nuclear fuel services, inc. p o. box 337, ms 123 (423) 743 ... · restricted to collecting the...

Nuclear Fuel Services, Inc.P O. Box 337, MS 123Erwin, TN 37650

(423) 743-9141

EMal :http:/Aw1 w.otnfs.com

AIRBORNE EXPRESS 21G-02-0087GOV-01-55-04

ACF-02-0063

March 15,2002

DirectorOffice of Nuclear Material Safety and SafeguardsU.S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, DC 20555

References:

Subject:

1) Docket No. 70-143; SNM License 1242) Letter from NRC to B.M. Moore, Nuclear Fuel Services, Inc., (TAC NO.

L31567) - Blended Low-Enriched Uranium Project Environmental Report,Request for Additional Information, dated March 1, 2002

3) Meeting at NRC Headquarters to Discuss Request for Additional Informationfor the BLEU Project, held on March 8, 2002

4) Letter from B.M. Moore to NRC, Additional Information to Support anEnvironmental Review for BLEU Project, dated January 15, 2002, (21G-02-0005)

5) Letter from B.M. Moore to NRC, Supplemental Environmental Report forLicensing Actions to Support the BLEU Project, dated November 9, 2001(21G-01-0261)

NFS Responses to NRC's Request for Additional Information to Support anEnvironmental Review for the BLEU Project

Dear Sir:

Nuclear Fuel Services, Inc. (NFS) hereby submits responses to address the referenced Requestfor Additional Information (RAI) for the BLEU Project. As discussed with your staff at thereferenced meeting, NFS believes that the information contained herein is sufficient to addresseach of the comments specified in the RAI (Reference 2).

,\z>52e \8Il

B.M. Moore to Dir., NMSSMarch 15, 2002

21G-02-0087GOV-01-55-04ACF-02-0063

If you or your staff have any questions, require additional information, or wish to discuss this,please contact me, or Mr. Rik Droke, Licensing and Compliance Director at (423) 743-1741.Please reference our unique document identification number (21G-02-0087) in anycorrespondence concerning this letter.

Sincerely,

NUCLEAR FUEL SERVICES, INC.

B. Marie MooreVice PresidentSafety and Regulatory

JSK/lsn

cc:

Regional AdministratorU.S. Nuclear Regulatory CommissionRegion IIAtlanta Federal Center61 Forsyth Street, SWSuite 23T85Atlanta, GA 30303

Mr. David TurnerCNWRA (Division 20)6220 Culebra RoadSan Antonio, TX 78228

Mr. William Gloersen, Project InspectorU.S. Nuclear Regulatory CommissionRegion IIAtlanta Federal Center61 Forsyth Street, SWSuite 23T85Atlanta, GA 30303

Mr. Pat LaPlantCNWRATwinbrook Metro Plaza, Suite 21012300 Twinbrook ParkwayRockville, MD 20852

Mr. Dan RichSenior Resident InspectorU.S. Nuclear Regulatory Commission

B.M. Moore to Dir., NMSSMarch 15, 2002

21G-02-0087GOV-01 -55-04

ACF-02-0063

Attachment I

NFS Responses to NRC's Requestfor Additional Information Regarding Proposed Blended

Low-Enriched Uranium Project

Attachment IACF-02-0063

NRC Comment No. 1: The BLEU project will involve storage and use of hazardous and reactivechemicals such as sodium hydroxide (NaOH), concentrated nitric acid (HN03), ammonia (NH3)ammonium hydroxide (NH4 0H), and fuels. Chemicals such as fuel oil can beflammiable or explosive,and others may produce compounds that can be hazardous or explosive such as hydrogen (H2) andammonium nitrate (NH4NO3). Provide sufficient information on the chemicals and chemical processesbeing carried out to demonstrate safe handling of these materials during operations. This informationshould be at a level of detail sufficient to assess potential safety and environmental impacts. Whereverappropriate, reference existing documents that contain the information. Update the existing informationas needed to make it applicable to the present license amendment request. This information is needed sostaff can assess potential hazards, detection, and mitigation measures associated with the proposedprocessing and storage. Information requested includes:

(a) A list specifying each chemical (including concentration) to be used in the proposed processes forthe Blended Low Enriched Uranium (BLEU) Preparation Facility (BPF). Table I in Attachment 3 to theadditional information letter (Ref 1) does not identify the BPF chemicals.

* NFS Response to Comment No. l(a): The Building 333 BPF Process Flow Diagram shows wherechemicals will be used in the BLEU Prep. Facility (BPF).

* 70% nitric acid (HN0 3 ) solution will be used to dissolve the uranium materials, both highenriched uranium (HEU) and natural uranium (NU), to form uranyl nitrate solution. Thischemical will be purchased in bulk.

* 30% hydrogen peroxide (11202) solution will be added during nitric acid dissolution ofuranium oxides to reduce NOx emissions. This chemical will be purchased in containers,

* 30% sodium hydroxide (NaOH) solution will be used in combination with barium hydroxideand sodium nitrate to dissolve the aluminum in the UAIx alloy material. This chemical willbe purchased in bulk.

* 45% sodium nitrate (NaNO3) solution will be used with sodium hydroxide and bariumhydroxide to dissolve the aluminum in the UAIX alloy material. This chemical will bepurchased in bulk.

* Barium oxide (BaO) solid will be dissolved in water to form barium hydroxide (Ba(OH)2)solution. The BaO will be purchased in containers but the size has not yet been determined.The procedure for dissolving the BaO has not yet been developed but since the reaction willgenerate much heat, care will be taken such that the procedure and tank design control theheat. The barium hydroxide solution will be as concentrated in barium as possible and usedin combination with sodium hydroxide and sodium nitrate solutions to dissolve thealuminum in the UAIx alloy material. The barium will combine with any carbonate presentin the sodium hydroxide solution to minimize forming uranyl uranium carbonate, which aresoluble in sodium hydroxide.

* Tributyl phosphate, (C4H9)3PO4, will be the extractant chemical in the solvent for theliquid-liquid extraction system that will purify uranyl nitrate solutions. This chemical willbe purchased in containers,_

* Normal paraffin fluid (specifically Norpars 12 fluid, a ExxonMobil Chemical product thatis 98 mass% linear paraffins, primarily Cl l-C12) will be the diluent chemical in the solvent

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for the liquid-liquid extraction system that will purify uranyl nitrate solutions. This chemicalwill be purchased in_

* Sodium carbonate (Na2 CO3) solid will be dissolved in water to.form a 5% sodium carbonatesolution. The Na2 CO3 will be purchased in containers holding approximatealeach. This solution will be used to remove extractant degradation compounds from thesolvent in the uranium purification system.

* Process waste solutions (vapor condensate, wet scrubber effluent, sodium hydroxide solutioncontaining the aluminum, and raffinate from the liquid-liquid extraction system) will bedirected to two 800-gallon tanks in a new dike adjacent to the BPF. One tank will berestricted to collecting the basic waste solutions. The second tank will be restricted tocollecting the acidic waste solutions. These solutions will be pumped from the BPF to NFS'Waste Water Treatment Facility (WWTF) as necessary to be treated to meet therequirements of the NPDES permit. The basic and acidic solutions will be kept segregatedup to the time they are treated in WWTF.

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(b) Size and locations of tanks to be used for storage of chemicals and wastes together with the size ofrooms housing the tanksand the size and configuration of berms io be used for spill control. Forexa the number and size of the berms to be used for spill control of the 24 large _

uranyl nitrate tanks in the proposed Uranyl Nitrate Building (UNB) need to bespecified.

NFS Response to Comment No. l(b): Sizes and locations of storage tanks for chemicals and processwaste solutions are provided in Attachments II and III.

(c) Basic information regarding chemical reactivity and any new monitoring or leak detection plans forthe storage of chemicals and wastes associated with the proposed action(s). This information is neededto provide confidence that the potential for impacts from storage ofhazardous and radioactive materialshave been adequately assessed. This comment pertains to planned storage activities noted in thesupplemental environmental report (Ref 2) such as

*: Twenty-four tanks for storing uranyl nitrate solution in the UNBSec2.2.1.2.

* An tank for storing natural uranyl nitrate blend stock in the UNB(Section 2.2.1.2.2)

* Two storage tanks for Effluent Processing Building (EPB) effluentwaste (Section 2.2.12.4)

* HN03 , NH4 0H, and NaOH bulk chemical storage tanks in the BLEU Complex (Figure 4)* New waste tanks for acid, base, and wet scrubber effluent located in the BPF (Section 2.2.2.2)*: New waste water tank at the waste water treatmentfacility (WWTF) (Section 2.2.2.2)

NFS Response to Comment No. l(c): Detailed information concerning the controls that will beimplemented will be provided in the Integrated Safety Analysis (ISA) Summary necessary todemonstrate compliance with 10 CFR 70.61 Performance Requirements. As described in the referencedISA Planl, the hazards associated with the chemicals listed above will be evaluated as part of the ISAprocess.

To support the Environmental Review (10 CFR 51) a preliminary overview of these mitigative controlsare included in the table provided in Attachment II.

(d) An explanation of control schemes to ensure safe processing. For example, process controlmechanisms used to ensure safe calcinations where ammonium diurinate solids are converted to uraniumoxide should be described. This process has the potential to produce compounds that can be hazardousor explosive such as hydrogen (H2 ) and ammonium nitrate (NH4NO3). IfNFSplans to use a processthat is identical to or consistent with an NRC-approved process, then NES should state this and providea reference. Also, if there are differences between an NFSprocess and an approvedprocess, then NFS

'Letter from NRC to B.M. Moore, Nuclear Fuel Services, Inc. Amendment 31 (TAC NO. L3 1535) to ApproveIntegrated Safety Analysis Plan and Delete License Conditions S-28 through S-38, dated October 30, 2001.

4

...


should describe the differences and provide additional information lo demonstrate that the process willbe safe. This information is needed to provide confidence that planned processing can be implementedin a safe manner.

NFS Response to Comment No. 1(d): The process and process support systems that will be usedin the BLEU Prep. Facility follow:

* HEU Storage - The containers of HEU materials will be stored in a vault and a high securitystorage area. Descriptions for storage areas of this type appear in Chapter 15.10 of NRC LicenseSNM-124.

* HE U Metal Sampling - This workstation will be new. When the HE U metal is packaged at theY-12 National Security Complex, they will place metal button pieces and swarfs (chips) createdwhen the buttons were broken in containers. After opening the container at NFS, inside theworkstation, the sample material will be collected from the swarfs.

* HE UAlx Alloy Dissolution - NFS will use a different process for dissolving UAIX alloy. TheHE UAlx alloy will be provided to NFS in the form of solid ingots (right cylinders). In thisprocess the UAIX alloy ingot will be placed in a dissolver with geometry favorable to nuclearsafety where sodium hydroxide with sodium nitrate and barium hydroxide will trickle over theingot dissolving the aluminum thereby leaving the uranium as sodium diuranate solid. (NFS isalso investigating using a mechanical means to size reduce the ingot prior to being placed in thedissolver.) The sodium nitrate helps the dissolution reaction create ammonia rather thanhydrogen and the barium helps keep the uranium insoluble. Since some hydrogen will begenerated during this dissolution step, there will be controls that will dilute the hydrogen with airto a safe concentration. In the case of an upset, the addition of sodium hydroxide mixture will behalted which will stop hydrogen generation. The sodium diuranate will be separated from thesolution and then nitric acid will be used in a dissolver with geometry favorable to nuclear safetyto dissolve the sodium diuranate to uranyl nitrate solution. The uranyl nitrate will be filtered andthen collected in a weighing system where it will be measured for uranium content. The uranylnitrate solution will then be moved to columns and then fed to a liquid-liquid extraction systemto purify the uranium.

* Liquid-Liquid Extraction -This system will purify the uranyl nitrate solution using equipmentthat is described in Section 15.3.8 of NRC License SNM-124. This system though will havedesign features that will keep the potential for a fire low enough that a wet-pipe sprinkler systemwill not be needed. The purified uranyl nitrate solution will be held in columns while waiting toproceed to HEU to LEU downblending.

* HE U Metal Dissolution - This system will be new. The HE U metal pieces will be placed infavorable nuclear geometry furnaces were the combination of heat and air will change the Umetal to U oxide. The U oxide will then be moved to a dissolver with geometry favorable tonuclear safety where nitric acid and hydrogen peroxide will be used to dissolve the U oxide touranyl nitrate solution. The uranyl nitrate solution will be held in columns while waiting toproceed to HEU to LEU downblending.

* HEU to LEU Downblending - This system is described in Section 15.3.13 of NRC LicenseSNM-124. The two tanks, blendstock dissolver tank and enrichment blend tank will be largerthan the tanks in Section 15.3.13. ITe blendstock dissolver tank will holdwwhilethe enrichment blend tank will hold The controls on 2 3 5U concentration remainthe same.

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* LEU Product Certification - Section 15.3.14 of NRC License SNM-124 describes moving theLE uranyl nitrate solution to an evaporator feed tank and then converting the LE uranyl nitrate.The product in the BPF will be the LE uranyl nitrate so there will be a tank, like the evaporatorfeed tank, but the same size as.the enrichment blend tank. This tank will be used to hold the LEuranyl nitrate from the time the batch has been made until it is released to pump to the UranylNitrate Building at the BLEU Complex. The controls on 2 3 5U concentration in this tank are thesame as for the evaporator feed tank.

Figure 2 provides an overview of the BLEU Conversion Complex processes. The majority of theseprocesses have been operated safely for more than 20 years at the Framatome ANP Richland plant underNRC License SNM-1227. The areas that do not have a parallel in Richland are the Uranyl Nitratestorage area (UNB) and the Liquid Waste processing systems, indicated by the dashed borders on thediagram. Note that the Richland facility does routinely store and process uranyl nitrate solutions, but noton the scale of the UNB storage facility.

The UNB facility can store up to f of uranyl nitrate solution in twenty-fivestorage tanks. No other chemicals are used or stored in the UNB. UNB operations aremonitored/controlled via comprehensive instrumentation and a central control system. Spills areprevented by high integrity primary containment and continuous primary and backup level monitoring inall tanks, and secondary containment with leak detection. The only significant safety risk in the UNBoperation is nuclear criticality related. Comprehensive controls are in place to mitigate this risk asdocumented in the facility's nuclear safety and process hazards analyses.

The concentration and solidification of the concentrate for solid waste disposal are not practiced inRichland. The feed solution consists primarily of dilute sodium nitrate in water. It is concentrated in theevaporator by about a factor of 6, resulting in 400 g/l sodium nitrate solution for solidification and apurified overheads stream for disposal to the sewer. Evaporation of sodium nitrate solutions is acommon industrial unit operation. The central control system monitors process conditions and shuts offsteam to the evaporator if temperature and or pressure limits are exceeded. The carryover of ammonia insolution from the prior Ammonia Recovery operation could present some safety issues, but extensiveprocess controls are in place (feed tank and stripper bottoms pH, etc.) to prevent this. The only potentialhazard involved in the solidification step is operator exposure to excessive dust from the solidifyingagent. Containment and ventilation is provided as needed to preserve an acceptable operatingenvironment.

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Figure 2

ADU Conversion Process

UNB

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p.-

A 0;

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NRC Comment No. 2: References and descriptions are required regarding the fire protection programfor the proposed action and mitigation or control plans for specific hazards. This information is neededto provide confidence in the NFS approach to fire hazard mitigation and control at the proposed BLEUprojectfacilfties. Specifically, provide thefollowing:

(a) Documentation or references for the fire protection program that will be used for the proposedaction. Clarify whether a fire hazard analysis will be included in the integrated safety analysis and ifnot, provide the just fication.

NFS Response to Comment No. 2(a): As described in the referenced ISA Plan, NFS will evaluatecredible process upsets from external hazards, such as fires, severe weather, and seismic eventsnecessary to demonstrate compliance with the performance requirements specified in 10 CFR 70.61. Tosupport the ISA, NFS will perform a Fire Hazards Analysis (FHA) to identify credible accident scenariosthat may result in high or intermediate consequences and define the management measures that will beinstituted to comply with 10 CFR 70.61.

A listing of FHAs completed thus far, including the FHA for the Uranyl Nitrate Building to beconstructed at the BLEU Complex, is provided in Chapter 10, Section I of the referenced licenseamendment request2. Future FHAs that will be conducted for the remainder of the BLEU Complex willalso be documented in this section of the license. The FHAs will also provide the basis formethods/commitments that will be instituted to comply with applicable portions of the National FireProtection Association's (NFPA) Codes, as specified in Chapter 6 of NRC License SNM-124.

(b) Information on the approach to mitigate the consequence of hazardous vapor release in case of afire involving volatile compounds such as anhydrous ammonia and concentrated HN03.

NFS Response to Comment No. 2(b) As described in the referenced ISA Plan, NFS will identifycredible accident scenarios involving hazardous chemicals (e.g., anhydrous ammonia and concentratednitric acid) that result in "high" or "intermediate" consequences. For these accident scenarios, ItemsRelied On Safety (IROFS) must be instituted (and maintained reliable) to mitigate the consequences toan acceptable level of risk, as specified in 10 CFR 70.61.

(c) Information on the strategy to ensure that afire involving BLEU Complex propane and dieselfuelstorage and use does not propagate to other nearby buildings, tanks, and structures and vice versa.

NFS Response to Comment No. 2(c): As described in the commitments identified in NRC CommentNo. 2(a), NFS will perform a EHA and ISA for special nuclear material (SNM) processes located at theBLEU Complex. An evaluation of credible fire scenarios that involve or are initiated by flammableagents (e.g., propane and/or diesel fuel) will be included in the ISA/FHA. Mitigative controls (IROFS)will be instituted and maintained reliable to ensure that accident scenarios involving fires are compliantwith 10 CFR 70.61. Moreover, these safety evaluations are inclusive of fire that may originate frompropane or diesel fuel storage and propagate to nearby buildings and vice versa. The FHA that will be

2 Letter from B.M. Moore to NRC, License Amendment Request to Support the Uranyl Nitrate Building at theBLEU Complex, dated February 28, 2002 (21G-02-005 1).

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submitted also provide the basis for methods/commitments that will be instituted to comply withapplicable portions of the NFPA Codes, as specified in Chapter 6 of SNM-124.

NRC Comment No. 3: Attachment 24 of the additional information letter (Ref 1) contains dose estimatesfrom radioactive emissions to air and water from the proposed actions. Provide the technical basis forthese dose calculations including the bases for effluent estimates and key assumptions. Transparency inthe documentation of calculations is necessaryfor staff to understand the technical basesfor estimates.

NFS Response to Comment No. 3: The technical basis used to calculate dose estimates is provided inAttachment IV.

NRC Comment No. 4: Identify any effluent permit (eg., air or water discharge) changes that will berequested as part of the proposed action. Section 4.1.1.2.1 of the supplemental environmental report(Reft 2) indicates that NFS will seek modifications to existing air permits for the BPF operation. Staffinterprets this to mean NFS will seek to modify the existing permit for the main stack Define"modifications to existing air permits "for the BPF operations and discuss any potentialfor degradation

in ambient air quality from these modifications. Information on changes to existing permitted releaseamounts is necessary to assess any changes to local air quality from the proposed action.

NFS Response to Comment No. 4: NFS is requesting an air pollution control construction permit beissued by Tennessee's Department of Environment and Conservation (TDEC), Division of Air PollutionControl to modify the existing air pollution control permit for the main stack (#416). Modification isnecessary to allow material input changes and installation of additional process and ventilationequipment. This modification deletes the processes in the now closed 200 Complex and incorporatesanticipated expansions of the Fuel Manufacturing Facility, as well as adding the BPF operations. Themodification of the air pollution control permit will not result in an exceedance of the National AmbientAir Quality Standards (NAAQS) as regulated by TDEC.

NFS currently has a NPDES permit allowing treated process wastewater to be discharged to theNolichucky River through Outfall 001. Treatment of BPF process wastewater will not require amodification to the current NPDES permit because no new processing chemicals will be used nor willthe additional throughput exceed permitted discharge limits.

NFS currently has a NPDES storm water discharge permit. This permit will not require modification asa result of construction and operation of the BLEU Complex. A separate storm water permit will beobtained for construction and operation of the BLEU Complex.

NRC Comment No. 5: Section 4.1.1.1.2 of the supplemental environmental report (Ref 2) indicates thatthe liquid effluent from the BPF will be processed at the NFS WWTF. Confirm the ability of the WWTFto manage the increased load from expected radiological and chemical emissions from the proposedaction. This information will support an assessment of the magnitude of any impacts from the proposedaction in relation to existing and past operations.

NFS Response to Comment No. 5: Historically, the wastewater treatment facility has treated processwaste water generated from down blending operations that occurred in the 200 Complex. The

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radionuclide characteristics and chemical parameters associated with the BPF operation will be similar tothat of effluent generated from the former 200 Complex operations. Wastewaters generated from theBPF operation and treated at the WWTF will not require a modification to the NPDES permit.

'NRC Comment No. 6: Provide an evaluation of any potential for surface water impacts resulting fromconstruction of the proposed BLEU Complex (e.g., erosion) and any proposed associated mitigation orcontrol measures.

NFS Response to Comment No. 6: The BLEU Complex site is relatively level. Surface water runofffrom the BLEU Complex Site drains to ditches located on the northwest site boundary. These drainageditches exit to Martin Creek. As required by the Tennessee Department of Environment andConservation (TDEC), Division of Water Quality, a storm water construction permit will be obtainedprior to any land disturbing activities. Erosion and sediment control measures, such as straw bales andsilt fences, will be used to mitigate sediment run off into the drainage ditches and Martin Creek. Thesesediment control measures in combination with the level topography of the site will reduce the potentialfor surface water impacts during construction of the BLEU Complex.

NRC Comment No. 7: Provide the location and type of existing and proposed environmental mediamonitoring locations. This information may be subdivided by type of monitoring station. Thisinformation is necessary to provide confidence in the adequacy of the monitoring program to detectpotential releases from the proposed action. The following provide additional details to support thisrequest:

(a) Section 4.1.2 of the supplemental environmental report (Ref 2) indicates more groundwatermonitoring sites will be added to the monitoring locations specified in the environmental report (Ref. 3).Include in an updated figure the proposed groundwater monitoring locations for the new facilitiesassociated with the proposed action. Indicating which of the three zones (alluvial aquifer, shallowbedrock aquifer, or intermediate bedrock aquifer) the wells will be screened in and the number of wellsscreened in each zone. Staff needs this information to update Table 3.11 of the license renewalenvironmental assessment (Ref 4). The request for the table update was originally in a letter from M.Adams to B. Moore (Ref. 5). With the addition of new wells, also update the groundwater monitoringwell depth range. If this information is not available at this time, NFS should indicate when it will beavailable for NRC review.

NFS Response to Comment No. 7(a): Appropriate administrative and engineered controls will be inplace at the BLEU Complex to reduce the potential for spills which could lead to groundwatercontamination. Examples of engineered controls to prevent spills include dikes for storage tanks, levelcontrol indicators, and installation of above ground piping. Administrative controls will include revisionof the existing Spill Control and Counter Measures Plan and implementation of appropriate proceduresto minimize spills and clean them up in the event they occur.

At a minimum, one upgradient and three downgradient wells will be installed to monitor groundwater.Information regarding the location, number, screening interval and depth of monitoring wells is not yetavailable. This information is expected to be available in third quarter 2002.

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Because the location of any potential wells has not yet been determined, this information (i.e., screening.zones) was not included in an update to Table 3.1.1 of the referenced Finding of No Significant Impactand Environmental Assessment (EAIFONSI)3 .

(b) Update thefigure of monitoring well locations (Ref 1, Attachment 20) to include the surface area ofthe NFS site where the BLEU Complex will be located.

NFS Response to Comment No. 7(b): Attachment V provides an updated drawing which includescurrent monitoring well locations and the surface area of the BLEU Complex site.

NRC Comment No. 8: The supplemental environmental report (Ref. 2) states that NFS environmentalmedia monitoring (except groundwater) will be covered by existing locations specified in theenvironmental report (Ref 3). The environmental report (Figure 12) indicates no air, vegetation, or soilenvironmental media monitoring stations are located to the immediate east, west, or south of the BLEUComplex (except for the background station) despite frequent winds to the south as identified in theenvironmental report (Ref 3) Figure 7. Clarify why areas adjacent and downwindfrom the proposedfacility are not to be covered by monitoring stations. This clarification should present the technicalbasis for considering the existing environmental monitoring locations to be adequate for monitoring theproposed new facilities. This information is necessary to provide confidence in the adequacy of themonitoring system to detect potential releases from the proposed action.

NFS Response to Comment No. 8: Additional monitoring locations for environmental media (e.g., air,vegetation, or soil) will be evaluated and submitted in the applicable license amendment request.

NRC Comment No. 9: NRC previously requested in the letter from M. Adams to B. Moore (Ref 5) thatNFS provide updates for Tables 4.1 and 4.5 of the license renewal environmental assessment (Ref. 4),which summarize the effluent and environmental monitoring programs, respectively. The additionalinformation letter (Ref 1) provided an update to Table 4.1 but did not update Table 4.5. If anyenvironmental monitoring stations will be added, then update Table 4.5. Include environmentalmonitoring of surface water, soil, sediment, vegetation, and groundwater and include the number ofmonitoring stations, sample type, collection frequency, parameters analyzed, minimum detection levels,and action levels or permit limits.

NFS Response to Comment No. 9: Additional monitoring locations for environmental media (e.g., air,vegetation, or soil), have not yet been designated. The environmental monitoring program will beevaluated and submitted in the applicable license amendment request.

NRC Comment No. 10: Additional information is required to describe the proposed radiologicalmonitoring of the storm water run-offfrom the BLEU Complex to Martin Creek This information isneeded to complete the description ofthe proposed action.

3 Letter from NRC to T.S. Baer, Finding of No Significant Impact and Environmental Assessment (TAC NO.L30873), dated January 29, 1999.

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Anachment IACF-02-0063

(a) Sections 2.2.2.3.2 and 4.1.1.1.2 of Mhe supplemental environmental report (Ref 2) indicate that theNational Pollutant Discharge Elimination System permit would regulate the storm water monitoring.Indicate whether or not the storm water will be monitoredfor radiological components.

NFS Response to Comment No. 10 (a): 'The current NFS NPDES Storm Water Permit does not requiremonitoring for radiological attributes. However, storm water runoff from the BLEU Complex will bemonitored for radiological constituents as described in Chapter 5 of the referenced license amendmentrequest for the UNB.

(b) Section 4.1.1.2.2 of the supplemental environmental report (Ref. 2, Figure 4) shows one storm watermonitoring point and one "potential " monitoring point. Clarify the status of the "potential " monitoringpoint and provide the basis for deciding whether it will be used. This information is needed to completethe description of the planned monitoring system.

NFS Response to Comment No. 10 (b): The potential monitoring point was identified in preliminarydesigns as a possible monitoring point for parking lot runoff However, due to design changes, all stormwater runoff from the site will exit at one location and the potential monitoring point will not be used.

NRC Comment No. 1!: Additional information is needed on the expected airborne emissions from theWVVTF to complete the staff understanding of the effluent management systems for the proposed action.The supplemental environmental report (Ref 2) does not specifically address airborne effluents from theWWTFfor the proposed action; however, Table I of Attachment 22 in the additional information letter(Ref 1) includes estimates of gaseous effluents. Identify which stack releases effluent from the WWTFand add the appropriate information to complete Attachment 4 (characterization of stack) andAttachment 14 (permitting and monitoring) of the additional information letter (Ref 1). This informationis provided for all other stacks associated with the proposed action. Clarify whether the term"gaseous, " when referring to effluents, includes all airborne effluents or just those in the gas phase.

NFS Response to Comment No. 11: The radiological emissions from the WWTF are not dischargedthrough a stack, therefore, these sources were modeled as fugitive emissions. The technical basis for thecalculated dose reported from the WW1TF is contained in Attachment IV.

NRC Comment No. 12 Clarify why the proposed sampling frequency for stacks of the UNB, oxideconversion building, and effluent processing building are different from the proposed samplingfrequency for stacks classified as "other uranium stacks" shown in Table 4.1 of the license renewalenvironmental assessment (Ref 4). Attachment 14 of the additional information letter (Ref 1) prescribesweekly sampling for the proposed stacks while the license renewal environmental assessment specifiesdaily sampling for "other uranium stacks." The technical bases for changes to existing programs areneeded to ensure the potentialfor environmental impacts have been considered.

