ML19296A833
| ML19296A833 | |
| Person / Time | |
|---|---|
| Site: | 07000036 |
| Issue date: | 01/28/1980 |
| From: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19296A831 | List: |
| References | |
| NUDOCS 8002190100 | |
| Download: ML19296A833 (23) | |
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C0CKET NO.
70-36 LICENSEE:
Combustion Engineering Corporation FACILITY:
Uranium Fuel Processing Plant Hematite, Missouri
SUBJECT:
RADIOLOGICAL ASSESSMENT OF INDIVIDUAL DOSE RESULTING FROM ROUTINE OPERATION--DEMONSTRATION OF COMPLIANCE WITH 40 CFR 190 I.
Backaround The EPA uranium fuel cycle standard, as specified in 40 CFR 190,1 limits the total dose to an individual from radioactivity associated with the routine operation of nuclear fuel cycle facilities to 25 mrem /yr to the total body, 75 mrem /yr to the thyroid, and 25 mrem /yr to any other organ.
The standard will become effective on December 1,1979, for all uranium fuel fabrication plants used for the production of LWR fuel.
The Combus-tion Engineering Corporation's (the licensee) plant is an existing uranium oxide fuel facility and is suoject to the EPA standards.
Based on the most current plant operation, emission, and monitoring data, the NRC staff conducted the following radiological assessment to determine if the licensee will meet the EPA's standard on fuel cycle facilities. As a result of this assessment, an action level on the effluent release rate from routine operat#cn of the facility will be establisned to provide reasonable assurant.e that the licensee will continue to comply with the standard during future operation.
II.
Discussion A.
Descriotion of the Facility 1.
Plant Ooeration - General Combustion Engineering Corporation owns and operates a facility for the production of low-enriched uranium dioxide fuel pellets which is located near the City of Hematite in Jefferson County, Missouri, about 3-1/2 miles west of Festus - Crystal City.
The pellets are shipped offsite for use elsewhere n. the manufacture of light water reactor fuel assemblies. The plant has a capacity of approximately 225 MTV per year.
Figure 1 shows the site fence and relative location of plant buildings on the Hematite site.
Table 1 cross-references the building number, building name and present use.
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't Scale of Feet TILE BARN FIGURE 1 LOCATION AND IDENTIFICATION OF BUILDINGS AND FACILITIES O COMBUSTION ENGINEERING HEA1ATITEPLANT SITE
3 TABLE 1 Buildings and Facilities on the CE Hematite Site Building No.
Building Name Present Use 101 Tile Barn Emergency Center and Equipment Storage Pump House Site Water Supply 110 New Office Building Guard Station and Offices 120 Wood Barn Equipment Storage 0xide Building and Dock UFs to UO2 Conversion 235 West Vault Naturil and Depleted Uranium Storage 240 240-1 Office and Cafeteria 240-2 and 3 Recycle and Recovery Area 240-4 Laboratory and Maintenance Shop 250 Boiler Room / Warehouse Steam Supply and Storage 252 South Vault Radioactive Waste Storage 255 Pellet Plant Fuel Pellet Fabrication U0 Storage and Laundry 2
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4 2.
Chemical Process The enriched uranium hexafluoride (UFs) is received as a solid in 2.5 ton cylinders.
These cylinders are heated in a steam Chest to vaporize the UFs.
The solid UFs is sublimed to a gas and, under its own vapor pressure, moves through pipes to the first fluid bed reactor. Here, it is reacted with an excess of dry steam to form fine particles of uranyl fluoride (U0 F ) and 2 2 hydrogen fluoride gas.
The gaseous HF and H 0 exits the reactor through a porous metal 2
filter; the solid UO F is moved to a second and third reactor 2
where it is pyrohydrolyzed in a reducing atmosphere of " cracked ammonia" to remove any residual fluorine and reduce the U0 F 22 to UO. Gases from the second and third reactor are also 2
filtered through porous metal filters and all gaseous reaction products are passed through towers packed with calcium carbonate to remove the HF prior to their release to the atmosphere.
Uranium dioxide (UO ) powder from the third reactor is cooled 2
and pneumatically transferred to storage silos.
The powder is withdrawn from the storage silos, milled to the required particle size range in a fluic energy mill, and pneumatically transferred to blenders prior to use in the pellet plant.
