ML20213H033
| ML20213H033 | |
| Person / Time | |
|---|---|
| Site: | 07000824 |
| Issue date: | 04/30/1987 |
| From: | Deming E OAK RIDGE ASSOCIATED UNIVERSITIES |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20213H023 | List: |
| References | |
| CON-FIN-A-9076-3 NUDOCS 8705190111 | |
| Download: ML20213H033 (28) | |
Text
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oa? Ridge Associated RADIOLOGICAL MONITORING mt Universities OF Prepared for
,t U.S. Nuclear Regulatory a
commission s STACK EFFLUENTS
) Region ll Office Supported by LYNCHBURG RESEARCH CENTER Safeguards and l'ss'"'S"'
BABCOCK & WILCOX Dividon of inspection Pro 9 rams:
LYNCHBURG, VIRGINIA Offico of Inspection and l
E. J. DEMING I
r Radiological Site Assessment Program Manpower Education, Research, and Training Division FINAL REPORT APRIL 1987 8705190111 870505 PDR ADOCK 07000824 C
RADIOLOGICAL MONITORING OF STACK EFFLUENTS LYNCHBURG RESEARCH CENTER BABCOCK & WILCOX COMPANY LYNCHBURG, VIRGINIA Prepared by E.J. DEMING Radiological Site Assessment Program Manpower Education,'Research, and Training Division Oak Ridge Associated Universities Oak Ridge, TN 37831-0117 l
Project Staff
(
J.D. Berger A.S. Masvidal R.D. Condra G.L. Murphy M.R. Dunsmore C.F. Weaver k.
R.D. Foley B.C. Williams Prepared for Safeguards & Materials Programs Branch Division of Inspection Programs Office of Inspection and Enforcement
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U.S. Nuclear Regulatory Commission Regi n II Office
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Final Ecport April 1987
-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 Universities performs complementa ry work under contract number DE-AC05-760R00033 with the U. S. Department of Energy.
TABLE OF CONTENTS Page List.of Figures.
11 List of Tables iii Introduction 1
Site Description and Information 1
Survey Procedures 2
Results 4
Discussion of Results 5
Summary..
6 References 18 Appendices Appendix A: Major Sampling and Analytical Equipment Appendix B: Analytical Procedures I
i
LIST OF -FIGURES Page FIGURE 1: Map of Virginia, Showing Approximate Location of Babcock and Wilcox Facility..
7 FIGURE 2: Map of Area Surrounding Babcock and Wilcox Facility.....
8 FIGURE.3:
Location of Buiding C Within the Lynchburg Research Center 9
FIGURE 4:
Plan View of the Lynchburg Research Center Indicating Location of the Main Exhaust Stack..
10 FIGURE 5:
EPA Standard Method 1 Criteria for Performing Air Velocity Measurements in Circular Ducts 11 FIGURE 6: Diagram of a Typical Particulate Air Stack Sampling System.
12 FIGURE 7: Diagram of the Sampling System Incorporating an Andersen Fractionating Particle Sampler.
13 FIGURE 8: Particle Size Distribution of Andersen Fractionating Particle Sampling from the LRC Stack
.................- 14 11
LIST OF TABLES Page Velocity Profile in the LRC Main Exhaust Stack........
15 TABLE 1:
- TABLE 2:
Lynchburg Research ' Center Stack Sampling Flow Rates and Volumes 16 TABLE 3: Results of LRC Stack Monitoring 17 111
RADIOLOGICAL MONITORING OF STACK EFFLUENTS LYNCHBURG RESEARCH CENTER BABCOCK & WILCOX COMPANY LYNCHBURG, VIRGINIA-INTRODUCTION The Babcock and ~ Wilcox Company's Lynchburg Research Center (LRC) facility near Lynchburg, Virginia, is licensed by the Nuclear Regulatory Commission'(NRC) for the research,. development and testing of nuclear reactor cores and nuclear fuel. The operations involved in.these processes have the potential for release of radionuclides to the environment, and the licensee has the responsibility to 7
ensure that established radiation protection guidelines for radioactive releases are me t.
To meet this requirement, Babcock and Wilcox has established a stack monitoring program to evaluate radioactive discharges.
The NRC periodically reviews such programs as a part of their continuing regulatory and inspection process. At the request of the NRC, Region II, the Radiological Site Assessment Program (RSAP) of Oak Ridge Associated Universities (ORAU) conducted independent radiological monitoring of the LRC main exhaust stack to evaluate the effectiveness of Babcock and Wilcox's monitoring program.
SITE DESCRIPTION AND INFORMATION The Babcock and Wilcox Lynchburg Research Center is located on Mt. Athos Road (Rt.
