ML20073F173

Annual Rept to NRC of Radiation Environ Monitoring Program 1990

ML20073F173
Person / Time
Site:	Prairie Island
Issue date:	12/31/1990
From:	Fey F, Huebner L NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9105020077
Download: ML20073F173 (103)

Text

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O rJ Northem States Power Company 414 Nicollet Mall Minneapolis, M!nnesota 65401 1927 Telephone (612) 330 5500 April 30, 1991 Prairie Island Technical Specification TS 6.7.C.1 U S Nuclear Regulatory Commission Attention: Document Control Desk Washington, D C 20555 Prairie Island Nuclear Generating Plant Docket No. 50-282 License No. DPR-42 l

Docket No. 50-306 License No. DPR-60 1990 Annual Rt'fiological Environmental Monitoring Report In accordance with the Prairie Island Technical Specifications, Appendix A to Operating License DPR-42 and DPR-60, we are submitting one copy of the Annual Radiological Environmental Monitoring Report, covering the period January 1 through December 31 of 1990.

Respectfully submitted, G

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Fey, Jr., Manager Nuclear Radiological Services Attachment 9105020077 901231 PDR ADOCK 0500028 R

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TPTELEDYNE ISOTOPES 1

MIDW(ST LABORATORY 700 L ANDWEHR ROAD NORTHBROOK, ILUNois 6tiot.2 2310 (706,664 0F00 F As (70lb 664 4517 NORTHERN STATES POWER COMPANY MitlNEAPOLIS, Mli NESOTA PRAIRIE ISLAND I4UCLEAR GENERAT!!iG PL ANT Docket No. 50-282 License No. OPR-42 50-306 DPR-60 ANNUAL REPORT to the UtilTED STATES NUCLEAR REGULATORY COMMISSION Radiation EnH ronmental Monitoring Program January 1,1990 to December 31, 1990 Prepared Under Contract by TELEDYNE IS0 TOPES MIDWEST LABORATORY Proj ect No. 8010 6 () J/

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T ?& dLR /'d Approved by:

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/i..G.Huebner

' General Manager 15 March 1991

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l PREFACE The staff of Teledyne isotopes Midwest Laboratory was responsible for the data presented in this report.

Samples were collected by acquisition of the contractor Interpoll Laboratories, Inc. from January 1 to M States Power Company, from March 16 to December 31, Department, Northernwas prepared by L. G. Huebner, General Manager, Teledyne isotopes Midwest Laboratory.

He was assisted in the report preparation by 1990.

The report other staf f members of this laboratory.

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TABLE OF CONTENTS

_Section Page ii Preface...........................

List of Tables........................

iv

1.0 INTRODUCTION

1 2

2.0 SUKMARY...........................

3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) 3 3

3.1 Program Design and Data Interpretation 4

3.2 Program Description.

3.3 Program Execution....................

5 3.4 Laboratory Procedures..................

6 3.5 Program Modifications..................

7 3.6 Land Use Census.....................

7 4.0 RESULTS AND DISCUS $10N....................

8 4.1 Atmospheric Nuclear Detonations and Nu c l e a r Acc i d e n t s...................

8 8

4.2 Program Findings 5.0 TABLES............................

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6.0 REFERENCES

CITED.......................

24 APPENDICES A

Interlaboratory Comparison Program Results.......... A-1 B

Data Reporting Conventions.................. B-1 C

Maximum Permissible Concentrations of Radio-activity in Air and Water Above Natural Background in Unrestricted Areas.............. C-1 D-1 0

Special Ground, Surf ace. and Well Water Samples iii

a LIST OF TABLES No.

Title Pace 5.1 Sample Collection and Analysis Program,1990.........

13 5.2 Sampl i ng Loc a ti on s......................

14 5.3 Missed Collections and Analyses,1990 16 5.4 Environmental Radiological Monitoring Program Summary 17 In addition, the following tables are in the Appendices:

Appendix A A-1 Interlaboratory Comparison Program Results. 1986-1990 A-3 A-2 Interlaboratory Comparison Program Results (TLDs)

A-18 A-21 A-3 In-house Spiked Samples A-3 I n-hou s e " Bl a nk " Sampl es...................

A-28 Attachment B:

Acceptance criteria for spiked samples A-35

'idendum to Appendix A:

Explanation of the Results Outside of Control Limits A-36 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unr est rict ed Areas.....................

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1.0 INTRODUCTION

1 This report summarizes and interprets results of the Radiation Environmental Monitoring Program (REMP) conducted by Teledyne Isotopes Midwest Laboratory at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during December, 1990.

lhis program monitors the levels of the period January radioactivity in the air, terrestrial, and aquatic environments in order to assess the impact of the plant or, its surroundings.

Tabulations of the individual analyses made during the year are not included in this report.

These data are included in a reference document (Teledyne isotopes Midwest Laboratory,1991ti) availai,1 at Northern States Power Company, Nuclear Generation Department.

Prairie Island Nuclear Generating Plant is located on the Mississippi River in Goodhue County, Minnesota, and operated by Northern States Power Company.

The plant has two 550 MWe pressurized water reactors.

Uni t I achieved initial criticality on 1 December 1973.

Commercial operation at full power began on 16 December 1973.

Unit 2 achieved initial criticality on 17 December 1974.

Commercial operation at full power began on 21 December 1974.

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2.0

SUMMARY

The Radiation Environmental Monitoring Program (REMP) required by the U.S.

Nuclear Regulatory Commission (NRC) Technical Specifications for the Prairie Island Nuclear Generating Plant is described. Results for 1990 are summarized and discussed.

Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Isl and Nuclear Generating Plant, with the exception of some of the additional special ground, well, and surface water samples.

These special ground, surface, and well water samples are sunrnarized and documented separately in Appendix D.

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3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 program Design and Data Interpretation The purpose of the Radiation Environmental Monitoring Program (REMP) at the Prairie Island Nuclear Generating Plant is to assess the impact of the plant on its environment.

For this purpose, samples are collected from the air, terrest rial, and aquatic environments and analyzed for radioactive content.

In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLDs).

Sources of environmental radiation include the f ollowing:

(1) Natural background radiation arising from cosmic rays and primordial radionuclides; (2) Fallout from atmospheric nuclear detonations; (3) Releases from nuclear power plants; (4)

Industrial and medical radioactive waste; and (5) Fallout f rom nuclear accidents.

In interpreting the data, ef fects due to the plant must be distinguished from those due to other sources.

A major interpretive aid in assessment of these ef f ects is the design of the monitoring program at the Prairie Island Plant which is based on the indicator-control concept.

Most types of samples are collected both at indicator locations (nearby, downwi nd, or downstream) and at control locations (distant, upwind, or upst ream).

A plant ef fect would be indicated if the radiation level at an indicator location was signifi-cantly larger than that at the control location.

The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising from other sources.

An additional interpretive t echnique involves analyses for specific radionuclides present in the environmental samples collected from the plant site. The plant's monitoring program includes analyses for tritium and iodi ne-131.

Most samples are also analyzed f or gamma-emitting isotopes with results for the following groups quantified:

zi rconium-95, cesium-137, cerium-144, beryllium-7, and potassium-40.

The first three gamma-emitting isotopes were selected as radiological impact indicators because of the dif ferent characteristic proportions in which they appear 3

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in the fission product mix produced by a nuclear reactor and that pro-duced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor:

each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown.

On the other hand,10 days af ter a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud,1963).

Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope.

They were chosen as calibration monitors and should not be considered radiological impact indicators.

The other group quantified consists of niobium-95, ruthenium-103, and

-106, cesium-134, barium-lanthanum-140, and cerium-141.

These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing.

Nuclides of the final group, manganese-54, iron-59, cobalt-58, and -60, and zinc-65, are activation products and arise from activation of corrosion products.

They are typical components of a nuclear power plant's ef fluents, but are not produced in significant quantities by nuclear detonations.

Other means of distinguishing sources of environmental radiation can be employed in interpreting the data.

Cu rrent radiation levels can be compared with previous levels, including those measured before the Plant became operational.

Results of the plant's monitoring program can be related to those obtained in other parts of the world. Finally, results can be related to events known to cause elevated levels of radiation in the environment, e.g., atmospheric nuclear detonations.

3.2 program Description The sampling and analysis schedule for the environmental radiation monitoring 3rogram at Prairie Island is summari zed in Table 5.1 and bricfly rev' ewed below.

Table 5.2 defines the sampling location codes used in Table 5.1 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the reactor site.

To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Teledyne isotopes Midwest Laboratory,1987).

To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations. Also, airborne iodine is collected by continuous pumping through charcoal filters at all of these locations.

Filters are changed and counted weekly.

Particulate filters are analyzed for gross beta activity and charcoal filters for iodine-131.

A monthly composite of all particulate filters is gamma-scanned on an HP Ge or Ge(Li) detector.

One of the five locations is a control (P-1), and four are indicator (P-2, P-3, P-4. and P-6).

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As a " Lessons Learned" commitment, ambient gamma radiation is monitored at thirty-two (32) locations, using CaSo4:Dy dosimeter with four sensi-tive areas at each location:

ten (10) in an inner ring in the general area of the site boundary, fif teen (15) in the outer ring within 4 - 5 mile radius, six (6) at special interest locations and one control loca-tion,11.1 miles distant f rom the plant.

They are replaced and measured quarterly. Also, a complete emergency set of TLDs for all locations is placed in the field at the same time as regular sets.

The emergency set is returned to TIML quarterly for annealing and repackaging.

Milk samples are collected monthly from six farms (five indicator and one control).

A new milk location (P 36) was added to the program in N ov emb e r, 1990 ).

The milk is collected biweekly during the growing season (June - September), because the milk animals may be on pasture.

All samples are analyzed for iodine-131 and gamma-emitting isotopes.

for additional monitoring of the terrestrial environment, leafy green vegetables (cabbage) are collected annually from the highest D/Q garden and a control location (P-25) and analyzed for iodine-131.

Corn is collected annually only f rom fields irrigated with river water and a control location (P-25) and analyzed for gamma-mitting isotopes.

Also, well water is collected quarterly from four locations and analyzed for tritium and gamma-mitting isotopes.

Additional special well water and ground water is collected monthly from six locations and quarterly from three locations near the plant and analyzed for tritium and gamma-mitting isotopes.

River water is collected weekly at two locations. one upstream of the plant (P-5) and one downstream (P 6, Lock and Dam No. 3).

Monthly composites are analyzed for gamma-emitting isotopes.

Qua rterly compo-sites are analyzed for tritium.

Drinking water is collected weekly from the City of Red Wing well.

Monthly composites are analyzed for gross beta, iodine-131, and gamma-mitting isotopes.

Quarterly composites are analyzed for tritium.

The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, periphyton or invertebrates, and bottom sediments.

Shoreline sediment is collected semi-annually from one location. All samples are analyzed for gamma-mitting isotopes.

3.3 Program Execution, The Program was executed as described in the preceding section with the following exceptions:

1.

No air particulate and 1-131 data was available for Location P-3 for the collection period ending 02-05-90 because of pump failure.

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No data was available for vegetation from Location P-24 becaute the sample was lost in transit.

3.

The TLD data for the fourth quarter of 1990 for Location P-14B was not available because TLD was lost in the field.

l Deviations from the program are sumarized in Table 5.3.

The responsi-bilitics of collecting and shipping samples were transferred to Nuclear Radiological Services (NRS) ef f ective January 1,

1990.

An additional person has been added to NRS since March 1,1990. Additional effort will be made to collect any missed milk sample if milk will become available shortly; damaged or missed TLD holders will be investigated, replaced, or relocated which are similar to the actions that have been taken in the past.

3.4 Laboratory Procedures All iodine-131 analyses in milk and drinking water were made by usir.o a sensitive radiochemical procedure which involves separation of the el ement by use of an ion-exchange resin and subs equent beta counting.

All gamma-spectroscopic analyses were performed with an HP Ge or Ge(Li) detector.

Levels of iodine 131 in cabbage were determined by HP Ge or Ge(Li) spectrometry.

Levels of airborne iodine 131 in charcoal samples were measured by HP Ge or Ge(Li) spectrometry.

Tritium levels were determined by liquid scintillation technique.

Analytical procedures used by the Teledyne Isotopes Midwest Laboratory are specified in detail elsewhere (Teledyne isotopes Midwest Laboratory, 1985).

Procedures are based on those prescribed by the National Center for Radiological Health of the U. S. Public Health Service (V. S. Public Heal th Service, 1967) and by the Health and Safety Laboratory of the U.

S. Atomic Energy Commission (U. S. Atomic Energy Commission,1972).

Teledyne Isotopes Midwest Laboratory has a comprehensive quality control /

quality assurance program designed to assure the reliability of data obtained.

Detail s of TIML's Quality Assurance Program are present ed elsewhere (Teledyne isotopes Midwest Laboratory.1991).

The TIML Quality Assurance Program includes participation in Interlaboratory Comparison 1;

(Crosscheck) Programs.

Results obtained in crosscheck programs are presented in Appendix A.

3.5 Program Modifications During the growing season, milk producers were monitored to determine when the dairy animals were on pasture or fresh cut feed.

The frequency of milk samples was increased to semimonthly during the grazing period because animals were on pasture or fresh cut feed.

One milk location was added to the program in November 1990.

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3.6 Land Use Census in accordance with Technical Specification 4.10, paragraph D1, a land use census is conducted in order to identify the location of the nearest milk animal the nearest residence, and the nearest garden of greater than b roducing fresh leafy vegetables in each of the 16 meteorological 500 ft p

sectors within a distance of 5 miles.

This census is conducted at least once per 12 months between the dates of May 1 and October 31.

New loca -

tions are added to the radiological environmental monitoring program within 30 days, and sampling locations having lower calculated doses or a lower dose commitment may be deleted from this monitoring program after October 31 of the year in which the land use census was conducted.

This land use census insures the updating of the radiation environmental monitoring program should sampling locations change within the 5 mile radius from the plant.

The 1990 Land Use Census was completed on August 30, 1990.

This census did not identify any locations of exposure pathways different from those used in the program during the first six months of the year.

Milk and garden sample locations did not change due to the requirements of the land use census.

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4.0 RESULTS AND DISCUS $10N All of the scheduled collections and analyses were made except those listed in Table 5.3.

All results are summarized in Table 5.4 in a format recommended by the Nuclear Regulatory Commission in Regulatory Guide 4.8.

For each type of analysis of each sampled medium, this table lists the mean and range for all indicator locations and for all control locations.

The locations with the highest mean and range are also shewn.

4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests in 1990.

The last reported test was conducted on October 16, 1980 by the People's Republic of China.

The reported yield was in the 200 kiloton to 1 megaton range.

There were no reported accidents at nuclear reactor f a:ilities in 1990.

4.2 Program Findings Results obtained show background levels of radioactivity in the environ-mental samples collected in the vicinity of the Prairit Island Nuclear Generating Plant in 1990, with the exception of some of the additional special ground water samples and well water samples.

Ambient Radiation (TLDs)

Ambient radiation was measured in the general area of sit e boundary, at outer ring 4 - 5 mi distant from the Plant, at special.nterest areas, and at one control location.

The means ranged from 15.0 mR/91 days at inner ring locations to 16.6 mR/91 days at outer ring locations.

The mean at special locations was 14.9 mR/91 days and 16.3 mR/91 days at the control location. The dif ferences are not statistically significant.

The dose rates measured at all indicator and control locations were similar to those observed in 1978 (12.1 and 15.1 mR/91 cays, respec-tively); in 1979 (12.6 and 15.3 mR/91 days, respectively); in 1980 (11.2 and 13.5 mR/91 days, respectively),; in 1981 (13.0 and 14.5 mR/91 days, respectively); in 1982 (12.0 and 13.0 mR/91 days, respectively),; in 1983 (13.0 and 14.9 mR/91 days, respectively); in 1984 (13.9 and 15.3 mR/91 days, respectively); in 1985 (13.9 and 15.3 mR/91 days, respec-tively); in 1986 (16.6 and 17.0 mR/91 days, respectively), in 1987 (15.4 and 16.0 mR/91 days, respectively), in 1988 (16.2 and 16.7 mR/91 8

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days, respectively), and in 1989 (15.8 and 16.3 mR/91 days, respectively).

No plant effect on ambient gamma radiation was indicated.

1 Airborne Particulates The average annual gross beta concentration in airborne particulates was nearly identical at both indicator and control locations (0.024 and 0.023 pC1/m3), respectively and was about the same as the levels bserved (0.025 pCi/m3), pCi/m3),

in 1982 (0.026 pC1/m3),

1983 (0.023 1984 (0.024 pCi/m ). 1985 (0.025 pCi/m3), 1986 and 1987 (0.024 pC1/m3).

