ML20211P294
| ML20211P294 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 05/31/1986 |
| From: | Deming E OAK RIDGE ASSOCIATED UNIVERSITIES |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20211P286 | List: |
| References | |
| CON-FIN-A-9076-3 27206, NUDOCS 8607230086 | |
| Download: ML20211P294 (44) | |
Text
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Prepared by Oak Ridge Associated RADIOLOGICAL MONITORING U niversit,es i
Prepared for O
U.S. Nuclear Regulatory I
commission, STACK EFFLUENTS Region II Office Supported by GENERAL ELECTRIC COMPANY g
Safeguards and len*c'i"'9'**
WILMINGTON, NORTH CAROLINA t
n.
I Division of Inspection Programs; Office of Inspection and E. J. DEMING Enforcement I
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I Radiological Site Assessment Program Manpower Education, Research, and Training Division ll FINAL REPORT l3 MAY 1986
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- I 8607230086 860624 DR ADOCK 0700 3
RADIOLOGICAL MONITORING OF STACK EFFLUENTS GENERAL ELECTRIC COMPANY WILMINGTON, NORTH CAROLINA Prepared by E.J. DEMING Radiological Site Assessment Program Manpower Education, Rcsearch, and Training Division Oak Ridge Associated Universities Oak Ridge, Tennessee 37831-0117 q
Project Staff J.D. Berger F.T. Lange R.D. Condra A.D. Luck G.R. Foltz C.F. Weaver Prepared for Safeguards and Materials Program Branch Division of Inspection Programs U.S. Nuclear Regulatory Commission Region II Office FINAL REPORT May 1986 This report is based on work performed under Interagency Agreement DOE No. 40-816-83 NRC Fin. No. A-9076-3 between the U.S.
Nuclear Regulatory Commission and the U.S.
Department of Energy.
Oak Ridge Associated r
Universities performs complementary work under contract number
(
DE-AC05-760R00033 with the U.S. Department of Energy.
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TABLE OF CONTENTS Page List of Figures.
11 List of Tables iii Introduction I
Site Description and Information J
Survey Procedures.
2 Results.
5 Discussion of Resulto.
7 Semmarx..............................
e h
References 34 Appendices Appendix A: Major Sampling & Analytical Equipment Appendix B: Analytical Procedures i
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LIST OF FIGURES
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FIGURE 1: Map of Wilmington, N.C. Area Indicating the Location of the General Electric Company Facility..........
11 FIGURE 2: EPA Standard Method 1 Criteria for Performing Air Velocity Measurements in Circular Ducts...
12 FIGURE 3: Diagram of a Typical Particulate Air Stack Sampling System 13 FIGURE 4: Diagram of the Stack Sampling System Incorporating an
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Andersen Fractionating Particle Sample 14 FIGURE 5: Typical Particle Size Distribution of Andersen l
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Fractionating Particle Sampling from Stack FURN0556...
15 FIGURE 6: Typical Particle Size Distribution of Andersen Fractionating Particle Sampling from Stack CHMN0541...
16 FIGURE 7: Typical Particle Size Distribution of Andersen Fractionating Particle Sampling from Stack
(
CKMSFMOX(546X) 17 FIGURE 8: Typical Particle Size Distribution of Andersen
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Fractionating Particle Sampling from Stack REDCAP 70...
18 FIGURE 9: Typical Particle Size Distribution of Andersen Fractionating Particle Sampling from Stack INEXBURN..
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.__________.______o___._.___
E LIST OF TABLES i
l Page TABLE 1: Velocity Profiles in Exhaust Ducts 20 E
TABLE 2: Stack Sampling Flow Rates and Volumes 23 TABLE 3: Results of Stack Monitoring - Stack GAD 02018.......
25 TABLE 4: Results of Stack Monitoring - Stack POWS 0562.......
26 TABLE 5: Results of Stack Monitoring - Stack FURN0556.......
27 TABLE 6: Results of Stack Monitoring - Stack REDCAP 70.......
28 TABLE 7: Results of Stack Monitoring - Stack CLABEAST.
29 TABLE 8: Results of Stack Monitoring - Stack CHMN0541....... 30 TABLE 9: Results of Stack Monitoring - Stack CHMSFMOX(546x).... 31 TABLE 10: Results of Stack Monitoring - Stack INEXBURN.
' 32 TABLE 11: Results of Stack Monitoring at CHMSFM0X(546x) and CHMN0541 Using K CO3 Treated Filters 33 2
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RADIOLOGICAL MONITORING I
^
0F STACK EFFLUENTS l
GENERAL ELECTRIC COMPANY WILMINGTON, NORTH CAROLINA N
INTRODUCTION The General Electric (GE) Company's Nuclear Fuel and Special Products Division located in Wilmington, North Carolina, is licensed by the Nuclear l
Regulatory Commission (NRC) to fabricate uranium fuel for commercial reactors.
