ML20236D210

Doses During Analysis of Radioactively Contaminated Waste Oil/Solvent by Lab & Technical Svcs

ML20236D210
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	05/05/1987
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20236D193	List: ML20236D190 ML20236D201 ML20236D210
References
EA-TAH-87-04, EA-TAH-87-4, NUDOCS 8710280072
Download: ML20236D210 (14)

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1 APPENDIX'NO EA-TAH-87-04

" Doses During Analysis of Radioactively Contaminated.

Waste Oil / Solvent by Lab and Technical Services" i

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Performed By Date N;50-8"7 DateI!5~//1 Technical Review By-!

8710200072BQ$3 g33 PDR ADOCK PDR P

MIO387-0100C-BX01

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1 1A>SES DURING ANALYSIS OF RADI0 ACTIVELY CONTAMINATED WASTE OIL / SOLVENT BY LAB AND TECHNICAL SERVICES Problem Statement and Use of Resultz Assuming samples of radioactively contaminated waste oil, solvent or a mixture of the two are sent to the Lab and Technical Services group for analyses, what dose to lab personnel is expected?

Input Data Description of analyses performed including equipment used, sample volume needed, estimated time samples handled by leb personnel, and total time to perform each analysis are listed in Attachment One (from D. Snedeker of Lab and Field Technical Services).

Major radioisotopes present in the contaminated oil / solvent are Mn 54, Co 60, FE 59, Cs 137, Cs 134, Ag 110m, and Nb 95.

Average energies and half lives l

of each isotope are given in Table Two. Other data from EA-TAH-87-02 are given with the calculations as appropriate.

Approximately 25 barrels (55 gallon drums) are presently on site. Three to five barrels are collected each year.

References I

EA-TAH-87-02 " Maximum Allowable Radioisotope Concentrations in Waste Oil /

I Solvent" performed by TAHancock.

I Regulatory Guide, 1.109, " Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance f

with 10CFR Part 50, Appendix I", October 1977.

Rockwell, Theodore III, Editor; Reactor Shielding Design Manual; D. VanNostrand l

Company, Inc; Princeton, New Jersey; First Edition.

U.S. Department of Health, Education and Welfare; " Radiological Health

'j Handbook;" U.S. Department of Health, Education and Welfare; Rockville, Maryland; January 1970.

Assumptions and Methodology 1

Assuming five barrels of waste oil / solvent having 1 pCi/ml concentrations of each radioisotope are produced each year, the doses to lab personnel can be estimated using methods in EA-TAH-87-02.

The most conservative dose to the lab personnel assumes ingestion of the samples of oil / solvent. More realistic j

doses result from the handling of the samples. These doses will be estimated using the method presented in Rockwell, assuming cylindrical source vnlumes.

The dose due to inhalation of radionuclides during the flashpoint analysis will be estimated using the calculations in EA-TAH-87-02 and the methodology

- of Reg Guide 1.109.

MIO387-0100C-BX01

EA-TAR-47-04 Pas 2 2 of 10 Calculations 1

A.

Dose due to Insestion of Radioactively Contaminated Waste Oil / Solvent Samples.

Assume the maximally exposed lab personnel ingest the entire one quart sample of waste oil / solvent.

The annual dose to the individual can be calculated as:

R = Raipj U/Uap Where

'Raipj = annual dose to organ j of an individual of age group a from nuclide i via pathway p in [mres/ year]. The maximal values as calculated in EA-TAH-87-02 are used.

Uap

= intake rate (usage) associated with pathway p in

[l/ year]. Uap = 3.81/ year as calculated in EA-TAH-87-02.

i U

= intake rate for the given pathway U =(1 quart sample / barrel)(5 barrels / year)(1 gal /4 quarts)(3.785 1/ gal)=4.7 1/yr D.

Dose Due to Handling Samples 1.

Wholebody Doses e

R.

