ML20137D178
| ML20137D178 | |
| Person / Time | |
|---|---|
| Site: | Dow Chemical Company |
| Issue date: | 07/24/1985 |
| From: | Felton J NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Condit R, Kohn S GOVERNMENT ACCOUNTABILITY PROJECT |
| Shared Package | |
| ML20137D185 | List: |
| References | |
| FOIA-85-256, FOIA-85-258, FOIA-85-259, FOIA-85-261 NUDOCS 8508220414 | |
| Download: ML20137D178 (5) | |
Text
1
' 1 b UNITED STATES
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.8' n NUCLEAR REGULATORY COMMISSION (
WASHINGTON, D. C. 20555 -
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%""** / JUL 2 41985 l Steve Kohn, Esquire Mr. Richard Condit Government Accountability Project IN RESPONSE REFER T0:
1555 Connecticut Avenue, NW, Suite 202 F01A-85-256, F01A-85-258, Washington, DC 20036 F01A-85-259, F01A-85-261
Dear Messrs. Kohn and Condit:
This is in further response to your letters of April 9,1985, in which you requested, pursuant to the Freedom of Information Act (F0IA), various categories of documents relating to Dow Chemical Company of Midland, Michigan.
The remaining documents subject to F01A-85-261, concerning compliance with various parts of the Code of Federal Regulations, are listed in the enclosed Appendices L, M, and N. With the exception of those portions identified in the following pa'ragraphs, these documents will be added to the folders in your name, under the F0IA numbers listed above, located in NRC's Public Document Room.
Appendix L identifies a document which is being released in its' entirety.
Portions of the documents identified in Appendix M contain information which identifies procedures for safeguarding licensed special nuclear material at a licensed facility or plant. This information is considered commercial or financial (proprietary) information pursuant to 10 CFR 2.790(d) and is being withheld from public disclosure pursuant to Exemption (4) of the F0IA (5 U.S.C. 552(b)(4)) and 10 CFR 9.5(a)(4) of the Commission's regulations.
The document identified in Appendix N is a two-page memorandum containing advice, opinions, and recommendations of the NRC staff regarding the draft report which is identified on Appendix L. It is being withheld from disclosure pursuant to Exemption (5) of the F0IA (5 U.S.C. 552(b)(5))publicand 10 CFR 9.5(a)(5).
Pursuant to 10 CFR 9.9 of the NRC's regulations, it has been determined that the infomation withheld is exempt from production or disclosure, and that its production or disclosure is contrary to the public interest. The persons responsible for the denial of the information are the undersigned and Mr.
James G. Keppler, Administrator of NRC's Region III.
8508220414 850724 PDR FOIA KOHN85-256 PDR
? -
This denial may be appealed to the NRC's Executive Director for Operations within 30 days from the receipt of this letter. As provided in 10 CFR 9.11, any such appeal must be in writing, addressed to the Executive Director for Operations, U.S. Nuclear Regulatory Comission, Washington, DC 20555, and should clearly state on the envelope and in the letter that it is an " Appeal from an-Initial F0IA Decision."
This completes action on F0IA request 85-261.
Sincerely,
. M. Felton, Director Division of Rules and Records Office of Administration
Enclosures:
As stated I
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Re: F01A-85-256,85-258, 85-259 and 85-261 APPENDIX L Additional Released Document, Re: F01A-85-261
- 1. 03/06/85 Letter to'Schumacher from J. D. Berger, enclosing Draft Report on the " Radiological Survey of the Fomer Dow Chemical Corporation Site, Bay City, Michigan" (56 pages) f i
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Re: F01A-85-256,85-258, 85-259 and 85-261 APPENDIX M Document of Which Portions Are Withheld Under Exemption 4 of the FOIA
- 1. 03/29/76 Letter to DeLine from Hind, re: Inspection 3/3-4/76 (11 pages)
- 2. 01/02/79 Letter to Langner from Hind, re: Inspection 11/16-17/78 (10pages)
- 3. '04/29/83 Letter to Rampy from Miller, re: Inspection 4/5-6/83 (8 pages)
c, Re: FOIA-85-256,85-258, 85-259 and 85-261 APPENDIX N Document Withheld In Its Entirety
- 1. 03/29/85 Memorandum to Schumacher from M. J. Destmann, " Review of Draft Report on ' Radiological Survey of the Former Dow Chemical Corporation Site in Bay' City, Michigan'" (2 pages)
GOVERNMENT ACCOUNTABILITY PROJECT 1555 Connecticut Avenue, N.W., Suite 202 Washington, D.C. 20036 April 9, 1985 (202)2324550 Freedom of Information Officer FREEDOM 0F INFORM ATION United States -
AC Nuclear Regulatory Commission Washington, D.C. 20555 {g %-- L(p l
Dear Freedom of Information Officer,
I L ll Under the provisions of the Freedom of Information Act, 5 U.S.C. 552, the Government Accountability Project (GAP) is requesting copies of any information compiled by and/or for the NRC/AFC reaarding the Dow Chemical Com-pany of Midland, Michigan which was compiled in order to comply with, and/or to determine the need to comply with, 10 CFR Parts 19, 20, 30, 31, 32, 33, 34, 35, 40, 51.4, 51.5, 51.6, 51.7, 70, 17 0,ht a tand/or GAP requests 40 CPR any fees Parts 1500.6.
be waived. As you know, the Act (5 U.S.C. 5 5 2 (a )' (4 ) (a ) ) permits you to waive any fees whea the release of the information is considered as "primarily benefiting the public." GAP believes that this request fits that category.
For any documents or portions of documents that you deny due to a specific exemption under the Act, please provide an index itemizing and describing the documents or portions of documents withheld. The index should provide a detailed justification of your grounds for claiming each exemption, explaining why each exemption is relevant to the document or portion of document with-held.