3.
Mechanical Process Blended powder from the conversion plant is agglomerated using an organic binder and a suitable solvent.
The agglomerated powder is granulated to insure a consistent press feed and pressed to the desired shape.
The green pellets are processed through a dewaxing furnace to remove the binder and subsequently si.'.ared to final density in a sintering furnace.
The dewaxing and sintering operations are performed in a reducing atmosphere of hydrogen or " cracked ammonia." The sintered pellets are ground to nominal diameter using a centerless grinder, dried, inspected, and packed for shipment.
8.
Waste Confinement and Effluent Controls Effluents from the various processes occur in three forms:
- gaseous, liquid, and solid. The effluents may contain small quantities of the radioisotopes U-234, U-235, U-236, and U-238.
The composition of the mixture will vary depending upon the enrichment of the material being processed; however, in all cases, the bulk cf the material will be U-238 (approximately 95% by weight or more), whereas the predominant activity will be from U-234 (up to approximately 86% of total activity).
Table 2 summarizes the types of liquid, gaseous, and solid effluents produced due to plant operations.
5 TABLE 2 Plant Operations and Effluents Liquid Effluents Gaseous Effluents Solid Effluents Process Steos Tyoe Effluent Tyoe Effluent Type Effluent
,es to UO2 Equip. cooling water UO2 fines, HF, N,
Calcium 2
and steam condensate H, H 0, CO2 Flouride (CaF )
2 2
2 Note 1.
Note 2.
UO Powder Steam condensate, UO fines Note 2.
2 2
Preparation Note 1.
TCE vapor UO Pellet Note 1.
UO fines Note 2.
2 2
Pressing UO Pellet Note 1.
UO fines Note 2.
2 2
Dewaxing N, CO, H O 2
2 2
Hydrocarbons UO Pellet Note 1.
U0 fines Note 2.
2 2
Sintering H 0, CO2 2
J0 Pellet UO2 contaminated UO fines Note 2.
2 2
Grinding cooling water, Note. 1.
UO2 Pellet and KOH solution cooling UO fines Note 2.
2 Powder Recycle water, Note 1.
H 0, HF, NH, N2 2
2 Hydrocarbons UFs Cylinder Heel Contaminated filtrate Yellowcake fines Lime, CaF2 Recovery Note 1.
NH 2 Note 2.
Regeneration of NaOH, Nacl, H SO 2 4 Demineralized Water System
6 TABLE 2 (Continued)
Liquid Effluents Gaseous Effluents Solid Effluents Process Steos Tyoe Effluent Tvoe Effluent
_,Tyoe Effluent Quality Control Equipment wash water, Various chemical Note 2.
Laboratory Laboratory residues, fumes Operations Note 1.
Site Laundry Detergent solution Note 2.
Steam Boiler
' eatment chemical H 0, C02 Note 2.
2 Treatment NOTE 1:
UO2 contaminated mop and cleaning water.
NOTE 2:
Effluent consists essentially of rags, paper, metal, plastic and rubber.
4 7
1.
Gaseous Effluenti Radiological Airborne radiological effluents include r eleases from the Oxide Building as a result of the UFs to UO 2 conversion process, from Building 255 as a result of the UO2 pc'.let fabrication process, and from Building 240 as a result of cylinder heel wash processing and the oxidation-reduction and pyrohydrolysis processing of recycle matei;al.
Figure 2 shows the " exhaust" stack locations.
As shown in the figure, there are eight release points for airborne radioactive materials from the Oxide Building.
Offgases from the UFs to UO F2 conversion process pass through two sets 2
of porous metal filters and are then routed through dry scrubbers.
The dry scrubbers contain limestone which reacts with the hydrofluoric acid in the filtered offgases to furm calcium fluorice.
Process ventilation air from the Oxide Building is passed through single absolute filters (99.97% efficient for removal of 0.3 micron particles) and is vented through the exhaust stacks to the atmosphere.
Continuous sampling is provided for each exhaust stack.
Process ventilation air from the Pellet Plant, Building 255, is exhausted through two new manifold systems which were installed in May 1975. These new consolidated systems replaced 15 former individual exhaust stacks.
Each system contains two banks of absolute filters and two banks of prefilters.
