ML20238B508

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Environ Radiation Study in Vicinity of Humboldt Bay Power Plant,Annual Rept 1986
ML20238B508
Person / Time
Site: Humboldt Bay
Issue date: 12/31/1986
From: Brownrigg D, Szalinski P, Jason White
PACIFIC GAS & ELECTRIC CO.
To:
Shared Package
ML20238B491 List:
References
420-87.61, NUDOCS 8709010253
Download: ML20238B508 (75)


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t ANNUAL REPORT ENVIRONMENTAL RADIATION STUDY Humboldt Bay Power Plant Unit No. 3

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1986 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF ENGINEERING RESEARCH 8709010253 870028 PDR ADOCK 05000133 R PDR

Report Issued: JUN 1 1987 Report 420-87.61 (6336/0479)

PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF ENGINEERING RESEARCH 1

Environmental Radiation Study in the Vicinity of Humboldt Bay Power Plant Eureka, California Annual Report 1986 Prepared By:

D. L. Brownrigg J. H. White P. A. Szalinski 1298A.1/CML7(dj )

1 i

l Report 420-87.61 ,

i TABLE OF CONTENTS Page l 1

LIST OF TABLES . . . . . . . . . . . . . .. . . . . . . .. .... ii LIST OF FIGURES . . . . . . . . . . . . . . ... .. . . . .... iii INTRODUCTION . . . . . . . . . . . . . . .. . . . . . . .. .... I METHODS OF SAMPLE COLLECTION AND ANALYSIS . . . ... . . . .... I l i

5 DISCUSSION OF ANALYTICAL RESULTS . . . . .. . . ... . . . .. . . i

. . . . . . . . . . . . .. . . . .. . .. . . .. 5 QUALITY CONTROL 8

REFERENCES . . . . . . . . . . . . . . . . . . . ... .. . ....

1 APPENDIX )

1 A. Summary of Radioanalytical Data l B. Quality Control and Supplemental Data l C. Detailed Quarterly Radioanalytical Data l D. Environmental Monitoring Results - Chernobyl Accident l l

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I l Report 420-87.61 LIST OF TABLES Table Page A-1 Number of Samples Collected . . . ............... A A-2 fummary of Radioanalyses - Marine and Terrestrial Samples . .. A-3 A-3 Summary of Gross Beta Activity - Air Particulate Samples. ... A-5 A-4 Summary of Environmental Radiation Measurements A-4a Stray Radiation Chambers - Off-Site . .......... A-6 A-4b Film Pack - Off-Site . . . ........-....... A-7 -l A-4c Thermoluminescent Dosimeters - On-Site ......... A-8 A-5 Maximum Values for the Lower Limit of Detection . ....... A-9 B-1 Summary of State Intercomparison Program. ........... B-2 l B-2 Summary of EPA Intercomparison Program. ............ B-5 B-7 j B-3 Summary of Saline Water Radioanalyses . ............

Radiological Data C-1 First Quarter . . . . . . . . . . ............... C-2 C-2 Second Quarter . . . . . . . . . ............... C-12 C-3 Third Quarter . . . . . . . . . . ............... C-22 C-4 Fourth Quarter. . . . . . . . . . ............... C-32 D-1 Environmental Monitoring of Chernobyl - Special Report .... D-3 11 ,

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1298a.1/CML7/(dj)  !

Report 420-87.61 LIST OF FIGURES Figure Page Station Locations . . . . . . . . . . . . . . . . . . ... 9 i 1

2 Station Locations . . . . . . . . . . . . ... . . .. .. 10 3 Station Locations . . . . . . . . . . . . . . . . .. . .. 11 4 Station Locations of On-Site Thermoluminescent Dosimetere . . . . . . . . . . . . . . . . . . . . . .... 12 ,

i 5 Chronological Display of Selected Environmental Heasureraents . . . . . . . . . . . . . . . . . . . . . .. 13 l

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iii 1298a.1/CML7(dj)

Report 420-87.61 INTRODUCTION This annual report contains the results from the environmental radiation monitoring program for the Humboldt Bay Power Plant (HBPP) Unit 3 compiled for calendar year 1986. Samples collected for the monitoring program were in accordance with the requirements of the North Coast Water Quality Control Boardi '2 and the California State Department of Health3 ,

The types of samples collected include 52 marine (i.e., fish, algae, bottom sediment), 20 terrestrial (i.e., milk, water, soil), 104 air particulate filters, and environmental dosimeters (779 stray radiation ion chamber {

results, 358 film packs, and 204 TLD results). The analyses include gross l

beta, gamma isotopic (including K-40 determinations), and iodine (I-131) l f

determinations, which are performed at the Pacific Gas and Electric Company, I Department of Engineering Research (DER). Environmental dosimetry is l

performed by HBPP personnel (stray radiation ion chamber readings), by DER I personnel (TLD processing), and by an outside contractor (film pack processing).  ;

I As part of the quality control measures for the monitoring program, DER participates in the Environmental Protection Agency (EPA) Intercomparison )

i Studies Program and an intercomparison program with the State of California.

The results from these programs are shown in the tables and the appendix.

Also included in the report are the data from the radiochemical analyses of influent and effluent water for HBPP Unit 3.

l A special section discussing the impact of the Chernobyl Accident is included in the Appendix D.