GAP would appreciate your handling this request as quickly as possible, and we look forward to hearing from you within ten (10) days, as the Act stipulates.
Sincerely, Steve Kohn Staff Attorney Richard Condit Staff Associate
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1.ocations of Elevated Contact Radiation Levels - Field Area. 9 FIGURE 11: s
l TABLE 1A DIRECT RADIATION LEVELS MEASURED AT BASELINE SAMPLE LOCATIONS FORMER DOW CHEMICAL SITE - BAY CITY, MICHIGAN Sample s Exposure Rate (uR/h)
Location Contact 1 m Above Surface 1 8 8 2 9 9 3 7 7 4 9 9 a See Figure 9.
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TABLE IB -
RADIONUCLIDE CONCENTRATIONS EASURED IN BASELINE SOIL AND SEDIMENT SAMPLES FORMER DOW CHEMICAL SITE - BAY CITY, MICHICAN Sample a Sample Radionuclide Concentrations (pC1/g)
Location Type Th-232 Th-228 U-238 Ra-226 1 Soil 0.50 + 0.31 b 0.28 + 0.26 1.05 + 1.15 0.48 + 0.20 2 Soil 0.57 I 0.27' O.10 I 0.09 <0774 0.80 I 0.19 3 Soil 0.85 7 0.35 0.47 I 0.31 1.41 + 1.19 0.59 I 0.15 3 Sediment 0.57 7 0.20 0.26 I 0.39 <0749 <0755 4 Soil 0.28 I 0.17 0.42 I 0.23 0.81 + 1.09 0.37 + 0.15 4 Sediment 0.96][0.34 0.89][0.29 1.35}[1.79 'O.35][0.33 a See Figure 9.
Rj b Errors are 20 based on counting statistics.
a TABLE IC RADIONUCLIDE CONCENTRATIONS MEASURED IN BASELINE WATER SAMPLES FORMER DOW CHEMICAL SITE - BAY CITY, MICHICAN Sample s Radionuclide Concentrations (pCi/J or x 10-9 uCi/ml)
Location Gross Alpha Cross Beta
.1 3.19 + 1.27 b 9.81 + 1.55 2 8.02 7 1.80 14.8 7 1.9 3 0.21 7 0.61 5.77 7 1.12 4 2.1330.97 6.2531.72 a See Figure 9.
b Errors are 2e based on' counting statistics.
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23
TABLE 2 DIRECT RADIATION LEVELS EASURED AT GRID LINE INTERSECTIONS - PROMSSING AREA PORER DOW GEMICAL SITE - BAY CITY, MICHIGAN Grid Location" Gamma Exposure Rates Gamma Exposare Rates at 1 m Above the Surf ace at the Surf ace (pR/h) (pR/h)
ON OE 8 8 i 20N OE 8 8 40N OE 8 8 60N OE 8 8 80N OE 10 11 100N OE 8 8 120N DE 8 8 140N OE 8 8 60N 20E 8 8 80N 20E 8 8 100N 20E 8 8 120N 20E -
8 8 140N 20E 9 10 60N 40E 7 8 SON 40E 8 8 100N 40E 8 8 120N 40E 8 8 ,
140N 40E 13 15 80N 60E 8 8 100N 60E 12 14 120N 60E 9 9 140N 60E 9 9 ON 80E 7 8 20N 80E 7 7 40N SOE 8 7 60N 80E 7 8 80N 80E 7 8 100N 80E 8 8 120N 80E 10 11 140N SOE 12 12 ON 100E 8 8 20N 100E 8 9 40N 100E 8 8 60N 100E 9 10 80N 100E 8 8 100N 100E 10 10 120N 100E 10 9 140N 100E 13 15 <
(N 120E 7 7 )
20N 120E 8 8 l 40N 120E 7 8 60N 120E 7 8 l l
24
TABLE 2 (Continued)
DIRECT RADIATION LEVELS EASURt.D AT GRID LINE !
INIT.RSECTIONS - PRO SSING AREA i FORER DOW GEMICAL SITE - BAY CITY, MIGIGAN Grid Location Gamma Exposure Rate s G amma Expo sur e Ra te s at 1 m Above the Surf ace at the Surf ace (pR/h) (pR/h)
SON 120E 7 7 100N 120E 8 8 120N 120E 8 8 140N 120E 10 11 ON 140E 8 8 20N 140E 8 7 40N 140E 8 8 60N 140E 8 7 80N 140E 7 8 100N 140E 7 7 120N 140E 8 8 140N 140E 9 11 ON 160E . 8 8 20N 160E 7 7 40N 160E 7 7 60N 160E 8 8 80N 160E 8 8 100N 160E 8 8 120N 160E 8 8 140N 160E 10 13 ON 180E 8 8 20N 180E 8 9 40N 180E 8 8 60N 180E 9 9 SON 180E 8 9 100N 180E 8 9 120N 180 E 9 9 140N 180E 10 9 20N 200E 8 8 120N 200E 10 10 140N 200E 11 15 ON 220E 9 10 20N 220E 7 8 120N 220E 9 11 140N 220E 10 9 20N 240E 8 8 120N 240E 10 9 140N 240E 9 9 ON 260E 8 8 20N 260E 9 9 40N 260E 9 9 60N 260E 9 9 80N 260E 9 10 25
j TABLE 2 (Cont inue d)
DIRECT RADIATION LEVE1.S IEASURED AT GRID LINE INIT.RSECTIONS - PRO SSING AREA FORMER DOW GENICAL SITE - BAY CITY. MIGIGAN Grid Location Gamma Exposure Rate s Gamma Exposure Rates at 1 a Above the Surface at the Surf ace (pR/h) (pR/h) 100N 260E 10 10 120N 260E 9 9 140N 260E 9 9 "Ref er to Figure 3.