The prefilters, located upstream of the final ventilation equipment, preserve the effectiveness and longevity of the final filters in the consolidated exhaust systems.
The final filters are equipped with pressure differential measuring devices to determine filter loadings.
The three exhaust points shown in Figure 2 are continuously monitored during operations involving dust or other activities where the potential release of radioactive material could occur.
Ventilation air from the cylinder heel processing equipment in Building 240 is exhausted through a single absolute filter and is continuously sampled. The offgases from oxidation-reduction and pyrohydrolysis operations are scrubbed with a potassium hydroxide solution to remove hydrofluoric acid, routed through a single absolute filter and continuously sampled.
All stac,ui exhausting radioactive effluents are equipped with continuca samplers except the exhaust from the laboratory fume hoods which handle wet chemicals and two of the three room air exhausts in the Pellet Plant dewaxing and sintering furnace area. All stacks have single or double absolute filters except
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I FIGURE 2.
EXHAUST STACK LCCATIONS FOR HEMATITE FACILITY
9 for the laboratory fume hood exhaust, the Pellet Plant furnace area and 0xide Building room air exhausts, and the Oxide Building offgas exhaust. These exhausts use other a.ans of filtration and scrubbing as discussed above.
Nonradiological Airborne nonradioactive chemical effluents are produced di.ing UFs to UO2 conversion, pellet dewaxing, and recycle pyrot drolysis
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operations. Gaseous effluent waste streams from these aurations' are also treated as if potentially contaminated with uranium compounds.
2.
Liouid Effluents Radiological Radiological liquid effluents which contain trace quantities of uranium are generated in Building Nos. 240 and 255 as floor mop water and cleanup water.
This water is collected and evaporated in a special hood to recover the uranium.
Similar effluents from the wet scrubber system and UFs cylinder heel washing and processing coerations in Building 240 are discharged to evaporation ponds located within the fenced plant area.
(See Figure 3 for pond locations.) Prior to discharge, this waste water is analyzed to ensure that uranium concentrations are below acceptable levels:
(a-activity, uCi/mi s-activity, uCi/ml) g) 3 x 10 s 2 x 10 s If the analyses shows a valre > 1, the wastes are quarantined in 55 gallon drums until the contained radionuclides decay to acceptable levels. Other rariological wastes, containing only small quantities of uranium are generated in the laundry, from cleaning laboratory glassware, and in sinks and showers in the change room.
The laundry and laboratory effluents are discharged to the industrial waste system; the change room liquid effluents are routed to the sanitary waste system.
These effluents contain smaller concentrations of radionuclides than the permitted MPC values of 10 CFR 20, Appendix B, Table II.
Nonradiological Sources of nonradioactive liquid sanitary wastes are toilets, sinks, lavatories and drinking fountains.
Sources of non-radioactive liquid chemical wastes are boiler treatment chemicals, laboratory chemicals, and effluent from regeneration of the demineralized water supply system.
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FIGURE 3 SANITARY AND INDUSTRIAL 'NASTE LINE FLOWS
11 Sanitary wastes from Building Nos. 110, 240, and 255 flow into sanitary waste lines which are routed to the site septic tank.
The originating points of the effluents are shown in Figure 3 along with the path that the wastes follow to the septic tank.
Most solids settle in the primary septic tank chamber and are digested by bacterial action.
The primary septic tank chamber overflows into a dosing chamber and a float-controlled pump discharges the overflow to a sand trickling filter.
The sand filter removes most of the remaining suspended solids and also reduces the BOD (Biochemical Oxygen Demand) of the effluent stream.
After passing through the sand filter, the effluent is routed to the site pond which discharges into Joachim Creek at the southern site boundary.
The average volume of sanitary water discharged is about 1,400 gpd.
The licensee has a Missouri National Pollution Discharge Elimination System (NPDES) Permit (M0-000761) to allow for the discharges.
Industrial water is discharged directly to the site pond via the industrial and storm drain lines.
This waste water is essentially unchanged in both physical and chemical quality and receives no cleanup treatment.
This effluent contains no solid wastes.
The origins of industrial waste waters, including storm drains, are shown in Figure 3 along with the routes followed by the drain lines to the site pond.
Liquid effluents from the laundry and from cleaning glassware in the laboratory are discharged to the industrial waste drains.
