-.. S H I EL DA L LOY M ETALLU RG I CAL CO RPO RAT1 ON - December 26, 1991 WEST BOULEVARD P.O. BOX 768 Mr. Yawar Faraz NEWFIELD, NJ 08344 TELEPHONE (609) 692-4200 TWX (510) 687-8918 FAX (609) 692-4017 Mail Stop 6H-3 Advanced Fuel & Special Facilities Section Division of Industrial & Medical Nuclear Safety (609) 697-9025 Office of Nuclear Material Safety and Safeguards United States Nuclear Regulatory Commission RE: Shieldalloy Metallurgical Corporation (SMC) Fuel Cycle Safety Branch ENVIRONMENTAL DEPARTMENT FAX Newfield, New Jersey Source Material Inventory and Ferrocolumbium (FeCb) Slag Leachability Reports NRC Docket No. 40-7012 Dear Mr. Faraz: As requested by your office, SMC has compiled the subject reports for your review in cdnnection with SMC's request to increase the source material possession limit. The leachability study was conducted in accordance with ANSI/ANS16.1 as requested by Mr. Jerry Swift's letter dated June 14, 1991. The FeCb leachability report was developed by Teledyne Isotopes of Westwood, New Jersey and is included as Attachment A. The source material inventory data reported in Attachment B was prepared by means of a SMC records search and a volumetric measurement of the FeCb slag piles. A high altitude stereo compilation photograph of the FeCb slag piles was provided by GEOD Corporation of Newfoundland, New Jersey. This volumetric measurement was conducted in mid-October 1991. The results of the GEOD measurements indicated the volume of FeCb slag in the source material storage to be approximately 17,875 cubic meters. This figure is consistent with past estimates of volume by O3k Ridge Associated Universities' (ORAU) Radiological Survey, July 1988 and SMC. Because of the irregular shapes of the FeCb slag, the GEOD reported volume value is adjusted by 20% to correct for void spaces within the slag pile. This was the most conservative void space value applied by ORAU in 1988 and is supported by geotechnical engineering calculations. SMC has historically reported a source material inventory based upon assays of Tho, and U308 by the ore vendor. This method of analysis significantly overestimates the amounts of Uranium-238 and Thorium-232 in SMC inventory. For the recent SMC inventory of source material reported in Attachment B, SMC utilized radiological analyses for Thorium-232 and Uranium-238 to determine the amount of source
Transcript
-..
S H I EL DA L LOY M ETALLU RG I CAL CO RPO RAT1 ON -
Mail Stop 6H-3 Advanced Fuel & Special Facilities Section
Division of Industrial & Medical Nuclear Safety (609) 697-9025 Office of Nuclear Material Safety and Safeguards United States Nuclear Regulatory Commission
RE: Shieldalloy Metallurgical Corporation (SMC)
Fuel Cycle Safety Branch ENVIRONMENTAL DEPARTMENT FAX
Newfield, New Jersey Source Material Inventory and Ferrocolumbium (FeCb) Slag Leachability Reports NRC Docket No. 40-7012
Dear Mr. Faraz:
As requested by your office, SMC has compiled the subject reports for your review in cdnnection with SMC's request to increase the source material possession limit. The leachability study was conducted in accordance with ANSI/ANS16.1 as requested by Mr. Jerry Swift's letter dated June 14, 1991. The FeCb leachability report was developed by Teledyne Isotopes of Westwood, New Jersey and is included as Attachment A . The source material inventory data reported in Attachment B was prepared by means of a SMC records search and a volumetric measurement of the FeCb slag piles. A high altitude stereo compilation photograph of the FeCb slag piles was provided by GEOD Corporation of Newfoundland, New Jersey. This volumetric measurement was conducted in mid-October 1991.
The results of the GEOD measurements indicated the volume of FeCb slag in the source material storage to be approximately 17,875 cubic meters. This figure is consistent with past estimates of volume by O 3 k Ridge Associated Universities' (ORAU) Radiological Survey, July 1988 and SMC. Because of the irregular shapes of the FeCb slag, the GEOD reported volume value is adjusted by 20% to correct for void spaces within the slag pile. This was the most conservative void space value applied by ORAU in 1988 and is supported by geotechnical engineering calculations.
SMC has historically reported a source material inventory based upon assays of Tho, and U308 by the ore vendor. This method of analysis significantly overestimates the amounts of Uranium-238 and Thorium-232 in SMC inventory. For the recent SMC inventory of source material reported in Attachment B, SMC utilized radiological analyses for Thorium-232 and Uranium-238 to determine the amount of source
Mr. Yawar H. Faraz, USNRC December 73, 1991 Page 2
- v
material on site. Therefore, SMC estimates the FeCb slag piles to contain 230,000 kg of Th-232 and 29,400 kg U-238. In addition the lime pile contains 17,000 kg of Th-232 and 1,800 kg of U-238 while work in process adds 907 kg and 73 kg respectively. Consequently t h e cumulative source material inventory is 248,000 kg of Th-232 and 31,000 kg of U-238. The radiological analysis of Th-232 and U-238 of pyrochlore is the means by which SMC will estimate inventory in the future, as it is a more precise and confident method of determining concentration values.
You have also asked us to project the source material inventory as of July 1993. Our rates of ferrocolumbium production are projected to be reasonably constant. The projected amounts of ores to be processed through 1993 and the historical processing rates since 1989 are set forth in Attachment C. Based upon these rates, SMC projects to have a source material inventory of 269,000 kg of Th-232 and 33,000 kg of U-238 in July 1993.
If you have any questions, please do not hesitate to contact me.
Sincerely,
Craig d. Rieman Radiological Safety Manager
CRR: l m s Enclosures CC: Michael A . Finn '
Charles L. Harp, Jr. , Esq. Jay E. Silberg, Esq. Carol D. Berger, IT Betsy Ullrich, USNRC-Region I
ti' d
ATTACHMEW A -
FERROCOLUMBIUM SLAG LEACHABILITY REPORT
DECEMBER 1991
for
SHIELDALLOY METALLURIGAL CORPORATION Newfield, New Jersey
Prepare by
TELEDYNE ISOTOPES, Inc. Westwood, New Jersey
7WELEDWE ISOTOPES
4
Introduction
Shieldalloy Metallurgical Corporation (SMC) in Newfield. New Jersey is a specialty metals production facility, In one operation, columbium is extracted from ore containing naturally occurring uranium and thorium. Durtng the process uranium, thorium and decay products remain in the form of a hard slag. The slag piles are segregated from other materials based on the origin of the ore (ferro columbium, ferro vanadium) which is related to their residual radioactivity. The material is stored on-site as uncovered piles.
