ML19263D032

Environ Radiation Surveillance Rept for 771001-780331. Environ Radioactivity Decreased During Time Period Until End of Mar,When Fallout from Atmospheric Detonation in China Reached Vicinity

ML19263D032
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Site:	North Carolina State University
Issue date:	03/13/1979
From:	Ball A, Debnam J North Carolina State University, RALEIGH, NC
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ML19263D029	List: ML19263D028 ML19263D032
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ENVIROIlME11TAL RADIATION SURVEILLANCE REPORT POR THE PERIOD OCTOBER 1, 1977 TO MARCH 31, 1970 Arthur C. Ball, Environmental Health Physicist Joshua Dobnam, Environmental Chemist Radiation Protection Council L. T. Caruthers, Radiation Protection Officer D.11. Morgan, Associate Radiation Protection Officer North Carolina State University Raicigh, North Carolina 7903200%3

2 in the vicinitico of the radioactive material burial grounds. These sampics ucre ached for 96 houro at 5200 C and then counted in the Ecchman Uide Beta II for alpha and beta activitics.

50-gram aliquoto ucre also analy=ed uith the Go(Li) detector and Huc1 car Data UD-100 analyzer for comma activity.

Soil opecific activitico are reported in Tabic 5.1.

Specific activitico for Thorium-22g and Radium-226 calculated from the gamma spectra of the 50-gram campics are observed to have high standard deviations. This is caused by the necccoity of subtracting one reic'4.vely large number (Background Pech) from another number only clightly larger (Sm lo Penh) to obtain not counts due to the sampic; houever, ir. n11 cases the campic camma photopenho contained more counto than the bachground peakc. Thus, the 50-gran configuration oppe.ro to be more reliabic than the previoucly used one Kilogram configurati - -^teh frequently produced fouer counts in a onmpic spectrum peak than in the corresponding background peak.

6.

VEGETATION Corn and coybean snmpico ucro co11ceted at harvcot time and analy=cd both Ic ally and at Tolodync Icotopco.

One granc and five pine needic sampics ucro taken in the vicinitics of the rac'onctive materini burial grounds, and one pine needle sampic una tchen at the Soutn coil location. Theoc campics ucre ashed in the semo manner as the soil and then analyzed for gross alpha and beta activitics. Hone of the onmpics appear to have abnormal readinga.

Theoc activitics are reported in Tabic 6.1 along tdth the recults of the corn and ooybcon analyses.

7.

Thermolumincocent Dosimetcro (TLDs)

Agreement betucen local and contracted analysis is very good for the majority of TLD readingo during this six month period. A feu discrepancies still exist, but it is hoped the current trend touard consistent readingo vill continue. TLD readings are reported in Tabic 7.2.

3 Tablo 2.1 Air Particle Samplin8 Locationo Designation Direction Distance Elevation Broughton Southucot 410 ft.

- 55 ft.

David Clark Lab (DCL)

Wcot Library Northwest 629 ft.

+ 36 ft.

Riddick Southcaat 325 ft.

- 46 ft.

Uithero Northcaat 270 ft.

- 19 ft.

Direction - Direction from Reactor Stack Diotance - Distance from Reactor Stack Elevation - Elevation with respect to top of itcactor Stack Tabic 2.2 Airborne Groco Beta Activity (fCi/113 1 c)

Date Broughton DCL Library Riddich Uithero 1977 10/3-10/7 000.2

• 47.8 649.3

• 36.3 678.4

• 37.7 702.2 38.9 926.3 50.0 10/10-10/14 149.6

• 11.;

145.3 i 11.4 Hot Operative 147.1

• 11.5 145.3

• 11.4 10/17-10/21 409.7 i 24.4 500.2

• 32.0 328.8

• 20.4 403,6

• 24.1 311.2

• 19.5 10/24-10/28 147.8

• 11.7 122.3

• 10.5 171.2 i 12.8 112.2

• 10.0 120.9 i 10.4 10/31-11/4 175.5 i 12.9

72.7

• 12.0 128.8 i 10.7 146.0

• 11.5 132.7

• 10.9 11/7 -11/11 309.7

• 19.4 33J 7 20.7 254.3

• 16.7 415.1 24.6 325.5

• 20.2 11/14-11/18 292.4 i 18.6 312.9 19.6 203.6

• 14.2 225.2

• 15.3 270.5

• 17.5 11/21-11/25 105.4 i 9.7 103.2

• 9.6 78.8

• 8.5 130.6 10.9 141.4

• 11.4 11/28-12/2 176.6

• 12.9 172.7

• 12.7 108.3 i 9.7 149.6

• 11.6 160.1

• 12.1 12/5-12/9 101.8 i 9.4 116.5 10.1 75.2

• 8'.2 131.7 10.8 102.2 i 9.4 12/12-12/16 159.7

• 12.2 142.4

• 11.4 111.2

• 9.9 125.2

• 10.5 133.1

• 10.9 12/19-12/23 44.6

• 6.9 42.1

• 6.8 30.9 6.4 34.2

• 6.5 39.6

• 6.7 12/26-12/30 200.0 14.1 198.2 t 14.0 128.4 10;7 206.5

• 14.4 102.7

• 13.3 1978 1/2-1/6 166.5

• 12.5 151.4

• 11.8 86.7 i 8.8 179.1

• 13.1 174.8

• 12.9 1/9-1/13 176.3 i 12.2 187.8

• 13.5 93.5

• 9.1 142.4

• 11.3 144.6

• 11.4 1/16-1/20 127.0 i 10.6 129.5

• 10.7 76.3

• 8.2 130.9

• 10.8 127.7

• 10.6 1/23-1/27 Not Operative 198.6 i 14.1 111.5 *10.0 187.4 a 13.5 103.8

• 13.4 1/30-2/3 157.2

• 12.1 148.6

• 11.7 138.1

• 11.2 143.5

• 11.5 164.0

• 12.4 2/6-2/10 189.9

• 13.7 142.4 11.4 128.4

• 10.8 139.6 i 11.3 145.0

• 11.5 2/13-2/17 145.3 i 11.4 160,1

• 12.1 116.5 10.0 152.5 t 11.8 155.8

• 11.9 2/20-2/24 190.3 i 13.0 161.2

• 12.4 122.3

• 10.6 150.4 2 11.9 142.1

• 11.5 2/27-3/3 140.3

• 11.3 103.2 i 9.6 128.1 i 10.7 52.9

• 7.4 146.0 i 11.6 3/6-3/10 150.0 i 11.7 145.0

• 11.5 50.0

• 7.2 133.5 = 10.9 137.8

• 11.1 3/13-3/17 237.4

• 15.9 252.5 16.6 190.6

• 13.6 169.1

• 12.6 166.9

• 12.5 3/20-3/24 4855.9 *246.4 5409.4* 274.1 3437.4 *175.5 4303.6*218.8 4174.5 *212.4 3/27-3/31 880.6 i 47.8 909.7

• 49.3 388.1

• 23.4 718.7

• 39.8 999.3

• 53.7

4 Tabic 2.3 Airbottic I' art.iculate Specific Activity (Y cnittero)

'Ccmpus Average fCL/113

• 1 c)

Date 1977 Co Ce 103,

106 95,

95 41 3

nu 3

3 10/3-10/7 52.2

• 2.4 67.4 6 0.8 47.0 i 0.7 11.6 3.5 60.0

• 2.4 59.5 0.9 10/10 10/14 13.8

• 2.0 9.7 i 0.6 7.5

• 0.4

< 5.0 10.9

• 1.7 13.8

• f.6 10/17-10/21 45.0 2.1 26.0 0.7 24.0 i 1.2 13.1

• 3.3 28.9 4 1.7 41.2 0.0 10/24-10/20 33.3

• 2.3 12.2 0.6 12.6

• 0.5

< 5.0 17.6

• 1.8 27.2

• 0.0 10/31-11/4 33.0

• 4.7 7.5 6 1.2 8.1 i 0.0

< 5.0 21.0 i 3.6 26.2 i 1.1 11/7-11/11 52.2 i 2.0 9.0

• 0.5 11.0

• 0.4 13.3 = 3.0 21.2 a 1.6 36.5

• 0.8 11/14-11/10 35.3 1.4 7.2 i 0.4 8.0

• 0.