This system also carries equipment cooling water and serves as the storm drain system. The storm sewer discharges into the site pond which overflows to form the site creek.
The overflow is con-tinuously propor'.ionally sampled and analyzed for gross alpha and beta activity.
The site creek discharges into Joachim Creek at the southern site boundary. Joachim Creek ultimately discharges into the Mississippi River.
The averace volume of the industrial waste water effluent generated is about 64,000 gpd.
The character and volume of radiological and nonradiological liquid effluents generated from plant operation are summarized in Table 3.
3.
Solid Wastes Radiological Solid radiological wastes having detectable contamination consist mostly of rags, papers, packaging materials, worn out shop clothing, and other miscellaneous materials that are generated in plant operations.
These are packaged in 55 gallon drums and 64 cubic foot plastic-lined wooden crates for disposal at a licensed inw-level burial site. Waste packages contain less than 25 pCi of activity according to monitored measurements.
4 12 TABLE 3 Type and Averaged Volume of Liquid Effluents (in GPD) Generated Industrial Liquid Effluent 64,000 Sanitary Liquid Effluent 1,400 Radiological liquid Effluent 3.
Discharged to Industrial Systems 3,5001 b.
Discharged to Sanitary Systems 1,0002 c.
Discharged to Retention Ponds 100
'Mostly aeionizea water from the laboratory with no contamination.
2Mostly water from showers with only trace quantities of uranium.
13 Gamma contaminated solid wastes are placed in sealed 55 gallon steel drums for licensed burial.
Bulky items with only low levels of surface contamination are placed in plastic-lined wooden boxes.
Calcium fluoride and limestone from the plant's dry scrubbers in the ventilation system may also contain radioactivity.
These spent materials, exhibiting barely detectable activity levels, are stored as fill material in the southern and south-eastern portions of the fenced c.anufacturing area.
Cu* rent operations produce approximately 100 cubic, yards of such material per year.
The maximum activity of this stored material does not exceed 50 dpm/gm which is less than would be found it: the majority of natural cres.
Nonradiolooical The bulk of tha norradioactive solid waste is collected and disposed of by a commercial waste disposal firm. Old items of noncontaminated equipment may be disposed of to commercial scrap dealers.
C.
Semiannual Effluents Emission Data Section 40.65 of 10 CFR Part 40 requires that the licensee suomit effluent monitoring reports on a semiannual basis.
Tables 4 and 5 summarize the recults of the airborne and liquid radioactive effluent measurements for the period July 1975 through December 1978.
D.
Descriotion of the Site Environment As Related to Establishing the Maximum Raolation Oose to a Nearoy Resident The following description of the site environment only provides information specific to the calculation of radiological impact to the nearest resident from radioactive effluents released during normal plant operations. Other general information can be found in the licensee's Environmental Impact Report issued in June 1975.2 1.
Site Location The Hematite site is located in Jefferson County, Missouri, approximately 35 miles south of the City of St. Louis.
Figure 4 shows population centers within 5 miles of the plant site.
2.
Land and Water Uses The plant site consists of about 152 acres in a lightly popu-lated rural area of east-central Missouri.
About 3% of the site is currently being used, with the remaining 97% consisting
s.
14 Table 4 Semiannual Airborne Release (Ci)
Period Release (No isotope definition)
July-Dec 1978 5.11x10 s Jan-June 1978 1.56x10 4 July-Dec 1977 5.68x10_5
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Jan-June 1977 9.40x10 5 July-Dec 1976 3.73x10_4
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Jan-June 1976 3.40x10 4 July-Dec 1975 4.70x10 5
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1.60x10[4 Ci 6 month average 3.19x10 4 Ci twice 6 month average Table 5 Semiannual Liouid Release (Ci)
Period Release (No isotope definition)
July-Dec 1978 1.32x10;2 2
Jan-;une 1978 1.00x10 July-Dec 1977 1.8x10 2 Jan-June 1977 1.22x10 2 July-Dec 1976
- 1. Mx10 2 Jan-June 1976 1.3x10 2 July-Dec 1975 3.5x10 2
- 1. 65x 10_"2 Ci 6 month average 3.31x10 2 Ci twice 6 month average
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16 of woodlands, water bodies, and open spaces.
The staff has concluded that there are no ongoing activities in the site environs which would present any hazard to the Hematite facility based on its review of the licensee's environmental statement and site visit.