NFS Response to Comment No. 12: NFS will sample air emissions from the UNB (Stack 501)continuously/daily, as described in Table 5.1, Combined Releases from Other Stacks of SNM-124. Thiscommitment is consistent with the stack sampling frequency contained in Table 4.1 of the referencedFONSI/EA. Future consideration will be given to modifying the frequency of sampling uranium stacks

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to a weekly basis instead of daily; however, this request will be incorporated into a future licenseamendment request.

NRC Comment No. 13:. Clarify the characterization of gaseous effluezts from the effluent processingbuilding so staff can describe the proposed effluents completely in the environmental assessment.Attachment 4 of the additional information letter (Ref. 1) identifies ammonia as the only potentialeffluent from the effluent processing building: however, Table 16 from the supplemental environmentalreport (Ref 2) provides an estimated amount of uranium release from the same building. Provide acomplete listing of expected effluents from the effluent processing building.

NFS Response to Comment No. 13: The radiological characterization data for the gaseous effluentsdischarged from the Effluent Processing Building are contained in Attachment IV. These data provide acomplete listing of specific radionuclides that are expected to be discharged from the Effluent ProcessingBuilding.

NRC Comment No. 14: Describe the radiation protection plan/procedures that will be used to ensure allproposed actions are in compliance with 10 CFR Part 20. While NFS has an existing radiationprotection plan that is likely applicable to the proposed actions, a statement should be providedregarding whether modifications will be needed to the existing radiation protection program to ensureall activities related to the proposed actions are in compliance with 10 CFR Part 20.

NFS Response to Comment No. 14: NFS' Radiation Protection Program is currently described inChapters 3 and 12 of SNM-124. With the exception of describing methods to comply with 10 CFR20.1301, these sections of SNM-124 contain commitments/descriptions of methods used to comply with10 CFR 20. No significant changes to NFS' Radiation Protection Program are expected to support thislicensing action. However, minor administrative changes to NFS' Radiation Protection ProgramProcedures may be required to incorporate the addition of the BLEU Complex.

As described in the referenced FONSIIEA, NFS has previously been excluded from complying with thedose constraint specified in Environmental Protection Agency's (EPA) Fuel Cycle Standard (40 CFR190) because the principal activities conducted at the site were not directly supporting "the production ofelectric power for public use utilizing nuclear energy". However, changes to the environmental safetyprogram may be necessary to comply with this more limiting regulation that is now required due to thenature of the BLEU Project. To comply with the more limiting annual dose constraint of 25 millirem(dose equivalent to whole body or limiting target organ), NFS has proposed use of occupancy factors asdescribed in NUREG-17364 in Chapter 13 of the referenced license amendment request. Albeit newdose assessment methods have been proposed, the change to the regulatory basis further limits the annualdose standard from 100 millirem (10 CFR 20.1301) to 25 millirem.

NRC Comment No. 15: Update the datafor tornado recurrence in the Unicoi County, Tennessee, region.The information provided on tornadoes ip. 341) in the supplemental environmental report (Ref 2) is at

4 Consolidated Guidance: 10 CFR Part 20 - Standards for Protection Against Radiation (NUREG-1736).

13


least 18 years old. This information is. needed to ensure the environmental assessinent. is based oncurrent information.

NFS Response to Comment No. 15: The National Weather Service has reported no other tornados inUnicoi C6unty, Tennessee. Between 1950 and 2000, Unicoi County, Tennessee has experienced onetornado (Ref.1). Available 2001 data indicates no other tornados have occurred in Unicoi County5 .

NRC Comment No. 16: The supplemental environmental report (Ref. 2) indicates there have been recentchanges to the 100-yearfloodplain analysis conducted by the Federal Emergency Management Agency.Provide an updated map of the 100-year floodplain. This information is needed to ensure theenvironmental assessment is based on current information.

NFS Response to Comment No. 16: The current map of the 100 year flood plain is provided inAttachment VI.

NRC Comment No. 17: Clarify whether the State Historic Preservation Office has been consultedregarding the proposed action. The environmental report (Ref. 3) indicates a Native Americanassociation existed within the area (eg.. the Overhill Cherokee once lived in the region). Although mostvillages were located 128 an [79.5 mij southwest of NFS, the NFS area may have been usedfor huntingand gathering activities. Although there are no known sites within the NFS protected area, it is not clearin the supplemental environmental report (Ref. 2) whether appropriate consultation with appropriatetribal officials has been conducted.

NFS Response to Comment No. 17: As stated in the 1996 Environmental Report, NFS has noknowledge of pre-historic or historic archaeological sites on the NFS plant site and no National Registerof Historic Places are identified as being located on the NFS site. The NFS facility was constructed inthe late 1950's. Several buildings have been added over the years and other land disturbing activitieshave been conducted since the late 1950's. NFS has no knowledge of pre-historic or archaeologicalartifacts being encountered during these activities. Additionally, the Tennessee Historical Commissionhas evaluated the northern portion of the plant site and determined that it did not contain any listedNational Register Historical Places or eligible properties6 . NFS believes the historic characteristics ofthe North NFS plant site are similar to the southern plant site. However, to clarify this issue, NFS hassubmitted a letter to the Tennessee Historical Commission requesting a historical evaluation of theproperty. Per a phone conversation with the Tennessee Historical Commission on March 14, 2002, theyhave not identified the proposed BLEU Complex Site as having historical significance. NFS willprovide NRC a copy of the Historical Commission's letter when it is received.

NRC Comment No. 18: Clarify whether construction activities will be monitored for archeologicalvalue. The supplemental environmental report (Ref. 2) does not provide any information on this issue.

5 Hart, J. Janish, P., Severe Plot Historical Severe Weather Report Database, Version 2.0, National Weather ServiceStorm Prediction Center, Norman, Oklahoma, February 1999. Data files include 1950 through 2000.

' Letter from NRC to B.M. Moore, Nuclear Fuel Services, Inc. North Site Decommissioning Plan EnvironmentalAssessment and Finding of No Significant Impact (TAC NO. L31033), dated May 3, 2001.

14


This information is needed to ensure potential archeological resources are not impacted by the proposedconstruction.

NFS Response to Comment No. 18: NFS has no knowledge of the presence of pre-historic or historicarchaeological artifacts at the proposed BLEU Complex site. As stated in NFS' response to NRCComment No. 17, NFS will obtain clarification on the historical significance of these properties from theTennessee Historical Commission. If the Tennessee Historical Commission agrees with NES' evaluationof historical significance then the site will not be monitored for archaeological value. However, if thesite is identified as having archeological value, then the site will be monitored in accordance with StateRegulations.

NRC Comment No. 19: Provide information on potential seismic hazard at the site. Also provideinformation on the relationship between possible seismic activity and the design offacilities to be used inthe BLEU project. The ground acceleration that buildings and storage facilities will be constructed andconfigured to withstand should be defined. This information is needed to provide confidence that designrequirements are sufficient to mitigate potential seismic hazards.

NFS Response to Comment No. 19: Performance Technologies, Inc. conducted a seismic analysis7, asrequired by License Condition S-28 of SNM-124 in Calendar Year 2001 for the NFS site. As describedin this report, a peak ground acceleration of 0.06 g with a return period of 1000 years was calculatedusing site-specific parameters obtained from the NFS site.

NFS is required to address the "Baseline Design Criteria" in the design of new facilities or processesduring the ISA process to ensure that the design provides adequate protection against natural phenomena(e.g., earthquakes) as described in 10 CFR 70.64 Requirements for New Facilities or New Processes atExisting Facilities. The new facilities at the BLEU Complex will be constructed to meet the standardsspecified in the Southern Building Code. This standard provides assurance that new facilitiesconstructed at the BLEU Complex will comply with the 10 CFR 70.64 requirements.

While 10 CFR 70.64 states that retrofits are not required to existing facilities (like the BPF) that maycontain new processes, NFS intends to upgrade the BPF to meet the Southern Building Codespecifications. This will ensure that the BPF will also withstand natural phenomena events.

NRC Comment No. 20: Update or clarify the inventory of public and private water supply wells andsprings within an 8-km [5-mi] radius of the site. Table 14 of the environmental report (Ref 3) indicatesthere were six public water supply wells within a 8-km [5-miJ radius of NFS, while the license renewalenvironmental assessment (Ref 4) indicates there were seven such wells. Clarify whether the watersupply wells are screened in a groundwater system that is connected to the aquifer underlying the site ofthe proposed action. The current number and location of groundwater wells is importantfor describingthe existing environment and understanding the potentialfor environmental impacts on groundwater.

'Seismic Hazards Analysis of the NMS Nuclear Fuel Fabrication Plant in Erwin, Tennessee, Prepared byPerformance Technologies, September 27, 2001.

15


NFS Response to Comment No. 20: Table 14 of the environmental report indicates that there were fivepublic water supply wells within a 3-mile radius of the NFS facility. This information is based on thePublic Water Systems database for Unicoi and Washington Counties. Section 3.6.2 -of the EnvironmentalAssessment End Finding of No Significant Impact report indicates that -there were seven publicgroundwater supply wells within an 8-lkm (5 mile) radius of the site. Both of these statements appear tobe correct but the disconnect is in the radius of search. The 3-mile radius search has been used moreextensively in the past (i.e., injection permits) and is more relevant to the NFS facility based on theregional flow regime. Therefore the five public water supply wells within a 3-mile radius of the NFSfacility will be discussed in terms of the of hydrostratigrahic formations and how they relate to the NFSfacility.

One public water system well was listed on the Public Water Systems database for Unicoi County withinI mile from the NFS facility. The groundwater well, approximately 0.75 miles northeast (up-gradient) ofthe NFS facility, is owned by Erwin Utilities and listed as Railroad Well. This well appears to bescreened in the same hydrostratigraphic formation that underlies the NFS facility. However, the well islocated up gradient of the NFS facility and modeling performed in 1996 indicates that groundwaterwithdrawn from the Railroad Well does not originate beneath or down-gradient from the NFS facility.

Erwin Utilities obtains water from one well (Birchfield Well) and one spring (O'Brien Spring) locatednortheast of the NFS facility. The Birchfield Well is not located down gradient from the NFS facilityand is not screened in the same hydrostratigraphic formation that underlies the NFS facility. TheO'Brien Spring is not located down gradient from the NFS facility and the source does not appear to befrom the same hydrostratigraphic formation that underlies the NFS facility.

USA Raft, Inc. and Nolichucky Gorge Campground each obtain water from springs located south of theNFS facility. Neither spring is located down gradient of the NFS facility nor does the source appear tobe from the same hydrostratigraphic formation that underlies the NFS facility.

Additionally, two privately owned wells and one spring have recently been identified as being locatedwithin a three mile radius of the plant site. These wells and spring are located north-northwest of theNFS plant site and across the Nolichuckey River. Completion data on the wells is not known; however,it is not believed that the capture zone of these wells lies beneath the NFS site. Hydrogeologiccharacterization of the NFS vicinity indicates a groundwater flow regime where groundwater exits to thesurface at "sinks" such as the Nolichuckey River. Therefore, water on the opposite side of the river ofNFS flows toward the Nolichuckey River. The origin of the spring is not known, however, it is likelythat the watershed area which feeds the spring is located to the mountains north of the spring.

NRC Comment No. 21: Provide a discussion of the hydrostratigraphic units and associated hydroiogyunderlying the proposed site for the BLEU Complex. This is requiredfor a complete description oflizeaffected environment, and for assessing the potential for environmental impacts on groundwater. Thisinformation will also support the staff evaluation of new monitoring well locations near the propoedfacilities.

NFS Response to Comment No. 21: The proposed BLEU Complex is located southwest and adjcentto the active NFS plant site. Extensive characterization has been conducted on the plant site awd a

16


portion of the proposed BLEU Complex site. Therefore, there is sufficient data to conclude that thehydrostratigraphic units and associated hydrology underlying the proposed site for the BLEU Complex isthe same as that of the NFS site. A discussion of the hydrostratigraphic units and associated hydrologyunderlying the NFS facility is described-in Sections 3.5 and 3.6 of the environmental report.

NRC Comment No. 22: The supplemental environmental report (Ref 2) indicates that (i) outfall 001 islocated at mil 94.6 on the Nolichucky River, (ii) the US. Geological Survey Embreeville gauge station isdownstream at mile 96.8, (iii) and the Jonesborough intake is downstream at mile 86.8. Mile markervalues are continuous and monotonic, therefore it is not possible for both markers 96.8 and 86.8 to bedownstream from 94.6. Clarify this information.

NFS Response to Comment No. 22: The U.S. Geological Survey Embreeville gauge station is locatedapproximately 2.2 miles upstream of the Jonesborough water intake (mile 86.8), not 2.2 miles upstreamof NFS outfall 001. The Embreeville gauge station is located at mile 89.0, not mile 96.8 as initiallyreported in the supplemental environmental report.

NFS WWTF Outfall 001 Mile 94.6USGS Embreeville gauge station Mile 89.0Jonesborough water intake Mile 86.8

NRC Comment No. 23: A reference or technical basis is requiredfor the statement (Ref 2. p. 3-6) thatno known threatened or endangered species are known to potentially reside on the NFS site. Theresponse should address both plant and animal species. This information is needed to complete thedocumentation for the environmental assessment.

NFS Response to Comment No. 23: Table 14 (p. 3-6) of the Supplemental Environmental Reportpresents federally listed threatened and endangered animal species known to potentially exist in the areasurrounding NFS to include all of Unicoi County, Tennessee. The Tennessee Department ofEnvironment and Conservation, Division of Natural Heritage8 has published a list of threatened andendangered species according to quarter quadrants. The BLEU Complex and NFS are located in thesoutheast quadrant of the Erwin quadrangle. No federally listed threatened or endangered plant or animalspecies are identified by the State of Tennessee as residing in the southwest or southeast quadrants of theErwin quadrangle. Based on historical information, the BLEU Complex site was previously used foragricultural purposes and endured continuous disturbance. It is likely that any potential threatened orendangered plant species would not exist because of the previous land use Therefore, NFS believes thatno indigenous plant or animal species would be affected by the construction of the BLEU Complex onthis site.

NRC Comment No. 24: The supplemental environmental report (Ref 2) provides "backgroundradioactivity" data for gross alpha (Table IS). NFS states that these measurements are for "mediapotentially affected by NFS operations. " This is inconsistent with the NRC definition of backgroundradiation in 10 CFR Part 20 which would exclude areas affected by NFS operations. Provide

'Tennessee Department of Environment and Conservation, Division of Natural Heritage, Nashville, TN.http://www.state.tn.us/environment/nhkiq/qqindex.htm. Information retrieved on March 2, 2002.

17


measurements, of background radiation that are consistent with the NRC definition. Also provide atechnical basis for limiting the reported measurements to gross alpha emissions.

NFS Response to Comment No. i4: Table 15 provides background radioactivity data.for ambient air,soil, sediment and water.. The terminology "Media Potentially Affected by NFS Plant Operations"means that these media (air, soil, sediment and water) may potentially be affected by plant operations.This does not mean that the sample locations and data presented in Table 15 are contaminated by NFSplant operations. Media potentially affected by NFS operations are routinely monitored and compared tobackground radioactivity. Background locations are monitored to determine background radioactivitylevels in the vicinity of NFS for the following media: ambient air, sediment, soil, vegetation, and water.Data from the background monitoring locations (i.e., those located in unaffected areas consistent with theNRC's definition of background), averaged over the period of 1996 through 2000, are shown in Table 15(page 3-7).

Currently, the major dose contributing radionuclides at NFS decay by alpha particle emission. Internaldoses attributable to alpha emitting radionuclides account for the majority of the potential dose tomembers of the public, attributable to NFS radionuclides. Therefore, SNM-124 only specifies grossalpha action levels for sediment, soil, vegetation, and groundwater. SNM-124 does specify gross betaaction levels for ambient air samples, but the gross beta concentrations at NFS' offsite ambient airsampling locations are routinely below the action levels and less than 2 times the backgroundconcentration. Therefore, although gross beta concentrations are routinely monitored at all samplinglocations and for all sample media, this information was not included on Table 15.

NRC Comment No. 25: Table 17 ofSection 4.1.1.2.1 of the supplemental environmental report (Ref 2)indicates several air pollutants are currently at the allowable limit. The addition of the estimatednitrogen oxide emissions from the proposed BLEU Complex (Rev. 2, Table 18) to the current estimatedactual emission (Table 17 of the supplemental environmental report) would result in an overall nitrogenoxide emission that would exceed the allowable limit (Table 17 of the supplemental environmntalreport). Describe NFS' approach for attaining compliance with the regulatory limits with the additionalBPF and BLEU air emissions. This information is needed to clarify that the potential impacts lo airqualityfrom the proposed action have been assessed.

NFS Response to Comment No. 25: The allowable emission limitations presented in Table 17 (par 4-2) represents a sum of allowable emission limitations from all NFS air quality permits in effect as of9/6/2001. Each air pollution source has allowable emission limitations based on material input anddesign criteria. Prior to constructing an air pollution source, application must be made for an air polhimoncontrol construction permit. The application requires all material inputs and emission estimate beidentified and quantified. After construction is complete, the approved construction permit conditionsbecome the operating permit. NFS' approach for complying with regulatory requirements is to submit anapplication for an air pollution control construction permit for each new emission source (BLEUComplex) according to the planned construction schedule. The same process is required for exitingsources (main stack #413) where material inputs and operational parameters will change (e.g., BLEUPreparation Facility). Once air permits are issued, NES attains compliance by meeting the pernitconditions.

18


NRC Comment No. 26: Update with current information the discussion on Prevention of SignificantDeterioration in the supplemental environmental report (Ref 2, p. 3-1). Reference is made to a 1996 U.S. Department of Energy report stating that no Prevention of Significant Deterioration permits have beenrequiredfor any emission source at NF&

NFS Response to Comment No. 26: Since the promulgation of Environmental Protection Agency's(EPA) Prevention of Significant Deterioration (PSD) regulations (40 CFR Part 52.21), no PSD permitshave been required for any emission source at NFS. To qualify for a PSD permit, the source must beproposing a major modification or the source must already be major and is proposing a significantincrease. NFS is not a major source. The definition of significant increase is defined in the regulationsas a single modification that results in a net emission increase of 250 tons per year or more of a regulatedpollutant. NFS has not approached this level of emissions for any pollutant nor will it with projectedemissions from the proposed licensing actions.

NRC Comment No. 27: Provide additional information on the radiological history and status of the soilat the location of the proposed BLEU Complex construction. NFS has identified contamination in thearea from a number of radionuclides and has reduced this contamination by removing soil. Plannedconstriction is expected to excavate 2,550 m3 [90, 000 23] of soil as described in the supplementalenvironmental report (Ref. 2). Attachments S and 12 of the additional information letter (Reft 1) indicatethat an initial gamma survey was conducted to identify areas of contamination. The gamma survey wasfollowed by soil sampling (to a depth of 7.6 cm [3 in] following excavation of 0.5 in [1.5ft] of soil) andisotopic analysis to determine more precise concentrations in the high gamma areas. 7te attachmentsprovide limited information on soil survey results used to determine postremediation concentrations anddose calculations for planned construction activities. Provide the following to clarify the radiologicalstatus of the area. This information is needed to ensure appropriate plans are in place to maintainradiological safety during construction and provide the necessary technical bases to assess potentialenvironmental impacts.

(a) Information on the radiological history ofthe area (ie., suspected origin of contaminants).

NFS Response to Comment No. 27 (a): Based on personnel interviews and historical aerialphotographs of the site, in the late 1960's the northwest comer of the BLEU Complex site wastemporarily used to store process equipment purchased from another facility. The equipment was eithertemporarily moved out of the nearby 310 Warehouse or it was temporarily placed in the site's northwestcomer because it could not be placed in the warehouse due to space limitations. The temporary storageof items intended for the 310 Warehouse is the most likely origin of the northwest corner's contaminants.

(b) Additional details regarding the initial gamma survey including scan minimum detectableconcentrations for the radionuclides of concern, survey locations, and scan duration at each surveylocation.

NFS Response to Comment No. 27 (b): The initial gamma survey performed in May of 2001 was notperformed to determine if the area was "clean" but was a scoping survey performed to determine thegeneral radiological status of the site. Scan minimum detectable concentrations (MDCs) for the

19


radionuclides of concern were not calculated because-it was a scoping survey conducted to scan forpotential fission products which may have been present as a result of Studsvik processing activities. Thescan MDCs were not calculated after the survey was conducted because the scan rate was not recorded.The scan rate is a variable in the equation for determining scan MDCs. However, typical scan MDCsare provided in Table 6.4. of NUREG 1507 and are as follows:

pCilg

Am 31.5Th-232 1.8

The May 2001 survey included the entire area of the BLEU Complex site but covered much less than100% of the area. The survey was a walkover survey and only locations of elevated areas (greater than1.5 times background) were recorded. Static surveys were not performed at discrete locations soinformation about scan durations at survey locations is not available.

The gamma survey performed in June of 2001 was a walkover survey conducted in the northwest comerof the site to define the area to be excavated. Samples were collected from elevated areas to determinethe required depth of excavation.

The gamma surveys performed in September and October of 2001 were walkover surveys conducted inthe excavation areas. Samples were collected from elevated areas to determine if the elevated soilidentified during the gamma survey had been removed.

(c) Description of the technique used to determine isotopic concentrations in the soil samples.

NFS Response to Comment No. 27 (c): The isotopic uranium, thorium, plutonium and americium datapresented in Attachment 5, Table 1 of the additional information to support an Environmental Review forthe BLEU Project were analyzed by alpha spectroscopy. The plutonium-241 and technetium-99 datawere analyzed by liquid scintillation. O'Brien and Gere Laboratory in Syracuse, NY performed theanalyses.

(d) Confirmation that all significant levels of contaminants have been identified and removed at theproposed construction site.

NFS Response to Comment No. 27 (d): NFS has defined significant levels of contamination for theproposed BLEU Complex Site as levels that could give a 25 mrem total effective dose equivalent(TEDE) to any member of the public during construction of the BLEU Complex. Once construction ofthe nuclear facility is complete the most significant exposure pathway for members of the public will beeliminated. Soil concentrations equivalent to 25 mremn/yr for a construction worker scenario areprovided in Revision I of the NFS document titled Potential Dose Due to Radiological Contaminants inNorth Site Soil and Groundwater (Appendix D, page D-327).

Radiological contamination has been found at a few locations, which were limited to a small portion (i.e.,<5% of the site) of the proposed site, in the northwest comer of the site. These locations were initiallyidentified by a gamma contamination survey that was performed on the proposed site in May 2001. The

20


gamma survey was performed using a judgmental straftegy intended to represent each portion of the site,and was not intended to cover 100% of the site. Soil samples collected from the elevated locationsindicated that the sum of fractions (SOF) for these locations only ranged between 1.4 and 0.5, withoutsubtracting background soil concentrations. The average SOF.for the entire BLEU Complex site isexpected to be well below 1.0, when background soil concentrations are subtracted from the results.

The northwest comer of the proposed site has since been remediated to lower levels, but those levels arestill above natural background levels. The TEDE to members of the public, attributable to the fugitiveemissions during excavation of the BLEU Complex, was estimated to be 0.0112 mrem, per the NFSdocument titled ISA Source Term Data and Radioactive Effluent Estimates for the TVA Project(Attachment IV) which is well below any levels of concern.

The initial gamma contamination survey was able to identify locations with elevated soil concentrationsbelow a SOF of 1.0, and helps to confirm that significant contamination levels never existed on themajority of the proposed site. NFS believes the contamination is isolated to the northwest comer of thesite. Based on NFS' historical knowledge of the proposed site and the remediation performed on thenorthwest comer of the site, NFS believes significant contamination levels are no longer expected to bepresent on the proposed site. However, NFS will conduct additional characterization to confirm thatsignificant levels of contamination are not present at the site before construction begins.

(e) Clarification regarding whether a radiation protection program will apply to this area duringconstruction activities to ensure worker safety and whether additional soil sampling and radiologicalcharacterization will be done during excavation.

NFS Response to Comment No. 27 (e): The proposed BLEU Complex site is not considered aradiological control area; however, periodic monitoring will be conducted to ensure that no exposurepotential exists. No additional soil sampling or radiological characterization will be performed duringexcavation.

69 Additional documentation for the dose calculations including details of the exposure scenario andassumptions.

NFS Response to Comment No. 27 (M: Additional information on the BLEU Complex Fugitiveemissions assessment is provided in Attachment IV.

(g) Plans for disposition and characterization of the estimated 2,550 ma [900ft3J of soil expected tobe excavated during construction.

21


NFS Response to Comment No. 27 (g)

Any excess soil that is excavated during construction will be stored on the NFS site until its ultimatedisposition is determined. Soils containing radiological constituents will be dispositioned in accordancewith applicable regulations.'

NRC Comment No. 28: Clarify the commitment in Attachment 10 to the additional information letter(Ref 1) to monthly monitoring of Tc-99 in Well 38 Attachment 20 of the same document indicates Well38 is abandoned.

NFS Response to Comment No. 28: Well 38 was relocated due to the installation of tanks to supportadditional treatment capabilities at the Waste Water Treatment Facility (WWTF. The additional tankswere to be placed on the gravel area that Well 38 was occupying. The newly installed well (Well 38R)was located approximately 15 feet north (true north) of Well 38, and is down gradient of potential Tc-99source areas. The new well was installed to the same specification as Well 38 with a 4-inch diameter, 5-foot long poly vinyl chloride (PVC) screen and a 4-inch diameter, 10-foot long PVC casing. The screenand casing were installed to a depth of 15 feet below ground surface. Monthly sampling of well 38R isconducted for Tc-99.

NRC Comment No. 29: Provide additional surface and groundwater monitoring results at the site toallow staff to complete the description of current conditions in the environmental assessment. Tilefollowing table updates were requested by NRC in the letterfrom M. Adams to B. Moore (Ref. 5):

(a) To complete the update of Table 4.8 of the license renewal environmental assessment (Ref 4)regarding environmental monitoring for gross alpha emitters in downstream surface water samples andstream-sediment samples, provide the surface water data from Banner Spring Branch. This informationwas not included in the additional information letter (Ref 1). The updated information for sites otherthan Banner Spring Branch has already been provided in Table 24 of the supplemental environmentalreport (Ref 2).

NFS Response to Comment No. 29 (a)

The gross alpha data for surface water and sediment samples from Banner Spring Branch wasinadvertently omitted from the additional information letter. The table below provides the requestedinformation to complete the update of Table 4.8 of the license renewal environmental assessment.

22

Attachment IACF-02-006 3

Environmental monitoring for gross alpha emitters in downstream surface water samples andstream sediment samples

OnsiteWS-2

Banner Spring Branch

Surface Water Sedimentear (pCi/L)a (pCi/g)b

1998 22.25 92.01999 13.14 95.92000 15.43 60.702001 17.12 55.10

a. Average of monthly composite resultsb. Average of quarterly samples

(b) To update Table 4.9 of the license renewal environmental assessment (Ref 4), provide recent well-specific data for gross alpha and gross beta activities in the vicinity of the Burial Ground. Providerecent well- and zone-specific data for uranium, thorium, plutonium,, and Tc-99 concentrations. Thisinformation was not included in the additional information letter (Ref. 1).

NFS Response to Comment No. 29 (b)

Attachment VII provides gross alpha, gross beta, uranium, thorium, plutonium and Tc-99 data for wells98A, 99A and 100A. Isotopic analysis is generally only performed when gross alpha activity exceeds 15pCiIL and gross beta exceeds 50 pCi/L.

(c) To update Table 4.10 and Table 4.11 of the license renewal environmental assessment (Ref 4)provide recent well-specific data for gross alpha and gross beta activities for the vicinity of the surfaceimpoundments. Also provide recent well-specific data for thorium, uranium, plutonium and Tc-99. T7hisinformation was not included in the additional information letter (Ref 1).

NFS Response to Comment No. 29 (c): Attachment VII provides gross alpha, gross beta, isotopicuranium, thorium, plutonium and Tc-99 data for wells 52, 101A, 102, and 103A. Wells 26 and 28 wereabandoned in August 1997 and October 1998 respectively. Available data for well 28 is in AttachmentVII. Isotopic analysis is generally performed only when gross alpha activity exceeds 15 pCiIL and grossbeta exceeds 50 pCifL.