It was 1988 (0.030 pC1/m3 at both indicator and control slightly ) lower than in(0.028 pC1/m3).

The average of 0.025 pCi/m3 for locations and 1989 1986 does not include the results from May 19 to June 9,1986, which were influenced by the accident at Chernobyl.

A spring peak in beta activity had been observed almost annually for many years (Wilson et al.

1969).

It had been attributed to f allout of-nuclides from the sTra,tosphere (Gold et al.,

1964).

It was pronounced in 1981, occurred to a lesser degreT1T1982, and did not occur in 1983, 1984,1985,1987 or 1988.

In 1986, the spring peak could not be identified because it was overshadowed by the releases of radioactivity f rom Chernobyl.

The highest averages for gross beta were for the month of January and the first quarter.

The increase of beta activity during winter months were also observed in 1983,1984,1985,1986 (exclusive of the period between May. 19, 1986 and June 9,1986),1987,1988, and 1989.

Two pieces of evidence indicate conclusively that the elevated activity observed during the-fourth quarter was not attributable to the Plant operation.

In the first place, elevated activity of similar size occurred simultaxously at both indicator and control locations.

Secondly, an identical pattern was observed at the Monticello Nuclear Generating Plant, about 100 miles distant from the Prairie-Island Nuclear Generating Plant (Northern States Power Company,1991a).

Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations.

8eryllium-7, which is produced continously in the upper atmosphere by cosmic radiation (Arnold and Al-Sal ih, 1955), was detected in all sampl es.

All other gamma-emitting isotopes were below their respective LLD limits.

Airborne lodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.07 pCi/m3 in all samples.

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Milk Iodi ne-131 results were below the oetection limit of 1.0 pCi/L in all sampl es.

Cs-137 results were below the LLD level of 15 pCi/L in all samples.

No other gamma-enitting isotopes, except potassium-40, were detected in any milk samples.

This is consistent with the finding of the National Center for Radiological Health that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow.

The common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health,1968).

In summary, the milk data for the 1990 show no radiological ef fects of the plant operation.

Drinking Water in drinking water from the City of ked Wing well, tritium activity was below the LLD level of 330 pCi/L in all samples.

lodine-131 activity was also below the LLD level at 1.0 pCi/L in all samples.

As with the other well water samples, all analyses for gamma-emitting isotopes yielded results below detection limits.

Gross beta averaged 7.0 pC1/L and was similar to the levels observed in 1979 (10.5 pCi/L),1980 (11.8 pCi/L),

1981 (10.7 pCi/L),1982 (6.9 pCi/L),1983 (8.0 pC1/L),1984 (7.9 pCi/L),

1985 (7.1 pCi/L),1986 (6.8 pCi/L),1987 (7.9 pCi/L),1988 (8.0 pCi/L),

and 1989 (7.0 pCi/L).

River Water At the upstream and downstream collection sites, qu a rt erly composite tritium levels were below the LLD level of 330 pCi/L in all but one sampl e The detected activity was 484 pCi/L in a composite sample for the third quarter from Location P-6.

The detected activity was close to the detection level and is not significant.

River water was also analyzed for gamma-emitting isotopes.

All gamma-anitting isotopes were below their respective detection limits.

Well Water At the control well P-25, Rohl Farm and three indicator wells (P-8, Community Center; P-6, Lock and Dam No. 3; and P-9, Pl ant Well No. 2) no tritium was detected above LLO level of 330 pCi/L in all s ampl es.

Gamma-emitting isotopes were below the detection limits in all samples.

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Crops One sample of cabbage was collected in September and analyzed for I-131.

The I-131 level was below 0.015 pC1/g wet weight in both samples.

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was no indication of a plant effect.

The field sampling personnel conducted a survey and found that there was no river water taken for irrigation into fields within 5 miles down stream form Prairie Island Plant.

Therefore, it was not necessary to collect and analyze corn samples.

Fish Fish samples were collected in May and September,1990.

The only isotope detected was naturally-occuring potassium-40 and there was no significant difference between upstream ar.d downstream results.

There was no indica-tion of a plant effect.

Aouatic Insects or Periphyton Aquatic insects (invertebrates) or periphyton were collected in May and October, 1990.

The samples were analyzed for gamma-emitting isotopes.

L All gamma-emitting isotopes except potassium-40 were below their respec-(

tive LLDs.

No plant effect was indicated.

i Bottom and Shoreline Sediments l

Sediment collections were made in May and October, 100.

The samples were analyzed for gamma-emitting isotopes.

Cs-137-was detected in one bottom sediment upstream sample (0.093 pCi/g dry weight).

All other gamma-mitting isotopes, except naturally-occurring potassium-40, were below their respective LLDs.

No plant ef fect was indicated.

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5.0 TABLES 12

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Table 5.1 Sample collection and analysis program, Prairie Island Nuclear Generating Plant, 1990.

Locations Collection Analysis Codes Type end Type and Medium No.

(and Type)a Frequencyb Frequencyc Ambient radiation 32 P-01 A - P-10A C/Q Ambient gamme (TL0s)

P-01B - P-15B P-015 - P-06S P-01C Airborne particulates 5

P-1(C),P-2, C/W GB, GS (QC of.

P-3, P-4, P-6 eachlocation)

Airborne iodine-5 P-1(C),P-2,P-3 C/W 1-131 P-4, P-6 Mil k 5

P-16, P-17, P-18 G/Md 1-131, GS P-14, P-25(C), P-36 River water 2

P-5(C),P-6 G/W GS(MC),H-3(QC)

Drinking water 1

P-11 G/W GB(MC),1-131(MC)

GS(MC), H-3(QC)

Well water 4

P-25(C),P-6, G/Q H-3, GS P-8, P-9 Edible cultivated 2

P-25(C),P-24 G/A 1-131 crops - leafy green vegetables Fish (one species 2

P-19(C),P-13 G/SA GS edible portion)

Periphyton or 2

P-5(C),P-12 G/SA GS

. invertebrates

-Bottom sediment-2 P-20(C),P-6 G/SA GS Shoreline sediment 1

P-12 G/SA GS

• Location cooes are defined in' Table 5.2.

Control stations are indicated by (C).

All other stations are indicators.

b Collection type is coded as follows: C/ = continuous, G/ = grab.

Collection frequency is coded as follows: W = weekly, M = monthly, Q =

quarterly, SA = semiannually, A annually.

c Analysis type is coded as follows: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium, 1-131

• iodine 131. Analysis frequency is coded as follows:

MC = monthly composite, QC = quarterly composite.

d Milk is collected biweekly during the grazing season (June - October) if milch anima,ls are on pasture.

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Table 5.2.

Sampling locations, Prairie Island Nuclear Generating Plant, 1990.

Distance and Type of Direction from Code Typea Collection Site Sampl eb Site Stack P-1 C

Air Station P-1 AP, Al 11.8 mi 0 316'/NNW P-2 Air Station P-2 AP, Al 0.5 mi @ 294'/WNW P-3 Air Station P-3 AP, Al 0.8 mi 0 313*/NW P-4 Air Station P-4 AP, Al 0.4 mi 0 359'/N I

P-5 C

Upstream of Plant RW, DO 2.3 mi 9 348'/NNW P-6 Lock & Dam #3 & Air AP,AI,RW.WW,BS 1.6 mi 0 129'/SE Station P-6 P-8 Cunmunity Center WW 1.0 mi 0 321*/WNW P-9 Plant Well #2 WW 0.3 mi 0 306'/NW P-11 Red Wing Service Center DW 3.3 mi 0 158'/SSE P 12 Downstream of Plant B0, SS 3.0 mi @ 116'/ESE P.3 Downstream of Plant F

3.5 mi @ 113*/ESE P-It Gustafson Farm M

2.3 mi 0 173'/SSE P-16 Johnson Farm M

2.6 mi 0 60'/ENE P-17 P1 ace Farm M

3.5 mi @ 25'/NNE P-18 Christensen Farm M

3.8 mi @ 88'/E P-19 Upstream of Plant F

1.3 mi @ O'/N P-20 Upstream of Plant F

0.9 mi 9 45'/NE P-24 Suter Residence VE 0.6 mi 0158'/SSE P-25 C

Rohl Farm M WW, VE 12.9 mi @ 352'/N P 36 Dosdahl Farm M

3.9 mi 0 9'/N General Area of the Site Boundary

-P-01A Property Line TLD 0.4 mi 0 359'/N P-02A Property Line TLD 0.3 mi 9 10'/N P-03A Property Line TLD 0.5 mi 0 183'/S P-04A-Property Line TLD 0.4 mi 0 204'/SSW P-05A Property Line TLD 0.4 mi 0 225*/SW P-06A Property Line TLD 0.4 mi 0 249'/WSW P-07A

. Property Line TLD 0.4 mi 0 268'/W l

l P-08A Property Line TLD 0.4 mi 9 291'/NNW P -09 A Property Line TLD 0.7 mi 9 317'/NW P-10A Property Line TLD 0.5 mi 9-333'/NNW-L 14

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Table 5.2.

Sampling locations, Prairie Island 14uclear Generating Plant, 1990 (continued)

Distance and Type of Direction from Code Typeo Collection Site Sampl eb Site Stack Approximately 4 to 5 miles Distant f rom the Plant P -01 B Thomas Killian Residence TLD 4.7 mi 0 355'/N P-02B Roy Kinneman Farr TLD 4.8 mi 0 17'/NNE P-03B Wayne Anderson Ferm TLD 4.9 mi 0 46'/NE P-04B Nelson Drive (Road)

TLD 4.2 mi 0 61'/ENE P-05B County Road E and Coulen TLD 4.1 mi @ 102'/ESE P-06B William Houschildt Residence TLD 4.4 mi 0 112*/ESE P-07B Red Wing Public Works TLD 4.7 mi 0 140'/SE P-08B David Wnuk Residence TLD 4.1 m1 0 165'/SSE P-09B Highway 19 South TLD 4.2 mi 0 IB7'/S P-10B Cannondale Farm TLD 4.9 mi 9 200*/SSW P-11B Wallace Weberg Farm TLD 4.5 mi 0 221*/SW P-128 Roy Gergen Farm TLD 4.5 mi 0 247'/WSW P-13B Thomas O'Rourke Farm TLD 4.4 mi @ 270'/W P-14B David J. Anderson fann TLD 4.9 mi 0 306*/NW P-15B Holst Farms TLD 4.2 mi @ 347'/Ni1W Special Interest Locations P -01 S Federal Lock & Dam 63 TLD 1.6 mi @ 129'/SE P-025 Charles Suter Residence TLD 0.5 mi 0 155'/SSE P-03S Carl Gustafson Farm TLD 2.2 mi 0 173'/SSE P-045 Richard Burt Residence TLD 2.0 mt 0 202'/SSW P-05S Kenney Store TLD 2.0 mi 0 270*/W P-06S Earl Flynn Farm TLD 2.5 mi 0 299*/ win P-01C Robert Kinnemen Farm TLD 11.1 mi 0 331*/N!N a "C" denotes control location. All other locations are indicators, b Sample codes:

AP = Airborne particulate WW = Well water A1 = Airborne iodine BS = Bottom (river) sediments M = Mil k SS = Shoreline Sediments VE = Vegetatior./ vegetables B0 = Bottom organisms (periphyton DW = Orinking water or macroinvertebrates)

RW = River water F = Fish 15

I Table E.3.

Missed collections and analyses,1990, Prairie Island Nuclear Generating Plant. All required samples were collected and analyzed as scheduled except the following.

Collection Date or Sample Analysis location Period Comments Air Particulates Gross beta P-3 02-05-90 Pump failure.

and Charcoal 1-131 Vegetation 1-131 P-24 09-10-90 Sample lost in transit.

Thermoluminescent kiibi ent P-14B 4th Qtr.

Lost in the field.

Dosimeters (TLDs)

Radiation 1990 i

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e Table 5.4.

Radiological Envirofunectal Mtmitoring Progree Seary ((eet inited )

%=c of Facility Prairie island >xleer Gmrating Plant Dodet No.

50-287. 50-306 location of Facility Goodhue, Pirmeseta Reporting Period Jarva n - Dec M er 19 M (Coimty. State) indicator locaties witM Highest Contret Sample Type and location.

Ancual Meen locattees b-her of Type Nuceer of Mean (F)C pe,n (p p peen (T)C

%n-rou t t ee C

C R esults' (Units)

Analyses LLDb pg,c locationd Ra-ge Range a

Crinking Wa*er la 12 1.0 7.0 (12/12)

' F-il. Red Wieg 2.0 (12/12) 9>>ne 0

(pCi/t )

(5.2-8.7)

Service Center (5 2-8.7) 3.3 et 9 153*/55E I-131 12 1.0

<ttD f*me 0

H-3 4

330

<tLD Ntee G

G5 12 5

m-54 15

<tt D kne 0

Fe-59 30

<t t D mme O

Co-58 15

<t LD fatw 0

Co-60 15

<t LD Nme 0

l In-65 30

<t LD Nee 0

l l

Tr-96-95 15

<ttD

%ae O

(s-134 10

<1 LD fece e

Cs-137 to

<tLD Nee f

Ba-ta-140 15

<ttD kne C

Cc-144 64

<Lt c ten

• O River Water H-3 8

330 484 (1/4)

P-6, tod and Dee 484 (1/4 4tD 0

N. 3, 1 6 ei!es (pCift )

9 129*/5E 05 74 Mn-54 15

<1LD 4 LD 0

Fe-59 30

<tt D

<t LD 0

e l

Table 5.4 Radiological Environmental Mcmitoring Progree Summary (curtimed) l

%me of Facility Fr trie island Nclear Generating Plant Doctet ho.

50-282, 50-306 tocation of Facility Coodhue. Minnesota Beorting Period January - December 1990 (County, State)

Indicator tocation with Mi hest Control 9

Samole Type and Locations Annual Mean Locations bee,er of Type

%st>er of Mean (F)C Mean p p Meae (F)<

, Fes-routine (Units)

Analysesa LLDb ganggc locationd RangeC Egc g pessits e River biater Co-58 15 4tD

<tt0 0

(pCi/L)

(continued)

Co-60 15

<ttD

<tto 1

0 In-65 30

<tLD

<t tD 0

1 Cs-134 15

<tt0

<tLD 0

Cs-137 18 410

<tLD 0

i Ba-to-140 15

<ttD

<t LD 0

?

eu Ce-144 66

<tt D

<tD 0

o

i. ell Eater M-3 22 330

<tLD

<t to O

(PCi/L)

GS 22 Mn-54 15

<tB

<ttD 0

Fe-59 30

<tLD

<tLD 0

00-58 15

<tLD

<tLD 0

i Co-60 15

<tLD

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i Zn-65 30

<tt0

<ttD 0

1 Z r-te>-95 15

<t1D

<tLD 0

Cs-134 10

<tLD 4t0 0

Cs-137 10

<t1D

<ttD 0

Ba-ta-143 15

<ttD

<ttD o

Ce-144 45

<tt 0

<tLD 0

t 1

[

j i

l

e Table 5.4.

Radiological Enviromertal Monitoring Program Sumary (contimsed) mee of Facility Prairie Island %cicar Generating Plant Docket fio.

50-282, 50-306 tocation of Facility Good %ue. Minnescia Reporting Period January - Deceanber 1997 (County, State) l Indicator tocation with Highest Centrol Sample Type and Locations Aamal Mean locations

%mber of Type Neer of Mean (F)E 4

Meae (F)C Mean (F)C

%.m-roottee (tM ts )

Analysesa LLDb gang,c locatiend ganget en 8ewits c

1 Crops - C4bbage 1-131 1

0.015

<t LD

<tle 0

(PC1/9 wet)

Fish - Flesh GS 4

(pC8/g =et)

)

E-40 0.1 2.52 (2/2)

P-19, tystream of 2.% (2/2) 2.96 (2/2)

O (2.24-2.8!)

Plaat, 1.3 et 9 (2.57-3.35)

{2.57 1.35) g O'/ tt w

l Mn-54 0.021

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<tLD

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<llD

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<tLO

<ttD 0

l Z n-65 0.055

<ttD

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2r-te-95 0.057

<t LD

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<ttD

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<t LD

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<t tD

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Inv ertebra tes GS 4

(pCl/g wet)

Be-T 4.34

<ttD

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K -40 2.57

<LLD P-5 (C), tipstreae 4.54 (1/2) 4.54 (1/2) 0 of Plant, 2.3 el 9 348*/Mrs i

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Table 5.4.

Radiological Environmental Monitoring Program Sumary (contf twed) hame of Facility Prairie Island Nclear Generating Plant Docket No.

