ML20247A992

Environ Measurement Verification of Radioactivity & Radiation Levels in Environ of Commission-Licensed Activities in State of or & Selected by Commission

ML20247A992
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	12/31/1987
From:	Martin S, Paris R, Toombs G OREGON, STATE OF
To:	NRC
Shared Package
ML20247A988	List: ML20247A982 ML20247A992
References
CON-NRC-32-83-685 NUDOCS 8905230348
Download: ML20247A992 (35)

Text

_ -

._g . - - - - _ _ . _ - . _ _ . _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ - _

e. ..4

~O * . . s.

(- ,.

y ENVIRONMENTAL MEASUREMENT VERIFICATION OF

' RADIOACTIVITY AND RADIATION LEVELS IN THE ENVIRONMENT OF COMMISSION LICENSED ACTIVITIES LOCATED WITHIN THE STATE OF

. OREGON AND SELECTED BY THE COMMISSION STATE OF OREGON 1987

- Prepared for U.S. Nuclear Regulatory Commission By Oregon State Health Division b

~

Radiation Control Section The work upon which this publication is based was performed pursuant to Contract No. NRC-32-83-685, Modification No. 6 between the Oregon State Health Division and U.S. Nuclear Regulatory Commission.

Prepared by: k

'SdviaMartin, Chemist Environmental Radiation Surveillance Program Reviewed by: >

George Ll Toombs, Supervisor l

Environmental Radiation Surveillance Program i

a [ -

Approved by: du &* OtAA/I '

RayD.P/ris, Manager Radiation Control Program 8

.. 8905230348 DR 890512 p ADOCK 05000344 PDC

J t, ,

4

(

~

r

. ABSTRACT This report presents information and data from the collection and-analysis of samples by the Oregon State Health Division as required under Nuclear Regulatory Commission Contract No. NRC-32-83-685, Modification No. 6. This work duplicates certain parts of the environmental monitoring activities of the Trojan Nuclear Plant for the purpose of verifying the surveillance data from Licensee's program.

Comparisons of data collected in the environs of this facility are made

. , with similar data obtained from the licensee's environmental radiation surveillance program report No. pGE-1006-87.

. It should be noted that the elevated levels of radioactivity observed during 1986 from the Chernobyl Nuclear Power Plant in the Ukraine, U.S.S.R., were observed to decrease to below detectable levels in 1987.

As in the past, radioactivity levels due to the operation of the Trojan Nuclear Plant remained below the Reporting Levels of the Trojan Radiological Technical Specifications.

When detectable concentrations of radionuclides or radioactivity were observed in the media sampled, comparability was observed in most cases.

8

, i i

i

b l.1 .

y ..

TABLE OF CONTENTS Pa9e ABSTRACT...................................-...................... i 3

1.0 INTRODUCTION

............................... .........f...... 1

+

2.0 SAMPLING PR00 RAM........................................... 3

. 2.1 Airborne Exposure Pathway Sampling.................... 3 2.2 Waterborne Exposure' Pathway Sampling................. 3, 2.3 Ingestion Pathway Sampling........................... 3 2.4 Aquatic Sediment..................................... 4 3.0 ANALYTICAL PROCEDURES...................................... 4 3.1 ' Gross Beta Determinations on Air Particulate....... 4 3.2 Tritium in Water..................................... 4 3.3 Gamma Spectrometry................................... 4 3.4 Iodine-131 in Milk.................................... 5 3.5 References.for Analytical Procedures................. 5 4.0 QUALITY ASSURANCE.......................................... 6 4.1- EPA Cross Checks..................................... 6 4.2 Technical Review..................................... 6 4.3. Traceability to'NBS.................................. 6

. 4.4' Detection Capabilities for Environmental Sample Analyses............................................. '7 4.5 Counting Statistics.................................. 7 5.0 DISCUSSION OF RESULTS...................................... 8 5.1 Scope and Objectives.................................

8

., 5.2 Airborne Pathway....................... ............. 9 5.3 Waterborne Pathway................................... 12 5.4 Ingestion Pathway.................................... 12 6.0 GL0SSARY................................................... 13 7.0 APPENDIX.................................................... 15 1.

t- .

- 'L 1 9

l

1.0 INTRODUCTION

This cooperative program for measuring concentrations of radioactivity and radiation levels in the envirens of the Trojan Nuclear Plant is

' accomplished through NRC Contract'No. NRC-32-83-685, Modification No. 6,.

between the United States Nuclear Regulatory Commission and Oregon State Health Division. The amount _provided by the Nuclear Regulatory Commission under this cooperative agreement for the 1987 period covered by this report was $12,600.00. The remaining funds are provided by the Oregon State Health Division. -

The principal Nuclear Regulatory Commission objective of this cooperative program is:

To provide reasonable assurance that environmental measurements made by the licensee under the Nuclear Regulatory Commission requirements are valid.

The full scope of this work is defined in Attachments 1-4 of this contract.

l t

4 e

m 0

.. ,e

, .' 2 SAH_AG _OCA ONS NRC- S" ATE OFOGEON n0;10OhlTDU6i Roc 2AA crTY or PAltflEnte -

3

\

"\)

TRo7AH rioRm sus eeurmy e '

peJAN %T Si *CetVMBih RNER

},. AT .. PLANT CWAlt-SWLc41A11tdo g

.s #

. A 1.0 CATION

. \

\.

PGE :I CODE

\l particulate & charecal Trojan 1-1 "h

Portland (StateOfficeBuilding) 19 \ - .

er A CityofSt.Helens(Domestic) 66 City of Rainier (Domestic)  : t-2 Columbia River 0 Plant Outfall i ,1, CR-3 g

' rant C1TV oF ST.WIR.ER e Columbia River 0 Plant Outfall CR-3

/

j Shiloh Basin (milk-Winans Farm) 68 L

(

Columbia River 9 Plant Outfall (fish) CR-3

• i Trojan florth Site Boundary (vegetables) 1-1 ."

u

~'

e Tttruwt> can,ee.mst-uows\ t

_ _ - _ _ _ _ _ - - - ~

. j 3

j 2.0 SAMPLE COLLECTIO! AND RECE!VING Samples were chosen for verification of exposure pathways. All samples were split between p0E (Licensee) and Oregon State Health Division (Contractor) [See Attac hment 1). .

2.1 Airborne Expostre pathway Sampling Air particulate and iadiciodine comparison sampling was performed for a one-week sampling 1.eriod once per month using a sampler identical to that used by the Liednsee. The samples were taken with low-volume air sampling devices which are adjacent to the units used by the Licensee

, at Trojan North Site Boundary (pGE-1-I) and portland State Office Building (pGE-19). The samplers are calibrated (traceable to NBS) for a flow rate of I cfm irrespective of filter loading during the weekly y collection intervals. (The periods of sampling coincided with the Licensee's sampling period).