The Ieachability data of radioactive material in the FeCb slag was requested by the NRC. SMC contracted with Teledyne Isotopes to determine the leachable fraction of radionuclides in FeCb slag following American National Standards Institute/American Nuclear Society Standard 16.1 - 1986. "measurement of the leachability of solidifled low-level radioactive wastes by a short-term test procedure".
Sample Collection and Analysis
The slag at SMC is generated at a furnace in Building D- 1 1 1. Various ores are mixed together and placed in a large furnace which is heated by electric arc to temperatures of 2,000" C.. for several hours. When the reaction is complete, the furnace is then tilted allowing the slag to cascade down to two successive cast iron pots. The slag cascades from the first pot to the second, the metal or metal and slag remain in the first pot. To obtain samples four six inch by three quarters of an inch metal pipes were constructed and capped on one end. An eight foot length of reinforcing bar was welded to the middle of each pipe. During a "melt" 011 7/12/91 each of the four sampling pipes was briefly placed under the liquid metal stream to collect the slag and then allowed to harden. The following day the pipes were packaged and shipped to Teledyne Isotopes' Westwood laboratory.
The slag samples were removed from the collection pipes by passing a thin router bit down the length of the pipe on both sides in 1 / 16" depth increments. The pipe halves were then pried apart, leaving 3 of the 4 slag samples intact. Two samples were chosen for the leachability test. Both the samples and the pipe halves were rinsed with demineralized water, which constitutes the first sample required by the ANSI 16.1 standard. Each of the samples were then suspended in a one liter graduated cylinder using stainless steel wire. The surface area of each sample was 83.9 cm2 so. per the ANSI standard, 840 ml of leachate was used. The opening was covered with a polyethylene film and the leachate changed at the specified frequency for the duration of the three month procedure.
During each leachate change out. the temperature and conductivity of the leachate was measured. The temperature ranged from 20°C to 25°C. The electrical conductivity of the deionized water was 0.1 pmho. The leachate was transferred to a one liter plastic bottle and submitted to the radiochemistry lab at Teledyne Isotopes' Westwood. New Jersey laboratory for analysis of uranium and thorium by alpha spectroscopy and Ra-226 by emanation.
The third slag sample was crushed at SMC. to a 100 mesh grade and then returned to Teledyne Isotopes for the same analysis as the leachate. The values obtained from this analysis were used as Ao, the "initial" activity. This is a departure from the ANSI standard which assumes the activity of the waste stream is known prior to solidification. However, the sample volumes were small compared to the total volume for the "melt" and they were collected in rapid succession. Therefore, the activities between samples should be comparable.
December 16. 1991 Page 1 SMC Leachability Test
IPWELEWNE ISOTOPES
4
The results of the leachability test are provided in Appendix I. Radium-226, Uranium-234,235, 238 and thorium-228, 230, and 232 were analyzed in the leachate from two slag samples in accordance with the standard. A description of each column will be provided in this section. The importance of each of the three parameters, total leachability index, confldence range, and correlation coefficient will be detailed in the discussion section.
Column one specifies the leach interval. The full leach test was performed rather than the 5 day abbreviated test, as allowed by the standard.
Column two shows the leaching time in seconds as required for calculations. The leaching times were. consecutively, 2 hours, 7 hours, 17 hours then four 24 hour periods, 336 hours. 672 hours and 1.032 hours.
The third column gives the mean time of the leaching interval. Mathematical@ this is derived by Equation 2 in the ANSI standard. It is the midpoint of the cumulative leach time for a given interval. This parameter is used in the calculation of the dausivity.
The fourth column is the activity leached from the slag sample in the given time interval. The laboratory results in pCi/l are provided in Appendix 11. The results in column four have been adjusted from the lab report by 0.84 because the volume of leachate was 840 ml.
The initial activity, in column five, is the result of analysis on a slag sample obtained at the same time as the two slag samples in the leaching study. The laboratory results in Appendix II which are in pCi/g, were multiplied by the weight of the slag sample to give the total activity available for leaching.
Column six is the initial activity divided by the activity leached for each time interval as a percent. The release rate in column seven is the fraction of activity released per second of leach time. This column is important because it normalizes the Merent leaching times and indicates trends in the release rate of radioactivity.
The diffusivity appearing in column eight is calculated using Equation 1 in the ANSI standard. It is based on the incremental fraction of radioactivity leached. It is a two-dimensional variable because it assumes that the leaching of radioactivity is controlled solely by dfiusion. and the sample is a semi-infinite medium, i.e. there is no volume to the sample, only surface area.
The final column lists the leachability index for each time intewal, which will be averaged over all intervals for the total leachability index. This is a dimensionless number which must be compared to leachability indices from tests on different materials and isotopes in order to have any relevance.
The total leachability index and confidence range as well as the correlation coefficient, are given at the bottom of each page in Appendix 1. These values are calculated using equations 6, 8, and 10, respectively, iE the ANSI standard.