Wholebody doses are estimated using methods given in Rockwell l

e p

= _B Sv R /J(6, Q g]

h[.R/hr]= P*he 2 AqA+ a')

i Where B = symbolic buildup factor through air. Shielding by the glass of

{

the container is neglected.

B,g, = 1

~

~

S = source strength [ca sec ] = 3.70E+04 dis /cm sec 3

Y (assuming 1 pCi/ml) from EA-TAH-87-02

-F (0,b ) = ge metry c rrecti n fartor 2

$1R/hr = flux to produce a dose rate of 1 R/hr a = distance from the source to the lab personnel = arms length ~3ft = 91.4 cm Z = effective self absorption thickness of source j

b; = b

+pZ where b =Ipt g

2 3

gg MIO387-0100C-BX01

EA-TAH-87 Pcao 3 cf 10-R = radius of source volume = 4 cm (approx radius of a beaker) i or

= 0.6 cm (approx radius'of a 40 m1 test tube)

H = height of source volume - different for each analysis.

Parameters and resultant doses are given in Table Two.

Assuming only one analysis is in progress at a time, the lab personnel will be exposed to the remainder of the 1 quart sample for the duration of. the analyses (t = 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br />)

Let R, = 2" = 5.1 cm 3

3 V=1 quart (1 gal /4 quarts)(3.785 1/ gal)(1000ml/1)(1cm /1ml)=946.25cm tH=11.6cm a = 6 ft = 183cm a/R,-= 183/5.1 = 36 >10 8 = 1.E' 2.

Dose to' hand while handling sample Assume the lab personnel holds the quart sample for the ent. ire 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br /> of the~ analyses. The dose to the hand can be calculated using the equation given below. Doses are recorded in Table Four.

i O[R/hr3

• B*% R*Fre,Q i

a 8.

2 %jy (4.+0 l

R,='5,Icm o.: o e a fo*

l

%: 3.7 E + 0 / c4he~'

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C.

Dose Due to Inhalation of Sample During Flashpoint Analysis l

Assume the total effluents from the oil is inhaled by the maximally exposed individual. Refering to EA-TAH-87-02 for assumptions and methodology

.Ra=75ml/ sample (1 sample / barrel)(5 barrel / year)(Im /10s l)(1670m eff/m oil) i 3

3 3

a 3

R, = 0.63m /yr the annual dose is calculated as D = R, X DFA parameters are defined and values are given in EA-TAH-87-02.

MIO387-0100C-BX01

EA-TAH-87-04' Page 4 of 10 1.

Dose to Lab Personnel la b ' Y l.4 C

16 7

• 5.91 E to 8 2.

Dose to General Public Assume the effluents are release from an elevated point (ie, fron'the j

ftam hood in the lab). For an individual 1/2 mile from the lab...

X " 3.17E+04 Q1 (X/Q) where Qg = release rate

= 1 pCi/m1(75ml/ sample)(5 samples /yr)(1Ci/1E+6pC1)=3.75E-04Ci/yr 3 (see EA-TAH-87-02)

(X/Q] = dispersion = 1.40E-05 sec/m i

so 3

X = 1.66E-04 pCi/m j

i D.

Doses Due to Maximum Allowable Concentrations of Isotopes in Oil / Solvent.

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Using the maximum allowable concentrations determined in EA-TAH-87-02, the doses to the lab personnel can be calculated as D,,,= DpCi/ml (C,,,/(1pCi/ml))

l Adjustments made to reflect 5 samples per year and to provide D,,, in (arem/yr].

Maximum Doses from each isotope are recorded in Table Seven.

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EA-TAH-87-04 Page 5 of 10 Summary Of Results Annual. doses the Lab and Technical Services group lab personnel are expected to be subjected to during analysis of radioactively contaminated waste oil / solvent have been estimated assuming five one quart samples containing maximum allowable radioisotope concentrations are analyzed each year. Total doses are given below.