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t TABLE 3 SURFACE RADIATION LEVELS MEASURED AT l
LOCATIONS IDENTIFIED BY THE WALKOVER SCAN - PROCESSING AREA FORMER DOW CHEMICAL SITE BAY CITY, MICHICAN Crid Location a Camma Exposure Rates ;
N E Prior to Decontamination Af ter Decontamination (UR/h) (pR/h)
At I m Above At the At 1 m Above At the The Surface Surface The Surface Surface i 53 253 21 175 14 42 57 257 17 105 13 32 65 197 14 175 10 13 82 58 *b 51 9 15 .
89 119
- 175 14 30 92 119 ,
- 84 14 30 :
60
- 105 13 11 .
100 '
118 94
- 47 10 11 15 I
!!8 226 15 105 14 121 58
- 33 14 30
- 13
- 122 82 71 126 40
- 33 13 15 ,
126 212
- 430 14 17 127 222
- 175 14 47 .
130 78
- 88 13 33 132 100
- 37 11 13 I
137 197
- 71 14 17 138 50
- 40 13 18 138 176
- 140 15 21 a Ref er to Figure 10.
b* Indicates no measurement was made. l
r TABLE 4 RADIONUCLIDE CONCENTRATIONS MEASURED IN SURFACE S0lt SAMPLES COLLECTED AT GRID LINE INTERSECTIONS-PROCESSING AREA FORMER DOW CHEMICAL SITE - BAY CITY, MICHIGAN Grida Radionuclide Concentrations (pC1/g)
Location Th-232 Th-228 U-238 Ra-226 N E 80 0 2.55 + 0.59 b 2.52 + 0.57 3.69 + 1.87 1.76 + 0.36 '
140 0 1.18 7 0.43 0.72 7 0.45 1.49 7 1.24 0.59 7 0.27 80 50 0.78 7 0.41 0.84-7 0.33 2.12 7 1.02 0.59 7 0.23 80 60 2.80 7 0.81 2.13 7 0.66 1.58 7 3.21 0.56 7 0.36 100 60 44.0 + 1.8 42.3 + 1.7 9.77 7 2.66 2.23 7 0.54 120 60 0.39 7 0.17 0.51 7 0.15 <0739 0.11 7 0.07 140 60 5.23 7 0.95 5.16 7 0.93 4.02 + 2.94 1.21 7 0.52 100 80 0.40 7 0.15 0.45 7 0.21 <0751 0.36 7 0.17 120 80 1.84 7 0.51 1.77 7 0.36 2.11 + 0.85 0.49'I 0.19 140 80 0.85 7 0.35 0.90 7 0.39 2.3971.26 0.72 7 0.19 0 100 0.65 7 0.31 0.60 7 0.30 (0752 0.52 7 0.13 20 100 0.84 7 0.30 0.93 7 0.24 0.81 + 1.47 0.65 7 0.14 40 100 0.66 7 0.38 0.54 I 0.24 0.51 7 1.05 0.44 7 0.15 60 100 1.'0 5 7 0.30 1.08 7 0.27 1.98 7 1.63 0.96 7 0.19 80 100 0.76 + 0.24 0.93 + 0.21 <0.50 0.44 + 0.17 100 100 1.62 7 0.32 1.53 7 0.27 <0.86 0.89 I 0.17 120 100 0.75 7 0.24 1.08 7 0.24 <0.58 0.60 7 0.17 140 100 2.82 7 0.57 3.00 7 0.51 2.97 + 1.46 1.07 7 0.28 0 120 0.52 7 0.24 0.78 7 0.24 0.95 7 0.94 0.52 7 0.13 20 120 1.77 7 0.47 2.40 7 0.48 <!710 0.47 7 0.27 40 120 1.02 7 0.62 1.29 7 0.42 <1.25 0.70 7 0.24 60 120 1.07 7 0.35 0.47 7 0.21 0.91 + 1.22 0.45 7 0.21 80 120 1.01 7 0.33 1.20 7 0.30 (0.67 0.95 + 0.18 100 120 1.82 7 0.40 1.32 7 0.41 2.30 + 1.15 0.85 7 0.21 120 120 0.79 7 0.49 0.96 7 0.30 0.86 7 1.25 0.68 7 0.26 140 120 5.48 7 0.65 5.07 7 0.60 5.56 7 1.95 0.90 7 0.25 0 140 '0.88 7 0.27 0.48 7 0.24 <0753 0.42 7 0.16 20 140 0.40 7 0.37 0.63 7 0.21 <0.69 0.36 7 0.11 40 140 0.55 7 0.22 0.93 7 0.27 <0.55 0.81 7 0.17 60 140 0.76 7 0.31 0.81 7 0.24 0.93 + 1.08 0.76 7 0.20 80 140 1.48 I 0.43 0.87 7 0.30 <0767 0.74 7 0.23 100 140 0.80 7 0.33 0.87 7 0.30 (0.79 0.69 7 0.18 '
120 140 1.02 7 0.40 1.11 7 0.36 1.53 + 1.27 0.76 7 0.23 140 140 4.73 7 4.65 7 0.54 <!746 0.94 7 0.26 0 160 0.34 7 0.22 0.51 7 0.27 <0.54 0.51 7 0.17 20 160 0.47 + 0.23 0.63 + 0.21 <0.60 0.57 + 0.12
