence, 355th Ave. ABuckeye-Salome Rd.

Sheppard Farms, 13202 S. 383rd Avenue Chowanec Residence, 371 Ave., South ofSalome Road Crosswinds Daixy, 295th Ave and Van Buren St.

Butler Dairy, Palo, Verde Road'8l Southern Gavette Residence, 39326 W. EiliotRoad Kerr Daixy, Dean 4 Buckeye Roads Dichnan Dairy, Broadway and Apache Roads Pew Daixy, McQuecn 4 Ryan Roads Well 27ddc Well 34abb A

PVNGS Evaporation Pond ¹1 PVNGS Reservoir Tolleson Produce Co., 91st Ave..and Van Buren St. Tolleson, AZ PVNGS Evaporation'Pond ¹2' control site.

(a) Distances and direction are from center-line ofUnit 2 containment.,

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TABLE2.2 SAMPLE COLLECTIONSCHEDULE [4]

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¹7 Collection Site APS Good ear OEce APS Buck e Otlice APS Gila Bend Substation Arlin on School Particulates W

W Airborne Radioiodine Milk Ve etation W

Groundwater Drinkin Water Surface Water

¹14A Buck e-Salome Road W

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¹17

¹21

¹29

¹35

¹40

¹48

¹50

¹51

¹52

¹53

¹54

¹56

¹57

¹58

¹59

¹60

¹62

¹63 NE Site Boun 351st. Ave South Site Boun W. Site Boun Tono Fire Station Trailer Park at Wintersbur McArthur's Residence Adam's Residence Sh ard Farm Chowanec Residence Crosswinds Dai Butler Dai Gavette Residence Kerr Dai Dickman Dai Pew Da Well 27ddc Well 34abb PVNGS Eva ration Pond ¹1 PVNGS Reservoir Tolleson Produce Co PVNGS Eva ration Pond ¹2 W

W W

W W= Weekly Q = Quarterly AA= As Available M= Monthly

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3.0 Sam le Collection Pro ram 3.1 Water Water samples were collected by PVNGS personnel using PVNGS procedures.

3.1.1'eekly samples were collected from the Reservoir, the Evaporation Pond ¹1, and Evaporation Pond ¹2.

Weekly, samples were collected in one-gallon cubitainers and 500-ml glass bottles at all three'sites and were composited monthly:.Cubitainer. samples. were acidified withHCIin the laboratory prior,to analysis.

3.1 2 Monthly composited.samples were collected. at four residence wells. Monthly composited:samples were collected;in 500 ml'glass."bottles and in one gallon cubitainers and were'acidified with"HCI in the laboratory prior to analysis.

3;1.3 Grab samples were obtained Rom on-site wells 34abb and 27ddc.

'Samples were collected in 1-gallon cubitainers and 500-ml glass bottles. Cubitainer samples were acidified with HC1 in the laboratory prior to analysis.

3.2 ~Ve etatiea Vegetation samples were collected by PVNGS personnel using PVNGS procedures.

3.2.1 Vegetation samples were scheduled to be collected monthly, as available.

3.3 AirFilters and Canisters Airsamples were collected by PVNGS personnel using PVNGS procedures.

3.3.1 Airparticulate filters and charcoal canisters were exchanged at llsites on a weekly basis.

3.4 Milk Milksamples were collected by PVNGS personnel using PVNGS procedures.

3.4.1 Monthly milk samples, were, obtained &om five;dairies during the year.

Samples were collected in 1 gallon cubitainers. Milk,samples are currently being stored and shipped in ice chests to prevent curdling.

e3.5 Slud e and Sediment Sludge and sediment samples were collected by PVNGS personnel using PVNGS procedures.

3.5.1 Sludge samples were obtained, from several on-site locations.

Samples were collected using 1000 ml plastic bottles at the following locations:

Water Reclamation Facility (WRP) centrifuge, Sewage Treatment Plant (STP) tanker, Sedimentation Basin ¹2, and Cooling Towers.

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4.0 Anal ical Procedures 4.1 CEP Anal ical Procedures

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

4.1.1 AirParticulate 4.1.1.1 Gross Beta Air,particulates'are analyzed for Gross Beta. In analyzing the material, the glass;fiber filter;sample is placed in'a 50 mm stainless'steel planchet and,counted for Gross Beta:,activity, utilizing'a low.-background. internal gas flow, proportional: counter.,CEP,:uses.the;Berthold, 10&hannel. Low Level,Planchet.Counting System discussed'n section'5.1.

The instrument's eQiciency. is checked weekly using an NIST.traceable Cs-137 standard.

4.1.1.2 Gamma S ectrosco The air filters are sealed in a standard geometry container and.counted on an intrinsic or Ge(Li) detector.

The detector, coupled to a computer based analyzer produces a spectnun. When the spectrum is analyzed by computer, specific nuclides, ifpresent, are identified and quantified.

CEP uses the Nuclear Data Model 9900 Gamma. Spectrometer, described in section 5.2.

The. detectors, are checked using,NIST traceable standard geometry sources.

4.1.2 Airborne Radioiodine 4.1.2.1 Refer to section 4.1.1.2.

0 4.1.3 Milk 4.1.3.1 Iodine-131 Two (2) liters ofmilk containing standardized Iodine carrier are stirred with anion exchange resin for one hour.

The Iodine is stripped from the resin with 2N.sodium perchlorate (NaC104) and precipitated with silver nitrate (AgNO3). The precipitate is, filtered on a tared glass fiber filter. The dried. precipitate is weighed:for percent recovery and counted for Iodine-131 in a thin window, gas Qow, proportional counter.

Samples are analyzed withinfortnight hours ofreceipt to keep the I-131 decay to a minimum.

4.1.3.2 Gamma'S ectrosco Four (4) liters of sample are placed in a 4 liter plastic Marinelli beaker and counted on a multichannel analyzer equipped with an intrinsic Ge detector (sce section 5.1). The resulting spectrum. is analyzed by computer, and specific nuclides, ifpresent, are identified and quantified.

4.1.4 Garden Ve etatlon 4.1.4.1 Gamma S ectrosco The wet sample is placed in a medium Marinelli beaker and counted, on a multichannel. analyzer with an intrinsic Ge detector (sce Section 5.1). The resulting spectrum is analyzed by computer and specific nuclides, ifpresent, are identified and quantified.

4.15~SIud e

4.1$.1 Gamma S ectrosco Refer to Garden Vegetation Section 4.1.4.1 10

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4.1.6 Water 4.1.6.1 Gamma S ectrosco A4.0 liter aliquot ofwater in a 4 literplastic Marinellibeaker is Gamma scanned utilizing a computer4ased multichannel analyzer equipped with an intrinsic Ge detector (sec section 5;1.1). The resulting spectrum is analyzed for nuclides present to yield values fortotal sample activity.

4.1.6.2 Tritium

'Three milliliters of water are mixed with liquid scintillation, cocktail.

The mixture used is twenty-three percent sample in,a clear liquid scintillation cocktail..

This gives,a Tritium counting,eQlciency of approximately thirtypercent. The counting system used'is a Beckman LS-5801 Liquid Scintillation Counter.

4.1.69 Iodine-131'ne liter ofwater, containing standardized Iodine carrier is acidiTied with nitric acid (HNO3), then ectracted

,with'carbon,tetrachloride.(CC14) and'sodium nitrate (NaNO2),to remove the. Iodine.

The Iodine is back extracted 'from the carbon tetrachloride (CCI4) using a 0.2% hydrazine solution that supplies more purification and an aqueous media for precipitation. Iodine is precipitated with silver nitrate (AgNO3) and filtered on a tared glass fiber Qlter as silver iodide (Agi). The dried precipitate is weighed for recovery and counted forIodine-131 in a thin window, gas Qow; proportional counter.

Samples are analyzed withinforty-eight hours ofreceipt to keep Iodine-131 decay to a minimum. The typical lower limitof detection for this method is 1.0 pCi/l.

4.1.6.4 Gross Beta A 250, milliliter,sample:is.placed in a beaker.

Ten milliliters,of,concentrated, nitric acid, is,added;to, the sample, which is then dried down.

The residue is wet ashed'with 30% hydrogen peroxide and 16N nitric acid. Nitricacid (.5N)'is then added to the'beaker and placed'on a stainless steel planchet and evaporated, Qamed, and weighed. The planchet is counted for gross beta in a gas flowproportional counter.

4.2.CEP Sam le Pre aration Methods The followingsample preparation methods are used routinely by CEP:

4.2.1Slud e and Sediment Sam Ie Pre aration

1. The plastic containers. are. opened,and weighed',when they arrive at the CEP,laboratory and after analysis, the contents are transferred into drying pans.

2. The pans are placed into an oven at 110 C and allowed to dry thoroughly.

3. Results are reported in pCi/Kgwet weight.

4.2.2Ve etation Sam IePre aration

1. The plastic bags are opened and the sample weighed immediately to obtain the wet weight.

2. Aknown wet weight ofsample is placed in a 4 literplastic Marinellibeaker for,Gamma Spectroscopy.

3. Results are reported at pCi/kg wet weight.

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TABLE4.1 TYPICALALI UOT SIZES Sample Type AirParticulates Airborne Radioiodine Fresh Mlk Broad leaf Ve etation Groundwater Drinkin Water Surface Water Gross Beta 430m 250 ml 250 ml 250 ml Gamma Spec.

5590m **

430m 4000 ml'000 g

4000 ml 4000 ml 4000 ml 1-131 (radiochem.

se aration 2000 ml 1000 ml 1000.ml H-3

Airsample volume determined for a constant flowrate of43'LPM over a 1-week period.

- Airsample volume determined for a constant Qow rate of43 SLPM over a 13-week period.

12

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TABLE4.2 TYPICALTIMES BETWEEN SAMPLE COLLECTIONAND COUNIING Sam le AirParticulates Airborne Radioiodine Fresh Mlk Ve etation Water Slud e/Sediment Time Between Collection and Countin 10da s

2da

<T<3da s 2da s<T<4da s*

2da s<T<5da s

3da

.<T<9da s

3da s<T<9da s

.Priority is given to I-131 radiochemical'assay, theri:measurement'of other nuclides with:longer half-lives.

13

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TABLE4.3 TYPICALCOUNTINGEFFICIENCIES ANDRADIOCHEMICALYIELDS GAMMASPECTROMETRY Ener e

0.134 0.365 0.537 0.605 0.622 0.662 0.765 0.811 0.835 1.095 1.115 1.173 1.596 Isoto Ce-144 I-131 Ba-140 Cs-134 R Rh-106 Cs-137 Zr Nb-95 Co-58 Mn-54 Fe-59 Zn5 Co-60 La-140 Detector EQicien 0.019 0.010 0.0064 0.0059 0.0057 0.0054 0.0047 0.0045 0.0043 0.0034 0.0033 0.0031 0.0024 A SPECTROMETRY detect OTHER THANGAMM or eQiciencies forvarious instruments Sam le AirParticulates Airborne Radioiodine Fresh Mlk Groundwater Drinkin Water Surface Water Gross Beta 0.40 0.32 0.32 0.20 I-131 chem. recove 0.12 0.30 0.70 0.30 0.90 0.30 0.90 0.30 0.90 H-3 0.35 0.35 0.35 14

I i W 4

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TABLE4.4 TYPICALSAMPLE'COUNTINGTIMES

'ountin times ma be increased to meet LLDr uirements Sample Type AirParticulates Airborne Radioiodine Fresh Ilk Broad leaf Ve etation Groundwater Drinkin Water Surface. Water Siud elSediment Gross Beta 200 min.

200 min.

Gamma Spec.

16 hr 16 hr.

16 hr.

I-131 (radiochem.

aration 100 min.

200 min.

300 min.

H-3 l'

hr.