TABLE EIGHT:

DOSES RESULTING FROM ANALYSIS OF FIVE 1-QUART SAMPLES OF WASTE OIL / SOLVENT Isotopes Parameter Mn 54 Co 60 Fe 59 Cs137 Cs134 Ag110m Nb 95 Max Conc [pCi/ml]

2E-04 2E-04 2E-04 2E-05 2E-05 2E-04 2E-04 Dose to Lab Personnel during 7.7E-02 3.5E-01 7.8E-02 4.7E-03 5.4E-03 2.8E-01 3.7E-02 analysestarec/yr Dose to General Public'during Flashpoint anal-ysis [ mrem /yr) 2.1E-14 9.7E-14 2.2E-14 1.3E-15 1.5E-15 7.7E-14 1.0E-14 The total dose to Lab personnel is estimated to be approximately 0.87 mrem / year.

Dose to the general public is negligible.

The lab disposes of the waste oil / solvent as hazardous waste when analyses are complete. Tne equipment used is thoroughly cleaned after each analysis which will prevent the buildup of activity in any instrument.

MIO387 0100C-BX01

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l TABLE ONE:

DOSE DUE TO INGESTION OF FIVE QUARTS PER YEAR OF 1 pCi/ml OIL / SOLVENT l

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Isotopes Mn 54 Co 60 Fe 59 Cs137 Cs134 Ag110m Nb 95 IL AG IL IL IL AG AG i

Raipj [ mrem /yr]

7.6E+04 1.5E+05 2.0E+05-2.3+06 2.7E+06 2.3E+05 8.0E+04 i

IL-AG IL IL IL AG AG R [ mrem / year]

9.4E+04 1.9E+05 2.5E+05 2.8E+06 3.3E+06 2.8E+05 9.9E+04

.1 I = Infant A = Adult L = Liver G = GI LLI i

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TABLE TWO WHOLE9007 DOSES RESULTINO FROM RANDI*XC OF WASTE OIL /SQLVFNT SAMPIAS I

ISOTOPES PMW fFe59 Mn 54 Co 60 Cs137 Cs134 Ag110e Nb 95 Ey (MeV)

.835

.1.25 1.15 0.662 0.703 0.842 0.765 th (daysl 312.5 1920 44.6 11012 752 253.0 35.1

$1R/br (co-2,,,-1/R/hr)

6. 4E +05' 4.6E+05 4.9E+05 7.88+05 7.4E+05 6.4E+05 6.9t+05 poil (ca'I]I 0.066 0.055 0.058 0.074 0.071 0.066

.07 poil Ro 0.04 0.03 0.03 0.04 0.04 0.04 0.04 I

poil 2 0

0.

0 0

0 0

0 2 (ca) 0 0

0 0

0 0

0 bg = pair t 8.1E 03 6.9E 03 7.1E-03 9.1E-04 8.9E-03 8.1E 03 8.5E-03 be 8.1E-03 6.9E 03 7.1E-03 9.18-04 8.9E-03 8.1E-03 8.5E 03 F(8,bs) 1.8E 02.

1.8E-02 1.8E-02 1.8E 02 1.8E-02 1.8E-02 1.8E-02 D(R/hr!

2.0F 06 2.9E-06 2.7E 05 1.7E 06 1.8E-06 2.0E-06 1.9E 06 D[h]

1.0E-06 1.5E-06 1.4E-06 8.5E-07 9.0E-07 1.0E 06 8.9E-07 pair (ca"Il 8.9E 05 7.5E 05 7.8E-05 1.0E-05 9.7E-05 8.9E-05 9.3E-05 Y

N' oil same as above l

2 0

0 0

0 0

0 0

bgabne as above s

.. F (8,bs) as above D (R) 1.0E-06 1.5E 06 1.4E 06 8.5E-07 9.0E-07 1.0E-06 8.9E-07 l

f p,gg Ro 0.26 0.22 0.23 0.30 0.28 0.26 0.28 p,gg 2

.13

.10

.11

.16

.15

.13

.15 i

2 2.0 1.8 1.9 2.2 2.1 2.0 2.1 5:

8.18-03 6.98-03 7.1E-03 9.1E-04 8.9E-03 8.1E-03 0.5E 03 p:

.138

.107

.117

.161

.159

.138

.159 F (8,bs) 1.5E 02 1.6E-02 1.6E-02 1.5E-02 1.5E-02 1.5E-02 1.5E-02 l

D [R/hrl 7.4E-05 1.1E-04 1.0E-04 6.1E 05 6.4E-05 7.4E-05 6.9E-05 D [R) 7.4E-05 1.1E 04 1.08 04 6.1E-05 6.4E-05 7.4E-05 6.9E 05

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p,gg same as PCB p oil 2 and 2 0

0 0

0 0

0 0

i b s bas as PCB i

F (0,bs) as PCB D[R/brl as PCB 2.0E 06 2.9E-06 2.7E-06 1.7E-06 1.8E-06 2.0E-06 1.9E-06 DlR]

7.0E 06 1.0E 05 9.5E 06 6.0E-06 6.3E-06 7.0E-06 6.7E-06 Total Dose due

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to direct handling I

(Real assuming 8.3E-05 1.2E 04 1.1E-04 6.9E-05 7.2E-05 8.3E-05 7.7E-05 1 pC1/mi conc i

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I TABLE THREE: WHOLEBODY DOSE'DUE TO REMAINDER OF QUART SAMPLE SAMPLE OF WASTF OIL / SOLVENT OPES PARAMETER l

Mn 54-Co 60 Fe 59 Cs137 Cs134 Ag110m Nb 95 poil Ro 0.34 0.28 0.30 0.38-

.36

.34

.36-poil Z

.16

.14

.15

.18

.17

.16

. 1.'

Z [ca]

2.~ 4 -

2.5 2.6 2.4 2.4 2.4.

2.4

.016

.014

.014

.002

.018

.016

.017 bi F(0,bt + Z) 2 6E-02 2.6E-02 2.6E-02 2.6E-02 2.6E-02 2.6E-02 2.6E-02 D [ rem]

1.1E-04 1.5E-04 1.4E-04 8.7E-05L 9.1E-05 1.0E-04 9.8E-05 1

TABLE FOUR: DOSE DUE TO HOLDING ONE QUART SAMPLE FOR 43 HOURS I*

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• Parameters Mn 54 Co 60 Fe 59 Cs137 Cs134-Ag110m-Nb 95 R.

.34

.28

.30

. 38-

.36

.34

.36 pdl

.16

.14

.15

.18

.17

.16

.17 Ziba]Z

~ 2.4-2.4 2.4 2.4 p

2.4 2.5 2.5 bg = pt = 0 0

0 0

0 0

0 0

b2 = poil Z

.16

.14

.15

.18

.17

.16

.17 F(0,b )

1.14 1.10 1.12 1.18 1.16 1.14 1.16 2

D[ rem /br]

3.6E-01_ 4.6E-01 4.2E-01 3.0E-01 3.1E-01 3.6E-01 3.4E-01 D[ rem]*

15.5 19.8 18.1 12.9 13.3 15.5 14.6 l

• Assuming a radioisotope concentration of 1 pCi/ul.

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TABLE FIVE: DOSE TO LAB PERSONNEL DUE TO INHALATION i

i 18 t Pes Parameters Mn 54 Co 60 Fe 59 Cs137 Cs134 Ag110m Nb 95 DFA.[ mrem /pCi]

7.14E-04 3.22E-03 7.25E-04 4.37E-04 5.02E-04 2.62E-03 3.42E-04 D [ mrem /yr]

269.4 1215.1 273.6 164.9 189.4 988.7 129.1 D* [ rem]

7.7E-02 3.5E-02 7.8E-02 4.7E-02 5.4E-02 2.8E-01 3.7E-02 t

• Actual exposure time = 1/2 hour per sample # 2 1/2 hour = 2.85E-04 years.