50-282, 50-306 tocation of Facility, _

Goodhue, Minneso*a Reporting Period January - Decenter 1990 (County, State)

Inficator Location with Highest Contr91 Saeple Type and Locatlees Annual Mean to(attoes humber of Mean U F Meen (F)c

%n-routine Meae{F)c Type itenber of d

gang,c g,,9,c Results' R ange tocatten a

L10D (Units)

Analyses Bottom and G5 5edtaents Mn.-54 0.c31

<11D

<ttD 0

Shoreline (pti/g dry)

(continued) 0o-58 0.038

<tt0 4tD 0

Co-60 0.039

< TLC

<t1D 0

Zn-65 0.074

<tt D

< tid 0

Nw otD 0

Ir-Nb-95 0.073

<t tD Ru-103 0.051

<tt 0

<ttD 0

F0-104 0.24

<tt0

<tt D 0

Cs-134 0.025

<t t D

<ttD fi (s-131 0.029

<tLD P-20. Upstream of 0.093 (1/2) 0.093 (1/2)

O Plant, 0.9 et @

45*/hE Ba-la -140 0.42

<tt D

<t LD 0

Ce-141 0.10

<tLD 4LD 0

Ce-144 0.13

<ttD

<t LD 0

a 68 = Gross beta; G5 = gawma scan.

b ttD = funninal lower limit of detection based on 4.66 sigma error for bethground sample. Traction of detectable measurements at specified location is indicated c Mean and range based upon detectable seasurements only.

in parentheses (F ).

d locations are specified (1) by name and code (Table 2) and (2) distance, direction, and sector relative to reacter site.

f Non-routine results are those which enceed ten times the control station value. If no co4rol stetten value is available, the result is considered non-routine if it exceeds ten tiees the preeperational value for the locatien.

I f One rewit for I-131 did not reach LLD (0.51 pCf /m3) due to very low volume.

L

s s

l I

l

6.0 REFERENCES

CITED l

Arnold, J. R. and H. A. Al-Salih.

1955.

Beryllium-7 Produced by Cosmic Rays. Science 121: 451-453.

Eisenbud, M.

1963.

Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275 and 276.

Gold, S., H. W. Barkhau, B. Shicin, and B. Kahn,1964.

Measurement of Natu-rally Occuring Radionuclides in Air, in the Natural Radiation Environ-ment, University of Chicago Press, Chicago, Illinois, 369-382.

Hazleton Environmental Sciences Corporation.

1979a.

Radiation Environmental Monitoring for Prairie 131and Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978.

1979b.

Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complet e Analysis Data Tables, January -

December 1978.

1980a.

Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January -

December 1979.

1980b.

Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -

December 1979.

19814.

Radiation Environmental Monitoring for Monticello l

Nuclear Generating Plant, Compl ete Analysis Data Tat,las, January -

December 1980.

1981b. Radiation Environmental Monitoring for Prarie Island Nuclear Generating Plant, Compl ete Analysis Data Tables, January -

December 1980.

1982a.

Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Compl ete Analysis Data Tables, January -

December 1981.

1982b.

Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -

December 1981.

1983a.

Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January -

December 1982.

24

0 6

Hohenemser, C.M. Deicher, A. Ernst, H.

Hof sass, G. Lindner, E. Racknagel.

1986.

"Chernobyl," Chemtech, October 1986, pp. 596-605.

National Center for Radiological Health, 1968.

Radiological Heaith and Data Reports, Vol. 9, Number 12, 730-746.

Northern States Power Company.

1979.

Prairie Island Nuclear Generating Pl ant, Annual Radiation Environmental Monitoring Report to the U.S.

Nuclear Regulatory Commission, January 1,

1978 tv December 31, 1978 (prepared by Hazleton invironmental Sciences).

Minneapolis, Minnescta.

1980.

Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1979 to December 31.1979 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.

1981.

Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1980 to December 31,1980 (prepared by Hazleton Environnental Sciences). Minneapolis, Minneuta.

1982.

Prairie Island Nuclear :enerating Plant, Annual Radiation Environmental Monitoring Report to tt e U.S. Nuclear Regulatory Commission, January 1,1981 to December 31,1581 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.

1983.

Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1982 to December 31,1982 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.

1984.

Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1983 to Occember 31,1983 (prepared by Teledyne isotopes Midwest Laboratory). Minneapolis, Minnesota.

1985.

Prairie Island Nuclear Generating Plant, Annual Raciation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1984 to December 31.1984 (prepaNd by Teledyne Isotopes Midwest Laboratory). Minneapolis, Minnesota.

1986.

Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory i

Commission, January 1,1985 to December 31,1985 (prepared by Teledyne Isotopes Midwest Laboratory). Minneapolis, Minnesota.

1987.

Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1986 to December 31,1986 (prepared by Teledyne Isotopes Midwest Laboratory). Minneapolis, Minnesota.

25 j

~.

i 1988.

Prairie Island Nuclear Generating P1 ant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1987 to December 31,1987 (prepared by Teledyne Isotopes Midwest Laboratory). Minneapolis, Minnesota.

Teledyne Isotopts Midwest Laboratory.

'9713.

Quality Control Program, Revision 7. 20, November 1984.

1990.

Quality Control Proc edures Manual, Revi sion 13, 21 September 1990.

1991.

Quality Assurance Program Manuai, Revi sion 7,

21 January 1991.

1985.

Analytical Procedures Manual, Revision 5, 29 July 1985.

1984a.

Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January -

December 1983.

1984b. Radiation Environmental Monitoring for Prairie Island Nucl ear Generating Plant.

Compl ete Analysis Data Tables, January December 1983.

1985a.

Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analyses Data Tables, January -

December 1984.

1985b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analyses Data Tables, January -

December 1984.

1986a.

Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analyses Data Tables, January -

December 1985.

1986b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analyses Data Tables, January -

December 1985.

1987. Sampling Procedures, Prairie Island Nuclear Generating Plant, Revision 16,18 December 1987.

1987a.

Radiation Environmental Monitoring for Monticello Nuc s ear Generating Plant, Compl ete Analyses Data Tables, January -

December 1986.

1987b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analyses Data Tables, January -

December 1986.

26

4 1988a.

Raviation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analyses Data Tables, January -

December 1987.

1968b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analyses Data Tables, January -

December 1987, 1989a.

Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analyses DLta Tables, January -

December 1988.

1989b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analyses Data Tables, January -

December 1988.

1990a.

Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analyses Data Tables, January -

December 1989.

1990b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analyses Data Tables, January -

December 1989.

1991a.

Radiation Environmental Monitoring far Monticello Nuclear Generating Plant, Complete Analyses Data TAivs, January -

December 1990.

1991b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analyses Data Tablas, January -

Decemt,er 1990.

U. S. Atomic Energy Commission.

1972.

HASL Procedures Manual, Health and Safety Laboratory, New York, NY.,

10014.

U. S. Public Health Service.

1967.

Radioassay Procedures for Environmental Sampl es, hational Center for Radiological Health, Rockville, Maryland (Public Health Service Publication No. 999-RH-27).

Wilson, D. W., G. M. Ward and J. E. Johnson.

1969.

In Environmental Contam-ination by Radioactive Materials, International Atomic Energy Agency.

p. 125.

l l

l 27

t l

l APPENDIX A INTERLABORATORY COMPARIS0N PROGRAM RtSULTS i

l NOTE:

TIML participates. in intercomparison studies administered by U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.

The results are reported in Appendix A.

Also reported are results of in-house spikes and blanks. _ Appendix A is updated twice a year; the complete Appendix is included in January and July monthly reports only.

Please refer to January and July Reports for information.

)

l January, 1991 l

l A-1 i

l

i Appendix A Interlaboratory Comparison Program Results Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of its quality control program in December 1971.

These programs are operated by agencies which supply environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency l

but not to participant l aboratories.

The pu provide an independent check on the laboratory,rpose of such a program is to s analytical procedures and to L

alert it to any possible problems.

l

\\

I Participant laboratories measure the concentrations of specified radionuclides and report them to the issuing agency.

Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.

The results in Table A-1 were obtained through participation in the environ-mental sample crosscheck program for milk, water, air filters, and food samples during_ the period January 1986 through December,1990.

This program has been conducted-by the U.S.

Environmental Protection Agency Intercompa ri son and Calibration Section, Quality _ Assurance Branch, Environmental Monitoring and Support Laboratory, Las Vegas, Nevada.

The results in Table A-2 were obtained for thermoluminescent dosinieters (TL0s) during the period 1976,1977,1979,1980,1984, and 1985-1916 through partici-pation in he Second, Third, Fourth, Fifth, Seventh, and Eighth Ir ternational Intercompariu of Environmental Dosimeters under the sponsorships listed in Table A-2.

Also Teledyne testing results are listed.

Table A-3 lists results of the analyses on in-house spiked samples.

Table A-4 lists results of the analyses on in-house " blank" samples.

l L

Attachment B lists acceptance criteria for " spiked" samples, j

Addendum to Appendix A provides explanation for out-of-limit results.

[

A-2 l

1

i Table A-1.

U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne isotopes Midwest Laboratory results for milk, water, air filters, and food samples,1986 through 1990.a Concentration in pCi/Lb EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysis 22cC 1s, N=1 Limits STF-447 Food Jan 1986 Sr-89 24.322.5 25.025.0 16.3-33.7 Sr-90 17.320.6 10.021.5 7.4-12.6 1-131 22.7 2.3 20.020.6 9.6-30.4 Cs-137 16.3 0.6 15.0 5.0 6.3-23.7 K

927 46 9502144 701-1199 STW-448 Water Feb 1986 Cr-51 45.0 3.6 38.025.0 29.3-46.7 Co-60 19.721.5 18.0 5.0 9.3-26.7 Zn-65 44.0 3.5 40.025.0 31.3-48.7 Ru-106

<9.0 0.025.0 0.0-8.7 Cs-134 28.322.3 30.025.0 21.3-38.7 Cs-137 23.720.6 22.0 5.0 13.3-30.7 STW-449 Water Feb 1986 H-3 5176248 52272525 4317-6137 STW-450 Water Feb 1986 V total 8.0 0.0 9.026.0 0.0-19.4 STM-451 Mil k Feb 1986 I-131 7.020.0 9.0 6.0 0.0-19.4 STW-452 Water Mar 1986 Ra-226 3.8!0.1 4.120.6 3.0-5.2 Ra-228 11.020.5 12.421.8 9.2-15.5 STW-453 Water Mar 1986 Gr. alpha 6.7 0.6 15.025.0 6.3-23.7 Gr. beta 7.320.6 8.0 5.0 0.0-16.7 STW-454 Water Apr 1986 1-131 7.020.0 9.026.0 0.0-19.4 STW-455 Water Apr 1986 456 (Blind)

Sample A Gr. alpha 15.0 1.0 17.0t5.0 8.3-25.7 Ra-226 3.120.1 2.920.4 2.1-3.7 Ra-228 1.520.2 2.0 0.3 1.5-2.5 Uranium 4.7 0.6 5.0 6.0 0.0-15.4 Sample B Gr. beta 28.7 1.2 35.0 5.0 26.3-43.7 Sr-89 5.7 0.6 7.025.0 0.0-15.7 Sr-90 7.0 0.0 7.0 1.5 4.4-9.6 Co-60 10.7 1.5 10.026.0 1.3-18.7 Cs-134 4.0 1.7 5.0 5.0 0.0-13.7 Cs-137 5.320.6 5.025.0 0.0-13.7 A-3

Table A-1.

(continued)

Concentration in pCi/Lb EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysis 22cc Is, N=1 Limits-STAF-457 Air Apr 1986 Gr. alpha 13.7t0.6 15.015.0 6.3-23.7 Filter Gr. beta 46.320.6 47.015.0 38.3-55.7 1

Sr-90 14.720.6 18.011.5 15.4-20.6 Cs-137 10.7 0.6 10.015.0 1.3-18.7 STU-458 Vrine Apr 1986 Tritium 4313270 44231189 4096-4750 STW-459 Water _

May 1986 Sr-89 4.3 0.6 5.015.0 0.0-13.7 Sr-90 5.0 0.0 5.0 1.5 2.4-7.6 STW-460 Water May 1986 Gr. alpha 5.310.6 8.015.0 0.0-16.7 Gr. beta 11.321.2 15.015.0 6.3-23.7 STW-461 Water Jun 1986 Cr-51

<9.0 0.015.0 0.0-8.7 Co-60 66.011.0 66.025.0 57.3-74.7 Zn-65 87.321.5 86.015.0 77.3-94.7 Ru-106 39.722.5 50.015.0 41.3-58.7 Cs-134 49.3 2.5 49.015.0 40.3-57.7 i

Cs-137 10.3 1.5 10.015.0 1.3-18.7 6

.STW-4 2 Water Jun 1986 Tritium 3427125 31251361 2499-3751 STM-464 Mil k Jun 1906 Sr-89

<1.0 0.025.0 0.0-8.7 Sr-90 15.3 0.6 16.021.5 13.4-18.6 I-131 48.3 2.3 41.0t6.0 30.6-51.4 Cs-137 43.721.5 31.015.0 22.3-39.7 K

1567 114 1600280 1461-1739 STW-465 Water Jul 1986 Gr. alpha 4.7 0.6 6.025.0 0.0-14.7 Gr. beta 18.721.2 18.025.0 9.3-26.7 STW-467

-Water Aug 1986 I-131 30.3 0.6 45.016.0 34.4-55.4 STW-468:

Water Aug 1986 Pu-239 11.310.6 10.1t1.0 8.3-11.9 STW-469 Water Aug 1986 Uranium 4.0 0.0 4.016.0 0.0-14.4 STAF-470 Air Sep 1986 Gr. alpha 19 3 1.5 22.025.0 13.3-30.7 471 Filter Gr. beta 64.0 2.6 66.025.0 57.3-74.7 472 Sr-90 22.021.0 22.0 5.0 19.4-24.6 Cs-137 25.7 1.5 22.0 5.0 13.3-30.7 STW-473 Water Sep 1986 Ra-226 6.020.1 6.1 0.9 4.5-7.7 Ra-228 8.711.1 9.1 1.4 6.7-11.5 A-4

9 O

Table A-1.

(continued)

Concentration in pCi/Lb EPA Resultd Lab Sampl e Date TIML Result Control Code Type Collected Analysis 2cc Is, N=1 Limits STW-474 Water Sep 1986 Gr. alpha 16.313.2 15.0 5.0

_6.3-23.7 Gr. beta 9.021.0 8.015.0 0.0-16.7 STW-475 Water Oct 1986 Cr-51 63.315.5 59.0 5.0 50.3-67.7 Co-60 31,012.0 31.015.0 22.3-39.7 Zn-657 87.315.9 85.015.0 76.3-93.7 Ru-106 74.7 7.4 74.015.0 65.3-82.7 l

Cs-134 25.710.6 28.025.0 19.3-36.7 Cs-137 46.321.5 44.025.0 35.3-52.7 STW-476 Water Oct 1986 H-3 5918 60 59731597 4938-7008 SPW-477 Water Oct 1986 (011nd)

Sample A Gr. alpha 34.016.0 40.015.0 31.3-48.7 Ra-226 5.810.2 6.0*0.9 4.4-7.6 Ra-228 2.7 1.0 5.020.8 3.7-6.3 Uranium 11.020.0 10.016.0 0.0-20.4 Sample 8 Gr. beta 38.7 1.2 51.015.0 42.3-59.7 Sr-89 5.0 0.0 10.015.0 1.3-18.7 S r-90 3.0 0.0 4.011.5 1.4-6.6 Co-60 24.7 1.2 24.025.0 15.3-32.7 Cs-134 11.012.0 12.0 5.0 3.3-20.7 Cs-137 9.321.2 8.015.0 0.0-20.4 STM-479 Mil k Nov 1986 Sr-89 7.711.2-9.025.0 0.3-17.7 l

Sr-90 1.020.0 0.021.5 0.0-2.6 I-131 52.313.1 49.0 6.0 38.6-59.4 Cs-137 45.723.1 39.025.0 30.3-47.7 l

K 14892104 1565278 1430-1700 STU-480 Urine Nov 1986 H-3 5540226 52572912 4345-6169 STW-481 Water Nov 1986 Gr. alpha 12.014.0 20.0 5.0 11.3-28.7 Gr. beta 20.023.5 20.025.0 11.3-28.7 l

i STW-482 Water Dec 1986 Ra-226 6.70.2

-6.8 1.0 5.0-8.6 Ra-228 5.2 0.2 11.121.7 8.2-14.0 STW-483 Water Jan 1987 Sr-89 19.7 5.0 25.025.0 16.3-33.7 Sr-90 21.0 2.0 25.0 1.5 22.4-27.6 A-5

e Table A-1.