December 16. 1991 Page 2 SMC Leachability Test
ANSVANS-16.1 Leachability Test for Shieldalloy Metalurgical Corp. Slag 7WELEWNE lsoTopEs
Leach Leaching Mean Time of Activity Initial Fraction Released Release Rate Diffusivity Leachability interval Time (sec) Leaching Leached (pCi) Activity During Interval (fractionlsec) (cm sq/sec) Index
(n) (1) lntetvai (An) (PCi) (Ln) m (A01
1 7.2 E+03
2 1.8 E+04
3 6.1 E+04
4 8.6 E+04
5 8.6 E+04
6 8.6 E+04
7 8.6 E+04
8 1.2 E+06
9 2.4 E+06
10 3.7 E+06
Sample #: 001
1.8 E+03
1.5 E+04
5.1 E+04
1.3 E+05
2.1 E+05
3.0 E+05
3.9 E+05
9.4 E+05
2.7 E+06
5.8 E+06
*
. Weight: 11 3.3
Leachability: 0.99
29.4
58.8
142
252
142
69.8
60.5
151
118
200
0.14%
0.29%
0.70%
1.24%
0.70%
0.34%
0.30%
0.74%
0.58%
0.98%
i 2.00 E-07 0.006 2.247
1.60 E-07 0.037 1.429 c 1.14 E-07
1.44 E-07
8.09 E-08
3.98 E-08
3.45 E-08
6.17 E-09
2.41 E-09
2.65 E-09
0.092
0.284
0.272
0.188
0.21 0
0.091
0.103
0.240
1.037
0.546
0.565
0.726
0.677
1.041
0.987
0.620
Nuclide: Ra-226
Confidence Range: Correlation Coefficient:
0.20 to 1.78 0.31
Appendix I - Page 1
ANWANS-16.1 Leachability Test for Shieldalloy Metalurgical Corp. Slag 9WELEWNE ISOTOPES
Leach Leaching Mean Time of Acthrity Initial Fraction Released Release Rate Diff usivity Leachability Interval Time (e) Leaching Leached (pCi) Activity During Interval (fractionlsec) (cm sq/sec) Index
ANWANS-16.1 Leachability Test for Shieldalloy Metalurgical Corp. Slag WTELEWNE ISOTOPES
Leach Leaching Mean Time of Activity Initial Fraction Released Release Rate Dlffusivity Leachability Interval Time (sec) Leaching Leached (pCi) Activity During Interval (fractionlsec) (cm sq/sec) Index
ANSVANS-16.1 Leachability Test for Shieldalloy Metalurgical Corp. Slag
Leach Leaching Mean Time of Activity Initial Fraction Released Release Rate Diffusivity Leachability Interval Time (sec) Leaching Leached (pa) Activity During Interval (fractionlsec) (cm sq/sec) Index
(n) (1) Interval (An) (PW (Ln) cr) (Ao)
1
2
3
4
5
i 6
7
8
9
10
>
7.2 E+03 1.8 E+03
1.8 E+04 1.5 E+04
6.1 E+04 5.1 E+04
8.6 E+04 1.3 E+05
8.6 E+04 2.1 E+05
8.6 E+04 3.0 E+05
8.6 E+04 3.9 E+05
1.2 E+06 9.4 E+05
2.4 E+06 2.7 E+06
3.7 E+06 5.8 E+06
Sample #: 001
Weight: 11 3.3 Leachability: 2.1 7
0.08 1.36E+03 0.01%
1.18 1.36E+03 0.09%
0.81
0.48
0.16
0.17
0.17
0.69
0.19
16.8
0.06%
0.04%
0.01~/0
0.01%
0.01 %
o.05°/o
0.01 Yo
1.24%
Nuclide: U-238
Confidence Range: Correlation Coefficient:
8.17 E-09
4.82 E-08
9.76 E-09
4.10 E-09
1.37 E-09
1.45 E-09
1.45 E-09
4.23 E-10
5.82 E-11
3.34 E-09
1.02 0.44
0.000
0.01 1
0.008
0.008
0.005
0.007
0.009
0.006
0.002
0.303
to
3.636
1.951
2.105
2.090
2.337
2.163
2.053
2.205
2.604
0.51 9
3.31
(I'
(I
Appendix I - Page 4
ANSIIANS-16.1 Leachability Test for Shieldalloy Metalurgical Corp. Slag 7WELEWNE ISOTOPES
Leach Leaching Mean Time of Activity Initial Fraction Released Release Rate Diffuslvity Leachability Interval Time (sec) Leaching L-ached (pa) Activity During Interval (fradionlsec) (cm sq/sec) Index
(n) (1) Interval (An) (PCi) (Ln) m (Ao)
1
2
3
4
5
6
7
8
9
10
7.2 E+03
1.8 E+04
6.1 E+04
8.6 E+04
8.6 E+04
8.6 E+04
8.6 E+04
1.2 E+06
2.4 E+06
3.7 E+06
Sample #: 001
1.8 E+03
1.5 E+04
5.1 E+04
1.3 E+05
2.1 E+05
3.0 E+05
3.9 E+05
9.4 E+05
2.7 E+06
5.8 E+06
Weight: 1 13.3 Leachability: . 1.09
1.85
1.68
2.52
1.51
2.27
3.53
2.52
12.6
8.23
2.52
0.24%
0.22%
0.33%
0.20%
0.30%
0.47%
0.33%
1 .66"/0
1.08%
0.33%
Nuclide: Th-228
Confidence Range: Correlation Coefficient:
3.39 E-07
1.23 E-07
5.44 E08
2.31 E-08
3.48 E-08
5.41 E-08
3.86 E-08
1.38 E-08
4.52 E-09
8.97 E-10
0.38 0.28
0.01 0
0.029
0.044
0.046
0.117
0.256
0.235
0.204
0.193
0.081
to
2.01 9
1.544
1.359 c , ' 1.339
0.932
0.592
0.628
0.690
0.71 4
1.090
1.80
Appendix I - Page 5
ANWANS-16.1 Leachability Test for Shieldalloy Metalolrgical Corp. Slag 7WELEWNE ISOTOPES
Leach Leaching Mean Time of Activity Initial Fraction Released Release Rate Diffuslvlty Leachability Interval Time (sec) Leaching Leached (pCi) Activity During Interval (fractionlsec) (cm swsec) Index