METHODS OF SAMPLE COLLECTION AND ANALYSIS Air particulate, milk, water, and soil samples are collected, and the stray radiation chambers are read, by PGandE Nuclear Plant Operations 1

1298A.1/CML7(dj)

l Report 420-87.61 personnel at HBPP. Marine samples (including algae, fish and invertebrates, ]

and sediment) are collected by personnel from Humboldt State University )

(

Foundation under the direction of Dr. J. A. Gast. Figures 1, 2, and 3 show ]

1 the locations where these samples are collected (on-site dosimeter locations are shown in Figure 4). l J

j Air samples are collected at two locations (Station 3 and 45) on a weekly basis. The constant flow samplers maintain a flow rate of 1-1.5

)

cubic feet (28-42 liters) per minute; an H-70 type filter paper is used as ]

the sampling medium. The filters are counted on a gas flow proportional counter to determine gross beta activity at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after collection to allow naturally occurring short-lived radionuclides to decay. l Milk samples are collected from two local dairies (Stations 16 and 48) on a quarterly basis. The samples are analyzed by gamma isotopic i 1

spectroscopy, and then radiciodine analysis is performed. To prepare the sample for radiciodine analysis, stable iodine is added to the raw milk to determine chemical recovery. Iodine is then separated from the milk by an ion exchange resin; the iodine is then stripped from the resin, purified, and precipitated as cuprous iodide for measurement by beta gamma coincidence spectrometry. The typical detection limit using this method is 0.2 pCi/ liter for I-131.

Domestic water 1-s collected on a quarterly basis. The sample is analyzed by gamma spectroscopy, then an aliquot is taken for tritium (H-3) analysis. The aliquot for tritium analysis is distilled and then a scintillation cocktail is added to the distillate before counting in a liquid scintillation spectrometer. The limit of detection by this method is typically 0.5 pCi/ milliliter for H-3 in water.

Soil samples are collected from two locations (Stations 1 and 5) on a quarterly basis. These samples are analyzed by gamma isotopic spectroscopy.

2 1298A.1/CML7(dj) 1

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Report 420-87.61 Marine samples include algae, fish and invertebrates, and sediment from 1

five locations in Humboldt Bay. The algae, fish, and invertebrate samples are analyzed by gamma isotopic spectroscopy. Sediment is oven-dried and then analyzed by gr a a isotopic spectroscopy.

Environmental radiation dosimetry (gamma radiation exposure) is determined by stray radiation ion chambers (Victoreen, Model 239), and film packs for off-site locations (as shown in Figures 1, 2, and 3).

Thermoluminescent dosimeters (Panasonic Model UD 814) are used to monitor f the on-site locations (as shown in Figure 4). The stray radiac%n ion chambers are read in the field on a biweekly basis; the film packs are exchanged on a monthly basis. These film packs are supplied and read out by l

the Radiation Detection Company (RDC) of Sunnyvale, California; the results i are reported relative to the background exposure at the RDC laboratory (

i (8 mR/ month). The Panasonic TLDs are exchanged on a monthly basis and are j l

processed at the DER laboratory.

Influent and effluent (saline) water is collected on a weekly basis.

The sample is analyzed by gamma spectroscopy, then an aliquot is taken for l tritium (H-3) analyses. The tritium sample is prepared in the same manner j as the domestic water samples.

The gamma isotopic spectroscopy is performed using either a Ge(Li) or Intrinsic Germanium detector and a multichannel pulse height analyzer. The limit of detectability attained in the gamma r,can is typically 5 pCi/E of i water solution containing a single radionuclides.

The + term in the following tables is the two-sigma error (i.e., the 95 percent confidence level). The lower limit of detection (LLD) is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with a 95 percent probability with only 5 oercent probability of concluding ' Tat a 3

1298A.1/CML7(dj )

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Report 420-87.61 "real" signal represents a blank observation.

For a particular measurement system, which may include radiochemical j separation:

4.66 sb E V 2.22 exp (- Xt) where:

LLD = the "a priori" lower limit of detection (picocuries per unit mass or volume) sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute)

E = the counting efficiency (counts per disintegration)

V = the sample size (units of mass or volume) ,

i 2.22 = the number of disintegrations per minute per picoeurie l l

Y = the fractional radiochemical yield, when applicable

) X = the radioactive decay constant for the particular radionuclides l (s-1) .

l t = the elapsed time between sample collection, or end of the sample ,

collection period, and time of counting (s)

Typical values of E, V, Y, and t are used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

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Analyses are performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. Table A-5 lists the maximum values for the LLDs of the analyses performed for the HBPP (

l Radiological Environmental Monitoring Program. t 4

1298A.1/CML7(dj)

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I Report 420-87.61 DISCUSSION OF ANALYTICAL RESULTS j

)

The environmental samples analyzed for this report contained radioactivity levels comparable to preoperational levels of similar samples 4 . The t:aximum integrated gamma radiation exposure at an off-site l

1 location was 110 mR at Station 9.

An on-site TLD monitoring program was started July 1983; data for 1986 is shown in Table A-4c. The highest integrated gamma radiation exposures at on-site locations for 1986 were along the northern site boundary near the

(

Waste Handling Area. This is due to the increase in processing radioactive f

waste for disposal in the Waste Handling Area.

Figure 5 graphically presents trends in data for three stations dut-ing (

I a five-year span. The gross beta activity of air particulate from Station l l

3 has remained consistent (except for the May 1986 spike as described in Appendix D. Monitoring Results of the Charnobyl Accident). A comparison between the gamma radiation at Station 14 (nearest occupied public facility)

I and Station 2 (a background location in Fortuna) does not show significant l differences.

I l

1 QUALITY CONTROL Routine quality control was performed throughout the year to ensure the accuracy of the equipment and procedure used in determining the results. I The DER rad.ological laboratory also participated in the EPA Environmental Radioactivity Laboratory Intercomparison Studies Program; the 1

i State cross check program; and the International Intercomparison of Environmental Dosimeters sponsored by the U.S. Department of Energy through the Radiological and Environmental Sciences Laboratory, Idaho Falls, the Environmental Measurements Laboratory, New York, the NRC, and the EPA. In l

l addition, DER also participates in a PG&E intracompany cross check program.