726) approximately 16 kilometers east of Lynchburg, Virginia (Figure.1).
The site occupies a total area of 212 hectares and is bounded on the north, west, and south by the James River (Figure 2).
The LRC utilizes 5.5 ha and the remainder of the property is divided between the Babcock and Wilcox Company's Naval Nuclear Fuel Division and the Commercial Nuclear Fuel Plant (Figure 3).
Research activities conducted at the LRC result in the generation of enriched uraniun fission products and activation products, as well as off-gases produced from the testing of nuclear fuel rods. Exhaust ventilation systems are utilized wherever the potential exists for the generation of airborne radioactive materials.
Each system is equipped with either single or double 1
HEPA filters, or a ~ sequence of roughing plus HEPA filters, depending on the scheduled operations in each area. All systems at the LRC are exhausted through the 1.2 meter diameter main ventilation stack, located on Building C (Figure 4).
Babcock and Wilcox continuously samples the LRC main exhaust stack in accordance with 10CFR20 and/or action points as defined by NRC license SNM-42.
The sampling rate is approximately (1 10%) isokinetic to assure that a representative sample of the particulate component is obtained.
Babcock and Wilcox uses a multipoint probe system in the LRC stack; samples are collected on Gelman Metragard (TM) filters, and the filters.are replaced weekly (on Wednesday).
SURVEY PROCEDURES Objective The objective of the survey was to monitor the radiological emissions from the LRC nain exhaust stack with regard to concentrations and particle size distributions.
The data gathered by ORAU was compared to measurements made by Babcock and Wilcox personnel during the same time period, to determine the adequacy and accuracy of the licensee's monitoring procedures.
Procedures The survey was conducted during the period of July 14-25, 1986, and was performed in accordance with a site specific survey plan approved by NRC Region II.
1.
Two 4 cm diameter holes were drilled at right angles in the LRC stack by Babcock and Wilcox personnel, to provide access for measuring airflow and inserting sampling probes.
The holes were placed at a location far enough f rom transitions or bends to minimize distortions in the flow pattern.
2.
A 91.4 cm pitot tube and Ainor velometer were used to measure the stack velocity at predetermined positions in the
- stack, based on recommendations found in EPA Standa rd Method #1 (CF77).
Figure 5 2
cummariz20 tha critaria for e21tetion of airflow measurement locations in circular ducts.
Because the stack diameter was 120 cm and the pito,t tube length was only 91.4 cm, it was not possible to measure the velocity across.the entire stack. The velocity. profile is presented in
-Table 1.
The stack was also scanned to check for the presence of any significant airflow variations.
- 3. - Velocity distribution measurements and calculations of corresponding nozzle diameter ' sizes were performed to determine appropriate flow rates for isokinetic sampling at selected sampling locations within the stack. The flow rates determined for each stack sampling location were in the range of 17.0 to 17.5 1/m.
4.
A ~ single sampling probe was installed in the LRC stack, from the west side.
The nozzle was connected to a pitot tube supported by a metal plate, held in place on the stack with flexible straps and duct tape.
The probe position was changed periodically to obtain samples from various locations within the airstream.
5.
Following installation of the probe assembly and connection of the vacuum, control, and measurement equipment (Figure 6), the airflow was adjusted to the calculated isokinetic sampling rate. The start-up time and the flow rate was recorded and periodic checks were made to assure that the desired flow rate was being maintained. Flow rates and sample volumes are summarized in Table 2.
6.
An Andersen Fractionating Particle Sampler was installed for determination of particle size distribution (AN84).
Samples were collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a flow rate of 28.3 1/m (Figure 7).
The probe nozzle was changed for this aspect of the survey to achieve isokinetic sampling.
7.
The samples were collected on 0.8 pm millipore particulate filters using in-line filter holders; Andersen samples were collected utilizing glass fiber filters in the cascade impactor stages.
8.
If sufficient sample mass was collected, the lung solubility of the radiological component was to be determined.
3
Sample Analysis and Interpretation of Results Samples were returned to Oak Ridge for analysis by ORAU lab ' personnel.
Gross alpha concentrations were datermined for the particulate filters.
Particle size distribution f c,r the LRC stack was determined using Andersen sampler it. formation. 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, from samples collected during comparable periods.
RESULTS l
l Gross Alpha Concentrations The gross alpha concentrations measured in sa.nples collected f rom the LRC main exhaust stack from July 14, 1986, to July 27, 1986, are presented in Table 3.
The samples ranged in daily concentration from minimum detectable 10~I")
10 I"
pCi/ml.