NRC Comment No. 30: Provide a technical basisfor the statement in the supplemental environmentalreport, Section 4.1.1.2.2 (Ref 2) that excess magnesium in storm water discharge (Table 20) isfrom

23


natural background and not from industrial activities. This information is necessary to complete thedescription of the existing environment.

NFS Response to Cormment No. 30: In 1998 NFS performed a study to evaluate magnesiumconcentrations in surface water and groundwater. The study involved obtaining upgradient samples fromBanner Spring Branch and the Nolichucky River and reviewing historical data from NFS' backgroundmonitoring well No. 52. The magnesium concentrations ranged from 3 mg/l to 11 mg/I for samplescollected at these surface and groundwater monitoring locations. The 1998 NFS NPDES Storm WaterPermit limit for magnesium was 0.0636 mg/L. The information has been provided to TDEC, Division ofWater Pollution Control. Ms. Qualls agreed9 that the magnesium limit for NES was not appropriate andexempted NFS from monitoring for magnesium for Calendar Year 2000 stormwater discharges(Attachment VIII).

NRC Comment No. 31: NFS refers to the proposed U. S. Environmental Protection Agency (EPA)maximum concentration limit for uranium in the supplemental environmental report (Ref. 2, pp. 4-9 and4-10); however, the EPA has completed the final rulemaking. The value did not change from theproposed to final rulemaking, however, NFS should refer to the final rulemaking in any subsequent useof the EPA maximum concentration limitfor uranium.

NFS Response to Comment No. 31: The referenced document cited in the text of the supplementalenvironmental report was written prior to final rulemaking and the maximum contaminant level (MCL)for uranium was a proposed MCL. NFS acknowledges that EPA has since prescribed a MCL for uraniumat 30 pCi/L in the final rule

NRC Comment No. 32: Some tables in the supplemental environmental report (Ref. 2) are missinginformation that is needed to evaluate data being presented. Specifically:

(a) Gross alpha activity values in Table 15 and surface water chemical concentrations in Table 23 donot specify the statistic being presented (e.g., single data value, average, or maxima).

NFS Response to Comment No. 32 (a): Table 15 (page 3-7) in the supplemental environmental reportrepresents the average background radioactivity in the vicinity of NFS from data obtained in 1996through 2000 for each station and media evaluated. Table 23 (page 4-7) in the supplementalenvironmental report represents annual averages of each chemical parameter.

(b) Table 16 activity units for air emissions have no time dimension.

NFS Response to Comment No. 32 (b): Table 16 (page 4-1) in the supplemental environmental reportrepresents annual radiological emissions estimates from each building of the BLEU Complex.

9 Letter from TDEC to T.S. Baer, NPDES Permit No. TNRO50873 Nuclear Fuel Services Storm Water Monitoringfor Magnesium, dated December 2, 1999.

24


References for NRC Comments

1. Nuclear Fuel Services, "Additional Information to Support an Environmental Review for BLEUProject," Docket No. 70-143, January 15, 2002.

2. Nuclear Fuel Services, "Supplemental Environmental Report for Licensing Actions to Supportthe BLEU Project," Docket No. 70-143, November 9, 2001.

3. Nuclear Fuel Services, "Applicant's Environmental Report for Renewal of Special NuclearMaterial License No. SNM-124," Docket No. 70-143, December 1996.

4. U.S. Nuclear Regulatory Commission, "Finding of No Significant Impact and EnvironmentalAssessment (TAC No. L30873)," Docket No. 70-143, January 29, 1999.

5. U.S. Nuclear Regulatory Commission, "NRC Comments on the Applicability of DOEIEIS-0240to NFS Proposed License Amendment to Construct and Operate a New Oxide ConversionFacility (TAC No. L31299)." Docket No. 70-143, July 25, 2000.

25

B.M. Moore to Dir., NMSSPage 4March 15, 2002

21G-02-0087GOV-01-55-04

ACF-02-0063

* Attachment II

Physical Description of Controls, Dimensions, Chemical Attributes for Tanks to be Installed at

BLEU Complex

Attachment 11ACF-d2-0063

Physical Description of Controls, Dimensions, Chemical Attributes for Tanks to Be Installed at BLEU Complex# of Description Chemical Size of Tank Level Leak Berm CommentsTanks Location Reactivity Room Volume Control Detection Detail

(gal)

Low Enriched UN 108' L x Continuous Level Sump area Control System24 Storage Corrosive 80' W x Instrument and has liquid prevents transfer to a

30' H High-High Level detection deep by tank at. High and High-Switch instrument. High Levels.

Uranyl Nitrate Sump is completelyBuilding sealed with corrosion

resistant coating.

Low Enriched UN 108' L x Continuous Level Sump area Control SystemI Receiver Vessel Corrosive 80' W x Instrument and has liquid prevents transfer to a

30' H High-High Level detection deep b tank at High and.High-Switch instrument. High Levels.

Uranyl Nitrate Sump is completelyBuilding l _ sealed with corrosion

resistant coating.

N IUN Storage 108' L x Continuous Level Sump area Control SystemCorrosive 80' W x Instrument and has liquid prevents transfer to a

30' H High-High Level detection deep b tank at High and High-Uranyl Nitrate Switch instrument. High Levels.Building Sump is completely

_sealed with corrosionresistant coating.

I

Attachment 11ACF-02-0063

"Physical Description of Controls, Dimensions, Chemical Attributes for Tanks to Be Installed at BLEU Complex"(Continued)

# of Description Chemical Size of Tank Level Leak Berm CommentsTanks Location Reactivity Room Volume Control Detection Detail

(gal)

Wastewater Hold 65' L x Continuous Level Sump area Control System2 None 35' W x - Instrument and has liquid prevents transfer to a

30' H High-High Level detection deep by tank at High and High-Effluent Processing Switch instrument. High Levels. * .Building Sump is completely

sealed with corrosionresistant coating..

Anhydrous Hydrolysis in Outside Tank level Sump areaI Ammonia water indicator has liquid

produces heat. detection deep byinstrument.

Outside Ambientammoniadetection alinstrument

Aqueous Ammonia Hydrolysis in Outside Continuous Level Sump area Control SystemI (23%) water Instrument and has liquid prevents transfer to a

produces heat High-High Level detection by tank at High and High-Switch instrument. High Levels.

Outside Ambient Sump is completelyammonia sealed with corrosiondetection resistant coating.

._ instrument

2


"Physical Description of Controls, Dimensions, Chemical Attributes for lTanks to Be Installed at BLEU Complex"(Continued)


(gal)

Nitric Acid (50%) Corrosive, Outside Continuous Level Sump area Control SystemI _ Oxidizer Instrument and has liquid prevents transfer to a

High-High Level detection de b tank at High and High-Outside Switch instrument. High Levels.

Sump is completelysealed with corrosionesistant coating.-

Nitric Acid (7%) Corrosive, Outside Continuous Level Sump area Control SystemI Oxidizer Instrument and has liquid prevents transfer to a

High-High Level detection dep by tank at High and High-Outside Switch instrument. High Levels.

Sump is completelysealed with corrosion

_ __ _ resistant coating.Liquid Nitrogen None Outside Tank level none none

I _indicator

OutsideinOxideConversion Building

Sodium Hydroxide Corrosive, Outside Continuous Level Sump area Control SystemI (50%) Hydrolysis in Instrument and has liquid O prevents transfer to a

water High-High Level detection by tank at High and High-produces heat. Switch instrument. _ High Levels.

Outside Sump is completelysealed with corrosionresistant coating.

3


"Physical Description of Controls, Dimensions, Chemical Attributes for Tanks to Be Installed at BLEU Complex"(Continued)


(gal)

Liquefied Petroleum Explosive, Outside Tank level none nonel Gas Flammable I _ indicator

"e Wf Fenced

Diesel Fuel Combustible Outside Tank level none none Diesel tank has doubleI _ .indicator containment

Outside1IIUNIB

4


21G-02-0087GOV-01-55-04

ACF-02-0063

*Attachmenf III

Physical Description of Process Controli Schemnes to be Instituted at BPF

Attachment IIIACF-02-0063

Physical Description of Controls, Dimensions, and Attributes for Chemical Storage TanksFor the BLEU Prep. Facility

No. Chemical Description Chemical Size of Volume Level Dike Commentsof and Tank Location Reactivity Room Control Detail

Tanks (Gal)1 Nitric Acid 70% Corrosive, Outside Tank Sight Volume of Dike is protected with corrosion

Oxidizer Glass and resistant coating.Existing Bulk Storage high levelArea sensor with

__ shutoffI Sodium Hydroxide Corrosive Outside Pressure Volume of Dike is protected with corrosion

30% sensor to resistant coating.indicate level

Existing Bulk Storage with highArea level shutoff

1 Hydrogen Peroxide Oxidizer Approx. None Approx.in Dike to be sealed with corrosion30% 16 ft. x sized resistant coating.

30 ft. x for largestNew area next to 1S ft. high tankBldg. 333

1 Sodium Nitrate Oxidizer Approx. Tank Sight A rox._ Dike to be sealed with corrosion45% 16 ft. x Glass sized resistant coating

30 ft. x for largestNew area next to 15 ft. high tankBldg. 333

1 Barium Hydroxide Strongly Approx. None A rox_ Dike to be sealed with corrosionAlkaline 16 ft. x _ sized resistant coating

New area next to 30 ft. x for largestBldg. 333 15 ft. high tank

2 Sodium Hydroxide Corrosive Approx. I Continuous A rox. Dike to be sealed with corrosion(6 molar) with Sodium 16 ft. x Ultrasonic _ sized resistant coatingNitrate and Barium 30 ft. x Level for largestHydroxide 15 ft. high Detector tank

New area next toBldg. 333

I

Attachment IIIACF-02-0063

Physical Description of Controls, Dimensions, and Attributes for Chemical Storage TanksFor the BLEU Prep. Facility _

No. of Chemical Chemical Size of Volume Level Dike CommentsTanks Description and Reactivity Room Control Detail

Tank Location (Gal)I Tributyl Phosphate Combustible Approx. None Portable Dike, When needed drum will be carried

Liquid 30 ft. x sized om in portable dike to Bldg. 333.28 ft. x Then returned to warehouse in

_ _ 11 ft. high portable dike.I Norpar 12' Combustible Approx. None Portable Dike, When needed drum will be carried

Liquid 30 ft. x sized fori in portable dike to Bldg. 333.Inside Bldg. 333. 28 ft. x _ Then returned to warehouse in

I lft. high portable dike.I SoiumCarnte Strong Base Approx. roneip Pan sized Solution pumped to I1' and 2"' pass

5% 55 ft. x for nuclear extraction systems continuously.26 ft. x safety

IjnjdeBid .333, 35 ft. high

1 Solvent (85% Combustible Approx. Approx. Tank Sight Drip Pan sized Tank to be typically empty.Norpar-120 and Liquid 55 ft. x Glass for nuclear Liquid-liquid extraction system15% Tributyl 26 ft. x safety will be charged with solvent andPhosphate 35 ft. high from that point on additional

solvent will only be neededInside Bldg.333, periodically.

2 Process Waste Corrosive Approx. _ Tank Sight Approx _ Dike to be sealed with corrosionSolutions (Basic and 16 ft. x Glass and i , sized resistant coating

Acidic 30 ft. x high level for largestNew area next to Solutions) 15 ft. high sensor with tankBldg. 333 _ shutoff

2 Uranyl Nitrate Corrosive Approx. Continuous Floor area of Floor in this area will be slopedSolution 540 ft2 x _ Ultrasonic _ With such that the volume of the largest

16 ft. high Level doorways set tank will be contained within the'and 500 ft2 x Detector above the area. Vinyl tile under tank and

iini__ T g 34 ft. high _ floor epoxy coating in other areas.

2

Attachment III -ACF-02-0063

Physical Description of Controls, Dimensions, and Attributes for Chemical Storage TanksFor the BLEU Prep. Facility

No. of Chemical Chemical Size of Volume Level Dike CommentsTanks Description and Reactivity Room Control Detail

Tank Location (Gal) . *:1 Uranyl Nitrate Corrosive Approx. ontinuous Floor area of Floor in this area will be sloped.

Solution 540 2 x Ultrasonic P vith such that the volume of the largest16 ft. high Level doorways set tank will be contained within theand 500 f 2 x Detector labove the area. Vinyl tile under tank and

inside Bldg. 333 34 ft. high floor epoxy coating in other areas.

3

B.M. Moore to Dir., NMSSPage 6larch 15, 2002

21G-02-0087GOV-0 1-55-04

ACF-02-0063

*Attachment lV

ISA Source Term Data and Radioactive Estimates for the TVA Project

21 T-02-0300HEA-21BPG-02-011.

* Nuilear Fuel Services, Inc.

Technical Basis

ISA Source Term Dataand Radioactive Effluent Estimates for the

TVA Project

Revision 0

March 4, 2002

Nuclear Fuel Services, Inc.Eri'in, TN

PrepareI bv.e: -

B. P. GlecAlerHealtih Phy'sicist

Reviewed;'c 1wL.R. Sanders

CHP

EA .2I/J/.GJ-tl{J II

TABLE F01 CONTENTS

1.0- PTRPOSE & SCOPE.*r;..- ......... .... *-----------------------------------;----...-----

2.0 ISA SOURCE TERM DATA .................................. .. 3

3.0 RADIOACTIVE EFFLUENT ESTIMATES .................... .................. 5

3.1 Gaseous Effluents .53.2 Liquid Effluents ........................................ 63.3 Fugitive Emissions .................. : . ; ; 7.

4.0 RIEFIERENCES .............. ; ; :.9

Attachment A - Radionuclide Data for the TVA Project's Feed MaterialAttachment B - Mass Balance & Process Flow DiagramsAttachment C - BLEU Preparation Facility (BPF) Radioactive Gaseous EffluenltsAttachment D - Wastewater Treatment Facility (WWTF) Radioactive Gaseous EffluentsAttachment E - BLEU Complex Radioactive Gaseous EffluentsAttachnment F - Historical Radioactive Gaseous Effluent Data and Compiled DataAttaclhmcntt G - BLEU Preparation Facility (BPF) Radioactive Liquid EffluentsAttachment H - BLEU Complex Radioactive Liquid EffluentsAttachment I - Historical Radioactive Liquid Effluent Data and Compiled DataAttachment J - Fugitive Emissions from Construction Activities

Page i

21 EJIi-2 '.3} I

* GLOSSARY

*-. *. ARF. AvgBLEUBPFECVEDMSEPBFRA-ANPHEHEPALENFSNMNRCOCBTEDEStd DevTVAUUNBUAI,WWTF

airborne release fractionaverageblended low enriched uraniumBLEU Preparation Facilityeffluent concentration valueEffluent Data Management SystemEffluent Processing BuildingFramatome-ANP; Inc.high enrichedhigh efficiency particulate airlow enrichedNuclear Fuel Services, Inc.not measuredU.S. Nuclear Regulatory CommissionOxide Conversion Buildingtotal effective dose equivalentstandard deviationTennessee Valley AuthorityuraniumUranyl Nitrate Storage Buildinguranium aluminum alloyWastewater Treatment Facility

effluent concentration value - The concentrations in 10 CFR 20, Appendix B, Table 2.

unit dose factor - the resulting TEDE divided by the quantity of radioactive effluent discharged

Page ii

21 PT-03OUW1IEA -21

1;0 PURPOSE-& SCOPE

This document provides the basis for the radioactive source term data and the radioactiveeffluent e6timates that were calculated for the project to dowfl-blend high enriched (HE) uraniuminto low enriched (LE) uranium reactor fuel to be used by the Tennessee Valley Authority (TVAProject). The information provided by this document is intended to support the integrated safetyanalysis (ISA) consequence analyses and to document the radioactive effluent estimates for the

*TVA Project. The following sections provide a summary of the inf6rmation needed for the ISAconsequence analyses and a summary of the radioactive effluent estimates. Detailed informationregarding thesecalculations and the assumptions that were used are included in the attachments.'Note that significant changes in the process data associated with the TVA Project may requirethese calculations to be revised, to account for the process change.

Page I

21 1 T- 02 -I.I IIA -2 1B11l'c;4)?4) /

(This Page Intentionally Left Blank)

Page 2

21 T-02-0300HEA-21BPG-02-01/

2.0 ISA SOURCE TERM DATA

The average uranium concentrations for the product stream and the-calculated.concentrations for the discard streams are provided in Table 2-1 The annual quantity-of uraniumin the discharge stream was divided by the annual volume discharged, to yield the uraniumconcentration of the discard stream. All the values used for this calculation are provided inAttachment B. The remaining uranium concentrations will need to be obtained from the processspecifications.

Table 2-1

| 6k>&,q2tibtxfefL

<kmLE Cvatstic ; -Condensate ; ' RaEtfinate'.:rs 4'': crubberj*;.'^PI2oduai~ii ti,.t *; Disiarge ;. . .i'froriaSXi.'; froxtrSX . i: .Slution

,J(57.. JUA)L________

1.27E-03 7.65E-04 8.30E-04 3.15E&04

" jr"". '.!;...;::,:..;,; '.:: ...... ::;.in..,*H'

A summary of the radionuclide concentrations for the various process streams is providedin Table 2-2. The radionuclide concentrations in the discard streams were calculated by dividingthe annual quantity of untreated radionuclide processed at the WWTF by the annual averagemass of uranium processed in each discard stream.

The concentrations for the caustic discharge stream were calculated assuming that thepercentages of uranium and the radioactive impurities going with the caustic discharge streamremain unchanged. The BPF process will use centrifuges to separate the uranium from thecaustic discharge stream. These centrifuges may change the radionuclide ratios, causing some ofthe impurities to be concentrated in the caustic discharge stream. If the radioactive impurities areconcentrated to a significant degree, the consequences analyzed using the data in Table 2-2 maybe biased low. When a consequence has been evaluated as being just below the next higherconsequence level, more accurate source term data may be needed to ensure that the consequencelevel is not any higher than what was already indicated.

Page 3

21T-02-0300HEA-21BPG-02-01 1

Table 2-2

Note:I - The nidionuclide concentrations in the caustic discharge stuarn were based on the bet available nroramton at th tirnm this document was issued.However, the process separates the turum Drom the caustic using centrifuges. which could concentrate the radioactive inputides in the caustic dischargescrearm Therewas nodcfinitivedataonthisprocess. sthetimethisdocumentwas issued. Bewae thtconsequcnceanalysestusingthecausticdischargeconcentrations could be biased low.

Page 4 of 17

21 T-'J2-0uoM)lIE4-21

(;-fl2-fo llh -

3.0 RADIOACTIVE EFFLUENT ESTIMATES

This section provides a. summary of the effluent estimates for gaseous effluents, liquideffluents; and fugitive emissions..

3.1 Gaseous Effluents

Comparisons of NFS' average annual radioactive gaseous effluents and the estimatedradioactive, gaseous effluents associated with the TVA Project are provided in Table 3-1. Asimilar comparison of the radio'active gaseous effluents, in terms of total effective doseequivalents (TEDE), is provided in Table 3-2

Table 3-1

Radioactive Gaseous Effluents - Radioactivity Releases

Current Averages' Estimated TVA Project Effluents Total

Elements Main Remaining BLEU EffluentsStack Stacks BPF2 Complex WVTF(Cilr) (Cilyr) (Cl/yr) (Ci/yr) (Ci/yr) (Ci/vr) (pCilyr)

Uranium 2.SE-04 3.1 E-05 1. IE-03 2.3E-05 4.SE-O5 I.5E-03 I.49S.32Thoriurn 6.3E-07 7.2E-06 I .7E-05 3.4E-07 I .2E-04 L.SE-04 147.05

Plutonium O.OE+00 4.7E1(05 S.5E-07 L.SE-OS 6.2E-06 5.4E-05 53.95

Americium OJoE400 9.4E-07 2.3E-0S 4.SE-10 I.7E-07 1. IE-06 1.13

Notes:I - Current averages arc based on release data from 1996 through 2000, which ware obtained from thc Safety

Dcpanmcnt's semiannual reports.2 - The BLEU Preparation Facility's (BPF's) gaseous effluents will be released through thc Main Stack.

Page 5

-

21 Th,2-l3.100IIE.*-21

Table 3-2

' Radioactive Gaseous Effluents - TEDE . :

AMain ' BLEU TotalsStack Stacks BPF2 . Complex NNINTF

{niremlyr) (mreinlyr) (mremlyr) | (mirimtyr) (mremlyr) (mrem/yr)

0.0260 0.0150 0.0740 0.0081 0.1532 0.2763

Notes:I - Current averages are based on release data from 1996 through 2000, which were obtained

from the Safety Depirtment's semiannual repors. The portion attributable to the MainStack was determined from the ECV fractions in the EDMS' Radioacrivify in EffluentAirreport for the period of 1996 through 2000.

2 -The BPF's gaseous cffluents will be reclased through the Main Stack.

3.2 Liquid Effluents

Comparisons of NFS' average annual radioactive liquid CIT1uenIs and the cstimllitedradioactive liquid cfluents associated with the TVA Project arc provided in Table 3-3. Theadditional dose to the public wvas estimated to be 2.45 mrem/yr, Attachment G. Historical dosesto members of the public were not available for comparison purposes, because NFS has onlyrecently established a method and procedure for calculating doses to members of tile publicattributable to radioactive liquid effluents.

Page 6

.2 1 7T(J2-0J3(1IIEA4-21flPG-02-f)1

. Table 3-3

Radioactive Liquid Effluents -. RadioActivity Released'.;.,; ;-.;i .'¢, .4i,.r'(c>..W; .. Z 7 jw > . ;.. . i

Strian Eleiit Current BLEU Ehuent. Averages BPFt Complex 3 Totals

._(Cvr)_* (i/y) (C r) (C r) CVyr)

Uranium 6.3 E-04 1.3E-04 7.6E-04Radium 1.3E-04 3.7E-01 No 3.7E-01

W.TP Thorium 4AE-06 9.1 E-03 Effluents 9.1 E-03Plutonium 5.32-07 1.9E-0 1 Expected 1.9E-0lTechnetium 16E-02 I.8-E04 I.6E-02

Uranium I.4E-02 I .4E-02Banner Radium- NM No No NMSpring Thorium 3AE-04 Effluents Effluents 3.4E-04Branch Plutonium 1.7E-04 Expected Expected 1.7E-04

Technetium 2.66-03 2.6E-03

Uranium 2.SE-03 ZAIE-04 3.2E-o3Sa*ta Radium NM . No NMSeniry Thorium 1.4E-05 Erucnts 1.3E-OS 1.4E-05SePlur Plutonium 1.3E-06 Expected 4.32-(09 1.3E-16

Technctium 2.5E-03 1.1 E-0.1 3.6E-03

Notes:- Current averages are based on release data from 1996 through 2000, which were

obtained rrom the Sarety Department's semiannual reports. "NM" - not measured.2 - The BPF's liquid emuents will only be discharged through the WWITF.3 - The BLEU Complcx's effluents will only be discharged to the sanitary sewer.

3.3 Fugitive Emissions

Radioactive fugitive emissions are only anticipated during construction of the BLEUComplex. The TEDE attributable to the construction of the BLEU Complex was estimated as0.0112 mrem.

Page 7

2 1 7:tI ' .1)311(1li/A.2/

l-'G-(1I2-'U

(Ihis-Page Intentionally Left Blank)

Page 8

lI XJ-21lPG-2-I I1

4.0 'REFERENCES

BENEDICT, 1981, Nuclear Chemical Engineering, Second Edition, M. Benedict, T.. Pigford,and H.W. Levi, McGraw-Hill Book.Comilpany, 1981, New York, New York.

BWXT, 2001, Contract No..DE-ACO5-00OR22800, Results of Statistical Sampling of SRSUranium Metal Buttons, Document Transmittal Formn No. HDPOIDT01-31, Memorandum fromRussell W. Schmidt to Dale Davis, dated November 14, 2001, BWXT Y-12 L.L.C, Oak Ridge,Tennessee.

NFS, 1996, Applicant's Environmental ReportforRenewal of Special Nuclear Material LicenseNo. SNM-124, Document No. LIC-01-02, File Classification GOV-01-55-04, December 1996,Nuclear Fuel Services, Inc., Erwin, Tennessee.

NFS, 1999, Routine Estimation of Off-site Exposurefronz Radioactive Air Effluents, NFSProcedure No. NFS-HS-A-27, Revision 4, Document No. 21T-99-0355. File Classification SYS-50-16-03, April 1999, Nuclear Fuel Services, Inc., Erwin, Tennessee.

N FS, 2001 a. Supplenmeital Enivironmenital Report for Licensing Actions to Support the B3lndedlLol -Ehriche(l Uraniaum Project at Nuclear Fuiel Services, November 2001, Nuclear FuelServices, Inc., Erwin, Tennessee.

NFS, 2001b. Dose ractors & Action Levelsfor WWTFRadioactive Liquid Effluents, DocumentNo. 21T-01-028, File Classification HEA-21, July 2001, Nuclear Fuel Services, Inc., Erwin,Tennessee.

NFS, 2001 c, Routine Estimnauion of Offsiie Dosefiron Radioactive Liquidl Efflifenws. NFSProcedure No. NFS-HS-A-66, Revision 0, Document No. 21T-01-0730, File Classification SYS-50-16-03, July 2001, Nuclear Fuel Services, Inc., Erwin, Tennessee.

Page 9

2/ Th'j2.1,.U(jllII-.?(I2 lIIPG-1121 'Ill

(This Page Intentionally Left Blank)

Pagc 10

Attachment A . .Radionuclide Data for-the TVA Project's Feed Material

.*Radionuclide Data for theTVA Project's Feed Material

The sample data for the liE U metal buttons, from BWXT Y-12 Memorandum HDPO/DTO1-31 (BWXT,2001), was compiled and averaged. The data was converted to the same units of concentration (i.e. pCi/gto pCi/g U) using the average uranium purity.

The ratio of Th-230:U -234 was calculated from the averaged results (1.19E-04). The average age for theHE U metal buttons was calculated to be approximately 13 years, using the Th-230:U-234 ratio and tfleRADDECAY Version 5.0 computer program. The age of the material was used to determine-thequantities of the radionuclides that were not specifically analyzed for that belonged to a decay series.Radionuclide concentrations were estimated by multiplying the concentration of a measured radionuclideto the ratio of the decay fractions, for radionuclides in the same decay series.

The HE U metal buttons could contain additional radionuclides that were not analyzed for in the samples,which may be significant because of their radiological properties. Radionuclides that could be prcscrltbut could not be accounted for using radionuclide decay equations include: Sr-90, Y-90, Pm-147, 13u- 154,I'u-24 1, and Am-24 1. Quantities of these radionuclides were cstimatcd using radionuclidc data ondischarged reactor fuel from a uranium fueled 1000 MWc pressurized water reactor. The data used wasprovided by Tables S.1 and 8.4 of the textbook titled ANticlear Ch'entical EngiLee'ring (Benedict. 198 1).T11is was the best data availablc at the time of the calculations. because data specific to thi IHE U metalwas not available. Excerpts of these tables are included at the end of this attachment. Isotopic ratioswere calculated for each potentially unaccounted for radionuclide using the referenced tables.

The fission product ratios wvere calculated using the data at the time of dischargc fior discharged reactorfuel, from Table S.1. Fission product concentrations were estimated by using the average Cs-137concentration from the measurements and determining how much Cs-137 was present at the time ofdischarge (i.e. 13 years ago). The Cs-137 concentration at the time of discharge was then multiplied bythe ratio of the fission product to Cs-137. to yield the concentration of the fission product at the tinme ofdischarge. The fission product concentration was then decay corrected for the estimated age of thematerial (i.e. 13 years). A Y-90 concentration was estimated from the estimated Sr-90 concentration byassuming Y-90 was in secular equilibrium with Sr-90.