2hr.

v 2 hr.

I, 15

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5.0 Nuclear Instrumentation 5.1 CEP Ma'or Instrumentation

~

5.1.1 Nuclear Data Com uter Based Gamma S ectrometer The Ganuna Spectrometer consists of a Nuclear Data Model ¹9900 Multichannel Analyzer equipped with

.eight intrinsic detectors having resolutions of 1.87 keV, 1.69 keV, 2.10 keV, 1.90 keV, 1.87 keV, 1.90 keV, 1.79 keV and 1.90'kcV determined by full width half mass with an energy. of 0.5 keV pcr channel; and respective ef6ciencies of 18.2/o, 19.9/o, 22.6/o, 23.7/o, 25.1/o, 30.6/o, 32.2/o, and 34.3% as determined by the manufacturer with~0.

The.Computer;Based Nuclear Data Ganuna'Spectroscopy,System is.used for all'Gatmna counting.

The system;uses".Nuclear~Data':developed'software'(automatic;isotope analysis) to search and identify, as well as quantify the peaks ofinterest.

5.1.2Beckman Li uid Scintillation Countin S stems ABeckman LS-5801 Liquid Scintillation Counters willbe used for all Tritiumdeterminations.

The system background averages approximately 20 cpm with a counting eQiciency of60% using an unquenched sample.

5.1.3 Berthold-10-Channel Low-Level Planchet Countin S stem The Berthold LB770 is capable of:simultaneously counting 10 planchets for Gross Alpha, and Gross Beta activities with proportional gas'Qow detectors.

The system has an average background count rate of less then 1 count per minute for Beta and.less than 0.05 count per minute for Alpha.

The instnuncnt has an Alpha eQiciency of'43% for Plutonium-239 and Beta eQiciencies of 54% for Strontium-Yttrium-90, and 42% for Cesium-137.

5.1.4 Numelec Nu20% Channel Low-LevelPlanchet Countin S stem The Nu20 is capable of counting 8 samples for Gross Alpha and Gross Beta simultaneously with

': proportional gas Qow detectors.

The:system has an average background count:rate of less than 1.count per... -..

minute for Beta and less than'0.10 counts per minute for Alpha. The instrument has an Alpha efnciency (Pu239) of42% and Beta (Sr90) eQiciency of44% and Beta.(Cs-137) ef5ciency of41%.

16

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6.0 Tsoto ic Detection Limits and Re ortin Criteria

~

6.1 Lower Limits ofDetection The lower limits'ofdetection (LLD) and the method for calculation are'specified:in'the PVNGS ODCM. [4].

CEP a prioriLLDs are prescntcd in Table 6.3.

6.2 Data Re ortin Criteria Allresults that are >MDA(aposteriori) are reported as positive activitywith.its associated 2a. error..Ifthe. error associated with a result exceeds that result, the value is reported as.<LLD.

Ifthe MDAexanis the ODCMrequired a priori LLD,the value is reported as ~A(ie., <30). Ifthe result is less than the a priori LLDand MDA,the value is reported'as cLLD.

OccasionaUy the PVNGS ODCM [4]apriori LLDs may not be achieved as a result of:

~

Background fluctuations' Unavoidably small sample sizes

~

The presence ofinterfering nuclides

~

Self absorption corrections

~

Decay corrections for short half-lived radionuclides

~

'Other.uncontrollable circumstances In these instances, the contributing factors.willbe noted in the table where the data is presented.

6.3 LLDand Re ortin Criteria Overview'aking a reasonable estimate of the'limits of detection for. a counting procedure or a radiochemical method is usually. complicated by the presence.of. significant background. It must. be considered that. the background or blank is not a fixed value but that a series ofreplicatcs would be normallydistributed. The desired net activity is thus the difference bctwecn the gross and backgiound'activity distributions. The interpretation of,this difference becomes a problem ifthe two distributions intersect as indicated in the diagram.

BACKGROUND

.GROSS Ifa suf5cient number of replicate analyses are run, it'is to be exliected that the results. would fall,in a normal Gaussian Distribution.

Standard statistics allow.an estimate ofthe probability of any particular deviation from the meanvalue. Itis common practice to report the mean*one or two standard deviations as the fmal result. In routine analysis such replication is not carried out, and it is not possible to report a Gaussian standard deviation

-*one or two Poisson standard deviations. The reported values are then considered to give some indication ofthe range in which the true value might be expected'to occur.

17

p~.

4t Cl 0

The simplest possible case to consider would be one where the background is negligible and the sample activity is zero. Itis sometimes not realized that ifa series ofcounts is taken on such a system, halfofthe net values should be

- less than, zero. Negative counts'are not possible, ofcourse.. But when, there is an appreciable background,,the entire scale.is:raised.

The resulting;situation: half of the sample. counts on a zero activity sample would be less than

~background... The negative net counts occur.'frequently in.low-level'easurements,,

causing considerable. concern.

Actually, such results are to be expected.

A',LLD's the smallest".amount.of;sample activity that willyield a"net.count:for'which there'is-confidenc.at a

predetermined level that activity.is:present.,LLDs are, calculated. values for.individual,nuclides based on a,number of

'ifferent factors including sample size,.counting eKciency,.and:background count, rate of,the,.instrument,the background and sample counting time, the decay time, and the chemical recovery ofthe analytical procedures.

LLDs are'normally calculated'using average'values'from.analyses;performed over a",long period of time. A minimum detectable activityvalue (MDA).is:the smallest amount. ofactivitythat can'be.detected:in,an:actmd.sample..and,uses the values obtained'from the instrument and outcome ofthe'analytical process. Therefore the MDAvalues may,differ

=

. from,the calculated LLD.values>ifthe. sample size'and chemical recovery;:decay values or.the'instrument eQiciency, background, or. count time differed'from those used in the LLDcalculation.

The factors governing the calculation ofthe'LLD and MDAvalues are discussed below:

1. Sample Size

2. Counting Efficiency The fundamental quantity in the measuremcnt of a radioactive substance is the number of disintegrations per unit time.

As with most physical'easurements in analytical chemistry, it is seldom possible to make an absolute

~ measurement ofthe disintegration rate, but rather it is, necessary to compare the sample with one or,more;standards.

The standards determine the counter efficiency that may then be used to convert sample counts per minute (cpm) to disintegrations per minute (dpm).

3. Background Count Rate

~,Any. counter willshow a certain counting rate without a sample;in position.:.,This background counting rate comes from several'.sources:

1) natural environmental radiation &om the surroundings, 2) cosmic radiation, and 3) the natural radioactivity in the counter material itself. The background, counting rate will depend on the amounts of these types ofradiation and the sensitivity ofthe counter to the radiation.

4. Background and Sample Counting Time The amount of time devoted to the counting of the background depends on the level ofactivity being measured.

In general, with low level samples, this time should bc about equal to that devoted to counting a sample (Table 4.'4).

5. Time Interval Between Sample Collection and'Counting Decay measurements are useful in identifying certain short-lived isotopes.

The disintegration constant is one of the basic characteristics'of a specific radionuclide and is readily determined,'f the half life is sufficiently short In order to ensure. the required LLDs are'achieved, conservative values are used in decay correction to allow for transit time and sample processing.

6. Chemical Recovery ofthe Analytical Procedures Most radiochemical analyses are carried out in such a way that losses occur during the separations.

These losses occur'due to'the large number ofcontaminants that may;be present and'interfere during chemical separations.

Thus, it is necessary to include a technique for estimating these losses in the development ofthe analytical procedure.

18

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TABLE6.1 ODCMLOWERLIMITSOF DETECTION- 'a riori'nal sis Gross Beta H-3 Mn-54 Fe-59 Co-58 -60 Zn-65 Zr-95 Nb-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Water Ci/l 2000 A

15 30 15 30 30 15 15 18 60 15 Airborne Particulate or Gas Ci/m3 0.01 0.07 0.05 0.06 Fresh Milk Ci/l 15 18 60 15 Food Products Ci/k,wet 60 60 80 NOTE:This list does not mean that only. these nuclides are,to be. detected and reported.

Other peaks that are measurable and identifiable, together with the above nuclides,, shall also be identified and reported.

"Ifno drinking water pathway exists, a.value of3000 pCi/1 may.be. used.

- Ifno drinking water pathway exists, a value of 15 pCi/l may be used.

19

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TABLE6.2 ODCMREPORTING LEVELS Anal sis H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 I-131 Cs-134 Cs-137 Ba-La-140 Water Ci/l 20000

1 000 400 1 000 300 300 400 2 **

30 50 200 Airborne Particulate

,. or Gas Ci/m3 0.9 10 20 Fresh Mlk Ci/I 60 70 300'ood Products Ci/k, wet 100 1 000 2 000 For drinking water samples.

This is a 40 CFR 141 value. Ifno.drinking water pathway exists, a value of30,000 pCi/l may be used.

" Ifno drinking water pathway exists, a reporting level of20 pCi/l may be used.

.20

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4%. 'P

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TABLE6B TYPICALLLDVALUESfor CEP 'a riori'nal sis Gross Beta H-3 Mn-54 Fe-59 Co-58 -60 Zn-65 Zr-95 Nb-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Water Ci/1 1000 12 12 14 1

10>>

45 14 Airborne Particulate or Gas Ci/m3 0.01 0.02 0.001 0.001 Fresh Milk Ci/l 45 14 Food Products Ci/k wet 28 15 19

1'Ci/l is the value for radiochemical seperation, 10 pCi/I is.the value for gamma spectroscopy.

21

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7.0 EPA Interlaborato Com arison Pro ram 7.1 CEP uali Control Pro m

CEP employs a multi-faceted Quality Control Program designed to maintain high.performance ofits,'laboratory.

The overall objectives ofthe program are to:

1. Verifythat work procedures are adequate to meet speciQcations ofAPS.

2.'Coordinate the in-house quality control, program, independent of.external:programs,to assure that CEP is operating at maximum ef6ciency.

Objectives are mct by a variety of procedures that:oversee areas of sample receipt'and,handling,:analysis, and data'review. These proaxhres include standard operating procedures, known and unknown spike analysis, bhnk analysis,'eagent, carriers and nuclide.standardization;as:,well, as participation, in the U.S. Environmental

'Protection Agency's Interlaboratory. Cromcheck Program.

During. 1993, 'CEP"tested the~ following USEPA distributed samples for analysis.-under thelaboratory intercomparison study:

~

Alpha, Beta, Gamma in AirPilter

~

Iodine inMilk

~

Beta in Water

~

Gamma in Water

~

Tritium'inWater

'erformance Study In addition, CEP analyzed duplicate, blank and<<intralaboratory spike. samples at a &equency of'10% for the analytical'procedures performed.

This means that for every ten.samples analyzed by CEP,.the. technician also submits one duplicate sample,,one blank and one intralaboratory spike sample., The acceptance ofthe laboratory analysis is dependent upon the outcome ofthose quality assurance samples.

CEP's Quality Assurance. Program is reviewed and revised,(when necessary) on a regularly scheduled basis.

This review. assures that the program meets'all current regulatory guidelines:as well as maintaining the highest standards ofquality assurance practice.

7.2 Intercom arison Resul Results for the intercomparison-program between CEP and the, USEPA are. presented in Table 7.1. APS commenced participation'in the'Interlaboratory Program during'1993 and the"results, for, the,intercomparison program between APS and the USEPA are also presented in Table 7.1; 22

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DATE TABLE7.1 SAMPLE TYPE EPA KNOWN VALUE U.S. EPA INTERCOMPARISONRIMULTS all results in Ci/l unless otherwise annota NORMALIZED DEVIATION 1 1-93 2-93 4-93 6-93 6-93 7-93 8-93 9-93 10-93 10-93 10-93 11-93 11-93 Gross beta in water

'-131 in water Performance Eval.