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I Report 420-87.61 Table B-2 presents the results of DER's participation in the EPA Environmental Radiological Laboratory Intercomparison Studies Program.

Participation included the following determinations (sample medium -

radionuclides combination): food and milk samples containing gamma emitters; water samples containing tritium, iodine-131, gamma emitters, alpha and beta emitters; and air particulate samples containing cesium-137, alpha and beta emitters. Three analyses were performed on each sample and the values were submitted for intercomparison with other participants.

The 1986 results shown were all within the acceptable range set by the EPA except for the results of the June gamma emitters in water. The data obtained in June was reviewed and the error was discovered in the computation of the activity concentration. The activity determined was for a sample volume of 4 liters; instead a volume of 0.5 liter was used in the computation. Therefore, the results submitted should have been divided by a i factor of 8. The table below shows the true values as they should had been submitted to the EPA:

l June Gamma Emitters in Water (pCi/L)

Radionuclides DER EPA DER / EPA Cr-51 <LLD 0 -

Co-60 63 66 0.95 Zn-65 86 86 1.00 Ru-103 43 50 0.86 Cs-134 42 49 0.86  ;

- Cs-137 10 10 1.00 l A training session for responsible personnel was held to review the applicable procedures and to assure that this error does not reoccur.

The DER results for the 1985 State cross-check were in good agreement with those obtained by the State. The 1986 State cross-check report has l not been received yet and therefore will be discussed in next year's report.

However, the results of the samples analyzed for the 1986 cross-check program which were sent to the state for 1986 are listed on Table B-1.

6 1298A.1/CML7(dj)

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Report 420-87.61 The preliminary results of the Eighth International Intercomparison of Environmental Dosimeters were returned to users in October 1986 and a comparison of the results is discussed in PG&E DER Laboratory Test Report 420-87.1. The dosimeters were placed in two field locations and also were- {

exposed to a laboratory calibration source. The Panasonic dosimeters exhibited a slight undertesponse, but were within the error limits of the -

results of all participants.

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l Rzport 420-87.61 l 4

REFERENCES

1. Letter from North Coast Regional Water Quality Control Board to PG&E, Attn F. F. Mautz, concerning modifications to waste discharge and environmental radiation monitoring requirements, dated May 7, 1965.  ;

l l

2. Letter from North Coast Regional Water Quality Control Board to PG&E, ,

Attn: Mr. P. Matthew, concerning modifications to waste discharge i requirements, dated April 8, 1966.

3. Department of Public Health letter to PG&E, Attn: Mr. P. Matthew, concerning modifications to environmental radiation monitoring requirements, dated June 17, 1966.
4. Environmental Radiation in the Vicinity of Humboldt Bay Power Plant, Reports 1-8.

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I Report 420-87.61

)

1 APPENDIX \

A. Summary of Radioanalytical Data '

B. Quality Control and Supplemental Data 4 C. Detailed Quarterly Radioanalytical Data '!

D. Environmental Monitoring Results -

Chernobyl Accident 3

i

)

1 l

1 1

l 1

j i

1298A.A/CML7/DJ i

Report 420-87.61 Summary of Radioanalytical Data Tables A-1 Number of Samples Collected A-2 Sumary of Radioanalyses - Marine and Terrestrial Samples A-3 Summary of Gross Beta Activity - Air Particulate Samples A-4 Summary of Environmental Radiation Measurements -

A-4a Stray Radiation Chambers - Off-Site A-4b Film Packs - Off-Site A-4c Thermoluminescent Dosimeters - On-Site A-5 Maximum Values for the Lower Limit of Detection A-1 1298a.a/CML7/dj

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Report 420-87.61 l l

TABLE A-4a )

GAMMA RADIATION MEASUREMENTS STRAY RADIATION CHAMBERS (OFF-SITE) l l

Quarterly Dosimeter Readings, mRl /

l Station 1st2/ 2nd3 / 3rd2 / 4th3 / Total 1 22.0 24.3 17.2 31.0 94.5 2 17.7 24.7 19.1 28.1 89.6 3 21.0 19.0 20.9 26.1 87.0 4 21.5 21.1 19.1 25.9 87.6 1

l 5 18.5 22.7 19.9 26.9 88.0 6 18.0 23.7 18.0 25.4 85.1 7 17.5 19.2 18.2 26.7 81.6 8 21.5 21.6 19.7 25.2 88.0 9 25.3 31.7 21.9 31.1 110.0 10 18.6 19.5 17.9 28.1 84.1 11 21.9 20.4 18.3 27.2 87.8 j 12 16.0 21.4 17.5 24.3 79.2 i 13 20.1 19.3 17.7 24.9 82.0 14 19.7 20.2 20.0 23.3 83.2 15 24.6 20.5 19.4 30.9 95.4 16 19.6 25.5 20.2 32.9 98.2 17 18.4 20.4 18.3 27.4 84.5 18 17.4 22.1 20.1 28.4 88.0 19 19.5 19.5 17.2 26.8 83.0 20 26.7 21.7 18.1 28.7 95.2 21 23.6 23.0 17.3 25.4 89.3 22 19.7 24.2 19.3 28.8 92.0 23 21.1 23.0 18.5 26.0 88.6 24 17.8 18.4 16.5 26.0 78.7 25 19.7 20.8 19.0 26.7 86.2 26 23.1 21.5 18.3 25.0 87.9 ,l 27 20.8 24.2 20.3 29.4 94.7 l 28 18.4 21.1 20.4 26.0 85.9 l 29 20.6 22.1 20.3 26.3 89.3 30 19.3 20.7 16.3 23.4 79.7 Grand Average 88.1 1/ All quarterly totals are based on biweekly readings of stray radiation 1 (ion) chambers. All quarterly totals have been corrected to estimate the )

exposure for the entire quarter (i.e., a missing reading has been replaced by the average of the other biweekly readings for that location). ,

i 2/ 6 sampling periods l 3/ 8 sampling periods A-6 1298A.A/CML7/dj

Report 420-87.61 TABLE A-4b I/

GAMMA RADIATION MEASURDfENTS FILM PACKS (OFF-SITE) 2 QuarterlyDosimeterReadings,mR]