( 80 160 0.85 + 0.38 0.78 + 0.39 <0.75 0.67 7 0.29 120 160 1.69 7 0.43 1.92 7 0.36 2.44 + 2.23 0.69 7 0.21 140 160 3.49 7 0.64 3.54 7 0.60 1.23 7 1.12 0.76 7 0.32 0 180 0.40 7 0.23 0.30 7 0.21 <0752 0.46 7 0.12 l 20 180 0.23}[0.17 0.243[0.15 <0.35 0.373[0.10 l
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4 TABLE 4 (Continued)
RADIONUCLIDE CONCENTRATIONS MEASURED IN SURFACE SOIL SAMPLES COLLECTED AT GRID LINE INTERSECTIONS-PROCESSING AREA FORMER DOW CHEMICAL SITE - BAY CITY, MICHIGAN Grida Radionuclide Concentrations (pCi/g)
Location Th-232 Th-228 U-238 Ra-226 N E 40 '180 <0.10 0.18 + 0.15 <0.48 0.56 + 0.11 60 180 0.97 + 0.27 0.78 7 0.27 <0.53 0.61 7 0.21 80 180 0.46 7 0.17 0.39 7 0.15 <0.47 0.48 7 0.11 100 180 0.74 7 0.28 0.48 7 0.24 <0.48 0.40 7 0.16 120 180 1.31 7 0.22 1.35 7 0.18 1.33 + 1.07 0.39 7 0.09 140 180 7.32 7 0.92 7.92 7 0.84 7.65 7 1.82 0.63 7 0.28 40 200 0.66 7 0.26 0.69 7 0.21 <0780 0.49 7 0.17 80 200 0.83 7 0.29 1.14 7 0.42 1.60 + 1.52 0.76 7 0.25 120 200 1.72 7 0.37 1.08 7 0.30 2.50 7 0.95 0.46 7 0.13 140 200 2.53 7 0.50 2.76 7 0.54 <0795 0.40 7 0.27 0 220 1.72 7 0.44 1.23 7 0.36 <1.02 0.95 7 0.19 20 220 <0709 0.15 7 0.12 0.48 + 0.63 0.39 7 0.12 120 220 1.17 + 0.28 1.14 7 0.27 2.03 7 1.21 0.52 7 0.15 140 220 0.41 7 0.23 0.42 7 0.30 ' <0740 0.14 7 0.07' 20 240 0.73 7 0.27 0.78 7 0.21 <0.64 0.42 7 0.15 120 240 0.43 7 0.28 0.60 7 0.36 1.10 + 0.96 0.50 7 0.13 140 240 <0.18 0.30 + 0.15 <0766 0.43 7 0.15 0 260 0.94 + 0.32 0.69 7 0.27 <0.44 0.31 7 0.11 20 260 1.35 7 0.32 0.88 7 0.24 <0.73 0.31 7 0.13 40 260 1.01 7 0.34 0.72 7 0.18 1.01 + 0.99 0.36 7 0.17
- 60 260 0.83 I 0.27 0.93 7 0.27 <0771 0.52 7 0.17 80 260 1.10 7 0.45 1.37 7 0.39 0.69 + 1.61 0.80 7 0.25 100 260 1.21 7 0.46 0.84 7'O.33 2.10 7 1.62 0.50 7 0.19 120 260 0.41 7 0.20 0.63 7 0.18 <0736 <0709 140 260 0.4630.25 0.6030.21 <0.66 0.63 + 0.13 a Refer to Figure 3.
b Errors are 20 based on ecunting statistics.
29
s
.~
RADIONUCLIDE 0)NCENTRATIONS DEASURED IN SURFACE SOIL SAMPLES COLLECTED FROM SELECTED LOCATIONS OF ELEVATED CONTACT RADIATION LEVELS PROCESSING AREA FORMER DOW CHEMICAL SITE - BAY CITY, MICHICAN .
Crid" Coordinate Radionuclide Concentrations (pC1/g)
N E 1h-232 . Th-228 U-238C Ra-226 65 197 149 + 4 h 153 + 4 <22.2 1.79 + 1.08 100 60 90.5 + 2.8, 92.4 + 2.4 <l5.4 4.14 + 0.83 118 226 85.3 + 2.7 82.2 + 2.5 <17.8 <0.48 g 137 197 123 + 3 120 + 3 <8.04 9.16 + 1.03 ,
a Refer to Figure 10.
b Errors are 20 based on counting statistics.
c Large minimum detectable values are due to interference from high thorium concentrations.
TABLE 6 RADIONUCLIDE CONCENTPJILTIONS MEASURED IN SOIL SAMPLES COLLECTED AFTER DECONTAMINATION - PROCESSING AREA FORMER DOW CHEMICAL SITE - BAY CITY, MICHIGAN Grida Depth Below '
Coordinate Original Surface Radionuclide Concentrations (pCi/g)