Operations involved in fuel fabrication have the potential for releasing radioactive material to the environment, and the licensee has the responsibility of insuring that all radioactive releases are within established regulatory guidelines for radiation protection.
To satisfy this requirement, GE has established a monitoring program to evaluate radioactive discharges.
The NRC periodically reviews such programs as a part of the continuing regulatory and inspection process.
At the request of the Nuclear Regulatory Commission, Region II Office, the Radiological Site Assessment Program (RSAP) of Oak Ridge Associated Universities (ORAU) performed independent monitoring of stack effluent releases at the GE - Wilmington plant during the period September 16-26, 1985.
This report presents the procedures and results of that survey.
SITE DESCRIPTION AND INFORMATION The GE Nuclear Fuel and Special Products Division plant is located in southeastern North Carolina, approximately 10 km north of Wilmington, North Carolina, on U.S. Highway 117 (Figure 1).
The site is bounded on the west by the North East Cape Fear River.
General Electric's fuel fabrication operations utilize uranium in a variety of chemical
- forms, including uranium hexafluoride, uranium (U 0s and tetrafluoride, uranium oxides UO ),
ammonium diuranate, uranyl 3
2 nitrate and uranium tetrox.
The U-235 content in the uranium ranges from depleted to approximately 4%, with an average enrichment of about 2%.
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l Operations having a potential for generating airborne radioactive material are conducted under exhaust ventilation conditions.
There are two major types of ventilation systems - dry filter and
- wet scrubber systems.
About 40 dry systems service such operations as grinders, presses and powder preparation.
These systems are equipped with prefilters at the process location and pre-and HEPA filters before final stack discharge.
There are 3 wet systems consisting of 3-stage wetted filters, demisters, reheaters, and pre-and HEPA filters. These three systems are equipped with redundant filter and blower units to permit continued operation during a filter change. A low level waste incinerator also utilizes a wet scrubber system, which includes a L
quencher, venturi scrubbe r, packed column, demister, reheater, and pre-and HEPA filters.
u All systems are continuously monitored by GE using single point pro bes.
The sampling rate is approximately (+ 20%) isokinetic.
Sampling is primarily for particulates, which are collected on HV-LB 5211 fiber filters.
Scrubber exhausts are also sampled for fluorides using calcium carbonate treated filters.
Samples are replaced daily or weekly, depending upon the emissions history of the system.
SURVEY PROCEDURES Objective The objective of the survey was to characterize stack effluents with regard to concentrations, isotopic composition and particle size distributions. The resulting information was compared to measurements made by CE, to evaluate the adequacy and. accuracy of the licensee's monitoring procedures.
{
Procedures The survey was performed during September 16-26, 1985, in accordance with a plaa approved by the Eegion II Of fice of the NRC.
Stacks were selected for monit,:, ring by Oak Ridge Associated Universities, based on emissions data prorided by the licensee.
The six stacks listed below wae identified as I
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routinely contributing significant fractions of the total plant air emissions and were selected for monitoring.
f 1.
CRMN0541 2.
FURN0556 3.
GAD 02018 4.
REDCAP 70 L
5.
CRMSFM0X(546x) 6.
INEXBURN Additionally, two systems with lower potentials for emissions (CLABEAST and POWS 0562) were monitored.
L Three systems (INEXBURN, CHMSFM0X(546x) and CHMN0541) utilize wet I
scrubber systems; the remainder of the stacks utilize dry filter systems.
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1.
Holes (approximate 40 mm diameter) were drilled in the selected stacks (except INEXBURN) by GE personnel, to provide access for measuring air flow and inserting sampling probes.
(INEXBURN already had two existing l
ports available for sampling so no additional holes were.necessary.) Two holes were drilled at right angles to each other in each of the stacks at locations far enough from transitions or bends to minimize distortions in flow pattern.
Because of its. large diameter, four holes were drilled in f
CHMN0541 to provide access across the entire diameter of the stack.
2.
A pitot tube and Alnor velometer were used to measure velocity distri'oution. Preliminary velocity measurements were made through direct velocity traverses at the section chosen for sampling, to detect any significant air flow variations. Measurements were made at predete'rmined distances in each of the stacks based on recommendations found in EPA Standard Method #1.I (Figure 2 summarizes the criteria for selection of air flow measurement locations in circular ducts.)
3.
Velocity distribution measurements and calculations of corresponding nozzle diameter sizes were performed to determine appropriate flow rates for isokinetic sampling.
The nozzles were connected to probes supported 3
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by metal plates which were held in position on the stack by flexible-straps. Velocity profiles for each stack are presented in Table 1.
The I
flow rates determined for each stack sampling location were in the range of 7.69 to 18.4 1/m.
4.
Two sampling probes were installed in each of the stacks.
One probe was maintained at a fixed location and the other probe was repositioned daily to evaluate possible differences in concentrations at various locations in the duct. A typical sampling train is diagramed in Figure 3.
5.