Plutonium-241 was estimated using the average Pu-238 concentration from the measurements and thedata in Table 8.4, which provides data for 150 days after discharge. The Pu-238 concentration wasdetermined for 150 days after discharge (i.e. 13 yr - 150 days = 4595 days ago). The Pu-238concentration, at 150 days after discharge, was multiplied by the ratio of Pu-241 to Pu-238, to yield theconcentration of Pu-241 during the same time period. The Pu-241 concentration was then decaycorrected for the estimated age of the material (i.e. 4595 days). The concentration of Am-241 was thenestimated by multiplying the Pu-241 concentration by the ratio of Am-241 :Pu-241 for 13 year oldmaterial.

Table A-I provides a summary of the radionuclide concentrations that were used for all furthercalculations. The other tables in this attachment provide the supporting data that was used to compileTable A-I

Table A-1Radionuclide Concentrations in the HE U Metal Buttons

(Decay corrected to November 2001)

*~~ ..-* .

* Radionudide .;..Concentratldn

.. .. '(CUgU)'

U-232 4.17E+05U-233 3.96E+OSU-234 7.89E+07U-235 1.19E+06*U-236 . 1.79E+07U-238 5.34E+04

Th-227 5.SOC+01Th-228 3.98C+05Th-230 9.35E+03Th-231 1.19E+06*I-i-232 3.921L+02I1-234 1.9313+04

I'o-238 4.61 E+03IPti-239.24)0 2.961:402f'u-24t 7.7SI.-04

Am-241 2.2613+03Np-237 3.27L+03

Thorium SeriesRa-22S 3.10E+02Ac-22S 3.101+02Ra.224 3.9S1 +O3Ilb-212 3.9-41:+051i-212 2.2413+40TI-20S 1.271E+05

Uranium SeriesPa-234 1.4 IE+02Pa-234m 5.34C+04Ra-226 2.60E+01

Actinium SeriesPa-231 3.281.+02Ac-227 5.94 C+OIRa-223 5.8413+01

Fission ProductsSr-90 I.A7E+02Y-90 1.47ri+02Tc-99 7.46E+01Cs-134 8.0s51+00Cs-137 2.0713402Pm-147 8.55£3+00Eu-154 6.5213+00

File: TVA Project (Isotopic Data for Feed Mat).odsSheet: HEU Isotopes3/1/02

Natural Uranium Data

Uranium Mass: 1.00 .g

-- WuIde'.y/4f) :~:(di) g) (CI)

U-234 0.0055% 234.,40904 2.445E+05 6.249E-03 5.500C-05 3A37E-07 3A44E405

U-235 0.7200%r. 235.043915 7.038E+08 2.1621-06 7.200E-03 1.556E-08 1.56E+04U-238 99.2745% 238.050770 4A68E+09 3.362E-07 9.927E-01 3.338E-07 3.34E+05

Total 100.000/ 6.931 E-07 I.OOE+00 6.931 E-07 6.93E+05

Notes:1 - Weighipercent values obtained from the Chanr of teNudides. General Electric, 1984.2 - Half-life values were obtained from DOE/TIC-I 1026. Radioactive Decay Data Tables. D.C Kocher. 1981.

File: IVA Project (Isotopic Data for FRed Mal).xlsSheet: Nat U311/02

Evaluation of Radionuclid.eConicentrati6ns ini HE U Metal Buttons(Based on Novemiber 2001 Sample Results)

1 llw~r kid

U-232U-233U-234U-236U-2361.3238

4.17E+O53.96E+057.89E+071.19E+061.79E+075.34E+04

23.70%h66.63'%5.60%I 3.291%17.73%1033%

Th-227 (U-235)'Th-22STh.230Th-231Th-231 (0-233)'Th-232Th-234

Np-237

Pu-238Pu ' 39240Iu-'4J (Pu-2u.S)Ani.241 (Pu-241 1'

fistion ProductsSr-90 eCs-I37)'Y-<)o (Sr-90 1Tc-99Cs- 134 (Cs-1 373Cs-137Pmn-147 (Cs-I3?)Eu-IS-i (Cs-137)

Thoriunta SericsRa12?S (Thb-132'Ac-22' (1fli.23)Ra-224Ri.-224 (T1h-22SIPb-2 I1Pb-212 (Th-228)Di-212T1-20STI-208 (Th-228)'

5.SOE+013.98E+059.35E+036.99E+05

I.19E+06392E4'021 .93E+04

21.44%1 L.00h21.57%

(See Note 3)151.99%53.64%

Th-227:tJ-23S - 4.8S73E-OS1I - 4.86C-05

Th-231:U.-235 - I .-

3.'7U-03 S7.8SI;

4.61E-012.96E-0'

7.7SEn042.26E-03

8.64¶.o0s.6ur

Pu-241:1'u-23S -2.tUL.-0 L.OW-0 - 2'Am'24: Pu-241 - 0.0OI12 0.534S6 * 0.02n

I.47E-o!.47E-02

7.46E-0OS.03E+00

2.07E-028.55>E00

6.52E+C0

3.0DE -3. OE-02

I.1E-063.98sr05

3.94E+0S3.98E+05

2.24C+051.27E+05

I.43E-05

79.15%;

47.65-;

106.56%.

(See Notc'2)22.84%

(See Note 4)21.96%22.18%

(See Note 4)

S 3 s -" .11 2.9) - o.72V-90;}Sr-,X} -- I I - I

Cs-134:.Cs-137 - 6.70'2.94 - '.2S

Pat. 147:0s-137 - 2.7S'2.94 -0.95Iu-154:Cs-117 - 1.29312.04 -0.06t

R1-224:11-228 - 9.0;2891.03 *).(XilAt.-03 * I

Ptb-2 1 2-Th?-2S - 9.0S29E-03!9.006Ct.03 - I

Ti208:Th-?2S - 3.2549SE-0319.006E403 - 0.36

Uranlum SerksPa-234 (Pa.234n)Pa-234inPa-234m (U-239)lRa-226 (U-234)-

1.412E02S.80E1O. 29.05%

5.34E+04 (Scc Note2)2.602>01

Pa-234:Pa-234mn- l.6CE-3f1 - 0.0016

Pa-234nttU-238 - 111 - IRa-226:I.-234 - 3.28897E-07/0.999963 - 3.31-07

Actinium SeriesPa-231 (U-235)-Ac-227 (U-235)'Ra-223 (U-235)-

3.28SE025.94E+01S.94E.01

Pa-23 :W-335 - 2.7493213-04l - 2.75f.-04Ac-227:U-235 - 4.97803E-0SII - 4.9StEOSRa-223:U-235 - 4.89387E-05/1 - 4.89E-05

I I

Notes:I - " indicates that the conceturation ais estiamed usurg the radionuclide in parentiheses. The

average aZc offltc buttons was estimated lo be 13 years. based on Th-230:t.1234 ratio.2 - The measured results were artiruially high duc to interference with other peaks. The estitrttcd

conceltration appears to be more accurwc and is reconinicnded instead ortlic measuted value.3 - The estimated Th-231 eonceitnaion is nwth greater titan tin teieasured result. the usC orthe

estinmted coneeittration is reconticnded. because this concentration is liore realistic based ona 13 year decay ofU-235.

4 - ThiC estimiated value cotflrms the tcasured rcsuiL

File: tVA Priojed (isotopic Data lor Feed Mat).xisSheet: Data Evalualionm311102

w . -

Result -6f decayingDecay time of 13 years =

Combining the same-daughters resuiltiiig

NuclideU-234Th-230Ra-226'Rn-222Po-218Pb-214Bi-214Po-214Pb-210Bi-210Po-210

U-235Th-231Pa-231Ac-227Fr-223Ra-223Rn-219Po-215Pb-211Bi-211T1-207Po-211Th-227

U-238Th-234Pa-234mPa-234U-234Th-230Ra-226Rn-222Po-218Pb-214Bi-214Po-214Pb-210Bi-210Po-210

Fraction9.99963e-0011.27016e-0043:28897eL0O73.28134e-0073 .28134e-0073.28065e-0073.28062e-0073.27993e-0074.00938e-0083.99168e-0083.54030e,008

1.OOOOOe+0001.OOOOOe+0002.74932e-0044.97803e-0056.86962e-0074.89387e-0054.89387e-0054.89387e-0054.89378e-0054.89378e-0054.8804le-0051.33600e-0074.85731e-005

1.OOOOOe+000l.OOOOOe+O001.OOOOOe+O001.60000e-0033.65839e-0052.12498e-0093.95494e-0123.94097e-0123.94112e-0123.94029e-0123.94003e-0123.93926e-0123.65643e-0133.63549e-0133.09859e-013

1 Curie4,748.25 daysfrom different decay paths.

Activity (Ci)9.99963e-0011.17016e,-004.3:28897e-0073.28134e-0073.28i34e-0073.28065e-0073.28062e-0073.27993e-0074.00938e-0083.99168e-0083.s4030e-008

1.OOOOOe+0001.OOOOOe+0002.74932e-0044.97803e-0056.86962e-0074.89387e-0054.89387e-0054.89387e-0054.89378e-0054.89378e-0054.88041e-00s1.33600e-0074.85731e-005

1.00000e+0001.00000e+O001.00000 ei0001.600OOe-0033.65839e-0052.12498e-0093.95494e-0123.94097e-0123.94112e-0123.94029e-0123.94003e-0123.93926e-0123.65643e-0133.63549e-0133.09859e-013

* .Result of decaying* .Decay.time of 13 years =

Combining the same daughters resulting

NuclideTh-232*Ra-228

: Ac-228Th-228Ra-224Rn-220Po-216Pb-212Bi-212Ti-208Po-212

Fractionl.OOOOOe+0007.91354e-001'7.91328e-001.6.91768e-0016.91251e-0016.91251e-0016.91251e-0016.91188e-0016.91182e-0012.48342e-0014.42840e-001

1 Curie4,748.25 daysfromt different decay paths.

Activity (Ci)1.OOOOOe+000.7.91354e-D001

. 7.91328e-0016.91768e.-001

* 6.91251e-0016.9125le-0016.91251e-0016.91188e-0016.91182e-0012.48342e-0014.42840e-001

Th-228Ra-224Rn-220Po-216Pb-212Bi-212Tl-208Po-212

* 9.00600e-0039.05289e-0039.05290e-0039:05290e-0039.05865e-0039.05919e-0033.25498e-0035.80423e-003

9.00600e-0039.05289e-0039.05290e-0039.05290e-0039.05865e-0039.05919e-0033.25498e-0035.80423e-003

Result of decaying 1 CurieDecay time of 13-years = 4,748.25 days

* Cotibining the same daughters resulting frbm different.decay paths..

NuclideU-232Th-228Ra-224Rn-220-Po-216Pb-212Bi-212Ti-208*Po-212

U3-233Th-229Ra-225Ac-225Fr-221At-217Bi-213T1-209Pb-209Po-213

U-236Th-232Ra-226Ac-228Th-228Ra-224Rn-220Po-216Pb-212Bi-212Tl-208Po-212

Fraction8.82363e-0018.97198e-0018.97274e-0018 .97274e-0018.97274e-0018.97284e-0018.97285e-0013.22394e-0015.748.90e-001

9.99943e-0011.22686e-0031.22134e-0031.21762e-0031.21762e-0031.21762e-0031.2176le-0032.63003e-0051.21755e-0031.19130e-003

1.OOOOOe+0006.41346e-0103.17482e-0103.17443e-0102.23244e-0102.22757e-0102.22757e-0102.22757e-0102.22697e-0102.22691e-0108.00129e-0111.42678e-010

Activity (Ci)8.82363e-00}8.9i198e-0018.97274e.-0018.97274e-0018.97274e-0018.97284e-0018.97285e-0013.22394e-0015.74890e-001

9.99943e-0011.22686e-0031.22134e-0031.21762e-0031.21762e-0031.21762e-0031.21761e-0032.63003e-0051.217S5e-0031.19130e-003

1.00000e+0006.41346e-0103.17482c-n103.17443e-0102.23244e-0102.22757e-0102.22757e-0102.22757e.-0102.22697e-0102.22691e-0108.00129e-011].42678e-020

* 354 NUCLEARCHEMICALENGINEERING

- R.hl 1 I IAZnad t.iv fissinn nro duet-t -.

* *In discbtrge fuel10* Ci/yr Elemental

boilingAt I SO-day I O-yr temperature,

Radionuclide Half-life discrazget decay decay °cs

3uA.. 71 n.. *u I -2 I .o I n-2 I no. v I A2 onn&An yr &.79 ^ AVp . A... - &U 9.V9 ^ au IUU

(as tritiatedwater)

Sc C 6.5 X 1 4 yrTotal!

*IRr i0.76 yrTotal

"Rb 18.66 daysTotal

89 Sr 52.7 days90 sr 27.7 yr

Total90 y 64.0 h91 Y 58.8 days

Total

93 Zr 1.5 X 1O6 yr

95 Zr 65.5 daysTotal

s3 mNb 13.6 yr9 smNb 901h9'Nb 35.0 days

Total

"s Tc 2.12 X 10' yrTotal

203 Ru 39.5 days'0 6 Ru 368 days

Total103nR~h 57.5 min106 Eh 30s

Total

7X l10 yrTotal

lnomAg 255 daysICAg 24.4 s

1 t 1 Ag 7.5 daysTotal

213mCd 13.6 yrlSmCd 43 days

Total11

7 mSn 14.0 days

mSn 250 days

(See footnotes on page 356.)

1.08 X 10510.0

0.30885.0

1.34 X l0-2

1.34 X 10-2

19.62.111.38 X 102

2.2025.5

2.0S X 102

5.ISX 10-537.396.2

3.95 X Io-'0.762

37.62.30 X 102

3.90X 10-29.7

33.214.875.7

33.220.2

1.17X 102

3.00 X IO-"9.10

0.1004.331.08

10.4

2.86X 10-40.01500.9811.62X 10-34A7X 10-4

1.08X 10o-1.O8x lo-,

0.300.0.3005.18 X 10-35.18X 10-3

2.652.094.74

2.094.396.48

S.15X 10-7.547.54

4.98X 10-60.160

14.214A3.90X 10-4

3.90X 10-4

2.4111.213.6

2.4111.213.6

3.00 X 10-63.00X 10-66.64 X 10-28.65 X 10-31.03 X 10-67.51 X 10-2

2.81 X 10-4

1.34 X 10-31.62X 10-

9.65 X 10'72.95X 10-4

1.08 X 10-51.08 X 10-

0.1620.162

00

01.651.65

1.6501.6S

S.Is x lo-$0S.15 X lo-,

2.3 X 10-5002.3 X 10-53.90 X 10-4

3.90 X 10-4

0l.SOX 10-21.50 X 10-2

01.SoX 10-21.SOX 10-2

3.00X 10.63.00 X 10-6

4.52X 10-65.88 X 10-705.11 x lo-

1.74 X 10-40

1.74 X 10-4

01.79 X 10'"

657

-153.4

705

1357

3337

4325

4842

3927

4227

3667

3112

2163

770

. .. I -

i PROPERTIES OF IRRADIATED FUEL AND OTHER REACrOR MATERIALS 355

Table 8.1 Long-lived radioactive fission productst (Continued)

In discharge fuel10 aCiyr.. Elemental

boilingAt IS0-day 10-yr temperature,

Radionuclide Half4ife discharger decay decay °C9

... t. 4

. .1

ItI

"I1

1.

123 Sn

126,Sn

Total

_Zh12s Sb

126 SbTotal

23ImTe125mTC

127m Tc!127Te

129mTe

To9 TeI Total

12S days9.4 days

105 yr

60A days2.71 yr

19.0 min12.5 days.

117 days58 days

109 days9.4 h

34.1 days68.7 min

0.2420.3681.49X IO-'

72.2

1.11 X 1020.2376.13 X 10-4

1.55 X 10-31.31 X 10

1:66 X I s8.47 X 1020.4201.961.569.181.63 X 102

1.055.81 X IO-,IA9X IOS1.051.9S X 1030.215

* IA9 X 10-5I.50 x lO-0.217

6.82 X 10'-8.69 X IO-00.1670.627.38X 10-23.87 X 10-'0.986

3.87 X 101001.49 X 10-5IA9 X 10-5 2722

01.85 X 10-21.49 X 10-51.47 X 10-s1.85 X 10-2 1625

07.66X 1O-300007.66X 10-3 1012

II

I

iI

i

129

131

Total131Mxe

133 Xc

Total34 Cs

15Cs

J36 Cs'"Cs

Total131 mBa

4o BaTotal

140 LaTotal

4" Ce144 Ce

Total143 Pr

144 PrTotal

14714d

Total

147Pm148m Pm

1.7X 10' yr 1.01 X 10-68.05 days 23.5

2.66X 102

11.8 days 0.1745.270 days 43.9

1.78X 10I

2.046 yr3.0X 106 yr

13.7 days30.0 yr

6.70 17.79 X 10-61.662.941.56X 10I

2.554 min 2.7512.80 days 39.5

1.51 X 102

40.22 h 40.91.49 X 102

32.5 days 37.9284 days 30.2

1.48 X I O2

13.59 days 32.717.27 min 30.5

1.23 X 102

11.06 days 16.024.9

1.02 X 10-6 1.02 X 10-15.94 X 10-5 06.04 X 10-s 1.02 X 10-6

8.50X IO-$ 0 /

I.46X 10- 08.51 X 10- 0

5.83 0.2287.79 X 10" 7.79X 10-65.42X 10.' 02.92 2.338.75 2.56

2.72 2.18.8 X 10-2 0

2.73 2.18

1.34 X 10-2 0l.34X 10-2 0

1.53 021.0 4.11 X 10-322.5 4.11 X 10-3

1.8S X 10-2 021.0 4.11 X 10- 3

21.0 4.11 X 10-3

2.58 X 10-3 02.58 X 10-3 0

2.65 0.2118.91 X 10-2 0

686

1634

3370

IiIII

i

II-I-IiI

I

183

-108.2

3470

3017

3111

4.4 yr41.8 days

2.781.06

(See footnotes on page 356.)

* 356 NUCLEAR CHEMICAL ENGINEERING

Table 8.1 Long-lived radioactive fission productst (Continued)

In discharge fuel106 Cilyr * Elemental.

boilingAt IS0-day 10-yr temperature,

Radionucide Half-life discharge decay decayC§

14 8 Pm S.4 days SA2 7.08 X 10-3 0Total 31.6 2.74 0.211 3200

'sSin .87yr 3AI.X 10-2 3.41X 10-2 3.16X 10-2Total I1.S 3.41 X 10-2 3.16 X 10-2 1670

IS2EU 12.7yr 3AIX10-4 3.32X10-4 1.92XtO-'"Eu 16 yr 0.191 0.187 0.12315sEu * 1.81t yr 0.204 0174 4A4 X 10-3ts6 Eu 15.4 days * 6.16 5.94 X 10-

3. 0

Total 6.56. 0.367 0.127 143010TI 72.1 days 3.49 X 10-2 8.24 X 103 0

Total 4.01 X 10-2 2470

Total, all fission products 3.76 X I0O 1.14 X 102 8.66

t Uranium-fuelcd I 000-MWc PWR, 3-year fuel life.?Total elemental activities for fuel at discharge include short-lived radionuclides not Usted here.

G. V. Samsonov ISI l.S Total activity of the elemeqt whose principal radionuclide(s) is (are) listed above.

PROPERTIES OF IRRADIATED FUELAND'OTHERREACrOR MATERIALS 369

Table 8.4 Actinides in discharge uranium fuelt

Elementalboilingtemperature,

Radionuclide Half-life kg/yr Cilyr OCt

2NU 2A7 X 0I yr 3.14 1.94 X 10'235u 7.1 X 10 yr 2.15 X 102 4.61 X 10-'2Mu 2.39 X 107 yr 1.14 X 102 7.2227u 6.75 days 9.15 X 10- 7.47 X 10'

U - 4.51 X 109 yr 2.57 X 104 8.56Total 2.60X 104 a 3.S6X 101 4135

W7.47X 101

23"Np 2.14 X IOW yr 2.04 X lO' 1.44 X 101.2'Np 2.35 days 2.05 X 10-' 4.78 X 102

Total 2.04 X 10' a 1.44 X 10 -

1 4.78 X 102"36Pu 2.85 yr 2.51 X 10-4 1.34 X 102238P, 86 yr 5.99 1.01 X to,

39Pu 24,400 yr I.44X 102 8.82X 10"240 6,580yr 5.91 X 10 1.30X 1024tPu 13.2 yr 2.77X 10' 2.81 X 10'242pu 3.79 X 10s yr 9.65 3.76 X 10'

Total 2.46X 102 a 1.23X 105 3508p2.81 X 10'

241Am 458yr 1.32 4.53 X 103242 mAm 152 yr 1.19 X 10-2 1.16 X 10243 Am 7,950 yr 2.48 4.77 X 102

Total 3.81 a5.01X 103 2880p 1.16X Ito

U2cm 163 days 1.33X 10-1 4.40X 10'243Cm 32 yr 1.96 X 10-3 9.03 X 10'44Cm 17.6 yr 9.11 X 10 7.38 X 104245Cm 9,300 yr 5.54 X 10-2 9.79

46 Cm 5,500 yr 6.23 X 10-3 1.92Total 1.11 a 5.14 X 10s -

Total 2.63X 10' r 6A2 X 10'P2.81 X 1O0

t Uranium-fueled 1000-MWe PWR, 150 days after discharge.$ G. V. Samsonov [SI 1.

TVA Metal Button Data

- -- ---I - - - I . . -

UraniumSifmp~le NumberI -f

Alpha Spec.U-232

fftnlo InU-233 U-234

lfnle II (anIu l U1

Mass Spec.t-235

Ilk,) fl U)U-236 l;-238

113Q1 Lo t1-) flint 1 UI

1SO'

Th-228(,11C'/p

Th by AI~lthSpec., *,,..Th.231N. t:232:i. MI f tP, i 8

Alpht SpeOs

N P@Rl7dN!CIJ37i~

Iso P10u by Alpha Spec.-; Pu-238 Pt-239/240tP;4* 1 -~' ;-e fr(Cifei

_____________,I- k-.-4 '--. ~ 1 I , 1 I -. '-- " -' .-- ., - . ..~ - - -- -- ... - '- "'--t- -

Y011160006Y011160009Y01 1160010Y011160011Y01I1160012Y011160013Y011160014YVO1 160015Y011160016YVO 1160017YOI 1160018Y011160019Yvot160020Y011160021Y011160022Y011160023Y011160024Y011160025Y011160026Y011580003

0.9997979120.9998896710.9999215520.9997910410.9998218630.9995000310.9998315230.9998397630.9998630230.9998737330.9996142830.9998762430.9998034230.9999049330.9999134430.9998425630.9999115910.9998361830.9998802610.999466051

17,40011,6679,2673,41717,00015,8316,03316,50015,03318,66715,45016,00018,00019,00018,83314,71716,83315.43316,13317,667

7,140 2,943,5687,140 3,208,859

10,710 2,855,9077,140 2,286,110

21,419 2,925,1137,140 2,938,955

24,989 2,927,42035,699 2,918,19317,849 2,920,50032,129 2,911,27224,989 2,918,19324,989 2,968,94421,419 2,980,4787,140 2,982,7857,140 2,980,4787,140 2,955,1037,140 2,962,0237,140 2,943,5687,140 2,934,3417,140 2,936,648

44,48139,71450,259(4,35442,12742,74842,74342,93442,84342,93342,89741.b5540,61040,35640,54844,00944,02145.041)44,57744.158

60.58t2772.611533,634207,581684,.339688.961690,2546R2.614683.501682,662681,968715.86737,791744,137739,946670,904070.832645,42.3655.410666,09(1

1!9312,0761,(951.2262,0652,0532,0472,0582.06X2,05X2,0672,0822.13(02.1372,1291,9501,94X1.9211,943I,953

4.3611+053.3(11+052.58XE+051.2614+053.0714+054.6811+054.93E+054.32E1+054.40I+54.031E+054.04E+054.7211+054.368+053.32E+053.671:+054.63 E+054.04E+054.23E+054.0(91:+054.70E+05

1.05E+04 3.708+02*9.61 E+03 1.77E+021.02E+04 2.46E+027.32E+03 1.34E+028.61 C+03 .1.67E+021.04E+04 1.53E+029.74E+03 3.37E+028.58E+03 1.28E+028.25E+03 3.50E+028.62E+03 4.66E+021.0IE+04 3.25E+021.07E+04 .5A646+028.88E+03 2.46E+029.79E+03 i.86E+038.228+03 .2.22E+021.05E+04 3.88E+028.32E+03 3.57E+028.728+03 1.98E8028.95E+03 1.65E+021.10+04 O.OOE+00

3. 51 +032.03E+022.59E+021.048+037.358+032.76E+034.19E+035.44E+035.55E+034.86E+033.71 E+03.5.34E+033.92E+031.65E+032.38E+033.29E+033.33E+03I.55E+031.54E+03,3.61 E+03

3,51018,3008,140

10,900. 2,300

3,530609

* 4,100*2,170

3,2401,1003,6744,5605,2803,360

. 4,9404,130

*th9204,740

* 1,650

ist1,1 I')

44',592141

7sf,756

143134757,)

140.13'926Ill14756S

Average 0.999808954 .41.5+04 1.46E+04 2.9211+06 4.421-.+04 (0.11i+405 1.9810+03 3.9814+05 9.35E+03 3.92E+02 3.27E+03 4.61E+03 2.96E+02Std Dev (%) 0.01% 23.70% 66.63% 5.60% 1 1.89% 17.73% 21(.33% 21.44% 11.00% 151.99/o 57.81% 86.64% 108.69%

Avg(pCI/gU) 4.17E+05 3.96E+05 7.89[+07 1.19)+06 1.791'+07 5341!+04 3.98E+05 9.35E+03 3.92E+02 3.27E+03 4161E+03 2.96E+2o

'Majority orsampic data <MDAAContains sample activities that are artificially high due to interrerence rom othtr yammuua specitnscopy pealks

File: TVA Project (Isotopic Data for Feed Mat).xls' Sheet: Dala311/02

TVA Metal Button Data

Sample Number UraniumPurity

Tc-99*(nC0/e)

TJ.208I(nCiue)

111-212 Cs.137* Pb.212Csamma Spec.