The sampler pump, metering device, and timer are contained in a weather proof case. A glass fiber filter for air particulate -

collection and charcoal cartridge for radioiodine collection are located in a holder at the sampler inlet which is parallel to and

, approximately 1 meter above the ground. After the sampling period, the sample holder was removed from the sampler, appropriate field data was recorded, and samples were submitted for analysis.

2.2 Waterborne Exposure pathway sampling Two samples of drinking water, both of Columbia River origin, were

• composited daily and collected and split monthly. The upstream control was from St. Helens, Oregon water supply and the downstream water supply was Rainier water supply, originating in the immediate vicinity of the discharge area.

2.3 Ingestion Exposure pathway Sampling 2.3.1 Milk A milk sample was collected monthly by p0E personnel at the Winans dairy farm in Shiloh Basin (p0E-68).

2.3.2 A_quatic Animals Routine aquatic animal sampling for this comparison was carried out on an annual basis by the Licensee using a collection permit issued by the State of Oregon, Department of Wildlife. Samples from the b

i .

. 4 Columbia River at Plant Outfall (PGE-CR-3) consisted of both indigenous (carp) and anadromous species of fish, and were acquired by seining, netting, or trapping. .These species are commercially or.recreac'ionally important.

2.3.3 Food Products c* , One leafy green vegetable sample was collected by PGE near the North site Boundary (1-I) during summer months. The sample was split between the Licensee and contractor.

2.4 Aquatic Sediment one . sediment sample was collected by tha Licensee using a Peterson Dredge from a boat in the Columbia River at Plant Outfall (PGE-CR-3).

The sample was split between the contractor and Licensee.

3.0 ANALYTICAL PROCEDURES 3.1 Gross Beta on Air Particulate

• Atmospheric particulate matter at a designated field location was accumulated for a one-week period on a glass . fiber filter using a low-volume air. sampler at'a collecting rate of one cubic foot-per minute.

" The particulate matter contained on the filter was counted for beta activity in a low-background counting system after a three-day period 1

allowing short-lived naturally occurring nuclides to decay.

. 3.2 Tritium in Water An aliquot.of sample was pipetted into a low-background polyethylene counting vial, combined with liquid scintillation solution, and counted a minimum of 300 minutes in a temperature-controlled liquid scintillation spectrometer.

3!3 Gamma Spectrometry Samples, after preparation to achieve a standard counting geometry, were analyzed using a lithium drifted germanium (GeLi) detector incorporated with a computer-based multichannel analyrer system.

3.3.1 Radioiodine in Air An activated charcoal cartridge positioned behind the particulate filter in a low-volume air sempler, was used to absorb airborne 4

et'

" . . 5 4

radioiodine, if present. The charcoal, after being transferred to a 15 mm x 10 mm plastic petri dish, was analyzed for iodine-131 activity by gamma spectrometry.

3.3.2 All other Media Including _ Water-After preparation to achieve a standard counting geometry, the

. samples were analyzed for radionuclides activity by gamma spectrometry.

3.4 .odine-131 in Milk 1 .resh unpreserved milk' sample was applied to an anion exchange resin to isolate radioiodine, eluted, extracted with carbon tetrachloride, precipitated as palladous iodide and counted for beta activity in a-low-background proportional counter.

. 3.5 References for Analytical Procedures

1. American Public Health Association, American Water Works Association and Water Pollution Control Federation (1971):

Standard Methods for the Examination of Water and Wastewater.

Thirteenth edition, pp. 583-632; 12th edition, pp. 325-352.

APHA, 1740 Broadway, New York, New York 10019.

2. Department of Health, Education and Welfare, Public Health

• Service Radioassay Procedures for Envi_tQngental Samples.

National Center for Radiological Health (1967) Sec. 1, pp.36-115.

3. Atomic Energy Commission: Regulatory Guide 4.3 (September 1973).

4. Health and Safety Laboratory, Atomic Energy Commission: HASL Ergeedures Manual (issued annually when AEC existed) HASL, 376 Hudson Street, New York, New York 10014.

5. National Environmental Research Center, Environmental Protection Agency: Handbook of Radiochemical Analytical Methods. Program Element lHA 325. Office of Research and Development, Las Vegan Nevada 89114.

6. National Bureau of Standards, Handbook 80, A Manual of Radioactivity Prqcedures. NCRP Report No. 28 (1961) pp. 26-28.

4

s. . .,

'. 6 4.0 QUALITY ASSURANCE Quality Assurance (QA) is a plan which "... prescribes the technical and administrative controls required to ensure valid analytical results, maximum productivity, and cost control."1 In addition,."...the.

objectives of the QA plan are validity, traceability, and reproducibility of results reported...; representativeness, compatibility, completeness, accuracy, and precision." The activities described below are designed to control the quality of sample handling counting equipment performance, radiochemical analysis, and data management.

4.1 EPA Interlaboratory Cross Check Program The Environmental Radiation Surveillance Laboratory participates in the EPA Interlaboratory Cross check Program, a quality assurance intercomparison study. (The results of the laboratories' performance for calendar year 1987 are listed in 8.0).

4.2 Technical Review A three-agency committee known as the Trojan Environmental Radiation Review Committee (TERRC) was established in 1972 to provide a formal means for information exchange among the States of Oregon and Washington and PGE Environmental Ser'Imes. This committee was involved with reviewing data from all Trojan environmental monitoring l

activities for consistency and quality assurance. Currently the.

functions of this committee have been taken over by a Quality Assurance Task Force established by the State of F -hington.

4.3 Traceability to NBS

)

l All instruments and procedures are used in analyses which require

. radionuclides standards for calibration purposes to verify instrument ef ficiency and stability, vital in producing reliable results.

Standards used to determine counting efficiencies were prepared from solution standards obtained from the U.S. EPA Environmental Monitoring and Support Laboratories' Quality Assurance Branch in Las Vegas, Nevada. Certification of these solutions is traceable to the National Bureau of Standards.

IRichard A. Beatty, Argonne National Laboratory, American Laboratory, p. 6, 8, August 1982.

t, .

3 ..

p. .: .,

.7 a:

u 4.4 Detection Capabilities for Environmental Sample Analyses A degree of uncertainty is present in any measurement' system. In the area of nuclear radiation detection, much work has been done through the.use of statistics to define the uncertaintyfassociated with a.

counting determination. The highest degree of uncertainty exists when defining the same activity near the background level. The lower limit of detection (LLD) of~ sample activity over background is stated in

. HASL-3002 by Pasternack and Harley:

"The smallest amount of sample activity that will yield a net count for which there is confidence at a predetermined level that activity.is present."

If the background and sample gross activity are very close numerically, the LLD in dpm at the 95% confidence level (see counting _

statistics)

= 4.66 , BKG cts (Bk.1 cts) time counted S (Counter eff)(Chem yield)

In this report, any analysis reported as "less than" (<) a certain activity is one in which there was no activity observed above the stated LLD. '

4.5 Counting Statistics

~

In low-level environmental radiation counting the poisson distribution is used to describe a discrete variable (detectable counts). The standard deviation (of the mean), s, of this distribution is expressed) s gj N A

. 2 HASL 300 p. D-08-01 f f.