Andersen Fractionating Particle Samplers were installed at CHMN0541, I
INEXBURN, FURN0556 REDCAP 70, and CHMSFM0X(546x) for detercination of particle size distribution.
Samples were collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with a flow rate of 28.3 1/m (Figure 4).
6.
Following installation of the probe assemblies and connection of the vacuum, control and measurement equipment, the air flow in each probe was adj usted to the calculated isokinetic sampling rate.
Times and flow I
rates were recorded; periodic checks of the flow rate were made to assure that the de: ired campling rate was being maintained.
Flow rates and E
g sample volumes are summarized in Table 2.
7.
The majority of the samples were collected on 0.8 um millipore particulate filters; Andersen Fractionating Particle Samplers utilized g
glass fiber filter media.
At two locations, (CHMN0541 and CHMSFMOX(546x)) potassium carbonate treated filters were also used for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in conjunction with particulate filters to measure levels of I
uranium fluorides.
Large amounts of condensed moisture in the sampling line from stack INEXBURN necessitated repeat sampling using a Whatman #1 filter.and on in-line liquid collection flask.
This - prevented the system from becoming clogged, thereby allowing an isokinetic sampling rate to be maintained.
8.
It was the intent of the survey plan that the ORAU sampling times would I
duplicate chose of the licensee.
However, it was necessary to terminate the ORAU sampling one day earlier than planned, due to severe weather I
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(hurricane) conditions in the Wilmington area.
Stacks were sampled for the following time periods:
CHMSFM0X(546x)-3 days; C100iO541-3 days; GAD 02018-6 days; POWS 0562-6 days; FURN0556-6 days; REDCAP 70-6 days; INEXBURN-1 day; and CLABEAST-6 days. In addition, stacks CHMSFMOX(546x),
CHMN0541, INEXBURN, FURN0556 and REDCAP 70 were sampled for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> using
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Andersen Fractionating Particle Samplers.
Sample Analyses and Interpretation of Results 4
Samples were returned to Oak Ridge for analysis.
Gross alpha concentrations were determined for all of the particulate filters and the water sample.
Alpha spectrometry for isotopic uranium concentrations was i
performed on the samples from FURN0556.
(This was the only sample with sufficient activity to enable such measurement.)
In addition, alpha spectrometry was performed on the liquid sample collected from INEXBURN.
Particle size distributions were determined for samples from CHMSFM0X(546x),
- CHMN0541, INEXBURN, FURN0556 and REDCAP 70, based on Andersen sampler information.
Additional information concerning analytical equipment and procedures can be found in Appendices A and B, respectively.
Results were compared to the monitoring data developed by the licensee' for the same or comparable time period.
RESULTS Gross Alpha Concentrations Results of monitoring at each of the stack locations are presented in Tables 3-10.
Stack GAD 02018 was sampled from two access ports for a period of six days. The gross alpha concentration in the sample collected from a fixed location in the duct (Sample II) was <1.60 x 10-15 pCi/cc which represents the minimum detectable concentration for this sample (Table 3).
The sample collected from varying locations within the stack had a gross alpha
- concentration of 3.08 + 2.38 x 10-15 pCi/ce. The gross alpha concentration in the sample collected by GE over a seven day period was 1.7 x 10-I pCi/cc.
5 O _ _ _ _. _
Gross alpha levels in fixed and variable locations within stack POWS 0562, as determined by ORAU over a six day period, were 0.5510.19 x 10-I" pCi/cc and 1.33 1 0.26 x 10-14 pCi/ce, respectively (Table 4).
In comparison, the licensee's result for a seven day period was 4.3 x 10 I" pCi/cc.
The gross alpha concentration measured in a fixed location in stack FURN0556 over a six day period was 2.6210.14 x 10-13 pCi/cc (Table 5).
The sample collected from varying locations within the stack had a gross alpha concentration of 2.501 0.14 x 10-13 pCi/cc.
In comparison, the gross alpha concentration measured for seven days by the licensee was 3.23 x 10 13 pCi/cc.
Stack REDCAP 70 was sampled for six days using two access ports.
The
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gross alpha level (Table 6) measured in the sample collected at a stationary location was 0.7910.26 x 10-I" pCi/cc.
The sample from the variable probe position had a gross alpha concentration of 0.24 1 0.19 x 10-1" pCi/cc.
The concentration (for the same time period) reported by GE was 1.06 x 10-13 pCi/cc.
Gross alpha concentrations measured by ORAU in stack CLABEAST were
<0.16 x 10 1" pCi/cc for the fixed sampling location and 0.29 1 0.14 x 10-1" pCi/cc for the variable probe positions (Table 7).
General Electric reports gross alpha concentrations of <0.6 x 10-1" pCi/cc for the same time period.
{
Stack CHMN0541 was sampled daily for three days.
The gross alpha concentration measured in the sample collected in a fixed location was 1.46 +
0.38 x 10-1" pCi/cc (Table 8).