The major stream nearest the plant is Joachim Creek, which runs into the Mississippi River.
The United States Department of Interior, Geological Survey (USGS), maintains a flow gauge at Hematite to measure the flow of the creek.
The creek flow data, based on relatively few observations, shows a range of between 12 and 330 cubic feet per second mean flow depending on the time of year.
The USGS also maintains gauging stations on the Mississippi River about 35 miles upstream and downstream of Hematite.
The average discharge at the downstream flow gauge, based on 99 years of record, is 176,000 cubic feet per second.
3.
Diffusion Climatoloav Onsite meteorological data on wind speeds and direction is not available from the licensee. However, general climatological characteristics in the area can be referenced to the U.S.
Weather Bureau recording station at St. Louis which is abcut 35 miles north-northeast of the site.
For the atmospheric dispersion calculations, joint frequency distributions of wind speed by stability class were calculated using the STAR 3 program based on observations made at St. Louis.
The meteorological dispersion factors (X/Q), were produced from the Gaussian Plume model and diffusion coefficients for Pasquill type turbulence using a computer code generated as described in Regulatory Guide 1.111.4'7 In evaluating the annual average X/Q values, a ground level release was conservatively assumed with no correction for building wake effects and assuming a neutral atmospheric stability (Pasquill type 0).3 The annual average X/Q's as a function of dictance up to 50 miles from the site in the sixteen 22-1/2 degree compass point sectors (i.e.,
centered on the north, northeast, southeast, etc.) were calculated and are shown in Table 6.
4.
The Nearest Resident Figure 4 shows the plant site and population centers within 5 miles.
The nearest resident, for which the evaluation was conducted, is located in the fown of Hematite approximately one-half mile southwest of the plant site.
The annual average X/Q values shown in Table 6 indicate that at the same distance, an individual (if any exists at that location) in some other direction may be subject to a higher dose due to less diffusion of the effluent. However, after evaluating the X/Q values in
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18 various directions and at the locations of other existing residences, the staff concluded that at the present time the nearest resident will probably encounter the maximum impact from plant releases.
E.
Environmental Imoact from Routine Plant Ooeration 1.
Methodolocy for Radiological Assessment The general approach to demonstrate compliance with the dose limits of the standard is as follows:
(i) Effluents released from plant operations will be monitored to determine the quantity of radionuclides discharged into the environment.
(ii) Environmental dose models developed by the NRC will be used to estimate dose commitment rates from all signifi-cant pathways.
It is only when noncompliance with the standard is suspected that a det'iled environmental monitoring program will be required to supplement the routine effluent monitoring.
The above approaches to demonstrate compliance are in conformance with the reccmmendations of the EPA as specified in their Final Environmental Statement (FES) for Environmental Radiation Protection Requirements for Normal Operations of Activities in the Uranium Fuel Cycle.8 The source terms (radioactive effluent release rates) from the Hematite plant are measured values. The atmospheric dispersion model is based on Regulatory Guide 1.111.7 Other environmental pathways and models are based on Regulatory Guide 1.1098 with the exception that for the inhalation pathway, dose conversion factors for various organs were generated using the ICRP Task Group Lung Model.972 The dose conversion factors from the Task Group Lung Model depend on the particle size and solubil-ity of released radioactive compounds.
If this information is not available from the licensee, a reasonable, conservative approach will be applied for the radiological impact assessment.
For example, the particle size is assumed to have an average diameter (AMAD) of 0.3 pm for particles passing through HEPA filters and 1.0 pm AMAD for particles not passing through HEPA filters. The released particles are further assumed first to be completely in an insoluble form which will provide a calcu-lated maximum lung dose for the inhalation pathway and then completely in a soluble form which will provide a calculated maximum bone dose for the ingestion pathway.
It is only when such conservative assumptions are critical to the standards (i.e., near or exceeding 25 mrem /yr) that the licensee will be required to conduct studies to obtain effluent characteristics data for a more realistic evaluation.
19 2.
Maximum Individual Dose The radiological impacts are assessed by calculating the maximum individual dose to the closest resident, who is living,at about one half mile southwest.