3HASL 300 p. A-06-02.ff.

6

7 I. -

(; -*.

I Where N is the number of counts obtained the standard deviation, s, for a' net sample counting rate is:

L snet rate : Bko rate + sample cross countino rate Ng Bkg time counted sample gross time counted 5.0. DISCUSSION OF RESULTS 5.1 Scope and Objectives The objective of this USNRC-0SHD contract activity is verification of the Licensee's environmental radiation surveillance data. However, the stipulations of this contract and technical specification requirements placed on the utility's program prevent effective comparisons in some cases at the low levels of radioactivity observed.

The data accumulated through this U.S. Nuclear Regulatory Commission (USNRC) Oregon State Health Division (OSHD) contract are displayed in Sec. 7 (Appendix). These results are a small part of the data accumulated in the offsite environment of the Trojan Plant. Both the

' Licensee and the State of Oregon have conti?uing comprehensive surveillance programs designed to detect and Jafine changes in the radioactivity present in the environs of the Trojan Nuclear Plant.

Information concerning the Licensee's program can be obtained from the Portland General Electric Company. The Oregon Department of Energy is the information source concerning the State of Oregon Trojan radiological surveillance.

A comparison of the Licensee, Portland General Electric and the Oregon State Health Division required reporting limits are listed on page 19.

Specifically, this listing contains the PGE technical specification requirements and OSHD-NRC contract reporting limits based on HASL 300 criteria (See Attachment 2), Sec. 7.2 Detection criteria is defined in HASL 300 (rev 8/74) pp. D-08-01-02-03

, at the 95% sonfidence level. For the data listed in this report, the procedures used in the calculation of the analytical detection limits and count rate error are discussed in Section 4.4.

6

- _ _ . _ . _ _ . _ - _ _ __.____-._..______m__.____ __m_...m_______--__

1

'7,. ,

9 l* ,

5,2 Airborne Fathway ,.

5.2.1 bir particulate Small differences in the reported gross beta activity between PGE

.and OSHD were apparent'as observed during past years at both the Trojan North-Site Boundary (1-1) and the portland State Office Building roof (19) locations. -A summary.of the average, maximum and minimum air particulate values from these two stations covering the years from 1982 through 1987 are listed on page 9. The ratios

.of the' average pGE/OSHD air particulate values for this same time period are shown on page.10.

The gross beta air particulate data for 1987 were comparable to

. data from the past five years except for samples collected during the period from May 5 through May 25, 1986. Data obtained for samples collected during this period were elevated due.to fallout I

• from Chernobyl. Gross beta concentrations were at pre-chernobyl levels during 1987. Gross beta concentrations in air particulate are presented in Tables 7.5.1 and 7.5.2.

4 I

i f

l 1 . i e

_ _ _ _ _ _ . _ _ _ _ . _ .____-.__..m_____ _ _ _ _ . _ - _ _ _ _ _ _ _ _

5 0 8 3 1 6 E 0 3 1 0 3 1 G 0 0 0 0 0 0 P

0 0 0 0 0 0 7

8 9

1 0 0 0 2 3 9 D 1 1 1 0 1 0 H 0 0 0 0 0 0 S

O 0 0 0 0 0 0 8 5 6 5 2 5 E 0 6 4 0 4 4 G 0 2 0 0 2 0 P

6 0 0 0 0 0 0 8

9 1

E D 3 4 9 6 1 4 T H 0 0 1 0 1 3 A S 0 1 0 0 2 0 L O U 0 0 0 0 0 0 C

I 9 T1 R 5 1 1 6 3 2 AD E 0 2 1 0 2 0 PN G 0 0 1 0 0 1 A P R 7 5 0 0 0 0 0 0 I I 8 8 A - 9 9 l1 1 2 D 2 8 6 5 5 2 GSH H 0 0 2 0 1 4 ANG S 0 0 0 0 0 0 ROU O EI O VTR AAH DS N

TT 2 E 0

7 0

0 3

1 7

0 2

0 6

0 0

4 1

0 3

2 AE8 G 0 0 0 0 0 0 G9 P 2 MP1 U

4 8

0 0 0 0 0 0 &

HMS 9 I OR 1 XRA D 1 4 3 1 5 1

, AFE H 0 0 1 0 0 1 M Y S 0 0 0 0 0 0 f S O

,EE 0 0 0 0 0 0 MI H UTT MI I VR 4 1 6 4 1 8 NI O E 0 2 5 0 2 5

' I TF C 0 0 0 0 0 0 MC P A 3 0 0 0 0 0 0 F 8 ~

OA 9 T 1 1 5 2 2 9 YE D 0 0 1 0 0 6 RB H 0 0 0 0 0 2 A S 0 M O 0 0 0 0 0 M < 0 U

S 5 8 5 5 3 3 2

8 E

G P

1 0

0 2

0 0

5 0

0 1

0 0

3 0

0 7

0 0

_ 9 1 2 2

6 0 D 1 1 2 1 1 3 H 0 0 0 0 0 0 S

O 0 0 0 0 0 0

_ N X G N X G I A V I A V M M A M M A C I 9

_ O - 1 L 1 h L

.6 j

11 1

RATIO OF AVERAGE PGE/OSHD AIR PARTICULATE VALUES FOR YEARS 1983-1987 1983 1984 1985 1986 1987 1-I 4.2 3.2 2.6 2.5 1.8 .

. 19. 2.3 2.8 1.5 1.3 1.8 Comparison of EPA Quality Assurance Program result.s between PGE/0SHD for gross beta analysis on air particulate (in '

PCi/ sample).

c KNOWN PGE OSHD PGE/OSHD' RATIO April'1987 43.0 1 5.0 47 0 +1.3 . 50 + 1.0 0.9 Since'1982, PGE air particulate gross beta analyses, on the

. average, have been greater than the OSHD results by a-factor of about two. However, .the ratio of the air particulate results f rom analyses of samples connected with the EPA Quality Assurance Program by the respective laboratories listed above, did not change

. significantly.

Slightly different sampling and collection procedures may account for the difference in values as noted. Counting procedure including lag time between sample removal and counting used by the F different analytical facilities are factors contributing to the observed differences.

From the information provided in the PGE report, it appears that

'the Contractor laboratory used by the utility does not participate in the intercomparisons as extensively as the Oregon State Health

. Division. Therefore, comparisons are limited.

_ _ . . . _ _ _ _ _ _ ._.._____..______.___.___-_____m.__.______. __

7_

i L . .

- 12 l

l i

5.2.2 Fadiciodine Radiciodine levels were below the detectable level of 0.1 pCi/m3  !

b for all reporting periods. The data for radiciodine concentrations in air particulate are listed in tables 7.5.1 and 7.5.2. (

]

The concentrations of gamma-emitting radionuclides in air

, particulate quarterly composite samples are listed in 7.5.3. It should be noted that all values were at, or below the specified minimum detection levels. Since these gamma isotopic analyses are j not required under the Licensee's technical specifications i comparisons could not be made with similar data from the PGE Trojan

' program.