The samples collected daily from varying 10-1" to locations within the stack ranged from 0.91
+
0.30 x
' 0.61 1 0.17 x 10 13 pCi/cc.
Gross alpha concentrations measured during the same time period by GE ranged f rom 1.1 x 10-13 to 2.5 x 10-13 pCi/cc.
As with stack CHMN0541, ORAU sampled stack CHMSFM0X(546x) daily for a period of three days.
The gross alpha concentration measured in the fixed 10-1" pCi/cc (Table 9).
The concentrations location was 0.2510.27 x
10-1" to measured at changing probe locations ranged from
<0.89 x
2.41 1 1.42 x 10-I" pCi/cc.
Gross alpha concentrations measured during the same time period by GE ranged from 4.1 x 10-I" to 4.7 x 10-1" pCi/cc.
6
Gross alpha levels measured by ORAU over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period for stack INEXBURN were 3.72 i 1.34 x 10-14 pCi/cc (Table 10).
In comparison, the licensee's results for the same period were 9.6 x 10'I4 pCi/cc.
Condensed moisture from the stack did not contain significant activity levels.
Table 11 presents the results of samples collected from stacks CHMSFM0X(546x) and CHMN0541 using Whatman particulate filters treated with 10-I" pCi/cc and K CO.
Gross alpha concentrations were 1.73 1 1.10 2 3 x
10-14 pCi/cc, respectively.
These results have been 0.94 + 1.02 x incorporated into the values reported above for concentrations measured in those two stacks.
Isotopic Compositions
[
Isotopic uranium analyses were performed on the samples collected from stack FURN0556.
These analysis indicated U-235 enrichments ranging from 1.5 to 3.7%.
The other samples did not contain sufficient activity to perform isotopic analyses.
Particle Size Distributions Particle size distributions determined from samples, collected by Andersen Fractionating Particle Samplers at stacks CHMSFM0X(546x), CHMN0541, FURN0556, REDCAP 70 and INEXBURN are illustrated in Figures 5-9.
Activity median aerodynamic diameters (AMAD) ranged from 1.6 pm to 2.1 pm.
(Figures 5-9).
DISCUSSION OF RESULTS Gross Alpha Concentrations A comparison of gross alpha concentrations measured by GE and ORAU indicates generally good agreement in the sampling results.
Taking into account the statistical errors associated with each calculated activity, GE and ORAU results differ in most cases by a factor of three or less.
7 s
Exceptions to this include results from the monitoring of stack GAD 02018 and CHMN0541. Results reported by the licensee were a factor of 5 higher at stack GAD 02018 and factors of 15 and 25 higher on two of the sampling days at stack CHMN0541.
Samples collected by GE are held for decay prior to counting for a period of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
This may not be sufficient time for decay of some thoron progeny, thus resulting in a higher gross alpha concentration than was j
measured by ORAU, which decayed filters for over 3 weeks before counting.
l Some differences for the GAD 02018, POWS 0562, and FURN0556 stack results may also be attributed to the difference in sampling times, i.e. 6 days by ORAU vs. 7 days by CE, caused by weather conditions.
It should be noted that
{
although GE corrects measurements for filter collection efficiency (97%) and self-absorption losses (30%), they do not determine statistical errors for their calculated stack releases.2 Comparison of sampling with a stationary probe and a probe which was
[.
repositioned daily indicates general agreement within a factor of two or less.
The one exception to this occurred at stack CHMN0541.
The sample (I) collected on September 17-18 from this stack had an activity level approximately 7 times greater than the other ORAU samples from that system.
It is possible that there is an obstruction within this stack (as was noted in the other scrubber system stacks), which alters the airstream pattern at this location.
However, the results generally suggest that single point sampling in these stacks will provide represet.tative data.
Guideline concentrations for uranium.in. air in unrestricted areas range from 3 x 10-12 to 2 x 10-IlpCi/cc. The highest concentration measured by ORAU was 3
2.62 x 10-13; this is an order of magnitude less than the most restrictive of the NRC uranium air concentration guidelines.
[
l Fluoride Concentration Samples collected on potassium carbonate treated filters from two stacks (CHMN0541 and CHMSFM0X(546x) provided results indicating that the uranium 8
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I fluoride levels present in these two stacks are insignificant (refer to Table 11).
Isotopic Compositions l
l The percent enrichment measured by ORAU is in good agreement with the percentages reported by General Electric.
l Particle Size Distribution 1
An AMAD of 1.6 - 2.1 um was determined, indicating that these particles I
would reach the alveolar region of the lung if inhaled. This size is slightly larger than the 1 pm diameter typically used for generic environmental dosimetry calculations.
SUMMARY
g During the period from September 16-26, 1985, Oak Ridge Associated W
Universities, at the request of the NRC, performed stack effluent monitoring l
at the General Electric Company facility in Wilmington, N.C.