10.2 t 2.2 14.5 1.2 26.0 0.6 11/21-11/25 16.0

• 1.5 2.7 0.4 2.9 t 0.3

< 5.0 4.7 i 0.6 10.5 i 0.5 11/28-12/2 23.9

• 1.5 2.0 0.4 2.0 0.3

< 5.0 7.4

• 1.1 14.1

• 0.5 12/5-12/9 17.2

• 1.5 1.5 0.4 1.2 i 0.3

< 5.0 4.2 i 0.6 8.5

• 0.5 12/12-12/16 23.5

• 1.5

< 1.0 1.3 = 0.3 7.0 2.4 3.4

• 1.1 11.6 0.5 12/19-12/23 6.8 i 2.0

< 1.0

< 0.5

< 5.0 11.1 1.1 5.0 0.7 12/26-12/30 16.4

• 1.5

< 1.0

< 0.5

< 5.0 4.1 0.9 9.5 i 0.4 1970 1/2-1/6 25.5 1.4

< 1.0

< 0.5

< 5.0 4.3 0.6 10.4 i 0.4 1/9-1/13 20.3 i 1.5

< 1.0 0.9 0.3

< 5.0 5.3

• 0.6 11.6

• 0.5 1/16-1/20 22.0

• 1.5

< 1.0 0.7 i 0.3

< 5.0 4.4 0.6 9.2

• 0.5 1/23-1/27 30.9 i 1.5

< 1.0

< 0.5 7.7

• 2.1 4.7 0.6 11.2 i 0.5 1/30-2/3 26.8

• 1.5

< 1,o

< 0.5

< 5.0 3.0 0.6 9.6 i 0.5 2/6 2/10

?8.5

• 1.6

< 1.0

< 0.5 10.1 i 2.4 3.2

• 0.5

8. 6

• 0 '5 2/13-2/17 23 3 i 1.4

< 1.0

< 0.5

< 5.0 3.7 i 0.6 7.5 0.4 2/20-2/24 20.2

• 1.6

< 1.0

< 0.5 4.9

• 1.4 4.1 0.7 9.5

• 0.5 2/27-3/3 23.4

• 1.7

< 1.0

< 0.5 6.0

• 2.3 3.5

• 0.6 0.8 i 0.6 3/6-3/10 27.1

• 1.6

< 1,0

< 0.5

< 5.0 3.6

• 0.6 8.1 0.4 3/13-3/17 37.3 1.6

< 1. 0

< 0.5

< 5.0 4.3

• 0.6 0.9 0.5 3/20-3/24 110.1

• 3.4 313.1

• 1.4 425.5

• 0.1 27.2 i 3.4 C0.5

• 2.2 34.2

• 0.7 3/27-3/31 26.0

• 1.0 55.2 0.7 91.3 0.0

< 5.0 16.1

• 1.2 12.3

• 0.4 Tabic 2.4 OtherFionionFragmentsDgtectedinAirSampicsFollouing Atnoophoric Tecto (fCi/M *1o)

Iootope 10/3-10/7 10/10-10/14 3/20-3/24 3/27-3/31 "IIo

< 5.0

< 5.0 316.7 4.7

< 5.0 1

To

< 0.5

< 0.5 96.8

• 10.2

< 0.5 131 I 37.2 1.0

< 1.0 910.9 C8.6 102.3 i 1.2 132Te

< 4.0

< 4.0 659.3 3.5 38.8 o 1.2 137 Co 5.0 0.4 2.3 i 0.4 10.6 0.5 5.7 0.3 40Ba 62.4 1.9 4.7 1.6 592.4

• 3.7 98.5 i 1.0 140La 47.1 i 1.0 6.6

• 0.9 451.5 2.7 76.9 i 1.0 I07Nd 40.0

• 6.9

< 5.0 145.1

• 1.0

< 5.0

5 Tabic 3.1 Milh Specific Activity (pci/1 1o)

O 0

3 Date Sr Sr I

10/77 2.96 1 0.67

< 2.0 11/77 3.04 0.83

< 2.0 12/77 3.05 i 0.60

< 2.0 1/78 3.91 i 0.97

< 2.0 2/78 4.49 0.05

< 2.0 3/78 6.12 1 0.79

< 2.0 3/78 C*

2.9 0.4

< 1.0

• C denotco scrapic contracted to Toledync Isotopen for analysio Tabic 4.1 Surface Water Specific Activity (pCi/1 1o)

Date Location

• Co Co Co 40;t 90 Gr os Beta SC 60 Sr Oct OIT

< 0.1

< 0.2 < 0.2 15.10 i 6.33 0.30 0.03 4.15

• 0.35 19/7 OFF

< 0.1

< 0.2 < 0.2 19.57 i C.22 0.60

• 0.04 5.35 0.41 ITov 0 11

< 0.1

< 0.2 < 0.2 30.61 i 7.56 0.16 0.02 4.11

• 0.36 1977 0FF

< 0.1

< 0.2 < 0.2 36.07 7.07 0.19 i 0.02 3.84

• 0.35 Dec Oli 0.017 i 0.52 < 0.2 < 0.2 67.94 6 24.27 1.29 i 0.03 13.60i 0.31 1977 0FF

< 0.1

< 0.2 < 0.2

< 2.0 1.43 t 0.00 14.251 0.85 Jan ON 0.25 0.40 < 0.2 < 0.2

< 2.0 0.25 i 0.02 2.90i 0.29 1970 0FF 0.71

• 0.50 < 0.2 < 0.2

< 2.0 0.39 0.03 2.40 i 0.26 Feb 011 0.10 i 0.49 < 0.2 < 0.2

< 2.0 0.33

• 0.03 2.40 0.28 1970 OFF

< 0.1

< 0.2 < 0.2 2.0 0.47 i 0.03 2.00

• 0.29 Mar ON

< 0.1

< 0.2 < 0.2 24.01 31.92 0.66 1 0.05 5.22 i 0.42 1978 0FF 0.17 i 0.59 < 0.2 < 0.2 57.30 *32.10 0.93i 0.06 5.19 i 0.41 4

+ Location

• Gross Alpha Gross Beta Th Ra Cs fs North (L) 2.54

• 0.75 20.86

• 2.50 0.014 i.044 0.289 i.036 0.444 *.015 0.044

.469 North (C)

< 7.0 18

• 2 0.56 0.06 1.26 0.60 1.12 1 0.11 4.08

• 0.57 South (L) 3.39

• 0.85 14.69

• 2.31 0.084 i.049 0.295 *.038 0.426 i.016

< 0.4 South (C) 9.2 i 6.5 10 i 2 0.52

• 0.05 1.27

• 0.17 0.71 i 0.07 2.60

• 0.46 East (L) 11.53 i 1.55 49.38 1 3.90 0.367

• 0.056 0.362 2.044 0.073 i.012 8.826 i 0.600 East (C) 9.2

• 6.5 45

• 3 1.01 1 0.10 2.04 1 0.23 0.10

• 0.04 18.1 1.C Wect (L) 5.25 1.04 10.15 2.46 0.235

.050 0.272 *.044 0.102 i.013 2.131 i 0.629 West (C) 23 9

21 i2 0.76 a 0.00 1.02 i 0.12 0.09

• 0.02 4.61

• 0.46 UBG Uorth (L) 6.78 i 1.17 44.20 3.67 0.625 i 8.971 0.790

• 2.475 2.692 i 0.225 5.111

• 10.107 UEG South (L) 1.69 0.64 11.98 i 2.22 2.104 i 9.125 5.917

• 5.494 2.044

• 0.232 10.147 i 10.165 UBC East (L) 5.33 i 1.10 33.53 i 3.17 0.694

• C.933 0.752

• 2.436 8.908

• 0.286 10.870 i 10.141 UDG Inside (L)

' 39 0.85 43.70 i 3.64 1.676 0.913 0.704 2.513 0.631 i O.190 17.800 i 10.220 UBG 4.5' East (L) 3.22 0.03 19.30 2.54 2.229 8.907 0.546 i 2.532

< 0.1 13.612 i 10.140 OBG 4.5' West (L) 2.71 1 0.77 12.22 i 2,23 2.141 10.522 0.817 i 2.393

< 0.1 5.042

• 10.138

+ Location - Denotes direction from reactor or burial ground Eurial Ground sangles are in near proximity to fence UEG denotes Heu Eurial Ground OBG denotes Cid Durial Ground (not presently in use)

Inside sample is above covered burial trenches 4.5' denotes depth of sample, others are at surface.