Except where specified, the term
" dose" as referred to in this assessment is actually a 50 year dose commitment, that is, the total dose to the reference organ from one year's chronic intake of radionuclides which will accrue during the remaining lifetime (50 years) of the individual.
For aireorne effluents released into the environment, the pathways considered in the individual dose estimates include (a) direct irradiation from either ground or shoreline deposi-tion, (b) direct inhalation, and (c) ingestion pathways (vege-tation, meat, milk) due to airborne deposition.
For liquid effluent releases, the pathways include (a) potable water, (b) aquatic food (fish), and (c) shoreline deposition.
The models and various assumptions involved in the above environmental pathways can be referred to in greater detail in Regulatory Guide 1.109.
Table 7 summarizes the results of the estimated maximum annual dose from airborne and liquid effluents to the nearest resident.
As shown in Table 7, the critical pathway is due to inhalation i % ulting in a maximum dose to the lung of 0.07 mrem /yr.
The above calculations assume a normal adult; the staff also considered a critical individual at the nearest residence. The critical individual in the inhalation pathway is an infant (0-1 years of age). The lung dose to the infant will be increased by a factor of about 1.8, i.e., 0.12 mrem /yr, less than 1% of the environmental standardl3 Therefore, the staff concluded that the maximum annual lung dose is well below the 25 mrem annual limit as specified in 40 CFR Part 190 and that there will be no adverse effect due to the release of effluents from normal plant operation.
Table 4 summarizes the semiannual release rates of radiological airborne effluents which were used as source terms for this assessment. The release rates are measured values.
The respec-tive semiannual release rates were averaged for a representative six-month rate and that value doubled for the annual release value shown in the tables and used in the calc; 3tions.
For liquid effluents discharged into Joachim Creek and then to the Mississippi River, it was conservatively assumed that the uranium is in a soluble form.
It was further assumed that the liquid release was only diluted by the river flow at the point of release to Joachim Creek.
.s 20 Table 7 Estimated Maximum Annuci Dose from Airborne and Liouid Effluents to the Nearest Resident Pathways Orcan Oose (milliremiyr)
A.
Air Effluents Total-Body Lung Bone 1.
Direct Irradiation 3.08x10 5 2.
Direct Inhalation
- 3.43x10 5 6.57x10 2 5.52x10 4
~
3.
Ingestion due to Airborne Deposition a.
Vegetation **
1.58x10 4
2.55x10 3 b.
Meat 6.44x10 7 1.04x10 5
~
c.
Milk 2.66x10 6 4.30x10 s B.
Liquid Effluents 1.
Potable Water 9.34x10 3 1.51x10 1
~
2.
Aquatic Food (Fish) 5.40x10 4
8.67x10 3 3.
Shoreline Deposition 5.72x10 11 Total (millirem /yr) 1.0lx10 2 6.57x10 2 1.63x10 1
" Assume 80% resiaence time.
- Includes nonleafy and leafy vegetables.
Since site specific information is not available, the staff assumed 76% of nonleafy and 100% of leafy vegetables eaten by nearest resident are produced in garden at residence as recommer.ded in Regulatory ^Jide 1.1C9.
3 21 F.
Conclusion and Recommendation The normal operation of the Hematite fuel fabrication plant results in the release of a minute quantity of radioactivity into the environ-ment.
Based on past operation, the annual release of radioactivity included approximately 319 pCi of uranium in airborne effluents and 33.1 mci of uranium in liquid effluents.
The nearest resident is located at about one-half mile southwest of the plant site.
The annual lung dose to the critical individual at the nearest residence was estimated under conservative assumptions to be 0.12 mrem /yr which represents less than 1% of the 25 mrem limit of the EPA standard as specified in 40 CFR 190.
The staff therefore concludes tiiere is no adverse impact from the release of radioactivity due to routine operation of the Hematite fuel fabrication plant.
The staff recognizes that the nearest resident (located one-half of a mile southwest of the facility) might not represent the potential maximum impact from the Hematite operation.
The staff estimated that the maximum impact in the unrestricted area could be at the nearest site boundary, 100 meters to the aorth of thhcenter30f the Oxide Building.
The X/Q at this locaticn of 1.48x10 sec/m.
If a critical individual were to live at this location in the future, the predicted annual lung dose would be 10.9 mrem / year, well below the 25 millirem limit.