Pn-234ma Rn.24 Th.~h24A U2~;4S U2A

9�1

Y011160006YOI I160009Y01 1160010YO 11 60011YO 11160012Y01 1160013YvO 1160014YO I1160015YOI1 160016YOI1 160017Y011160018Y0v1 160019YOl 1160020Y01v1 160021Y011160022YvI I I60023Y011160024Y011160025Y011160026YOI IS80003

0.9997979120.999SR986710.9999215520.9997910410.9998218630.9995000310.9998315230.9998397630.9998630230.9998737330.9996142830.9998762430.9998034230.9999049330.9999134430.9998425630.9999115910.9998361830.9998802610.999466051

100140315344145

262045

13031

1603090758571

100242

1.40E+059.40E+047.6012+043.40E+041.3011+051.50E+051.30E+051.30E+051.40L+051.30E+051.30E+051.50E+051.40E+051.501.+051.40E+051.30E+051.40E+051.30L+051.30E+051.40E+05

2.50E+05 2.9)0E+02 4.60E+051.7011405 I.'1, I+02 2.901X051.3011+03 r .00)l '01 2.401141)i6.202.+04 1.2011402 1.101+052.301+05 2.4011+02 4.001 4(52.60E+05 3.501:+02 4.7014+052.40E+05 2.901+02 3.80E+052.30E+05 1.(01+02 3.90E+052.40E+05 2.20U1+02 4.501+052.40C+05 3.3011+02 4.1014+052.30E+05 1.601-+02 3.901 +052.60E+05 9.0014+01 4.801.+052.50E+05 1.8014+02 4.10E40.S2.7014+05 7.001l.01 4.701+052.402+05 2.10114(12 4.I1014052.301.05 3.2011402 4.00(1+052.4014+05 ft00t -101 41.501+052.40E+05U 3.701 +02 4.0011+OS2.30E+05 1.6(d11102 3.80E4052.40E+05 2.70E+02 4.8014+05

6(81; 104

68.011+04

9.6014043-7011-4043.3017+046.3031:404

9.4014+047.90r2+041. 10141+5

7.0021-404

7.4021+04

1.10114031 .221:+051 .401410i

2.1011+06 5.70E+05 1.302+04 4.60E+07 . 1.20E+06 1.30E+042.2014+05 7.10E+05 2.30E+04 7.00E+07 1.00E+06 2.30E+041.2011*0i 5.10E,+05 1.70+404 4.40E407 . 1.30E+06 1.701-+048.9)01.+04 1.20E+06 1.40E+04 4.60E+07 t.70E+06 1.402+042.401.+05 6.70E+05 2.102+04 5.90E+07 I.IOE+06. 2.102+042.10E+06 7.902+05 7.00E+03 4.10E+07 1.10+06 7.002+033.00E+05 7.00E+05 1.802+04 5.80+07 1.10O+06 . 1.80E+042.10E+06 6.60E+05 2.30E+04 5.90E+07 I.IOE+06 2.30E+042.10Lt)+5 5.502+05 SAOE+04 4.10E+07 1.0tE+06 5.40E+043.501:+05 7.002+05 2.70E+04 6.20E+07 I-IOE+06 2.702+042.10E+06 6.80E+05 1.60E+04 6.202+07 1.10406 1.60E+042.10Et+06 7.502+05 1.102+04 4.50E+07 I.IOE1+06 1.IOE+04I.90)+06 6.002+05 2.60E+04 5.60E+07 I.OOE4406 2,60E+042.20114N5 7.20E+05 1.702+04 4.00F+01 I.IOE+06 1.70E1+043.501 405 6.302+05 1.202+04 6.30E+07 I.001E+06. ,1.20E+042.701+05 6.70E+05 1.70E+04 5.60E+07 I.102+06 I,70E+042.6021106 5.402405. 1.20E+04 4.30E+07 1.20E+06 i.20E+04.1.5014+05 7.402+05 2.40E+04 6.10E+07 1.202+06 2.40E+042.0012405 6.70E+05 6.00E+03 5.20E+07 1.102+06 6.00E+034.201 +06 9.202+05 2.80E+04 8.30E+07 1.30E+06 2.80E+04

Average 0.999808954 7.46E+0 1.27E+05 2.24E+05 2.071E+02 3.941.+05 8.8014+04 1.II 1+06 6.99E+05 1.93E+04 5.44E+07 1.15E+06 1.93C+04Std Dev(%) 0.01% 79.1S% 22.18% 21.96% 47.65% 22.84% 29.05v.. 106.56% 21.57% 53.64% 20.66% * 13.38% S3.64%/

Avg (pCIlg U) 7.462:+01 1.27E+05 2.241.+0t 2.0171:402 3.941.+05 8.N011404 1.111 406 6.99E+05 1.93E+04 5.44E+07 1.15E+06 * 1.93E+04-

*Majority of sample data <MDAContains sample activities that are artificially high due to intcrrcrencc from o(I1Lr pgtinta spcwroscopy peauks

311(02FHIe TVA Project (Isotopic Data for Feed Mat).xis

*Sheet: Data

TVA Metal Button Data: Th-230:U-234 Ratios

Z- ' ... .1 -': ;..". k! , -.�Afpk�J, ,,,9 A ai

vrazieumb ?flu m ZFd.$Aanlp urber 'i ' ' ' '~.-P_____ Iurltv - B- ) pC/ U)OZJ UJ ..

Y0l1160006 0.999797912 2,943,568 7.96E+07 1.05C+04 1.05E+04 1.32E-04Y011160009 0.999889671 3.208,859 8.67E+07 9.61E+03 9.61 E+03 1.1 E-04YOI 1160010 0.999921552 2,855,907 7.72E+07 1.02E+04 1.02E+04 1.32E-04YO 11160011 * 0.999791041 2,286,110 6.1 tE+07 7.32E+03 7.32E+03 L.8E-04Y01160012 0.999821863 2,925,113 7.9IEtO7 8.6 1 E+03 8.61 E+03 1.09E-04YOI 1160013 . .999500031 2.938,955 7.94E+07 1.04E+04 1.04E+04 1.31E-04YOI 1160014 0.999831523 2,927,420 7.91E+07 9.74E+03 9.74E+03 1.236-04YOI 1160015 0.999839763 2,918,193 7.89E+07 8.58E+03 . 8.58E+03 1.09E-04Y01 1160016 0.999863023 2,920,500 7.89E+07 8.2SE+O3 8.25E+03 1.OSE-04YOI 1160017 0.999873733 2,911,272 7.87E+07 8.62C+03 8.62E+03 1.1OE-04Y011160018 0.999614283 2.918.193 7.89E+07 1.I0+04 1.0IE+04 1.28E.04YO l 1160019 0.999876243 2.968.944 8.02C+07 1.07E+04 1.07E+04 1.33E-04Y0 I1 60020 0.9998s03:42 2.980.478 8.06E+07 8.88C+03 8.88E+03 1.102.-04Yol 1160021 0.999904933 2.982.785 8.06E+07 9.79r+03 9.791+03 1.21E-04nl0I IWx)22 O.999 :: .980.47S 8.062+07 8.221+03 S.221+03 1.02E-04

.Vl 160023 0.99'J845c.3 2,955.103 7.99E.+07 1 .05:+04 I .052+04 1.312-04Vo II60tl24 t.s99991! JI5 2.962.023 S.0 11+07 S321.403 S.3 2+113 1.1141:414Ytl I 36002i 0.999330183 2.943.568 7.962+O; S.721.+03 S.72103 1.102-'t414Y(l I 160026 0.9998S02o1 2.934.341 7.93r.+07 s.935+03 S.951+03 2.132!.4Y(lI58051M3 0.'i994461 '.5 2.936.648 7.942+07 .1OE+204 .I02404 1.39F1E4

A.')r)98O}S J 2.9212+06 7.89 .+0 7 9.35E403 9.3513 j 2.191-04

Std 1k(-(%) 0.0 1. 5.60% j I.ao, 9.9 2

File: TVA Project (Isotopic Data for Feed Mat).xlsSheet: Age Ratios311102

Result.of decaying I Curie of U-234Decay time of.13 years = 4;748.25 days

Combining the same daughters resulting fromh different decay paths.

-Nuclie .U-234Th-230Ra-226Rn-222Po-218Pb-214Bi-214Po-214Pb-210Bi-210Po-210

Fraction9.99963e-0011.17016e-0043.28897e-0073.28134e-0073.28134e-0073.28065e-0073.28062e-0073.27993e-0074.00938e-0083.99168e-0083.54030e-008

ACt lVl ty kL1J)

9..99963e-001i;17016e-0043.28897e-0073.28134e-0073.28134e-0073.28065e-0073.28062e*0073.27993e-0074.00938e-0083.99168e-0083.54030e-008

Th-230:U-234 = 1.170E-04

Result of decaying 1 Curie of U-234Decay time of 5 years = 1,826.25 dayssame daughters resulting from different decay paths.Combining the

NuclideU-234Th-230Ra-226Rn-222Po-218Pb-214Bi-214Po-214Pb-210Bi-210Po-210

Fraction9.99986e-0014.50082e-0054.87111e-0084.84179e-0084.84177e-0084.84066e-0084.84055e-0084.83954e-0082.4102le-0092.38208e-0091.75485e-009

Activity (Ci)9.99986e-0014.50082e-0054.8711le-0084.84179e-0084.84177e-0084.84066e-0084.84055e-0084. 83954e-0082.41021e-0092.38208e-0091.75485e-009

Th-230:U-234 = 4.51E-05

* . Result.of decaying 1 Curie of U-234*Decay time of 10 years.= 3,652.50 days

Combining the tame daughter .resulting from differenit decay paths.

NuclideU-234 -

*.Th-230Ra-226Rn-222Po-218Pb-214Bi-214Po-214Pb-210Bi-210Po-210

Fraction9.99972e-0019.00138e-0051.'94700e-0071.94113e-007'1.94113e-0071.94071e-0071.94069e-0071.94028e-0071.86446e-0081.853,69e-0081.58584e-008

Activity (Ci).9.99972e-0019.0oi38e-00S.i.94700e-007,1:94113e-0071.94113e-0071.94071e-0071. 94069e-0071.94028e-0071.86446e-0081.85369e-0081.58584e-008

Th-230:U-234 = 9.OOlE-05

Result of decaying 1 Curie of U-234Decay time of 15 years = 5,478.75 days

Combining the same daughters resulting from different decay paths.

NuclideU-234Th-230Ra-226Rn-222Po-218Pb-214Bi -214Po-214Pb-210Bi-210Po-210

Fraction9.99957e-0011.35017e-0044.37751e-0074.36871e-0074.36871e-0074.36779e-0074.36776e-0074.36684e-0076.07139e-0086.04826e-0085.45190e-008

Activity (Ci)9.99957e-0011.35017e-0044.37751e-0074.36871e-0074.36871e-0074.36779e-0074.36776e-0074.36684e-0076.07139e-0086.04826e-0085.45190e-008

Th-230:U-234 = 1.350E-04

AttachmentJBMass Balance Data & Process Flow Diagrams

BPF Process Mass Balance Pata* w- x-^ye _; 'v-i':! !,r',;w 3'ge. 't *@ -4$1¢All*

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Uranium Input StreamsHE U Metal Buttons PiecesHE UAI, Alloy IngotsNatural__U Oxide, U03, for TVA Down-blending JNatural U Oxide, U0 3, for SRS Down-blending

ProductsLE.Uranyl Nitrate Solution (4.95%°/ U 3 5 ,G1

Natural Uranyl Nitrate Solution, for SRS Down-blending |Liquid Effluent Streams

Caustic Disclharge 184,737 'yr

Condensace from Solvent Extraction (SX) hl5 .t47l r

Ratlinate from Solhcnt Extraction (SX)' | I

Scrubber Solution d 597.542 lJyr

Notes:a - Based on a 0.01% loss ofiE U. from UAI, ingots in caustic discard Strcam.b - Based on a 0.005% loss of lIE U. from UAI. intzots in SX condensate strcam.c - Based on a 0.0004% loss orfF U, from UAIX ingots in SX raffinate strcam.b - Based on a 0.0035% loss ofHE U, from U metal buttons and UAI. intots in

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. Attachment C

.IBLEU Preparation Facility (BPP) Radioactive Gaseous Effluents

The radionuclide concentrations inithe HE UAlI alloy ingots are the same (on a pCi/g U basis) as the HE-'U metal buttons. The -only difference between these two forms of feed material is the aluminum.

The concentration for the low enriched uranyl nitrate solution (LE UN) was calculated by summing theannual quantities processed for the three uranium feed material streams used for the down blending (ic.

*HE U metal buttons, HE 0AI alloy ingots, and Natural U Oxide). The radionuclide concentrations inthe LE UN were calculated by dividing the Ci/y of each radionticlide processed by the kg U/yr of IE UNprocessed, which results in radionuclide concentrations in units of pCi/g U after some unit conversions.

Calculation of Unit Dose Factors: BPF Gaseous Effluents

Unit dose factors for the gaseous effluents from the BPF were calculated for I Ci/yr releases of eachradionuclide using the CAP88-PC Version 2.0 atmospheric dispersion anid dose assessment computermodel. These factors; in units of mrem/Ci of radionuclide released, were used to estimate the potcigialannual dose to the maximally exposed individual (MEI) attributable to the facility's radioactive gaseouseffluents.

CAP8S8-PC Version 2.0 Input Data:

Tfhc mcteorological data used for the calculations was obtained from the Nl:S' 1996 Emvironmenal)Report. The wind data filc that was created using the rcferenced nmcicorological data has been namedNI'S5Y.WNI). Tfhe referenced mcetorological data also included: 1) an annual average preeci)itation of103.4 cm, 2) an annual average ambient temperature of 13 "C. and 3) an S00 m lid height.

Thc "rural" sclection wvas chosen for the EPA Food Source Scenario, using all of hic default parametersassociated with this selection. Dose calculations w%'ere performed for the followinu distances: 150.200,250, 300. 350, 400. 450, 500, 550, 600, 650, 700, 750. 800. 850. 900; 950. 1000. 1500. and 2000 meters.All particle sizes were assumed to be I pml AMAD. The default solubility classes were used -. call casesexcept for the following radionuclides, which have solubility classes that are dictated by NWS ProcedureNFS-HS-A-27 (NFS, 1999).

Th-230 and Th-232 Class WPlutonium Isotopes Class WTc-99 Class W

The radioactive gaseous cffluents from the BPF will be released via the 416 Main Stack. The physimlstack height is 33 in. the stack diameter is 1.52 m. the plunm rise is momentum dominatcd. and thecxitvelocity is 10.77 tn/s.

The maximally exposed individual was determined to be 700 m in the NNE direction.

Estimate of the Aiinnual Radioactive Gaseous Effluents frorn the BPF

A""ual Pronessizn stimNtei - W;sed on Mass Babince lIfornalon, . *-HE U Meta BDutaow=. Natwal U Oikde. UO. io1VA.

Cuntjubttve ARF: I .S4 i3 .iunl U Oxide. UO,. io STott Natural U Oxide, UO,:

HE UAL Alloy lauos: CusuSulative ARF (TVA Masem?)- I i =Cunanulatve ARF: 4m99iE,03 Cuunwulative ARF (SRS Maerial): 2.90E4.03

Effickocy aMMitip ion Equip 94.97% (HEPA Filtet) L -*m LE UN:

* ~Cumn wubtivc ARf. 4 O01sO

.. ,. .. CAssC Summary of Stint DPF Gaseous EffluentsX X X oe sed', , ,-- gated JL.5-

'ci ia 4IF cI'r9 " ('L y J _ _ __ _ _

U-232 234 .A4E-02 J.31E-6 03746% 1.0E-03 13635%U-233 66-5 1.36E-02 4.09E46 0.3SS7 2.73E-04 0.36s5%U-234 63S 23E+00 9.65E-04 7S.1334% 5.69E-02 76.9108%U-23S 62.9 4.s4E42 IASE-05 12622% 9.14E44 1.2352%U-236 623 6.17E-01 1.5E5-04 16.0751% 1.15E02 IS.5830¶AU-233 S3.6 1.61E4-l 4.52E.OS 4.1881% 2.32E-03 3.3131%U Subtotal 3.74E*0o 1.12E-0.4 97.3920% 7.5E-02 99.2791%

ns-223 117 I.37E)O2 J.l I E6 0.3575% 4.31S-04 0.6307%Tn.230 147 3I22E4t 9.67C-0s 0.0034% 1.42E-05 0.0192%lh.231 4.73E.04 4.101.42 1231.45 $ 1.063. 525E.09 0.0000on71.2.52 163 1_3515OS J.05-09 0.000.1% 6.S31.07 oo0.00 :T2.!3I 4.535.02 6.6i5- . 2.00o-07 0.0173t. 9.145J09 0.00001.Th Subtulal -57F-01 Ib.67t4o5 1.4525% 4.906,04 0.6701%

I.'2 2.34 1.91:4O J.775-3 0.0041oJ 1.121:503 0.01$1'_l'u-2,240 21 ln.l:J1)5 3 0 0.0003.t%. 7.9917:07 0.0011%rN.241 2.77 261'5V3 8.04.5.07 0.06s9r 2.2tl4K6 0.003n-" Sulbnatl 2JAS:-0 3s.55547 a.0743'/. 5.41f:Un5 (1.0 191%

Ans-241 269 7.7-.05 2%4F5-OS 0.0020% 6.21S-S0 0.0035os:Nr-237 246 13541 33-03 0.003sr0% 3.32oo0E 0.011O%

Thoium SericsKa.223 4233 1.071-0J 3.201:.09 0.0)03 IA40t.00 0.0000%n oAc-223 4.OOE02 1.071-05 .1201!.09 0.0003% 1.23.ilO o.o00%R.''2J4 1A6 1.371:-0 J.1II.06 0.3575% 6.t3E46 0.0092rrb-212 7.7E402 161E-02 4.07E.06 03539% 3.171.47 0.0004%IWi.112 1.52E4-02 7.72C-0t 32.-06 02012% 3321:40S 0.0000%TI-203 s7E-04 4.3S4-03 1.311-06 0.1141% 679r.50 o.o0000%

tSrawhen SoriYsr a234 1.63E403 416E406 1AGE.09 0.0001% 2.33E-12 0.0000%/

P&-234nt 6.61 E07 1 84C.03 5M52r07 0.04so% 3.63S-13 0.0000%/Ra-226 I0.S S9E.07 2.69E.10 0.0000% 2.S2E409 0.0000%

Acetdutou SeriesPa-231 24S 1.13E.05 3.39E.09 0.0003% t31C407 0.0011%Ac-727 313 2.OSE-06 6.14C-10 0.0001% 192E507 0.0003%Th-227 5.49 2.00E406 6.00C-10 0.0001% 3-2s9-09 0.0000%tRa-223 4.S7 2.01E46 6.041-10 0.0001% 2.76E49 0.0000%

Fission ProductsSt-so 2.29 5.07E06 l.25.09 0.0001% 3JAE-09 O.0000%Tcs 4.34tG01 2MM5 6 7.71-10 0.0001% 3335E-lo 0.0000%/CS-13J 2.04 2.77£46 3.32r:-0 0.0001% 1.705-09 0.0000%Cs-137 7.3S5.01 7.13E406 2.14E.09 0.00012% 1.57C409 0.0000%Panw147 2.40C-02 2.9sE.07 334C.11 0.0000% 2.12E-12 0.0000%Eu-IS4 337 2255.07 674C.1I 0.0000% 227-C10 0.0000%

Crand Totals L.SE41 100.0000%/Y 7.40f-02 100.000%

I'u-- TVA Prokect (ISA lad Source Temis & EMuents).xlsSheet: BPF Air Eff

Estimate of the-Annual Radioactive Gaseous Efflucuts from the BPFA-naP FT.essiuf 811100" _____

lE U Metal BuflonS mCumrnulalave AF: 1.084E1-0

HE UIAI. Alloy Ingotr:Cfulnubtive ARF: 4D.9SE-0

Eficidercy ofMitiCltion Equip: 99.97% OEPEA Filter)

Natural LI Osirkd. UO^. to revsNatural U Wide. UO. to SRS: _

Tout Natural U Oxide. UOJi

Cumrmulative ARF (TVA Material): 2 .Cunurmulativc ARF (SRS Material),: 2--AE-03

LEUN.Cunuilulaiie ARF: 4IO-03

CAP8rc. . * r HEUMeial Buttons ..s ~k Die ksj4OzIfy. Ulcgme. ed 10m

U-232 234 4.17E+0S _ .37E03 4.1 EE47 9.62Eo-SU-.233 66.6 3.96EtO05 130E-03 3.90E47 2.60E-05U-234 6S.8 7 A9E407 2.59E41t .7.7SE.05 5.12E43U-235 62.9 1.194506 3.91Ez03 1.17E-06 7.1E.05U-236 62.3 091.7 07 SASEt02 1.76E-OS 1.10E-03U1-23 5S.6 5.34E104 1 764.04 5.7E403 3.09E-06t' Subtata* 3.256.01 9.7651.0S 6.421E0.1

'll"i.2 it? PAN I .05 1.3Il4t.1

: -01 J.5S.Ml3OtThn-20 117 g .t1-0.1 3.07F-03 9.1-.49 13.16.06

11..23l J.~t-I ).I~l.. .. 9114.'3 1.4k. 14.413.910

Itt-I i *15-.4 _6,11%i03 I.',IE.4et S.-21l:.10

11 Subiowal 5..1 41 I Vl J.7.'1S

r,-:.: ':..1 j3.-l3 1."1 .52 I .1I.0 l*.2^.i 3.^. 1 :1-I .*a.'2 - _ r~'~ ."- -- t~i.t -. .2l3Ar...2.'t : .- - ~ -l.-SI': _ -,C,,( IIJ -I l 2..S : .1'1-.0-Uz Suibtolal I.71VA4 XaE.01 I.uo

Am.241 1) 2.261:*II 7.J.413414. !2110) 5.9913-07

N1 37 U !. 01 1.071.0C 1 .2'1:4) 7.95EL.07

Thouisu Seric,

R-.?S J .!53 :.ilo 013.. jn1-3.I0l-o l.3~.'L.Ac-.2S IA.4.U2 .L0-132 1.02 I4K. 3.061.-10 1722E.-I

a-.?J. 1.66 3!'l-o5 _ 1.4111-0' I1J?1:-07 S11:417Pl-?21? 7.71113.2 3I 1-S91E-03 3.41:41; 27 3.0311--0

U11 ; ? .21? 1: 7.KI:J.04 11:41 7 .36I t60911-205 3.I714J 1.?7E-OS J.101304 I12SI3.07 6.J71:.11

Craniuni Series

pa4.3 1.631:.J7 1391. 10 2.27E-13PJ 234mi 6.61E4-07 S.3413I 1.76434 5 .22E .03 3.JSE 14RPa-226 10.5 2k0o 1 S.SSE-OS 2.5613- 1 2.69E-10

Aalnsun SermPl-23I 245 32340 I.03I.06 3.23C.10 7.92E 03Ac-227 3115 3.94J 01 1.95E407 5.561.11 123E-03l-227 SAS S.S O 0 1.9113.07 S .73E-ll 3.131.10Ra-22 J.57 S.S41 01 1.9214.07 5.76113I I 2.63E-10

Fusiof Priduets

Sr-90 2 9 1.J7E-02 _ 4.331.07 1.451E-10 3.32E-10Tc-99 43411411 7.461DI01 2.451.-07 7K361-II 3.l9-Cs.114 2?04 S.0.0S4 _ 2.6b3S07 7.915.11 1.621:-10Cc 1 7 7 'SI-01 2,071302 6*013.07 2.0Jl1-40 1.50C.10Pam-147 2.4013.2 3.53E400 23.SIE-05 S.41E-12 2.02C-13Eu-ISA 3.37 6S213109 ._141?.03 6.41E-12 2.17-.11

Dose Tolah 6J71O.

File: TVA Profca (ISA kid SourccTeCsmt& Et&luets.alsShotg: ItF~i 2lff

Estimate orthe Annual Radioactive Gaseous Effluents from thie.BPFAnnabi Procslar Fi.rates BDisfd on M3i4 Rtance nonnhiio;. *

HIE U Metal Buttons:Curnuudati4e ARF: I .0S4E-03

HE UA1. Alloy Ingots:Cumrnlative ARF: 4 09SE403

Effiecy ofMtigatson Equip. 9997% (HEPA p'lter)

Natural U Oxide. UO3. to IVA:

Total Natural U Oxide. UOf _Cwtgnnulative ARF (TVA Materia): 2.280E03Cntantutative ARF (SRS Material): 22'tE*03

LE UN:Cunintultive ARF: .10E3

I

Fit: TVA Projet (ISA RAd Source Ternit & ElIlumnasa).ASSiscmt lltFAi l'ff

Estimnate of the Annual Radioactive~Gaseous tfflueiits from tie BPF

An inst Processin. Es1ivies- . ;ed ao Mass Bablnce bqrohUmtdo.:

HE U Metal Lus2asC* rmnublaie AltF: I.OUE403

HEUAI.AlloylngotsCmnu latsc ARF. l: JD9SE43

ElflKecy of MitigaSton Eqsip.: .9.97% (HEPA Filier)

tiural U Oxidc. UO. to TVA:.*Natuhal U Oxide, UO . IC, SRS: *

Toul Natural U Oxide. UOv: _Cunmutzive ARF (VA Mtcrial): 2.20E-03Cummnuadvte ARF (SRP Macri l): 2.290E43

LE UN:Cunmsuiulvt ARF: 4.010

Fiq TVA Projal (ISA Rad Soure Tcnts & Eaaascs).xIsSlt: Off Air Effs.. 0.

. Estimate of the Annual Radioactive Gaseous. Effluents from the BPFAnnual Procetsinr Estiuaves -BMsed on ltia Balance Infonnatlon,.

HE U Metal Butons:Cuhminltv CARF: l.SlE.03

Natural U Oxide. UO,. to TVA:iatural U Oide. uO,. to SRS:

HE UAI AlIoy lngotsCummubtive ARF: 4.095E.03

' EmsecyotrMigationEquirp.: 99.97% (HEPA Filter)

Total Natural U Oxide. UO1,Commulative ARF (TVA Matrial) 2.280E-03Cummulative ARF (SRS Material): 2.290E.04

LE UN:Canmulltive ARF: 4OIOE.03

kCAiwPCU-232 234 .ME03 2.70E-06 6.31E44

U-233 "A IE43 2.56E46 I.71E4U-23i 6S - 1.79E+oo * 5.37-04 3.53E-02

U-235 62.9 2.96E-02 S.89E06 S.S9E.04U-236 . 62.3_ 3J6E-01 1.16E-04 7.21E403U-23s 53.6 _.SSE-02 2.57E503 1.1E03U Subtotal 231[E+O0 692r.44 45SE402

11Th.' 117 _.5SC-03 2.571:.46 3.L.01E41lh-'30 147 202 _E.04 6.051:,4 SS9C.E6T-:231 J.7.3E04 _.57E-02 7.701.0e 3.64r.o)Ih.232 163 _.J45r.06 23S-IE4 f J1.21:-07lb -:34 4.S5E40 1.161-04 1.51.07 5.72E'.)T.Subtotl .49Cl42 1. -5 .. E 1 EI .043 t5.3J _1_ 9.1.9J t lS ... 0 2 .9SE 0.1OPo2.%9'40 261 3 _ -1 S7

Pu-.21 2.77 _-1.651:07 I..-A0I6.O6Po Subtntal 1.75F4-3 ".3S107 X157V.V06

Ant-1- 269 4.S7E4.5 1.461.4S 3.931106

Np-217 246 - _ 7.03C43 2.121>4S S'201C06

Tboriun miSciRa-2:s .533 6.69E-06 2.1Ei-09 S.7t.07

Ac.22S 4.00OE40 6.69E>06 2.011i09 S .02E-II

R.a-22J 1.66 S.SSE-03 2.57E.06 4.272>06

MbM'l' 7.79C-01 O.502-03 2.51-06 1.991.071;212 1.52E-02 4.33E4-03 I.J5E06 2' 2C0.sTl-203 5.17E4 _.74E-4. 3S.":07 J.251-l0

Vrumilu Series3a.234 1.63E-03 3.04E.06 9.12E.10 1.49E12

PA 234n 6.61E-07 _.ISE403 3.4AE-07 2.23E-13

Ra.226 6.1MS0. 5.61 E-07 I.6SE-10 1.77C-09

AclolubmSerlks

Pa-3l 1 24S 7.07D£-06 2.12E.09 5.204-07Ac-227 313 1.21lE-06 3t4E 10 1.20E-07Th-227 S.AS 1.2506 3.75E-10 2.06E49Ra-223 437 1.26E-06 3.781S*10 1.734.09

FdsS"o r,-sldsnStr90 2.29 3.17E-06 9.51EU I0 2.13E.09

Tc.99 4.34E401 IAIE.06 4.83E 10 2.09E-10Cs-134 2.04 1.74E06 53.21E10 1.06C.09

Cs-137 7.3SE401 4.46E-06 134E-09 9.841E10rm s147 2.40E02 _.S4E-07 5.53E-I1 123312.2

Eq-154 3.37 A1.41E-07 4.22E-l 1.4210AI

Dose Totals 4.S71102

rk: IVA Pfeoi (ISA kid Soure Teumis & rtflesnis).xI.Sleect: DM2' Air I' IT"ml',

Estimate .of the Annual Radloactivc Gaseous Effluents from the BPF

-A..,..l Pn-en1.. E r t- t * .en M.. . aIn.. Infr-nnn -a.