~iad water gross beta Co%0 Cs-134 Cs-137 Tritiumin water Gamma in Water Co40 Zn<5 Ru-106 Cs-134 Cs-137 Ba-133 Gross beta in water

~ir Filter gross beta Sr-90 Cs-137

~il I-131

, Cs-137 Gross beta in water I-131 in water erformance'al.

lind wate gross beta CCATS Cs-134 Cs-137 Tritiumin water Gamma in Wate Co%0 Zn-65 Ru-106 Cs-134 Cs-137 Ba-133 44.0 100.0 177.0 39.0 27.0 32.0 9844.0 15.0 103.0 119.0'.0 5.0 99.0 43.0 47.0 pCi/filter 19.0 pCi/filter 9.0 Ci/filter 120.0 49.0 15.0 117.0 58.0 10.0 12.0

'10.0 7398.0 30.0 150;0 201.0 59.0 40.0 79.0 35.3 152.0

'41.3

, 25.0 29.0 9458.7, 15.7 107.3 108.3'.0 6.0'3.0 35.'3 53.0 pCi/filter 18.3 pCi/filter 12.0 Ci/filter 128.7 54.0 12.0 110.0 48.0 11.0 11.0

- 9.3 7046.7 30.0

, 156.7 166.0.

52.0

'1.3 75.0

-3.0

-2.7

-1.6 0.8 A.7

-1;0 A.7 0.2 0.8

-1.5 0.3 0.3

-1.0

-1.9 2.1 A.2 1.0 1.3 1.7

-1.0

-1.7 0.3

%.3 W.2 0.0 0.8

-3.0 9

-2.4 0.5 W.9 QCQ'ES:

(1)

Norinalired deviation (N) acceptance criteria is -3M&

~

0 CEP's reported value is 166.0 pCi/1 which is right at the lower limitof 166.3 pCi/L The grand average reported by all responding labs was 175 pCi/I, well below the known value of 201 pCi/L It appears the EPA standard is biased low (for Ru-106).by 2-3 sigma based on the statistical;results of. respondents.

CEP performed an investigation as to the reasons for the low result and considers, the reported value to be valid. No actions are to be taken.

23

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TABLE7.1 DATE 8-93 SAMPLE TYPE ttirFilter EPA KNOWN VALUE

'PVNGS LAB RESULT U.S. EPA INTERCOMPARISON1UHULTS all results in Ci/I unless otherwise annotat NORMALIZED DEVIATION 1 10-93 10-93 10-93 11-93 11-93 gross beta Cs-137 Gross beta in water I-131'n water Performance Eval.

lind water gross beta Co-60 Cs-134 Cs-137 Tritiumin water Gamma 'n Water Co-60 Zn<5 Ru-106 Cs-134 Cs-137

'a-133

'7.0 9.0 15.0 117.0 58.0 10.0 12.0 10.0 7398.0 30.0 150.0 201.0 59.0 40.0 79.0 62.3 9.0 19.7 128.3 48.7 11.3 11.0 11.0 7266.7 29.0 161.3 161.3 51.0 42.0 77.7 5.3 9 0.0 1.6 1.6

-1.6 0.5

-0.3 0.3 A.3 1.3

-3.4 0

-2.8 0.7 A.3 (1)

Normalized deviation (N) acceptance criteria is -35¹3 9

Outs'ts.

erformed ew e cienc ide control hxm P

n ffi y calibration using geometxy more closely resembling the crosscheck air filter,supplied by the EPA program. EPA crosscheck air filter,supplied is a Styxofoam disc with source material deposited on the surface of the disc. This results in no surface attenuation due to self absorption

.as in a glass fiber filter. A source prepared using'a glass fiber,filterwas originally purchased with NIST traceable certification for efficiency determination since this most closely represents the REMP air samples.

Using this new non-abso*ing counting efficiency on the raw CPM data for the blind provides agreement.

6 Outside'control limits. An evaluation was performed on the parxuxieters in the nuclide analysis library used in the multi-channel analyzer and all parameters are in agreement with the Radioactive Decay Tables (Kocher) 1981.

Also performed was a calibration verification on the geometry used for the analysis. The verification standard

.was a more recently prepared (Oct. 1993) mixed gamma source supplied withNIST traceable certification, than was used for the original calibration. Allverification values were within 3% of the certificate between 88 to 1836 keV. Evaluation of.further corrective action is ongoing, which includes use ofdifferent geometry, calibrations to reduce the effects ofpossible cascade summing. However, it is not understood.why,this did not affect other nuclides which decay by multiple gamma emissions such as Cs-134 and Ba-133. Evaluation of the November 1993 and the June 1993 Gamma in Water EPA Intexcomparison Study indicates the Grand Average for all Non~tliers is consistently 12-13% 'lower than the actual known value supplied by the EPA, as well as only 34-38% ofparticipants in agreement.

24

~.2

~

S.O Data Inter retations and Conclusions Associated with the analytical process are potential random and systematic errors.

Systematic errors can be caused by instrument malfunctions, incomplete precipitation,. and back scattering and.selfWsorption.

Random errors. are beyond the control ofthe analyst and are caused by the random nature ofradioactive decay.

Etrorts are made to etuninate both systematic and random errors in the data reported.

Systematic errors are eliminated by performing reviews throughout the analysis.

For example, instrument calibrations are checked with radioactive sources daily and atter any instruxnent maintenance or adjustment, and recovery and selfWsorption factors'based.on individual sample analyses are incorporated into the calculation:equations

.where xuxx<mxy.

Random errors are reduced by comparing all data to historical data for the same, site and performing.cross comparisons between analytical results when available (e.g., comparing a Gross Beta result to a: Strontium-90 result);, In addition;,when data docs not appear to match historical results, analyses would be rerun on a separate aliquot of the sample to verify the presence of the activity. In addition; CEP's'Quality Assurance Plan xequires the analysis of quality control samples with each set of samples.

The results of these samples willindicate whether an error (random or systematic) occurred that could be associated with the entire set. The acceptance ofthc data Rom the set is dependent upon the results ofthese quality assurance samples and is part ofthe data review process for all analytical results.

The "plus or,minus value" reported with each analytical result represents the error associated with the.result and gives the

'95% confidence'(2 xx) interval around the data Results and interpretation ofthe data for all.ofthe samples analyzed during 1993 are presented in the following sections.

Assessment of prcwpcrational and operational, data revealed no significant changes.to environmental radiation levels.

There was no observed impact on the environment due to PVNGS operations in 1993.

8.1 AirParticulates Weekly gross beta results, in quarterly format, are presented in Tables 8.1 and 8.2 and depicted in graphs in Figures 8.1 and 8.2.

Average quarterly activities are calculated using all weekly activities except those marked invalid. Also presented in the tables are the weekly averages of all the sites as well as the pexcent standard deviation of the data.

The findings are consistent withp~perational baseline and previous operational results.

Figure 8.2 shows the results of the gross beta in air from the p~perational phase compaxed to the 1993 gross beta in air results. As can be seen, the sampling sites trend consistently with the control site. Table 8.3 displays the results of gamma spectroscopy on the monthly composite.

The results are summarized in Table 11.1'. No Cs-'134'r Cs-137 was observed. The control'location for Airborne Particulates and radioiodine,, Site ¹6, was out of service for a ten week period due to a power outage. The power outage was as a result of severe flooding which disabled the electrical substation that powers the sampler at site ¹6. Site ¹29 was out of service for a four week period due to storm damage.

8.2 Airborne Radioiodine Tables 8.4 through 8.5 present the quaxterly radioiodine results.

No radioiodine was detected in any of the samples.

8D V~te etette>>

Table 8.6 presents gamma isotopic data for the vegetation samples.

No activity was observed in any of the samples. The vendor laboratory failed to achieve the required I-131 LLD on several samples due to excessive delay prior to counting and also failed to meet the required Cs-134,Cs-137 LLD's on one sample, due to insuQicient volume. These problems, were identified and corrected by the vendor.

25

J I

a 0

8.4 Drinkin Water Samples were analyzed for Gross Beta, H-3, and for gammamnitting mxlides.

Results of these analyses are summarized in Table 8.7. Gross Beta activity ranged Rom 2.3~ pCi/1 to a high af 18.3M.S pCi/I (Chowanec Residence June 93 Composite). Tritium'.was detected in two samples at levels well below the ODCM specified LLDof2000 pCi/I. The samples were the. second quarterSite ¹48(Sheppard Residence) 496%480 pCi/l and the fourth quarter Site ¹46(McArthurResidence) 500&$2 pCi/1.

8.5 Groundwater Groundwater samples were analyzed for Tritium, and for gamma~tting nuclides.

Results obtained Rom the analysis ofthe samples are presented inTable 8.8.

No gamma~tting nuclides were observed above the LLDvalues.

H-3 was detected in one, groundwater sample. The activitywas 585%487.pCi/L'his is below the vendor lab's typical MDAof SOO pCi/l and.well below the ODCM speciQed LLD.The third and fourth quarter samples were not available att site ¹57, (well,27ddc) due to mechanical problems on the pump.

8.6 Surface Water Surface water samples &om the Reservoir and Evaporation ponds were analyzed for H-3 and gamma~tting nuclides.

Results are presented inTable 8.9. I-131 was detected inEvaIeration Pond ¹ 1, Evaporation Pond ¹ 2 and thc.Reservoir periodically over the year in the monthly composite@. The activity ranged from 4K to I&

8pCi/l. The I-131 is introduced into the site's circulating water systems via radiopharmaceutical discharges into the Phoenix sewage system. Refer to Section 11 ofthe 198S~R for a detailed explanation. Influent samples collected by the WRF were analyzed for gammawmitting nuclides and H-3. The results, presented in Table 8.9, demonstrate that I-131 was observed routinely. The highest concentration was 2S pCi/1 (September Composite).

The results arc consistent with assays Rom the previous years.

Table 8.9 presents gamma spectroscopy and tritium'easurements. of samples~collected'om Sedimentation Basin ¹2 (J-Hook Pond). I-131 was detected in the May 17, 1993 sample at 5.0&pCi/L This was most likelythe result of run-oK Rom circulating water overQow Rom the cooling towers, which Qows into the site drainage system which ultimately collects in the sedimentation basin. Tritiumwas also detected in 12 of23 grab samples ranging from '54~37 to 3595%417 pCi/1. These concentrations are consistent with historical data and no increasing trends were evident.

8.7 Milk Fresh Milksamples were analyzed by, gamma spectroscopy for Cs-134, Cs-137, Ba-140, and La-140. Samples were also analyzed radiochemically for I-131. Results can be found in Table 8.12. There were no positives detected via gamma spectroscopy. No samples contained I-131 in excess of the 1pCi/1 LLD. The highest I-131

" was detected in.the, March 8,,'1993,sample from Pew dairy. (site,¹56). Avalue of 0.'73&.43 pCi/l was reported.

This is thc control site which is located approximately 60 miles East of the Site. Therefore, it is reasonable to conclude that the I-131 reported was not as a result ofemuent releases fromPVNGS.

26

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~O d"

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8.8 Slud e and Sediment Sludge samples were obtained. from several on-site locations and analyzed by gamma spectroscopy.

Results for WRF~te centrifuge sludge and Sedimentation Basin ¹2, sludge can be found in Table 8.10. The I-131 in the WRF waste centrifuge sludge is consistent with historical, values and as previously discussed, it is due to radio-pharmaceuticals in the WRF infiuent. Cs-137 was.detected in the Sedimentation basin ¹2 sediment and it is consistent withprewperational levels in soil.

'Sludge'was removed from cooling towers at Units 1 and,2. during 1993. The sludge.was'analyzed,by gamma spectroscopy to verify the limits imposed in Ground water Permit.¹G77%7 were not exceeded. prior to disposal in the onsite landfill.