5.3 Waterborne 5.3.1 Surface Water A comparison of waterborne radioactivity and specific radionuclides in St. Helens and Rainier drinking water is presented in 7.6. It

, should be noted at the low concentrations of activity present (below detectable levels) and detection limit differences between the PGE and OSHD-NRC programs prevent an evaluation involving data comparability on these samples.

5.3.2 Sediment Gamma isotopic radionuclides, specifically, cesium-137 and cobalt-60 in the Columbia River sediment sample detectable in 1986 from the Chernobyl accident were not observed by either program in 1987.

5.4 Ingestion 5.4.1 Milk A comparison of specific radionuclides, which are known to accumulate in milk and of concern from a public health standpoint, are listed in 7.7. Again, considering detection limits and the low concentrations present, effective comparisons for all radionuclides analyzed for cannot be made.

5.4.2 Eish The samples of aquatic animals collected frem the Columbia River for analysis in conntetion with this comparative study are listed

e. ,

o

. 13 i

l in 7.8. The radionuclides detected by the OSHD using gamma spectrometry are listed. The levels observed, specifically gamma  :

emitters, were observed below reportable levels by both programs. .

5.4.3 Veaetables The vegetables split with the Licensee along with the analytical data are listed in 7.8. The gamma emitters in these samples were also observed below reportable levels by both programs.

6.0 GLOSSARY OF TERHS USED IN DATA TABLES GROSLEETA - An analytical technique (non-specific f or any particular beta-emitting radionuclides) to detect beta particles.

CHARCQAk.CARTAIDgE - A sampling device containing charcoal for the selective collection of gaseous elements in an airstream.

01ASA.U BER_ULTER - A sampling device used to collect particulate material in an airstream.

RADIQ10DIlfE - A radioactive isotope of iodine (atomic wt. 131) decaying through beta and gamma emissions, with a half-life of 8.1 days, collected on charcoal. ,

PJCQCUBLE_(pcil - A unit of radioactivity. 1 picoeurie equals 10-12 Curies, or one trillionth of a curie.

HIT WEIOHT - A unit of reporting associated with biota specifically for samples analyzed in their normal hydrated state; e.g., animal tissue or food.

DELHEIGHT - A unit of reporting which is associated with samples i analyzed after a drying process to remove water; e.g., sediment and vegetation.

GNiliA_ISQIQPICJCT1YlTI - An analytical technique f or detecting gamma photons emitted by a radionuclides. This technique is specific for each gamma-emitting nuclide.

NAu RS J R - Terms used to indicate no analysis (NA) on a particular sample; no sample was received (NS) due to a sampling anomaly; or the analysis was not required (NR) by the contract.

l .. - - - - - - --_ a

? e.

s:

14

{<) "LESLTHAN" Indicates that the activity present in a sample is l

lower than (less than) the Analytical Detection Limit. (LLD, see p. 8).

. ANALYTICAL DifECTION LIMIT - See Page 8. '

IRAggAgILiff - A' National Bureau of Standards calibration. sequence insuring acc tracy of equipment and analyses.

QUALITLASSUEMCE - The docu::.ented laboratory plan for providing reliable data.

+

o e

O

_.__m- ___.. _ _ ______m..m____ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ w

F. .

+ _. . . ...

?* e .

4 :

p-15 f

l.

j :.

l 7.0 APPENDIX Page 7.1 Contractual Requirements: Attachment 1......... ........ 16 7.2 Contractual Requirements: Attachment 2.................. 18 7.3 Contractual Requirements: Attachment 3.................. 19 7.4' Contractual Requirements: Attachment 4.................. 2 01 7.5 Comparison of OSHD and PGE Reporting Levels.............. 21

~

7.5.1 Comparison of Airborne Particulate Gross Beta and

< Radioiodine Activity, North site. Boundary (Location 1-1)...................................... 22 7.5.2 Comparison of Airborne Particulate Gross Beta and Radioiodine Activity, Portland (Location 19)......... 23 7.5.3 Comparison of Air Particulate--Quarterly Composite....... 24 7.6 Comparison of Waterborne Radioactivity (Drinking Water)..................................... 25 7.7 Comparison of Radionuclides in Hilk...................... 26 7.8 Comparison of Radionuclides in Food...................... 27 7.9' Comparison of Radionuclides in Shoreline Sediment........ 28 EPA Interlaboratory Cross Check 8.0 Results.................. 29 t

e 4

---___.----___-___--_.._-__--____n___-___.___ _____._ - . , _

j!ji i l' i l

t_ e y - y t eol igsr s

i y vnie .s c ia t y s

_ n that l es ccma at m.

i mu

_ ui a 1 ni d s qs oraq 3 ny ey i eg

.at al 1

rl dt s - cr i a Fa al ri I it cn n rios p i a p

fA ff y r od o a l o t n .

oe f t gea f oay t n eo ent n s l oi sd p biia e i yr y ws z l e i o T sooc sl pi y aht ac i

l mt r mi ol mp r ooo a

n mna aou md Gf ct A Gmq aa Gr' G n N o s y I

y cna h l R e ot h O c rvhri .

t T n eet pw h n I e l snp t o NS d u p oas n m ~

OT MN nq ae mem an eo .

n o A r m e .

sohk sa l

- NL gF cait r p .

OP n f ramra e m I in ooe ad p a .

TR l o f op s AE pi n dt m e CW I O mt ac oyo o 's l p e il idce t FP Se t sre e m i y l I l aueres a s l RR l ropit n s o h T EA o eu uae p t N VE C p n y qi c e m n E L 0iaeri n o o M LC

• td rpl o c K AU M C CN A I l T GD d t - eo e T

A ON nn eaknr tl - .

LU oud l t not iaaQ OO i on o hari n hsuc/

I R s t raf r .

ti ord o t doX DA e ag o . t s i d(dnc ifil A l c n r n e wem ,m a wf v t RM pn odoye o t m LR A mo ai l eitl tti p c a t mea) a t oies dhe i igeye AG TO St a

maamm ol ria m

o l

u c

l pmat pt rrl r i enth l hi pt g

ti NR f.c r ut xs r i sohsps s rah EP oo f cno f t rcnup o M L l ere r ,f swsu ,t a l g N

O r eacpe e a e io e man ed l cn s l . p l ,dd rt . l ,r mi R b n p oen pn pe ean I ma u

mhcse mo s meftt o peaiv mef na V

N N ag oc ai a asosaei as ah E

sil l i st a e sn ewl t sny h eel ear pa erkn e v - ec m eceagmc ecil o nf enf no a nir enao niaii Ool io Ol S Ol anisl Old mt y

ae wl s hp e t m t aa a e  :

PS l n E  :

u i N e N er E c d Rc O r o Ni o Oa I u/ Rt i Bf Tk sd on O r B a c R r Sl pa i Eu Ei RP d TS GM x I a A N E A R W I m

1 1 1 2 33 _

7 2 2 22

b b f i y i i ea s c d d ne y n e eil l es d a ui f non n qs o oie ,

a ey ce rl c cir id g c

F a i i n p pa p f A o oR n o o t t o . t f o . o e o eo p

ss s . sl s i n i nib . i y o osa T ai aiyt a nt mtl mr ag e m mr m ao aone a G p G pav G y t c s n e e v d u nq n r i a ae h r r gF o f n y o

i n l o l e pi l m mt a i ac u t y S e n . l l nn e l l ao h a o i s t u .