The objective of the survey was to characterize stack releases in terms of gross alpha L
concentrations. ieotopic eranium comooeitions and partic1e eire distributions.
The results of the survey indicated generally close agreement between ORAU.and GE on gross alpha concentrations in samples collected from all of the stacks surveyed.
ORAU measurements performed at different locations within the stacks suggest that single point sampling is providing a representative I
sample. Measured concentrations were well below the NRC guideline levels for uranium in air in unrestricted areas.
Based on the results of this survey it is ORAU's conclusion that the GE stack monitoring program is adequate and provides sufficiently accurate data.
If anything, the values reported by GE are conservative, due possibly, to the 9
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short decay time allocated for radon and thoron progeny.
It is recommended that this procedure be evaluated further by GP. and also that procedures be implemented to include calculation and reporting of uncertainity values associated with stack discharge data.
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.g.........
.t........>...
8 oo o
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........ 4................:.........................:...............:.....
a.
3...
e i
......................y.......................................
g...
-i t
0.1 i
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i 10 100 Cumulative % Less Than Stated Size FIGURE 8: Typical Particle Size Distribution of Andersen Fractionating i
Particle Sampling from Stack REDCAP 70 4.
1 1
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1
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U Particle Size Diameter Graph - INEXBURN 10.
.g.
.............l...
.......g...._......
p.
........g.
.q..........
.........p......
......p E.,.
......p..
..................4.................
....p..................
...l.....
......g........
u o
s
- ...... E.......
4....
u.
O
=
w u
f.
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?
Geometric Mean Diameter
.I.......................q........./.;........j......;......g.....;.....i....;...
d = 2.I25
.........a g
- ....... 4...............t.....;....<..
o
.......t..
- ......;.......9...;...
v2
_.......................... /.....g....
n
......................4......e g
Geometric Standard Deviation
- p
..........;.................;...........4........>...
m o = 2.255 e
_............ g..................;..........:.......j......:.....;....:.. j...
g o
+
u m
u n.
l 0.1 i
i e
i i
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i 10 100 Cumulative % Less Than Stated Size FIGURE 9: Typical Particle Size Distribution of Andersen Fractionating Particle Sanpling from Stack INEXBURN 1
1 e
l l
l l
TABLE 1 I
VELOCITY PROFILES IN EXHAUST DUCTS GENERAL ELECTRIC COMPANY WILMINGTON, NORTH CAROLINA I
Stack Diameter Measurement Location Velocity I
(cm)
(cm from duct wall)a m/ min I
II CHMSFM0X(546x) 152 3.2 671 381 10.2 580 458 18.0 549 503 I
26.9 503 442 38.1 473 427 54.4 442 488 I
98.0 458 519 114.0 397 671 125.0 397 732 134.0 458 763 142.0 458
'763 149.0 458 610 Centerline 76.2 458 366b CHMN0541 122 2.5 457 427 8.3 518 549 14.0 457 610 I
21.6 640 640 30.5 579 671 43.2 518 640 I
78.7 671 671 91.4 686 702 centerline 61.0 640 640 CLABEAST 76.2 1.3 305 244 5.1 579 671 8.9 610 793 13.3 701 824 19.1 671 793 26.7 732 793 I
48.9 610 305 57.2 610 305 62.9 640 244 67.3 671 244 I
71.1 701 244 74.3 701 183 Centerline 38.1 671 305b 20
I I
TABLE 1 (Continued)
VELOCITY PROFILES IN EXHAUST DUCTS GENERAL ELECTRIC COMPANY WILMINGTON, NORTH CAROLINA I
Stack Diameter Measurement Location Velocity I
(cm)
(cm from duct wall) m/ min I
II POWS 0562 60.7 2.0 518 488 6.4 503 518 11.4 533 518 I
19.7 518 488 41.3 442 503 49.0 457 533 I
54.6 396 518 59.1 411 488 Centerline 30.5 427 472 I
GAD 02018 68.6 1.3 396 549 4.5 579 640 7.6 732 701 1
12.1 792 762 17.2 792 732 24.1 701 671 43.8 518 549 I
51.4 579 518 56.5 579 488 60.3 549 488 64.1 518 427 67.31C 427 366 Centerline 34.3 518 518 FURN0556 81.2 1.3 107 122 5.8 152 152 9.5 152 183 I
14.6 198 198 20.3 198 198 29.2 229 213 I
52.1 198 229 61.0 244 229 69.2 244 244 71.8 229 229 I
76.2 244 213 79.4 213 213 Centerline 40.6 229 229 I
I 21
F L
TABLE 1 (Continued)
VELOCITY PROFILES IN EXHAUST DU, CTS
\\
GENERAL ELECTRIC COMPANY r[
WILMINGTON, NORTH CAROLINA Stack Diaueter Measurement Location Velocity (cm)
(cm from duct wall) m/ min I
II r-L REDCAP 70 45.7 1.3 1676 1219
{
5.1 1829 1524 8.9 1829 1524 14.6 1524 1524 31.1 1524 - 1524 u
36.8 1524 1524 40.6 1829 1524 44.5 1829 1524
{
Centerline 22.9 1829 1676 INEXBURN 45.7 1.3 686 991 E
5.1 914 884 L
8.9 792 732 14.6 732 610 31.1 792 594 36.8 686 747 40.6 640 671 44.5 640 396
{
Centerline 22.9 762 732 r
aRefer to Figure 2.