Nuclide: Th-232 t ' Confidence Range: 0.84 to 2.28
Leachability: 1.56 Correlation Coefficient: 0.28
Appendix I - Page 7
ANSI/ANS-16.1 Leachability Test for Shieldalloy Metalurgical Carp. Slag WTELEUYNE ISOTOPES
Leach Leaching Mean Time of Activity Initial Fraction Released Release Rate Diffusivity Leachability Interval Time (sec) Leaching Leached (pCi) Activity During Interval (fractionlsec) (cm sqlsec) Index
(n) (1) Interval (An) (PW (Ln) m (Ao)
1 7.2 E+03
2 1.8 E+04
3 6.1 E+04
4 8.6 E+04
5 8.6 E+04
6 8.6 E+04
7 8.6 E+04
8 1.2 E+06
9 2.4 E+06
10 3.7 E+06
1.8 E+03
1.5 E+04
5.1 E+04
1.3 E+05
2.1 E+05
3.0 E+05
3.9 E+05
9.4 E+05
2.7 E+06
5.8 E+06
Sample #: 002
Weight: 11 1.6 Leachability: 0.98
17.6
40.3
109
134
160
168
92.4
227
104
200
2.01 E+04
2.01 E+04
2.01 E+04
2.01 E+04
2.01 E+04
2.01 E+04
2.01 E+04
2.01 E+04
2.01 E+04
2.01 E+04
0.09%
0.20%
0.54%
0.67%
0.80%
0.84%
0.46%
1.13%
0.52%
1 .OO%
Nuclide: Ra-226
Confidence Range: Correlation Coefficient:
1.22 E-07
1.11 E-07
8.89 E-08
7.75 E-08
9.26 E-08
9.72 E-08
5.35 E-08
9.41 E-09
2.16 E-09
2.69 E-09
0.02 0.37
0.003
0.026
0.071
0.153
0.31 1
0.460
0.326
0.139
0.092
0.244
to
2.464
1.587
1 A46
0.81 4
0.507
0.338
0.487
0.858
1.036
0.61 3
1.95
Appendix I - Page 8
ANSI/ANS-16.1 Leachability Test for Shieldalloy Metalurgical Corp. Slag 3e"TELnr/NE ISOTOPES
Leach Leaching Mean Time of Activity Initial Fraction Released Release Rate Dlffusivity Leachability Interval Time (sec) Leaching Leached (pCi) Activity During Intend (fraction/sec) (cm sq/sec) Index
ANWANS-16.1 Leachability Test for Shieldalloy Metalurgical Corp. Slag 7WELEWNE ISOTOPES
Leach Leaching Mean Time of Activity Initial Fraction Released Release Rate Diffusivity Leachability internal Time (sec) Leaching Leached (pCi) Activity During lntetval (fractionlsec) (crn sq/sec) Index (n) (1) Interval (An) (PCi) (Ln) m (Ao)
5.8 E + O ~ 0.67 2.01 E+02 0.33% 9.01 E-10 0.082 1.088
Weight: 11 1.6 Leachability: 1.79
Nuclide: U-235
Confidence Range: 0.81 to 2.77 Correlation Coefficient: 0.38
Appendix I - Page 10
ANSI/ANS-16.1 Leachability Test for Shieldalloy Metalurgical Corp. Slag miiTELEWNE ISOTOPES
Leach Leaching Mean Time of Activity Initial Fraction Released Release Rate Diffusivity Leachability Interval Time (sec) Leaching Leached (pCi) Activity During Interval (fractionkc) (cm sqlsec) Index
ANSIIANS-16.1 Leachability Test for Shieldalloy Metalurgical Corp. Slag WFldDYNE lsoTopES
Leach Lemching Mean Time of Activity Initial Fraction Released Release Rate Dlffusivity Leachability Interval Time (sec) Leaching Leached (pCi) Activity During Interval (fraction/sec) (cm sq/sec) Index
ANSIIANS-16.1 Leachability Test for Shieldalloy Metalurgical Corp. Slag '1WELEWNE ISOTOPES
Leach Leaching Mean Time of Activity Initial Fraction Released Release Rate Diffusivity Leachability Interval Time (sec) Leaching Leached (pCi) Activity During Interval (fractionlsec) (crn sqlsec) Index
(n) 0) Interval (An) (Pa) (Ln) cr) (Ao)
1 7.2 E+03 1.8 E+03
2 1.8 E+04 1.5 E+04
3 6.1 E+04 5.1 E+04
4 8.6 E+04 1.3 E+05
5 8.6 E+04 2.i E+05
6 8.6 E+04 3.0 E+05
7 8.6 E+04 3.9 E+05
8 1.2 E+06 9.4 E+05
9 2.4 E+06 2.7 E+06
I O 3.7 E+06 5.8 E+06
1.09
0.84
0.5
0.42
0.45
0.1 7
0.07
1.68
0.17
0.84
2.1 2E+02
2.1 2E+02
2.1 2E+02
2.1 2E+02
2.1 2E+02
2.1 2E+02
2.1 2E+02
2.1 2E+02
2.1 2E+02
2.1 2E+02
0.51 70
0.40%
0.24%
0.20%
0.21%
0.08%
0.03%
0.79%
0.08%
0.40%
Sample #: 002
Weight: 11 1.6 Leachability: 1.38
Nuclide: Th-230
Confidence Range: Correlation Coefficient:
7.14 E-07
2.20 E-07
3.87 E-08
2.30 E-08
2.47 E-08
9.32 E-09
3.84 E-09
6.60 E-09
3.34 E-10
1.07 E-09
0.94 0.1 7
0.020
0.051
0.031
0.046
0.083
0.044
0.023
0.097
0.01 4
0.097
1.695
1.291
1.507
1.341
1.081
1.356
1.631
1.01 1
1.845
1.01 3
to .1.82
Appendix I - Page 13
ANSIIANS-16.1 Leachability Test for Shieldalloy Metalurgical Corp. Slag WTELEUYNE ISOTOPES