C ma n 0 ee t n 8 ss A A 9 1

a h ,

c s t ne 3

- rti ne aih 2 i ashit r t s

h cy t rl e hl eew t anh ra s osm erf h y

a e i el ng i p gaewdl ao t M l wmair winiet ebf i

- pn mn a cwh r at ga a w n mo ai t oosh i ciec t no i i r e awnrt re aaeor t o

St l ti s l pp rgh yyl h g a i n a paaci t nb pcen l e f c s eed s s a svee p h oo f r p ft g ddi dt s o L ,ocsf s o c n m eid y r a C r e e o e uiot u f ai e ed l ,rt l .d vr a q n a gd l y bn pe ny peoaf gi ee e pe r ma u

mer at merh rr il el em me r asoti . asp b t m . as a N sney r nt sn t orh nait sn L oin ed n iceev n e ecl pci ocoiQ iveiea ec .

nil mio wioo/sh ar rhl ni r Ol aiv p Tl t pXi wh gpt p ol D y

y b ae s s m wl e t o d h p t c r e t m a u f z aa r d e i PS b o t n r r e r ni o er ot P el h r o a/ h e r

d me i r t

u sd sv o d o a on in o eh pa FI F SS s x a E

e g

2 3 n

. a 1 3 3 4 h C

7 2 2 2

• _ ii !lll

e o dioat m . tf( a i o 0 i eae h dk 5 dbvbit e/ 1 a r( r Si rl e or cp l s ii fibrrn e

( owooen ' i t a ntkrsm oanp o s) iha p a t t ttl a ce a b ah uw r) n c tdaanu do . nn as ro 0 0 eut s coaasn Pk 6 6

/ nrh a i.

S di ogtd

, E S

oc op ck cgnoe etd Y F( tsbifaninm r L

A e d edo N l mud nf A ) l el .ar 1 at cs e E k/ m s ni m p L b l i 1 5 5 syo e P i C 1 1 scDt e M ,

MD( e L sb A a h e yL y t vl S sd

. ) oee l L D sbsht u A L ) aal t no T L .

t ( a eh N ( t ye ,

ft ms E arw st ae

. M N et nnfhrs 2 N O Ml ,

0 0 0 ouot ue .

O I ua 3 6 6 0

3 i o sss T R T ,~ o k t c yd a y n N I C hP/

1 2 2 1 a t eel o E V E s i cti zmai M N T i rc i eli nt H E E Fop f ninaAi bg C D ( i d A R caaof n T O F e bco pd o e

.o T F O t c A

S T t e sl ep r r yt n e 'e E I a ei eimn I M sy%bl ei T I l

u e 5 i rt I L c h dbuu

. L i ) tl yl aqo I R t s) 2 2 l l upar B E ram 1

- - fi noae A W 0 0 owohcmr aG/ 0 1 1 s e P O P i A L rC 0 s't h erd C eoD x x eatth an n ( shiI tl u N r 7 1 ot w p

u O o gcd I b rey .nie T r ul tli t v C i ppi at re E A ml nnai T r e i g e ph E osbi s c D f aseaa

. ) ,abo r pre r1 e/

4 d eiparf n r "l eob t i 2 0 5 6 ac 3 1 0

3 5

1 1 0 5 5 n e- l Wp 1 1 il% rttl 3 f a5 iii

(

ei9"aiimmw d r eh ll s stt s D

~

l i ait))L e mwnttL v

• D . ecc s e s L ed saad L C L veeff e i a 7 it r t s t

• w 3 et cpeea Y e o

• o 1

• h ceehht l B C b L a Tat rtt s a 0 N , L n s *

• 6 -

• s a A s n e r I C B 2 o M F ,

Z 1 4 0 r H 4 9 8 5 3 3 4 .

7 G 3 5 5 5 9 1 1 1 a

)

ll

\

ljil ,

I J

!l)!u m% .

s -

. w=

y 7 N 8 O 9 I 1 T C

, E 1 R 3 I t D s

- c D

e e w N hh hh h h dD A tt tt t t t t o ru ru u s r s i - E oo oo o a o a -

r C NS NS S E N E e7 N _

P8 A 9 'T g1 S n I i , D t1 r -

o . -

pn

. ea -

RJ E

M A .

N I9 26 8 3 I 3 N - 1 6 6 - - -

O 1 R 1 R I

T C C A

N C

. O O I L S .

I V

I D _

3 -

H T T E -

N L L E A P M E M _

H H A C S A E T T E

- T A T A T A e e S C t t I a a N L c c -

O P i t t t i t G U l i i i l i E D p l l l p l R u p p p u p O R D S S S D S O

T I

L P

S D

E 1 L 0

2 P

M s 7 A e 9 S t a s n

Y l e A ue k t o W cn r l a

, g H ii e i r he T td t M b t r A ro a e -

5O P ai W t Pc  : r

. , R i l n e Wd O ed a o v t

. n na p i n n Sa M rR i t i e o c 3

0t 0 r l U I

D b

r i

n s /

e g

h s

d o

i d

m 4 o E i u n i o e ._

7 1P M A M I F F S i

!, l j lt'I!!i t Il'!ll'lfl lltI<

l O a n

A d

n f a o 9 1 3 2 3 1 4 l

2 2 3 .

2 t .

r o o N P

_ . l a

t N o O T -

I T

A C

O L

1 3_

l 1

2 1

1 I

' m

- u s i 9 e t s i y r l T a

4 n A

. T N

. f E o M an H sn a 4 2 2

_ C ' o. n e 2 1 1 4 A N aS T G

- T A

sa 9

. st 2 oe rB G

e t

es a r l l y u a T c o i c e t r t -

l r a n

. n p a h e o m P C m 5429 g a 3418 e S i k d h 1 r

r r O d l o s O

i i 2 e i o i A A H S M F F f

o s e

e ce t i c

, a s .

vn gran t e d S l e nero p d iSui m n l st

a e pl sa Y S p maAr 9 1 4 1 T 2 2 2 2 1 2 x ac t I f 1 E Siys L o tti I s d yi n 4 C r l lli eaam A u 7 F Lo N. o i nud H FAQA T'

'c -

i ,1 l l

?