The staff estimated that the airborne effluent release rate would have to be increased to greater than 733 pCi/ year if the facility were to exceed the 25 crem limit for a critical individual living at the nearest site boundary.
To insure ompliance with the regulations, the staff proposes a license condition requiring an action level 'n effluent releases.
Since the liquid effluent is not the major pr.'.hway in individual dose calculations, the action level will be br. sed on measured air-borne releases.
Even though the staff's analysis shows that an effluent release of over 733 pCi/yr would be necessary to exceed the 25 mrem limit to the critical individual at the nearest site boundary, considering present release rates of approximately 319 pCi/yr it is the staff's opinion that in order not to violate principles of ALARA, a somewhat lower action level should be defined. The proposed action level will be a reporting requirement unless circumstances warrant more strict enforcement.
The staff then recommends an action level on the release of airborne effluents to be at 150 pCi of U per quarter which is' equivalent to an annual lung dose to an infant at the nearest site boundary of about 20.5 mrem /yr. Accordingly, the staff recommends that the following conditions be added to the license:
2 22 1.
If the radioactivity in plant gaseous effluents exceeds 150 uCi per calendar quarter, the licensee shall, within 30 days, precare and submit to the Commission a report which identifies the cause for exceeding the limit and the corre the licensee to reduce release rates.ytive actions to be taken by If the parameters important to a dose assessment change, a report shall be submitted within 30 days which describes the changes in parameters and igcludes an estimate of the resultant change in dose commitment 2.
In the event that the calculated dose to any memb'er of the public in any consecutive 12-month period is about to exceed the limits specified in 40 CFR 190.10, the licensee shall take immediate steps to reduce emissions so as to comply with 40 CFR 190.10. As provided in 40 CFR 190.11, the licensee may petition the Nuclear Regulatory Commission for a variance from the requirements of 40 CFR 190.10.
If a petition for a variance is anticipated, the licensee shall submit the request at least 90 days prior to exceeding the limits specified in 40 CFR 190.10.
23 References 1.
Environmental Protection Agency, " Title 40 - Protection of the Environment, Part 190 - Environmental Radiation Protection Standards for Nuclear Power Operations," Federal Register 42(9):
2558-2561 (January 13, 1977).
2.
Combustion Engineering, Incorporated, Power Systems Group, Environmental Imoact Information, Hematite. Missouri Plant Site, Hematite, Missouri, (June 1975).
3.
STAR Program for On-Site Data Diffusion Climatology, WESD, Monroeville, Pennsylvania, (1972).
4.
" Meteorology and Atomic Energy," David H. Slade, Editor, USAEC, Division of Technical Information, pp.97-104, (July 1968).
5.
Snyder, W. H., and R. E. Lawson, Jr., " Determination of a Necessary Height for a Sttck Close to a Building--A Wind Tunnel Study," Atmosoheric Environment, Vol. 10, pp. 683-691, Pergammon Press, (1975).
6.
40 CFR 190, Environmental Radiation Protection Requirements for Normal Operations of Activities in the Uranium Fuel Cycle, Final Environmental Statement, Vol. 1, pp. 143-146, USEPA, (November 1976).
7.
U.S. Nuclear Regulatory Commission - Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Office of Standards Development, (July 1977).
8.
U.S. Nuclear Regulatory Commission, Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," (March 1976).
9.
Task Group of Committee 2, ICRP, Task Grouo on Lung Dynamics for Committee II of the ICRP, Health Physics, Vol. 12, (1966).
10.
Task Group of Committee 2, ICRP, The Metabolism of Comoounds of Plutonium and Other Actinides, ICRP Publication 19, Pergammon Press, Oxford, (1972).
- 11. Houston, J.
R., D. L. Strengh, and E. C. Watson, DACRIN - A Computer Program for Calculating Organ Dose from Acute or Chronic Radionuclide Inhalation, BNWL - B-389, Battelle Pacific Northwest Laboratories, Richland, Washington, (1975).
12.
M. H. Momeni, Y. Yuan and A. J. Zielen, The Uranium Dispersion and Dosime-try (UDAD) Code, NUREG/CR-0553, ANL/ES-72, Version IX, (1979).
- 13. NUREG-0172, Age-Specific Radiativn Dose Commitment Factors for a One-Year Chronic Intake, BNWL, (November 1977).