[
bObstruction at centerline.
cDuct wall encountered at this point.
[
[
[
[
[
22
M M
M M
M M
M M
M M
TABLE 2 STACK SAMPLING FLOW RATES AND VOLUMES GENERAL ELECTRIC COMPANY WILMINGTON, NORTH CAROLINA STACK DATE SAMPLING POINT VELOCITY SAMPLING SAMPLING SAMPLE AND LOCATION AT SAMPLING RATE TIME VOLUME (cm from duct wall)
POINT (m/ min)
(1/ min)
(min)
(1 x 10")
GAD 02018 9/20-9/26 17.2-11 (East) 732 12.3 8610 10.6 9/20-9/23 12.7-I (North) 793 13.4 4110 5.51 9/23-9/25 34.3-I 518 8.71 2880 2.51 9/25-9/26 64.1-1 518 8.71 1560 1.36 POWS 0562 9/20-9/26 15.2-1 (Northeast) 526 16.6 8640 14.3 9/20-9/23 10.2-II (Southeast) 518 16.4 4170 6.84 w
9/23-9/25 30.5-II 472 14.9 4320 6.44 9/25-9/26 55.9-11 404 12.8 1560 2.00 FURN0556 9/26-9/26 20.3-II (East) 198 9.78 8670 8.48 9/20-9/23 10.2-1 (North) 160 7.91 4200 3.32 9/23-9/25 40.6-I 229 11.3 2850 3.22 9/23-9/26 61.0-1 244 12.0 1590 1.90 REDCAP 70 9/20-9/26 12.7-II (West) 1524 12.1 8490 10.3 9/20-9/23 12.7-I (South) 1829 14.5 4050 5.87 9/23-9/25 22.8-I 1829 14.5 2880 4.18 9/25-9/26 41.9-I 1829 a
CLABEAST 9/20-9/26 19.1-II (West) 793 13.4 8460 11.3 l
9/20-9/23 10.2-1 (South) 640 10.8 4020 4.34 j
9/23-9/25 38.1-I 671 11.3 2880 3.26 9/25-9/26 66.0-I 671 11.3 1560 1.76 l
M M
M M
M
. TABLE 2 (Continued)
STACK SAMPLING FLOW RATES AND VOLUMES GENERAL ELECTRIC COMPANY WILMINGTON, NORTH CAROLINA STACK DATE SAMPLING POINT VELOCITY SAMPLING SAMPLING SAMPLE AND LOCATION AT SAMPLING RATE TIME VOLUME (cm from duct wall)
POINT (m/ min)
(1/ min)
(min)
(1 x 10")
CHMN0541 9/17-9/20 30.5-II (East) 579 18.4 4320 7.94 9/17-9/18 30.5-I (South) 671 11.3 1440 1.63 9/18-9/19 14.0-I 610 10.4 1380 1.43 b
61.0-I 640 10.8 1440 1.56 9/19-9/20 CHMNFMOX( 546x) 9/17-9/20 38.1-II (East) 427 13.5 4410 5.96 9/17-9/18 10.2-1 (South) 579 9.76 1500 1.46 s,
8-9/18-9/19 10.2-I (North) 457 7.69 1380 1.06 b
9/19-9/20 38.1-II (West) 671 11.3 1500 1.70 INEXBURN 9/23-9/24c 30.5-I (South) 793 13.3' 1350 1.80 l
aDash indicates equipment failure bK CO3 Sample was also collected during this time at this location.
2 j
cSample collected using Whatman #1 filter.
l i
i
[
TABLE 3 RESULTS OF STACK MONITORING - STACK GAD 02018 GENERAL ELECTRIC COMPANY WILMINGTON, NORTH CAROLINA DATE SAMPLEa ANALYSIS BY RADIONUCLIDE CONCENTRATIONS (pCi/cc)
Gross Alpha 9/20-26/85 I
ORAU 3.08 + 2.38 x 10-15b 9/20-26/85 II ORAU
<1.60 x 10-15c
{
9/20-27/85 GEW l.7 x 10-14 aSample I = Variable probe position; Sample II = Fixed probe position bErrors are 2a based on counting statistics.