• L - Denotec Locally Evaluated Sampic c - Denotes Contracted Analysis by Tcledync Isotopes Tabic 5.1 Soil Specific Activity (pCi/gm 1 c) t e

1

Tabic 6.1 Vegetation Specific Activity (pCi/gu

• 1 a) 40

+Sampic*

Grono Alpha Gross Beta Cn g

Soy (L)

< 0.03 17.24 o 0.92 1.10 0.30 9.72 0.02 Soy (C)

< 0.7 31 i 1

< 0.03 15.3 1.5 Corn (L)

< 0.01 1.90 i 0.12

< 0.1 0.03 0.02 Corn (C)

< 0.6 6.5

• 0.3

< 0.03 3.79 i 0.00 S - Pine (L) 0.034

• 0.000 2.57 0.14 11BG Pine (L) 0.104 4 0.014 3.70 i 0.20 IIBG Graco (L) 0.120 i 0.015 1.75 0 0.10 GBG ITE Pine (L) 0.025 0.007 4.37 i 0.23 ODG SE Pine (L) 0.024

• 0.007 7.19

• 0.37 OBG SW Pine (L) 0.023

• 0.006 6.32 0.33 CBG IET Pine (L) 0.020 0.007 3.95

• 0.21

+S - Denotec come location as South Soil Sample IIBG - Denotco Hou Burial Ground (outside fence)

OBG - Denotco Old Durial Ground (inatdo fence)

IIC, SE, SU, FM - Dcnotc8 800 Graphic quadrant of Burial Ground

8 Tabic 7.1 Thermoluminescent Dosimeter (TLD) Locations Designation Location Broughton 410 ft, couthuest of and 55 ft. belou top of Renctor Stack DCL Roof of David Clark Laboratorica Library 629 ft. northuest of and 36 ft. above top of Reactor Stack Riddich 325 ft. coutheast of and 46 f t. below top of Reactor Stach Withers 270 f t, northeast of and 19 f t belou top of Reactor Stach Control Room 214 David Clark Labs R-3 Entrance to UCSUR-3 Reactor Bay from Control Room PULSTAR PULSTAR Rcactor Bay, Ucst Wall Equipment Room PULSTAR Equipment Room East of PUL' TAR Bay Control Room PULSTAR Control Room Pool Over PULSIAR Reactor Pool Stach Top of PULSIAR Reactor Stack Tabic 7.2 Thermoluminescent Dosincter Readings (Average mR/dk based on Co-60 Standard)

Arca Monitors 10-77 11-77 12-77 1-70 2-78 3-78 Broughton L

1.9 2.4 2.0 1.2 2.5 2.3 Broughton C

1.9 2.0 1.9 2.1 1.9 2.2 DCL L

1.4 1.5 1.3 0.9 1.3 1.6 DCL C

1.2 1.3 1.2 1.5 0.0 1.4 Library L

2.1 2.3 2.3 1.2 2.7 2.7 Library C

1.0 2.0 1.9 2.1 1.7 2.1 Riddick L

2.2 2.4 2.4 1.3 2.5 2.0 Riddick C

2.6 2.5 2.1 2.2 1.0 2.5 Uithers L

1.6 2.0 1.7 1.3 1.9 2.2 Uithers C

1.5 1.0 1.8 1.5 1.3 1.0 Control L

1.6 2.0 1.3 1.2 2.2 2.2 Control C

2.3 1.0 1.5 1.0 1.3 1.G Reactor Honitors R-3 L

3.5 4.2 4.2 2.3 5.4 5.3 R-3 C

3.3 3.3 3.1 3.2 2.9 3.4 FULSTAR L

5.5 6.5 7.6 4.2 39.3 53.0 PULSTAR C

4.0 4.0 4.2 5.6 11.9 12.1 Equipment Room L

16.1 16.5 17.0 8.9 30.5 24.6 Equipment Room C

19.4 17.0 15.0 18.2 22.0 22.5 Control Room L

4.1 5.5 5.4 2.8 8.7 8.0 Control Room C

4.2 5.1 3.9 4.5 4.3 4.3 Pool L

23.4 20.1 21.6 10.4 44.9 34.3 Pool C

26.0 28.5 19.5 23.9 30.4 25.3 Stach L

Lost

'0 5.4 1.3 3.1 2.8 Stach C

1.6 1.8 1.1 1.7 1.2 1.9

• L - Denotes Locally Evaluated LiF Dosimeters C - Denotes CaSO :Dy Dosincters contracted to Telodync Isotopes for analysis 4

ENVIROINENTAL RADIATION SURVEILLANCE REPORT AND ANALYSIS PROCEDURES APRIL 1,1978 TO SEPTDBER 30, 1978 Arthur C. Ball, Environmental Health Physicist Joshua Debnam, Environmental Chemist Radiation Protection Council L. T. Caruthers, Radiation Protection Officer D. W. Morgan, Associate Radiation Protection Officer North Carolina State University Raleigh, North Carolina

1.

INTRODCCTION The Environ = ental Radiation Surveillance (ERS) program at North Carolina State University has been in operation on a ILmited basis since August 1970 and as a funded program since Jaly 1973. During these first five years as a funded operation, the program has grown to maturity. Local analyies now in-clude gross alpha and beta counting of air, water, soil, vegetation, and sewage. Gamma analysis is performed on air, water, soil, vegetation, and

= ilk.

Strontium-90 analysis is perfor=ed on water, milk, sewage, and waste water.

In order to perform the large and still growing nu=ber of analyses, the ERS staff of two full tbse persons and one part time student assistant utilize a well equipped laboratory. In addition to chemicals and chemistry apparatus, the laboratory includes a Beckman Widebeta II Low Eackground Alpha and Beta Counter and a Nuclear Data ND-100, 4096 Channel Ga==a Analyzer used with a Ge(Li) Detector and NaI(TI) Co=pton Suppression *? nit on one half of the memory, and a 4" x 4" NaI(TI) Detector Crystal with a 1" x 2" Well on the second half.

The Ge(Li) system, having high resolution (but low efficiency), is used to identify specific radionuclides in air, water, vegetation, and soil sa=ples.

Counting times are necessarily long as activities are low.

The NaI Well Crystal is used for detection of specific radionuclides where identification is known and higher efficiency is required.

Iodine-131 detection in air and milk samples is the primary function of this system.

Ga=ma spectra from sa=ples counted on both detectors are stored on magnetic tape and analyzed on the IEM-370 Model 165 computer at the Triangle Universities Computer Center (TUCC). NaI(Tl) spectra are first examined on the Cathode Ray Tube (CRT) on the ND-100 by = cans of overlaying a background spectrum of similar counting time.

Any photopeaks observed are then analyzed by mear of the Gruss analysis program. Ge(Li) spectra are analyzed for all gn=ca photopeaks by metns of the MONSTR Program which was made available by Oak Ridge National Laboratories in late 1975.

Calculations for specific activities for all as=ples are accemplished on a Wang Model 462 Progra=mable Electronic Calculator.

2.

AIR MONITORING Airborne particles are collected with high volume samplers equipped with 6" x 9" glass fiber filters and millipore pumps 2 quipped with 47 mm millipore filters and activated charcoal cartridges.