'Ihe Unit 1 samples from tower 3 identified Co-60: activity in the range of 290.to 2.9.E4,pCi/kg,and Cs-137 ranging from 36 to 73 pCi/kg.. This sludge was.removed and is being stored onsite awaiting disposition. No

.sludge was,removed. from.Tower 2 at.Unit:1. Allother. cooling,tower:sludge.samples.showed;results;below the limits established for disposal in the onsite landfilL A total of approximately 160 cubic yards of sludge was removed from the cooling towers and disposed ofin the landfill.

The table below summarizes cooling tower sludge sample results and associated volumes disposed of in the onsite landfill; Sample Date 3-19-93 4-2-93 4-29-93 10-1-93 Unit No.

Tower'o.

Volume 40 40 40 ActivityRange (pCi/kg)

Mn-54 Co<0 I-131 Cs-137

<MDA

<MDA-39

<MDA 22-43

<MDA

<MDAA2

<MDA

<MDA-42

<MDA

<MDA-35

<MDA-9.7 280-580

<MDA-23 3842 8.10~Settt ePlsnt Sewage Plant samples were collected on a batch, sample basis as each tanker truck was filled with Digester liquids and sludge.

I-131 was identified in the March 27, 1993 sample at a level consistent with radiopharmaceutical discharges. Although the actual individual(s) could not be identified, the I-131 was almost certainly the result ofa medical uptake ofI-131. The absence ofany other principle gmnma emitter supports this conclusion; The results of the sewage plant samples are presented in Table 8.11. Sampling of the Sewage Treatment Plant was discontinued in April 1993, after the Water Reclamation Facility commenced pumping the sludge back to the treatment plant for reuse.

8.11 Summa ofResults Sample data is presented in graphic form in Figures 8.1-8.4. When practical comparisons to pr~perational data are displayed. A sunnnaxy ofthe sample results is presented in Table 11.1.

27

~

TABLE8.1 PARTICULATEGROSS BETAINAIR1ST - 2ND QUARTER PARTICULATEGROSS BETAINAIR(

Vm3 ODChf. sam les denoted b SI'ART STOP Site Site Site Site Site Hrst rter Site Site Site Site Site Ste WcckN DATE DATE 6'4A'5'7A 21'9 hfcan

%SD I

29-Doc-92 5-Jan-93 2

S-Jan-93 12-Jan-93 0.021 0.012 0.019 0.010 0.021 0.011 0.022 0.012 0.017 0.010 0.021 0.018 0.015 0.020 0.010 0.019 0.011 0.018 0.011 0.022 0.012 0.020 8.282 0.011 12.529 3

12-Jan-93 19-Jan-93 4

19-Jan-93 26-Jan-93 5

26-Jan-93 2-Fcb.93 0.012 0.016 0.032 0.009 0.019 0.038 0.010 0.016 0.040 0.010 0.018 0.038 0.009 0.013 0.035 0.014 0.036 0.011 0.018 0.040 0.009 0.015 0.033 0.011 0.015 0.036 0.010 0.014 0.029 0.010 0.015 0.030 0.010 0.016 0.035 9341 11.532 10.271 6

2-Fcb-93 9-Fcb-93 7

9-Fcb.93 16-Fcb.93 8

16-Fcb-93 23.Feb-93 9

23-Fcb-93 2-Mar-93 10 2-Mar-93 9-Mar-93 11 9-Mar-93 16-Mar-93 12 16-Mar-93 23-Mar 93 13 23-Mar-93 30-Mar 93 0.043 0.014 0.031 0.033 0.037 0.020 0.016 0.042 0.015 0.039 0.017 0.018 INV 0.019 INV INV I

INV 0.030 INV 0.020 INV 0.015 INV 0.046 0.016 0.024 0.014 0.035 0.041 0.021 0.016 0.040 0.016 0.021 0.011 0.031 0.035 0.022 0.01$

0.037 0.016 0.017 0.011 0.029 0.030

. 0.020 0.017 0.046 0.018 0.021 0.014 0.033 0.036 0.022 0.017 0.047 0.017 0.021 0.014 0.030 0.032 0.022 0.016 0.044 0.015 0.016 0.013 0.033 0.035 0.022 0.016 0.047 0.015 0.019 0.014 0.032 0.041 0.021 0.0 17 0.016 0.023 0.013 0.032 0.02S 0.022 0.017 0.043 0.016 0.021 0.014 0.032 0.034 0.021 0.017 7.796 6.$09 19362 16.179 5.311 14.011 4.112 4.886 Avera e

0.024 0.021 0.022 0.024 0.021 0.023 0.024 0.022 0.022 0.022 0.020 0.022 5.555 Wack N START STOP DATE DATE 15 6.

93 13-

-93 16 13-

-93 20-93 17 20-93 27-

-93 18 27-93 4-Ma -93 14 30-Mar-93 6-93 Site 0.020 0.023 0.026 0.020 0.025 Site Site6'ite 7A 0.019 INV 3

0.01$

0.024 INV 3

0.023 0.022 INV 0.025 0.02S 0.030 0.021 INV 3

0.022 Ste 14A'.020 0.020 0.019 0.024 0.02S nd ttnrtcr Site 15'.021 0.023 0.022 0.023 0.02S Site 17A 0.021 0.021 0.022 0.022 0.024 Site 21'.023 0.022 0.021 0.021 0.026 Site 29 0.022 0.019 0.024 0.023 0.02S Site 35 0.023 0.020 0.016 0.021 0.026 Site 40'.021 0.020 0.016 0.022 0.025 hfcan 0.021 0.021 0.021 0.022 0.026

%So 4.765 7.941 15.001 6358 5.869 19 4-Ma 93 II-Ma -93 0.021 0.023 0.02S 0.02S 0.026 0.026 0.028 0.025 0.027 0.028 0.02S 7.754 18-Ma 93 20 11-Ma 21 18-Ma 93 25.Ma 93 0.022 0.010 0.025 0.011 0.021 0.010 0.024 0.011 0.028 0.010 0.02S 0.011 0.023 0.024 0.011 INV I

0.023 0.010 0.028 0.011 0.025 0.021 0.024 S.623 0.012 27.315 22 2S-Ma 93 2-Jun-93 0.018 0.013 0.016 0.020 0.018 0.021 0.019 0.017 0.022 0.016 0.017 0.018 9.753 23 2-Jun-93 8-Jun-93 0.019 0.020 0.016 0.017 0.020 0.018 0.01$

'.019 0.015 0.017 0.015 0.026 6.880 24 8-Jun-93 15-Jun-93 25 15-Jun-93 22-Jun-93 0.026 0.028 0.028 0.026 0.033 0.027 0.028 0.025 0.031 0.029 0.032 0.025 0.024 0.022 0.031 INV I

0.029 0.026 0.031 0.026 0.034 0.030 0.030 9.213 9.213 26 22-Jun-93 29Jun-93 0.025 0.031 0.027 INV I

0.028 0.027 0.030 0.028 0.031 0.028 0.028 0.028 6331 Avera e 0.021 0.022 0.022 0.023 0.023 0.023 0.022 0.023 0.023 0.022 0.023 0.023 I S le invalid due to EIMmalfunction.

Sa lc invalid duo to malfunction.

S lc invalid duc to 4

Sa lc not accessible, 28

r I

1~4 Ci d'l'

TA 8.2 GROSS BETA INAIR3RD - 4TH QUARTER PARTICULATEGROSS BETAINAIR ODChL sam les denoted usrtcr START Wcekl DATE 27 29Jun-93 28 6-Jul-93 29 13.Jul-93 30 20-Jul-93 STOP DATE 7-Jul&

13-Jul-93 20-Jul-93 27-Jul-93 Site 0.021 0.023 0.017 0.021 Site 0.023 0.021 0.021 0.017 Site 0.022 0.020 0.020 0.01$

Site 7A 0.026 0.024 0.020 0.019 Site 14A>>

0.024 0.021 0.020 0.018 Site IS 0.025 0.020 0.015 0.021 Site 17A 0.02S 0.019 0.019 0.019 Site 21>>

0.02S 0.020 0.019 0.019 Site 29 0.026 0.019 0.020 0.020 Site 35 0.029 0.023 0.020 0.019 Site 0.024 0.021 0.02S 0.024 Mean 0.02S 0.021 0.020 0.020

% SD 8.397 7.597 11.948 9.349 31 27-Jul-93 3-Au 93 0.022 0.022 O.O22 0.022 0.021 0.024 0.02S 0.020 0.02S 0.024 0.036 0.024 17.241 32 3-Au -93 10-Au -93 0.029 0.029 0.028 0.027 0.031 0.029 0.029 0.021 INVAL 3

0.030 0.032 0.029 5.200 33 10-Au 93 34 11-Au 93 3S 24-Au -93 36 31.Au 93 37 7$

93 38 14$

93 17-Au -93 0.026 31-Au -93 0.018 8$

93 0.026 14$

93 0.029 21$

93 0.029 24-Au -93 0.023 0.027 0.025 0.017 0.028 0.028 0.026 0.025 0.026 0.020 0.025 0.027 0.02S 0.027 0.037 0.015 0.027 0.027 0.028 0.024 0.016 0.025 0.028 0.027 0.02S 0.022 0.015 0.024 0.029 0.031 0.026 0.029 0.018 0.029 0.030 0.028 0.030 0.030 0.027 0.035 0.029 0.029 0.028 INV 0.028 INV 0.016 INVAL 0.030 0.022 0.016 0.030 0.029 0.027 0.028 0.024 0.016 0.027 0.033 0.028 0.027 0.026 0.017 0.028 0.029 0.028 6.335 16.136 8.902 10.710

$.502 5.564 39 21$

93 Avcrs e

28$

93 0.031 0.024 0.031 0.02S 0.031 0.024 0.036 0.026 0.035 0.024 0.03$

0.024 0.039 0.026 0.036 0.025 0.036 0.027 0.035 0.026 0.037 0.027 0.036 0.02S 6.824 4.086 Week it DATE STOP DATE Site Site Site 6>>

Site 7A Fourth Site14A'artcr SiteIS'ile 17A She21'ite 29 Sita 3$

Site

% SD 40 28$

93 41 5'-93 42 1243ct.93 54ct-93 0.047 1243ct-93 0.029 1943ct.93 0.027 0.043 0.028 0.017 0.046 0.030 0.016 0.049 0.027 0.019 0.045 0.026 0.021 0.045 0.029 0.018 0.050 0.02$

0.021 0.047 '.048 0.021 0.023 0.025 0.050 0.027 0.029 0.048 0.027 0.023 0.047 0.027 0.022 4.478 8.600 18.209 43 194ct-93 44 26~-93 45 2-Nov-93 46 9-Nov-93 47 16-Nov-93 2-Nov-93 9-Nov 93 16.Nov-93 23-Nov-93 0.056 0.039 0.046 0.046 0.044 0.034 0.051 0.028 0.044 0.04$

0.031 0.054 0.023 0.051 0.038 0.037 0.050 0.028 0.050 0.039 0.044 0.047 0.030 0.044 0.041 0.035 0.045 0.026 0.044 0.055 0.03$

0.053 0.034 0.045 0.043 0.035 0.055 0.028 0.049 0.047 0.039 0.059 0.029 0.046 0.055 0.043 0.053 0.034 0.056 0.038 0.036 0.054 0.029 0.044 0.046 0.038 0.052 0.029 0.047 13.895 8.068 1.864 10.882 1.869 48 23-Nov-93 49 30-Nov-93 50 7-Dcc-93 51 14-Dcc-93 52 21-Dcc-93 7-Dcc-93 0.038 14.Dcc-93 0.037 21-Dcc-93 28-Dcc-93 0.037 0.04$

30.Nov-93 0.044 0.041 0.035 0.040 0.035 0.043 0.040 0.036 0.042 0.040 0.040 0.035 0.043 0.038 0.044 0.039 0.031 0.037 0.033 0.036 0.041 0.031 0.042 0.038 0.039 0.045 0.031 0.041 0.042 0.037 0.045 0.033 0.050 0.038 0.058 0.042 0.033 0.045 0.041 0.043 0.045 0.043 0.040 0.044 0.044 0.037 0.030 0.044 0.039 0.036 0.042 0.034 0.042 0.039 0.043 10.718 8.831 7.983 14.321 Ave 0.041 0.031 0.039 0.038 0.036 0.031 0.040 0.041 0.040 0.043 0.037 0.039 9.842 I Sa lc invalid duo to EIMmalfunction.