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TABLE SIX: DOSE TO GENERAL PUBLIC DUE TO INHALATION j

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Isotopas Mn 54 Co 60 Fe 59 Cs137 Cs134 Ag110m Nb 95 D [ rem /yr) 7.5E-11 3.4E-10 7.6E-11 4.6E-11 5.2E-11 2.7E-10 3.6E-11 l

D* [ rem]

2.1E-14 9.7E-14 2.2E-14 1.3E-14 1.5E-14 7.7E-14 1.0E-14 1

• Actual exposure time = 1/2 hour per sample.

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EA-TAH-87-04' Pega 10 cf to.

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l TABLE SEVEN: DOSES DUE TO ANALYSIS OF FIVE SAMPLES OF WASTE OIL / SOLVENT PER YEAR j

1 I8 t Pes Parameter Mn 54 Co 60 Fe 59 Cs137 Cs134 Ag110m

.Nb 95 Max Conc [pCi/ml]

2E-04 2E-04 2E-04 2E-05 2E-05 2E-04 2E-04 Ingestion of 5 quarts waste oil /

solvent per yr 1.9E+01 3.8E+01 5.0E+01 5.6E+01 6.6E+01 5.6E+01 2.0E+01 PCB Analysis 1.0E-06 1.5E-06 1.4E-06.

8.5E-08 9.0E-08 1.0E-06 8.9E-07

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Total Metals.

1.0E-06 1.5E-06 1.4E-06 8.5E-08 9.0E-08 1.0E-06 8.9E-07 EP Toxicity Metals 7.4E-05 1.1E-04 1.0E-04 6.1E-06 6.4E-06 7.4E-05 6.9E-05 Total Halogens 7.0E-06 1.0E-05 9.5E-06 6.0E-07 6.3E-07 7.0E-06 6.7E-06 Storage of T

Remainder of 8

Quart Sample 1.1E-04 1.5E-04 1.4E-04 8.7E-06 9.1E-06 1.0E-04 9.8E-05 J!,

Flashpoint.

7.7E-02 3.5E-01 7.8E-02 4.7E-03 5.4E-03 2.8E-01 3.7E-02

{

Total 7.7E-02 3.5E-01 7.8E-02 4.7E-03 5.4E-03 2.8E-01 3.7E-02 8

Holding Quart Sample 43 Hrs, a

5 Times / year j

Dose to hands 1.6E+01 2.0E+01 1.8E+01 1.3E+00 1.3E+00 1.6E+01 1.5E+01 Dose to Generii Public Due to l

Flashpoint Test 2.1E-14 9.7E-14

2. 2E -14 1.3E-15 1.5E-15 7.7E-14 1.0E-14

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The probability that any individual would drink the oil is very slim as is the probability that any individual would hold the quart samples for 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br /> at a time. These doses are calculated as items of interest only.

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l ATTACHMENT ONE DESCRIPTION OF WASTE OIL / SOLVENT ANALYSES 3 pages i

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MIO387-0100C-BX01 l

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s-To GLEalterborn,1-258 rno.

TAEancock, BIG ROCK POIFT p New Wa FINt0ARY 25,1987 messmrssammuuss heaect WASTE CIL AEALYSIS PROCEDURES imenm coan<seonoe=ca I

CC DCC E/A TAE 87-02

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In reference to my telephone conversation on February 13 during which I talked with Debra Phelps:

I am in the process of preparing a request to the Nuclear Regulatory Commission to allow Big Rock Point to dispose of slightly radioactively contaminated vaste oil. solvent or mixture in the same manner as non-radioactively contami-nated vaste o,il/ solvent..To provide a complete description of the handling of the vaste oil / solvent, I must includ,e a desciption of the vaste. oil. solvent or mi.xture analyses performed by your lab.

Please provide,a description of the analyses performed including the following information:

1) Eief description of equipment used

2) Volumes o,f sample used in each analysis

3) Approximate amount of time the ssmple is handled by the lab technician k) Approximate amount of time, to complete each analysis

5) 71nal disposal of the sample Your cooperation is greatly appreciated.

If you have any questions please call me at ext. 18b.'

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