)

yE TrG 0 NdP 0 E( 1 M

I g DK E/D -

0 SiH 5 CS 1 pO

)

t E 0 S eG 0 L wP 5 5 E D(

V O E Og L FK

/D 0 0 G iH 6 N CS 6 I pO T

R O

P E E rG 5 R eP 0 0 Kt 0 5 5 D Li 5 E I l 8 R H/ 6 I iD -

U CH 1 5 5 3 Q PS 1 1 8 E O -

R 2 3

E -

G E 0 0 0 C

P G 0 0 0 0 R 0 0 0 0 0 0 0 gP 1 1 1 1 N

D 1 1 1 HK N S/

A I i o FC N D pD 0 0 0 0 0 H H 3 t S S 1 6

2 3 6 3 n

. O O 1 2 1 e m

F e O 2 e E 0 r N G 0 g

O 3 P 1 3 A S Rm 0 I I/ 0 0 e R Ai v A CD 1 7 1 i

P pH 0 t M S 0 0 a O O 0 r C 0 0 e p

. o

) o E 5 0 5 5 5 5 5 0C 5 5 5 8 rG 0 2 2 2 2 2 2 2 2 ,

eP 0 0 Rt 1 k2 Ei o Tl ) ot A/ 0b n WiD 2 0 5 a0d e 0 5 0 0 0 5 5 i3 nm CH 3 1 3 1 3 1 1 1 1 r - ah PS 3 O eLHc t S a iASt rHBt a C(NA t

s (

S C gD D e e 7 nHEH I B F 3 a iSGS S 0 b Y s 1 L tOPO 6 N a r L

A s n e n r 1 ,

B o 5 o H F , Z Z 1 4 0 p h r H 4 9 8 5 5 3 3 4 e 7 A G 3 5 5 5 6 9 1 1 1 R

y 3 3 2 3 3 3 t

3 3 3 3 3 3 0 0 0 0 0 0 0 0 0 i 0 0 0 0 0 0 0 0 0 0 0 0 v 0 0 0 si 0 0 0 0 0 0 0 st 0 0 0 0 0 oc 1 1 1 1 1 f 1 1 s rA 1 1 1 1 s C 7 4 5 1 3 9 6 e S a 0 1 0 1 1 0 0 0 4 3 3 9 0 l E ) t 0 0 0 0 0 0 0 1 2 1 1 n U s e 0 0 0, 0 0 u L e B 0 0 0 0 0 0 0 A l 0 0 0 0 0 3 V p .

m m . /

C a i I s C R .

p T y Y C l e 1 T E k m 5 0 0 5 5 5 0 I L e u3 8 9 8 8 0 5 5 0 5 5 V 8 8 9 E e l m 2 2 2 2 2 2 2 8 8 8 8 8 0 I

w o 2 2 2 2 2 <

T L V C A e y A R n t

. E i i E N d v N E n i I

D G o td O

p c D s e 3 7 7 1 9 6 4 At I

N e t 1 1 8 5 3 4 5 1 2 1 1 O A r a 1 1 1 1 2 1 e Y n n I L r D b r r y n D R T o a e a p a u l

u g p t v c i A A R C n J F M A u e c o e d R Di O ( o M J J A S O N D o N m P i - - - - - iw D U/ t

- - - - - - - or

. N Oi c 6 0 0 4 2 9 ie TA BC p e 0 1 1 1 1 0 7

0 1 8 6 7 8 dh

- N l 1 0 0 1 0 at AA E l n b r r y n g p R LT T n o a e a p a u l

u u t v c

• PE I i C J F M A M J e c o e B S J A S O N D R d AS H e ES Ts7 LO R s8 CR O e9 UG N r1 N p E - m

. NT E AA 1 y JL 1 y t OU t i RC Ni v 0 0 0 0 0 0 TI O v si 1 1 1 1 0 0 0 1 1 1 T I i st 0 0 0 0 0 0 1 1 R Tt

• oc 0 0 0 A A c S rA 0 0 0 0 0 0 P CA E G < < < 0 0 0 s

< < < (

O U a < < s R L L 1 t e I A e l e A V h__

t B n n - u F N o O O m 3 I _. m N S r _ /

O I e _

i S V C I

R I

D I.

g e 3 0 6 0 7 8 1 3 1 p

m A n u3 6 9 0 1 1 7 P H 7 3 1 4 0 M

i l m 2 2 3 4 2 2 4 2 4 T j o 7 7 7 7 3 2 3 O L p V 3 3 0 C A m <

E a H y

s. t E ke e i T e l p v A t l e i T w. e 0 9 9 p 0 m td 7 a S

e t_ 2 1 1 m 2 1 l

p 8

1 i

l S 5

2 7

1 ce At a a m N n D n b r S y y a g p o v c O O a e a a a S u e N o e en n

G ( n J F M o M M A S N D i e E o N o R .

i -

- d s O t

- - N - - - - oi c 3 2 2 3

r iwS 1

0 - 1 0 e 9 0 or e 1 1 1 l 1 1 1 1 b 1 1 i e 5 -

l n b r i

r y n y o dh l

o a e a p a u l

u g

u p t v c at 7 _. C J F M A M e c o e R o J J A S O N D

• l 1

ll llll11llllljii)

= .

u y_ 3 3 3 3 3 3 3 3 3 3 3 3 t_ 0 0 0 0 0 0 0 0 0 0 0 0 i 0 0 0 0 0 0 0 0 0 0 0 0

, v si 0 '0 0 0 0 0 0 0 0 0 0 0 st oc s rA 1 1 1 1 1 1 1 1 + 1 1 1 s_

e 8 G 4 2 5 6 3 0 0 0 5 9 6 9 l S a 1 1 0 0 1 1 1 1 1 1 1 0 n _

E ) t 0 0 0 0 0 0 0 0 0 0 0 0 u U s e L e B 0 0 0 0 0 0 0 0 0 0 0 0 l A l p . m V /

m i C a C I s p

_ R T y 1 334 Y C l e 0 000 T E k m 5 5 5 5 5 0 5 5 5 5 5 5 000 I L e u3 8 8 8 8 8 8 8 8 8 8 8 8 0 V E e l m 2 2 2 2 2 2 2 2 2 2 2 2 < 000 I w o T L V y 111

. C A a t A R n i a592 E i v t011 E N d i e000 N E n tdB I G o ce 000 D p At s O D s e 0 4 7 1 9 6 1 8 5 0 4 5 osN> G I N e t 2 2 1 2 1 1 2 1 1 2 2 1 enoI i V

. Ob A r a n rMMA I L r D n b r r y n l g p t v c ieG D4 A

} T R C o

n J a

F e

M a

A p

M a

J u

J u

A u

S e

O c

N o

D e ds oiE O ( o iwC P

Rm-_/

D

_3m i

i t

c 3 7

0 4

2 9

4 1

8 3

7 8

- crP ie dh TA P C e 1 1 1 1 1 0 1 1 0 1 1 0 at N P l Ro -

AA LT N e n'W l C

o J

n a

b F

e M

r a

A r

p M

y a

J n

u l

J u

A g

u S

p e

t O

c N

v o

D c

e B

R ed AS 5e PEWmi ES LO CR UG N

E 8 s7 Os8 t e9 Nr1p

- x NT E y AAT JLIMy 1 1 1 1 t 0 0 0 0 OU t i 0 0 0 0 RC Ni v 0 0 0 0 0 0 0 0 T I~ Ov si 0 0 0 0 1 1 1 1 1 1 1 1 T Ii st 0 0 0 0 0 0 0 0 R Tt

• oc 1 1 +. 1 A

P Ac CA S

E G rA 9 9 2 3 0

0

(

0

'0 0

0 0

(

0

. sy sr O U a 0 0 0 1 ea R L L ) t 0 0 0 0 l n I A V

h B

e nm ue A t 0 0 0 0 n S F N o 3 O O I

m ma

/t N S r i e O I e 8 CB -

p

• S V p 8 -

I I g

e 2 7 0 9 2 4 3 6 8 2 3 1 s- 1 R D m 7 s112 A n u8 4 5 2 4 0 4 3 2 6 5 6 3 o000 P H T

i l o

m 5 5 9 0 8 9 3

7 8 6 6 2 5 3

0.