(continued)

\\

Concentration in pCi/Lb l

EPA Resultd Lab Sample Date TIML Result Control l-Code Type Collected Analysis 22cc Is, N=1 Limits l

STW-484 Water Jan 1987 Pu-239 17.022.3 16.7 1.7 13.8-19.6 l

STF-486 Food Jan 1987 Sr-90 36.014.0 49.0210.0 31.7-66.3 l

1-131 78.023.4 78.028.0 64.1-91.9 Cs-137 89.7 3.0 84.025.0 75.3-92.7 K

942256 980249 895-1065 STF-487 Food Jan 1987 Sr-90 2.020.0 (Blank) 1-131

<3 l

Cs-137

<2 K

9932102 STW-488 Water Feb 1987 Co-60 49.020.0 50.025.0 41.3-58.7 Zn-65 96.027.2 91.0 5.0 82.3-99.7 Ru-106 92.0220.2 100.0+5.0 91.3-108.7 i

Cs-134 53.023.4 59.026.0 50.3-67.7 Cs-137 89.3 4.6 87.025.0 78.3-95.7 STW-489 Water Feb 1987 H-3 4130 140 4209t420 3479-4939 STW-490 Water Feb 1987 Uranium 8.3 1.2 8.0 6.0 0.0-18.4 STM-491 Mil k Feb 1987 l-131 10.020.0 9.0 0.9 7.4-10.6 STW-492 Water Mar 1987 Gr. alpha 3.7 1.2 3.025.0 0.0-11.7 Gr. beta 11.3 1.2 13.0 5.0 4.3-21.7 STW-493 Water Mar 1987 Ra-226 7.0 0.1 7.321.1

5. 4 -9 '. 2 Ra-228 7.122.3 7.521.1-5.5-9.5 STW-494 Water Apr 1987 1-131 8.020.0 7.020.7 5.8-8.2 STAF-495 Air Apr 1987 Gr. alpha 15.020.0

-14.0 5.0 5.3-22.7 Filter Gr. beta 41.022.0 43.015.0 34.3-51.7 S r-90 16.3 1.2 17.0 1.5 14.4-19.6 Cs-137 7.020.0

-8.0 5.0 0.0-16.7 STW-496 Water Apr 1987 497 (Blind)

Sample A Gr. alpha 30.7 1.2 30.028.0 16.1-43.9 Ra-226 3.90.2 3.9 0.6 2.9-4.9 Ra-228 4.920.9 4.0 0.6 3.0-5.0 l

Urani e.n 5.020.0 5.0 6.0 0.0-15.4 L

L l-6

Table A-1.

(continued)

Concentration in pCi/Lb EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysi s 2cc Is, N=1 Iimits STW-496 Water Apr 1987 497 (Blind)

Sample B Gr. beta 69.319.4 66.025.0 57.3-74.7 Sr-89 16.313.0 19.015.0 10.3-27.7 Sr-90 10.010.0 10.011.5 7.4-12.6 Co-60 8.313.0 8.025.0 0.0-16.7 Cs-134 19.0 2.0 20.015.0 11.3-28.7 Cs-137 14.7*1.2 15.015.0 6.3-23.7 STU-498 Urine Apr 1987 H-3 60171494 56202795 4647-6593 STW-499 Water May 1987 S r-89 38.016.0 41.0 5.0 32.3-49.7 Sr-90 21.022.0 20.021.5 17.4-22.6 STW-500 Water May 1987 Gr. alpha 9.0 3.4 11.0 5.0 2.3-19.7 Gr. beta 10.311.2 7.025.0 0.0-15.7 STW-501 Water Jun 1987 Cr-51 40.018.0 41.025.0 32.3-49.7 Co-60 60.313.0 64.025.0 55.3-72.7 Zn-65 11.315.0 10.015.0 1.3-18.7 Ru-106 78.316.4 75.025.0 66.3-83.7 Cs-134 36.723.0 40.0 5.0 31.3-48.7 Cs-137 80.324.2 80.025.0 71.3-88.7 STW-502 Water Jun 1987 H-3 2906186 28951357 2277-3513 STW-503 Water Jun 1987 Ra-226 6.920.1 7.311.1 5.4-9.2 Ra-228 13.3 1.0 15.222.3 11.2-19.2 STM-504 Mil k Jun 1987 Sr-89 57.024.3 69.015.0 60.3-77.7 S r-90 32.011.0 35.015.0 32.4-37.6 1-131 64.0 2.0 59.026.0 48.6-69.4 Cs-137 77.7 0.6 74.025.0 65.3-82.7 K

1383217 1525276 1393-1657 STW-505 Water Jul 1987 Gr. alpha 2.3 0.7 5.0 5.0 0.0-13.7 Gr. beta 4.011.0 5.015.0 0.0-13.7 STF-506 Food Jul 1987 1-131 82.7!4.6 80.018.0 66.1-93.9 Cs-137 53.7 3.0 50.015.0 41.3-58.7 K

1548157 1680184 1534-1826 STW-507 Water Aug 1987 I-131 45.724.2 48.016.0 37.6-58.4 A-7

T' s

Table A-1.

(continued)

Concentration in pC1/Lb EPA Resultd Lab Sample Date 11ML Result Control Code Type Collected Analysi s 12cc Is, N=1 Limits STW-508 Water Aug 1987 Pu-239 5.820.2 5.3 0.5 4.4-6.2 STW-509 Water Aug 1987 Uranium 13.310.3 13.016.0 2.6-23.4 STAF-510 Air

-Aug 1987 Gr. alpha 9.720.4 10.025.0 1.3-18.7 Filter Gr. beta 28.310,5 30.025.0 21.3-38.7 S r-90 10.010.9 10.021.5 7.4-12.6 Cs-137 10.021.0 10.015.0 1.3-18.7 STW-511 Water Sep 1987 Ra-226 9.920.1 9.7 1.5 7.2-12.2 Ra-228 8.111.4 6.311.0 4.6-8.0 STW-512 Water Sep 1987 Gr. alpha 2.020.6 4.015.0 0.0-12.7 Gr. beta 11.3 1.3 12.025.0 3.3-20.7 STW-513 Water Sep 1987 H-3 44732100 44921449 3714-5270 i

STW-514 Water Oct 1987

-(Blind)

Sample A Gr. alpha 29.312.6 28.027.0 15.9-40.1 Ra-226 4.920.1 4.8 0.7 3.6-6.1 Ra-228 4.2 1.0 3.610.5 2.7-4.5 Uranium 3.010.1 3.0 6.0 0.0-13.4 Sam'ple B Sr-89 14.321.3 16.015.0 7.3-24.7 Sr-90 9.720.4 10.0 1.5 7.4-12.6 Co-60 16.723.0-16.025.0 7.3-24.7 Cs-134 16.722.3 16.0 5.0 7.3-24.7 Cs-137 24.313.3 24.015.0 15.3-32.7 STW-516 Water Oct 1987 Cr-51 80.3117.5 70.015.0 61.3-78.7 Co-60 16.0 2.3 15.025.0 6.3-23.7 Sample A Zn-65 46.315.6 46.025.0 37.3-54.7 Ru-106 57.3 15.4 61.025.0 52.3-69.7 Cs-134 23.7 2.5 25.0 5.0 16.3-33.7 Cs-137 51.723.2 51.015.0 42.3-59.7 STU-517 Urine Nov 1987 H-3 7267 100 74322743 6145-8719 STW-518 Water Nov 1987 Gr. alpha 3.022.0 7.0 5.0 0.0-15.7 Gr. beta 15.722.3 19.025.0 10.3-27.7 STW-519 Water Dec 1987 I-131 26.0 3.0 25.0 6.0 15.6-36.4 A-8

O 6

Table A-1.

(continued)

Concentration in pCi/Lb EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysis 22cc Is, N=1 Limits STW-520 Water Dec 1987 Ra-226 5.1 0.8 4.820.7 3.6-6.0 Ra-228 3.420.1 5.3 0.8 3.9-6.7 STW-521 Water Jan 1988 Sr-89 27.3 5.0 30.025.0 21.3-38.7 Sr-90 15.321.2 15.021.5 12.4-17.6 STW-523 Water Jan 1988 Gr. alpha 2.321.2 4.025.0 0.0-12.7 Gr. beta 7.7 1.2 8.025.0 0.0-16.7 STF-524 Food Jan 1988 Sr-89 44.024.0 46.025.0 37.3-54.7 Sr-90 53.022.0 55.0 2.8 50.2-59.8 1-131 102.314.2 102.0 10.2 84.3-119.7 Cs-137 95.7!6.4 91.025.0 82.3-99.7 K

10112158 1230 62 1124-1336 STW-525 Water Feo 1988 Co-60 69.3 2.3 69.0 5.0 60.3-77.7 Zn-65 99.0 3.4 94.029.4 77.7-110.3 Ru-106 92.7214.4 105.0210.5 86.8-123.2 Cs-134 61.7 8.0 64.0 5.0 55.3-72.7 Cs-137 99.7 3.0 94.025.0 85.3-102.7 STW-526 Water Feb 1988 H-3 34532103 33272362 2700-3954 STW-527 Water Feb 1988 Uranium 3.020.0 3.06.0 0.0-13.4 STM-528 Mil k Feb 1988 1-131 4.7 1.2 4.0 0.4 3.3-4.7 STW-529 Water Mar 1988 Ra-226 7.1 0.6 7.6 1.1 5.6-9.6 Ra-228 nae 7.71.2 5.7-9.7 STW-530 Water Mar 1988 Gr. alpha 4.311.2 6.0 5.0 0.0-14.7 Gr. beta 13.3 1.3 13.025.0 4.3-21.7 STAF-531 Air Mar 1988 Gr. alpha 21.0 2.0 20.0 5.0 11.3-28.7 Filter Gr. beta 48.020.0 50.025.0 41.3-58.7 Sr-90 16.7 1.2 17.021.5 14.4-19.6 Cs-137 18.721.3 16.0 5.0 7.3-24.7 STW-532 Water Apr 1988 I-131 9.0 2.0 7.5 0.8 6.2-8.8 A-9

Table A-1.

(continued)

Concentration in pCi/Lb EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysi s 2cc Is, N=1 Limits STW-533 Water Apr 1988 534 (Blind)

Sample A Gr. alpha NDf 46.0!11.0 27.0-65.0 Ra-226 ND 6.421.0 4.7-8.1 Ra-228 ND 5.620.8 4.2-7.0 Uranium 6.0 0.0 6.0 6.0 0.0-16.4 Sample B Gr. beta ND 57.0 5.0 48.3-65.7 Sr-89 3.3 1.2 5.0 5.0 0.0-13.7 Sr-90 5.321.2 5.021.5 2.4-7.6 Co-60 63.321.3 50.025.0 41.3-58.7 Cs-134 7.721.2 7.0 5.0 0.0-15.7 Cs-137 8.3 1.2 7.025.0 0.0-15.7 STU-535 Urine Apr 1988 H-3 6483!155 6202 620 5128-7276 STW-536 Water Apr 1988 Sr-89 14.7 1.3 20.0 5.0 11.3-28.7 Sr-90 20.0 2.0 20.0 1.5 17.4-22.6 STW-538 Water Jun 1988 Cr-51 331.7 13.0 302.0 30.0 250.0-354.0 Co-60 16.0 2.0 15.0 5.0 6.3-23.7 Zn-65 107.7 11.4 101.0210.0 83.7-118.3 Ru-106 191.3211.0 195.0120.0 160.4-229.6 Cs-134 18.3 4.6 20.0 5.0 11.3-28.7 Cs-137 26.3 1.2 25.0 5.0 16.3-33.7 STW-539 Water Jun 1988 H-3 5586 92 55652557 4600-6530 STM-541 Mil k Jun 1988 Sr-89 33.7211.4 40.0 5.0 31.3-48.7 Sr-90 55.325.8 60.0 3.0 54.8-65.2 1-131 103.7 3.1 94.029.0 78.4-109.6 Cs-137 52.723.1 51.015.0 42.3-59.7 K

1587 23 1600280 1461-1739 STW-542 Water.

Jul 1988 Gr. alpha 8.714.2 15.025.0 6.3-23.7 Gr. beta 5.3 1.2 4.0 5.0 0.0-12.7 STF-543 Food Jul 1988 Sr-89 NDf 33.0 5.0 24.3-41.7 Sr-90 ND 34.022.0 30.5-37.5 I-131 115.0 5.3 107.0 11.0 88.0-126.0 Cs-137 52.726.4 49.025.0 40.3-57.7 K

1190266 1240262 1133-1347 A-10

Table A-1.

(continued)

Concentration in pCi/Lb EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysis 12cc Is, N=1 Limits STW-544 Water Aug 1988 I-131 80.020.0 76.0 8.0 62.1-89.9 STW-545 Water Aug 1988-Pu-239 11.0 0.2 10.221.0 8.5-11.9 STW-546 Water Aug 1988 Uranium 6.0 0.0 6.0 6.0 0.0-16.4 STAF-547 Air Aug 1988 Gr. alpha 8.020.0 8.025.0 0.0-16.7 Fil ter Gr. beta 26.321.2 29.025.0 20.3-37.7 Sr-90 8.022.0 8.021.5 5.4-10.6 Cs-137 13.0 2.0 12.025.0 3.3-20.7 STW-548 Water Sep 1988 Ra-226 9.320.5 8.422.6 6.2-10.6 Ra-228 5.8 0.4 5.4 1.6 4.0-6.8 STW-549 Water Sep 1988 Gr. alpha 7.022.0 8.0 5.0 0.0-16.7 Gr. beta 11.321.2 10.0 5.0 1.3-18.7 STW-550 Water Oct 1988 Cr-51 252.0 14.0 251.0 25.0 207.7-294.3 Co-60 26.0 2.0 25.0 5.0

'16.3-33.7 Zn-65 158.3 10.2 151.0 15.0 125.0-177.0 Ru-106 153.0 9.2 152.0215.0 126.0-178.0 Cs-134 28.7 5.0 25.0 5.0 16.3-33.7 Cs-137 16.3 1.2 15.0!5.0 6.3-23.7 STW-551 Water Oct 1988 H-3 23332127 2316:350 1710-2927 STW-552 Water Oct 1988 553 (Blind)

Sample A Gr. alpha 38.328.0 41.0210.0 23.7-58.3 Ra-226 4.520.5 5.0!0.8 3.6-6.4 Ra-228 4.420.6 5.220.8 3.6-6.4 Uranium 4.7 1.2 5.0 6.0 0.0-15.4 Sample B Gr. beta 51.3 3.0 54.0 5.0 45.3-62.7 Sr-89 3.71.2 11.025.0 2.3-19.7 Sr-90 10.7 1.2 10.0 1.5 7.4-12.6 Cs-134 15.3 2.3 15.0 5.0 6.3-23.7 Cs-137 16.7 1.2 15.0 5.0 6.3-23.7 A-11

Table A-1.

(continued)

Concentration in pCi/Lb EPA Resultd Lab -

Sample Date TIML Result Control Code Type Collected Analysi s 22cc Is, N=1 Limits STM-554 Mil k Oct 1988 Sr-89 40.327.0 40.0 5.0 31.3-48.7 Sr-90 51.022.0 60.023.0 54.8-65.2 1-131 94.0t3.4 91.029.0 75.4-106.6 Cs-137 45.024.0 50.025.0 41.3-58.7 K

1500245 1600280 1461-1739 STU-555 Urine Nov 1988 H-3 3030 209 3025 359 2403-3647 STW-556 Water Nov 1988 Gr. alpha 9.0 3.5 9.0 5.0 0.3-17.7 Gr. beta 9.7 1.2 9.025.0 0.3-17.7 STW-557 Water Dec 1988 I-131 108.7 3.0 115.0 12.0 94.2-135.8 i

STW-559 Water Jan 1989 Sr-89 40.0 8.7 40.0 5.0 31.3-48.7 l

S r-90 24.3 3.1 25.021.5 24.4-27.6 STW-560 Water Jan 1989 Pu-239 5.8 1.1 4.2 0.4 3.5-4.9 STW-561 Water Jan 1989 Gr. al pha 7.321.2 8.025.0 0.0-16.7 Gr. beta 5.321.2 4.0 5.0 0.0-12.7 STW-562 Water Feb 1989 C r-51 245 46 235224 193.4-276.6 Co-60 10.022.0 10.015.0 1.3-18.7 Zn-65 170 10 159 16 139.2-186.7 Ru-106 18127.6 178218 146.8-209.2 Cs-134 9.723.0 10.025.0 1,3-18.7 Cs-137 11.711.2 10.025.0 1.3-18.7 i

STW-563 Water Feb 1989 I-131 109.0 4.0 106.0211.0 86.9-125.1 STW-564 Water Feb 1989 H-3 2820220 27542356 2137-3371 STW-565 Water Mar 1989 Ra-226 4.2 0.3 4.920.7 3.7-6.1 Ra-228 1.9 1.0 1.7 0.3 1.2-2.2 STW-566 Water Mar 1989 U

5.020.0 5.0 6.0 0.0-15.4 l

STW-567 Air Mar 1989 Gr. al pha 21.721.2 21.0 5.0 12.3-29.7 Filter Gr. beta 68.3 4.2 62.025.0 53.3-70.7 I

S r-90 20.0 2.0 20.0 1.5 17.4-22.6 Cs-137 21.3 1.2 20.0 5.0 11.3-28.7 A-12

l Table A-1.