I Station lsL 2nd 3rd 4th Total 1 0 12 0 0 12 2 0 12 0 0 12 3 0 0 0 0 0 '

i 4 0 0 0 0 0 l l

5 0 0 0 0 0 6 0 12 0 0 12 7 0 0 0 0 0 8 0 0 0 0 0 1 9 0 0 0 0 0 0 0 0 0 0 l

10 11 0 0 0 0 0 I

0 0 0 0 0 12 13 0 0 0 0 0 4

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24 0 0 0 0 0 25 0 12 0 0 12 26 0 12 0 0 12 3 12 0 0 12 27 0) 0 28 0 0 0 0 0 0 0 0 0 29 '

0 0 0 0 0 30  !

I) Film packs are analyzed by an outside contractor.

2) All values reported are above a background of 8 mR/ month as determined by the contractor.

3/ Film pack for February was reported damaged; quarterly total based on two-month average.

i/ Film pack for April was reported damaged; <;uarterly total is based on a two-month average.

A-7 1298A.A/CML7/dj

_____________-a

Report 420-87.61 TABLE A-4c i

l GA.59tA RADIATION MEASUREMENTS THERM 0 LUMINESCENT DOSIMETERSI / (ON-SITE)

Quarterly Dosimeter Reading Station 1st 2nd 3rd 4th Total T1 14.4 14.8 12.8 11.6 53.6 T2 12.3 13.8 12.7 12.4 51.2 T3 13.1 13.6 13.3 12.1 52.1 T4 13.3 14.4 13.2 13.5 54.4 T5 16.5 21.2 17.4 13.7 68.8 T6 27.1 30.5 21.9 19.3 98.8 T7 47.3 44.2 28.4 46.5 166.4 T8 22.5 23.4 15.7 14.9 76.5 T9 15.7 16.4 13.7 13.0 58.8 T10 12.5 13.2 12.3 11.5 49.5 Til 15.0 14.8 15.7 12.6 58.1 T12 16.4 15.1 16.0 13.4 60.9 T13 16.3 14.8 16.3 11.8 59.2 T14 12.9 13.7 14.9 12.6 54.1 TIS 12.9 14.0 15.0 12.4 54.3 T16 13.9 13.5 15.4 12.6 55.4 T17 11.9 12.1 13.6 11.7 49.3 1/ The Panasonic Dosimetry System is used for the on-site environmental dosimetry stations.

A-8 1298A.A/CML7/dj

Report 420-87.61 TABLE A-5 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)l/.

Food Drinking Airborne Fish Products Sediment Water Particulate (pCi/kg, Milk (pCi/kg, (pCi/kg, Analysis ,

(pCi/C) (pCi/m3) original) (pCi/E) original) dry)

Gross Beta 0.01 H-3 20002 /

Co-60 15 130 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 1/ See body of report for explanation of LLD 2/ For surface water samples, a value of 3000 pCi/2 may be used.

l A-9 1298A.A/CML7/dj

Report 420-87.61 l

I Quality Control and Supplemental Data Tables B-1 Summary of State Intercomparison Program

  • B-2 Summary of EPA Intercomparison Program B-3 Summary of Saline Water Radi: analyses l

l

  • The data in Table B-1 are the results of analyses performed by DER. The results of the analyses performed by the State laboratory have not been I

published as of the issue date, and the comparison will be discussed in the 1987 Annual Report.

(

1 B-1 1298A.B/CML7/dj

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I

.Raport 420-87.61 l TABLE B-1 (continued)

SUMMARY

OF STATE INTERCOMPARISON PROGRAM.

Quarterly Environmental Radiation Exposure. mRI /

Annual Total Station 1st 2nd 3rd 4th (mR) 1 22.0 24.3 17.2 31.0 94.5 3 21.0 19.0 20.9 26.1 87.0 14 19.7 20.2 20.0 23.3 83.2 18 17.4 22.1 20.1 28.4 88.0 24 17.8 18.4 16.5 26.0 78.7 e

1/ Quarterly totals are based on biweekly readings of stray radiation (ion) chambers. The data have been corrected to reflect exposures occurring )

in each exact quarter.

B-3 1298A.B/CML7/dj

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Report 420-87.61 TABLE B-2 EPA ENVIRONMENTAL RADIOLOGICP. LABORATORY INTERCOMPARISON STUDIES FROGRAM Sample Type Radionuclides Month DER EPA ALL(2) DER / EPA DER /ALL Air Filter Gross Alpha Apr. 16.66 15.00 15.74 1.11 1.06 Sep. 21.33 22.00 21.53 .97 .99  ;

Gross Beta Apr. 56.00 47.00 51.36 1.19 1.09 l Sep. 75.67 66.00 70.59 1.15 1.07 Cs-137 Apr. 9.33 10.00 11.48 .93 .81 Sep. 19.66 22.00 24.12 .89 .82 Food I-131 Jan 23.33 20.00 21.03 1.17 1.11 i July 30.00 30.00 28.24 1.00 1.06 l Cs-137 Jan. 18.33 15.00 16.52 1.22 1.11 July 22.00 20.00 21.49 1.10 1.02 '

K-40 Jan. ---

9.50 9.56 .00 .00 July 11.23 11.50 11.51 .98 .98 Milk I-131 Feb. 10.00 9.00 9.01 1.11 1.11 q June 45.66 41.00 43.94 1.11 1.04 Oct. 56.67 49.00 49.25 1.16 1.15 f Cs-137 June 39.33 31.00 36.55 1.27 1.08 {

Oct. 46.00 39.00 43.51 1.18 1.06 )

K-40 June 15.13 16.00 16.01 .95 .95 l Oct. 15.93 15.65 15.65 1.02 1.02 j Feb. 54.67 52.27 51.05 1.05 1.07 j Water H-3 June 33.10 31.25 30.52 1.06 1.08  !