Leach Leaching Mean Time of Activity Initial Fraction Released Release Rate Diffusivity Leachability Interval Time (sec) Leaching Leached (pCi) Activity During Interval (fractionlsec) (cm sq/sec) Index
(n) 0) Interval (An) (PCi) (Ln) (a) (Ao)
1 7.2 E+03
2 1.8 E+04
3 6.1 E+04
4 8.6 E+04
5 8.6 E+04
6 8.6 E+04
7 8.6 E+04
8 1.2 E+06
9 2.4 E+06
10 3.7 E+06
Sample #: 002
1.8 E+03
1.5 E+04
5.1 E+04
1.3 E+05
2.1 E+05
3.0 E+05
3.9 E+05
9.4 E+05
2.7 E+06
5.8 E+06
Weight: 11 1.6 Leachability: 1.66
0.08
0.5
0.25
0.34
0.34
0.25
0.17
0.76
1.68
0.84
3.46E+02
3.46E+02
3.46E+02
3.46E+02
3.46Ei-02
3.46E+02
3.46E+02
3.46E+02
3.46E+02
3.46Ei-02
0.02%
0.14%
0.07%
0.10%
0.10%
0.07%
0.05%
0.22%
0.49%
0.24%
Nuclide: Th-232
Confidence Range: Correlation Coefficient:
3.21 E-08
8.03 E-08
1.18 E-08
1.14 E-08
1.14 E-08
8.40 E-09
5.71 E-09
1.83 E-09
2.02 E-09
6.56 E-10
0.82 0.33
0.001
0.01 9
0.01 0
0.023
0.038
0.040
0.035
0.027
0.086
0.059
to
3.042
1.729
2.021
1.646
1.416
1.401
1.458
1.569
1.063
1.226
(T
c . 2.49
Appendix I - Page 14
SCOTT OENNERLEIN C / O TELEOYNE ISOTOPES INC 5 0 V A N BUREN AVE YESTWOOO N J 076
TELEOYNE SAHPLE CUSTOMER'S NUH8ER IOENT I F I C AT ION
TELEDYNE ISOTOPES
REPORT OF ANALYSIS RUN DATE 1 0 / 0 8 / 9 1
PAGE 1. WORK OROER NUH8ER CUSTOMER p e a . NUMBER DATE RECEIVE0 DELIVERY DATE
3 -3141
W A T E R
COLLECTION-DATE STA START STOP NUM OAT€ TIME DATE T I P € NUCLIDE
WORK OROER NUMBER CUSTOMER P o 0 0 NUMBER DATE RECEIVED DELIVERY DATE PAGE 2
6 6
SCOTT OENNERLEIN 3-3141 C / O TELEOYNE ISOTOPES INC 50 VAN BUREN AVE WESTWOOO N J 0 7 6 7 5
1
0 8 / 1 2 / 9 1 09/ 1 4 1 9 1
H A T E R
TE UEDY NE COLLECTION-DATE H IO-COUNT SAMPLE CUSTOMER'S STA START STOP ACTIV ITY NUCL-UNIT-% TIME VOLUME - UNITS NURBER XOENTIFICATION NUM DATE TIME DATE T IPE NUCLIOE t P C I l L I T E R ) U/H * O A T € TIHE ASH-WGHT-X * LAB.
47;:O OOISMCSLAC T 48H SH A LLOY / 0 8 / 0 7 085ORA-226 U-234 TH-230
l O I O 7 09 /18 0 9 / 1 6 09/10 0 9 / 1 8 09/16 0 9 / 1 6
: c 6
6 6 6
6 6 6 6
2 ~
6 6 6 6 6
6 c 2 6 6 6 6 6 6
TELEOYNE I S O T O P E S
REPORT nF A N A L Y S I S RUN D A T E I O / l € l t 9 1
WCRK ORDER NUMBER CUSTOHER P o 0 0 NUMBER O A T € R E C E I V E D D E L I V E R Y O A T € PACE 1
SCOTT O E N N E R L E I N 3-3403 08/29/91 10/01/91 C / O T E L E O Y N E I S O T O P E S I N C SO V A N BUREN A V E u E s T n a o o N J 01615
W A T E R
M IO-COUNT T F L E D Y N E COLLECTION-DATE SAMPLE CUSTOMER'S S T A START STOP A C T I V I T Y NUCL-UNIT-% T I M E VOLUME - U N I T S NUMBER I O E N T I F I C A T I O N NUN D A T E T I M E OAT€ T I R E N U C L I O E t P C I t L I T E R ~ U /M * DATE T I W E ASH-YCHT-X * LAB.
494S5 O O I S H C S L A C T - 3 3 6 H SMA L L O Y ! 08/23 0840RA-226 1.8 *-0.1 E 02 U-234 LIT. 1. E-01 T H - 2 3 0 L O T O 1. E 00 U - 2 3 5 L O T O 3 r E - 0 1 U-231 LOT. 1. E-01 TH-232 LOT. 9. Em01 TH-228 1-5 +-0.3 E 01
09116 10106 lot14 lO/O6 10/06 10114 10/14
: c 6
6 6 6 6
L A S T PACE OF REPORT /A&-- APPROVED B Y .k CUENTHER 10/18/91
SEND 1 C O P I E S TO T E 5 0 9 2 SCOTT O E N N E R L B I N
2 -. C A S LAB. 3 - R A O I O C H E M I S T R Y LAB. 4 - G E t L I P GAMMA SPEC LAB. 5 - T R I T I U M GAS/L.S. LAB. 6 - A L P H A SPEC LAB.
c
.
TELEDYNE I S O T O P E S
REPORT OF A N A L Y S I S RUN DATE 1 1 / 1 2 / 9 1
WORK ORDER NUM8ER CUSTOMER P.0. NUMBER DATE RECE I V E D D E L T V F R Y DATE PAGE 1
S C O T T O E N N E R L E I N 3 - 3 7 2 8 0 9 / 2 0 / 9 1 1 O / 7 3 / 9 1 C / O T E L E O Y N E I S O T O P E S I N C 5 0 V A N BUREN AVE YFSTWOOO N J 07675
N A T E R
TEL EDY NE COLLECTION-DATE SAMPLE CUSTOMER'S STA START STOP A C T I V I T Y NUCL-UNIT-% NUMBER I D E N T I F I C A T I O N NUN O A T € TIHE DATE T I R E N U C L I D E I P C I / L I T E R ) U/H * 51776 0 0 1 5 M C S L A C 1 - l l 2 b H SH 0 9 / 2 0 0 8 3 5 R A - 2 2 6 104 +-001 E 0 2
U-234 1.7 4-1.2 E - 0 1 TH-230 L O T O 3. E - 0 1 U-235 LOT. 7. E - 0 2 U - 2 3 8 L O T O 1. E - 0 1 T H - 2 3 2 L O T O 3. E - 0 1 TH-228 9.8 + - l e 0 E 00
HID-COUNT T I M E
DATE TIME
10/17 1 0 / 2 8 1 0 / 2 8 1 w z s 1 0 1 2 8 10/28 10/28
VOLUME - U N I T S ASH-WCHT-% * LAB.