. HE U Meal Buttonsr Cuneulaiivc ARF: I.OS4E.03

Nalural U Oxide. U03. toIVA:Naursl U 6Oxide. UO,. to SRS:

Total Natural U Oxidc. UO,.Cuinniublivew. F (IVA Matcrial):Cbmuliati ARF (SRS Matcrial):

NHE UAI Alloy laeotr _CumundatveARi: 4.9GSE403

EflenyotMiltgaton Equip. 99.97% (1fiEA Fidtr)

2-10E-03

LE UN:Curmimiulatve ARF:

.,CArSwc. *!- Na;(uranU'qOidc,U0J,Io'SRS

U-d lgalcd .s(1tnkaed.

sE:,~

U-232U-233U-234U-23SU-236U-23SU Sublatal

1l1-225-Th.230Th.2.'l711-232

Tb Sublal

Pu. s. siaI u2JIPta Sula:..tai

Am-J241\r.237

XRa2.'s

Ac-2!25Ra-2:4Pb-212

lrniu 3Sek

(Xrzapiuall Selics

Pa-234ra-234m

Ra-226

Actialumi SefisPa-231Ac-227Tb1-227RJ-223

ressa P-rnducxtst5t 90Tc-9'9Cs 11 37Cs-I137Pm-147EU. 154

D.er I-Gltta

23466.66S.62S62.358.6

1171 J7

4.73E104168

4.5sc-02

2612.77

2h9246

438d.oorC02

1.667.79E-02IXE-025.17i,.4J

1A3E4036.61 E-07

10.5

245313SA4.57

2.)4.34CEi

2.0473sr-Cl2.4AEC02

3-37

3.4648051.566404

3.34E0S

.26SE.021.22E43

2.60E-02S.JIE42

LOSE-OG3AME-07

7.81 E-061.62E-OS

5130E442.30C-0S

1.S31 1.(1.o I Fe O

1. IE.-0._____________ J I

JFc: 1YA ProjtcI (ISA Rid S4uncc Tinns& 2illuisJllsSb5ctr U l'Air Eff

Calculation of Airborne Rclease Fractions (ARFs) for tlze BPF Processes

pracala6 I(E tPl daflal~bo s

OsidazicnetP4aul (Ul6) . .000-OS 03004ID0K.010-P4.Sscslsa .31.210 ' .IDb442. kvasng~ne *.scACM Di d; (OSid (UN) LOW.-O5 DOCE-HDl; O-94o TabTlhk 4-1!. 1000 m po.JrSpillsf tcon I mnighlTInn, fl Proaes Moaisanq Con.. I.OOE46 (DOt-ltlOlZ.010A44. Tabsl 34. I000 al UNL1 spilli lInin I als highlTrasfer vo UN Sst Cohma,, I.0E40S (D DEN DEO:40l1O-94. Table 3J4 2000 ad UNH spills fmn I m high)IIlEU ttkegd Calm" 1.00E4 (DOE4-IIDO I 301044. Table 31.61000 ad U I spills from I In bightTrafer so IEU Fced Colianus I.OOE4S6 (0-.D(EI30l0-94. Tabk 146.1000 ns UNH spills from lns Ibrh)

Caunlssvt ARF: I.OUE43 *

Prnessng CilE VAZ Ail, lagolsC . . .,, t.-,,. ~ . ., -s; w...;_....-. ._.'.I....e+ .

�� 4;�,,, �',' -: -'. , �2 1 il Z �� '- , �, .1 �" ":, '. :.'. � :.- �

Sin Reda iCau isc'ACd Dissol.1ion ofUAI, (t1rra.dr bo A ubilly'0 ColulaosIta Pass S.aho Evtractio.Ins Pas Strippapeaedr usilt Pass E .pa.k r FeW t.-C.sn lass E1pvras.r RCO.. CA...m

on N'ass LI, cvmvm,,w C,1.sae!n1 pIso Ss.4 Emsi..s.1:nl r " SmI*"S

:,J r..s Swilvi'v.sJ l. cm n l

:.raI r .. .. W - R,1.n- C.lNJ Cwotmn . ol t d

Irasuk, I..l% 2! FesScela

I.OE-

I OOC4S1.00C4Sa 050-06

1.00C.46

I rw:.-OhI X-3.411.

I .n"Mfi

. nOx:.0I 00L4a.I. 1541610.ra4nbI 01b.04

(No AMF vsak mvaibl bk, aad lsoust ARI daemod rasoatbl4(fOE4llOK.3010-94.TAbk 4-13. 1000 sa podva spaills fioan I mWsMhl(DO0.01108K.310194.Table 34. 1000 all UNlt spills from I n Witlh(DOP..l Hrnz 3I016. Tjbhk .5 I2Obn0a 1g UN'Il spills fronM sI tallsh100C.EIl1lJ0K 10 44. Tale b 4. 1000 ml M1lI splls twin I nUaight

I210tl IDUlJ;!I00.94. T"bk-6. 1000 pd L7'71 spills fen" I naipbat( IIOE UlDI1.3Y 1%1,. Secii.u M. .! P. 3-45. I..au s sas.q0N~l)l. R.3010.4,1J !ae a.. 1100 ad "AUXII spills flewil I ahiobHX)O0.221 I .I.al;. q. labJIA-,k UI-P) Ila LNII spills fia..M I ,.0

IX0I .191f111W.Su014. Ylibk !. In3 pdi LNIH s'.1 li.- I lhhSI -iOM 4 0Imi. I .01099J 1 A.bk 3,. 2I00 n l tNII slls

6,aI I higlh,

I rOlc-I I D Is I0 94. Tabalk Mb. 1.00 ad LNII sills fInw. I aIs2IX) I MI.2l .N.) 1 1,094. Se .n.s .2.3. p .S. )4M k"J I, 54

qtXlO: Itl I.K3)1 a2.94. Tbk- 1-6. I4Oad txll N IfI pislb, I s,, hisalIIOE.Jll)ltK.yml TabI l .. W al l ad I apiSl f(mn I rb

itl lE.ll3IDI0 l0 401. Tlabk! b. I2000 ai tNIlI opilli fS;u" mIhih'IIXN: I l1llt O3010 1..TabkJ .!6. ISOUmI LlOM spisllis f lis I "I o.$h

CaubilatJO.ARlIT 4.09SE40

Faioe.lastexataeal COidt Sam Do0 tllIallae

Slap | ARFISPets

I.... LM. ig, thl.por 1S1!0 .0(l:-lWlll0.. elOl 11. Tale I.k *0 1. ad rXu&Jrsills lnu I as lib.Clv-,e r.*var safv . k. fi-sugiam TainkI I.03 aOl? OXr IIIIIK.31010a. Ss.4.AI4..1. p. J441

Acd l ess.dagksa M. .. wiliivr £002 ILoE4$05 II)XX: IlDIII;R.Ol0.94. Tibb1 4.13. 1000 ai pii s Jpills fftm I m nlighl

Cuwlst..ie APR: 2.2tOE43

trucslang of LE UN

Sltp ARm 1.cferos

Ewaidawea DlvkS% Task sisYar 2 .00E43 WDOE.IIDOO.3010-9J.,5diot1s 3.2...P.3-2.bo.mdia sslbw)LCUPraok~tTAs Alk s 2.00E403 DOE.10ftC.3010SJ.Srtin3213.r 3.15.beaudiah.lTrusstraiTanLcar TnJCk 10C.UsS (005I lmilO.30Il sTall 3.. ad UI r pllra 0fvn !.

Convilhat ASF: 4.010C.43

rsmilng of lalarvl U OSde fkr SRS

SI | ARF Racera.

lAidD O. ia.e Itlppor 1.2(30t4 1ql0.llllMlDlcSIM-3o4. T bkd 4.3. 10 ad4 p-aas fapn. aniON1i.C-nnor Tranme efUO, io Disasil.6on Tank I2.-C' P4 OIDUlKl-ll0300l094. Srih *J 4.4.3.3.1. p. 4-841AciJ Diusiaa *PXO. halixer(UN) .OOE43 (DOr lll)DC-3010094. Tibk 4-43. 1000 daltlorda spills fcm I 2 hSi1h)Teasafa in Titlr Triak l.JJUI.:5 fIXI21:1)IDIIIC4Ir91.Tbla34. 2000 all tJX IIpillS r,,s 3 J Sgish)

Cassusatai ARF: 2.290t.05

Nle: A. AR F tf L.OC-06 for trarass at lOHU Mas dcsrowd asu'le. bariase atrb faall dbncoi usieu IIal, am l"srLThr DOE's itt rrsuhs -at based Cona E Id bong droed oral a hard flat swfa . aieh brahs ia a hi ARF Ibir therrnfter of' * w r a 0u.t dbaear raaoi

FilAr TVA I'oaeet (ISA Rid Soar. TornaA E!lanul.%UShekl: t5'F ARrs

Attachment DWastewater Treatment Facility (WWT.F) Radioactive Gaseous Effluents

* Calculation of Unit Dose Factors: WWVTF Gaseous Effluents

Unit dose factors for the gaseous effluents from the. WWTF were calculated for I di/yr rcleasesof each radionuclide using the CAP88-PC Version 2.0-atmosphlric.dispersion and doseassessment computer model. These factors, in units of mrem/Ci of radionuclide released, were'*used t6 estimate the potential ahnual dose to the maximally exposed individuaL (MEI)attributable to the facility's radioactive gaseous effluents.

CAP88-PC Version 2.0 Input Data:

The meteorological data used for the calculations was obtained from the-NFS' 1996Environmental Report. The wind data file-that was created using the referenced meteorologicaldata has been named NFS5Y.WND. Theyreferenced meteorological data also included: 1) anannual average precipitation of 103.4 cm, 2) an annual average ambient temperature of 13 'C,and 3) an 800 m lid height.

The "rural" selection was chosen for the EPA Food Source Scenario, using all of tile defaultparameters associated with this selection. Dose calculations werc performed for the followingdistances: 150, 200, 250, 300, 350, 400,450, 500, 550, 600, 650, 700, 750, 800, 850, 900, 950,1000. 1500. and 2000 meters. All particle sizes were assumed to be I ilm AMAD. The defaultsolubility classes were used in all cases except for tic following radionuclides, which havesolubilily classes that are dictated by NFS Procedure NFS-HS-A-27 (NFS, 1999).

Th-230 and Th-232 Class WPlUtOniu1m lsotopesClass WTc-99 Class W

The radioactive gaseous effluents from the WWTF were modeled as an area emissions source(i.e. di ffuse source). The release height was assumed to be 1 0 m, the arca size was assumed to be1O m 2, and the plume rise was set to zero.


* Estimate of Additional Radioactive Gaseous Effluents from the WWVTF

TbeNVWTF's rdiotlive gastous tMueisls; re "urentky anrtuiated.

Ann Jst Presnshnz EtInett - Bsated on itas R *la6 nee In rons.6n.HE UAJ. Alloy Ingt0s:HttU Mcttl 8uoon5

Causkpischarge: 114 737 WJ, Cuminut5veARF: 2.032E-03*n onasedcnaCO.1 HHEUAIloss)

Condensate from SX: 3S3347 Uyr CutnauttivcARF: 3.20CE5inDased 20.0osOt5% IE tUAlloss)

Rafinatc from SX: I Curinmuttive ARF. 3.2COE-45iBkBased on a 0.0004%. HE UAI Ioss)

Scrubber Solio.t: S97ft4X Ulyr Cunmnuladve ARF: 3200E405ased on a 0.003S% HE (Metal & UAI) loss)

F~ . N . X '' Fr. WE PYUlit Dose . * Unniilsstfd' 'asl . o. - tii ed

' Counstitent Factors Efheats . TEDE

. (nsrtXCI) . (ch rt) I (Itrt r) . (/.)

U1-232 040 2.03E-07 0.0759% t.021:-03 0.6678.U-233 J2O 1.9XE07 0.0721% 2.74E44 0.17S3%.tJ2.'4 340 3.SJEO45 14.3393s 5.3SE-02 5S.0or'2%13.5S 3)50 5.7103.07 (0.2I66% 7.701:.04 °<'0.19-mVL236 15 KW S.711.4 3.23577r. 1.16C102 7.RA1s:.U.23S 1 40 2.6013>s 0.0097% 3.43rs 0.0132.l Suoblu l J.t10 E-05 17.9913Z. 6.75E402 44.034o%

rb.:2t25s.5 3.03 3E-OS 11 31.244. 7.76E.42 50.6350%.slh-2PI5 321' .. n.,C07 0.2641%; .2.264-03 1 .J7{-.lb l I.0l:-o2 S.99W-COS 33.6114% ).26C407 O.oow .

111-232 3630 1.966F.OS 0.0111% I.9E-04 0.0711';Th-234 7.71:-01 IA6E-06 05.451% 1.12E-6 0.0007oo

Th Subiosal 1.22>04 45.16731% 7.9E-02 52.18601%

Pu-23S 5n00 3, .4 07 0.1302" I.7-JE-03 1.1367..PU-23s9 240 550o 2.24J:45S 0.00545: I.2SE44 0.0115;Pu-2J 1 57.7 5.5ssE4-6 2.1974% 0..WE44 O'22 1 rru Sublotal 6.253.-c6 2 3.W0% 2.21 .413 1.4395%.

Anm-24 5750 1.71E-07 0.06.3S% 9.32-Cs 0.640$'-Np.?

37 $280 Z.47E.07 0.0924% I92LX-03 0.5450-.

Tboraur SericsRA-223 695 23-SE-S 0.00S3% I.63C406 0.0011%Ae-22S 811 2.34C-OS 0.0053% 2.07E43S 0.0000%Ra-224 362 3.01 E-OS 112414% 1.09E.43 0.7105%Pb-212 IJE400 2.9s3s45 11.12S5% S.12E03s 0.0334%Di-212 1SE-41 I.6A9E-0 6.3263% 5.96E-06 0.0033%11203 2.13E-02 939E406 3.5S71% 2.01E407 0.0001%

Uranium SeriesPA-214 31.2.02 1.074-0S 0.0040% 3.45E-10 0.0000hrs-234in 7311r-5 4.03E.06 1 0so3Y. 2.93E-10 0.0000-.Ra.-226 175 1.67r.-09 0o07%1 3.50E-07 0.00o0Y%

Aceliun ScriesPa-231 5200 2.4sC-C 0.0093% 123E-04 O0S04%Ac-227 6720 4.49Es09 0.0017% 3.02E4C5 0.0197%T11-227 120 4.3S3E09 0.0016% 5.26C-07 0.0003%Ra-221 94.5 4AIEs09 0.0016% 4.17E-07 0.0003%

Fission ProductsSs-90 33L6 1.1 I E.-OS 0.0042% J.537E.07 0.0002%Tc-99 5.43 S.64E09 0.0021% 3.09E.0s 0.0000%Cs-13J 29.1 6.0SE-09 0.0023% 1.774-07 0.0001%Cs-137 9.4 136C-os 0.0035% 1.47E-07 0.0003%

nri-147 4JSE.01 6.46CAOI 0.0002% 3.07E-10 0.0000-.Eu-134 52.6 4.93&-0 0.0002% 2.59E40S 0.0000%

Crand Tolats 2.67E.04 300.0000o% 5.533-03 300.0000%

IfINI,Fik: TVA ltoject (ISA RFd Sourcc Tcnns & Elnlucnts).xs

Slwe: WWVA'Air 3fT

Estimate.of Additionial Radioactive Gaseous Effluents from the WWVTF * -

The WvITs |Tradioactive gaseus oseents ire curreotmatntdtigated.,

Annual Procsslin EstimsateHE UAI. Alloy Ingos -HE U Metal Buttons:

Ce InufanI1uikn.

Caustd Disciarge: 114.37 *W. Cummaldve ARF: 2.032E03* * _ l d an a 0.61 X HE UAl lo-)

Condensale from SX: 2 C e7( sod on a 0.005% I E UAI loss)

RaFinate fios SX: Ia c t3ascd on a 0.0004% HE UAI loss)

CunmuniativeARF: 3.200E-03

Cummuladve ARF: 3120E-05

Scrubber Soludon: 597,542 4 . Cummulative ARF: 3200E-05_(Eaaed on a 0.0035% HE (Meal & UAI) loss)

nIjat Dose Wastewater Uatiltipted EstliutedConstilpetI . Faors Procesed . E tnt TEDE

* (nrnVasc) (CWO (CL~rr) (-nrevmr)

U.232 t4o0 9. Sl>05 l.sE.07 I.ooE.03t -2J1 I J.N 4 YE4r-oS I " sr..o7 2.68rs4J

l',3 3 '1: 3.762l:O' $.2>:102

O ',,1 ~~Q -):t. S..114. Il~:o'..l>OJ 3:)< s .A~l:.07 .sil.lso~s- )l413 *4~206 .131.-02

V.213: 2l :sl:.03 2.53C>05S 3.151>t0i1 Sul-s,.Ia 4.71 :.S* 66120-0i!

Ib 23' .15.b . ul:4v. 1A6.4^.sy l.:JI:-°

h-23i Jht O.E.4S I.S71%lo 6.5SE.071.23,' 7.721 :>02 . $3306 9.201.09 7.04E-09

Th SubI..tal 7.71E-tt7 5.0JE-t4

m-w.23 F3.0 ; -.7S14)6 2.01: 09 l.1.03C4pu.23JI'J40 5 PO 4..JE.0S 1.411>40 7.S71:07l'u.2.l 3.7 , : >03 3.711:-Ms 2.lJl:-06I'm SUlatutal .94F:418 l091FSl

Am.24l 5730 1.41.07 I.O5Ii.0') 6.19rn-06Np-2,7 S 4.) b..,l 7 1.56E409 S.1-1:46

Thnnuai ScricsRa.225 69.s -.27EOs 1.131.10 1.03E.4SAc-22S3 5.8E.01 -.27E4S 1.43E.l0 IJOE.10Ra.224 36.2 4.3JE.05 I.90E.07 6.57E46Pb-21 I 2.7 9.24E.0s Im.r107 3.23E407W.2 212 3.4610 1 $.2GE.OS I.07C407 3.69E.OS77-203 2.11L>02 2.93E.0s 6.05r.4S 1.27E109

Ursidus:i Srer

Pa-23J J.2 JE-02 3.31E:4. 6.72C1 I 2.1SE1142

Pa-234m 7761.4j I.SC.05 2.55E Is03 1.M512RJ-226 178 6.)O1-W) 1.214-IlI 2.2E1.09

AakdiurSefrksPa.231 MMtl .69E4S 11.10 8.13E-07Ac-227 6720 1.391E-s 2.331S1.1 1.90E.0711.227 1211 261-SG 2.76E-111 .32E-09RJ 22J 94.5 1 .S71.03 2.73C-1 1 2.63s-09

Fissln PrenodelsS,-90 31 3.J451-0S 7.01 E-lI 2.23JE09Tc99 SrtS 1.7IE-0 33611-1 l.95E.0Cs- 134 !9.1 I.s9Et.i 3.3E .11 1.12r-0Cs.137 9.4 J.36E103 9.s7E11. 9.23E.10rPn-147 4.7510.11 2.01 C09 4.031-12 1.94C.12

lEos154 S2hoa 6c 3.11E-I2 1.63E.10

Ihsel et~is G6E"-02

I,, .1I ok: TVA Pgseet CISA Rid Souice Terns & F.Macwts).Alg

qhg. Wrrr A;, Fff

-.--

Estimate-of Additional.Radioactive Gaseous Etfluents from the WTF.-The %%%'Trs radioactive taseous emuents are cumrtlrn mitipgaled.

Annual I'mccrnr E stigges. B s"e on 1ntlatRslahe Inf.oritudga,HE UAI Alloy lngots-

HE U Mttal Buttons-

Causii Dige 1 l4U37sed on sC.01%HUAIlb5)

Condcnsntew fronSX: 153347 iJyrmaascd oil a 0.005% IlIE UAI loss)

Cummubladve ARF: 2.032E-03

CummulaiiveARF: 3.200E-05

R finste from SX: I*5 s Based on a 0.0004% HE UAl loss)

Cunmrulative ARF: 3-2OE-03

aScrubber 5;oluton: 1 H . Cummubtive AF: 3200EOSon a 0.0035% HE (Metal & UA) )los)

t; ¢ tr~a{s.CA s ./

U.dI Dose wstersater- Utsd *ssinuledConstituist Factoars rocessid Effluctts 'TEDE

(wrernV) (ClMr) " Civt (inrcn)

U-23'uet3tU-'YAt:-:.2

Tb Submlti

pv-2n5rim-239 240ru SA PId j

Ani-:41

Pu 7bauia

As,,-24 1

Npr-237

Thouiut sSerksRa-225Ac-223Ra-224

Bi-212TI-2 0S

rragiums SerisPI-234Pa-23-InsRa-22.6

Acliniut I Series

Ac-227T11-227Rt-223

Fission ProductsSt.90Tc-991Cs-l34Cs-137ri,. 147Eu-154

Dose Totals

5040I4201400

13301250

.55o07.7E-ol

500U

S7.7

57509240

69.8S.tE OI

36.21.73+3003.5E-12.1E-02

3.23E027J1E05

17S

52006720

12094.5

31ft5.4S29.19.4

4.&C-0352.6

4.39E -OS E73-094.65r.4-5 1 .49C099.253e-03 2.9613.07I.40JE4J JA71.092.101403 6.724-OS6.2633-06 2.0033.30

.6 tl-X,:.O OE-IO3.0

4.6'E4S '.J' 41.10106 11 . 3Il 11.403.04 4.7134-094.SOE-OS l.47-.122.26h-6 7.24JL-I

5.4J E-07 1.73E.1 I3A7C45 LI.II-129.1.33E06 2.92:.10

3.303.10

2.65E-07 3..tSF.-23.S tE.07 1.231-11

7j933-062 11.-06

5.9431106S.9J1.4052.51 E-07

3.12E-07

.3AC. 115.J I E.095.59E-I I3.97E tK;

6.20E.t09I h69E4SL.393-07

J .SSE456.4311.0S

S.12E-1 I1.03E-125.4 I E-ft2.543-092.91E-10L.OOE- I I

3.6440S3.64ES034.67E4-54.62E4.52.63E05I A9E-05

1.16E-121.16E.121.49E49I.4SE09t41.E-104.77-I10

1.65E-oS 5.29E.13 1.71E-146.26E406 2.00E.10 1.46E 143.05E49 . 9.76E.14 1.743-lI

I.ZSE-036.97E-096.80E-096.t5E-09

1.72E43St.75E4099.4JE-092.43E043I.OOE-097.6SE-10

1.23r3-122.23C.132.2C3-132.19C313

5.5217.132.80C-133.02E-.I37.717:.133.21 C-142.45-14

6.40E-09l.SOE-092.61E3II2.07£Il

1.75E-I II1.53E-128.79E.I2730E-121.52E-I4119E 12

5.24C.04______________________________ L �

Ijilc: TSA Poject %ISA R34 Sourvce Tenn$s &. ltuentsl.xAs111C:~* ...clV t.. ... _... .. _-

Estintate-jof Additional Raidioactive Gaseous~ Efflubnts from the NWWTFThe NWWIrs radioactive gaseous e~n~eats are Curnly eam..Lltigstd.

An nugl Prouessi'tp Egisnawr Bfased of; Malss Balance Ivnniwat Ion,

IE U MetalButtons:

C4igCNShtC .CurnmuladiweARF. 2.032E-03

lased 6 a IHEIIUA1lo)

Condcs~terromjX: Baed sa 0.005% lIE UAI loss)

RuIfinate tram" SX: IIO 'G a 0.000% IIE UAI losi)

ScrubbcerSolut~o45: 597.542 Llyr

Cununtulzi'c ARF: 3.200C-0S

Cummrulathe ARF: 3.20007-03

Cumutsltive ARF: .3.200E4-53n1 as a 0.0035% lIE (IL~eUI & UAI3 loss)

.IUnit Dos . atcaert Unllaeul IziuConstituefti- Factosi Processid Mentas- TEWC

{mmF~d) (C1~S" C'r (u'

V.232U-2S31

U.233U-734V.231

111-2.10111-211II1I-2.%2Th-!34TI. Sublotal

ru-2.33Pv-2W:-Q45?u.241re SOMAuij

.U11-241

Tborium Setic,

Ac-229Ka-124rb-212Di-212TI-202

Urldantiu SeriesFa.2-lPa-23amiP.3-226

Actiniual SerieSl'a-l3IAc-227Th-227PRa-223

Fissol vProductsSr.90TC.99Cs-I 34CS-137?n'-147rCu-154

Duse Totals

504014202400

1330O

1230

1.00-02IS30

7.7 0-0 I

I30005530O57.7

5750

3240

69.3

36.21.71+00

3-SE-012.20.-C

730.03173

5200

67201 2094.S

31.3

5.4329.1

9.44.3E.01

52.6

.

3.91 E-06 I.2$0.l03.72E-06 1.1911-10

.400-04 2.3 7 10-O S

430110.07 1.60012)1

2.9 : O .970- Oi7

..79C-00 3.93C-039.190.04 2.940'-034.M3-02 v.45E-06

1.2 2-04

2030.-02 3.4610-76.94rj-04 .122270.I.32C0 CI 3t.34E.06

6.2 1 .06

SJOE-03 3.700-07'E.E03 2.450-07

1.69E-07

2.001:-OS4.26r-Os

7.710-02

qS: :'5 0

LO.SE-041.120-067.940-02

1730C-031.24E-443371-043

2.19E0-03

9.73r4412190-03

m!6E-062.05E-03i.OSE-035.09E-GS5.32-06

2.000-07

7.2704t7.27E-493t4-019.24E-015250-01

2.9s£-01

3.31 E-04122E-01

6.10E45

7.69E-041239E0-41360C44137E44

3.4S-041.75E44Ii9C-04

4.360-042.0 E-Os

1.53C-OS

2.33E-03

2.33E-052.99E-OS2.96E45O1.6SE4-5933C-6

I.06C-03 3.43E-104.0l0.06 2.91E-101.9s5-09 JA7-07

2.46E-44.46C0094.35.0-094.35E-Ot

1.10C0-Ox

5.60E-096.040-09I.55E-0S6.42E-104.39C-10

2230-043.000-05527E-07

4.14E-07

3.5IE-07307E4-1.76E-07i.46E-073.05-E102.57E-03

S 2E-02

_

NSi,: TVA frojw t lIA Rid Souacc Tcam & EfllusamsakSscet WrVwAifJ. .. o.

Estirnate.of Additional Radioactive Gaseous Effluents from the WWTFThe NVVTFIs ndaoactive gaseous eCuents *it ctumltly uannbititated.

AnnuhI PrnccodnaEsliesal' s-ado liiBlne a~ml1I1I UAS Alloy Iutpts

HEU U Mettt Buttons

Clustic Discharge 14.737 *L/O.* * . _(Based onZ 0.71% HE UAI loss)

Condensate fiom, SX: 153347 LJye(Based on a 0.005% HE UAI loss)

Cumnmtultive ARF .2.032E-03,

Cummladtive A(F: 3.200E-05

Cumniulabi ve ARF: 3.20OOE45Rtfnate from SX 11305 LJyr(Bosed on a 0.0004% 1E UAI loss)

ScrubberSolution . 597 I2 *.CunurrvuveARF:. 32001E45_(B esed on a 0.0035% HE (Medl & UAI) loss)

*tma(1aed. 3~ue., .: l * : UsiDose Wstnn t{i"td iiuib

Coostseol Factor- PIoctssed . E£Me Ns TEot(MeeMICI) (CVyr) (Cl' 7 , (ntr t'r.)

U-232L 7233

.-23.1

('-23(5U'ItTh.2t2

t11 2tllou

11a23!Th-234

ru -. sPJ-239 2J0PU-Z41Pa.Sub~tatl

An-24 INp-237

Therfun StriesRS-"31

Ac-228

pb-212fli-21211-203

Iran lsi Series

Ps-234mrRa-226

AeolumalnSeriesPa-231Ac-2l7Th-227Ra-223

Fission PraducesSr-v0

Cs-134Cs-137Co-l54Eu-l 5s

Dose Tgstal

504014203400

I.02

.73-41

sothl555057.7

.SiE-t35 531E3497.J51-05 239E-409,JA1E-0 J.73t.E7

2.242:44 7.171:-0)j. 3~I:-o. l.ttS13o1I Ol l -OS 3.21E-10

S.951.47

I.-'.l:.o6 5.631-1 12.24: 1.4 7.1 7134Y,.35I!-OS 7.3613.I!

36JE46 1.16E1-09.741-09

F.5,13.07 IVA5:- I I$.S71:4. 1.75'.-12t.561.05 J 69fi-10

J.:tl.-O I7UI . It,.l(.13-7 1.971:-1 1

1.277103.