Sam lc invalid due to Sam lc invaBd duc to malfunction.

4 Sam lcnotacceaaiblc.

29

V, V

"4 t

't~

~O e

'J i

8.3 GAMMAINAIRFILTERCOMPOSITES (pCi/m3)

(ODCM samples denoted by *)

QUARTER ENIDPOINT 1ST 4/1/93 6/29/93 Site NUCLIDE 1

Cs-134

<LLD Cs-137

<LLD Cs-134

<LLD Cs-137

<LLD Site

<LLD

<LLD Site Site Site 6*

7A 14A*

<LLD <LLD <LLD

<LLD <LLD <LLD Site 15*

<LLD

<LLD Site Site 17A 21*

<LLD <LLD

<LLD <LLD Site 29 Site Site 35 40*

<LLD <LLD

<LLD <LLD 9/28/93 Cs-134

<LLD Cs-137

<LLD

<LLD 12/28/93 Cs-134

<LLD Cs-137

<LLD

<LLD <LLD <LLD <LLD <LLD <LLD <LLD 30

e P ~a) te P

0 k

,J 43s Jl

AIRBORNERADIOIODINE( CVm3 ODCM. sam les denoted b First Qua rter TA E 8.4 RADIOIODINEINAIR1ST - 2ND QUARTER Week8 START STOP DATE DATE Site Site Site

.6*

Site 7A Site14A'ite15'ite 17A Site 21*

Site 29 Site 35 Site 40'9-Dec-92 5-Jan-93 5-Jan-93 12-Jan-93 12-Jan-93 19-Jan-93 19-Jan-93 26-Jan-93

<LLD

<LLD INVALIDI

<LLD INVAL 1

<LLD

<LLD 26-Jan-93 2-Feb-93 2-Feb-93 9-Feb-93 9-Feb-93 16-Feb-93 16-Feb-93 23-Feb-93

<LLD

<LLD 10 23-Feb-93 2-Mar-93 2-Mar-93 9-Mar-93 9-Mar-93 16-Mar-93 INVALID2

<LLD

<LLD INVALIDI

<LLD INVALID3

<LLD INVALID3)

<LLD

<LLD 12 13 16-Mar-93 23-Mar-93 23-Mar-93 30-Mar-93

<LLD

<LLD INVALID3

<LLD

<LLD Week 8 14 START STOP DATE DATE 30-Mar-93 6-Apr-93 Site

<LLD Site 15" Site 17A Site 21*

Site 29 Site 35 Site 40" 15 16 17 18 6-A r-93 13-A

-93 13-A

-93 20-A

-93 27-A"r-93 27-A

-93 4-Ma -93

<LLD

<LLD INVALID(3

<LLD INVALID(3)

<LLD INVALID3

<LLD

<LLD 19 20 4-Ma -93 11-Ma -93 11-Ma -93 18-Ma -93

<LLD

<LLD 21 22 23 24 18-Ma -93 25-Ma -93 25-Ma -93 2-Jun-93 2-Jun-93 8-Jun-93 8-Jun-93 15-Jun-93

<LLD

<LLD INVALIDI

<LLD

<LLD 25 26 15-Jun-93 22-Jun-93 22-Jun-93 29-Jun-93 INVALIDI

<LLD

<LLD INVALIDI

<LLD

<LLD I Sam le invalid due to ETMmalfunction.

Sam le invalid due to wer outa e.

2 Sam le invalid due to um malfunction.

Sam Ic not accessible.

31

"A iO 0

v<-

iO

TA 8.5 RADIOIODINEINAIR3RD - 4TH QUARTER AIRBORNERADIOIODINE CVm3 ODCM. sam lcs dcnotcdb Third Quarter START Week 8 DATE 27 29-Jun-93'8 7-Jul-93 29 13-Jul-93 30 20-Jul-93 31 27-Jul-93 STOP DATE 7-Jul-93 13-Jul-93 20-Jul-93 27-Jul-93 3-Aug-93 Site COLD Site COLD

<LLD Site 6a

<LLD COLD Site 7A CU.D Site 14A*

Site 15 COLD OLD Site 17A Site21'ite 29 Site-35 COLD Site 40'2 3-Aug-93 10-Au -93 CLLD CU.D 33 10-AU -93 34 17-Au -93 35 24-AU -93 36 31-Au -93 17-AU -93 24-Au -93 31-Au -93 7-S 93 COLD

<LLD COLD OLD COLD CU.D

<LLD OLD OLD COLD CKD

<LLD COLD COLD INV 3

CU.D INVAL 3

COLD 37 7-S 93 38 14-S 93 14-S 93 OLD 21-S 93 COLD

<LLD 39 21-S 93 28-93 OLD Fourth Quarter START DATE 40 28-S 93 41 5~t-93 STOP DATE 5Mt-93 12'-93 Site COLD Site OLD

<LLD Site CU.D OLD Site 7A OLD Site14A'ite 15 Site 17A Site21'ite 29 Site 35 COLD Site 40'2 12'-93 19'-93

<LLD CU.D 43 19'-93 44 26~t-93 45 2-Nov-93 46 9-Nov-93 47 16-Nov-93 2M)ct-93 2-Nov-93 9-Nov-93 16-Nov-93 INV 23-Nov-93 COLD

<LLD OLD COLD OLD OLD CU.D 48 23-Nov-93 49 30-Nov-93 7-Dec-93 OLD 30-Nov-93

<LLD OLD OLD OLD OLD CU.D OLD OLD COLD CfLD COLD 50 7-Dcc-93 51 14-Dcc-93 52 21-Dec-93 14-Dec-93 COLD 21-Dec-93 COLD 28-Dcc-93 OLD COLD INVAL 4

COLD CAD COLD COLD OLD CU.D COLD 1

Sam le invalid due to ETMmalfunction.

Sam le invalid due to wcr outa e.

2 Sam le invalid duc to um malfunction.

Sam le not accessible.

32

- gW'I q 'l~

pl P+

I iO I

I

~li

TA 8.6 DATE 1993 VEGETATION(pCi/kg)

(ODCM sample denoted by *)

(1)

(I)

LOCATION TYPE Lettuce Beet Tops SITE N47'wiss Chard ADAMS Lettuce 13-Apr-93 4-May-93

<LLD

<LLD COLLECTED Ba/La-140 Co-58 13-Apr-93 13-Apr-93

<LLD

<LLD Co-60

<LLD

<LLD Cs-134 Cs-137

<152

<168

<LLD

<LLD Fe-59

<LLD

<LLD I-131 Mn-54

<797

<LLD

<213

<LLD

<60

<LLD

<66

<LLD Nb-95 Zr-95 Zn-65 Beet Tops Swiss Chard 4-May-93 4-May-93

<LLD

<79

<LLD

<86

<LLD

<LLD <LLD <LLD

<LLD <LLD <LLD Leaf Lettuce SITE 852'omaine Lettuce GAVETTE Lettuce Cabbage 6-Apr-93 6-Apr-93

<LLD

<LLD 6-Apr-93 4-May-93 4-May-93

<LLD

<LLD <LLD

<93

<LLD

<83

<LLD

<LLD <LLD <LLD

<LLD <LLD <LLD Collards Mustard Grns Turnip Grns Collards 6-Jan-93 6-Jan-93

<LLD

<LLD 6-Jan-93

<LLD

<LLD 9-Mar-93

<LLD

<LLD <LLD

<LLD <LLD <LLD

<LLD COLD <LLD SITE 062*

Mustard Grns TOLLESON Turnip Grns Spinach Parsley Collards 9-Mar-93 9-Mar-93 6-Apr-93 6-Apr-93 6-Apr-93

<LLD

<61

<LLD

<LLD <LLD

<213 OLD

<198

<LLD

<LLD <LLD

<LLD <LLD <LLD

<LLD <LLD <LLD Cabbage 4-May-93

<LLD

<LLD <LLD

<LLD

<LLD <LLD <LLD <LLD <LLD (1)Vendor lab failed to meet required LLD, (see section 8.3).

33

'0 ff.

C+ j

'A

~~

TAB E8.7 SAMPLE DATE LOCATION COLLECTED 26-Jan-93

'3-Feb-93 30-Mar-93 27-A r-93 25-Ma -93 29-Jun-93 27-Jul-93 MCARTHUR RESIDENCE (SlTE ¹46)

31-AU -93 28-S

-93 26-Oct-93 30-Nov-93 28-Dec-93 26-Jan;93 23-Feb-93 30-Mar;93 27-A r-93 25-Ma -93 29-Jun-93 GAVETTE RESIDENCE (SITE ¹52)

27-Jul-93 31-Aug-93 28-S

-93 26-Oct-93 30-Nov-93 28-Dec-93 Ba-140 DRINKINGWATER Cllliter)

(ODCM sam les denotedb

)

Cs-137 Fe-59 I-131 La-140 Co@8, Co-60 Cs-134

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD.<LLD 34 Mn-54

<LLD

<LLD Zr-95 Nb-95 Zan

<LLD <LLD. <LLD 500+/M2 Gross Bet 4.8

+/-

2.3

+/-

2.85

+/-

3.74

+/-

3.75

+/-

2.96

+/-

3.79

+/-

4.24

+/-

4.92

+/-

9.2

+/-

2.6 2.2 2.35 2.3 2.23 2.57 1.95 3.58 2.5

I k

fM 4%

f, 1) k

TA 8.7 SAMPLE DRINKINGWATER Ci/liter)

(ODCMsam lesdenotedby*)

LOCATION COLLECTED 26-Jan-93 23-Feb-93 30-M81'-93 Ba-140 La-140 CMS Co40

<LLD

<LLD Cs-134

<LLD Cs-'137 Fe-59 I-131

<LLD

<LLD <LLD Mn-54 Zr-95 Nb-95 Xn<5

<LLD <LLD

<LLD H4 'rois Be SHEPPARD RESIDENCE (SITE QS)

27-A r-93 25-Ma -93 29-Jun-93 27-Jul-93 31-Au -93 28-S

-93 26-Oct-93 30-Nov-93 28-Dec-93

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD 3.8 496+/480

<LLD 3.8 3.62 4.7

+/-

2.26

+/-

2.3

+/-

1.92

+/-

2.3 SCOTT CHOWANEC RESIDENCE (SITE 849)

26-Jan-93 23-Feb-93 30-MK-93 27-A r-93 25-Ma -93 29-Jun-93 27-Jul-93 31-Au -93 28-S