2 4 c 6 6 6 6 6
LAST PAGE OF REPORT
SEN0 1 C O P I E S TO TE5092 SCOTT D E N N E R L E I N
9 ? b d b APPROVE0 BY GUENTHER 1 1 / 1 2 / 9 1
2 - G A S LAB. 3 - R A D I O CHEHSSTRY LAB. 4 - G E t L I t GAHHA SPEC LAB. 5 - T R I T I U M GAS/LoS* LAB, 6 - ALPHA SP€C LAB*
RUN DATE 1 0 / 0 8 / 9 1
TELEOYNE ISOTOPES
REPORT OF ANALYSIS
1 1 WORK OROER NUMBER CUSTOMER
SCOTT OENNERLEIN 3 -3141 C / O TELEOYNE ISOTOPES INC 50 VAN BUREN AVE WFSTWOOO N J 0 7 6 7 5
W A T E R
TELEDYNE COLLECTION-OATE sAnPL E CUSTOHFR'S STA START STOP NUMBER IOENTIF ICATION NUH OAT€ TIHE DATE T I P € NUCLIOE
ACT1 V I TY NUCL-UNI 1-% ( P C I / L I T E R I U/M * 1.6 +-Om1 E 0 2 L O T O 3. E-01 L.T. 5. E-01 L I T . 2. E-01 L.T. 3. E-01 LOT. 4 0 E-01 2.5 +-Om9 E 00
1.9 +-0.1 E 0 2 LOT. 1. E 00 5.3 +-4.3 E-01 LOT. 5. E-01 LOT. 9. E-01 L.T. 4. E-01 3.0 4-0.9 E 00
2.0 +-0.1 E 0 2 L.T. 5. E-01 LOT. 2. E -01 LOT. 3. E-01 L O T O 5. E-01 L.T. 3. E-01 1.7 +-0.9 E 00
1.1 +-0.2 E 0 2 LOT. 2. E-01 L O T O 8 0 Ea02 L.T. 7. E-02 3.1 + - l o 8 E-01 2.0 + - l o 1 E-01 3.9 +-0.5 E 00
2 - G A S LAB. 3 - RADIO CHEMISTRY LAB. 4 - G E I L I I GAMMA SPEC LAB. 5 - TRIT IUM CAS/L.S..LAB. 6 ALPHA SPEC LAB.
TELEOYNE ISOTOPES
REPORT OF A N A L Y S I S RUN OATE 10/10/91
VCRK OROER NUMBER CUSTOMER P.0. NUMBER OATE R E C E I V E 0 D E L I V E R Y OATE PACE 1
10/01/91 SCOTT DENNE'RLEIN 3-3403 01/29/91 C / O TELEOYNE ISOTOPES I N C SO VAN BUREN AYE UESTUOOO W J 0 7 6 ~ s
W A T E R
TEL EDY NE COLLECTION-OAT€ MIO-COUNT A C T I V I T Y NUCL-UNIT-% 1 IRE VOLUMF: - UNITS SAMPLE CUSTOMER*S I T A START STOP
N W B E R I O E N T I F I C A T I O N NUH OAT€ T I M E OAT€ T I M E NUCCIDE ( P C X f L I T E R I U f M 9 OAT€ T I P € ASH-UCH1-X 9 LAB.
O W 23 OOS'IRA-226 0-234 T H - 2 3 0 U-235 U-23R T H - 2 3 2 T H - 2 2 1
LAST PACE OF UEPORT
SEND 1 C O P I E S TO T E S 0 9 Z SCOTT DENNERLEIN
2.7 +*O-1 E 0 2 LOT. 2. €-OF LOTO 21 E 00 LOT. 2 1 E - Q l L.T. 2. E-OP LOT. 2. E 00 L.T. 9. E 00
091 16 10106 10/14 10/06 10/06 IO/ 14 IO/ 14
3n-A- APPROVE0 BV CUENTHER IOfl~/91
2 - GAS LAB. 3 - U A O I O CHEMISTRY LAB. ' 4 - CE(L1) C IMMA SPEC LAB- 5 - T R I T I U R CAS/L.S. LAB. 6 ALPHA SPEC LAB.
TELEDYNE 1,SOTOPES
REPORT OF & N I L I S I S
WORK ORDER NUW0ER CUSTONER ?rOo MUWEA
f C @ T T OENNEPLEIN 3-372P C / r ) TELEDYNE ISOTOPES INC 5 0 V A N BUQEN AYE YFSTYOOD N J 07675
W A T E R
'TFLEOYNE COLLECT ION-DATE ' 5 AMPLE CUST0NER.S STA START STOP ACT I V 1 TY *NUMBER I D E N T I F I C A T I O N NUN OAT€ T I M E OAT€ T I H E NUCLIDE f P C I l L I T E R l
* R W OAT€ 11/12/91
PACE 1 OITE RECE IVEO DEL i w e y DATE
O W 2 0 1 91 10/?3/91
' HID-COUNT W C L - U N I T - t T I M E VOLURE - UNITS
U IH DATE T IME ASH-YCHT-I * LAO.
51779 OOZSMCSLAG T=ll2IH SH i
09/20 OI5ORA-226 1 - 2 +-0.1 E 02 U-234 L O T O 6. E-01 TH-230 L I T . 2. E-01 U-235 L i f e 3- E-01 U-238 LOT. 4. E-01 TH-232 4.8 +-2-5 r-01 TH-22 I 1.2 +-O.I E 01
LAST PAGE OF REPORT
SEND 1 COPIES TO TE509Z SCOTT DENNERLEIN
2 - GAS LAB- 3 - R A O I O CHEHISTRY LAB. 4 - C E f L f B 6AHMA SPEC LAB.