33913.066.6S1-04N9.5313.46

9.021-:07I.J T:44

1.501.07

73330.3tI3.6513-09

3.613i ttJ

6.313-O:ta

I 39C-07

7. )13.O' 1

2.70E45O3.7613-tt7

7.5JE4SI .oJE407

1.6513-122.6313-03

4.67E-101.61E-II

69.3&.2E-01

36.21.7134003.SE-012.1E-02

7349E.0S7.J7451-

7.42C4S04.22E4S5239£4.5

I.M713-11.17C13

2.4013492.37E-0913E-097.65E-10

3j13-02 I 2.65E-5s7JE-03 I.LolE405

1 7 4.59JE-09

SA 1E-IJ 2.7SE1.43722 I10 2.341E141.5711-3 2.79E- I

52006720120

94.5

31.35.4529.19.4

4.36-0252.3

6.17C43I .12E431.09E503

2.77E-0

1.4013-OSI.521E45

3.904-OSI.613Ot0I.2JIE409

1.9SE1-22

3.55E-I33.49E1333.52E-13

SS5E -134.49C13.4.S5E1IJI SE1-I!

5.15E-14

3.9313.214

I.03C43S2.4JO-094.19EII I3.32E-I I

2.32E-1 I2.46E-I2IAIC11-2

I.17E-1 I2.45E-14

2.07E-12

S.45E4J

Fik-: WA P.ojic (ISA Rid Souice TernmsA &11unts).XISSheet: W %VTFAk CfrYItJ0

* Calcutlation of Airborne Release Fractions (ARFs). for the WWTF Processes

ProcesslogotCaustic Discharge

-; ' *.:.*.: .. i.^-*,_ fl s v

:'Step . RARFnce

Transrer to Wastewater Storage Tank LOOE-05 (DOE-I 11)13K-3010-94 Table 3-6. 1000 ml UN] I spills from 3 m high)Transfer to WRT 1.001OOE5 (DOE-HDBK-3010-94.Tablc 3-6, 1000 ml UNII spills from 3 m high)Mixing WRT 1.001-06 (DOE-IIDUK-3010-94.Tabkc 3-6. 1000 ml UNII spills from I in high)Mixing WRT (retreatment) L.OOE-06 (DOE-HDBK-3010-94, Table 3-6, 1000 ml UNH spills irom I in high)Ammonia Stripper 2.OOE403 (DOE-IIDBK.3010-94, Section 3.2.1.3. p. 3-1S. boundinp value)Tansfer to Neutralization Tank l.OOE-OS (DOE-iDBK-3010-94, Table 3-6. 1000 ml UNH spills from 3 in hiigl)

Cumulative ARF: 2.03E-03

Processing of Condensate front Sohl ent Extraction (SX)

Step ARF Reference

Ir'itsfertaWatte aierStorage to kI tl0l3t)5 (1)0 3.lll)l1D.Z-31)0-94. Table 3-0. 60W fil I I spill' froril.i in igisIranstfu ru VRT 1 lt13 (lX)l.l lo WRTK- tl014. *rahk 3-4,. 1o00i0l I Nllspi lls oli fi flhight

xlixiicin, w1.r 001* -lx)l.IKll)ll;Z-310-94. Table 3-6. I100 nil I I spilsk tli in I lt highstM4ixingj WRT (retreanweiui II.00 1)' tlX)l.*lIl)llK-Nt)It(-94. Ithble 34i. 10011 evil U NII qiall fi.un I In Ilighllraiiitkr ti, N-u iral,4ttn *lank l.t*3X)l41) OX)IM-llI 11 -3tI1l0-94. TahL 3-6'. IIXX) ml I Nl ,r::'1;i. .f ig ht

<Cumul ative ARF:- 3. 01.4tz

Processilng a( Raffinate front Soltvnt Extraction (SX)

Step ARF Referefice

Transfer to Wastewater StiragerTan' l.ID40 (DOE-I ID13BK-'10-94. Table 3-6. I100 ml U'NII spills from 3 in highl)TransIcr to WRT I.lOE-05 (DOE-ID)l3tK-3010-94, Table 3-6. 1000 nil UNI I spills from 3 mo high)Mixing WRT 1.001-06 (DOE-IIDUIK-3010-94.7Table 3-6. 1000 ml UNI I spills from I m high)Mixing WRT (rctreatmcnt) 1.001:-06 (DOE-IIDBK-3010-94.Table 3-6. 1000 ml tNII spills from I in high)

Transfcr to NeutralizationTank 1.0012-05 (DOE-IIDB1K.3010-94. Tabl 3-6. 1000 ml UNII spills from 3 n high)

CumulatIve ARF: 3.20E-0

Processing of Scrubber Solutlons

Step ARfI Reference

Transfer to Wasmcwawer Storage Tank I.OOE4-0 (DOE-I IDDK-301D-94. Table 3-6. 1000 nil UXNII spills from 3 m high)Transfer ao WRT l.OOE-05 (DOEl-IIDDK-3010-94. Table 3-6. 1000 nil UNII spills from3 In high)Mixing %VRT I.OOE-06 (DOlE-1 IDBk-30 10-94. Table 3-6. 1000 ml l)NI I spills From I in high)

Mixing WRT(retreatmcne) 1.001-06 (DOE-I ID13K-3010-94. Table 3-6. 1000 ml UNII spills from I m high)Transfer to Neutralization Tank .00E405 (DOL-lI l)DK-30l10-94, Table 3-6. 1000 iml UNI I spills from 3 to highl)

CuowalativC ARF: 3.20E;-0j

Fik: TVA Project (ISA Rad Soirac Terms & Efilucnts).xsSheet: WWI IARMs311/02

Attachment E* . .BLEU Complex Radioactive Gaseous Effluents

.I ..

Caliulation ofiUnit Dose Factors.- BLEU. Complex Gaseous Effluents

Unit dose factors for the gaseous effluents from the BLEU Complex were calculated for I Ci/yrreleases of each radionuclide using the CAPA8-PC Version 2.0 atmospheric dispersion and doseassessment computer model. These factors, in units of mrem/Ci of radionuclide released, wereused to estimate thie otenitial atinualAQse to the maximally exposed individtual (Ml')attributableto the facility's radioactive gaseous effluents.

CAP88-PC Version 2:0 Input Data:

The meteorological data used for the calculations was obtained from. the NFS' 1996Environmental Report. The wind data file that was created using the referenced meteorologicaldata has been named NFS5Y.WND. The referenced meteorological data also included: 1) anannual average precipitation of 103.4 cm, 2) an annual average ambient temperature. of 13 0C,and 3) an 800 m lid height.

The "rural" selection was chosen for the EPA Food Sourcc Scenario, using all of the defiultparameters associated with this selection. Dose calculations Were performed for the followingdistances: 150, 200, 250, 300, 350, 400, 450, 500, 550, 600, 650, 700, 750, 800, 850, 900,950,1000. 1500. and 2000 meters. All particle sizes wvere assuncd to be I Stm AMAD. The defaultsolubility classes were used in all cases except for the following radionuclides, which havesolubility classes that are dictated by NFS Procedure NFS-HS-A-27 (NFS, 1999).

Th-230 and Th-232 Class WPlutonium IsotopesClass WTc-99 Class W

The radioactive gaseous effluents from the BLEU Complex will be released via three proposedstacks. A single set of unit dose factors was developed for use with each of the three stacks bycalculating weighted averages for each of their physical characteristics, because the mostsignificant physical characteristics (i.e. stack height and exit velocity) were relatively equal. Theestimated uranium releases for each stack were used for the calculation of the weighted averages.The average physical stack height is 15.99 mn, the average stack diameter is 0.656 m, the pJlule

rise is momentum dominated, and the average exit velocity is 9.40 m/s.


File: TVA Project (ISA Rad Source Terms & Effluents).xls

3/1/02 Sheet: BLEU Stacks

* .' Estimate of the Aiuual Radioactive Gaseous Effluents from the BLEU Coml)lexAnnual Prat lo~Iln- Estimsft. Ilis3aedn twr FrstimeANr. 222PA Vlbtmt IIntjlum Itele,;e Essima2* .

ur3.)I Ngrasr Stroige P.afir~ig (UNWO) 1 70C-01 miv Uty2.0311-02 3 Ulyr

Oxide Contmion~ Fxicay (0C1): 2.24E*01 .Ci tv4i2.6SE400 SUly

Effluevi. Promtsuig Buildir (EPB): S.OOE-02 *wCs Ulyr,S.9Ct03 g Ufyr

LE UN Specific Actiniy. SS$E-6 cirg

Total Uranium Eni~ssioeu 2.27E401. mC a U2~j,. . . . . - 2Jo+o z tUy

'**4*I.. Sunmmary oEMiitman ldcAiwS.C ---.~~LEU.Complex Emiss~oas .

U.232U-233

(1.235U1-236U1-23S

Th-22S

Th.231

Th.2.!4

Th Subtota

Pu.2J41tw Smb.W.Cu

Am.241

P1.222N

Oi-212

Uraniu.m Setlcs

Pa-234m

Ra.226

Aamlnum SeriesPa.231Ae.227TI..237

k1uslon ProductsSe.90Tc.99Cs1134Cs-IS?lim-Ill

Eu-I 3.4

DoseToials

1270360

33833,317

6.29

2

2 141C.411

I 27-1

14 7

I-ICA

4312.-01II 6217.0243 471!.03

3,27E404 1.332-OS3.112.0.3 - 13-026.502+06 1.7612-05I1012403 2 91 -071.402*06 3 791E-063.122203 3 432-07

3 122*04 S OV2-0733E2.0: I QO$!.00)

If72l $M.11

1 7711.02 W3 702.1256r.'0 (.032.20

24311i01 O-SM1.12.43.02.33 0372.223122*-J4 X 43r;-tj3s 0'1W.0.3 1 3$12.03* W-C~-04 S 7.34131

00203 26092! .0

1.12E-043.02E.056.252E039.2132-0I 212E-032 (.72.043.04-03

5.2724C35

IJO. II2.2

1 5203:4

2MJE-13

IC 33CI.l13

9 17E17

2 J64!.08

.3 791E-1S

2 &3E.I 1

I 202.20

2 502.232 0332.23

2 J42-02

532SE-03 OI 9)E-01 292.2,.l2t-O4 4.29C*03 132-os

*tS J2042.00 5.22

1320170030224 2

931 672.41

2Is1 23702

14 7

217E*01 69SE II4 66E400 12262.114 533*OD I 23t-I I45 124O 0 2242.22

1.15ECOI II 1E.I I

251 -co I 5222.220.3120O 1 71E.IIt.62E0 4 MtElE670E-01 1 2IC.2S.2IE-01 I 3 2.122

rk1 IVA P~ojcd (ISA Il SortcTenes Mcm,),xus

ShM RM EWAjir

Estimate of the Annual Radioactive Gaseous Effluents from the BLEU ComplexAaauS3 roe in. Eslmr - Bsed et FransioneANri 1367A Fliwered UrOOlnqm Itelevse E1:IMn,1es

* Ursylnse SuO~gE 3u (U7l): 31.70E.01 ;Ci UYlr206E.02 g Uyr

OxnecCqowiioonFaaiky[OCF):, 2.24E401 eCaUUYr2.6SE+00 . z User

Eluent Procasng Building (EB): S.00--02 ta Uyr5.96E.03 g Ulyr

LE UN Specific Activt 8.19-06 CVgt. .

.7;ota Uranium Eniissons: * 2.27E+0o UO UIyr270E+oO . Ul>r-

* CAP83.?C ;.Esfinatled UND Cous fueals

A IU-232 1270 3 27E404 6.63E-10 t.42E-07

Vi-i 360 3.IIE+04 6196-30 2174E07W3.4 J36 4650E+06 132E607 4.69E.05W.235 338 . .1.086+05 2.121-09 7.31E07.

U-236 337 1.40C606 2 84E.0O 9.59E-06U-238 317 33l21.0 632E609 2 OOE6V Subtota 1.70E.07 4.036-5

Th-22S c4-a 3 1:1-04 63 C.19 J 36.nTh-230 so, 7.33o-02 11.491-l I O 50.03Th-231 2 941:-03 9 !tW-.O 3 99C.4-. .390-I:Th.-23 .'2 3 f.1-0I 62 W-I' 57SI.3f

Tb :3J "-I14l1 I IE-I! 307" *" 6441. 12TI S0,.1n1al 2.57C.V9 4.8.2307

Pu- ' 127P) .I~tl-o 7.43E.t. 9.')C.r7N- J.) 3:I*nl .76.13) 43it-.) l

ru-:4I 14 7 C 1.11--O 1 2C.lt I S:1409I'd S!al1u.II I tl E.30 l.ISE.114s

AmrN-l1 J 1 7M-02 3 5I1.31 5246.0

Np-237 3). :.<hEO: 5:201.1: 691E469

17 orium ScriesIb-229 2 4 : tlE01 .J931.13 956.I2Ac-2 s:-Iti 24311-01 J93E.13 1.097.13R3- J 91I 3 12o04 6 32C.1l S 76o-09

Pb-212 S 311:.2 3 09E04 6 26.10 Z70E.1011-212 S 62143 766-04 31561.10 307E-IITl-2 4 4J71A.I 99t1-13 - 026.3'3 90:E.13

ra.nl.w SerksP3-234 S.'S.03 I IIE301 24E-l It21E-15pa-234n I3IS145 .19E603 &49E.-I 1 OOE-I5Ra-226 4 5 20JE-OJ 4.131-l4 J OOC-12

Actinlum SctlisPa-231 132') 257E+01 5.21E-.3 6St6-10Ac-227 17tM) A666400 944S1.4 1460E-10Th-227 302 453E+00 9.22E-I. 2 735-12

a3-223. 242 456.M 00 9.2SE-14 225E6-

rIsMoa Produ osSr-90 9 3t I15E-01 2 34E-13 276E-32Tc.99 1.67 5853600 1.19E1-3 19SE-13Cs1334 t41 6.33I00 1.25E-. 1OSE12Cs-137 95 I626.03 3.29E-11 9.37E.13Prn.147 1.23E-0O 6W70E-01 1-36.11 1 67E-15

u.l54 14.7 S3IIE-0I 04C6.3 1 52E-13

DOM Tatals 6.0tE.OS

F'ic TVA Pratt (ISA Red Source Tc-m & ERfimas}) ISShea: OLEU Air 60

Estimate of theAnoual Radioactive Gaseous Effluents from the BLEU Complex. . . . .. . . .

Uranyl Nirare Storage OuBdting (ONO)' I.?OE701 sCi Ulyr2.03C-02 UyT '

Oxidc Conftnion acilgiy (OCF): 2.424040 uCI U)yr2.68E+00 gUlyT

EtM. Procuing Buing (EPB) 5.00E-02 ud UI/y5.96F,03 g Uyr

EL UN Spcir. Aivuy * &.390-0 Cifs

Total Uranium Emissionn: 227E+01 uCi Usr2.70+00 g Uyr

cAn-ic .Eslnuated OCF Gewous Emtr RtsUslit it Z.

U232 1270 3.27E+04, .78-08 t.llE-4*U.233 . 360 3,1.EO4 3.32E.0 299E-O5

U1-234 3* 6 6.50E806 1.74045 6t96r03u -235 333 . I.0t+0s 23SE-07 9.74E-5U-236 337 I A4E406 3 75E-06 1.27i-03U.231 317 312E+80 a 35E.7 2.6SE-04U Subot3i 2.24r.4s 7.9E-03

ThS h649 112E-04 S13-.0 542'405Th-340 SOl 7 33r-02 I 960E49 I SC80r :!931 : (W '-71.1 e I 5.0E47 b J7E. I0Th-2123 07L-o1 S ::E2-I I 7 r!£4S

127.' 4' 618*. 401:I.44 S 317.I6

i'...2%a:" 0.1 C 5 42-0 621.11% 1230R.41 44 h SI:,Ot t 211_19 D7 6 MAE4

Pa.41 11 _ I. 198.nl3 1 63047S 3.& it.u?7.. 3abg,,jl 1.7.3)4X 9.51846

A.211 lt 1..) 1 77E-02 A 1JE.IU 6K928.47.%.zt7 tl!O 2 (.02 hS660.0 l 9I -07

TbhrI.. SkhRj-22: Dl4 24 : .0: a E otC- II I 260E-'Ac.32: :1.01:: 2JIE-Ut o5.0C-II 64C-ti

I I J 911 3 12E804 S 355ot 7 01 E47PtL.21 4 'II.Eu 3I !r. 04 s :6E1 A 35E0.0o

6M- 1: S 2:2 1 76bE OJ 470E-cS 4 050.01: 427J.03 C496C.0 2 66h.0OS 19I -aID

tn..Iu,,,. Str.raPa.2J4 £8Ist 4 It1E-01 2968.66 2488-ISF-23Jm I ISE4-S J 39C*03 12E4-S I 932-IR3.236 48J5 :048'OU 5.4sJ-12 265E-10

Alnt..m Senpa-2l1 9320 2 57E401 698C1-I 90 E8OtAc-227 1700 4668*00 1.25E2-11 2.12£-4Th-227 30:2 4 SS400 1.22E-11 367?E-10R3-2253 2 4 5£400 123rI0t 296E-10

81;o.. Froducts53-90 9 I 2580 I 3 08C-.1 237C.10Tc-99 167 3853.00 I 56C-I1 2631E-1Cs-134 8 4J 6 318E00 1.69E-II 14 JE-O0Cs.17 2:2 163.01 4 342-11 1248.10Pnm-147

123I.01 670b-o0 179E-12 22IE-13£a-154 14 1 511E01 1 37E-12 201£.11

Dose Totl% S E-03

F'ke TVA Projcct(ISA R Sowww A EA41.

Sfi BIWAkfr

.E

Estimate of the Annual Radioactive Gascous Effduenti from the BLEU Complex.Annaal TM ro 'Cstmn, stl t- .tlased en Fr,,prolne-ANP, l tIEA r t. Us'mn n ttekbe Folltatet.

UrabnylWrte§ae Su~dlng (UNO) 1.7011-01 wnC. U/yr.2.03E-02 S L3Y)-

oi&dcCo."aio ramnly (OCV) 2.24E01 . vad Wyr* 2.686.00 g 8Uty

EftMoart roceig Building (EPD): 5.00E-02 dCe U/yr

5.%E6-03 . L~yr

* LE UN Specific Acaivwy . 39E-06 CifS

TOWa UrwniuM Emhscomr: 2.27E401 maCe Uyr2.706+00 ZJJ6-r

CAr* -PC Estil`na(eiEr'B C2SCOUti Em. Ids*. 'r4M U~iN . Midgald rst"Nated

,. ts .gw'.,,,T.DE

U-232 2270 3.27E+04 1.95E-10 2.4SE47U-233 360 3.14E+04 I15E-10 6.166E1U-234 356 6.50E+06 3.136-CS 13605U-235 313 1.08t+o5 6.42E-10 2.1t7E0U-236 337 t 406+06 3.372-09 2.t2E46U-2M1 317 3 I2E+05 I S6E-09 5.90E47USubtoill S.O0E.0S 1.77C675

nh6223 -4 t 1:1-04 I S6L-10 2 1E-07Th-2.50 s07 73S6o0 J 37-22t 3 531-09Ti-2321 2Drr.-03 eI.EOj 5$%E.21 2 446.22Th-2*.2 9 s q-ol l2. C. It 1701:-0rb.234 2 2rC2-u 1$ I:-05 9 'tI.22:2T Subtotal 7.4661-8 t .1,417

Pa-23S 1270 361E02 2O I -.2 27J4q-0pu-23:9:J) 2120 : 32E6l I 3sE-II 1 051:-10r4-241 IJ 7 iOg:.,it 3 61-.1 5 I-IO0ria Subtotal 3.12 3.47E-09

Arm t t4l-t 1 77L-e2 I no-E2 I 54sJ0o2l MU') : <%61-o I 'J-I2 205 Cs4

Tbociowt ScricIta-228 194 : 02 2O IJl.lI 2'12.I2Ac-22: 2S:21:.01 2.A3:01 1 41- 13 22C.24Ra."J 911 32126-04 I toE-lo I 69-c09pb-212 8321.:t 3 0c-04 1 $414.0o 794E.2IBli-212 o 1622: I 70E-04 I OM'6-: 90022.I2

9l0ER 44760 949o6-03 SEs-lr. 2656.13

tsazlun. S.ksPa-234 *383603 IIE201 2 5-5I.24 S.32E-16Pa-234n 2 ISE.05 A 19EJ03 2.50.11 295E-l6Ra-216 41S 204Eo00 12.2E-I4 5 99213

Aadnl.. S easPs-231 13'0 257.+01 1.53E-I3 2.02E-10Ac-227 1 2700 J66E.00 2.7E6-14 4.72-E.1Th-227 10.2 4556o00 2.71E-24 2.t9C-13g.22). 2422 A 5SE-00 2.73r-24 6.61E.23

linlo, ProducsSr.-90 9.3 5.0SEIOI 6S7X-4 63916-23Tc-99 1 67 568C.00 3491'.4 5.12E24CS-134 414 632C600 3U76-14 3216613Cs-137 2 ss 1 62E-01 9 76-14 2.76E6.3P.+l247 1 2i12-0 6 706-.0 4JE-125 4.J9!E16Eu-15t 2J 7 51 IEO16 3.036-15 4 43J.14

Po.s Totak I.t'tE.S

VIN11r~il TVA Proj..-cr(ISA Rad S ac e T anus& 6t~uems2.xk

Sh~cet h3LEU Air Ef

From: Napier; Jimaiy D.Sent: Monday, October 22, 2001 6:24 pMTo:, 'Holman, Charlie'Cc: 'Urza, NAk'; Koppel, Pat L.Subject: RE: Emission Estimates

Charlie. (and others)Based on our conversation Monday afternoon, the units reported for the activity should be in uCi(not mCi):Just confirming and keeping everyone updated.

Jim NapierEnvironmental ScientistNuclear Fuel Services, Inc1205 Banner Hill RoadErwin; TN 37650

(423)743-9141, ext 1202idnapierfinaxs.net

-Original Message-From: ,Sent: Friday, October 19, 2001 6:04 PMTo: Napier, Jimmy D.Cc: Urza, Nak; Koppel, Pat L.Subject: Emission Estimates

Jim,As we discussed, here is the estimate for air emissions from the BLEU Complex. Note that tpy isin metric tons.Stack H2 NOx NH3 Acty

OM~y Opy) (tpy) c;i U)UNB 0 024 0 0.17OCB 2.1 17.6 0.25 22.44EPB .._ .. 0 ..0.4A .005 .

Total 2.1 18 0.69 23- ->

Give me a call if you have any questions.Charlie HolmanFramatome ANP, Inc.509-375-049charlie holmana)nfuel.com

Attachment F

Historical Radioactive Gaseous Effluent Data and Compiled Data

A g n a s EAkverage Annual Radioactive Gaseous Effluents

*J 2.ge Reieais's 6) $''v-si Pr: F . ?

Element i; * 17. **s , 4 2. .2 ...LJ ,(cz- ,.') (Cll. (Co)' (CUy) -

Uranium 5.E-05 1.OE-04 7.5C2-04 2.61-04 2.1 E04 ME-04 27S.41Thorium 7.9E-07 6.32-07 1.6E-06 IAE-07 2.14-09 6.3E-O7 0.63Plutonium O.OC+00 O.OE+00 0.0I+00 0.OE+00 0.024+00 O.OE+00 0.00Americium 0.02+00 0.0E+00 0.0E+O0 O.OE+00 0.02+00 O.OE+00 0.00

.

Release data obtained from the Safety Departmentws Semiannual Reports.

Average Releases (1996-2000) - Remaining Slacks

Element 1996 1997 1998 1999 2000 Average(Cf) (Ci) (CO (). (CI) (CiA.'! (u)ii)

I ran.um 5 2.')I-U3 2.51- 5 4.21-i4I 3.11. 31.22Thuriuni 2.11'417 !.71-oi. .61-4I I.(1 -4J ').214". *.21.41)t _1

I'liwoniun 7.21 '4t7 A!J1.-t)( 3.4A ltt6 1.11 -(14 1.21 .t4) 4.2.1l4)} 46 S3Americium 7.61.4)OS 5.31: 07 5-311-tl7 I .9E*UJ6 1.61.41 ').41 4) 0.94

ReIcasc data obtained from thc Sarcty Dcpacrtnt's Scmiannual Rcpons.

Filc: TVA Project (ISA Rad Source Terms & Efluccnts).xisSheet: NiS Air Lff314/02

Attachment GBLEU Preparation Facility (BPF) Radioactive Liquid Effluents

Liquid effluents generated from the BPF vwil be sent to the:Wastewater Treatment Facility*.(WWTF) for treatment prior to being discharged to the Nolichucky River. Offsite dosesattributable to liquid effluents were calculated in accordance with NFS Procedure NFS-HS-A-66(NFS, 2001c).

* Minimum Removal Factor Calculations:

The spreadsheet specifies "Minimum Removal Factors" for the WWTF, which are the minimumfractions that the WWTF needs to reduce the radionuclide content to comply with the dischargel limits specified in SOP 299. Minimum removal factors were specified for the most significantdose contributing radionuclides, because treatment factors for the WWTF were not available.The discharge limits of SOP 299 are based on the concentrations specified in 10 CFR Part 20,Appendix B, Table 2, Column 2. The annual average concentrations were calculated for each ofthe discard streams by dividing the annual radionuclide quantity released by the annual volumeof the discard stream. The minimum removal factors were calculated by dividing the applicableAppendix B concentration by the annual average concentration. Details on the calculation of theminimum removal factors can be found in Table G-1.

Unit Dose Factor Calculations:

Unit dose factors wvere calculated for the liquid eftiucuts using the NFS tcchnical basis documenttitled Dose Faclors & Action Levelsfor WS14'TF Rmlioactive Liqui(l E:lutents (NFS, 2001 b). Thisdocuminent provides the basis for the unit dose factors and provides unit dose factors for a limitedlist of radionuclides. Unit dose factors for additional radionuclides wverc needed for thesecalculations, and wvere calculated in accordance with tile methods prescribed by the technicalbasis document. A summary of the unit dose factor calculations has been included in tlls hack ofthis attachment.

Table G-1

Calcul'ion of Minimum Removal Factors for the;5

- Caustle Dlfcharge - Condensate from SX Ralnate from SX

Untreated Minimum Untreated Minimum Untreated Minimum*-Alpha `.. Alpha Alpha Removal Alpha Removal Alpha Removal

Material Limit Cone. . Factor Conc. Factor Conc. raetor"..,

(pC/Lj. (pCI/L) : . *. Needed (pCIVL) Needed (pCI/L) . Needed

UraniumTh-228Th-232PlutoniumRa-224

3002003020200

125,539SOS0.56

505

0.00240.39571.00001.00000.3957

75.6183040.34

304

0.00400.65691.00001.00000.6569

82,058S2,580.092

81,3351.017,935

82,SS3,092

0.00372.42E-060.00041.96E-052.42E-06

.4 .4. 1 .4. .3..

Note: The alpha limits are procedural discharge limits for the WWTF. The W\VWTF can not dischargc batchcs cxcecding these limits, without the Environmental SafetyManager's approval to do a dose based release per NRC License SNM- 124. Thc removal factors for the rarrniatc were disregarded because they were unrealisticand thatdischarges of treated raMnate can not only be released when they cxceed the alpha limits without mIanwagIlniLet approval. The WWTF has nearly the same removal efficiencyfor uranium and thorium. As a result, the uranium removal factor was used (or thoriutm. Thc Ra-224 removal factor was rounded to 0.4000.

File: TVA Project (ISA Rad Source Terms & Emuents).NskShect: WWTr'lirs3/4/02

* .Estimate 6f the.Annual Radioactive- Liquid Efflicnts from the IBPF

All lqigud eflllyents are disciarsda a. te B Pr to lb. Nalichucky R~I~r iiat he %V%IT

332 UAI.Al loyhssotsin Co.t~ Mcsartic.

-H U Metal Buttons: d*M" Basd oni a 0.03% HE UAM loss)Iy -11A I" A

PA&INC " SXE' mEn'Based on a 0.0057. HE UAl bss)

Based on a 0.0004% HE UAS bs)SacruberSoluion 93LR 1J

_ascd on a 0.0035% 3 IC (ctal & UIA) blssl

.Wf. s NNCRP-123 : Sunmuna et Estimated DFLlquid EMtients

- VD ~ ~~Taeted "lshse *

U.232 0.0024 58 229E.04 5.50-07 0.0000% 319E45 0.0013%U -233 0.0O24 2.1 2.1S1E04 s.22E.47 o.0000% 1.10.-06 0.0000%

U-234 0J14 2 4.34E2 1.04E204 0.0042% 2.02E404 0.0O05%U-235 0.4 2 9.5 6.54E44 1 57E06 0.0001% 1.49E4.5 0.0006%U-236 00024 1.9 9.84J-03 2362E5 0 .00010% 4.49E405 00018%U-133 0 024 4. 2 93E.05 7049.00 00000% 3.10O-07 00000%t Subtotal 43241 IJ3t-04 0.005 O3 3.0 1£4 0.0123%

Tb.:22 oka J IJ 9.UC4.o1 22JI:.01 00909% 3 IE-02 I 242.r.