CMinimum detectable concentration.
l ll ll 25
TABLE 4 I
RESULTS OF STACK MONITORING - STACK POWS 0562 GENERAL ELECTRIC COMPANY WILMINGTON, NORTH CAROLINA I
DATE SAMPLEa ANALYSIS BY RADIONUCLIDE CONCENTRATIONS (pCi/cc)
Gross Alpha 9/20-26/85 I
ORAU 0.55 + 0.19 x 10-14b 9/20-26/85 II ORAU 1.33 I 0.26 x 10-14 9/20-27/85 GEW 4.3 x 10-14 I
aSample I = Fixed probe position; Sample II = Variable probe position bErrors are 2a based on counting statistics.
I I
I I
I 26
I TABLE 5 I
RESULTS OF STACK MONITORING - STACK FURN0556 GENERAL ELECTRIC COMPANY WILMINGTON, NORTH CAROLINA I
DATE SAMPLEa ANALYSIS BY RADIONUCLIDE CONCENTRATIONS (pCi/cc)
Gross Alpha 9/20-26/85 I
ORAU 2.50 + 0.14 x 10-13b I
9/20-26/85 II ORAU 2.62 I 0.14 x 10-13 9/20-27/85 GEW 3.23 x 10-13 I
aSample I = Variable probe position; Sample II = Fixed probe position bErrors are 2a based on counting statistics.
I 1
I I
I I
I I
I I
I 2,
r L
TABLE 6 I'
RESULTS OF STACK MONITORING - STACK REDCAP 70 GENERAL ELECTRIC COMPANY 7
WILMINGTON, NORTH CAROLINA L
DATE SAMPLEa ANALYSIS BY RADIONUCLIDE CONCENTRATIONS (pCi/cc)
Gross Alpha 9/20-26/85 I
ORAU 0.24 + 0.19 x 10-14b 9/20-26/85 II ORAU 0.79 + 0.26 x 10-14
{
9/20-27/85 GEW 1.06 x 10-13
,s r
aSample I = Variable probe position; Sample II = Fixed probe position L
bErrors are 2a based on counting statistics.
l l
g.
E E
[
bl
[
[
i
[
28
TABLE 7 I
RESULTS OF STACK MONITORING - STACK CLABEAST GENERAL ELECTRIC COMPANY WILMINGTON, NORTH CAROLINA DATE SAMPLEa ANALYSIS BY RADIONUCLIDE CONCENTRATIONS (pCi/cc)
Gross Alpha 9/20-26/85 I
ORAU
<0.16 x 10-14b I
9/20-26/85 II ORAU 0.29 + 0.14 x 10-14c 9/20-27/85 GEW
~ <0.6 x 10-14 I
aSample I = Variable probe position; Sample II = Fixed probe position bMinimum detectable concentration.
cErrors are 2a based on counting statistics.
I.
I I
I I
I I
I I
I I
2e
I I
TABLE 8
)
I RESULTS OF STACK MONITORING - STACK CHMN0541 GENERAL ELECTRIC COMPANY WILMINGTON, NORTH CAROLINA I
DATE SAMPLEa ANALYSIS BY RADIONUCLIDE CONCENTRATIONS (pCi/cc)
Gross Alpha 9/17-20/85 II ORAU 1.46 + 0.38 x 10-14 9/17-18/85 I
ORAU 0.61 + 0.17 x 10-13 9/17-18/85 GEW 1.1 x 10-13 9/18-19/85 I
ORAU 0.91 + 0.30 x 10-14 9/18-19/85 GEW 1.4 x 10-13 9/19-20/85 I
ORAU 0.94 + 1.02 x 10-14 9/19-20/85 GEW 2.5 x 10 -13 E
D. ple I e P. ;1able probe position; Sample II = Fixed probe positicg
\\
I I
I I
lI I
I I
30
I TABLE 9 I
RESULTS OF STACK MONITORING - STACK CHMSFM0X(546x)
GENERAL ELECTRIC COMPANY WILMINGTON, NORTH CAROLINA DATE SAMPLEa ANALYSIS BY RADIONUCLIDE CONCENTRATIONS (pCi/cc)
Gross Alpha l
9/17-20/85 II ORAU 0.25 + 0.27 x 10-14 9/17-18/85 I
ORAU
<0.89 x 10-14b 9/17-18/85 GEW 4.7 x 10-14 9/18-19/85 I
ORAU 2.12 + 1.61 x 10-14 9/18-19/85 GEW 4.1 x 10-14 9/19-20/85 I
ORAU 2.41 + 1.42 x 10-14 9/19-20/85 GEW 4.1 x 10-14 I
aSample I = Variable probe position; Sample II = Fixed probe position bMinimum detectable concentration.
I I
I l I 1I I
I I
31
I TABLE 10 I
RESULTS OF STACK MONITORING - STACK II{EXBURN GENERAL ELECTRIC COMPANY WILMINGTON, NORTH CAROLINA DATE ANALYSIS BY RADIONUCLIDE CONCENTRATIONS (pCi/cc)
Gross Alpha 9/23-24/85 ORAU 3.72 + 1.34 x 10-14a 9/23-24/85 GEW 9.6 x 10-14 aErrors are 2a based on counting statistics.