(continued)

Concentration in pCi/Lb EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysis 22cc Is, N=1 Limits STW-568 Water Apr 1989 569 (Blind)

Sample A Gr. al pha 22.722.3 29.017.0 16.9-41.2 Ra-226 3.620.6 3.520.5 2.6-4.4 Ra 228 2.6 1.0 3.6 0.5 2.7-4,5 V

3.010.0 3.0 6.0 0.0-13.4 Sample B Gr. beta 52.3 6.1 57.025.0 43.3-65.7 Sr-89 9.315.4 8.015.0 0.0-16.7 Sr-90 7.020.0 8.0 1.5 5.4-10.6 Cs-134 21.0 5.2 20.025.0 11.3-28.7 Cs-137 23.022.0 20.025.0 11.3-28.7 STW-570 Mil k Apr 1989 Sr-89 26.0210.0 39.0!5.0 30.3-47.7 Sr-90 45.714.2 55.023.0 49.8-60.2 Cs-137 54.016.9 50.0 5.0 41.3-58.7 K-40 1521 208 1600 80 1461-1739 STW-5719 Water May 1989 Sr-89

<0.7 6.015.0 0.0-14.7 Sr-90 5.0!1.0 6.0 1.5 3.4-8.6 STW-572 Water May 1989 Gr. alpha 24.012.0 30.0 8.0 16.1-43.9 Gr. beta 49.3115.6 50.025.0 41.3-58.7 STW-573 Water Jun 1989 Ba-133 50.721.2 49.0 5.0.

40.3-57.7 Co-60 31.312.3 31.0 5.0 22.3-39.7 Zn-65 167110 165117 135.6-194.4 Ru-106 12329.2 128 13 105.5-150.5 Cs-134 40.3 1.2 3915 30.3-47.7 Cs-137 22.321.2 2015 11.3-28.7 STW-574 Water Jun 1989 H-3 45132136 45032450 3724-5282 STW-575 Water Jul 1989 Ra-226 16.8 3.1 17.722.7 13.0-22.4 Ra-228 13.823.7 18.3 2.7 13.6-23.0 STW-576 Water Jul 1989 U

40.321.2 41.026.0 30.6-51.4 STW-577 Water Aug 1989 I-131 84.7 5.8 83.028.0 69.1-96.9 STAF-579 Air Aug 1989 Gr. alpha 6.0 0.0 6.025.0 0.0-14.7 Filter Cs-137 10.3 2.3 10.025.0 1.3-18.7 A-13

Table A-1.

(continued)

Concentration in pCi/Lb EPA Resultd Lab Sample Date TIML Result Control Cooe Type Collected Analysis 12cc 15, N=1 Limits STW-580 Water Sep 1989 Sr-89 14.711.2 14.016.0 5.3-22.7 Sr-90 9.7 1.2 10.021.5 7.4-12.6 STW-581 Water Sep 1989 Gr. alpha 5.010.0 4.025.0 0.0-12.7 Gr. Beta 8.7 2.3 6.015.0 0.0-14.7 STW-583 Water Oct 1989 Ba-133 60.3210.0 59.016.0 48.6-69.4 Co-60 29.024.0 30.025.0 21.1-38.7 Zn-65 132.326.0 129.0113.0 106.5-151.5 Ru-106 155.326.1 161.0 16.0 133.3-188.7 Cs-134 30.726.1 29.015.0 20.3-37.7 Cs-137 66.314.6 59.0 5.0 50.3-67.7 STW-584 Water Oct 1989 H-3 34071150 34961364 2866-4126 STW-585 Water Oct 1989 586 (811nd)

Sample A Gr. Alpha 41.7 9.4 49.0112.0 28.2-69.8 Ra-226 7.910.4 8.421.3 6.2-10.6 Ra-228 4.4 0.8 4.110.6 3.1-5.1 V

12.020.0 12.026.0 1.6-22.4 Sample 3 Gr. Beta 31.7 2.3 32.025.0 23.3-40.7 Sr-89 13.3i4.2 15.0 5.0 6.3-23.7 Sr-90 7.022.0 7.023.0 4.4-9.6 Cs-134 5.0!0.0 5.025.0 0.0-13.7 Cs-137 7.0 0.0 5.025.0 0.0-13.7 STW-587 Water Nov 1989 Ra-226 7.9 0.4 8.721.3 6.4-11.0 Ra-228 8.911.2 9.311.2 6.9-11.7 STW-588 Water Nov 1989 U

15.020.09 15.026.0 4.6-25.4 STW-589 Water Jan 1990 Sr-89 22.725.0 25.025.0 16.3-33.7 Sr-90 17.321.2 20.021.5 17.4-22.6 STW-591 Water Jan 1990 Gr. Alpha 10.3 3.0 12.025.0 3.3-20.7 Gr. Beta 12.3 1.2 12.0 5.0 3.3-20.7 l

t A-14 l

I Table A-1.

(continued)

Concentration in pCi/Lb j

EPA Resultd Lab Sample Date TIML Result Control Ccde Type Collected Analysis 2cc Is, N=1 Limi ts STW-592 Water Jan 1990 Co-60 14.722.3 1525.0 6.3-23.7 Zn-65 135.026.9 139.0 14.0 114.8-163.2 Ru-106 133.3 13.4 139.0214.0 114.8-163.2 Cs-134 17.321.2 18.025.0 9.3-26.7 Cs-137 19.3t1.2 18.025.0 9.3-26.7 Ba-133 78.010.0 74.027.0 61.9-86.1 STW-593 Water Feb 1990 H-3 4827283 49762498 4113-5839 STW-594 Water Mar 1990 Ra-226 5.020.2 4.920.7 4.1-5.7 Ra-228 13.510.7 12.721.9 9.4-16.0 STW-595_

Water Mar 1990 V

4.020.0 4.026.0 0.0-14.4 STW-596 Air Mar 1990 Gr. Alpha 7.321.2 5.025.0 0.0-13.7 Filter Gr. Beta 34.0 0.0 31.025.0 22.3-39.7 Sr-90 10.020.0 10.021.5 7.4-12.6 Cs-137 9.3 1.2 10.025.0 1.3-18.7 STW-597 Water Apr 1990 598 (Blind)

Sample A Gr. Alpha 81.023.5 90.0223.0 50.1-129.9 Ra-226 4.920.4 5.020.8 3.6-6.4 Ra-228 10.620.3 10.221.5 7.6-12.8 U

18.7 3.0 20.0 6.0 9.6-30.4 Sample B Gr. Beta 51.0210.1 52.025.0 43.3-60.7 Sr-89 9.321.2 10.025.0 1.3-18.7 Sr-90 10.3 3.1 10.0 1.5 8.3-11.7 Cs-134 16.0 0.0 15.0 5.0 6.5-23.7 Cs-137 19.022.0 15.025.0 6.3-23.7 STM-599 Mil k Apr 1990 Sr-89 21.723.1 23.015.0 14.3-31.7 Sr-90 21.0 7.0 23.025.0 14.3-31.7 1-131 98.7 1.2 99.0210.0 81.7-116.3 Cs-137 26.0 6.0 24.025.0 15.3-32.7 K

1300.0269.2 1550.0278.0 1414.7-1685.3 STW-600 Water May 1990 Sr-89 6.022.0 7.0 5.0 0.0-15.7 Sr-90 6.7 1.2 7.025.0 0.0-15.7 STW-601 Water May 1990 Gr. Alpha 11.022.0 22.0 6.0 11.6-32.4 Gr. Beta 12.3 1.2 15.025.0 6.3-23.7 A-15 i

e e

Table A-1.

(continued)

Concentration in pC1/Lb EPA Resultd L ab Sample Date TIML Result Control Code Type Collected Analysis 12cc Is, N=1 Limits STW-602 Water Jun 1990 Co-60 25.312.3 24.015.0 15.3-32.7 Zn-65 155.0210.6 148.0115.0 130.6-165.4 Ru-106 202.7117.2 210.0221.0 173.6-246.4 Cs-134 23.721.2 24.025.0 18.2-29.8 Cs-137 27.713.1 25.0 5.0 16.3-33.7 Ba-133 100.718.1 99.0110.0 81.7-116.3 STW-603 Water Jun 1990 H-3 29272306 2933:358 2312-3554 J

STW-604 Water Jul 1990 Ra-226 11.810.9 12.121.8 9.0-15.2 Ra-228 4.121.4 5.11123 2.8-7.4 STW-605 Water Jul 1990 V

20.311.7 20.813.0 15.6-26.0 STW-606 Water Aug 1990 1-131 43.011.2 39.026.0 28.6-49.4 STW-607 Water Aug 1990 Pu-239 10.011.7 9.110.9 7.5-10.7 STW-608 Air Aug 1990 Gr. alpha 14.020.0 10.0 5.0 1.3-18.7 Filter Gr. beta 65.311.2 62.025.0 53.3-70.7 Sr-90 19.026.9 20.025.0 11.3-28.7 Cs-137 19.012.0 20.015.0 11.3-28.7 STW-609 Water Sep 1990 S r-89 9.022.0 10.015.0 1.3-18.7 Sr-90 9.022.0 9.015.0 0.3-17.7 STM-610 Water Sep 1990 Gr. alpha 8.311.2 10.025.0 1.3-18.7 Gr. beta 10.3 1.2 10.015.0 1,3-18.7 STM-611 Mil k Sep 1990 Sr-89 11.723.1 16.015.0 7.3-24.7 Sr-90 15.010.0 20.025.0 11.3-28.7 1-131 63.026.0 58.0 6.0 47.6-68.4 Cs-137 20.0 2.0 20.0 5.0 11.3-28.7 K

1673.3 70.2 1700.0185.0 1552.5-1847.5 STW-612 Water Oct 1990 Co-60 20.323.1 20.0 5.0 11.3-28.7 Zn-65 115.3112.2 115.0212.0 94.2-135.8 Ru-106 152.0 8.0 151.0215.0 125.0-177.0 Cs-134 11.020.0 12.0 5.0 3.3-20.7 Cs-137 14.022.0 12.0 5.0 3.3-20.7 Ba-133 116.7 9.9 110.0 11.0 90.9-129.1 STW-613 Water Oct 1990 H-3 71671330 7203 720 5954-8452 A-16

e o

Table A-1.

(continued)

Coocentration in pCi/Lb EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysis 22cc Is, N=1 Limits STW-614 Water Oct 1990 615 Sample A Gr. alpha 68.717.2 62.0116.0 34.2-89.8 Rc-226 12.920.3 13.612.0 10.1-17.1 Ra-228 4.2t0.6 5.011.3 2.7-7.3 V

10.420.6 10.213.0 5.0-15.4 Sample B Gr. beta 55.028.7 53.025.0 44.3-61.7 S r-89 15.722.9 20.015.0 11.3-28.7 Sr-90 12.022.0 15.015.0 6.3-23.7 Cs-134 9.021.7 7.015.0 0.0-15.7 Cs-137 7.711.2 5.025.0 0.0-13.7 STW-616 Water Nov 1990 Ra-226 6.821.0 7.421.1 5.5-9.3 Ra-228 5.3 1.7 7.721.9 4.4-11.0 STW-6179 Water Nov 1990 V

35.020.4 35.513.6 29.3-41.7 a Results obtained by Teledyne Isotopes Midwest Laboratory as a participant in the environmental sample crosscheck program operated by the Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S. Environmental Protection Agency (EPA), Las Vegas,

Nevada, b-All results are in the pCi/1, except for elemental potassium (K) data in

-milk, which are in mg/1; air filter samples, which are in pCi/ filter; and food, wnich is in mg/kg.

t c Unless otherwise indicated, the TIML results are given as the mean 2

standard deviations for three determinations, d USEPA results are presented as the known values and expected laboratory precision (1s,1 determination) and control limits as defined by EPA.

O NA = Not analyzed, f ND = No data; not analyzed due to relocation of the lab.

9 Sample was analyzed but the results not submitted to EPA because deadline was missed (all data on file).

l 1

l A-17

o.

6

-Table A-2.

Crosscheck program results, thermoluminescent dosimeters (TLDs),

mR Teledyne Average 22cd Lcb Result Known (All Code TLD Type Measurement 12ca Yaluec Participants) 2nd International Intei comparisonb 115-2 CaF :Mn Field

'17.021.9 17.1 16.417.7 2

Bulb Lab 20.824.1 21.3 18.817.6 3rd International Intercomparisone 115-3 CaF :Mn Field 30.7 3.2 34.924.8 31.523.0 2

Bulb Lab 89.626.4 91.7114.6 86.2224.0 L

4th International' Intercomparisonf 115-4 CaF :Mn

-Field 14.1 1.1 14.1 1.4 16.019.0 2

Bulb Lab (Low)-

9.321.3 12.212.4 12.027.4 l

Lab (High) 40.421.4 45.829.2 43.9213.2 5th International Intercomparison9 115-5A

-CaF :Mn Field 31.411.8 30.0 6.0 30.2114.6 2

Bulb Lab at be9 inning 77.425.8 75.227.6 75.8 40.4 Lab at the end 96.625.8 88.418.8-90.7131.2 115-5B LiF-100 Field 30.324.8 30.0t6.0 30.2 14.6 Chips-Lab at beginning 81.117.4 75.2 7.6 75.8240.4 l

Lab at the end 85.4211.7 88.418.8 90.7231.2 7th International Intercomparisonh 115-7 A LiF-100 Field 75.4 2.6 75.8 6.0 75.1129.8 Chips Lab (Co-60) 80.0 3.5 79.924.0 77.9227.6 Lab (Cs-137) 66.622.5 75.023.8 73.0222.2 l

A-18

o 6

Table A-2.

(continued) mR Tcledyne Average 12cd Lab Result Known (All Code TLD Type Measurement 120a Valuec Participants)

CaF :Mn Field 71.522.6 75.816.0 75.)129.8 115-78 2

Bulbs Lab (Co-60) 84.816.4 79.9t4.0 77.9127.6 Lab (Cs-137) 78.8 1.6 75.023.3 73.0122.2 115-7C CaSO :Dy Field 76.822.7 75.816.0 75.1 29.8 4

Cards Lab (Co-60) 82.523.7 79.924.0 77.9127.6 Lab (Cs-137) 79.023.2 75.023.8 73.0*22.2 l

8th International Intercomparisoni 115-8A Lif-100 Field Site 1 29.521.4 29.721.5 28.9112.4 Chips Field Site 2 11.320.8 10.420.5 10.129.06 Lab (Cs-:37) 13.7 0.9 17.220.9 16.216.8 115-8B CaF2:Mn Field Siti: 1 32.311.2 29.721.5 28.9212.4 Bulbs Field Site 2 9.011.0 10.4 0.5 10.119,0 Lab (Cs-137) 15.820.9 17.210.9 16.216.8 i

115-8C CaSO4:Dy Field Site 1 32.3 0.7 29.711.5 28.9112.4 Cards Field Site 2 10.610.6 10.410.5 10.1 9.0 Lab (Cs-137) 18.1 0.8 17.210.9 16.226.8 Teledyne Testingd 89-1 LiF-100 Lab 21.020.4 22.4 Chips 89-2 Tel edyne Lab 20.9 1.0 20.3 CaSO :Dy 4

l Cards l

l A-19

)

i Table A-2.

(continued) mR Lab Teledyne Average 12cd Result Known (All Code TLD Type Measurement 22ca Valuec Participants)

_Teledyne Testing) 90-1k Teledyne Lab 20.6 1.4 19.6 CaSO :Dy 4

Cards 90-11 Tel edyne Lab 100.814.3 100.0 CaSO :Dy 4

Cards b Second International Intercomparison of Environmental Dosime in April of 1976 by the Health and Safety Laboratory (GASL), New York, New York, and the School of Public Health of the University of Texas, Houston, Texas.

c Value determined by sponsor of the intercomparison using continuously operated pressurized ion chamber.

d Mean 22 standard deviations of results obtained by all laboratories parti-cipating in the program.

e Third International Intercomparison of Environmental Dosimeters conducted in sumer of 1977 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas Houston, Texas, f

Fourth International Intercumparison of Environmental Dosimeters conducted in summer of 1979 by the School of Public Health of the University of Texas, Houston, Texas.