N E (cm) Th-232 Th-228 U-238 Ra-226 53 253 30 - 45 264 +Sb 256 +5 <33.3 30.4 + 1.6 57 '257 30 - 45 1.57 7 0.50 2.64 I 0.54 <0.94 0.68 I 0.21 82 58 IOC 35.5 I 1.7 38.4 7 1.7 <9.34 1.10 I 0.48 92 119 65c 73.3 I 2.8 74.7 7 2.7 <l5.2 3.73 7 0.90 13.9 I 1.2 l 100 90 30 - 45 13.8 T 1.2 <5.55 1.11 7 0.42 106 91 15 - 30 10.0 T 0.6 11.7 7 0.7 <10.2 1.09 7 0.25 118 68 45 - 60 11.6 7 0.8 11.8 7 0.8 <6.57 0.57 7 0.29 i 118 94 30 - 45 2.75 7 0.48 2.40 T 0.36 1.42 + 1.53 0.58 T 0.14 (
121 58 15e 55.3 T 2.8 53.7 7 2.4 < ! 771' 2.56 T 0.77 122 79 30 - 45 7.36}0.68 6.30 _I 0.69 <l.80 1.11}0.29 l w 126 40 15 - 30 7.09 + 0.69 7.14 + 0.60 4.93 + 1.41 1.17 + 0.29 l
~ 126 208 45 - 60 7.93 + 0.73 7.83 + 0.57 5.17 + 2.52 0.97 + 0.29 126 212 45 - 60 3.04 T 0.68 2.94 I 0.60 2.23 I 2.27 1.50 7 0.30 126 216 45 - 60 1.08 + 0.39 1.32 + 0.27 4.52 + 1.36 1.03 + 0.19 126 220 80 - 95 22.1 T 1.6 22.4 T 1.4 <6 97 0.91 T 0.50 127 222 60 - 75 45.5 T 1.8 42.6 7 1.7 <10.2 1.38 I 0.56 127 232 30 - 45 2.44 T_ 0.49 2.16[0.36 3.17 + l.41 1.05 7 3.22 130 78 30 - 45 17.6 + 1.5 18.3 + 1.4 <6.79 0.98 + 0.47 132 36 15 - 30 5.00 7 0.69 4.50 I 0.57 <l.63 1.05 7 0.24 136 43 15 - 30 1.75 I 0.42 1.92 7 0.39 <0.66 0.27 7 0.25 136 173 55 - 70 0.64 7 0.33 0.54 T 0.18 1.29 + 0.76 0.52 7 0.14 13o 180 55 - 70 7.15 7 0.76 6.48 T 0.72 3.42 I 1.50 0.87 7 0.20 136 184 55 - 70 0.91 I 0.33 0.48 I 0.33 <0769 0.27 7 0.18 136 189 55 - 70 0.52 T 0.33 0.63 I 0.36 1.14 + 1.07 0.37 7 0.17 137 24 30 - 45 6.02 I 0.62 5.34 I 0.54 <4750 1.04 I 0.30 137 30 15 - 30 4.00 I 0.61 4.26 I 0.60 <l.36 0.88 7 0.30 138 50 15 - 30 1.40 _+ 0.39 1,71 _+ 0.30 <l.01 0.52 I_ 0.14 3 i
a Refer to Figure 3.
b Errors are Zo based on counting statistics.
c Over subsurface concrete or metal structure.
TABLE 7 -
r RADIONUCLIDE CONCENTRATIONS MEASURED IN SOIL SAMPLES ,
COLLECTED FROM BOREHOLES - PROCESSING AREA l FORMER DOW CHEMICAL SITE - BAY CITY, MICHICAN Borehole" Grid Depth Location Coordinate (m) Radionuclide Concentrations (pCi/g)
N E Th-23f. Th-228 U-238 Ra-226 B1 17 140 0 - 0.15 0.16 +.0.28 b 0.18 + 0.12 <0.37 0.19 ~+i0.17 1 - 1.5 0.91}0.33 0.60 _I 0.30 1.43 + 1.28 0.57 +iO.19 B2. 58 262 0 - 0.15 0.80 + 0.30 1.35 + 0.36 <0.97 0.50 + 0.19 1 - 1.5 0.82 7 0.35 0.81 7 0.24 1.91 + 1.24 0.48 7 0.14 2.5 - 3.0 1.0510.61 0.57}0.30 <0768 0.51 7 0.18 B3 59 19 0 - 0.15 0.92 + 0.32 0.66 + 0.33 0.47 + 1.30 0.56 + C.16 l' - 1.5 0.47 T 0.29 0.44 7 0.28 0.51 T 1.45 0.43 T 0.16 g 2.5 - 3.0 0.82 _I 0.39 0.65}0.31 0.89 _I 1.10 0.54 _I 0.18 i
)
B4 79 183 0 - 0.15 0.62 + 0.25 0.81 + 0.24 2.11 + 0.93 0.75 + 0.18 0.37 7 0.20 0.57 T 0.19 0.69 7 0.99 0.44 I 0.20 1 - l.5 2.5 - 3.0 1.03 _T 0.29 0.75 _T 0.21 <0783 0.51 I 0.14 B5 100 60 0 - 0.15 90.5 + 2.8 92.4 + 2.4 <l5.4 4.14 + 0.83 1 - 1.5 0.25 7 0.24 0.48'T 0.21 <0.56 0.31 7 0.18 2.5 - 3.0 0.59 _T 0.39 0.6010.24 <0.69 0.5210.18 B6 119 140 0 - 0.15 0.40 + 0.25 0.29 + 0.18 0.74 + 0.86 -
0.16 + 0.10 1 - 1.5 1.23 T 0.40 0.60 T 0.21 <0 46 0.41 T 0.17
- 2. 5 - 3.0 0.97 _I 0.38 0.96 _I 0.24 <0.82 0.63 _I 0.21 87 130 43 0 - 0.15 2.51 + 0.42 2.46 + 0.39 2.21 + 1.17 'O.97 + 0.26 1 - 1.5 0.62 T 0.32 0.60 7 0.21 1.05 + 0.60 0.52 7 0.17 (0775 2.5 - 3.0 0.76 _T 0.37 0.51 _T 0.24 <0711 a See Figure 5.
b Errors are 2a based on counting statistics.