I I
I I
I I
I I
I I
32
[
TABLE 11 RESULTS OF STACK MONITORING AT CHMSFMOX(546x) AND CHMN0541 USING K CO3 TREATED FILTERS 2
{
GENERAL ELECTRIC COMPANY WILMINGTON, NORTH CAROLINA
[
STACK DATE RADIONUCLIDE CONCENTRATIONS (pCi/cc)
Gross Alpha CHMSFMOX(546x) 9/19-20/85 1.73 + 1.10 x 10-14
{
CHMN0541 9/19-20/85 0.94}1.02x10-14 aErrors are 2a based on counting statistics.
[
[
[
[
[
[
(
[
[
[
[
33
L
[
{
REFERENCES 1.
Title 40, Code of Federal Regulations, Part 60, Standards of Performance for New Stationary Sources, 1977.
2.
Phone conversation with Paul Stansbury, GE Nuclear Fuel and Special Products Division, February 26, 1986.
[
3.
Title 10, Code of Federal Regulations, Part 20, Standards for Protection Against Radiation, 1985.
[
[
[
[
[
[
[
[
[
[
34
I I
I I
APPENDIX A I
MAJOR SAMPLING AND ANALYTICAL EQUIPMENT I
I lI I
I I
[
APPENDIX A Major Sampling and 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 employers.
A.
Air Sampling
(
Aluminum in-line filter holders 47mm Cat. #996209
{
(Research Appliance, Co., Cambridge, MD)
Stack sampling nozzles (NuTech Corp., Durham, NC)
Rotameters, 0-30 1pm (Union Carbide Corp., Linde Air Products Div.,
{
Birmingham, AL)
Rotameters 0-100 1pm p
(Union Carbide Corp., Linde Air Products Div.,
L Birmingham, AL)
Cast Vacuum Pumps
(
115v/60Hz Cat. #P8400 (American Scientific Products, Stone Mountain, GA)
Andersen 1 ACFM Non-viable Ambient Earticle Sizing Sampler (Anderson Samplers, Atlanta, GA)
Velometer - all purpose set Type 6000 a.p.
{
(Alnor Instrument Co., Niles, IL)
" Precision" Wet Test Meter p
Used to calibrate rotameters L
(Precision Scientific Co., Chicago, IL)
Additional supplies
{
Plastic tubing, connectors, particulate filter paper (0.08 pm),
Whatman #1 filter paper
{
B.
Laboratory Analysis Automatic low-background Alpha-Beta Counter Model LB5110-2080
[
(Tennelec, Inc., Oak Ridge, TN) b A-1
I I
Multichannel analyzer Model ND-66 (Nuclear Data, Schaumburg, IL)
Alpha Spectrometry System
.g Tennelec Electronics, EG6G ORTEC g
Surface barrier detectors (Tennelec, Inc., EG&G, Oak Ridge, TN)
I l
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E E
E E
E E
E APPENDIX B ANALYTICAL PROCEDURES
[
E E
E E
E
[
[
[
[
I APPENDIX B Analytical Procedures Gross Alpha Measurements Gross alpha measurements on particulate filter samples were made using an, automatic low-background proportional
- counter, Tennelec Model LB5110.
Aliquots of liquid from INEXBURN were evaporated to dryness and counted for gross alpha levels using the same equipment as used for filter samples.
Results of these gross alpha analyses were related to the total sample activity using ratios of analyzed volume to total sample volume.
Alpha Spectrometry An aliquot of liquid from INEXBURN was acidified and evaporated to dryness and the samples collected from FURN0556 were ashed. The residues were then dissolved by pyrosulfate fusion and precipitated with barium sulfate.
Barium sulfate precipitate is redissolved and uranium separated by liquid -
I liquid extraction.
Uranium was then precipitated with a cerium fluoride carrier and counted using surface barrier detectors (ORTEC),
alpha spectrometers (Tennelec), and an ND-66 Multichannel Analyzer (Nuclear Data).
Particle Sizing Sizing of the particulates collected by the Andersen impactor was in accordance with instructions for ra particles as presented in the operatingmanualforthatinstrument.gioactive Errors and Detection Limits The uncertainties associated with the analytical data, presented in the tables of this report, represent the 95% (2a) confidence levels based only on counting statistics.
Other sources of error associated with the sampling and analyses introduce an additional uncertainty of 6 - 10% in the results.
Calibration and Quality Assurance Laboratory analytical procedures are documented in manuals prepared by the ORAU Radiological Site Assessment Program.
Laboratory and analytical instruments are calibrated using NBS-traceable standards.
Quality control procedures on all instruments included daily I
background _and check-source measurements to confirm acceptable equipment operation.
The ORAU laboratory participates in the EPA Quality Assurance Program.
I Operating Manual for Andersen 1 ACFM Non-viable Ambient Particle Sizing Samplers, Andersen Samplers, Inc., Atlanta, GA, February 1984.
I B-1 J