9 Fifth International Intercomparison of Environmental Dosimeter conducted in fall of 1980 at Idaho Falls, Idaho and sponsored t:y the School of Public Health of the University of Texas, Houston, Texas and Environmental Measure-ments Laboratory, New York, New York, U.S. Department of Energy.

h Seventh International Intcrcomparison of Environmental Dosimeters conducted in the spring and sumer of 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, the U.S. Nuclear Regulatory Commission, and the U.S. Environmental Protection Agency.

I Eighth International Intercomparison of Environmental Dosimeters conducted in the fall and winter of 1985-1986 the U.S. Department of Energy.

at New York, New York, and sponsored by 3 Chips were submitted in September 1989 and cards were submitted in November 1989 to Teledyne Isotopes, Inc., Westwood, NJ for irradiation.

k Cards were irradiated by Teledyne Isotopes, Inc., Westwood, NJ on June 19, 1990.

I Cards were irradiated by Dosimetry Associates, Inc., Northville, MI on October 30, 1990.

A-20

i Table A-3.

In-house spiked samples.

Concentration (pCi/L)

Lab Sample Date TIML Expected Code Type Collected Analysis Result Known Precision n=3 Activity 1s, n=3a l

QC-MI-6 Mil k Feb 1986 Sr-89 6.011.9 6.423.0 8.7 Sr-90 14.221.7 12.922.0 5.2 1-131 34.213.8 35.213.5 10.4 Cs-134 32.011.8 27.315.0 8.7 Cs-137 35.812.1 35.015.0 8.7 QC-W-14 Water Mar 1986 Sr-89 1.610.4 1.621.0 7.1 Sr-90 2.410.2 2.422.0 4.2 QC-W-15 Water Apr 1986 1-131 44.9 2.4 41.527.0 10.6 i

Co-60 10.621.7 12.125.0 7.lb Cs-134 30.222.4 25.818.0 7.lb Cs-137 21.921.9 19.915.0 7.lb QC-MI-7 Mil k Apr 1986 I-131 39.7 3.3 41.517.0 10.4 Cs-134 28.7 2.8 25.828.0 8.7 1

Cs-137 21.222.8 19.925.0 8.7 t-SPW-1 Water May 1986 Gr. alpha 15.8 1.8 18.0 5.0 Sc QC-W-16 Water Jun 1986 Gr. alpha 16.220.7 16.9 2.5 8.7 Gr. beta 38.413.5 3J.2 5.0 8.7 QC-MI-9 Mil k Jun 1986 Sr-89

<1.0 0.0 7.lb Sr-90 12.611.8 13.3 3.0 4.2b I-131 38.927.0 34.8 7.0 10.4 Cs-134-33.0 3.4 36.125.0 8.7 Cs-137 38.512.8 39.015.0 8.7 SPW-2 Water Jun 1986 Gr. alpha 16.811.8 18.025.0 Sc SPW-3 Water Jun'1986 Gr. alpha 17.7 0.8 18.0 5.0 Sc QC-W-18 Water Sep 1986 Cs-134 34.7 5.6 31.315.0 8.7 Cs-137 51.127.0 43.318.0 8.7 QC-W-19 Water Sep'1986 Sr-89 13.6!4.1 15.6 3.5 7.lb Sr-90 6.4 1.6 6.2 2.0 4.2b A-21

(

t e

Table A-3.

In-house spiked samples (continued)

Concentration (pCi/L)

Lab Sample Date TIML Expected Code Type Collected Analysis Result Known Precision n=3 Activity 1s, n=3a QC-W-21 Water Oct 1986 Co-60 19.222.2 18,513.0 8.7 Cs-134 31.715.2 25.618.0 8.7 Cs-137 23.8 1.0 21.625.0 8.7 QC-MI-11 Mil k Oct 1986 Sr-89 12.311.8 14.313.0 8.7 QC-W-20 Water Nov 1986 H-3 38552180 39601350 520b QC-W-22 Wat er Dec 1986 Gr. alpha 9.8 1.4 11.224.0 8.7 Gr. beta 21.722.0 23.8 5.0 8.7 QC-W-23

-Water Jan 1987 1-131 29.822.5 27.913.0 10.4 QC-MI-12 Mil k Jan 1987 I-131 36.5 1.3 32.615.0 10.4 Cs-137 32.624.2 27.418.0.

8.7 QC-MI-13 Mil k Jan 1987 Sr-89 10.4t2.1 12.2 4.0 8.7 Sr-90 14.611.6 12.623.0 5.2 1-131 49.511.2 54.9i8.0 10.4 Cs-134

<1.6 0.0 8.7 Cs-137 33.320.6 27.418.0 8.7 QC-W-24 Water Mar 1987 Sr-89 24.723.6 25.915.0 8.7 Sr-90 23.923.8 22.828.0 5.2 QC-W-25 Water Apr 1987 I-131 28.0 1.9 29.315.0 10.6 QC-MI-14 Mil k Apr 1987 I-131 25.0 2.2 23.9 5.0 10.4 Cs-134

<2.1 0.0 8.7 Cs-137 34.212.0 27.217.0 8.7 QC-W-26 Water Jun 1987 H-3 34221100 33622300 520 C o-60 24.821.4 26.527.0 8.7 Cs-134

<2.0 0.0 8.7 Cs-137 21.2 0.5 21.6 7.0 8.7 QC-W-27 Water Jun 1987 Gr. alpha 8.511.9 10.1 4.0 8.7 Gr. beta 22.6 1.9 21.225.0 8.7 QC-W-28 Water Jun 1987 Gr. alpha 8.721.3 10.1 4.0 8.7 Gr. beta 12.225.2 9.423.0 8.7 A-22

\\

0 Table A-3.

In-house spiked samples (continued)

Concentration (pC1/L)

Lab Sampl e Date TIML Expected Code Type Collected Analysis Result Known Precision n=3 Activity 1s, n=38 QC-W-29 Water Jun 1987 Gr. alpha 16.421.3 18.915.0 8.7 Gr. beta 15.914.0 11.824.0 8.7 QC-M1-15 Mil k Jul 1987 Sr-90 19.411.6 18.823.5 5.2 I-131 43.5 0.7 45.317.0 10.4 Cs-134 17,922.2 16.0 5.3 8.7 Cs-137 25.421.8 22.7 5.0 8.7 QC-W-30 Water Sep 1987 Sr-89 17.513.0 14.315.0 8.7 Sr-90 18.4 2.2 17.512.2 5.2 QC-W-31 Water Oct 1987 H-3 20531939 2059 306 520 QC-W-32 Water Dec 1987 Gr. alpha 8.6 1.0 10.115.0 8.7 Gr. beta 15.2 0.1 13.123.0 8.7 QC-W-33 Water Dec 1987 Gr. alpha 7.721.4 10.125.0 8.7 Gr. beta 10.921.0 7.923.0 8.7 QC-W-34 Water Dec 1987 Gr. alpha 4.0 0.9 5.1 3.0 8.7 Gr. beta 9.420.9 7.923.0 8.7 QC-MI-16 Mil k Feb 1988 Sr-89 31.824.7 31.716.0 8.7 Sr-90 25.5 2.7 27.8 3.5 5.2 1-131 26.420.5 23.225.0 10.4 Cs-134 23.822.3 24.226.0 8.7 Cs-137 26.510.8 25.1 6.0 8.7 QC-MI-17 Mil k Feb 1988 1-131 10.6tl.2 14.321.6 10.4 QC-W-35 Water Feb 1988 1-131 9.711.1 11.621.1 10.4 QC-W-36 Water Feb 1988 1-131 10.521.3 11.611.0 10.4 QC-W-37 Water Mar 1988 Sr-89 17.1 2.0 19.8 8.0 8.7 Sr-90 18.720.9 17.325.0 5.2 QC-MI-18 Mil k Mar 1988 1-131 33.2 2.3 26.7 5.0 10.4 Cs-134 31.3 2.1 30.225.0 8.7 Cs-137 29.9 1.4 26.2!5.0 8.7 i

A-23

s e

Table A-3.

In-house spiked samples (continued)

Concentration (pCi/L)

Lab Sempl e Date TIML Expected Code Type Collected Analysis Result Known Precision n=3 Activity 1s, n=3a 3

QC-W-38 Water Apr 1988 I-131 17.1 1.1 14.2 5.0 10.4 QC-W Water Apr 1988 H-3 4439231 41762500 724 QC-W-40 Water Apr 1988 Co-60 23.7 0.5 26.124.0 8.7 Cs-134 25.4 2.6 29.214.5 8.7 Cs-137 26.622.3 26.224.0 8.7

~

QC-W-41 Water Jun 1988 Gr. alpha 12.310.4 13.125.0 8.7 Gr. beta 22.621.0 20.1 5.0 8.7 QC-M1-19 Mil k Jul 1988 Sr-89 15.121.6 16.4 5.0 8.7 Sr-90 18.0 0.6 18.325.0 5.2 1-131 88.414.9 86.628.0 10.4 Cs-137 22.720.8 20.826.0 8.7 QC-W-42 Water Sep 1988 Sr-89 48.5 3.3 50.8 8.0 8.7 Sr-90 10.921.0 11.423.5 5.2 QC-W-43 Water Oct 1988 Co-60 20.923.2 21.4 3.5 8.7 Cs-134 38.721.6 38.026.0 8.7 Cs-137 19.0 2.4 21.0.3.5 8.7 QC-W-44 Water Oct 1988 1-131 22.220.6 23.3 3.5 10.4 QC-W-45 Water Oct 1988 H-3 4109143 41532500 724 QC-MI-20 Mil k Oct 1988 I-131 59.820.9 60.629.0 10.4 Cs-134 49.6 1.8 48.6 7.5 8.7 Cs-137 25.824.6 24.724.0 8.7 QC-W-46 Water Dec 1988 Gr. alpha 11.5 2.3 15.2 5.0 8.7 Gr. beta 26.5 2.0 25.725.0 8.7 QC-MI-21 Mil k Jan 1989 Sr-89 25.5 10.3 34.0 10.0 8.7 Sr-90 28.3 3.2 27.1 3.0 5.2 1-131 540 13 550 20 10.4 Cs-134 24.522.6 22.6t5.5 8.7 Cs-137 24.0 0.6 20.5 5.0 8.7 A-24

s Table A-3.

In-house spiked samples (continued)

Concentration (pCi/L)

Lab Sample Date TIML Expect ed Code Type Collected Analysis Result Known Precision n=3 Activity 1s, n=3a QC-W-47 Water Mar 1989 Sr-89 15.2 3.8 16.115.0 8.7 Sr-90 16.421.7 16.923.0 5.2 QC-MI-22 Milk Apr 1989 I-131 36.321.1 37.2 5.0 10.4 Cs-134 20.812.8 20.718.0 8.7 Cs-137 22.2 2.4 20.4 8.0 8.7 QC-W-48 Water Apr 1989 Co-60 23.St2.0 25.128.0 8.7 Cs-134 24.2 1.1 25,918.0 8.7 Cs-137 23.6 1.2 23.018.0 8.7 QC-W-49 Water Apr 1989 I-131 37.223.7 37.2 5.0 10.4 QC-W-50 Water Apr 1989 H-3 3011 59 30892500 724 QC-W-51 Water Jun 1989 Gr. alpha 13.0 1.8 15.0 5.0 8.7 Gr. beta 26.021.2 25.518.0 8.7 QC-MI-23 Mil k Jul 1989 Sr-89 19.426.5 22.0 10.0 8.7 Sr-90 27.6 3.5 28.6 3.0 5.2 1-131 46.8 3.2 43.425.0 10.4 Cs-134 27.4 1.8 28.3 6.0 8.7 Cs-137 24.1tl.8 20.816.0 8.7 QC-MI-24 Mil k Aug 1989 Sr-89 25.422.7 27.2 10.0 8.7 Sr-90 46.011.1 47.8 9.6 8.3 QC-W-52 Water Sep 1989 l-131 9.610.3 9.7 1.9 10.4 QC-W-53 Water Sep 1989 I-131 19.0!0.2 20.9 4.2 10.4 QC-W-54 Water Sep 1989 Sr-89 25.824.6 24.724.0 8.7 Sr-90 26.5 5.3 29.7 5.0 5.2 QC-MI-25 Mil k Oct 1989 I-131 70.023.3 73.5 20.0 10.4 Cs-134 22.1 2.6 22.618.0 8.7 Cs-137 29.421.5 27.5 8.0 8.7 QC-W-55 Water Oct 1989 I-131 33.3 1.3 35.3 10.0 10.4 A-25

~

6 Table A-3.

In-house spiked samples (continued)

Concentration (pCi/L)

Lab Sample Date TIML Expected Code Type Collected Analysis Result Known Precision n=3 Activity 1s, n=3a QC-W-56 Water Oct 1989 Co-60 15.220.9 17.425.0 8.7 j

Cs-134 22.1 4.4 18.918.0 8.7 Cs-137 27.221.2 22.9 8.0 8.7 QC-W-57 Water Oct 1989 H-3 3334 22 3379 500 724 QC-W-58 Water Nov 1989 Sr-89 10.9 1.4d 11.121.0d 3,7 Sr-90 10.421.0d 10.321.0d 5.2 QC-W-59 Water Nov 1989 Sr-89 101.026.0d 104.1 10.5d 17.5 Sr-90 98.0 3,0d 95.0210.0d 17,0 QC-W-60 Water Dec 1989 Gr. alpha 10.8 1.1 10.6 4.0 8.7 Gr. beta 11.620.5 11.424.0 8.7 QC-MI-26 Mil k Jan 1990 Cs-134 19.3 1.0 20.8 8.0 8.7 Cs-137 25.2 1.2 22.828.0 8.7 QC-MI-27 Mil k Feb 1990 Sr-90 18.0 1.6 18.8 5.0 5.2 QC-MI-28 Mil k Mar 1990 1-131 63.812.2 62.626.0 6.3 QC-MI-61 Water Apr 1990 Sr-89 17.9.5.5 23.128.7 8.7 Sr-90 19.422.5 23.5 5.2 5.2 QC-MI-29 Mil k Apr 1990 I-131 90.729.2 82.5 8.5 10.4 Cs-134 18.321.0 19.7 5.0 8.7 Cs-137 20.321.0 18.225.0 8.7 QC-W-62 Water Apr 1990 Co-60 8.720.4 9.4 5.0 8.7 Cs-134 20.0 0.2 19.7 5.0 8.7 Cs-137 28.7 1.4 22.7 5.0 8.7 QC-W-63 Water Apr 1990 I-131 63.528.0 66.0 6.7 6.6 QC-W-64 Water Apr 1990 H-3 19412130 1826.0 350.0 724 l

QC-W-65 Water Jun 1990 Ra-226 6.4 0.2 6.9 1.0 1.0 I

QC-W-66 Water Jun 1990 V

6.2 0.2 6.0 6.0 6.0 i

A-26 I

6 Table A-3.

In-house spiked samples (continued) i Concentration (DCi/L) 7 Lab Sample Date TIML Expected Code Type Collected Analysis Result Known Precision n=3 Activity 1s, na38 QC-MI-30 Mil k Jul 1990 Sr 89 12.810.4 18.4110.0 8.7 Sr-90 18.211.4 18.716.0 5.2 Cs-134 46.011.3 49.015.0 8.7 Cs-137 27.621.3 25.315.0 8.7 QC W-68 Water Jun 1990 Gr. alpha 9.820.3 10.616.0 8.7 Gr. beta 11.420.6 11.317.0 8.7 l

QC-MI-31 Mil k Aug 1990 1 131 68.821.6 61.4112.3 10.4 l

QC-W-69 Water Sep 1990 Sr 89 17.711.6 19.2110.0 8.7 t

Sr-90 13.9 1.6 17.4110.0 5.2 QC-M1-32 Milk Oct 1990 1-131 34.820.2 32.426.5 8.7 Cs-134 25.821.2 27.3110.0 8.7 Cs-137 25.322.0 22.4110.0 8.7 QC-k-70 Water Oct 1990 H-3 2355159 22761455 605 QC-W-71 Water Oct 1990 1-131 55.920.9 51.8210.4 10.4 QC-W-73 Water Oct 1990 Co-60 18.322.7 16.815.0 8.7 Cs-134 28.312.3 27.015.0 8.7 Cs-137 22.711.3 22.425.0 8.7 QC-W-74 Water Dec 1990 Gr. alpha 21.411.0 26.116.5 11.3 Gr. beta 25.9tl.0 22.315.6 9.7 a n = 3 unless noted otherwise, b n a 2 unless noted otherwise.

c n = 1 unless noted otherwise, d Concentration in pCi/ml.

l l

A-27

s e

i Table A-4 In-house " blank" samples.