Oct. 54.37 59.73 56.94 .91 .95 I-131 Apr. 9.33 9.00 8.62 1.04 1.08 Aug. 45.00 45.00 41.64 1.00 1.08 Cr-51 Feb. 39.00 38.00 38.80 1.03 1.01 June --- 0.0 8.67 --- .00 Oct. 59.00 59.00 56.11 1.00 1.05 Co-60 Feb. 18.00 18.00 18.35 1.00 .98 June *508.60 66.00 64.47 7.71 7.89 Oct. 31.66 31.00 31.23 1.02 1.01

~

Zn-65 Feb. 42.00 40.00 41.21 1.05 1.02 June *686.00 85.00 85.65 7.98 8.01 Oct. 92.67 85.00 85.48 1.09 1.08  ;

Ru-106 Feb. ---

0.00 15.01 --- .00 June *343.00 50.00 49.82 6.86 6.88 i Oct. 78.67 74.00 68.18 1.06 1.15 I Cs-134 Feb. 26.33 30.00 27.55 .88 .96 June *349.70 49.00 45.76 7.14 7.64 Oct. 27.66 28.00 26.31 .99 1.05

)

B-5 1298A.B/CML7/dj

l Report 420-87.61 i TABLE B-2 (cont.)

EPA ENVIRONMENTAL RADIOLOGICAL LABORATORY INTERCOMPARISON STUDIES PROGRAM Sample Type Radionuclides Month DER EPA A11(2) DER / EPA DER /ALL Cs-137 Feb. 22.00 22.00 22.49 1.00 .98 June *77.33 10.00 10.53 7.73 7.34 1 Oct. 49.33 44.00 45.23 1.12 1.09 j

1.00 .84 l

Gross Alpha Jan. 3.00 3.00 3.59 4 l Mar. 11.00 15.00 13.11 .73 .84 May 6.00 8.00 7.35 .75 .82 i July 6.67 6.00 6.18 1.11 1.08 {

I Sep. 18.33 15.00 14.96 1.22 1.23 Nov. 14.33 20.00 17.33 .72 .83 Jan. 6.33 7.00 7.20 .90 .88 (

Gross Beta Mar. 9.33 8.00 9.73 1.17 .96 i May 15.00 15.00 14.75 1.00 1.02 I July 18.66 18.00 17.85 1.04 1.05 Sep. 8.67 8.00 9.53 1.08 .91 i

l- Nov. 19.33 20.00 20.44 .97 .95 )

l l

(1) All of the values shown are relative therefore, the total activity or l i concentration levels are not indicated. l (2) The "All" designation refers to all participating laboratories which performed l similar analyses. Those values considered by EPA to be statistical outliers I are excluded. ,

O Values were submitted to the EPA as indicated. There was an error in the computation of the activity concentration. Values should have been divided by a factor of 8. See " Quality Control" section in the main body of this report for further explanation.

1 P-6 1298A.B/CML7/dj

i Report 420-87.61 TABLE B-3 j

1986

SUMMARY

OF RADI0 CHEMICAL ANALYSIS OF SALINE WATER i

Gamma ActivityI _/, pCi/2 H-3 Activity _/,

2 nCi/E i

1st 2nd 3rd 4th 1st 2nd 3_r_d 4th Station l

40 Influent Week 1 ND ND ND ND ND ND ND ND 2 ND ND ND ND ND ND ND ND 3 ND ND ND ND ND ND ND ND 4 ND ND ND ND ND ND ND ND 5 ND ND ND ND ND ND ND ND 6 ND ND ND ND ND ND ND ND 7 ND ND ND ED ND ND ND ND' l

! 8 ND ND ND ND ND ND ND ND 9 h3 E hT E E E h3 E 10 ND ND ND ND ND ND ND ND f f ND ND 1 1 ND ND ND ND ND ND

! E E E E E E E E f l

13 ND ND ND ND ND ND ND ND 14 ND ND 41 Effluent Week 1 ND ND ND ND ND ND ND ND i

2 ND ND ND ND ND ND ND ND E E E E hT E E E  !

3 4 E hT E E E E E E )

5 ND ND ND ND ND ND ND ND 6 ND ND ND ND ND ND ND ND 7 Cs-137: Cs-137: ND ND ND ND ND ND 3.611.0 3.612.1 ND ND ND 8 ND ND ND ND ND 9 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND l 10 l 11 ND ND ND ND ND ND ND ND .

ND ND ND ND ND ND ND ND

. 12 ND ND ND ND ND ND ND ND 13 14 Cs-137: ND 5.1+1.2 i

I/ Gamma measurements are performed on the original sample and results are l '

_ corrected to time of s,ampling. Naturally occurring isotopes are not reported. The maximum lower limits of detection (LLD) for selected nuclides are (in pCi/E): .

Mn-54 15 Co-60 16 Nb-95 15 l' Fe-59 30 Zn-65 30 Cs-134 15 Co-58 15 Zr-95 30 Cs-137 18 2/ Tritium (H-3) analysis is performed on a measured aliquot of distilled l

~

sample. The LLD is 0.5 nCi/f.