TABLE 8 RADIONUCLIDE CONCENTRATIONS MEASURED IN I' SEDIMEffr SAMPLES PROCESSING AREA - FORMER DOW CHEMICAL SITE BAY CITY, MICHIGAN Sample Location a Grid Radionuclide Concentrations (pC1/g)
Identification of Location Th-232 Th-228 U-238 Ra-226-Number Sample N E 1 Conveyor Pit 13 100 0.82+0.57b 1.20 + 0.33 <0.89 0.61 + 0.20 2 Conveyor Pit 20 120 0.80 + 0.40 0.96 + 2.94 <0.65 0.55 + 0.24 3 Conveyor Pit 50 120 1.06 + 0.32 0.93 + 0.36 <0.79 0.73 + 0.18 4 Conveyor Pit 62 120 0.68 + 0.44 1.02 + 0.36 0.67 + 1.73' O.61~+ 0.23
$ 5 Conveyor Pit 92 125 2.90 + 0.57 3.12 + 0.63 2.58 + 2.44 0.79 + 0.22 6 Conveyor Pit 105 128 0.75 + 0.59 0.57 + 0.36 <0.60 0.52 + 0.16 7 Drain 25 196 1.02 + 0.43 1.26 + 0.45 .<0.76 0.60 + 0.23 8 Drain 56 255 28.0 + 1.7 27.1 + 1.7 <l2.0 3.34 + 0.65 9 Drain 72 49 1.42 + 0.38 1.08 + 0.36 0.96 + 1.33 0.47 + 0.19 10 Drain 77 103 4.50 + 0.63 4.53 + 0.54 2.63 + 1.88 0.41 + 0.25 11 Drain 82 193 1.00 + 0.26 0.99 + 0.27 <0.84 0.67 + 0.18.
a Refer to Figure 7.
b Errors are 20 based on counting statistics.
~
TABLE 9 RADIONUCLIDE CONCENTRATIONS MEASURED IN WATER SAMPLES - PROCESSING AREA FORMER DOW CHEMICAL SITE - BAY CITY, MICHIGAN Sample Location a Grid Radionuclide Concentrations (pC1/1 or x 10-9 pC1/al)
Identification of Coordinate Gross Alpha Gross Beta Ra-226 Ra-228 Number Sample N E I Conveyor Pit 13 100 4.54 + 1.26h 40.0 f; 2.1 ---c ---
2 Conveyor Pit 20 120 5.36 f; 1.33 38.2 f; 2.1 ---
3 Conveyor Pit 50 120 1.63 f; 0.97 36.7 f; 2.1 ---
4 Conveyor Pit 62 120 2.30 f; 1.08 36.9 j; 2.1 --- ---
y 5 Conveyer Pit 92 125 2.23 f; 1.08 34.0 f; 2.0 --- ---
6 Conveyer Pit 105 128 3.36 f; 2.00 33.2 f; 3.6 --- ---
7 Drain 25 196 <0.75 5.82 j; 1.47 --- ---
8 Drain 56 255 1.61 f; 0.78 14.6 f; 1.5 9 Drain 72 49 186 j; 10 0.17 j; 0.05 11.9 f; 5.2 1.04 f; 0.43 10 Drain 82 193 4.41 f; 2.22 33.6 f; 3.5 --- ---
11 Borehole B3 59 19 13.2 f; 2.5 6.36 j; 2.28 0.10 j;0.05 2.46 f;0.51 12 Borchole B4 79 183 30.6 f; 7.3 16.1 f; 7.1 0.72 f;0.22 1.54 f;1.79 13 Borehole B5 100 60 5.06 f; 3.02 179 ff 8 ---
14 Borehole B6 119 140 20.7' f; 3.8 13.3 f; 3.1 <0.12 3.38 f; 1.48 a See Figure 5 and 8.
b Errors are 20 based on counting statistics.
C .
Dash indicates analyses not pe r fo rmed .
}
'l TABLE 10 DIRECT RADIATION LEVELS EASURED AT GRID LINE 1 INTERSECTIONS - FIELD PEA FORER DOW GEMICAL SITE - BAY CITY, MIGIGAN ,)
I Grid Loca tion
- Gamma Exposure ' Rate s ~ Gamma Exposure Rate s at 1 m Above the Surf ace at the Surf ace (pR/h) (pR/h)
ON OE~- 8 8 20N OE 9 9 40N OE 9 10 60N DE 13 13 80N OE 8 9
-10N 20E 9 8 ON 20E 10 10 20N 20E 10 10 40N 20E 9 9 60N 20E' 10 10 i 80N 20E 10 10
-10N 40E ,
9 9 ON 40E 9 9 20N 40E 9 9 40N 40E 9 9 60N 40E 9 9 80N 40E 9 9 3
20N 50E 9 9 40N 50E 9 9
. 60N 50E 9 9 80N 50E 9 9
- Refer to Figure 4.
35
TABLE 11 SURFACE RADIATION LEVELS MEASURED AT LOCATIONS IDENTIFIED BY THE WALKOVER SCAN - FIELD AREA FORMER DOW CHEMICAL SITE BAY CITY, MICHIGAN Grid Location a Gamma Exposure Rates N E Prior to Decontamination Af ter Decontamination (pR/h) (pR/h)
At 1 m Above At The At 1 m'Above At The The Surface Surface The Surface Surface 11 15 18 40 13 15 20 17 *b 51 11 21 26 32
- 37 15 18 31 4
- 140 13 27 33 20
- 51 13 37 35 10
- 30 10 21 45 30
- 105 11 30
- a. 46 3
- 63 14 15 53 20
- 30 13 18 55 18
- 63 13 40 77 30
- 105 13 18 77 34 21 175 13 18 79 20 21 279 13 18 80 25 30 314 13 18 80 27 45 600 13 18 a Refer.to Figure 11.
D*' Indicates no measurement was made.
36
o ..