-93 26-Oct-93 30-Nov-93 28-Dec-93

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD 3.61 7.65 18.3

+/-

2.44

+/-

2.41

+/-

2.8 35

'I P

'C F

y%g

,g, Pq j 4,

4" 0

TA 8.7 DRINKINGWATER( Cillitcr SAMPLE LOCATION SITE DRINKING WATER DATE COLLECTED 5-Jan-93 3-Feb-93 2-Mar-93 7-A

-93 17-Ma -93 2-Jun-93 7-J01-93 4-Au -93 22-S

-94 4'-93 Ba-140 La-140 Co-58

<LLD

<LLD.<LLD

<LLD

<LLD Co40

<LLD

<LLD Cs-134 Cs-137 Fe-59

<LLD

<LLD I-131

<LLD

<LLD Mn-54 Zr-95 Nb-95

<LLD <LLD <LLD

<LLD

<LLD UN1T¹1 DW 1-Nov-93 13-Dec-93

<LLD

<LLD <LLD <LLD

<LLD <LLD <LLD UNIT¹2 DW 1-.Nov-93 13-Dec-93

<LLD

<LLD <LLD <LLD

<LLD <LLD <LLD UNIT¹3 DW 1-Nov-93 13-Dec-93

<LLD

<LLD. <LLD

<LLD

<LLD <LLD <LLD

<LLD <LLD <LLD N. ANXDW 1-'Nov-93 13-Dec-93

<LLD

<LLD <LLD <LLD

<LLD <LLD <LLD 36

J y4 r,

4' l~

0

TABLE8.8 SAMPLE DATE GROUNDWATER Ci/liter)

(ODCM sam les denoted by *)

LOCATION COLLECTED Ba-140 La-140 Co-58 Co40 Cs-134 Cs-137 Fe-59 I-131 Mn-54 Zr-95 Nb-95 H-3 WELL27ddc (Site 857)*

15-Feb-93 17-Ma -93 16-AU -93 15-Nov-93

<LLD

<LLD invalid(1) invalid(1)

<LLD <LLD

<LLD

<LLD 585

<LLD <LLD

+/-

487 WELL34abb Site 858

15-Feb-93 17-

-93 16-AU -93 15-Nov-93

<LLD

<LLD CU.D

<LLD 1

sam lenotavailabledueto um mainteriance.

37

J 4

4

~ 4'

~ g Y I 0

8.9 SURFACE WATER Cilliter (ODCM sam les denoted b

~

SAMPLE LOCATION EVAP POND 1 DATE COLLECTED 25-Jan-93 22-Feb-93 29-Mar-93 Ba-140 La-140 Co-58

<<LLD

<LLD

<<LLD

<<'LLD

<LLD

<<LLD

<<LLD Co-60 Cs-134 Cs-137 Fe-59

'<<LLD

<<LLD

<LLD

<<LLD 12 I-131

+I-6

+/-

7 Mn-54 Nb-95 Zn45

<<LLD

<<LLD <<LLD CAD

<<LLD Zr45 145.1

+I-163.6

+I-46.0

+/-

132 13.0 3.8 Gross Beta SiteN59 26-A r-93 24-Ma -93 28-Jun-93 26-Jul-93 30-Au -93 274 93 25~-93

<<LLD

<LLD

<<LLD

<<LLD OLD

<LLD

<<LLD

<LLD

<<LLD

<LLD

<<LLD

<LLD

<<LLD

<LLD

<<LLD 6.0

+/-

5

+I-4

+/-

2

<<LLD

<LLD <<LLD

<<LLD

<<LLD <<LLD

<<LLD

<<LLD <<LLD

<<LLD

<LLD 72.0

+/-

149.8

+I-51.7

+I-401.0

+I-166.0

+I-6.6 13.6 3.8

552

+/-

56.4 15.1 OLD 491 29-Nov-93 27-Dec-93

<LLD

<<LLD

.<<LLD

<LLD

<<LLD

<<LLD 108A

+/-

291.9

+I-18.4 17.1 621

+I-429 EVAP POND 2 Sltet/63

'5-Jan-93 22-Feb-93 29-Mar-93 26-A r-93 24-Ma -93 28-Jun-93 26-Jul-93 30-Aug-93 274 93 25Mt-93 29-Nov-93 27-Deo-93

<<LLD

<LLD

<<LLD

<LLD

<<LLD

<LLD

<<LLD

<<LLD.

<LLD

<<LLD

<<LLD cLLD

<<LLD

<<LLD OLD

<<LLD

<LLD

<<LLD

<LLD

+/-

3

+/-

2

<<LLD

<<LLD <<LLD

<<LLD

<LLD

<<LLD

<<LLD <<LLD

<LLD

<<LLD <<LLD 156.8

+I-88.1

+I-51.8

+/-

55.9

+/-

226.2

+I-471.1

+/-

449.6

+I-NA 277.4

+/-

202.2

+/-

195.9

+I-13.5 10.9 3.9 959

+/-

6.2 15.5 60.2 1615

+I-57.9 18.2 1642

+I-21.8 14.8 2289

+/-

495 486 417 450

4 I

0 ll t

TABLE8.9 SURFACE WATER Cmiter (ODCM sam les denoted b

~

SAMPLE LOCATION DATE COLLECTED 25-Jan-93 Ba-140 La-140 Co-58

<LLD

<LLD COLD Co-60

<LLD Cs-134 Cs-137 Fc-59

<LLD COLD

<LLD 12 I-131+/-'n-54 Nb-95 Zn45 COLD COLD OLD Zr-65 Gross Beta 145.1

+/-

13.2 H4 EVAP POND 1 Sltett59

'2-Feb-93 29-Mar-93 26-A

-93 24-Ma -93 2&-Jun-93 26-Jul-93 30-Aug-93 27493 25~-93 29-Nov-93 27-Dec-93

<LLD OLD

<LLD

<LLD CU.D

<LLD

<LLD COLD

<LLD COLD OLD cLLD

<LLD COLD COLD

'LLD

<LLD WLD

<LLD

<LLD OLD

<LLD

<LLD CU33

<LLD

<LLD CAD

.<LLD OLD

<LLD 6.0 COLD WLD

+/-

<LLD OLD

<LLD OLD 163.6

+/-

46.0

+/-

72.0

+/-

149.8'/-

51.7

+/-.

401.0

+/-

NA 166.0

+/-

NA 108.4

+/-

291.9

+/-

13.0 3.8 CAD 6.6 13.6 3.8 552 56.4 15.1 COLD 18.4 17.1 621

+/-

491 429 EVAP POND 2 Sitett63

'5-Jan-93 22-Feb-93 29-Mar-93 26-A

-93 24-Ma -93 28-Jun-93 26-Jul-93 30-Au -93 27493 25@et-93 29-Nov-93 27-Dec-93 COLD

<LLD

<LLD COLD OLD OLD OLD

<LLD OLD

<LLD

<LLD COLD

<LLD OLD OLD WLD

<LLD

<LLD COLD CUB OLD

<LLD OLD OLD CAD OLD cLLD

<LLD COLD cLLD OLD COLD

<LLD OLD

<LLD

<LLD CUD)

COLD

<LLD

+/-

OLD

<KLD COLD OLD OLD CAD COLD COLD COLD CAD

<LLD <LLD COLD

<LLD OLD CU.D CAD

<LLD COLD OLD OLD CKD

<LLD

<LLD OLD 156.8

+/-

88.1

+/-

51.8

+/-

55.9

+/-

226.2

+/-

471.1

+/-

449.6

+/-

277.4

+/-

NA 202.2

+/-

195.9

+/-

13.5 10.9 3.9

. 959 6.2 15.5 60.2 1615 57.9 18.2 1642 21.8 14.8 2289

+/-

495 486 417 450 39

I

<L 5

0 r

',CL Ll V

'c 0

h ~

8.9 SURFACE WATER Ci/liter)

SAMPLE DATE LOCATION COLLECTED 27-Jan-93 Ba-140

<LLD La-140 Co-58 Co-60

<LLD

<LLD Cs-134 Cs-137 Fe-59

<LLD <LLD 20 I-131

+/-

7 Mn-54 Nb-95 Zan Zr45

<LLD <LLD

<LLD INFLUENT 22-Feb-93 29-Mar-93 27-A r-93 24-Ma -93 28-Jun-93 26-Jul-93 31-AU -93 28-S '3 26-Oct-93 20-Nov-93 27-Dec;93

<LLD

<LLD <LLD <LLD

<LLD <LLD 10.0

<LLD <LLD <LLD

<LLD <LLD 10

<LLD <LLD 26

<LLD <LLD 8

<LLD <LLD <LLD

<LLD <LLD 15

+/-

8

+/-

2

+/-

3

+/-

4

+/-

15

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD OLD

<LLD COLD

<LLD

<LLD <LLD CU3) 40

I f 9 U Wl Cl

+4

8.9 LOCATION..

SEDIMENT.

BASIN¹2 DATE COLLECTED 4-Jan-93 11-Jan-93 25-Jan-93 1-Feb-93 22-Feb-93 1-Mar-93 8-Mar-93 15-Mar-93 22-Mar-93 29-Mar-93 7-A

-93 12-A

-93 19-A

-93 26-A

-93 3-Ma -93.

10-Ma -93 17-Ma -93 9-Au -93 16-Au -93 22-Nov-93 29-Nov-93 6-Dec-93 13-Dec-93 Ba-140 La-140 Co-58

<LLD

, <LLD CfLD

<LLD OLD

<LLD

<LLD OLD

<LLD

<LLD OLD

<LLD OLD COLD

<LLD OLD COLD..

<LLD cLLD OLD

<LLD OLD 'AD

<LLD NA NA NA OLD OLD

<LLD Co40

" OLD

<LLD SURFACE WATER Ci/iiter I-131 Cs-134 Cs-137 Fa59

,OLD COLD

<LLD

%LD COLD 'CLED CUJ)

OLD

<LLD OLD CU.D OLD

'LLD CLLD

<LLD CAD CLLD COLD OLD 5.0

+I-CLLD NA NA NA NA

<LLD

<LLD OLD D

41 Mn-54 Nb-95 Zn45

<LLD CLLD COLD NA NA

.NA CKD

<LLD OLD COLD

.OLD 'COLD OLD'LD CAD Gross Beta NA NA NA NA NA NA NA NA NA NA NA 678

. 542 1641 2038 1489 3595 1174

'660 1742 715

+I-509

+/-

458

+/-

437

+/-

525

+/-

524

+/-

533

+/-

417

+/-

526

'+/-'30

+/-

519

+/-

532

+/-

414

0

'Ql J%

6 0

0

TAB S.10 SLUDGE SAMPLE DATE LOCATION COLLECTED Ba/La-140 Co-58 Co%0 Cs'-'134 Cs-137 Fo-59 I-131 Mn-54 Nb.-95 Zr-95 WRF WST CNTFG 5-Jan-93 13-Jan-93 28-Jan-93 23-Feb-93 17-Mar-93 30-Mar-93 13-Apr-93 27-Apr-93 11-May-93 25-May-93 8-Jun-93 23-Jun-93 7-Jul-93 13-Jul-93 3-Aug-93 17-Aug-93

. 31-Aug-93 14-Sep-93 284ep-93 12@et-93

<LLD

<LLD <LLD <LLD

<LLD

<LLD 1669

<LLD 3381

<LLD 1499

<LLD 466

<LLD <308

<LLD 233

<LLD 1153

<LLD 827

<LLD 303

<LLD 1614

<LLD 498

<LLD 793

<LLD 838

<LLD 2299

<LLD 2213

<LLD 664

<LLD 971

<LLD 2260

<LLD 1738

+/-

47

<LLD <LLD

+/-

76

<LLD <LLD

+/-

190

<LLD <LLD

+/-

66

<LLD <LLD

+/-

137

<LLD <LLD

+/-

+/- 266

<LLD <LLD

+/-

188

<LLD <LLD

+/-

33

<LLD <LLD

+/-

28

<LLD <LLD

+/-

54

<LLD <LLD

+/-

19

<LLD <LLD

+/-

18

<LLD <LLD

+/-

7

<LLD <LLD

+/-

28

<LLD <LLD

+/-

17

<LLD <LLD

+/-

28

<LLD <LLD

+ -

60

<LLD <LLD

+/-

15

<LLD <LLD

+/-

9

<LLD <LLD SAMPLE 264ct-93 9-Nov;93 23-Nov-93 7-Dcc-93 21-Dec-93 DATE

<LLD

<LLD <LLD <LLD

<LLD

<LLD 1331

<LLD 1554

<LLD 1829

<LLD 1356

<LLD 2694

+/-

12

<LLD <LLD

+/-

9

<LLD <LLD

+/-

26

<LLD <LLD

+/-

140

<LLD <LLD

+/- 348

<LLD <LLD SED BSN 2 (1)