0G r000

. M l_ 3 3 3 4 3 3 3 3 3 O L p V 000 C A m yD E a tH111 H s i S vO239 E k i 01 0 T e td000 A e ce T w  ? 0 7 9 4 0 7 4 8 7 1 5 7 At 000 S t 2 2 1 2 2 1 2 1 1 2 2 1 e o e a senNXG N n D n b r r y y l . g p t v c on I AV O 0 a e a p a a u u e c o e HieMMA G { n J F M A M M J A S O N D ds E .

o doi eiw R i - - - - - - - - - - -

O _

_ t . pcr

_ c 3 0 2 7 3 0 7 1 0 4 9 0 mie 2

e 1 2 1 1 1 1 1 1 1 1 1 1 adh

. l rat 5 l n b r r y n l g p t v c CRo o a e a p a u u u e c o e *

- 7 ._ C J F M A M J J A S O N D *

• jtllrlll

_ t s J. 0 0

,. : u 0 0 0 0 0 0 0 0

_ - i < < < ( < < < <

s e  ?

. C S

_ E L

P R

A S

E

, T 4 A 3 L 1 1 1 1 1 1 1 U - 0 1 1 0 0 0 0 0 0 0 C

I T i a0< 0 0

0 0

0 0

0 R s _

A 3 e P m C

/ -

R i >

TI C <

NA P A

LE n PT i I

RS d AO e EP s7 LM s8 CO e9 UC r1 F p Y x NL E AR

. JE y OT t RR i n

. TA v o 9 9 9 9 1 I I I

_ - U i i 1 1 1 1 1 I I I

_ Q t t k

_ c a a a a a a a a a N A c t t t t t t t t

. I o S S S S S S S S L

S E

D -

I L

- C D

h O

I O

. - D

_ A R ,

m d

o i

, r e r n p c r n p c P a u e e a u e e M J S D M J S D n

o - - - - - - - -

, i t n r l t n r l t

. c a p u c a p u c 3 e J A J O J A J O l

5 l o

7 C i

i t

c A

c Y i p

L P o _

P t U o .

S s I _

, R E a T mD 5 5 5 5 5 5 5 5 5 5 5

. 6W A mE aS 2

(

2 2

2 2

(

2

(

2

(

2

(

2 2

2 6 GO L

NA _

OP yE 0 0 0 0 0 0 0 0 0 0 0

. - I I tG 0 0 0 0 0 0 0 0 0 0 0

- TC iP 0 0 0 0 0 0 0 0 0 0 0

. AI v 1 1 1 1 1 1 1 1 1 1 1 TN i < < < < < < < ( < < <

• SU t R M c E A

. T S A N m u

W E L i G E tD 0 0 0 0 .

N H i H 3 3 3 3 I rS 3 3 3 3

. - K . TO < < < <

N T I S R n N D o A i 5 2 2 6 4 1 5 3 1 5 2

- L N t e 0 0 0 0 0 0 0 0 3 0 0 P I ct ea n b r r y n l g g t v R Y l D a e a p a u u u u c o A T l J F M A M J J A A O N E I o L V7 C C I8 U T9 0

N C1 yE 0 0 0 0 0 0 0 0 0 0 0 A tG 1 1 1 1 1 1 1 1 1 1 1 1 N 0 i P < < < < < < < < < < < <

. A I v J D i ^

O A t c

R T

R F

O A

c i

N Y p O L o

. S P t I P o .

R U s A S I -

P M R a O E mD 5 5 5 5 5 5 5 5 5 5 5 5 C T mH 2 2 2 2 2 2 2 2 2 2 2 2 A aS < < < < < < < < < < ( <

2W GO NL OA yE 0 0 0 0 0 0 0 0 0 0 0 0

. I P tG 0 0 0 0 0 0 0 0 0 0 0 3 TI i P 0 0 0 0 0 0 0 0 0 0 0 0 AC v 1 1 1 1 1 1 1 1 1 1 1 1

- TI i ( < < ( < < < ( < < < <

SN t U c M A R m E u I i N tD 0 0 0 0 I i H 3 3 3 3 A rS 3 3 3 3 R TO < < < <

n o 6 3 1 5 2 7 i 5 2 2 6 4 1

- t e 0 0 0 0 0 0 0 0 3 0 0 0 ct ea n b r r y n l g g t v c l C a e a p a u u u u c o e 6 l J F M A M J J A A O N D o

7 C

~

~

~

+ i' l i

S yi 7 7 E) tl 3 3 U e i c 1 1 u

Ll vu - -

Ap in s s V m t 0 C C 0 0 0 0 0 0 0 0 a cr 1 ( ( 1 1 1 1 1 1 CS Ae < < < < < <

1 1

I p 4 3  !< 1 Rt a Ti ml 1 1  ;*

Cl n/ ,

Ep ai 9 6 GC LS 1 2 E D o

L n Ai Rd

, En y N o t E p i G s v .

e i Dr t Nr c Ao Al LC / 5 5 5 5 5 5 5 5 5 5 T( 1i 5,

) R 3C 0 0 0 0 0 0 0 0 0 0 0 N O 1 p < < < < < < E < < < <

R P -

. A e KF n L i I S d M' o N I NA I N I

N S A E (W L D .

P I N LI M 0 R CS A l4 A UA ( /1 E NB i -

L O 7 Ca C I H8g S pL U E -

N AL1 U ya N

A DO9%

RI FS H

L A)

V e i

t B v:

5 2

(

5 2

5 2

5 2

5 2

5 2

5 2

5 2

5 2

5 2

5_

2 J

O O 4 N p l i7 t3 .  ;  ;  ;  ;  ;  ;  ;  ;  ;  ;  ;

R N Om c1 O7 %C 0 0 0 0 0 0 0 0 0 0 0 T I a A 1 1 1 1 1 1 1 1 1 1 1 S SS ,

I N I a4

- RO d e Vt m3 AI t Ii m1 PT Dl a -

MA h" p Gs OC c f iS C CO t T L L L o An E g Ei y

G q Hd P p n t E o i Tp v As i T e t S r c r Al N o /

OC 1i 1 1 1 1 1 1 1 1 1 1 1 G( 3C < < < < < < < < < < <

E 1 p R -

O e n

i d

o I

n o

i 5 9 9 5 8 6 3 1 2 0 8 t e 0 0 0 0 0 0 0 3 1 1 0 ct ea n b r r n l g g t v c 7

l D a e a p u u u u c o e l J F M A J J A A O N D o

C

)

e l i

0 0 0 tG 0 0 0 iP 1 1 1 v < < <

i

.. t  !

c A

c i

- p o

• t '

o s

I a

unD 5 5 5 nH 2 2 2 aS < < <

GO S -

E 1 1 1 .