TABLE 12 RADIONUCLIDE CONCENTRATIONS MEASURED IN SURFACE. SOIL SAMPLES COLLECTED AT GRID LINE INTERSECTIONS - FIELD AREA FORMER DOW CHEMICAL SITE - BAY CITY, MICHIGAN Sample a Location Radionuclide Concentrations (pC1/g)
N E Th-232 Th-228 U-238 Ra-226 0 0 0.35 + 0.29 b 0.36 + 0.21 <0.61 0.38 + 0.18 20 'O 0.66 7 0.07 0.66 I 0.06 2.76 + 0.32 0.44 7 0.04 40 0 1.49 7 0.51 1.56 7 0.42 0.93 I 1.37 0.37 7 0.20 60 0 2.32 7 0.60 2.46 I 0.60 0.89 7 1.87 0.56 I 0.24 0.97 7 0.25
~
80 0 0.57 I 0.51 0.51 7 0.30 <0786
-10 20 0.58 I 0.26 0.45 I 0.27 <0.77 0.39 7 0.18 0 20 1.45 I 0.78 2.34 I 0.51 1.75 + 1.00 0.31 7 0.23 20 20 0.31 7 0.37 0.69 7 0.21 <0761 0.28 I 0.12 40 20 0.55 I 0.37 0.39 7 0.33 <0.46 0.19 7 0.09 60 20 1.14 7 0.54 0.78 I 0.54 0.68 + 2.50 0.70 7 0.17 80 20 0.55 I 0.05 0.45 7 0.03 0.44 7 0.21' O.41 7 0.03 140 20 1.06 I 0.50 0.72 7 0.42 <1702 0.49 7 0.37
-10 40 0.78 I 0.44 0.90 7 0.42 <0.82 0.40 7 0.33 0 40 0.51 7 0.64 0.69 I 0.42 <6.47 0.49 I 0.30 20 40 0.57 7 0.41 0.36 7 0.27 <6.19 0.27 7 0.14 40 40 0.66 I 0.34 0.75 7 0.30 <3.62 0.27 7 0.10 60 40 0.51 7 0.51 0.39 7 0.45 <0.71 0.51 7 0.19 80 40 0.86 I 0.54 1.'14 I 0.27. <0.87 0.67 7 0.19 100 40 1.00 T 0.43 0.96 7 0.39- <0.68 0.57 I 0.27 140 40 0.91 7 0.38 0.84 7 0.27 <0.67 0.33 7 0.12 20 50 0.51 7 0.34 0.65 7 0.27 1.02 + 2.25 0.33 7 0.22 40 50 0.74 I 0.28 0.90 7 0.27 <0777 <0709 60 50 0.57[0.43 0.57[0.36 <0.71 0.52 + 0.25 a Refer to Figure 4.
b Errors are 20 based on counting statistics.
37
TABLE 13 RADIONUCLIDE CONCENTRATIONS MEASURED IN SURFACE SOIL SAMPLES COLLECTED FROM SELECTED LOCATIONS OF ELEVATED CONTACT RADIATION LEVELS - FIELD AREA FORMER DOW CHEMICAL SITE - BAY CITY,' MICHIGAN Grida Coordinate Radionuclide Concentrations (pC1/g)
N E Th-232 Th-228 U-238C Ra-226 11 15 0.77 + 0.25b 0.60 + 0.27 0.77 + 0.9 0.23 + 0.12 21 16 -34.5 + 1.8 34.2 + 1.8 <9.33 <0.26 33 20 41.1 + 1.8 40.5 + 1.8 <10.4 0.99 + 0.50 45 30 43.0 + 2.0 42.0 + 1.9 <8.69 0.52 + 0.47 s
53 20 15.2 + l.5_
14.8 + 1.3 <7.80 0.65 + 0.34 77 30 274 + 5 272 +
_5 <33.8 25.2 + 1. 5 a Refer to Figure 4.
b Errors are 20 based on counting statistics.
c Large minimum detectable values are due to interference from high thorium concentrations.
4#
TABLE 14 ,
RADIONUCLIDE CONCENTRATIONS MEASURED IN SOIL SAMPLES COLLECTED AFTER DECONTAMINATION - FIELD AREA FORMER DOW CHEMICAL SITE - BAY CITY, MICHIGAN Crida Depth Below Coordinate Original Surface Radionuclide Concentrations (pC1/g)
N E (cm) Th-232 Th-228 U-238 Ra-226 11 15 80 - 95 6.51 + 0.78 h 6.75 + 0.78 <3.80 <0.14 26 14 15 - 30 7.67li 0.83 7.83 I 0.78 <4.52 0.36 + 0.32 26 32 15 - 30 6.81 7 0.92 7.26 7 0.81 <5.09 0.19 7 0.17 34 16 15 - 30 8.25 7 0.74 8.19 7 0.81 <7.10 0.48 I 0.20 35 10 15 - 20 1.98 T 0.40 1.62 7 0.42 1.24 + 1.53 0.35 7 0.13 46 3 15 - 30 1.09 7 0.32 1.17 I 0.27 <0781 0.28 I 0.15 55 18 15 - 30 1.65 I 0.58 1.74 I 0.36 <l.23 0.39 I 0.15 g 55 21 60 - 75 1.77][0.48 2.01][0.45 3.81 + 1.35
, 0.61][0.18 a- Refer to Figure 4.
b Errors are 20 based on counting statistics.
m . _ _ =
TABLE 15 RADIONUCLIDE' CONCENTRATIONS MEASURED IN SOIL SAMPLES COLLECTED FROM BOREHOLES - FIELD AREA FORMER DOW CHEMICAL SITE - BAY CITY, MICHIGAN Sample a Crid Depth Location Coordinate (m) Radionuclide Concentrations (pC1/g)
N E Th-232 Th-228 U-238 Ra-226 B8 31' 4 0 - 0.15 10.4 + 1.0b 10.6 + 0.8 <2.12 0.28 + 0.25 1 - 1.5 0.48}0.22 0.51l_0.30 <0.52 0.3510.16 89 40 20 0 - 0.15 1.16 + 0.30 0.43 + 0.20 <0.59 0.37 + 0.12 1 - 1.5 0.45 I 0.24 0.39 I 0.30 <0.57 0.50 I 0.18 2.5 - 3.0 0.91 _I 0.31 0.46 + 1.28 0.66 _I 0.33 0.5510.16 8
a Refer to Figure 6.
b Errors are 20 based on counting statistics.