These samplers are located in five sampling stations on the NCSU campus (see Table 2.1) and operate for six hours a day, Monday through Friday of each week.

Samplers are turned on and off by a seven-day clock switch with actual time of run recorded on an electric timer which is switched on and off simul-taneously with the samplers.

After a ten-day decay period to eliminate naturally occurring radon and thoron daughters, the 6" x 9" glass fiber filters are combined for a composite sample and analyzed with the Ge(Li) Detector and ND-100 Gamma Analyzer. The spectra are then put on magnetic tape and gamma activity is determined by use of the MONSTR Program on TUCC IBM 370 Computer.

The millipore filters are counted for 100 minutes each for gross alpha and beta activity (also after a ten-day decay period) with the Widebeta II.

The charcoal cartridges are analyzed immediately as a composite sample for halogen activity by means of a long count (over the weekend following Friday collection) on the 4" x 4" NaI(TI) Crystal and ND-100 Gamma Analyzer.

Determination of halogen activity in gaseous form is accomplished by means of the overlay feature of the CRT on the ND-100.

The sample spectrum is displayed simultaneously with a background spectrum of similar counting time. Gamma peaks above background which are observed in the sample spectrum may then be measured to determine specific activity by means of the corputer program " GAUSS" and the TUCC Computer. To date, no gaseous halogen hos been detected in air samples. Iodine activity which has been reported following atmospheric nuclear detonations in the Peoples Republic of China nas been measured on the glass fiber filters indicating that the halogen has attached itself to dust particles and is no longer in gaseous form.

Gross alpha and beta activity is calculated from the Widebeta II printout and reported as Specific Activity in femto Curies per Cubic Meter (SA fCi/M ).

{

f C + B +.0025 (C - B)

SA =

where C = Sample counts per 100 min B = Background counts pe-100 min

"* (

• " Y}

U = (.222 (100 = n (fC1) )(

For a sample collection time of 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> at a flow rate of 30 liters per minute:

1. 8 Volume = ( 30

)(30 hrs)(60 min /hr)( 1000 iters ) = 54 M Efficiency =.278 for alpha in the millipore configuration

.380 for beta in the millipore configuration therefore, U = 3.33 for alpha 4.56 for beta This problem is solved on the Wang Calculator with program " Gross or and 5 2 1c" Verification No. 234 or "SA Beta Air" Verification No. 309.

Specific Activity for gamma emitters is calculated from the computer printout for the spectrum and is also reported as Specific Activity in fCi/M. The fission products reported as present in air samples do not nomally appear in background spectra; thus, it is not necessary to substract background peaks from sample peaks.

SA = Y/sec (

)(

)

^

+.0025 5

Y 3.7 x 10 y

where y/sec is taken from the MONSTR printout or converted from the area of the peak as determined from the GAUSS printout I - Intensity (or abundance) of the ga=ma V = Volume of sample T = Half-life of nuclide in days o = Standard deviation of counts per see taken from MONSTR Y

printout or converted to decimal from GAUSS printout.

This problem is solved on the Wang Calculator with program "y Specific Activity" Verification No. 413.

During the period of this report, airborne activity has generally been declining following the last atmospheric test at the Lop Nor test site n March 1978. Typical lung hazard fission products are reported in Table 2.3 and other fission products associated with the Chinese testing are reported in Table 2.4.

Gross beta activity is reported in Table 2.2.

No significan' alpha activity has been detected.

Table 2.1 Air Particle Sa=pling Locations Desienation Direction Distance Elevation 55 ft.

Broughton Southwest 410 ft.

David Clark Lab (DCL)

West Library Northwest 629 ft.

+ 36 ft.

Riddick Southeast 325 ft.

- 46 ft.

19 ft.

Withers Northeast 270 ft.

1Direction - Direction from Reactor Stack Distance - Distance from Reactor Stack 3Elevation - Elevation with respect to top of Reactor Stack Takle 2.2 A*.rborne Gross Beta Activity (fCi/M

=10 )

Date Brouchton DCL Librarv Riddick Withers 1978 4/3-4/7 264.6 = 15.7 233.4 = 14.1 130.1 = 9.1 221.3 = 13.5 219.8 = 13.5 4/10-4/14 334.5 = 19.1 307.9 = 17.8 280.9 = 16.4 315.8 = 18.1 330.5 = 18.9 4/17-4/21 59.6 = 5.7 48.6 = 5.2 36.3 = 4.7 57.6 = 5.6 45.1 = 5.1 4/24-4/28 170.5 = 11.0 166.6 = 10.8 145.7 = 9.8 181.3 = 11.5 27.0 = 4.4 5/1-5/5 142.4 = 9.6 125.5 = 8.8 81.3 6.7 149.9 9.9 132.2 = 9.1 5/8-5/12 108.6 = 7.9 107.5 = 7.8 103.5 = 7.7 90.8 = 7.1 118.5 = S.4 5/15-5/19 44.6 1 4.9 46.7 2 5.2 27.3 2 4.2 52.7 1 5.3 49.5 = 5.2 5/22-5/26 123.7 = 8.6 130.5 = 9.0 118.9 = 8.5 89.9 = 7.1 156.3 = 10.3 5/29-6/2 129.2 = 8.9 101.9 = 7.6 118.7 = 8.4 3.7 = 3.3 97.8 = 7.4 6/5-6/9 78.7 = 6.7 65.7 = 6.1 63.5 = 5.9 79.6 i 6.7 82.6 = 6.8 6/12-6/16 165.9 i 10.8 151.9 = 10.1 127.9 = 8.9 165.0 = 10.7 146.1 = 9.8 6/19-6/22 163.9 = 10.7 152.9 = 10.21 138.9

• 9.5 146.6 = 9.9 175.2 = 11.3 6/26-6/30 148.8 = 9.9 111.8 = 8.2 108.1 = 8.0 113.8 = 8.3 101.5 = 7.7 7/3-7/7 83.7 = 6.8 85.5 = 6.9 72.3 = 6.3 73.8 = 6.3 Not Operational 7/10 7/14 117.6 = 8.4 108.4 = 7.9 104.2 7.7 103.1 = 7.7 90.5 = 7.1 7/17-7/21 146.8 = 9.9 129.0 = 8.9 123.5 = 8.7 130.5 2 9.1 141.9 = 9.6 7/24-7/28 49.2 2 5.1 44.6 = 4.9 35.4 = 4.5 42.9 = 4.8 43.3 = 4.9 7/31-8/4 64.6 = 5.8 58.7 = 5.5 52.5 = 5.2 66.4 = 5.8 62.9 = 5.7 8/7-8/11 48.6 = 5.3 58.0 = 5.6 38.9 = 4.9 44.4 = 5.1 41.5 = 4.9 8/14-8/18 60.0 = 5.7 54.7 = 5.4 48.1 = 5.1 54.5 = 5.4 61.5 = 5.7 8/21-8/25 96.3 = 7.4 104.4 = 7.7 S0.2 = 6.6 105.3 1 7.8 90.3 = 7.1 8/28-9/1 48.6 = 5.1 49.5 = 5.1 42.2 = 4.8 44.6 = 4.9 61.3 = 5.7 9/4-9/S 65.9 = 5.9 85.9 = 6.8 S0.4 = 6.6 88.1 = 6.9 86.4 = 6.8 9/11-9/15 95.0 = 9.3 91.4 = 9.1 88.1 = 8.9 92.1 = 9.1 109.4 = 9.9 9/18-9/22 80.2 i 8.4 75.2 = 8.2 69.8 = 7.9 63.3 = 7.7 92.8 = 9.0 9/25-9/29 96.4 = 9.1 78.1 = 8.3 70.1 = 7.9 91.7 = 8.9 80.2 S.4 4

Table 2.3 Airborne Particulate Specific Activity ( y emitters)