In comparison, the concentration (<1.59 x to 1.34 x Itcensee's measurements ranged f rom 2.42 x 40 16 to 6.03 x 10 16 pCi/mi over three, 7-day intervals covering the ORAU survey period.
Particle Size Distributions The particle size distribution determined from samples collected on July 23, 1986, using an Andersen Fractionating Particle Sampler are illustrated in Figure 8.
The act1 icy median aerodynamic diameter (AMAD) is 2.6 tra.
Lung Solubility Because of the very low concentrations of uranium in the
- stack, insufficient sample mass was collected to enable determination of lung solubilities.
4
4 DISCUSSION OF RESULTS Gross Alpha Concentrations Gross alpha concentrations, determined by ORAU for individual stack effluent samples,- were, with one exception, less than the measurement sensitivities of the analytical techniques used. The concentrations reported by Babcock and Wilcox were well below the measurement sensitivities achieved by ORAU, thus precluding quantitative direct comparisons of ORAU results with Babcock-and Wilcox results.
Reasons for the differences in measurement sensitivities were:
1.
Babcock and Wilcox counted samples for a longer time (100 minutes) than ORAU (60 minutes).
l 2.
The background of the counter used by Babcock and Wilcox was 0.04 cpm, as compared to the higher ORAU counter background of 0.14 cpm.
3.
Samples collected by Babcock and Wilcox represented a span of 7 days (greater sample volumes), while ORAU samples were for shorter periods (1 day or 3 days).
All of these factors result in greater sensitivity for the Babcock and Wilcox analyses than for the ORAU analyses.
Additional factors may also have influenced the representativeness of the Babcock and Wilcox sampling as compared to the ORAU sampling. However, because the concentrations present were very low and, in most cases, below the-measurement sensitivities of the analytical procedure the impact of these factors could not be determined. These additional factors are:
1.
Sampling location - the location of the licensee's sampling probe was about 3 duct diameters downstream of the blower assembly.
This may place the intake in a region of turbulent and inconsistent airflow patterns.
ORAU's samples were collected about 8 duct diameters from the blower, in a region shown by measurements to have an even flow pattern.
2.
Sample line loss - ORAU filters were attached to the probe on the LRC stack, while Babcock and Wilcox filters are located at least 8 meters away from the sampling probe.
The distance involved, between the 5
sampling location and collection filter, increases the potential ror particulate deposition in the sample line.
Although the low concentrations prevented quantitative comparisoes of ORAU and Babcock and Wilcox data, the study did substantiate that the stack effluent is well within NRC guidelines for unres t ricted areas.
The guideline concentrations for various uranium isotopes in unrestricted areas, as defined in 10 12 10 11 pCi/ml (CF85).
The highest 10CFR20, range from 3 x to 2 x concentration measured by ORAU was less than the minimum detectable concentration (<5.43 x 10 I
pCi/ml), which is almost two orde rs of magnitude less than the most restrictive of these uranium air concentration guidelines.
Particle Size Distribution Particle size information collected from the LRC stack using an Andersen Fractionating Particle Sampler, produced a calculated AMAD of 2.6 tm with a geometric standard deviation of 2.2 pm.
Particles of this size would primarily accumulate in the nasopharyngeal region, with a smaller percentage distributed between the tracheobronchial region and the alveoli.
This size of particle would also have a somewhat greater tendency for sampling line loss than would particles of smaller size.
SUmfARY At the request of the NRC, Oak Ridge Associated Universities performed stack effluent monitoring of the LRC main exhaust stack at the Babcock and Wilcox facility near Lynchburg, Virginia.
The survey took place during the period of July 14-27, 1986. The objective was to characterize stack releases in terms of gross alpha concentrations and particle size distribution.
The results of the survey indicate that concentrations of uranium in stack ef fluents are well within the guideline levels for unrestricted areas.
Because of the low concentrations, quantitative comparisons of Babcock and Wilcox data with ORAU data were not possible.
It is, however, ORAU's recommendation that Babcock and Wilcox evaluate their stack sampling progran relative to the location of the probe and the potential for particulate deposition within the sampling line.
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1
TABLE 1 VELOCITY PROFILE IN THE
'LRC MAIN EXHAUST STACK BABC0CK AND WILCOX COMPANY LYNCHBURG, VIRGINIA Measurement Location Velocity (cm From Duct Wall)a (m/ min) t West Port (I)
North Port (II) 2.5 457 457 8.1 488 518 14.4 518 518 21.6 549 579 30.5 549 595 43.4 518 579 61.0 (Centerline) 549 518 78.5 533 595 91.4 533 579 Average 522 Average:
549 aRefer to Figure 5.