1 B-7 1298A.B/CML7/dj l

I l

I Report 420-87.61 0

Detailed Quarterly Radioanalytical Data Tables C-1 First Quarter Radioanalytical Data i

C-2 Second Quarter Radioanalytical Data C-3 Third Quarter Radioanalytical Data C-4 Fourth Quarter Radioanalytical Data l

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Radioanalytical Data l l

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Rsport 420-87.61 TABLE 5 FILM PACK MEASUREMENTS Period Start: 12/31/85 01/28/86 03/11/86 Period End: 01/28/86 03/11/86 04/08/86 Elapsed Time, Days: 28 42 28 Station Total mRI / Total mRl / Total mRl /

1 0 0 0 2 0 0 0 3 0 0 0 4 0 0 0 5 0 0 ~0 6 0 0 0 7 0 0 0' 8 0 0 0 9 0 0 0 10 0 0 0 11 0 0 0 '

i 12 0 0 0 13 0 0 0 14 0 0 0 15 0 0 0  ;

16- 0 0 0 l 17 0 0 0 l 18 0 0 0 19 0 0 0 20 0 0 0 21 0 0 0  ;

22 0 0 0 23 0 0 0 24 0 0 0 25 0 0 0 26 0 0 0 27 0 2f o 28 0 0 0 29 0 0 0 30 0 0 0 i

1/ Above background of 8 mR/mo.

7

_/ Damaged I

C-9 1298A.C/CML7/dj

Report 420-87.61 TABLE 6 AIR PARTICULATE STATION NO. 3 GROSS BETA ACTIVITY Sample Volume Collection Counting Number (m**3) Date Date pCi/m**3 86A16 427 01/07/86 01/14/86 0.008+0.001 86A49 434 01/14/86 01/22/86 0.02050.002 86A58 418 01/21/86 01/26/86 0.005+0.001 86A87 436 01/28/86 02/01/86 0.016IO.002 86B11 436 02/04/86 02/11/86 0.007IO.001 86B51 415 02/11/86 02/19/86 0.014IO.002 86B67 436 02/18/86 02/28/86 0.005IO.001 86B95 428 02/25/86 03/06/86 0.00370.001 86C22 416 03/04/86 03/08/86 0.011IO.001 86C44 434 03/11/86 03/18/86 0.008IO.001 86C82 423 03/18/86 03/23/86 0.006I0.001 86D15 440 03/25/86 04/04/86 0.007IO.001 86D34 417 04/01/86 04/08/86 0.009{0.001 j i

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1298A.C/CML7/dj

Report 420-87.61 TABLE 7 AIR PARTICULATE STATION No. 45 GROSS BETA ACTIVITY Sample Volume Collection Counting Number (m**3) Date Date DCi/m**3 l 86A17 419 01/07/86 01/14/86 0.00710.001 86A50 440 01/14/86 01/22/86 0.017+0.002 86A59 406 01/21/86 01/26/86 0.004TO.001 86A88 438 01/28/86 02/01/86 0.016I0.002-86B12 430 02/04/86 02/11/86 0.006IO.001 86B52 422 02/11/86 02/19/86 0.014TO.002 86B68 431 02/18/86 02/28/86 0.005IO.001 86B96 476 02/26/86 03/06/86 0.004IO.001 86C23 363 03/04/86 03/08/86 0.015IO.002 86C45 439 03/11/86 03/18/86 0.008IO.001 86C83 418 03/18/86 03/23/86 0.005IO.001 86D16 436 03/25/86 04/04/86 0.007IO.001 86D35 421 04/01/86 04/08/86 0.00710.001 i

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Report 420-87.61 Radioanalytical Data C-2 Second Quarter 1986 l

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Report 420-87.61  !

I TABLE 5 FIlli PACK MEASURNENTS Period Start: 04/08/86 05/06/86 06/03/86 Period End: 05/06/86 06/03/86 07/01/86 Elapsed Time, Days: 28 28 28 Station Total mRI / Total mRI / total mRI /

1 12 0 0 2 12 0 0 3 0 0 0 4 0 0 0 5 0 0 0 6 12 0 0 7 0 0 0 8 0 0 0 9 0 0 0 10 0 0 0 11 0 0 0 12 0 0 0 13 0 0 0 14 0 0 0 15 0 0 0 16 0 0 0 17 0 0 0 18 0 0 0 19 0 0 0 20 0 0 0 21 2/ 0 0 22 0 0 0 3 '

23 0 0 0 24 0 0 0 25 12 0 0 )

26 12 0 0 27 12 0 0 28 0 0 0 29 0 0 0 30 0 0 0 1/ Above background of 8 mR/mo.

3/Dosimeterdamaged.

I C-19 J 1298A.C/CML7/dj-

Report 420-87.61 TABLE 6 j AIR PARTICULATE l STATION NO. 3 GROSS BETA ACTIVITY Sample Volume Collection Counting Number (m**3) Date Date pC1/m**3 86D70 430 04/08/86 04/13/86 0.006+0.001

, 86D80 423 04/15/86 04/19/86 0.009IO.001 l 86E25 436 04/22/86 04/30/86 0.008IO.001 l 86E43 420 04/29/86 05/02/86 0.011I0.001 86E80 430 05/06/86 05/13/86 0.007IO.001 86F04 428 05/13/86 05/19/86 0 429IO.0381 /

86F86 481 05/21/86 05/27/86 0.336IO.030T /

86F93 384 05/27/86 06/30/86 0.082IO.008T /

86G24 417 06/03/86 06/30/86 0.012IO.002T /

86G58 432 06/10/86 07/07/86 0.049IO.00ST /

~

86H02 440 06/17/86 07/07/86 0.015IO.002 86H17 424 06/24/86 07/11/86 0.005I0.001

~

86H46 432 07/01/86 07/09/86 0.00510.001 1/ A Gamma isotopic ana)ysis of this air filter was performed. See Table 8.