L yE

. P t G 0 0 0 M iP < < <

A v S i t

. Dg c

- OK A O/

Fi 1 T C 3 N N p 1 A I -

L n e P Si n E - iD 0 0 0 R Dd dH 6 6 6 A

. I e oS < < <

E L s 7' I O L Cs8 C Ue9 U N r1 N Op .

I x N DE A A J Ry O t

. R Fi n -

T Ov o i i 3 3 -

Nt t - I -

O c a R - R -

SA c C 1 C I o -

R L

- A P '

M O

C d

a

, e e e k p h c on y l u oo T et ea t

t nm il t e e ha SM L CS n

o i 1 0 3 t e 1 1 0 ct ea r n p l D a u e 8 l M J S

. o 7 C i

S h -

. P, ) g SET K ETH /

UTG i LI I AME co

' VEW 0

EAY 0 GMR 1

. PMD < .

Af G .

9 E

L

. P g M K A /

S i T

C P

N Ss E EC 0 M U7 0 I L3 1 D A1 <

. E V .,

S

. D4 0 ._

E H3 5 _

N S1 1 T I O <

N L .

A E L R P O H

R S

.. A E N7

a. L I 8 C 9

- U S1 N E .

D N I )

A L l J C i O U o R N S T O D

I e

A N n O i R I l T e F_ A r O C o O h

.- N L s O (

~. S

. I 3 R -

A R P C M

O C

E T

A D

N 2 O 0

. I

, T p C e

_ E S L

. 9 L O

7 C

29

(. . . ; ..

SUMMARY

OF RESULTS FROM PARTICIPATION IN EPA INTERLABORATORY CROSSCHECK PROGRAM DURING 1987 (VALUES EXPRESSED IN pCi/ Liter UNLESS OTHERWISE NOTED)

, Known Value and OSHD Result Control Limits-kakoratory Performance Evaluation Study

. April 1987 Gross Alpine 35 30 1 14'

. Gross Beta 76 66 i 9 Strontium-89 25 19 i 9 .

Strontium-90 12 10 1 3 Radium-226 3.1 3.9 1 1.0 Radium-228 5.8 4.0 1 1.0 Cobalt-60 9 8 1 9 Cesium-134 18 20 1 9 4

Cesium-137 15 15 -+ 9 1 ..

Uranium (Nat.) 4 5 1 10 October 1987 Gross Alpha 34 28 1 14 Gross Beta 69 72 1 9

. Strontium-89 16 16 i 9 i Strontium-90 9 10 1 3 Radium-226 4.2 4.8 1 1.3 Radium-228 3.4 3.6 1 0.9 Cobalt-60 17 16 i 9 Cesium-134 15 16 i 9 Cesium-137 25 24 1 9 4

0

p .; . g -

..y*,.

30 t .

' Known Value and.

OSHD Result Control Limits Onpa Emitters in Watit February'1987 Coba1t-60 51 *50- i 9 Zine-65 51- 50 1 9 Ruthenium-106 89 100 1 9

- Cesium-134 52 59 i 9 Cesium-137 85 87 i 9 .

June 1987 Chromium-51 34 41 1 9

, Cobalt-60 68 64 ~19 Zine-65 12 10 1 9 Ruthenium-106 66 75. i 9 Cesium-134 36 40 i9

., Cesium-137 79 80 1 9 October.1987 Chromium-51 72 70 19, l- Cobalt-60 17 15 i 9 Zinc-65 49 46 i .9 RQthenium-106 58 61 1 9 .q

- Cesium-134 24 25 i 9

[ Cesium-137 52 51 1 9

. Gross Alpha and Beta in Water .I January 1987 Gross Alpha 8 11 1 9

. , Gross Beta 12 10 1 9 May 1987 Gross Alpha 11 11 1 9 Gross Beta 7 7 i 9 p

4

___. ___-__- __-_____-__ _ __ - _ _ m

' ". 'f 3.y* ,

..?- . 31

.Known Value and N

QJ@ Result ContI O .imLt1 i

- September 1987 Gross Alpha '4 4 i 9 Gross Beta 13 12 1 9 Iodine-131 in Water August 1987 Iodine-131 53 48 1 10 i

kQM_kty31 Iodine in Milk l '

Pebruary 1987 Iodine-131. 8 9 1 2 Tritium in Water I* February'1987 Tritium 4250 4209 i 729 June 1987 Tritium '2883 2895 1 618 October 1987. Tritium 4323 4492 1 778 Radionuclides on Air Filter

- April 1987 - Gross Alpha 19 14 1 9 Gross Beta 50 43 1 9.

i Strontium-90 24 17 1 9 I Cesium-137 12 10 1 9 Radium in Water

', March 1987 Radium-226 6.3 7.3 1 1.9 Radium-228 8.3 7.5 1 2.0 June 1987 Radium-226 6.0 7.3 1 1.9 Radium-228 14.5 15.2 1 4.0 September 1987 Radium-226 7.3 9.7 1 2.5 l*

Radium-228 9.6 6.3 1 1.7 Strontium in Water i

4

w-fl .$.

... 68- tj ..

yf . y*[ , 32-

, e -

j ~,. 'z&.; e  !

y.

Known Value and OSHD Result Control Limits

, t.

January 1987 Strontium-89 29 25 i 9 Strontium-90 27 25 i 3

, , tj May 1987 Strontium-89 60 .

41 1 9 l a,

it Strontium-90 25 20 1 3 e .

Radionuclides '.n Fo_gd July 1987 Strontium-89 25 20 1 9 Strontium-90 25 30 1 3

• Iodine-131 83 80 i 14

, Cesium-137 58 50 1 9 Stable Potassium 1830 1680 i 146 (mg/KGM)

Uranium in Water February 1987 Natural Uranium 8 8 1 10 August 1987 Natural U' e;am

. '12 13 1.10

. Lilionuclides in Milk June 1987 Strontium-89 51 69 i 9 l

Strontium-90 27 35 1 3 Iodine-131 73 59 1 10 Cesium-137 85 74 1 9 a Stable Potassium 1627 1525 1 132 (mg/L)

Plutonium in Water l August 1987 Plutonium-239 4.7 5.3 1 0.9 G '

L,

- _ _ . _ _ _ _ _ _ _ _ _ _ _ _