lo/ 1 lo/ 2 11/06 10/29 1 O/ 29 11/06 11 106
__ ~
ATTACHMEm B
LJ SOURCE MATERIAL INVENTOR> October 1991
FeCb Slas Pile
volume Density Mass
17,875 m3 (a) 2,740 kg/m3 (b)
48,977,500 kg
U-238 Th-232
48,977,500 kg 48,977,500 kg
230,194 kg 29,387 kg X 0.47% Th-232 by mass (c) x 0.06% U-238 by mass (c)
Lime Pile
Volume Density Mass
13,576 m3 (dJ 2 , 740 kg/m
37,198,240 kg
U-238 Th-232
3 7,19 8 , 2 4 0 kg 37,198,240 kg 17,000 kg 1,860 kg X 0.046% Th-232 by mass (c) x 0.005% U-238 by mass (c)
InventorvlWork in Process (181,436 kql
Th-232 U-238
181,436 kg x 0.5% Th-232 by mass (e)
18 1,4 3 6 kg x 0.04% U-238 by mass (e)
907 kg 73 kg
Total
U-238 Th-232
248,000 kg 31,300 kg
FOOTNOTES
(a)
(b) (c)
GEOD measurement corrected by 20% per ORAU Radiological Survey (7/88 and Geotechnical Enqineerinq Investiqation Manual, McGraw Hill, 1984 Analysis provided by SMC laboratory. A mean average of analytical data provided in ORAU's 7/88 Radiologica Survey. GEOD measurement corrected by 10% per Geotechnical Enqineerini Investiqation Manual, McGraw Hill, 1984. Analytical analysis provided by SMC, 9/91.
**********t*~***************************~**************~* SAMPLE IDENTIFICATION IS 65021-018 SAMPLE: VOLUME IS 729 GMS SAMPLE COWNT TIME IS 35080 SEC S A P L E TYPE IS MARINELLI SAMPLE MATRIX
. Ra226* AT 0,186 MEV 5 . 3 + /- .3498 . 4 ~ w a ~ .Ac228** AT 0 . 9 1 1 MEV 5 . 9 + /- . 110 9.02294IE-02
* URANIUM SERIES(U238) / ** THORIUM SER-?ES(TWSZ> T U 3 4 PHOTOPEAKCO. 093) ELEVATED DUE TO Ac228 (0.09331
NUCLIDE AND ENERGY pCi/grarn MDAC (pCi/grn)
TU%* AT 0.093 MEV 15 + /- .705 .972412Q -7205901 Ra226* AT 0.186 HEY 6.2 + /- ,5208
A ~ 2 2 8 * * AT 0.911 MEV 9 . 5 8 +/- . 17244 ,327691 Ac228** AT 0,869 MeV 8.87 t/- ,29271 .3060597 K4 0 AT 1.460 MEV 1.5 + /- ,318 -3772496
j: URANIUM SERIES (U2S8) 1 ** TffORIOM SERIES (Th232) TU34 PHOTOP-EAK(D.093) ELEVATED DUE TO A d 2 8 ( 0 . 0933)
.'
'4 DATE OF REPORT: 12-12-1991
i /
HILBERT ASSOCIATES, INC.
x***********X***************************************~********** RADIOACTIVITY CONCENTRATIONS AND MDAC VALUES
SHIELDALLOY METALLURGICAL CORPORATION, NEWFIELD, NJ O ~ U ~ ~ t 9 ~ t X X X t ~ k ~ t X X x ~ * x x ~ x ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ x ~ ~ ~ ~ x ~ ~ ~ * ~ ~ x ~ ~ ~ ~ ~ ~ x ~ ~ * * *
FOR
**~****X*****X*********************************~X****~*** SAMPLE IDENTIFICATION rs 65021-OIC SAMPLE VOLUME IS 773 GMS SAMPLE COUNT TI.ME IS 5013 SEC
' SAMPLE TYPE IS MARINELL1 SAMPLE MATRIX t ~ * X X X ~ * X ~ ~ t X X * X x ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ x * ~ ~ ~ ~ ~ ~ ~ ~ x x ~ ~ ~ ~ ~ x * x * ~ ~ ~ ~ ~ ~ ~
NUCLIDE AND ENERGY pCi /cxm MDAC (pCi/gm) Th234* AT 0.093 MEV 13.9 +/- 1,4456 2.000771 Ra22W AT 0.186 MEV 5.3 +/- 1.1448 1.593831. Ac228** AT 0.311 MEV 10.3 +/- ,3811 .2612862 A~228** AT 0.969 MEV 9.59 +/- .56581 .5498742 E4 Q AT 1.460 MEV 2.2 -k /- .616 .67218
* URANIUM SERIES (U238) / ** THORXTJM SERIES (TU321 TU34 PHOTOPEAK(O.093) ELEVATED DUE TO Ac228 (0.0933)
*****~t**T***********x*~********************************* SAMPLE IDENTIFICATION IS 65021-011) SAMPLE VOLUME IS 736 GMS
SAMPLE TYPE IS HARINELLI SAMPLE MATRIX ******************************************~***~**~~***~~* NUCLIDE AND ENERGY PCi/gram M)AC (pCi i 8 n )
SAMPLE COUNT TIME IS m e 9 SEC
TM34* AT 0.093 MEV 14.2 + I - 1.4484 2'082673 Ra226* AT 0.186 MEV 6 . 3 +/- 1.1277 1.560448 Ac228** AT 0.911 MEV 9.8 4.1- .3724 ,2634688 Ac228** AT 0.969 MEV 9.62 +/- 155796 .5159991 K4 0 AT 1.460 MEV 2.3 + /- .667 .7[365353
* URANIUM SERIES (U238) / ** THORIUM SERIES (Th232) T U 3 4 PHOTOPgAK(D. 093) ELEVATED DUE TO Ac228 ( 0 . 0 9 3 3 )