SED BSN 2 (2) 4-Aug-93 4-Aug-93 LOCATION COLLECl'ED Ba/La-140

<LLD

<LLD <LLD <LLD

<LLD Co-58 Co40 Cs-134

<LLD <LLD <LLD I-131

<LLD Fe-59

<LLD 67

<LLD 71 s-137 Mn-54 Nb-95

+/-

6

<LLD <LLD

+/-

14

<LLD <LLD Zr 95 SED BSN 2 (3)

Ditch Center 4-Aug-93 4-Aug-93

<LLD

<LLD <LLD <LLD

<LLD 62

<LLD 12

+/-

6

<LLD <LLD

+/-

15

<LLD <LLD 42

I 0

k 0

TAB 8.11 SAMPLE DATE SEWAGE (pCi/kg)

LOCATION COLLECTED 31-Jan 10-Feb 18-Feb 27-Mar Ba/La-140 Co-58 Co%0

<LLD

<LLD <LLD

<LLD

<LLD <LLD

<LLD

<LLD <LLD Cs-'134

<LLD Cs-137 Fe-59

<LLD <LLD

<LLD <LLD 1397 I-131

+/- 569 Mn-54

<LLD Nb-95 Zr-95 Zan Sampling dtscontinued aAer WRF began pump4ack operations.

43

E 4 1 wp

<,t jp' w"

)"

TABLE8.12 DATE CROSSWINDS DAIRYSITE //50'DCM aatu denoted DATE BUTLERDAIRYSITE //51 COLLECTED I 131' CS.134 CS.137 BA/LA-140 COLLECTED I-131 BA/LA-140 5-0.68

+/-

0.64 cLLD

cLLD" cLLD OLD 037

+/

0.19 0.38 0.4

+/

035

+/-

0.2 cLLD

'8-Nov-93'0;42

> +/-.033 8-Nav43 DATE AIRYSIT DATE DICKhiAN AIRYSITE //54 COLLECTED 4@an-93 8-Pcb.93 8-Mat 93 3-Ma 93 8-Jun-93 6.Jul-93 9-93 I-131 CS-134 CS-137 BA/LA-140 COLLECTED I-131 5-93 3-Ma 93 S.Jun-93 6-Jul-93 9-93

+/- 0.5 CS-134 CS-137 BA/LA-140 5M-93 8-Nov-93 6.Dcc 93 0.48

+/- 034 5~93 8-Nov4t3 6.Dco-93 DATE COLLECTED DAIRYSIT E'/56'EW 1-131 CS.134 CS-137 BA/LA-140 1 5/3/93 Vendor lab error!csultcd 7/6/93 No le available.

forI-13 8 Fcb-93 8-Mat 93 5-93 3-Ma 8-Jun-93 6-Jul-93 9-93 invali

+/-

0.43 6/8/93 No lo available.

5M-93 8-Nov.93 6-Dcc-93

Gross Beta ln Air 1985-1993 1.000 Chernobyl Accident 0.100 o

Btd 0.010 Weekly Average 0.001 0

Or+

CO Ol C

00 C

Kl 00 00 0

Ort 00(0 Sample Collection O

Date 45

rIG s.z 0.05 Gross Beta in AirParticulates Comparison

= Pre-operational (1981-1985) vs Operational (1991-1 993)

Gross Beta in AirParticulates-pre-operational (1981-1985) 0.045 0.04 0.035 CONTROL LOCATION

rtGross Beta in Air-1991

~ Gross Beta in Air-1992

~ Gross Beta in Atr-1993 0.03

~ 0.025 E

O 0.02 0.015 0.01 0.005 Sample location 46

FIG 8.3 Gross Beta in Drinking Water -1993 35 30 25

~ 20 0)

O~<5 Admin. action level

~McArthur (site ¹46)

crGavette (site ¹52)

~ Sheppard (site ¹48)

rrChcwanec (site ¹49) 10 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 47

0 l

0 4~

ll

FIG 8.4 0

Comparison of Pre-Operational Soil Activity(Cs-137) with Onsite Sediment 250 238 200 209 150 O

100 67 50 0

17 40

,t s~

Pre-Op. Soil Study (1976 onsite avg.)

Sedimentation Basin 2-1992 Pre-Op. Soil Sedimentation Study (1984-Basin 2-1990 onsite avg.)

(Sedimentation Basin 2 accepts site storm runoff, no other gamma emitters present)

Sedimentation Basin 2-1993 48

I a

fI' 0

k Crz

/de~

0

9.0 Thermoluminescent Dosimet Results and Data Inte retation Thermoluminescent Dosimeters were placed in fiftylocations ranging Rom one to forty-five miles Rom the Palo Verde Nuclear Generating Station.. Beginning in 1984,.the:Panasonic.Model;812 Dosimeter replaced all other TLDs in use.

The 812'is a multi&ement dosimeter'combining two.elements ofLithiumBorate and two elements of Calcium Sulfate under various filters.

TLD locations are shown in'Figures 2.1 and 2.2. TLD locations are described in Table 9.1. TLD results for 1993 are presented in Table 9.2; TLD results for 1984.through.1993'.are presented',in'.a,"graph'on.Figure 9.1 (excluding. transit control TLD845).

Figure 9.2 shows the results ofthe environmental TLDs Rom the pre-operational phase compared to 1993,environmental TLD results. The TLDs were compared site, to site to:provide:the:most meaningful-.information. As, evidenced by the graph, the.1993,results trend closely,with'the'prewperational.results:

It is logical to conclude that the ofisite.dose, as measured by the TLDs, has not changed since PVNGS became operational.

During 1993, the APS Dosimetry Group participated in the Tenth Iiiternational Intercomparison of Environmental Dosimeters. APS sent in their standard environmental dosimetry devices to be tested under very rigorous conditions; i.e.,

very low dose laboratory irradiations and environmental exposures in the mountains ofIdaho (heavy snowfall, snow driQs and high winds).

The intercomparison results show that the APS TLDs were very accurate and precise. The preliminary graphs sent by INEL show that some facility's results were factors ofthree to five low, while others were almost a factor of two high as compared to.the delivered doses. The"APS results were clearly, among the'best values being within 5.7% of the INEL expected results and within3.4% ofthe INELQA dosimeter measurements.

Also during 1993, the Dosimetry Group completed extensive testing ofthe TLDProgram during it's NVLAPCertification e

Proficiency Testing. The TLDs that are used for personnel dosimetry, as well as for the environmental dosimetry, passed all eight ofthe available categories.

49

I Cl C r Cl V

p 'pe

TABLE9.1 THERMOLUMINESCENTDOSMETRY (TLD),SITE.LOCATIONS (distances and directions are relative to Unit 2 in miles)

TLD NVMBER TLDLOCATION LOCATIONDESCRXPTION 10 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 E30 ENE24 E21 E16 ESE11 SSE31 SE7 SSES SS SES ESES Nl E2 ESE2 SE2 SSE2 S3 SSW3 WS SW4 WSWS SSWS Swl WSWl Wl WNW1 APS Western Division Office, Good ear Scott-Libb School, Pe

'lie and Thomas Roads Libert School, 19800 W. H

. 85 APS Bucke e Office, 615 N. 4th St., Bucke e Palo Verde School, Palo Verde Rd. (291st Ave.) and Old US 80 APS Gila Bend substation, fronta e road west oftown Old US 80 and Arlin on School Rd.

Southern Pacific Pi eline Rd., 1.4 miles SW of355th Ave.

Southern Pacific Pi eline Rd., 2.5 miles SW of355th Ave.

SE corner of355th Ave. and ElliotRd NW corner of339th Ave. and Dobbins Rd NE corner of339th Ave. and Bucke e-Salome Rd.

.N. site bounda NNE site bounda NE site bounda, WRF access road ENE'site bounda E site bounda ESE site bounda SE site bounda SSE site bounda S site bounda SSW site bounda 2-miles north ofElliotRd., 3 miles west ofWintersbur Rd ElliotRd., 2 miles west ofWintersbur Rd.

ElliotRd., 3,miles west ofWintersbur Rd. at cattle ard Sheppard farm, 13202 S. 383rd Ave., 0.5 miles west of house SW site bounda WSW site bound W site bounda Wl'AVsite bound NW site bounda NNW site bounda 50

II if'~g e

4 ~

i C'~

igy

TABLE9.1 THERMOLUMINESCENTDOSIMETRY(TLD) SITE LOCATIONS (distances and directions are relative to Unit 2:in miles)

TLD NIJVtIBER TLDLOCATION LOCATIONDESCRIPTION 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 N3 WI'AV20 N45 ENE35 E16 ENE30 E35 E24 ENE11 Bucke e Rd., 0.5 miles west. of395th Ave SE'corner. of395th Ave. 'and Van'Buren St Fire Station, 40901 W. Osborn Rd., Tono ah SW corner ofWintersbur

.Rd. and Van Buren St.

SE corner of363rd Ave. and Van Buren St.

SW corner of355th Ave. and Bucke e Rd.

.343rd Ave., 0.5 miles south ofLower Bucke e Rd.

Wintersbur, Transmission Rd. south oftrailer ark Harquahala Valley School, Van Buren St.,

1 mile west of Steve Martori Dr.

Ruth Fisher, School, Indian School:Rd. and Wintersbur Rd Vulture-Peak. School, 1 mile south ofUS 60, Wickenbur APS El Mira e Office, 12313 W. Grand Ave.

APS Buckeye Office, 615 N. 4th St., REMP trailer (lead i

LitchfieldPark School, 13825 W. Indian School Rd Littleton School, 115th Ave. and H

. 85, Cashion Jackrabbit Trail south ofI-10, north ofFilmore St.

Palo Verde Rd., 0.25 miles south ofI-10 3.5 miles west ofWintersburg Rd., 2 miles south of Bucke e-Salome Rd.

51

'K p'

<r

~~>>

~O Q*,

,k k

&1 4

<l pt4 w

QV

~ ~

0 W

P

TABLE92 Station 1st Qtr mR/std qtr 1993 Environmental TLDResults 4th Qtr 2nd Qtr 3rd Qtr mR/std qtr mR/std qtr mR/std qtr Average mR/std qtr 10 12 13 14 15 16 17 18 19 20 21 23 24 25 26 27 28 29 30 31 32 33 35 36 37 38 39 40 41 42 43 45 46 47 48 49 50 192 20.3 20.3 20.3 18.8 23.8 212 26.8 20.7 212 20.7 22.2 21.2 18.4 212 212 23.8 19.9 19.9 21.2 25.3 21.2 20.3 23.3 24.6 26.1 24.6 20.7 23.8 20.3 21.8 23.8 17.7 4.5 17.7 INVALID(1) 19.9 20.3 16.4 18.1 20.5 22.0 19.0 20.5 25.9 21.6 20.5 22.0 21.6 19.7 20.5 21.0 20.1 20.1 20.1 25.5 22.0 24.0 20.5 23.5 23.5 26.4 21.0 20.1 21.0 23.5 22.0 17.7 4.3 18.1 24.8 19.7 19.7 16.6 17.7 17.7 19.9 19.2 18.4 21.8 21.2 19.9 18.8 20.3 18.4 20.3 19.9 17.7 192 18.8 20.3 18.8 20.7 21.2 18.8 17.3 19.2 23.3 21.8 20.7 20.7 18.8 20.3 21.8 20.7 19.2 18.8 19.9 20.7 15.8 3.9 15.8 18.4 14.9 21.6 21.0 27.4 25.1 29.4 24.0 25.1 23.5 21.6 24.0 24.0 26.4 22.0 22.0 27.9 27.4 25.1 25.1 27.0 29.4 27.0 23.5 23.5 26.4 24.0 18.1 4.1 19.0 25.9 22.0 21.6 18.1 18.9 20.6

.20.9 21 ~ 1 19.3 21.1 26.6 21.0 20.5 21.3 19.3 20.8 21.2 23.5 20.2 19.8 20.7 25.2 23.2 23.3 20.6 23.4 24.4 26.6 23.2 20.8 20.7 21.5 24.1 23.0 17.3 17.7 202 20.0 16.5 (1) Site N47 not accessable.