/

c f

v*

C-20 ,

1298A.C/CML7/dj h- -

Report 420-87.61 TABLE 7 AIR PARTICULATE STATION No. 45 GROSS BETA ACTIVITY i

Sample Volume Collection Counting Number (m**3) Date Date DCi/m**3 86D71 393 04/08/86 04/14/86 0.007+0.001 86D81 413 04/15/86 04/19/86 0.01070.001 i 86E26 439 04/22/86 04/30/86 0.007IO.001 86E44 372 04/29/86 05/02/86 0.011IO.001 86E81 397 05/06/86 05/13/86 0.009IO.001 86F05 419 05/13/86 05/19/86 0.505IO.0451 /

86F87 439 05/20/86 05/27/86 0.368IO.033T / '

86F94 426 05/27/86 06/30/86 0.098IO.009T /

86G25 426 06/03/86 06/30/86 0.015IO.002T /

86G59 384 06/10/86 07/07/86 0.049IO.005T /

86H03 436 06/17/86 07/07/86 0.014IO.002-86H18 378 06/24/86 07/11/86 0.007IO.001 07/09/86 )

86H47 429 07/01/86 0.006_IO.001 1/ A Gamma isotopic analysis of this air filter was performed. See Table 8.

l J

l C-21 l

1298A.C/CML7/dj

Report 420-87.61 I

Radicanalytical Data C-3 Third Quarter 1986 l

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I Report 420-87.61 TABLE 5 ]

FILM PACK MEASUREMENTS Period Start: 07/01/86 07/29/86^ 08/26/86 Period End: 07/29/86 08/26/86 09/23/86 Elapsed Time, Days: 28 28 28-Station Total mRl / Total mRl / Total mRl/.

1 0 0 0 2 0 0 0 3 0 0 0' 4 0 0 0 5 0 0 0 6 0 0 0 7 0 0 0 8 0 0 0 9 0 0 0 10 0 0 0 11 0 0 0 <

12 0 0 0 13 0 0 0 14 0 0 0 l 0  !

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l 25 0 0 0 26 0 0 0 27 0 0 0 28 0 0 0 29 0 0 0 ,

30 0 0 0

-l l/ Above background of 8 mR/mo.

]

C-29 .

1298A.C/CML7/dj

Rnport 420-87.61 TABLE 6 AIR PARTICULATE l J

STATION NO. 3 GROSS BETA ACTIVITY Sample Volume Collection Counting Date Date pCi/m**3 Number (m**3) 86H77 418 07/08/86 07/12/86 0.005+0.001 86I05 434 07/15/86 07/22/86 0.005IO.001 86I42 500 07/23/86 08/01/86 0.006I0.001 86I68 359 07/29/86 08/06/86 0.006ID.001 86IB8 430 08/05/86 08/10/86 0.002IO.001 86J06 425 08/12/86 08/20/86 0.003IO.001 86J48 432 08/19/86 08/26/86 0.005IO.001 86J65 422 08/26/86 09/02/86 0.008IO.001 86K15 439 09/02/86 09/07/86 0.005IO.001 86K38 421 09/09/86 09/19/86 0.004IO.001 86K65 424 09/16/86 09/20/86 0.009IO.001 86K94 438 09/23/86 09/28/86 0.013IO.002 i 86L18 424 09/30/86 10/07/86 0.010;IO.001 l l

l l

l l

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3 C-30 I 1298A.C/CML7/dj

Report 420-87.61 TABLE 7 AIR PARTICULATE STATION NO. 45 GROSS BETA ACTIVITY Sample Volume Collection Counting Number (m**3) Date Date pCi/m**3 86H78 368 07/08/86 07/12/86 0.00610.001 86I06 440 07/15/86 07/22/86 0.00710.001 86I43 494 07/23/86 08/01/86 0.00710.001 86I69 365 07/29/86 08/06/86 0.00610.001 86I89 381 08/05/86 08/10/86 0.00510.001 86J07 389 08/12/86 08/20/86 0.00510.001 86J49 382 08/19/86 08/26/86 0.007+0.001 86J66 381 08/26/86 09/02/86 0.008IO.001 86K16 390 09/02/86 09/07/86 0.008IO.001 86K39 423 09/09/86 09/19/86 0.007IO.001 86K66 418 09/16/86 09/21/86 0.010IO.001 86K95 438 09/23/86 09/28/86 0.014IO.002 86L19 381 09/30/86 10/07/86 0.01210.002 c-31 1298A.C/CML7/dj

Report 420-87.61 Radior.alytical Data C-4 Fourth Quarter 1986 1

1 C-32 1298a.c/CML7/dj

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n hk dd ee o t e oos m i oe iipi t 234567890 BW rraT a 222222223 eel PPE t

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Report 420-87.61 TABLE 5 FIlli PACK MEASUREMENTS Period Start: 09/23/86 11/04/86 12/02/86 Period End: 11/04/86 12/02/86 12/30/86 Elapsed Time, Days: 42 28 28 Station Total mRl / Total mRl / Total mRl /

1 0 0 0 2 0 0 0 3 0 0 0 4 0 0 0 5 0 0 0 6 0 0 0 7 0 0 0 8 0 0 0 9 0 0 0 10 0 0 0 11 0 0 0 12 0 0 0 13 0 0 0 14 0 0 0 15 0 0 0 16 0 0 0 17 0 0 0 18 0 0 0 19 0 0 0 20 0 0 0 21 0 0 0 22 0 0 0 23 0 0 0 24 0 0 0 25 0 0 0 26 0 0 0 27 0 0 0 28 0 0 0 29 0 0 0 30 0 0 0 1/ Above background of 8 mR/mo.