Concentration (pCi/L)

Acceptance Lab Sample Date Results Criteria Code Type Collected Analysis (4.66 o)

(4.66 c)

BL-1 D.I. Water Nov 1985 Grc3s alpha (0.1

<1 Gross beta

<0.4 (4

BL-2 0.1. Water Nov 1985 Cs-137 (gamma)

<1.9

<10 BL-3 0.1. Water Nov 1985 Sr-89

<0.5

<5 Sr-90

<0.6 41 BL-5 0.1. Water Nov 1985 Ra-226

<0.4

<1 Ra-228

<0.4

<1 SPW-2265 D.I. Water Apr 1985 Gross alpha

<0.6

<1 Gross beta

<2.2

<4 Sr-89

<0.2

<5 Sr-90

<0.4

<1 1-131

<0.2

<1 Cs-137 (9amma)

<7.4 (10 BL-6 D.I. Water Apr 1986 Gross alpha

<0.4

<1 BL-7 0.1. Water Apr 1986 Gross alpha

<0.4

<1 BL-8 0.1. Water Jun 1986 Gross alpha

<0.4

<1 BL-9 0.1. Water Jun 1986 Gross alpha

<0.3

<1 SPW-3185 0.1. Water Jan 1987 Ra-226

<0.1

<1 Ra-228

<0.9

<1 SPS-3292 Mil k Jan 1987 1-131

<0.1

<1 Cs-134

<6.2

<10 Cs-137

<6.4

<10 SPW-3554 D.I. Water Feb 1987 H-3

<18C

<300 Gross beta (2.6

<4 SPS-3555 Mil k Feb 1987 Sr-89

<0.6

<5 Sr-90 1.920.4a

<1 SPS-3731 Mil k Mar 1987 Cs-134

<2.2

<10 Cs-137

<2.5

<10 A-28

o Table A-4 In-house

• blank" samples (continued)

Concentration (pCi/L_1 Acceptance Lab Sample Date Results Criteria Code Type Collected Analysis (4.66 c)

(4.66 c)

SPS-3732 0.1. Water Mar 1987 Sr-89

<0.9

<5 Sr-90

<0.8

<1 1-131

<0.3

<1 Co-60

<2.3

<10 Cs-134

<2.2

<10 Cs-137

<2.4

<10 Ra-226

<0.1

<1 Ra-228

<1.0

<1 Np-237

<0.04

<1 Th-230

<0.05

<0.1 Th-232

<0.02

<0.1 U-234

<0.05

<0.1 U-235

<0.03

<0.1 U-239

<0.03

<0.1 SPS-4023 Mil k May 1987 1-131

<0.1

<1 SPS-4203 0.I, Water May 1987 Gross alpha

<0.7

<1 Gross beta

<1.7

<4 SPS-4204 Mil k May 1987 Sr-89

<0.5

<5 Sr-90 2.410.68

<1 SPS-4390 Mil k Jun 1987 Cs-134

<4.7

<10 Cs-137

<5.2 (10 SPS-4391 D.I. Water Jun 1987 Sr-89

<0.4

<5 Sr-90

<0.4

<1 1-121

<0.1

<1 Co-60

<3.8

<10 Cs-137

<5.7

<10 Ra-226

<0.1

<1 Ra-228

<0.9

<1 SPW-4627 0.1. Water Aug 1987 Gross alpha

<0.6

<1 Gross beta

<1.4

<4 Tritium

<150

<300 SPS-4628 Mil k Aug 1987 Sr-89

<0.6

<5 Sr-90 2.4:0.6a

<1 A-29

o l

Table A-4.

In-house " blank" samples (continued)

Concentration (pC1/L1 Acceptance Lab Sample Date Results Criteria Code Type Collected Analysi s (4.66c)

(4.66 c)

SPS-4847 Mil k Sep 1987 Cs-134

<4.4

<10 Cs-137

<5.3

<10 SPS-4848 0.1. Water Sep 1987 1-131

<0.2

<1 SPW-4849 0.1. Water Sep 1987 Co-60

<4.1

<10 Cs-134

<4.8

<10 Cs-137

<4.0

<10 Sr-89

<0.7

<5 Sr-90

<0.7

<1 SPW-4850 0.1, Water Sep 1987 Th-228

<0.04

<1 Th-232

<0.8

<1 U-234

<0.03

<1 U-235

<0.03

<1 0-238

<0.02

<1 Am-241

<0.06

<1 Cm-242

<0.04

<1 Ra-226

<0.1

<1 Ra-228

<1.0

<2 SPW-4859 0.1. Water Oct 1987 Fe-55

<0.5

<1 SPS-5348 Mil k Dec 1987 Cs-134

<2.3 (10 Cs-137

<2.5

<10 SPW-5384 0.1. Water Dec 1987 Co-60

<2.8

<10 Cs-134

<2.6

<10 Cs-137

<2.8

<10 1-131

<0.2

<1 Ra-226

<0.1

<1 R a-228

<1.2

<2 Sr-89

<0.5

<1 S r-90

<0.4

<1 SPW-5385 0.1 Water Hov 1987 Gross alpha

<0.4

<1 Gross beta

<2.2

<4 Fe-55

<0.3

<1 SPS-5386 Mil k Jan 1988 1-131

<0.1

<1 SPW-5448

" Dead" Water Jan 1988 H-3

<177

<300 l

A-30

Table A-4 In-house " blank" samples (continued)

Concentration (PCi/L)

Acceptance Lab Sample Date Results Criteria Code Type Collected Analysis (4.66 c)

(4.66 c)

SPS-5615 Mil k Mar 1988 Cs-134

<2.4

<10 C s-137

<2.5

<10 1 131

<0.3

<1 Sr-89

<0.4

<5 Sr-90 2.4 0.Sa

<1 SPS-5650 D.1. Water Mar 1988 Th-228

<0.3

<1 Th-230

<0.04

<1 Th-232

<0.05

<1 U-234

<0.03

<1 U-235

<0.03

<1 U-238

<0.03

<1 Am-241

<0.06

<1 Cm-242

<0.01

<1 Pu-238

<0.08

<1 Pu-240

<0.02

<1 SPS-6090 Mil k Jul 1988 Sr-89

<0.5

<1 Se-90 1.8 0.5

<1 1-131

<0.4

<1 Cs-137

<0.4

<10 SPW-6209 Water Jul 1988 Fe-55

<0.8

<1 SPW-6292 Water Sep 1988 Sr-89

<0.7

<1 Sr-90

<0./

<1 SPS-6477 Mil k Oct 1988 1-131

<0.2

<1 Cs-134

<6.1

<10 Cs-137

<5.9

<10 SPW-6478 Water Oct 1988 l-131

<0.2

<1 SPW-6479 Water Oct 1988 Co-60

<5.7

<10 Cs-134

<3.7

<10 Cs-137

<4.3

<10 SPW-6480 Water Oct 1988 H-3

<170

<300 SPW-6625 Water Dec 1988 Gross alpha

<0.7

<1 Gross beta

<1.9

<4 A-31

e Table A-4.

In-house " blank" samples (con 61nued)

Concentration (pci/L)

Acceptance Lab Sample Date Results Criteria Code Type Collected Analysis (4.66 o)

(4.66 c)

SPS-6723 Mil k Jan 1989 Sr-89

<0.6

<5 S r-90 1.910.58

<1 1 131 (0.2

<1 Cs-134

<4.3

<10 Cs-137 (4.4

<10 SPW-6877 Water Har 1989 Sr-89

<0.4

<5 Sr-90

<0.6

<1 SPS-6963 Milk Apr 1989 I-131

<0.3

<1 Cs 134

<5.9

<10 Cs-137 (6.2

<10 SPW-7561 Water Apr 1969 H-3

<150

<300 1

SPW-7207 Water Jun 1989 Ra-226

<0.2

<1 i

Ra-228

<0.6

<1 SPS-7208 Mil k Jun 1989 Sr-89

<0.6

<5 Sr-90 2.110.58

<1 1-131

<0.3

<1 Cs-134

<6.4

<10 Cs-137

<7.2

<10 SPW-7558 Water Jun 1989 Gross alpha

<0.2

<1 Gross beta

<1.0

<4 SPS-7322 Mil k Aug 1989 Sr-89

<1.4

<5 Sr-90 4.8tl.08

<1 1-131

<0.2

<1 Cs-134 (6.9

<10 Cs-137

<8.2

<10

-SPW-7559 Water Sep 1989 Sr-89

<2.0

<5 Sr-90

<0.7

<1

-SPW-7560 Water Oct 1989 l-131

<0.1

<1 SPW-7562 Water Oct 1989 H-3

<140

<300 A-32

o e

Table A 4.

In-house " blank" samples (continued)

Concentration (pCi/L)

Acceptance Lab Sample Date Results Criteria Code Type Collected Analysi s (4.66c)

(4.66 c)

SPS-7605 Mil k Nov 1989 l-131

<0.2

<1 Cs-134

<8.6

<10 Cs-137 (10

<10 SPW-7971 Water Dec 1989 Gross alpha' (0.4

<1 Gross beta

<0.8

<4 SPW-8039 Water Jan 1990 Ra-226

<0. 2

<1 SPS-8040 Mil k Jan 1990 Sr-89

<0.8 (5

Sr-90

<1.0

<1 SPS-8208 Mil k Jan 1990 Sr-89

<0.8

<5 Sr-90 1.610.5a

<1 Cs-134

<3.6

<10 Cs-137

<4. 7

<10 SPS-8312 Mil k Feb 1990 Sr-89

<0.3

<5 Sr-90 1.210.3a

<1 SPW-8312A Water Feb 1990 Sr-89

<0.6

<5 S r-90

<0.7

<1 SPS-8314 Mil k Mar 1990 1-131

<0.3

<1 SPS-8510 Mil k May 1990 1-101

<0.2

<1 Cs-134 (4.6

<10 C s-137

<4.8

<10 SPW-8511A Water May 1990 H-3 (200

<300 SPS-8600 Mil k Jul 1990 Sr-89

<0.8

<5 S r-90 1.710.6a

<1 1-131

<0.3

<1 Cs-134

<5.0

<10 C s-137

<7.0

<10 SPM-8877 Mil k Aug 1990 1-131

<0. 2

<1 SPW-8925 Water Aug 1990 H-3

<200

<300 l

A-33

Table A-4.

In-house " blank" samples (continued)

Concentration (pCi/L)

Acceptance Lab Sample Date Results Criteria Code Type Collected Analysis (4.66c)

(4.66 o)

SPW-8926 Water Aug 1990 Gross alpha

<0.3

<1 Gross beta

<0.7

<4 SPW-8927 Water Aug 1990 V-234

<0.01

<1 U-235 (0.02

<1 0-238

<0.01

<1 SFW-8928 Water Aug 1990 Mn-54

<4.0

<5 Co-58

<4.1

<5 00-60

<2.4

<5 Cs-134

<3.3

<5 Cs-137

<3.7

<5 SPW-8929 Wate-Aug 1990 S r-89

<1.4 (5

Sr-89

<0.6

<1 SPW-69 Watar Sep 1990 Sr-89

<1.8

<5 S r-90

<0.8

<1 SP'.' 106 Water Oct 1990 H-3 (180

<300 f N4-107 Milk Oct 1990 1-131

<0.4

<1 Cs-134

<3.3

<5 Cs-137

<4.3

<5 SPW-370 Water Oct 1990 Mn-54

<1.7

<5 Co-58

<2.6

<5 C o-60

<1.6

<5 Cs-134

<1.7

<5 Cs-137

<1.8

<5 SPW-372 Water Dec 1990 Gross alpha

<0.3

<1 Gross beta

<0.8

<4 a low level of Sr-90 concentration in milk (1 - 5 pCi/L) is not unusual.

A-34

---

.----..--.--_u..

T itil-BL IND-01 Revision 0, 12 29 66 1

ATTACHMENT B ACCEPTANCE CRITERIA FOR "$ PIKE 0" SAMPLES LABORATORY PRECISION:

ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa

=

One Standard Deviation Analysis Level for Single Determination Gama Emitters 5 to 100 pCi/ liter or kg 5 pCi/ liter

>100 pCi/ liter or kg 5% of known value Strontium-89b 5 to 50 pCi/ liter or kg 5 pC1/ liter

>50 pCi/ liter or kg 10% of known value Strontium-90b 2 to 30 pCi/ liter or kg 3.0 pCi/ liter

>30 pC1/ liter of kg 10% of known value Potassium

>0.1 g/ liter or kg b% of known value Gross Alpha

<20 pCi/ liter 5 p';i/ liter

>20 pCi/ liter 25% of known value Gross Beta

<100 pCi/ liter 5 pCi/ liter

>100 pCi/ liter 5% of known value Tritium

<4,000 pCi/ liter is = (pC1/ liter) =

169.85 x (known).0933

>4,000 pCi/ liter 10% of known value Radium-226,

<0.1 pCi/ liter 15% of known value Radium-228 Plutonium 0.1 pCi/ liter, gram, 10% of known value or sample lodine-131, b

<55 pCi/ liter 6 pCi/ liter lodine-129

>55 pCi/ liter 10% of known value Uranium-238

<35 pCi/ liter 6 pCi/ liter Nickel-63,

>35 pCi/ liter 15% of known value b

Technetium-99b Iron-55b 50 to 100 pCi/ liter 10 pCi/ liter

>100 pCi/ liter 10% of known value From EPA publication, " Environmental Radioactivity Laboratory Intercompari-a s n Studies Program, Fiscal Year 1981-1982, EPA-600/4-81-004.

b TIML limit.

A-35

---

._----.----.__2_-______.

o

. ADDENDUM TO APPENDIX A The following is an explanation of the reasons why certain samples were outside t he. control limit specified by the Environmental Protection Agency for the 15terlaboratory Comparison Program starting January 1987.

EPA TIML Control Result

_ Limit Lab Code ' Analysis (pC1/L)a (pCi/L)8 Explanation STM-504 S r-89 57.014.3 60.3-77.7 Milk had high fat content which S r-90 32.021.0 32.4-37.6 made analyses difficult.

Ad-dition of errors to TIML result would put values within EPA control limits.

EPA als? had the same problem in analyzing its own sample.

STW-511 Ra-228 8.121.4 4.6-8.0 TIML results ar2 usually within EPA control limits.

Analysis of the next sample was within EPA control limits.

No further action is planned.

STW-516 C r-51 80.3:17.5 61.3-78.7 Results in the past have been within EPA control limits and TIML will monitor the situation in the future.

STF-524 K.

1010.72158.5b 1123.5-1336.5b Error in transference of data.

Corret.t data was 1105233 mg/kg.

Results in the past have been within the limits and TIML will monitor the situation in the future.

STW-532 1-131 9.022.0 6.2-8.8 Sample recounted after 12 days.

The average result was 8.811.7 l

pCi/L (within EPA control limits).

The sample was recounted in order to check the decay.

Results in the past have been within the limits and TIML will continue to monitor l

the situation in the future, a Reported in pCi/L unless otherwise noted.

b Concentrations are reported in mg/kg.

A-36

!w

e ADDENDUM TO APPEkDIX A (continued)

EPA TIML Control Result Limit Lab Code Analysis (pci/L)a (pC1/L)a Expl anat ion l

STW-534 Co-60 63.311.3 41.3-58.7 High level of Co-60 was due to contamination of beaker. Beaker was discarded upon discovery of

)

contamination and sample was recounted.

Recount results l

53.213.6 and 50.922.4 pC1/L.

STM-554 Sr-90 51.022.0 54.8-65.2 The cause of low result was due to very high fat content in the mil k, i t should be noted that 63% of all participants failed this test.

Also, the average for all participants was 54.0 pC1/L before the Grubb and 55.8 pCi/L after the Grubb.

i STW-560 Pu-239 5.8*1.1 3.5-4.9 The cause of high results is not known it is suspected that the standard was not properly calibrated by supplier and is under i nvestigation.

New Pu-236 standard was obtained and will be used for the next test.

STW-568 Ra-228 2.611.0 2.7-4.5 The cause of low results is not known.

Next EPA crosscheck results were within the control l

l limits.

No further action is pl anned.

STM-570 Sr-89 26.0210.0 30.3-47.7 The cause of low results was S r-90 45.724.2 49.8-60.2 falsely high recovery due to suspected incomplete calcium removal.

Since EPA sample was used up, internal spike was prepared and analyzed.

The results were within control limits - (See table A-3, sample QC-MI-24).

No further action l

l 1s planned.

a Reported in pCi/L unless otherwise-noted.

A-37

...... ~,, -

/e-dee g-7 32-p-

r *ww d,ew g---wm,--

w,.-w ur s,mwg--e-wwmH e-nu,->m-rw-v--

-tas+-

h-6 Tr gr-g--

ai- - - -, - -

. yewww-w--vygr-=

z' r*"

• --*"-'1

o ADDENDUM TO APPENDIX A (continued)

EPA TIML Control Result Limit Lab Code Analysis (pCi/L)a (pCi/L)a Explanation STW-589 Sr-90 17.321.2 17.4-22.6 Sample was reanalyzed in tri-plicate; results of reanalyses 18.811.5 pCi /L.