(Campus Average fCi/M =1o) 141 103 106 5

95 Date 1978 Ce Ce Ru Ru Zr Nb 4/3-4/7 64.3 3.7 5.5 0.5 8.6 = 0.6 11.9 = 1.4 6.8 i 0.8 13.1

• 0.8 4/10-4/14 79.4 i 4.4 8.2 0.7 14.7 A 0.7 14.3 3.1 9.2 1.0 16.2 1.0 4/17-4/21 15.2 = 1.6 0.96 =.3

< 0.5

< 5.0

< 1.0 4.6 0.5 4/24-4/28 55.8 3.2

< 1.0 1.7 0.3 14.6 2.4 4.3 0.7 9.6 0.7 5/1-5/5 46.5 : 2.9 1.6 0.4 1.5 i 0.3 13.8

• 2.7 4.4 0.7 8.7 i 0.6 5/8-5/12 32.3 i 2.7

< 1.0

< 0.5

< 5.0 3.3

• 0.9 11.5

• 1.2 5/15-5/19 12.4 1.6

< 1.0

< 0.5

< 5.0 2.0 2 0.6

< 0.5 5/22-5/26 47.6

• 3.0

< 1.0

< 0.5 6.3 1.5

< 1.0 7.2 = 0.6 5/29-6/2 42.4

• 2.8

< 1.0

< 0.5 8.4 i 2.0 3.7 1.0 6.5 0.6 6/5-6/9 24.6 i 2.1

< 1.0

< 0.5 9.5 i 2.9 2.7 i 0.6 5.4 i 0.6 6/12-6/16 49.8 i 3.0

< 1.0

< 0.5

< 5.0 3.1 0.6 6.9 i 0.6 6/19-6/23 61.9 3.6

< 1.0

< 0.5 14.5 2.8 2.9 0.6 6.9

• 0.6 6/26-6/30 31.4 2.4

< 1.0

< 0.5

< 5.0

< 1.0 1.4 0.5 7/3-7/7 25.4 = 2.0

< 1.0

< 0.5

< 5.0 0.8 0.3 3.3 i 0.5 7/10-7/14 30.6 i 2.4

< 1.0

< 0.5 10.9 i 2.9

1. 4 i 0. 5 3.5 = 0.6 7/17-7/21 36.3 i 2.6

< 1.0

< 0.5 12.5 2.9

< 1.0 3.8 0.6 7/24-7/28 11.7 1.7

< 1.0

< 0.5

< 5.0

< 1.0

< 0.5 7/31-8/4 11.5 = 1.8

< 1.0

< 0.5

< 5.0

< 1.0

< 0.5 8/7-8/11 7.3 i 1.7

< 1.0

< 0.5

< 5.0

< 1.0

< 0.5 8/14-8/18 9.2 i 2.2

< 1.0

< 0.5

< 5.0

< 1.0 1.2 0.6 8/21-8/25 26.8 i 2.4

< 1.0

< 0.5

< 5.0

< 1.0 2.6 0.7 8/28-9/1

< 1.0

< 0.5

< 5.0

< 1.0

< 0.5 9/4-9/8 12.9

• 1.7

< 1.0

< 0.5

< 5.0

< 1.0 1.7 0.7 9/11-9/15 13.6 i 1.6

< 1.0

< 0.5

< 5.0

< 1.0 1.4 i 0.6 9/18-9/22 5.9 i 1.5

< 1.0

< 0.5

< 5.0

< 1.0

< 0.5 9/25-9/29 8.5 1.7

< 1.0

< 0.5

< 5.0

< 1.0

< 0.5 Table 2.4 Other Fission Products Detected in Air Samples (fCi/M i1c)

Isotope 4/3 - 4/7 4/10-4/14 4/17 - 4/21 I

6.1 0.7

< 1.0

< 1.0 131 Cs 8.0 0.6 9.6 i 0.7 1.4 = 0.4 137 Ba 7.6 0.8 13.9 i 1.8

< 1.0 1O La 8.3 2.5 11.6 i 3.6

< 1.0 140 3.

MILK Milk is collected from the NCSU Dairy on a monthly basis. Samples are analyzed for Strontium-90 activity according to the procedures in Appendix A.

Milk in also analyzed for Iodine-131 activity as follows:

500 ml of milk is put into a 1000 mi beaker.

20 gm of Dovex 1-X8, 200-400 mesh anion exchange resin is added and the sampic is stirred on a magnetic stirrer for thirty minutes.

The resin is allowed to settle, transferred to a 20 mi vial and counted for gn=ma activity in the well of the 4" x 4" NaI(T1) Crystal for 99,000 sec.

The spectrum is then examined on the ND-100 CRT display and compared to a background spectrum with the use of the overlap feature of the ND-100.

If an Iodine peak were observed, it would be evaluated with the use of the GAUSS Program and the TUCC Computer.

To Gate no Iodine-131 has been detected in the milk from the NCSU Dairy.

Thi.= may be attributed to the fact that the cattle producing this milk are primarily silage fed, and therefore, would not generally ingest substantial

^

quantities of the short lived nuclide Iodine-131 (half-life = 8.041 days).

Tests conducted on spiked samples of milk have shown the Iodine procedure to be approximately 95% efficient and the NaI(T1) Crystal has a 51% efficiency for the 364.5 kev gamma emitted by Iodine-131 in a sample counted in the well of the crystal. 1he intensity (or abundance) of the 364.5 Kev gamma is 82%

giving a 40% total efficiency for this procedure.

Table 3.1 Milk Specific Activity (pCi/1 i l o )

90 131 Date 3

7 4/78 5.19

• 0.61

< 2.0 5/78 4.26 2 0.54

< 2.0 6/78 3.37 0.47

< 2.0 7/78 5.87 0.49

< 2.0 8/78 3.14 0.48

< 2.0 9/78 3.20 0.70

< 2.0 4.

SURFACE WATER Surface water is collected from Rocky Branch Creek at two locations:

ON where the creek flows onto NCSU campus and 0FF - where the creek flows off of NCSU campus.

Samples are collected in five-gallon Nalgene containers.

(These containers hold 19 liters when filled to the top.)

Care is taken when filling the containers to avoid floating debris and bottom sediment.

Surface water is analyzed for gross alpha and beta activity according to the procedures in Appendix B and for gamma activity according to the procedures in Appendix C.

Following gamma analysis, the condensed 18-liter sample is diluted to 500 ml and analyzed for Strentium-90 activity according to procedures in Appendix A.

Specific Activities for surface water samples are reported in Table 4.1.

No unusually high readings of Strontium-90 were noted during this reporting period; hence, the hypothesis of a delay in fallout from atmospheric nuclear tests being washed into Rocky Branch Creek remains unverified at this time.

Table 4.1 Surface Water Specific Activity (pCi/1 i i c )

58 60 O

O Date Location

• Cs Co Co K

Sr Gross Beta April ON

< 0.1

< 0.2 < 0.2 17.98 24.01 0.26

• 0.02 6.01

• 0.49 1978 0FF

< 0.1

< 0.2 < 0.2 8.89 23.97 0.51 0.04 8.08 0.59 May ON

< 0.1

< 0.2 < 0.2 6.13

• 26.31 0.51 0.0, 5.49 i 0.45 1978 0FF 0.68 0.55 < 0.2 < 0.2

< 2.0 0.75

• 0.05 5.90

• 0.47 June ON 1.35

• 0.33 < 0.2 < 0.2

< 2.0 0.21 0.02 3.55 0.36 1978 0FF 1.49

• 0.37 < 0.2 < 0.2 14.97 i 27.85 0.35 0.03 3.67 0.37 July ON

< 0.1

< 0.2 < 0.2

< 2.0 0.37 0.03 3.23 i 0.37 1978 0FF

< 0.1

< 0.2 < 0.2 23.70 22.32 0.29 0.03 6.18 0.50 Aug ON

< 0.1

< 0.2 < 0.2

< 2.0 0.64 0.04 5.40 0.46 1978 0FF 0.10 = 0.52 < 0.2 < 0.2

< 2.0 0.59 0.04 5.78 0.48 Sept ON

< 0.1

< 0.2 < 0.2

< 2.0 0.50 0.04 3.91 0.38 1978 0FF

< 0.1

< 0.2 < 0.2

< 2.0 0.52 0.04 3.86 i 0.38

• 0N - Denotes Rocky Branch Creek as it enters NCSU campus OFF - Denotes Rocky Branch Creek as it leaves NCSU campus 5.