DATE OF RBPQRT: 12-19-183i HILBERT ASSOCIATES, rNc. * * * t * X X * X * * * * * X * * * x * * ~ x * * * * * * * * * * * * * * * * * ~ * ~ * * * ~ * * * * * * * * ~ * * * * * ~
FOR SHIELDALLOY METALLURGICAL CORPP9RATION, NEWP IEL3, NJ
*****Y~~***************x***~***~***x*************~**~~*** SAMPLE IDENTIFICATION IS 65021-02C SAMPLE VOLUME IS 723 GMS SAMPLE COUNT TIME IS 2002 SEC SAMPLE TYPE IS MARINELLI SAEPLE MATRIX
Th234* AT 0.063 MeV 4.1 +/- 3.69 5 . 3 5 8 198 Th234* AT 0.093 MEV 10.2 +/- 2.754 3 684395 Ra2266* AT 0.186 MET: 9 . 5 +/- 1 . 7 1 2,194479 Ac228%* AT 0.911 HEV 4 . 6 7 1- , 506 .5182858 Ac228** AT 0.969 MEV 4 . 4 .t 1- .66 ,7057816
* URANIUM SERIES (13236) / ** THORIUM SERIES (Th232) TU34 PROTOPEAK(D.093) ELEVATED DUE TU Ac228 (0. 09331
*******k~M*t*~~**********~*~*******~****~~*~*******X***** SAHPLE IDENTIPICATZON IS 65021-02D SAMPLE VOLUME IS 392 GMS SAMPLE COUNT TIME IS 2005 SEC. SAMPLE TYPE IS MAR XNELL I SAMPLE MATR XX
SAMPLEl TYPE IS MARINELLX SAMPLE MATRIX ~ ~ ~ X ~ X Y X 1 X I I X ~ ~ ~ I ~ ~ X ~ ~ * ~ ~ X X ~ ~ ~ ~ ~ ~ Y * ~ ~ X * ~ ~ ~ ~ ~ ~ ~ ~ X ~ ~ ~ ~ X ~ X ~ ~
SAMPLE COUNT TXME IS zoo2 SEC
NUCLIDE AND ENERGY pC i /gram MDAC I p C i I m ) . Th234x AT 0.063 MEV 3 +/- 2.97 5.781175 Th234* AT 0.093 MEV 3 +/- 2.97 4.287681 Ra2266* AT 0.186 MEV 6 , l +/- 1.83 2.456221
Ac220** AT 0.969 kEV 7 + /- . a4 .8697483 * URANIUM SERIES (U238) / ** THORfDM SERIES (Th292) TU34 PHOTOPEAKCO. 093) ELEVATED Due TO Ac226 (0.0933)
Ac228** AT 0.911 WV 6 . 5 + /- .65 .5417445
****x****x**x*~~*~***~*******~*x**********x**x*~**~*$**** SAMPLE IDENTIFICATION IS 65021-03B SAMPLE VOLDMX IS 699 GMS SAWLE COUNT TIME IS 2002 SEC SAMPLE TYPE rs MARINELL1 SAMPLE MATRIX
***************+**************~*****~************~***~**~ SAHPLE IDENTIFICATION IS 65023-03C SAMPLE VOLUMg IS 753 GM'S SAMPLE: COUNT TIME IS 2003 SEC SAMPLE TYPE IS MARINELLI SAMPLE MATRIX
Y * ~ ~ Y * ~ ~ ~ * * * x X X ~ ~ t ~ x x ~ ~ ~ ~ ~ ~ ~ ~ ~ x ~ ~ ~ ~ ~ ~ ~ ~ * ~ ~ ~ ~ ~ ~ * ~ ~ ~ x ~ ~ ~ ~ ~ x
NUCLIDE AND ENERGY pCi/gram
Th234* AT 0.063 MEV 3 . 3 3.1- 3.267 5.294736 TM34* AT 0.093 MEV 2.3 +/- 2.277 3.9498 13 %2266* AT 0.186 HEV 4.7 ' +I- 1.739 2.299633 Ac228** AT 0 . 9 1 1 HEv 6.5 + 1- . 5 2 . 4 17 1694 Ac22B** AT 0 . 9 6 9 n5V 6.8 + /- .748 . $127191
* URANIUM SERIES (0238 1 / ** THORIgM SERIES ITh232) TU34 PHOTOPEAK(0. 093) ELEVATED DUE TO Ac228 (0.0933)
* * X X X * ~ Y X ~ * W I ~ * * ~ * ~ X ~ ~ ~ ~ ~ ~ x ~ x ~ ~ ~ * ~ ~ ~ ~ ~ x ~ ~ ~ ~ ~ ~ ~ x ~ x ~ ~ ~ ~ x x ~ ~ SAMPLE IDENTIPICATION IS 65021-03D SAMPLE VOLUME IS '634 GMS SAMPLE COUNT TIME IS 2003 SEC SAMPLE TYPE IS MARINELLI SAMPLE MATRTX
SAMPLE IDENTIFICATION IS 65021-04B SAMPLE VOLUME IS 680 GMS SAMPLE COUNT TIME IS 2004 SEC SAMPLE TYPE IS MARINELLI SAMPLE MATRIX
... .
NUCLIDE AND ENERGY
TU%* AT 0. 063 MEV ThZ34* AT 0. 093 MEV Ra2266.u: AT 0. 186 MEV Ac228** AT 0.911 MEV Ac228W AT 9 . 9 6 9 MEV
2.8 12.2 6 9 . 8 a, 5
2.772 2.684 1 . 9 8 .588 1.02
MDAC (PCi/gm)
5.973907 3.774364 2.721814 .. 4913207 I- 131047
* URAN.IUM SERIES (U238) / ** THORIUM SERIES (Th232) TU34 PHOTOPEAK(O.083) ELEVATED DUE TO Ac228CO.0833)
DATE OF REPORT: 12-19-1991 HILBERT ASSOCIATES XNC, ~ x I x x x Y Y ~ x x x x I x ~ x x x Y ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ x ~ ~ ~ ~ * ~ ~ ~ ~ ~ ~ x ~ ~ ~ ~ ~ ~ x ~ x ~ ~ * ~ x x ~ x ~ ~ ~
* URANIUM SERIES (0238) 1 ** THORIUM SERIES (Th232) TU34 PHOTOPEAK(O.093) ELEVATED DUE TO Ao228 ( 0 . 0 9 3 3 )
P t X X ~ x ~ t ~ X m X ~ t * X I ~ S O ~ ~ x ~ ~ ~ ~ * * ~ ~ ~ ~ ~ z ~ x ~ ~ x ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ x ~ ~ ~ ~ SAMPLE IDENTIFICATION IS 650231-041) SAKE'LE VOLUME IS 604 GIG S W L B COUNT TIME IS 20045 SEC SAWLE TYPE IS MARlffELSI SAHPL,E MATRIX