No further action is planned.

STM-599 K

1300.0169.2c 1414.7-1685.3c Sample was reanalyzed in trip-licate. Results of reanalyses, 1421.7195.3 mg/L.

The cause of low results is unknown.

STW-601 Gross 11.0 2.0 11.6-32.4 Sample was reanalyzed in trip-Alpha licate. Results of reanalyses, 13.4 1.0 pCi/L.

a Reported in pCi/L unless otherwise noted.

c Concentrations are reported in mg/L.

A-38

l l

l i

Appendix B Data Reporting Conventions l

B-1

Data Reporting Conventions 1.0.

All activities. except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.

2.0.

Single Measurements Each single measurement is reported as follows:

xis where x = value of the measurement; s = 2a counting uncertainty (corresponding to the 95% confidence level).

In cases where the activity is found to be below the lower limit of detection L it is reported as

<L where L = is the lower limit of detection based on 4.660 uncertainty for a background sample.

3.0.

Duplicate Analyses 3.1.

Individual results: x1 i s1 xg t sg Reported result:

xis where x = (1/2) (x1 + x2) s=(1/2)

+sf 3.2.

Individual results: <ll

<L2 Reported result:

<L where L = lower of L1 and L2 3.3.

Individual results: x s

<L Reported result:

x i s if x > L;

<L otherwise B-2

l o

4.0.

Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations.

The average x and standard deviation (s) of a set of n numbers x1, x2'

• Xn are defined as follows:

x = f Ix I(x-x)2 3,

n-1 4.2 Values below the highest lower limit of detection are not included in the average.

4.3 If all of the values in the averaging group are less than the highest LLO, the highest LLO is reported.

4.4 If all but one of the values are less than the highest LLO, the single value x and associated two sigma error is reported.

4.5. In rounding eff, the following roles are followed:

4.5.1. If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged.

As an example,11.443 is rounded off to 11.44, 4.5.2 If the figure following those to be retained is greater than 5, the figure is dropped, and the last retained figure is raised by 1.

As an example,11.446 is rounded off to 11.45.

4.5.3. If the figure following those to be retained is 5, and if there are no figures other than zeros beyond the five, the figure 5 is dropped, and the last-place figure retained is increased by one if it is an odd number or it is kept unchanged if an even number.

As an example,11.435 is rounded off to 11.44, while 11.425 is rounded off to 11.42, l

B-3

+

Appendix C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas C-1

+

o Table C 1.

Maximum permissible concentrations of radioactivity in air and water above natural background in ut,astricted areas.8 Air Water Gross alpha 3

pCi/m3 Strontium 89 3,000 pC1/1 Gross beta 100 pCi/m3 Strontium 90 300pCi/1 lodine-131b 0.14 pCi/m3 Cesium-137 20,000 pC1/1 Barium-140 20,000 pCi/1 lodine 131 300 pCi/1 Potassium-40c 3,000 pCi/1 Gross alpha 30 pCi/l Jross beta 100 pCi/1 Tritium 3 x 106 pCi/1 a Taken from Code of Federal Regulations Title 10 Part 20. Table !! and appro-priate footnotes.

Concentrations may be averaged over a period not greater than one year.

1. 1 From 10 CFR 20 but adjusted by a f actor of 700 to reduce the dose resulting from the air-grass-cow-milk child pathway, c A natural radionuclide.

1 l

l l

l C-2 1

3 -....,_. -...,...,....,, -, -,.

.,-~e

1 Appendix D j

v Special Ground, Surface, and Well Water Samples

~

.-.e-p..y n.,uy.A w,,

1,-+V-7-w re ww--

w h

w--

w tw t

vv v

e---

---c-w%4+t r-e w - - +

%m--

en--

e-~

• -ew erwewe nw w==-eev'+%-e-g.'y=

rghw+g w

+=Mk.>e-wy7m-7vva 7-e-4

e e

1.0 IFTRODUCTION This appendix to the Radiation Environmental Monitoring Program Annual Report to the United States Nuclear Regulatory Commission j

summarizes and interprets results of the special well, ground, and surface water samples taken at the Prairie Island Nucicar Generating Plant, Rod Wing, Minnesota, during the period January

- December, 1990.

This supplemental special sampling program was establish in December of 1989 when tritium was detected in e nearby residence well sample.

Tabulations of the special sampling program individual analysos made during the year are included in this appendix.

A summary table of tritium analyses is also included in this appendix.

D-1

_.._.______..._.__._.____.._._..m__._.___._____.__

e a

2.0

SUMMARY

4 This special sampling program was established following the detection of tritium in a nearby residerce well water sample, The program is described and the results for 1990 are summarized 4

and discussed.

Program findings show a

low level of tritium in a

nearby residence well, some ground water seepage

samples, and some levels slightly above the LLD in a few other well water sampics.

None of the samples exceeded any limits and did not qualify as non-routine sample results.

However because of the ability to detect tritium at levels above the control locations the dischargo canal system was modified to help preclude any further introduction of tritium into the ground water system.

l l

1 i

D-2 L_.___..___._.,_--_.----_.-.___-_.-.-.---_

~ ~ -.

2 3.0 Special Tritium Samolina_Proar.gj!)

3.1 Proaram Desian and Data Internretation The purpose of this n,ampling program was to assess the impact of the tritium leaching into the environment (ground water system) from the discharge canal.

For this purposo special water samples are collected and analyzed for radioactive content.

After it was determined by collection and analyses that tritium was the only isotopo that wo would see at this level of leaching the gamma isotopic analyses of special water samples was suspended.

3.2 Procram Descriotion The sampling and analysis schedule for the special water nampling program is summarized in Table 4.1 and briefly reviewed below.

Table 4.2 defines the additional sample locations and codes _for the special water sampling program, dome samples were not coded due to thero one timo sampling or they were not offsito camples.

Special well and ground water is collected monthly at six locations, one control sample from the PINGP Biology Station (P-30),

two from the nearest residences doop and shallow wells (P-24d and P-24s, Sutor Residenco), two ground _ water acepage from near Birch Lake (P-31 and P-32), and well water from the PI Training Center (p-26).

Quarterly well water is collected from three other nearby residences (P-27, Hauer Residence; P-28, Perkins Residence; P-29 Childs Residence).

Additional non routine samples were collected on a non frequent basis or a one time basis as can be soon in the complete data table Table 4.4.

3.3 Er.qcram Execution The special water sampling was executed as described in the preceding section with the following exception:

1.

No water sample was availablo during the months of March,_May, June, and October from the Birch Lake locations (P-31 and P-3P) due to high water levels in the lake.

The ground seepage Fample locations were under water.

l D-3

e 3.4 Procram Modificationg The samplo collection included como one tino sampling of surface water locations, both insido the sito boundary and outside.

Due to those one time sampling and insido site boundary locations they woro not added to the sample location list as other samplos woro.

3.5 Results and Dis m algn Results obtained show very low lovels of tritium in como well water and ground water samples.

Whilo not all of the results can be positively identified as being a result of I

the operation of the Prairio Island Nuc) oar Generating Plant due to their levels being very slightly abovo the Lower Limit of Detection.

The rollability of the analysis at this low a level is suspect and not normally obtained in the routino REMP sampling.

Several of the higher levels are probably due to the scopage of discharge canal water into the ground water due to elevation difference betwoon the Vermillon River and the discharge canal, this clovation difference is approximately ton feet and duo to the lock and dam system downstream.

The Suter Residence is directly betwoon the discharge canal and Birch Lake which is attached to the Vormillon River.

The dischargo piping is being extended to allow offluent dischargos to bypass most of the discharge canal and therefore reduce the impact on the ground water due to effluent releason.

D-4

e Table D-4.1 Sample collection and analysis program for special well, ground, and surface water samples, Prairio Island Nuclear Generating Plant, 1990.

Locations Collection Analysis Type and Type and b

Frequencyc Medium No.

Codes (and Type)a Frequency Well water monthly 4

P-30(C), P-26, G/M H-3 P-24s, P-24d Well water qtrly 3

P-27, P-28, P-29 G/Q H-3 Ground water 2

P-31, P-32 G/M H-3 Surface water 6

G/X H-3 a Location codes are defined in Table D-4.2.

Control stations are indicated by (C).

All other stations are indicators, b Collection type is coded as follows: C/ = continuous, G/ =

grab.

Collection frequency is coded as follows: W = wookly, M = monthly, Q = quarterly, SA = semiannually, A = annually, X = no specified frequency or one time.

c Analysis type is coded as follows: GB = gross bota, GS =

gamma spectroscopy, H-3 = tritium, I-131 = iodine 131.

Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly composito.

D-5

e e

i i

i l

Table D-4.2 Sampling locations, for special well, ground, and surface water samples, Prairie Island Nuclear Generating Plant, 1990.

D. stance and Type of Direction from Code Typea Collection Site Sampleb Site Stack l

P-24d Suter Residence, deep WW 0.6 m.', 0 158*/SSE l

well P-24s Suter Residence, WW 0.6 mi 0 158'/SSE shallow well P-26 PINGP Training Center WW 0.4 mi 0 258'/WSW P-27 Nauer Residence WW 0.9 mi 0 154'/SSE P-28 Perkins Residence WW 1.0 mi 0 152'/SSE P-29 Childs Residence WW 1.2 mi 0 149'/SSE P-30 C

PINGP Biology Station WW 0.2 mi 0 32'/NNE i

P-31 Birch Lake Seepage # 1 GW 0.8 mi 0 169'/SSE P-32 Birch Lake Seepage # 2 GW 0.7 mi 0 179'/S a

"C" denotes control location.

All other locations are l

indicators.

j b

Sample codes:

AP e Airborne particulate W e Well water Al e Airborne lodine B$ = Bottom (river) sediments M e N(lk

$$ e Shoreline $ediments Yt a vegetation / vegetables 80 = Bottom organisms (periphyton or macrotnvertebrates) l DW s Drinking water f s Fish RW m ltiver water GV e Ground water t

l l

l l

D-6

Table D-4.3 Radictogical Envircreental Monitoring Program Sumery; Specist uett, Grourd, Surface refer Sarples Name of facitity Prairie 1stard exteer Generatirw Plent Docket No.

50-??2. 50 3 %

tocation ret Facility Gooduse, Minnesets Reportirg Period Jarw;ery - Deceder 1Y90 (County, State) l Indicator tocations M th highes'.

Control Sample Type and Locations Annual Mean Locations Nweaer of c

hon-routine g,,n gyy Type kster of

,,,n gy)c d

8N perutts' a

b Range tecatian Range (Units)

Analyses LtD uett Water i u-3 60 210 839 (42/48)

P-245, Suter's 1131 (12/12)

< LLD 0

(210-1870)

Shot toe we t t,

(33C - 1870)

(pci/t) 0.6 mi a 158*/SSE Groi.nd unter M-3 16 210 664 (16/16)

P-31, airch tote 702 (8/8)

< tto 3

(510-910)

Seepage #1, 0.8 mi (510-910)

(pci/t) 3 169*/SSE surf ace water M-3 9

210 560 (1/9) f>xk Pend #2, 560 (1/4)

< LLD 0

0.3 m:i 3158*/SSE (pCi/t)

I a GB = Gross beta; GS = gerna scan.

LLD = Norminal tower timit of detection based on 4.66 sigma error for backgroirnd sarepte.

b Fraction of detectable measurements at specified location is irdicated Mean and range based upon detectabte measurements only.

C in parentheses (F).

d Locations are specified (1) by name and code (Table 2) and (2) distance, direction, and sector relative to reactor site.

• hon-routine results are those which exceeds ten times the control station vattse. If re control station value is available, the is considered non-routire if it exceeds ten times the preoperational value for the location.

result D-7

lABLE D-4.4.1 Radiological Eavironmental Monitoring Progran, Complete Data Tables.

I SAMPituG 1/15' 2/12 3/12 4/10 5/17*

6/12 7/20-8/9 9/10 10/24 11/12 12/11 DATES Suter's Deep pci/t pci/t pci/t pci/t pci/t gi/t pci/t

ci/t pct /t pci/t pci/t pci/t Well Se ptie I.D.

8045 8281 8371 848al 6233 8720 8868 8949 25 144 214 313 i

P-24d n-3 1540 1570 1180 1190!

1310 1330.

1290 1560 1370 1740 1220 1320 Gross Alpha

<0.6 1.5

<0.8

<0.9 Gross Beta 2.2 1.7 2.4 2.8

1. tt 54

<4.2

<4.9

<5.2

<4.8 fe-59

<14.1

<11.2

<10.4

<9.7 Co-58

<4.8

<5.2

<4.3

<4.e co-60

<4.9

<4.8

<4.7

<3.1 In-65

<9.5

<10.0

<8.8

<3. 6 i

Zr-Nb-95

<5 5

<5.8

<4.9

<6.1 i

Cs-134

<4.1

<4.4

<3.1

<4.3 Cs-137

<5.6

<4.4

<4.9

<3.9 Ba-La-140

<6.0

<6.9

<6.2

<6.1 L

<27.2f ce-144

<52.6

<39.4

<31.6 D-8 l

lI llll l

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TABLE D-4.4.4 Radiological Environmental Monitoring Prograa, Complete Data Tables.

i SAMPLING 1/15 2/12 3/12 4/10 5/17 6/12 7/20 8/9 9/10 10/24 11/12 12/11 CATES Birch Lake pci/t pci/t pct /t pct /t pct /t pci/t pci/t pct /t pci/t pci/t pci/t pci/I No.2 Sanpte I.D.

8051 82 5 8496 8373 8953 20 219 318 P-32 n-3 520 550 650 600 760 700 510 720 Gross AtrAs

<1.0

<1.0 1.6 Gross Beta 1.9

<1.1 1.2

% -54

<5.5

<3.1

<4.2 Fe-59

<14.9

<9.2

<7.2 i

co-58

<6.4

<3.7

<4.0 co-60

<6.0

<3.9

<4.1 Zn-65

<12.4

<S.8

<7.5 Zr-Nb-95

<7.6

<4.9

<5.8 cs-134

<4.7

<3.2

<4.0 cs-137

<6.5

<4.4

<5.5 Sa-ta-140

<13.1

<3.8

<4.6 I

ce-144 460.4

<35.0

<47.2 l

D-11 i

n TABLE D-4.4.5 Radiological Environmental Monitoring Program, Complete Data Tables.

4 SAMPLING 1/15 2/12 3/12 4/10 5/17 6/12 7/18 8/9 9/10 10/24 11/12 12/11 DATES PI Training s i/t Center pci/t pci/t pct /t pct /t pci/t gi/t gi/t pci/t pci/t pci/t gi/t c

Sanpte I.D.

8044 8278 8369 8488 6230 8719 8876 8950 26 146 216 315 P-26 H-3 390 470 260 290 330 210 450 320 310 330 310

< 190 I

f Gross Atrha

<0.7

<1.9

<C.7

<0.6 Gross Beta

<0.9 2.5 1.6 2.1 Hn-54

<4.4

<4.3

<3.8

<4.8 fe-59

<11.4

<8.1

<10.0

<10.5 co-5S

<4.5

<3.6

<3.5

<4.0 co-60

<3.1

<3.7

<3.8

<3.9 Zn-65

<9.7

<8.8

<8.6

< T.2 Zr-Wb-95

<4.5

<4.4

<4.7

<5.2 cs-134

<4.7

<3.7

<3.7

<3.3 cs-137

<5.2

<4.1

<4.9

<4.3 l

Ba La-140

<9.1

<4.0

<4.0

<5.7

<42.3f ce-144

<43.4

<42.4

<42.0 1

l l

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ll

,1l

o TABLE D-4.4.9 Radiological Environmental Monitoring Program, Complete Data Tables.

1 i

SAMPLING 1/15 2/12 3/12 4/10 5/17 6/12 7/ 8 8/9 9/10 10/29 11/12 12/11 DATES Res. No.

2' Perkins pci/t pct /t pct /s pci/t pci/t pci/t pci/t gi/t

.ri/ t pci/t pci/t pci/t Well Sanpte I.D.

8048 8492 8870 175 P-28 H-3 260 240 250 220 Cross At@a

<1.0 0.8 Gross seta 3.3 6.6 f

Mn-54

<5.4

<3.9 Fe-59

<9.4

<10.1 Co-58

<6.9

<4.5 co-60

<4.1

<4.3 Zn-65

<9.1

<7.6 Z r-Nb-95

<7.1

<5.3 cs-134

<3.8

<3.3 cs-137

<6.1

<5.0 Ba-La-140

<11.0

<8.8 ce-144

<41.5)

<40.8 D-16

fl1II l

9 O

1 t

1

/

/

t 2

c 1

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