SOIL Soil samples are collected in January and July of each year. Surface samples are taken at four sites on or near campus and deep samples (4.5 feet below surface) are taken outside of the radioactive materials burial ground.

An additional deep sample was taken this reporting period in the vicinity of the West sample for comparison purposes.

The locations of the four surface samples are: North - near Bell Tower; South - between Morrill Drive and Western Blvd.; East - next to Rocky Branch Creek as it flows off of NCSU campus; West - next to Rocky Branch Creek as it flows onto NCSU campus.

Soil samples are screened to remove rocks and vegetation matter, then ashed in a muffle furnace at 520 C for 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />. Approximately 0.1 gram from each sample is transferred to an aluminum planchet and counted for gross alpha and beta activity and approximately 50 grams are transferred to a plastic dish and analyzed on the Ge(Li) Crystal for gamma activity.

Following 100 minute counts each for alpha and beta activity, gross specific activities are calculated as follows:

SA =

{

f C + B +.0025(C - B) where C = Sample counts per 100 min B = Background counts per 100 min U = (Efficiency)(Mass)(222

"")

Efficiency =.278 for a

.380 for 3 This problem is solved on the Wang Calculator with program " Gross a or S i 1 c "

Verification No. 234.

Soil samples to be scanned for gamma activity are weighed in small plastic dishes, placed in the Compton Suppression Well above the Ge(Li) Detector, and counted for 100,000 seconds each. The spectra are transferred to magnetic tape and sent to TUCC for analysis by the MONSTR program on the TUCC Cceputer.

Specific Activity for gn=ma emitters is calculated from the computer print-out for the spectrum and is reported in Table 5.1 in picoCuries per gram.

The gamma energies from nuclides normally found in soil samples do occur in background spectra and are long-lived so they do not r quire decay time correction.

{ ih o

+#

+.0025 (C - B)

SA =

C B

where C = Ys per see from sample spectrum B = Ys per sec from background spectrum p{c

)( n ensity)(Mass)

U = (.037 ur o = Sample err r fr printout C

e = Background error from printout B

This problem is solved on the Wang Calculator with program "Sp Act Y with Ekg" Verification No. 359.

Table 5.1 Soil Specific Activity (pCi/gm i 1 o )

6 Location

• Gross a Cross S Th Ra Cs K

North 4.86d0.98 9.72*2.08 0.707 0.487 0.650 0.408 1.078*0.197

< 0.4 South 4.05do.90 17.31i2.39 0.303*0.466 0.804*0.378 4.007 0.286

< 0.4 1

i 6.48 l.12 34.26*3.15 1

1.530 0.462 1.556do.377 0.872 0.177 34.811 8.561 East West 4.05 0.90 21.10 2.60 1.231do.454 1.105*0.362 0.141*0.161 9.032i8.233 W(4.5')

1.94dO.66 13.63t2.21 OBG(4.5')

3.06*0.84 15.39 2.47 NBG(4.5')

5.20*1.06 28.06*3.01

• Location - Denotes direction from reactor Burial Ground samples are in near proximity to fence NEG denotes New Burial Ground OBG denotes Old Burial Ground (not presently in use) 4.5' denotes depth of sample; others are at surface 6.

VECETATION Edible crops (corn and soy beans) are collected frem the NCSU Farm at harvest time and analyzed for gross alpha and beta activity and specific ga=ma emitters.

Pine needles and grass samples are collected in January and

.Tuly and are also analyzed for gross alpha and beta and specific ga=na activities.

During this reporting period, only one pine needle sample and one grass sample were taken. These were in the vicinity of the South soil sample.

Specific Activities are reported in Tabic 6.1.

Procedures for preparation and analysis of vegetation samples are reported in Appendix D.

Table 6.1 Vegetation Specific Activity (pCi/gm i 1 e )

Sample Gross a Gross 5 Cs K

Pine 0.064 i.014 4.784 0.258 < 0.02 5.17 = 1.73 Grass 0.058 :.021 9.686 0.525 < 0.03 10.70 4.32 7.

REACTOR WASTE TANRS AND SEWAGE Reactor waste tank monitoring has never been considered a part of Environ-mental Radiation Surveillance (ERS); however, gross alpha and beta determina-tions have been carried out by Radiation Survey Technicians prior to release of tank contents into the Raleigh sewage system. The ERS personnel have developed a procedure for the determination of Strontium-90 in vaste tank water and the specific activities determined are reported in Table 7.1 along with the gross alpha and beta activities for the same sa=ples.

Sewage water from the Raleigh treatment plant is being analyzed for gross alpha and beta and Strontium-90 activity as an addition to the ERS program.

These specific activities are reported in Table 7.1 along with the reactor waste tank specific activities.

Procedures for gross alpha and beta analysis of sewage water and Strontium-90 analysis of both sewage water and waste tank water are in Appendices E and F respectively.

Table 7.1 Wasta Tank and Sewage Specific Activity (pCi/1 i 1 c)

Sample Gross a Gross 5 Sr WT #1 June

< 0.5 587.1 i 30.6 1.23 1 0.25 WT #2 June

< 0.5 667.9 = 34.6 1.38 = 0.26 WT #2 July

< 0.5 332.0 i 18.6 0.77

• 0.22 WT #3 July

< 0.5 352.6 1 19.6 0.88 0.23 WT #2 Aug

< 0.5 65.2 = 5.6 0.96 = 0.22 WT #3 Aug

< 0.5

< 5.0 0.45 = 0.21 WT #1 Sept

< 0.5 57.9 = 5.2 1.44 = 0.25 WT #3 Sept

< 0.5 39.4 4.5 2.40 2 0.29 May Sewage

< 0.1 10.45 i 0.88 1.16 = 0.45 July Sewage

< 0.1 10.48 = 1.33 1.73 0.58 Sept Sewage

< 0.1 15.44 1.47 1.69 = 0.65 8.

THERM 0 LUMINESCENT DOSIMETERS (TLDs)

TLD packages of two LiF chips and one CaSO :Dy dosimeter are located at 4

the five air sampling stations on the NCSU campus and at six reacter moni-toring stations. A control package is also kept ist Room 214 David Clark Laboratories away from ionizing radiation sources. Locations of all TLD stations are indicated in Table 8.1.

LiF TLDs are exchanged monthly and read locally for exposure. CaSO :Dy 4

TLDs are also exchanged monthly and sent to Teledyne Isotopes for analysis.

Transit dosimeters accompany those shipped to Teledyne so that exposure accumulated during transit may be subtracted fre exposure received on station.

Abnormally high readings for the locally analyzed dosimeters located en the West Wall of the PULSTAR Reactor Bay for August and September may be attributed to open beamport work conducted during those months. Low readings for corresponding contracted dosimeters are unexplained.

TLD exposure is reported in Table 8.2 as average weekly exposure (mR/wk).

mR/wk = (

)7 D

where E = Exposure Reading for TLD T = Transit Reading (if applicable)

D = Time on Station for TLD (in days) 7 = days in week This problem is solved on the Wang Calculator wt 1 program "TLD Weekly Avg" Verification No. 184.