C-39 1298A.C/CML7/dj

Report 420-87.61 TABLE 6 AIR PARTICULATE STATION No. 3 GROSS BETA ACTIVITY Sample Volume Collection Counting Number (m**3) Date Date pCi/m**3 86L97 425 10/07/86 10/26/86 0.015+0.002 86L71 429 10/14/86 10/20/86 0.01510.002

.86M27 422 10/21/86 11/03/86 0.02010.002 86M17 434 10/28/86 11/03/86 0.01610.002 86M41 425 11/04/86 11/13/86 0.01110.001 86M64 364 11/10/86 11/16/86 0.01110.001 86N09 490 11/18/86 11/23/86 0.01910.002 86N88 432 11/25/86 12/15/86 0.009+0.001 86N64 428 12/02/86 12/11/86 0.012IO.002 86N90 429 12/09/86 12/15/86 0.023IO.002 86P13 422 12/16/86 12/25/86 0.016IO.002 86P45 436 12/23/86 12/30/86 0.015IO.002 86P71 423 12/30/86 01/07/87 0.00910.001 C-40 1298A.C/CHL7/dj

Report 420-87.61 TABLE 7 AIR PARTICULATE STATION NO. 45 GROSS BETA ACTIVITY Sample Volume Collection Counting Number (m**3) Date Date pCi/m**3 86L98 431 10/07/86 10/26/86 0.017+0.002 86L78 428 10/14/86 10/20/86 0.01810.002 86M28 378 10/21/86 11/03/86 0.026+0.003 86M18 430 10/28/86 11/03/86 0.018IO.002 86M42 429 11/04/86 11/13/86 0.013IO.002 86M65 360 11/10/86 11/16/86 0.011TO.001 86N10 494 11/18/86 11/23/86 0.021TO.002 86N89 427 11/25/86 12/15/86 0.009IO.001 86N65 386 12/02/86 12/11/86 0.013IO.002 86N91 424 12/09/86 12/15/86 0.027IO.003 86P14 429 12/16/86 12/25/86 0.020TO.002 86P46 382 12/23/86 12/30/86 0.015IO.002 86P72 382 12/30/86 1/10/87 0.01150.002 l

C-41 1298A.C/CML7/dj

Report 420-87.61 APPENDIX D THE MONITORING OF THE CHERNOBYL ACCIDENT 1298a.d/CML7/dj

Report 420-87.61 APPENDIX D DER ENVIRONMENTAL MONITORING REPORT - CHERNOBYL ACCIDENT On April 26, 1986, a major accident occurred at Unit 4 of the Chernobyl Nuclear Power Plant in the USSR. Radioactivity was released continuously from the damaged reactor beginning with the explosion and concluding on about May 6, 1986. The airborne releases of megacurie quantities of fission products into the atmosphere were carried by prevailing winds and subsequently reached the United States in early May.

The initial observation of detectable amounts of radioactivity from Chernobyl was detected at DER on May 5. An air sampler was set up to monitor the airborne radioactivity at DER, the results of which are compiled on page D-5 of this appendix. The air particulate filter was analyzed for gross beta activity and was also analyzed for gamma emitters on the gamma spectrometer. Gamma isotopic analysis was also performed on the iodine cartridge collected.

At DER, the fission products detected were I-131, Cs-137, Cs-134, Ru-103, Te-132, La-140, Ba-140. The gross beta activity detected reached its highest peak of 1.306 i .115 pCi/m 3 during the collection period of 5/9/86 to 5/12/86. The activity dropped gradually and was barely detectable towards the end of the month (see page D-5). I-131 was also detected in the iodine cartridges during the collection periods and it reached a maximum of 1.33 1 0.80 pCi/m3 ,

DER also gathered data from the air samplers located at routine sampling stations in the Diablo Canyon Power Plant environs, Santa Barbara County and in the Humboldt Bay Power Plant environs. Special air samplers l

were also set up at different locations on the plant sites at DCPP and HBPP.

Air particulate samples from DCPP had gross beta activity ranging from 0.46 l

to 0.72 pCi/m3 during the collection period 5/7 - 5/13 (see pages D-1 to D-3).

D-1 1298a.d/CML7/dj

Report 420-87.61 Similar activities were detected also at the Santa Barbara County. The highest activity was detected at Solvang with an activity concentration of 0.654 pCi/m3 (collection period 5/7-5/13). At HBPP the highest concentration was detected during the 5/13 - 5/21 collection period and it was 0.368 pC1/m 3 . Iodine-131 was detected at all air sampling stations during this period. Its highest concentration corresponded with the period of highest gross beta activity.

Special samples of interest were also analyzed to confirm the presence of fission products in the environment. Rain water was collected at DER for analysis. However the collected sample volume was too small for gamma analysis therefore the sample was analyzed for gross beta activity. The analysis showed a gross beta activity of 3.4 + 1.9 pC1/L.

Milk samples were collected from Pedrotti and Challenge dairies in Humboldt County, a dairy in Petuluma and Caroni Dairy in Santa Barbara County. A milk sample was also bought off-the-shelf at a supermarket in San Ramon. Iodine-131 was detected in all the milk samples. The concentration ranged from 25 to 93.5 pCi/L (see page C-9).

Lawn clippings from Alamo, California and Salt Lake City, Utah were also analyzed and were found to contain 1680 and 3790 pCi/kg of I-131 respectively. The other radioisotopes detected in elevated concentrations were Cs-137, Ru-103 and Os-134. Vegetable samples collected at routine sampling stations at DCPP also showed deposition of I-131, Cs-137 and Ru-103.

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