52

FIG 9.1 27.0 PVNGS Network TLD Exposure Rates mR/Std Qtr = Network Avg Exp Rate 90 24/1000 25.0 g 23.0 c 21.0 E

19.0 17.0 mR/Qtr ~ BASELINE~ MEAN 15.0 F)

Cr)

W W

LO ID Co Co Co Co Co Co 0O CO CO CO CO

~

Co Co CD CO CO 0O 0O Co Co 0l O

Co 0lc CO C)

CD l

0lc CO CD 0l Crl 0l 0lc CO 4

1983-1993 Quarterly TLD Results 53

t 0

0 0

FIG 9.2 Environmental TLD comparison - Pre - operational vs 1993 35 30

~~25 Q

> 20 E

P) 15 0

CLK o

10 PRE-OP (1 984-1 985)

~ 1993AVG CONTROL TLD LOCATION TRANSIT CONTROL TLD 1

2 3

4 5

6 7

8 9 1011 12131415161718192021 2223242526272829 30 31 3233 3435 3637 38394041 42434445 TLD NUMSER 54

'I 0

"A;a I

~O if'

'I 10.0Land Use Census 10.1 Introduction In accordance with the PVNGS ODCM Section 6.2, the annual Land Use Census was performed within a fivemile radius ofthe mid-line'ofUnit 2 containment inFebruary and March, 1994.

Observations were made in each:of the 16 meteorological sectors to determine the nearest milking anunals,,residences, and gardens ofgreater than 500 square feet. This census was completed by driving the roads and speaking with residents, withina fivemile radius ofPVNGS.

The results ofthe Land Use Census are. presented in Table 10.1, and discussed below. The, directions and distances listed are in sectors and miles &omthe Unit 2 containment. The mileage was estimated fiom map positions, ofeach location. 'Unless'otherwise stated,.the. actual location is.the;same as stated in the 1992 AREOR 10.2 Census Results 10.2.1 Nearest Resident There were three changes in the nearest resident status noted in the 1993 census. Residents were located nearer to the plant in the N, NNE and ESB sectors. These changes are noted on Table 10.1 There were no milkingariimals located in the Qve mile radius in the 1993 census.

10.2.3 Ve etable Gardens There were no changes in garden locations as a result ofthe 1993 census.

10.3 Conclusion Nearest resident status changed for,the N, NNE and ESE sectors. No changes were made to any ofthe sampling locations as a results ofthe 1993 Land Use Census.

55

I

'P+w 0

il

TABLE10.1 1993 LANDUSE CENSUS (Distances and directions are relative to Unit 2 in miles)

SECTOR NEAREST RESIDENT NEAREST GARDEN NEAREST COW NEAREST GOAT CHANGED LOCATION N

'E SSE SSW SW WSW W

1.77 0 1.62 8 2.10 2.80 2.89 3.70 9 4.31 4.37 4.28 NONE 2.65 NONE NONE NONE 4.08 2.51 NONE NONE NONE 2.85 NONE NONE NONE NONE NONE NONE 3.14 NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE

'ONE NONE NONE NONE NONE NONE NEAREST RESIDENT NEAREST RESIDENT NONE NONE NONE NEAREST RESIDENT NONE NONE NONE NONE NONE NONE NONE

'ONE NONE NONE NOTES:

0 Previous nearest resident was 1.83 miles.

6 Previous nearest resident was 1.66 miles.

6 Previous nearest resident was 3.78 miles.

56

)

~,

~~

0 A

g

11.0 Summa and Conclusions

~

The conclusions'are based on a review of the radioassay results and background gamma radiation measurements for the 1993,.calendar year.

The radioassay conclusions, are:.based on observations of5ssion product radionuclides and do not include observations ofnaturally occurring radionuclides such as the uranium or thorium'series, C-14, or K-40.

A sununary of all.sample'results for 1993 is.presented. in Table.-ll.l.. 'With the.exception;of,onwite sudace,water;and'ssociated sludge, all sample assays presented in the annual report reveal no detectable man-made radioactivity which can be attributed to PVNGS;, 1-131 concentrations in,the. Reservoir,,Cooling, Towers and Evaporation Ponds are the result of off-site sources and appear in the eQlucnt sewage. from Phoenix.. The levels of 1-131 detected. in these, locations are consistent withlevels identified in previous years.

Natural background radiation is consistent, with:measurements reported in previous prewperational: and'perational radiological environmental monitoring program annual reports. [2]

57

~ C

TASLE 11.1 ENVIRONMENTALRADIOLOGICALMONITORINGPROGRAM ANNUAL

SUMMARY

Palo Verde Nuclear Generating Station Maricopa County, Arizona Docket Nos. STN 50-528/529/530 Calendar Year 1993 Medium or Pathway Sampled (unit of measurement) hir Particulates (pCi/m')

hir Radioiodino Cl/m Bcoadlcaf Vegetation C'wet

'ype and (fotal Number of hnalyscs Pc cformcd)

Gcoss Beta (547)

Gamma Spec Cocnpositcs 44 Radioiodine (547)

Gamma Spec (21) hH Indicator Locations Mean (a)

Range 0.027, (506/506) 0.009 - 0.059 Location With Highest hnnual Mean Site //35 8 miles 3304 0.028 (52/52) 0.01 - 0.056 Nh Nh Nh Namo Mean (a)

Distance de Range Direction Control Locations Mean (a)

Range 0.027 (41/41) 0.010 - 0.054 Number of Non-coutinc Reported Measure-ments 0.

Drinking Water (pCi/L)

Groundwater (pCi/L)

Milk (pCi/L)

Sucfsco Water (pCi/L)

Gross Beta (48)

Ganuna Spec (48)

Tritium (16)

Gamma Spec (6)

Tritium Gacnma Spec 58 I-131 (57)

Tritium (12)

Gamcna Spec I-131 5.2 (17/48) 2.3 - 18.3 498 (2/16) 496 -500 585 (I/6) 585 (LLD 0.48 (8/46) 037- 0.7 864 (7/12) 552-2289 17 (8/36) 4-19 Sito f49 2 miles 134 Nh Sito f46 9 miles 325'h Site f57 onslto 90'h Sito f54 17 miles 90'ite f63 Onsitc 1804 Site l60 Onsito 6r 13 (2/9) 7.7-183 500 (1/4) 500 585 (1/6) 585 0.7 (1/12) 0.7 1626 (4/4) 959 -2289 11.6 (3/12) 5-19 Nh Nh Nh Nh 0.73 (1/11) 0.73 Nh Nh (a) Mean and range are based upon detectable measurements only. Fraction of detectable nieasurements at specified locations is indicated in parentheses.

NOTE: Miscellaneous samples which are not indicated on Table 6% of the ODCM axe not included on this table.

58

I't t'

- jP 0

r>>

Wp 0

12.0 References 1.;Pre~rational Radiological MonitoringProgram, Summa@ Report 1979-1985 2.

'1985 - 1990 Annual, Reports, Palo Verde, Nuclear Generating Station's Radiological Environmental-Operational MonitoringProgram.

3.'alo Verde Nuclear, Generating Station Technical Specifications.

4. 'OQsite Dose Calcuhtion Manual; PVNGS,Units 1, 2, and 3.

'5. 'Regulator Guide 4.8, Environmental Technical Specifications forNuclear Power Plants.

6.

Branch Technical Position, Revision 1, November 1979.

59

Hl I

,t4 8 C'

if'

'lp APPENDIX A - Corrections to 1992 AREOR

~ << ~*The followiag pages are corrections: to;information,previously. reported in the. 1992:Annual'Radiological Environmental Operating Report.

I 60

0 0

VW l

i~

WV 0

TABLE11.1 (1992 revised)

ENVIRONMENTALRADIOLOGICALMONlTORING,PROGRAMANNUAL

SUMMARY

Palo Verde Nuclear Generating Station Maricopa County, Arizona Docket Nos. STN 50-528/529/530 Calendar Year 1992 Medium or Pathway Sampled (unit of mcasuremcat)

Type aad @otal Number of Analyses Performed)

AllIndicator.-

Locatioas

'Mean (a)

Rango Location With Highest Annual Mean Nemo Mean (a)

Distaneo &,

Range Direction Control

~

'Locations Mean (a),

Range

,.'Number'of Noa-mutinc

. Reported Measurem-entss AirPatticuhLtcs (pCi/m')

Gmss Beta (551)

Gamma Speo Composites.

44 0.025 QP~/49 0.000'-0.065 Site f21 3 autos lgty'h 0.027 (S2/$ 2) 0.008 - O.OS3 0.024

($2/$2) 0.005 - 0.053 Air Radioiodine Radioiodino, (551)

Ci/m Nh Bmadlcaf Vegetation Ci

-wet Drinking Water (pCi/L)

Gmundwatcr (pCi/L)

Milk (pCi/L)

Gaauna Spec (21)

Gross Beta (48)

Gamma Spec 48 Tritium (16)

Gamma Spec (8)

Tritium (8)

Gamma Spec

($9)

I-131 (59) 4.7 (24/4S) 1.7-113 (LLD

'44(IQQ 644 649 (1/8) 649 1.6~

1.2- +4 Nh Site f48 5 miles 190'A Site f46 9 miles 325'h Site gSS on>>its 40'h Sito gal Q miles 75>>

53 (7/12) 3-113 644 (I/~

649 (1/8) 649

~4~/2 Lk Nh Nh Nh Nh Nh 61

qh

8

-4kC, tt l

I 4 O 4

~O

TABLE11.1 0

A IOLOGIC LMO 0

GP OGRAM con 'ed Medium or Pathway Sampled (unit of measurement)

Typo and g'otal Numher of Analyses Pcrformcd) hll Indicator Locations Mean (a)

"Rango Location With Highest

,Annual Mean Name Mean (a)

Distance A Range

'irection Mean (a)

Rango Numhcr of Non-routine Reported Measure-ments Surfaco Water (pCi/L)

Tritiunl (11)

Gamma 'Spec I-131 1

864 (6/11) 569 - 1237 17'(10/31) 7-3&

Site $59 Onsite 180'ite 1t59 Onsite180'76 (3/3) 569'- 1237 26 (4/7) 11-38 Nh Nh (a) Mean and range are based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses.

'NOTE: Miscellaneous samples which are not indicated on Table 6A of the ODCM are not included on this table.

62'

Qg 0

i~

Wp J

p P

Pyl l~'

Comparison of Pre-Operational Soil Activity(Cs-137) with Onsite Sediment 250 200 150 O

100 50 0

Pre-Op. Soil Study (1976-onsite avg.)

Pre-Op. Soil Study (1984-onsite avg.)

Sedimentation Basin 2 - 1990 Unit 2 Cooling Towers - 1991 Sedimentation Basin 2-1992 63

fb H

J 4l

!I

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