Table 8.1 Thermoluminescent Dosimeter (TLD) Locations Designation Location Broughton 410 ft. southwest of and 55 ft. below top of Reactor Stack DCL Roof of David Clark Laboratories Library 629 ft. northwest of and 36 ft. above top of Reactor Stack Riddick 325 ft. southeast of and 46 ft. below top of Reactor Stack Withers 270 ft. northeast of and 19 ft. below top of Reactor Stack Control Room 214 David Clark Laboratories R-3 Entrance to NCSUR-3 Reactor Bay from Control Room PULSTAR PULSTAR Reactor Bay, West Wall Equipment Room PULSTAR Equipment Room East of PULSTAR Bay Control Room PULSTAR Control Room Pool Over PULSTAR Reactor Pool Stack Top of PULSTAR Reactor Stack Table 8.2 Thermoluminescent Dosimeter Readings (Average mR/wk based on Co-60 Standard)

Area Monitors

• 4-78 5-78 6-78 7-78 8-78 9-78 Broughton L

2.3 2.6 2.3 1.9 1.9 1.9 Broughton C

2.7 1.3 1.9 X

0.3 2.9 DCL L

1.6 1.9 1.1 1.3 1.3 1.3 DCL C

2.0 1.0 1.1 X

0.5 2.1 Library L

2.6 2.7 2.1 2.2 2.1 2.2 Library C

1.8 1.4 1.7 X

0.8 2.3 Riddick L

2.9 2.7 2.3 2.2 2.2 2.1 Riddick C

2.5 1.6 2.0 X

0.2 3.2 Withers L

1.9 2.3 1.9 1.8 1.6 1.9 Withers C

1.6 1.1 1.7 X

0 2.8 Control L

2.5 2.0 2.5 1.8 1.4 1.8 Control C

2.0 1.3 1.4 X

1.6 1.9 Reactor Monitors R-3 L

5.1 5.4 4.7 4.7 4.2 4.4 R-3 C

3.6 2.2 3.2 X

1.4 4.1 PULSTAR L 26.4 35.0 86.3 129.0 299.1 150.2 PULSTAR C 13.7 12.7 14.1 X

21.3 15.4 Equipment Room L 25.4 29.1 22.0 21.0 25.6 23.1 Equipment Room C 19.4 13.8 17.2 X

18.8 17.5 Control Room L

6.4 7.3 9.4 10.4 23.5 13.0 Control Room C

4.4 3.5 3.9 X

3.5 4.7 Pool L 36.2 41.0 38.4 42.5 71.9 51.8 Pool C 26.2 22.6 24.3 X

28.7 26.3 Stack L

3.8 3.0 2.1 1.8 2.6 2.6 Stack C

2.0 1.3 1.5 X

0.7 2.5

• L Denotes Locally Evaluated LiF Dosimeters

• C Denotes CaSO :Dy Dosimeters Contracted to Teledyne Isotopes for analysis 4

X Teledyne reports that Contracted dosimeter readings for July were lost during a company relocation APPENDIX A Sr PROCEDURE FOR MILK AND WATER Phase 1 1.

Put 500 m1 milk into 1000 mi beaker, or dilute water sample to 500 m1 in 1000 m1 beaker.

2.

Add 30 gm Dawex 50W-X8 200-400 mesh resin and stir for one (1) minute on magnetic stfrrer.

3.

Adjust pH to 6.0 with pH Meter using 6 M NaOH while stirring. Continue stirring for 30 minutes after pH adjustment. (D0 NOT ADJUST pH OF WATER SAMPLES.)

4.

Allow resin to settle., then aspirate milk or water from above resin and discard.

5.

Add 200 ml distilled water (washing beaker sides) and stir.

6.

Allow resin to settle again; then aspirate milk-water from above resin and discard. Repeat washing if necessary to remove milk solid particles.

7.

Add 200 ml 8N HNO an at r n magnet c stirrer for 30 minutes.

3 8.

Filter resin-acid mixture through Whatman-42 (or eqcivalent) filter paper in Buchner funnel, 9.

Wash heaker with 50 ml 8N HNO and continue filtering. Repeat washing two 3

more times allowing each wash to filter completely. Discard resin.

Save filtrate.

10.

Add the 350 mi solution to a 500 m1 beaker containing several glass beads and evaporate to dryness.

11.

Add 50 ml 30% H 0 and evaporate to dryness.

22 12.

Add 20 ml 8N HNO and evaporate to dryness.

3 13.

Add 20 ml 30% H 0 and evaporate to dryness.

22 14.

Add 10 ml 0.08 N hcl and warm.

15.

Add to 125 mi separatory funnel containing 20 ml 20% HDERP.

16.

Rinse beaker with 5 ml 0.081[ hcl and add to separatory funnel.

17.

Repeat Step 16 and shake for two (2) minutes.

18.

Allow phases to separate and drain off bottom aqueous layer into clean 100 mi beaker.

19.

Add 20 ml of fresh 20% HDEHP to second clean separatory funnel.

20.

Add contents of beaker to second separatory funnel. Shake for two (2) minutes and allow to settle.

21.

Drain off bottom aqueous layer into 20 mi vial for storage. Record time and date as T.7 90Sr Procedure for Milk and Water, Continued Phase II (after at least 14-day ingrowth period) 1.

Pour sample into 125 m1 separatory funnel containing 20 ml 207. HDEHP.

2.

Rinse vial with one or two ml 0.08N hcl and add to separatory funnel.

Shake for two (2) minutes and allow to settle.

3.

Drain off bottom aqueous phase into its 20 mi vial. Record time and date as T '

2 4.

Add 20 ml 0.08N hcl and shake for two (2) minutes. Drain off bottom aqueous phase and discard.

5.

Add 20 ml 8,N HNO and shake for two (2) minutes, kain o H bottom aqueous 3

phase into clean 100 mi beaker.

6.

Repeat Step 5. (Add to same beaker.)

7.

Evaporate contents of beaker to a few ml.

8.

Transfer solution to flamed and cooled 2" planchet.

9.

Wash beaker with a few ml 8_N HNO and add to planchet. Continue washing 3

until beaker is clean.

10.

Evaporate solution in planchet to dryness under infrcred lamp.

11.

Count planchet in low background beta counter for 100 minutes and record midpoint of counting time as T

• 3 Milk samples are normally processed in pairs of spiked and unspiked one-half liter samples from each collection. Yttrium-90 ingrowth which occurs between T and T becomes important only when T

~T is cubstantially dif-2 2

1 ferent between spiked and unspiked samples. Percent of ingrowth

/64 h

(

) may be fcund by solving the equation

=1-2 0

3 Sr s

This equation is solved en the Wang Calculator with program " Y Ingrowth" owf Verification No. 207.

If is ess than.M or greater ed than 1.01, multiply this fraction by the actual spike added for use in 90 calculating Sr Specific Activity.

Specific Activity = 1 c (PicoCuries per liter) is calculated as follows:

S2

-T/64 SA = C - B C' -c

%1 where C = Counts per 100 min (unspiked sample)

C' = Counts per 100 min (spiked sample)

B = Counts per 100 min (Background)

Sp = Quantity of Sr spike in picoCuries (corrected for ingrowth if necessary)

~

)unspk (in hours) 3 2)Spk sT3 2

T = (T

~

Sr Procedure for Milk and Water, Continued

~b

~

B/C' - C) + C(C ' - B) 2 + C' (C - B)2 c=

(C' - C)4 This problem (Specific Activity with Standard Deviation) is solved on the Wang Calculator with program " OSr SA Milk" Verification No. 609.

Specific Activity for water is determined as follows:

2 C + B +.0025(C - B)2

{

SA =

where C = Counts per 100 min (sample)

B = Counts per 100 min (background) 3 3 (in hours)

T=T

-T U = (18 liters)(222 100 min ) (E)(I) d E =.265 = Total efficiency for water procedure I = Ingrowth percentage as explained earlier

=.974 after 14 days;.980 after 15 days, etc.

therefore,1031 < U < 1059 (depending on ingrowth tim).

Specific Activity for water is solved on the Wang Calculator with program "Sp.

90 Act, with Decay Sr" Verification No. 397.

APPENDIX B GROSS ALPHA AND BETA DETERMINATION IN WATFR 1.

Transfer one (1) liter of water to a 1000 mi cr 1500 m1 beaker and evaporate to approximately 50 ml on hot plate in hood.

2.

Transfer sample to 100 m1 beaker using distilled water and rubber policeman as necessary to insure complete transfer. (See Note.)