15
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TABLE 2 l
LYNCilBURG RESEARCH CENTER STACK SAMPLING FLOW RATES AND VOLUMES l
l BABCOCK AND WILCOX 00MPANY LYNCllBURG, VIRGINIA t
Date SampIfng Point Velocity at Sampling Rate Sampling Sample Voluge (cm From Duct Wall)
Sampling Point (liter / min)
Time (min)
(liter x 10 )
(m/ min) 7/14/86 91.4 533 17.0 1500 2.55 7/15/86 91.4 533 17.0 1385 2.35 7/16/86 30.5 549 17.5 7/17/86 30.5 549 17.5 1429 2.50 a
a 7/18-20/86 61.0 549 17.0 4338 7.38 7/21/86 61.0 549 17.0 1326 2.25 7/22/86 30.5 549 7/23/86 30.5b 17.5 1394 2.44 549 28.3 1396 3.95 7/24/86 61.0 549 17.5 1453 2.54 7/25-27/86 61.0 549 17.5 4391 7.68 aEquipment failure-time unknown.
hAndersen Fractionating Particle Sampler in place.
f TABLE 3 RESULTS OF LRC STACK MONITORING BABCOCK AND WILCOX COMPANY LYNCHBURG, VIRGINIA Date Analysis by Gross Alphg Concentration (x 10-pCi/ml) 7/14/86 ORAU 1.34 i 1.16 7/15/86 ORAU
<5.20 7/16/86 ORAU b
7/17/86 ORAU (4.89 7/18-20/86 ORAU
<1.66 7/21/86 ORAU
<5.43 7/22/86 ORAU
<5.01 7/23/86 ORAU c
7/24/86 ORAU (4.81 7/25-27/86 ORAU
<l.59 7/9-16/86 B&W
.024 7/16-23/86 B&W
.060 7/23-30/86 B&W
.044 aErrors are 2a based only on counting statistics.
bEquipment failure.
cAndersen Fractionating Particle Sampler in place for particle sizing study; concentration not determined.
17
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REFERENCES AN84 Operating Manual for Andersen 1 ACFM Non-viable Ambient Particle Sizing Samplers, Andersen Samplers, Inc., February 1984.
1 CF77 Title 40, Code of Federal Regulations, Part 60,-Standards of Performance for New Stationary Sources, 1977.
CF85 Title 10, Code of Federal Regulations, Part 20, Standards for Protection Against Radiation, 1985.
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APPENDIX A MAJOR SAMPLING AND ANALYTICAL EQUIPMENT
APPENDIX A Major Samping 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 47 e.m Cat. #996209 (Research Appliance, Co., Cambridge, MD) l l
Membrane Filter paper l
Metricel GA-4, 47 mm l
(Gelman Sciences, Ann Arbor, M1) l Stack Sampling Nozzles t
l (NuTech Corp., Durham, NC) l Rotameters Dwyer Model RMD Dwyer Instrumente, Inc.
(Michigan City, IN) l Cast Vacuum Pumps 115v/60ltz Cat. #P8400 (American Scientific Products, Stone Mountain, GA)
Andersen 1 ACFM Non-viable Ambient Particle Sizing Sampler (Andersen Samplers, Atlanta, CA)
Veloneter - all purpose set Type 6000 a.p.
( Alnor Instrument Co., Niles, IL)
" Precision" Wet Test Meter Used to calibrate rotameters (Precision Scientific Co., Chicago, IL)
Additional Supplies Plastic tubing, connectors 1
A-1 l
8
B.
Laboratory Analysis Automatic low-background Alpha-Beta Counter Model LB5110-2080 (Tennelec, Inc., Oak Ridge, TN)
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,mJ,s af,a4-N APPENDIX B ANALYTICAL PROCEDURES
APPENDIX B Analytical Procedures Cross Alpha Measurements Gross alpha measurements on particulate filter samples were made using an automatic low-background proportional counter, Tennelec Model LB5110.
Results of these gross alpha analyses were related to the total sample activity using ratios of analyzed volume to total sample volume.
Particle Sizing Sizing of the particulates collected by Andersen impactor was in accordance eith instructions for radioactive particles as presented in the operating _ manual for that instrument.
Errors and Detection Limits The uncertainties associated with the analytical data, presented in the tables of this re por t, represent the 95% (20) confidence icvels based only on counting statistics.
Other sources of error associated with the sa;;pling and analyses introduce an additional uncertainty of i 6 to 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 background and check source measurements to confirm acceptable equipment operation.
The ORAU iaboratory participates in the EPA Quality Assurance Program.
B-1