1
- 1 REFERENCES
- l. Deconunissionina of the DOW/Wellman Foundry Site in Bay City. Michigan. ,
Letter from R.A. Olson (DOW) to M. Schumacher (NRC), October 8, 1982. l
- 2. Title 40, Code of Federal Regulations, Part 141, Interim Primary Drinkinz Water Standards. Federal Register, July, 1976. ;
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- f APPENDIX A MAJOR ANALYTICAL EQUIPMENT I
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APPENDIX A Major Analytical Equipment The display or description of a specific product is not to be construed as an endorsement of that product or its manufacturer by the authors or their employer.
A. Direct Radiation Measurements Eberline PRM-6 Portable Ratemeter (Eberline, Sante Fe,'NM)
Victoreen Gamma Scintillator (Nal) Probe Model 489-55 (Victoreen, Inc.. Cleveland, OH)
Reuter-Stokes Pressurized Ionization Chamber Model RSS-111 (Reuter-Stokes, Cleveland, OH)
B. Laboratory Analyses Ge(Li) Detector Model LGCC2220-SD, 23% ef ficiency (Princeton Gamma-Tech, Princeton, NJ)
Used in conjunction with:
Lead Shield, SPG-16 (Applied Physical Technology, Smyrna, GA)
Pulse Height Analyzer, ND680 Model 88-0629 (Nuclear Data, Inc., Schaumburg, IL)
High-Purity Germanium Detector Model GMX-23195-S, 23% efficiency (EG&G ORTEC, Oak Ridge, TN)
Used in conjunction with:
Lead Shield, G-16 (Gamma Products Inc., Palos Hills, IL)
Low Background Alpha-Beta Counter Model LB5100-2080 (Tennelec. Inc., Oak Ridge, TN)
A-1
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APPENDIX B ANALYTICAL PROCEDURES i
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a APPENDIX B Analytical Procedures Gamma Scintillation Messurements Walkover surface scans and measurements of gamma exposure rates were performed using Eberline Model PRM-6 portable ratemeters with Victoreen Model 489-55 gamma scintillation probes containing 3.2 cm x 3.8 cm Nr.I(TI) crystals. Count. rates were converted to exposure rates (pR/h) using f actors determine'd - by cross calibration of the scintillation detectors with a Reuter Stokes model RSS-111' pressurized ionization chamber, at several locations on the surveyed property.
Soil and Sediment Sample Analysis Soil and sediment samples were dried, mixed, and a portion sealed in a 0.5-liter Marinelli beaker. The quantity placed in each beaker was chosen to reproduce the calibrated counting geometry and ranged from 400 to 800 g of soil. Net soil weights were Jetermined and the samples counted using Ge(Li) and intrinsic germanium detectors coupled to a Nuclear Data model ND-680 pulse height analyzer system. Background and Compton stripping, peak search, peak identification, and concentration calculations were performed using the computer capabilities inherent in the analyzer system. Energy peaks used for determination of radionuclides of concern were:
Th-232 - 0.911 MeV from Ac-228*
Th-228 - 0.583 MeV from T1-208*
U-238 - 0.094 MeV from Th-234 or 1.001 MeV from Pa-234m*
Ra-226 - 0.609 MeV from Bi-214*
- Secular equilibrium was assumed Water Sample Analysis Water samples were rough-filtered through Whatman No. 2 filter paper.
Remaining suspended solids were removed by subsequent filtration through 0.45 um membrane filters. The filtrate was acidified by addition of 10 ml of concentrated nitric acid. Aliquots ver e then evaporated to dryness and counted B-1
g '8 ed for gross alpha and gross beta using a Tennelec Model LB 5100 low-background proportional counter.
Samples were analyzed for Ra-226 and 228 using the standard technique EPA 600/4-75-008 (Revised).
~ Calibration and Quality Assurance All survey and laboratory instruments were calibrated with NBS-traceable standards. Quality control procedures on all instruments included daily background and check-source measurements to confirm acceptable equipment operations. The ORAU laboratory participates in the EPA Quality Assurance Program.
4 a
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APPENDIX C NUCLEAR REGULATORY COMMISSION GUIDELINES FOR RESIDUAL CONCENTRATIONS OF THORIUM AND URANIUM WASTE IN SOIL 4
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Guidelines for Residual Concentrations of Thorium and Uranium Wastes in Soil On October 23, 1981, the Nuclear Regulatory Commission published.in the Federal Register a notice of Branch Technical Position on " Disposal or Onsite Storage of Thorium and Uranium Wastes from Past Operations." This document establishes guidelines for concentrations of uranium and thorium in soil, that will limit maximum radiation received by the public under various conditions of future land usage. These concentrations are as follows:
Maximum Concentrations (pCi/g')
for various options
. Material 18 2D 3' 4o Natural Thorium (Th-232 + Th-228) with daughters present and in equilibrium 10 50 -
500 Natural Uranium (U-238 + U-234) with daughters present and in equilibrium 10 - 40 200 Depleted Uranium:
Soluble 35 100 -
1,000 Insoluble 35 300 -
3,000 Enriched Uranium:
Soluble 30 100 - 1,000 Insoluble 30 250 -
2,500 abased on EPA cleanup standards which limit radiation to 1 mrad /yr to lung and 3 mrad /yr to bone from ingestion and inhalation and 10 pR/h above background from direct external exposure.
bBased on limiting individual doses to 170 mrem /yr.
cBased on limiting equivalent exposure to 0.02 working level or less.
dBased on limiting individual doses to 500 arem/yr and in case of natural uranium, limiting exposure to 0.02 working level or less.
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Option 1 concentrations permit unrestricted use of the property and is the guideline applicable to surf ace soils. Options 2, 3, and 4 apply to buried wastes and assume that intrusions into the burial sites may occur.
Regardless of the concentrations in the buried materials, surface soil must meet the Option 1 concentration guidelines.
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