3.

Evaporate sample to less than 10 ml.

4.

Transfer sample to flamed and cooled 2" stainless steel planchet using distilled water and rubber policeman as necessary to insure complete transfer. (See Note.)

5.

Evaporate sample to dryness under heat lamp.

6.

Count sample for alpha and beta activity for 100 minutes each in low background alpha and beta counter.

Note: 8N ENO may be used if necessary to insure quantitative transfer of 3

sample.

Calculations:

Specific Activity (SA) pCi/1.

{ i f C + B +.0025(C - B)

SA =

where C = Sample counts per 100 min B = Background counts per 100 min U = (222)(Volume)(Efficiency)

= (222 disintegrations /100 min /pci)(1 liter)(E)

E =.287 for beta,.210 for alpha U = 15.93 for beta, 11.655 for alpha This problem is solved on the Wang Calculator with program " Gross a or a i 1 c "

Verification No. 234.

APPENDIX C GAMMA ISOTOPIC ANALYSIS OF SURFACE WATER 1.

Transfer approximately three (3) liters of 18-liter water sample into five liter boiling flask and boil at reduced pressure. (.7 atmosphere vacuun is maintained in evaporation system to reduce boiling te=perature and decrease possibility of volatilizing dissolved solids.)

2.

As volume in boiling flask is decreased, periodically add water from 18-liter sample and continue boiling until entire sample has been reduced to approximately 200 ml.

(As sa=ple approaches final volume, reduce flame to prevent evaporation to dryness and reduce possibility of breaking flask.)

3.

Transfer sample to 400 mi beaker rinsing flask several times with distilled water to insure quantitative transfer.

4.

Evaporate sample en hot plate in hood to approximately 25 ml.

5.

Transfer sample to 50 ml covered plastic dish rinsing beaker with distilled water as necessary to insure complete transfer.

6.

Place dish containing sample in Compton Suppression Well of GeLi Detector system and count gamma activity for 100,000 seconds.

Analyze gamma spectra for Specific Activity using MONSTR Program on the TUCC Computer.

Specific Activity for gamma emitters is calculated in picoCuries per liter as follows:

^"

. 025(C - B)

.03 IV C

B IV(.03 sec )

pCi where C = Y/sec from IBM Printout for sample B = Y/sec from IEM Printout for background Sample error converted from Printout c =

C CB = Background error converted from Printout I = Intensity (or abundance) of gn=ma V = Volume of sample = 18 liters This prob 1cm is solved on the WanF Calculator with program "Sp Act Y with Ekg" Verification No. 359.

If peak does not appear in Bkg Spectrum, O may be entered for B and c

• B APPENDIX D PREPARATION AND ANALYSIS OF VEGETATION SAMPLES 1.

Weigh out 100 gn of sample in drying dish and heat in drying oven for one day at 100 C.

2.

Weigh and record weight of ceramic crucible, then transfer sample to crucible for ashing.

Note: Grass and Pine Needle samples should be pulverized in blender before ashing to reduce volume so they will fit in crucible.

3.

Ash sample in muffle furnace for 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> at 520 C.

4.

Weigh crucible with ashed sample in it to determine reduction factor (R)

R=

net wt after ashing 5.

Weigh approximately 100 mg of sample in 2" aluminum planchet and count in Widebeta II for alpha and beta activity for 100 minutes each.

Calculations for gross alpha or beta Specific Activity (SA)

} i f C + B +.0025(C - B)

SA =

where: C = Sample counts per 100 min B = Background counts per 100 min pf*

")

U '= (Ef ficiency)(Mass)(R)(

This pr,blem is scived on the Wang Calculator with progre.m " Gross a or S i 1 o" Verification No. 234.

The remainder of the ached sample is transferred to a plastic dish and analyzed for gamma activity in the Compton Suppression Well of the Ge(Li)

Detector for 100,000 seconds. The spectrum is thea put on magnetic tape and sent to TUCC for analysis on the TUCC Computer with the MONSTR program.

Specific gamma activity is determined from the computer printout with the same calculations and Wang Program as is used for soil samples using mass of sample times reduction factor in place of mass.

APPENDIX E ANALYSIS OF SEWAGE WATER FOR GROSS ALPHA AND BETA ACTIVITY 1.

Place 250 mi sewage water in 400 mi beaker and evaporate in hood to a few ml.

2.

Transfer evaporated sewage water to 2" stainless steel planchet using 8N HNO to wash beaker and insure all of sample is transferred.

3 3.

Evaporate sewage water to dryness on planchet under infrared lamp.

4.

Count evaporated sample for gross alpha and beta activity in Widebeta II for 100 minutes each.

Specific Activity (SA) calculation:

{ i f C + B +.0025 (C - B)

SA =

where C = Sample counts /100 min B = Background counts /100 min U = 222 VE = 222(.25)(Efficiency)

Efficiency =.278 for beta,.210 for alpha in this configuration U = 15.93 for beta, 11.655 for alpha This problem is solved on the Wang Calculator with progres " Gross a or 5 i 1 o "

Verification No. 234.

APPENDIX F STRONTIUM-90 ANALYSIS OF WASTE TANK AND SEWAGE WATER 1.

Dissolve sample by placing planchet in approximately 200 ml of 8N HNO 3

in 250 ml or 400 m1 beaker.

2.

Heat to boiling on hot plate in hood and remove planchet with hemostat, washing planchet and hemostat jaws with 8N HNO3 89"****

3.

Add a few glass beads to beaker to prevent bumping and evaporate sample to dryness.

4.

Add 50 ml 307. H 0 and (vaporate to dryness.

22 5.

Add 20 ml 8N HNO and evaporate to dryness.

3 6.

Add 20 ml 30% H 0 and evsporate to dryness.

22 7.

Add 10 ml 0.08N hcl and warm solution to insure sample is dissolved.

8.

Transfer solution to 125 mi separatory funnel containing 20 ml 20% HDEHP.

9.

Shake sample for two minutes and allow phases to separate.

10.

Drain off bottom aqueous phase into 20 ml vial. Note:

Ingrowth period for Yttrium-90 is not required in this procedure since strontium and yttrium have not been separated until this point and are considered to be in equilibrium. The aqueous phase is saved only as e precaution and tests have shown that subsequent extraction of Yttrium-90 ef ter an in-growth period (See Milk Strontium-90 Procedure) produces the same results; however, efficiency is lower if ingrowth and extraction is used rather than direct extraction.

(Total efficiency =.265 with resin and ingrowth.

Total efficiency =.332 with direct extraction.)

11.

Add 20 ml 0.08N hcl and shake for two minutes.

12.

Allow phases to separate, drain off bottom aqueous phase and discard.

13.

Add 20 ml 8N HNO and shake for two minutes.

3 14.

Allow phases to separate and drain off bottom aqueous phase into 100 m1 beaker.

15.

Repeat Steps 13 and 14.

(Add to same beaker.)

16.

Evaporate acid solution to a few ml on hotplate in fume hood.

17.

Transfer sample to flamed and cooled 2" stainless steel planchet using 8N HNO r m squeeze bottle to wash beaker and insure complete transfer.

3 Strontium-90 Analysis of Waste Tank and Sewage Water, Continued 18.

Evaporate sample to dryness under infrared lamp.

19.

Count sample for Yttrium-90' beta activity for 100 minutes in Widebeta II.

Sr Specific Activity (SA) calculations:

T/T T/T y

'/ C + B +.0025 (C - B)2 SA = C - B 2 U

U where C = Sample cot nts per 100 minutes B = Background counts per 100 minutes T = Decay time from extraction to midpoint of count T = lialf-life of Yttrium-90 = 64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br />

P*

U = (222

)(V lume)(Efficiency)

C e

U = (222)(.25)(.332) = 18.426 for 250 mi sample U = (222)(1)(.332) = 73.704 for one liter sample This problem is solved on the Wang Calculator with program "Sp. Act with Decay OSr" Verification No. 397.

s