Th0. 0O024 9 2 39E.02 4: S.0 00021% 4.74J.4 0094%lsTh.:l3 00.24 IOE.02 4 7:-3oo 6 7DEJI3 0 2717% 6 7DE405 0 Mr7.

Th- 'l' OC4. 2, *.0 4 *'IE-' 0a) CM 432-104 o00Q4

Th.:!J O.^24 3 21 .J4' J S1.4:02 130.04 (I6t1U 33 J41: 5 os t.m 1

Tb Sultotal 3.792:t00 9.3 32-03 3.3692% J.3-241O 3-Ol 1

ru-:M 1 .06 I MOO.0 4 002.1) * !N5' 3 Sll: 03 153134J._Pu. :o 43 g.94.. o .9J3: 4 *" Fs2-. 3 1): n IO!f -

Pu.2.3I Ii l 09: I Sllol. I (7J3*.133I . WlS.ru Subwt, I .94C43 1.714-01 7.$671i/ k.3 o0l t 2J.t4a4

Am.241 I W U0 .9 5.101.03 5.l30rl:n 11 2ln. 2r 0 413 3063-9 .

Np:-27 0000 sx 7072.-0 7671-33 OJII0 J 44S-41 IS IN75'.

Tharium S ric%R.::22Y 040"I 9$ 7 271:41 2:911.3 )Oils% 2 7r-.02 I 12%Ac '00A) 22'02 72711'u 7 27244 0 0o91% I.60C.05 0 0o7o.R.0 4 006 Z I .31413 3731:3-03 1534WM 7.94>41 32 05SIS%rPl: I12 3 00 I S4-01 9 2C3.01 3 2E-441 37 J77% I 3!.04 680-).tli212 1 o0W 7.1E4-03 S o141 5 E.01 21 3071% 3 731E.03 0 I"-

n-.os NW 343-05 :490.03 :2902.nl I: 0914% I01-os Coons-.

t'nmhaum-, Ser,;, 2JJ 3.0n0 sE402 333E.04 3332-04 00134% 5.95C06 0.0002e %

Pi-234m I O0m0 I.OE07 125E.01 1,25C.01 50795% I 252-0S 0.0000%Lt-226 o0100 I3o 610-E45 2444Es05 0000% 2.611103 0.1097%

Aelliua SeriesPa-231 10 00O 120 7.70E-04 7.70E44 003512 92J3E-2 3.7744%

Ac-227 I 0000 170 I 39C-04 t392-4M 00057%A 2372-02 0.96S4%n-227 0.0021 2 11 36-04 3.27E-07 00000% 6.53J-07 0.0000%

.R-223 04000 5 4 1 37E44 5 4SE4-05 00022 2.90E.04 00121%

Fission ProductsSr-90 I GM0 10 3 J5E04 45-04 00140A 3 4 5E-403 0 I4J10%:Tc.99 I ODO 1.7 1 7S04 I 75-C4J 0 0071% 2 9s5404 001221%Cs- UJ 1 o0(o 27 1 89E04 I E-04 0 0077% 5 oC-03 0 2.0NJ4

Cs-lJ7 10000 27 486C44 4A6-v04 00197% 1.33C-02 05360%_Pa-147 I 3o00 2 4C02 2 03E.S0 2 01 C-05 0 0008% 4 9127 OOotur.

u-154 I o0o0 10 153JE-03 353-05 0 0006%A 3.20141 00063%

Crand Totals 2.47C00 300.0000% 24SE+200 30.0000o%

Mr TVA Proec JSA La Souccromns AEflhweo) xs

Sheet WWrF Laq 2ff

estimate of the.Annual Radioactive Liquid Effluents from the BPF

Al liquid ifflueps ari*dscharied frona the SPI'to the Nolichuc1ky RJ er steshe IVTF

,8ng/st Pr~ocsIn- Estimates - Based on lA191Balance~~rfoHE UAt. Alloy Ingots: Caus'c Disharge- IS4.7 1.1

E U meta Bustos (Based on a 0.01% HEI)JAI loss)- ~Comee r.. sx -

* _ t sd on a 0.005% HE UAI I=)*Rafunte Gmon sx:-

(Basedon a 0.000% liE UMA lo)

* * * ~~ScrubbcrSolut~t5om ~ stased on a 0 0035% IIEC (Metal UAI) I=)

NCRIPl213. ,2t3l Disch arge .

Uok2*K',,rated kI Fissdm9id'

U.232 00024 5S 4.17E+05 9.73ECS 2.35E-07 1-36E-05U-233 0.0024 2.1 3.96E.OS 9.29-05 2.2tE-7 4.6E.07U1234 0.0024 2 7.39E207 t.SE4-02 4.44E45 S.J2SE4-5UI-235 0.0024 9.5 1.19=406 2.79C-04 670.E47 6.371-06U.236 00024 1 9 1.79E+07 4.204-03 I.0OE405 1.91E4-5U-23S 0.0024 .4 J 534E-04 12SE-05 3.01E-4 1.321-07U Subiotsl 2.J2-02 3.572- 1.29E-4

Th-2s5 0 524 IJ .3 Is o -0 9.3U4S-0 224: .07 3 14C-0Thn-2o 0004 95E-OS 19E-C S261:-09 .7JC-SThl-.1 0 002o 1 4 I E142 I IOE-0t 2.79E4. 6701.07 701.09Tl-23 Of. O J :: !9:E-t 92 0.0:4s 1:.1" 4 S61 .0Th.234 O,5)24 1.03 I 9t7'-t4 4 ttEJI- I2 Ol:" *JI4910Tt Subtl.et 3.79E-04 9.10I:.07 J.2JI:-t6

Pu-: tS 1 ,4. J 61E-. I 031.4k, I 01.1:4 fr)t.05i too) u 1 :l:r-.': 69415-03 #qA1.'- 2515.'u :JI Ai 2h.1'1 ? -S7-04 I1 4.v0 I S.'l5-u5 1 4lr-415

r.- SUbusald. 1.94r-os 1.9I:05 tr-tt

An.2.l1 I 'O1k) 44 2 ::m-E-OL 5.3v-07 5 331.407 : t01 1.$

Np-2:7 I 'Out) 5S 3 :7E-03 7.67E47 7 67E07 J 452E-5

Tt orlum SrrkiR1.2!6 s OJ's -'5 3 1t01-02 7271S.C 2.91E-0S 2:7(Er.OhAe-2-15 I 1-1P 3 2101:-0: 7.27E41S 727E4Sw I (43-R1.224 0400u :1 395E-05 9343-05 373E-45 7SJ4115-Pb-212 I (IVW 2I I1-0 304E-05 9 242.5 92405 IhfE (-14Sni-212 I 1NIO) 7 I C4-. 2 :4J-05 526E-03 5 261.-0 3 73.t-07Tl-2)S I kit), 3!tJl:.-(3 27E.05 2 9SE-O 9XE-05 01olE4709

t1rslraian SeriesP3.234 I oW£.3 I sE402 1.41 3-02 3.31E-5S 3.3E12-S 5.95E-10Pa-23.nt I10000 W oo-I 7 .3-25.4E- 1.25E-4S 1.25S-0S 1.25E-12Ra-226 0.4000 110 2.60E.01 6 2OE409 2.44C49 2 632.07

Acliilual St'mespa-231 1.0000 120 3.23E.0 7.69E-05 7.69E-04 923206Ac-227 I.0000 17u 594E201 1.39oS 139E.03 2.37E4-<Tb-227 0.0024 2 50SE202 OI 362E 3272-11 6.532-1I.Ra-223 0.4000 54 5.34UE01 IJ7E4S 5 4S.49 2.96E-03

Fissu- lFroducisSt-90 2o0a0 In I 47E-02 3 456-05 3.45E-4 3.454-07Tc-99 I (NW 127 7 462401 1.7SE40S 1.75E4.03 2.98E-08Cs-134 I20000 27 1025E0I 2.S972-0S 1.S9E-0S 5.10C-07Cs-137 I wisxJ 27 207E202 4S6E-OS 41614-0 1.31E-06Prnul47 IlI0O 2J402 3.552+00 201C09 201E409 4SIE-IIEu-154 I (tW It' 62.00 E I 530E49 I33209 I 53E40S

D.%tToials 3.731E-O

Fik- TVA Prvj~-t (ISA KA8 Source Tmms & Ufluents) xl.Shcet WWTV-F Liq EffJIP

Estimate-of the Annual Radioactive Liquid Effluents from tire BIIFal Aqulid qudMJts are disesrged rot the R 0 r othe Nollchucky Iluv. it the w'X1 T

Annualsl Pfoeenil- Esllrn-sltu UAl, Ally Ingou:

* Ile U Wil Butious:

Based an 11AgIt-bse tIhnform laonato,

Oauslk Dirdge: 3SA737 .

wd on a 0.01% lE UAI Ios)Cosmicw fromnSX: .< 37 w^

llWd e a 0.005% 11C CAI lou)RWfww Som S%:

Rlw imXnd a 0.0004% 190 UAI kw)

SUw Solulion 40a_§lasb on a 0 00357% Oft (Nkull & UAI) IDSS)

.V " 1s, NCRPt-1u3 ... Con ienste from Solvent Extracdioti (SX) ..

*1ta$i .4t~ . . ~ c .'Av

U.232 0.0024 53 4.17E+0S 4.t9E.45 I.7E47 6.SIE-C0U-233 o.0024 2.1 * 35.9E05 4.65E-05 I.tE-07 73411-07U-234 0.0024 2 7.39E+07 9.25E-03 2.22E45 . 4A.4EoSu-23s 0.0024 9.5 1.19E006 1.40E-04 335E07 3.11EoCGU-236 0.0024 1.9 1.79E+07 2 IOE-03 5.04E-06 9.571;'05U-25s 00024 4.4 5.3JE*04 6 26£-06 I.5OE4OS 6.61E.OStISubltotal 1.16E42 2.71EA45 ¢43F C.,

Th.-s22t 00s24 14 3351.s05 A6710 n I IE-07 t 57r-M-Th.-23a 0002. o 43'05 I 1101o:00 263Es.09 2 375 s

h.!1n 00o!4 1 1 O5-0 I -Ot.0 1 400.04 3 )3S.107 3315.0')I:'0 t 221 ) .' 4 -az 4 C-11t:5.0 I 101! 10 :n9

Th-23.J 1411:4 .12.41 1 71:-OJ 2-l Ca 21 5 .0' 37JLYilI .. uI .1.W14.J 4.51,t7 1.3:-11.,

I (A sln. 4 M 1:@0. 5 4g11- 7 413:40 1 )*1 gr t-o:3 I2 *I :t)C 4J1St 3 J71:-1 1>:1:4'1I-: I I 43 7 7S: .oJ 9 I:.'. 9 I X.-tet. s ME -ru S.1-wl 9.701:46o 9.7"lr4 2t.49.1,01

C.".: 3 Ioo u 2oE.l03 2 6W5.07 26SE-07 1 l.05Np237 I 500 54 3 27E-03 3 S4JE.07 . 84J007 2 21:40S

Tbh-iow. Svre%0.) 0U)0 4S t 1o0- A .WICl0S 1 JS5E0t 1 3510

AI-223 10000 21'402 3 I30502 364 1-4S 364J4t K.6905.3,la-: 4 n 4000 2 1 3 ssE5OS 4 67C-.0 I S:7E4S 3 9X1>135Pb.212 Ito o I Sl-ol I s 94CECos A 6l:.Os 4 621:-4S S 3.-.

f;.1212 I 0000 7.11-43 4E.0OS 61-.45 2 63E4S I S7E.4.7TO.2ugS I 0) 3 41E.05 1 275.0 1'491.0S I. 91-05 5071.140

crawlo... SrvlesF).214 1.0000 I.SE02 V.4I502 a 651.Os 1651OS 2 931.10Pa-23

4m 1.0000 I.OC-07 5.34+:04 626E46 626E-06 626E.I.I

R3.226 04000 110 260E.0c 30O35.0) 1.221-09 1.341:>07

AetIolual SeriesP2-231 1.0000 120 3.2:0.02 3 SSE4S 395.t0r * 62E46Ac-227 10000 170 5940E+01 697E-09 697Es09 1.1lSE-46Th-227 00024 2 5 90E1o 1 61OE009 1 63E-11 3.271>I1&a-22.' 0.4000 54 $3401 6 SSE-09 2 74.09 1.4911.OS

FitsIon rroducsS.190 I 0000 t0 I47E002 1 72ErOg 1.72E408 172t.07Tc -9s 1.0000 3.7 7 46E01 t .7E s 7sE4 s 175J-09 n .490-Cs-134 I 0000 27 3 o5E0ol 9 44C.0n9 9 440.' l SS.n07Cs-17 I3.O000 27 207E502 2 .43EOS 2.43Et09 6 61.07Pm-147 1.0000 2.4E.02 3.55E+00 I OoE07.9 300-09 2 411.-11Eu-s4 t 10000 30 6 520.00 7E5.10 7650.30 7.651409

Duse'Totals 1.371:.04

Fler. TVA mimt (LSA RSd Soaue Toans & aekts) AsSICt WfTF LU Enf

Estimate of theAnnual Radioactive Liquid Effluents from the BPFAii liquid mela are dischared from the BPF to tbe Nolihucsky River vi the %'.VTF

Annu2l Peowsin? ES11'"Ifet EeL flroiwallon.oHEUAI AIloyylott: Caustic Discea:cr 134.737 14-v

HF U Metal Buwonu: Based on a 0 .t1% HE UAI Io=)Coodeosale front SX:

*(O aseasd on a 0.005% HE UAI Iaos)Rafetue from Sx. 5,I.

lsued on a O0:0004% HE UAI Ioss)

Scn~bbe~oluliu: a0s d on a 0.0035% il IC (etal & UAI) km)s

.. , .

U-232 00024 ss 41 7E+05 3.91E-06 939E-09 s 45E-07.U-233 0.0024 2.1 3.94E205 3.72E-06 5.9211-09 11s-01U.234 0.0024 2 7.96707 7.40E.04 1.7B 06 3.5-606.W1235 0.0024 . 9.5 1.19E406 1.12E05 2f68E43 23552.07U-236 0.0024 1.9 1.79E+07 .1.68E.04 4.03E207 7.66E407U-23J 0.0024 4.4 5.342+04 solE-07 120E409 5.29E-osU Sebttat. 912SE04 2.23E-06 5.14-

Th-223 000ooo: -ii Its2oS to, .4 2.24.1 J 14-.02Th-230 00024 9 9.35E-03 2 19QE0i S 21.05 4 74E420Th-231 00024 0or;-2 I 192.06 2.79o00 670E.n3 670.05Th-2.t: U C0024 22) 3 921102 9 19C-04 2 *s!E -04Th-2'4 1)10)24 I 2r..41 IInX .1 2--l J 1 (2 3.132415Th Subtilofl 1792.043 9. 0I:.0. j.ui:.i

Pu-:23 1 MINI 31 J 61C.1 s 1 r05En I 1I-.IJet si M.EIPu. 2I Ook0t 41 2 07-it!2 cJ*li 1.9Jr:j-h lhEuI412

An-,241 I WOO J9 2:61.-03 5$'Oll0.' 5 3411:4! 20E-ClINp-237 I0000 5o 3 27E-03 767-03 76 0713 4 45-041

Thorluu SerksR3I.21 0R ol 9s5 J 1020. 7:7E04J 2912-04 276f.02

Ac-22. 1.00 :_.2E-04 5oE0402 7.27E-04 727C.04 1 60E.5R1-224 0 4000 21 9 s 9205 9.34201 3 7!-.01 7 U41-01P'b-212 3.00to I SE- .1394C.05 9 e24E-0 9.24.01 1 66C.01l3B-212 I.0o00 7 1E03 2:J.E05 52.5-01 I 52-T0 3 73203

TI0 I01 .tJE451.05 I V7-OS 29! 19.-O 2.9-Ci 2 0)2.05

Un,,iu.S. ks?a-234 10000 I.Sc-02 1o1 1t 02 3 JI2-04 3 3-0E4 5 952-s0Pa-23 n1.0000 t.OE-07 5.342E04 1.25E401 1 25C.01 1 25E 0SRa-226 0.4000 Ito 260C.01 6.10E45 2442.05 2.6SE-03

Artilatn SeriesPa-231 I.0000 120 32.'E02 7.69.04 7.69E-04 9.234-02AC-227 1.0000 170 5.94E 01 129E204 I 359E-4 2.37E-02Tb 227 0.0024 2 5.SOE+01 1.36E-04 3 272.07 6.53E407Ra-223 0.4000 54 5.34r2Ol 1.37E-04 541S403 296E-04

FiUsioa rroducisSr.90 1.000 10 1.47E202 3.45E404 3.4!E04 3.45E203Tc-99 1.0000 1.7 7462401 1.75E-04 1.751-4t 2.97-4JCs-134 1.0000 27 S.05O01 I 19E.04 2 1924t 5.10E-03Cs-137 1.0000 27 2072.02 416E-.0 4S36E.04 131E402Pn-147 I.OOCO 2.4E4-Z S.554E00 2.01C-05 201E-05 4.SIE-07Eu-15J 1.0000 10 6.52E200 1.532-05 1 532-05 1.53E-O4

Dose Totals 24SE40

2'Cr: TVA Ps..jcct (ISA IRad Sout-ce Tenist & UliIu:,s) uli

Estimate 6f the Annual Radioactive Liquid Effluents from the BPF-

All liquid fitflats are dlid.red from the jrF to the Natichuciy Ritvr %U 1t W'VTF .

Annual 1mtesdlflp FlrntseHE UAI Alloy Ingos:

HE U Meaw Bultca. -'moI Causlk DLVAXSc: c173.7 Uyrasoed on a 0.01% HE UAI km)

Condenzae 6mrSX 5lld ona0.00S5% HE UAI oss)

tajlnatc om SX .. Ion a 0.0004% HE UAI 1I)

ScrubeSluaon: 97.

*~lasd _on a 0035%1IEI(Mcsi& UhAlbt)

.Wv ;., .- NCRP-123. .. ....ScrubberSaludo .. .. l~. .~ . Obn3>UoltbDse -fv g.Ce~jV.Uereoed Teaid .- * ^; . atl~td.

U-1J2 *0.0024 5S 4.370405 7150-OS 3130-7 1.09E45SU-25J 0.0024 2.1 3.960405 7.45E-45 1.79E47 .3.76E4C7W-34 0.0024 2 7196407 1.49E-42 3.50E-05 7.1JE-0S

U-235 OX024 9. I.I9E40d 2.24E-44 5.3*07 5.11E-OdU-236 * 00024 1.9 3.790407 3.J77.0J tO9E06 1540.05U-2JS 0002J 44 5340.04 I.OIE45S 2JtE.4S l.OSE-47U Subtoalt 3160-02 4J47E4$ 3130-04

7h- :9 60024 34 19sE-.05 7J9E-05 ISOE.47 251.-E40lu 2.0 Oo0024 9 9 350.03 1 760-c .1 ': C49 J.WE0-05

lh-2!l 001124J 101-0: I leE-Ot "4-°' 531SE07 3J3:.tl9Th.:! O : . 0011 9 : 342002 7SW.uSE4 I 770.0 9o~.lC!4lI..2U 113512. t 1:E4I1 1 9!E-04 Jt!£F.4t 3720.t9 2 7'JZ Ut

Tl Sokm...I J.OJI:.DJ 7.11147 2.6a3:.116

r:! ssnMs S.^ 4olE-C' s 1-20-17 Sl .sE0.07 5 I 0.e'5rJ4:!s ::2. a 1os .f)l oE-: 2.0.02 5 570.02 : 37002 7P4.2.11 I 045O1 eV 7 7SI:-0J I Y l .0'S I JIOAII I !'I.JI5ro S..I...i,,t 1343:.c ,sg--. 4s .701:.o1

Am-241 Jl00 I21 OVO J :-.0 4:5E4)7 J 5E-OJ7 t1SE.05Np-J,.3 I.OOo 't 1 2704.03 e 360-07 f 3lt.0? 35S7E450

ll-or um Stl.sU.4032 V5 4.17E0O0 571E.I0 JIE4S 2.!(.

2 ::s24oooo 22.1E 300.06E- 57.45E.4 5140.1 I3234?)R..234 7J 0.000 21 391.07 749E4.0 300E.05 e 9C3

U-.236 100004 7. I 1O .79C10- 42210.03 42209.06 2991:C?0U1-23 1 00: I OO ISE041 1.JE.05 2J14 7JX IEIJI 1.06Ofll-l Sllotal 1l~ .8JE-05 J::457*E4S . :931,41

T7-2$ 10000 .'JE-05 I 7E-05 2).90-r : 39E45E-07 IlJ.l0

t.2.4) 0 000 S I 9J-IE-3I0 2 0. L4)s 2650E0t 7x.010Pj.23J1n 10000 10107. 5340+.0 I0IE-05 1010.05 IOIE-1 IRs-226 0J000 110 260E3 ?.8J9E.-0 196£7210 : 5C.07

Pu-231 I 0000 120 I 7S-0.1 6 174-OS 617E40S 7.E4SS10Ae.:_7 1.000.0 70 5 9JE 03 I.l0-ES 1.12f-OS 190E-06Th-2_7 0.0014 2 51tE0003 1 .09E0S : 6E> 11 524E-0.

R..22.1 0.4000 5.4 $140.01 I.lOE-Ot J4400-9 2.17E-OS

Sr.92 o .Oooo 10 I 470.02 :.77E-4S :.77£4OS 2 77E-07Te.es I.O000 97 7.46E'01 1.40E-Oi IJ40- E4 23E-041Cs-1,4 1.0000 27 050401 t 72I0OS I Sx-OES 40940-7Csl-li 1.0000 27 207E-02 3.00E-O6 390E43 1050E-0pmI? I.D0000 2JE-02 3.550E+ I 103-019 I 6E4-09 I.t60-IIE I.--IS 10000 10 63520.00 234-09 6 23049 1.234-0

Dose T74ls . 2490-01

rik. TVA I'icti (ISA R03ourcc lawte A Eause) skSet WVTF tq Eff

Attachment HBLEU Complex Radioactive Liquid Effluents

The BLEU Complex will only produce radioactive liquid effluents (hat can be disposed of via the

sanitary sewer. The estimates of the sanitary sewer discharges.from the BLEU Complek were

*provided by Framatome-ANP.

* : .A# . . . * .

Fugitive Dust Emissions'

Discuss fugitive dust control measures and excavation activities during construction of the OCF.

Holman

Estimate the excavation volume for construction?

Fugitive dust will be controlled by watering as needed to mitigate emissions.

2.1.4.2 Uiquid Waste Management

Discuss liquid effluent treatment systems for the OCF. Provide information to update Figure 2.2of the January 1999 EA.

Holman (will need a new figure to supplement Figure 2.2 for the new system)

See Section 2.1.3.4 input for general information

RadiologicalEffluents (Bl tL Ir Awt.TNb 1/ bt'^PrILc hi5,cuP42

Additional input for Table 2.6 Annual releases of radionuclides in liquid effluents

Sewer

Uranium isotopes 1.95E-04 Ci

Thorium isotopes 1.31 E-08 Ci

Plutonium isotopes 4.32E-09 Ci

Tc99 1.II E-03 Ci

Non-radiological Effluents

The liquid discharge to the sewer will be water boiled out of the process liquid effluent(condensate) in an evaporator and reject water from the reverse osmosis purification system.The primary constituents in the discharge to the sewer are listed in the following table.

(I.Liu- -rh -[Jl u1 hh P bbD-(r iX1 0'scn~- 4-r)

| Discharged Volume | 6300 gpd

Attachment IHistorical Radioactive Liquid Effluent Data and Compiled Data

Average Annual Radioactive Liquid Effluents

I

Average Annual Uiquid Effluent Discharges -1996 through 2000

WVNTF Sewer BSB Total .Total Average'.. Z~I~it C~, .1Totil. :;:-t[ .- .~.Total. .4XDicharge *;.,Dischar~c -Cone.~,

Uranium 6.3E-04 2.BE-03 l.AE-02 1.7E-02 9.0E408 . .9&O.SRadium 1:31-04Thorium 4E.4306 M.E-OS 3A4E-04 3.E-04 4.OE-10Phluonium S.3E-07 1.3E.06 1.7E-04 *l.71E-04 1921Tcchinclium 1.6E-02 2.SE-03 2.6E-03 2.1 E-02 2.3E-OS

Release data Obtaincd r(0111 the Safety Department's seffli:1111141:11 Reports.

3/1/02File-. TVA Project (ISA Rad Source Tcnms & EMients).*i

S~rc,: NI1S L~iq ar

. Attachment JFugitive Emissions from Construction Activities

Fugitive emissions are only expected during the construction of the BLEU Complex, specificallyduring the excavation portion of the construction. Only a portion of the proposed 3LEU Complex site-has elevated soil concentrations (i.e. concentrations above natural background) that could produceradioactive fugitive emissions. Section 2.2.1.ofNFS' Supplemental Environmental Report S2001a) provides an estimate of the total volume of earth to be excavated and the amount of surfaceArea to-be excavated. Tie volume and the surface in the Supplementq! Environmental Report wereused to calculate the average excavation depth.

Calculation of Unit Dose Factors: BLEU Complex Fugitive Emissions

Unit dose factors for the fugitive emissions from the BLEU Complex were calculated for I Ci/yrreleases of each radionuclide using the CAP88-PC Version 2.0 atmospheric-dispersion- and doseassessment computer model. These factors, in units of mremlCi of radionuclide released, wereused to estimate the potential annual dose to the maximally exposed individual (MEI)attributable to the facility's radioactive fugitive emissions.

CAPSS-PC Version 2.0 hiput Data:

Thlc neteorological data used for the calculations was obtained from the NFS' 1996E.ini-irolnmetnl Report. The wind data file that was created using the rcfcrcnced mctcorologicaldata has been named NFS5Y.WND. The referenced meteorological data also included: 1) aliannual average precipitation of 103.4 cm, 2) an annual average ambient temperature of 13 0C,and 3) an 800 m lid height.

The "rural" selection was chosen for the EPA Food Source Scenario, using all of tile defaultparameters associated with this selection. Dose calculations were performed for the followingdistances: 150, 200, 250, 300, 350, 400, 450, 500, 550, 600, 650, 700, 750, 800, 850, 900, 950,1000, 1500, and 2000 meters. All particle sizes were assumed to be I pum AMAD. The defaultsolubility classes were used in all cases except for the following radionuclides, which havesolubility classes that are dictated by NFS Procedure NFS-HS-A-27 (NFS, 1999).

Th-230 and Th-232 Class WPlutonium Isotopes Class WTc-99 Class W

The radioactive fugitive emissions from the BLEU Complex will be released from ground level,as an area source type. The physical release height is 0 m, the area of the source is 1,072 m2

(1 1,540 fl2), and the plume rise was set at zero.

The maximally exposed individual was determined to be 1 50 m in the NNE direction.

BLEU Cofplex Fugitive Emiissionis Assessment(Fugitive.Radioactive Emissions Estimate for BLEU Cbmplek Consttuction Activities)

Scenario: Only a fraction (I IS40 ft) ofdlie 4.5 acre constuction site would involve soil tOat has radionuclide concentrations above naturally occuring soi.concentrations. Radioictive fugiive enissions mere only estinuted hfr the portion Ortie construction site with slightly eekvated soilconcentratons. The total estimated volume ofsoil (90.000 fR) was divided bj4.5 acres to determine the average depth ofexcavation, which was

0.46 fII The aewrageexcavation depth was multiplied bythe area involved (I 1.540 fl). which resulted in a volumn oftSJ08 f (150 Sm).Excavation is estimated to last 90 days. onc it is stared.

Voluine ofSoil Disturbed.Soil Density!

Mass of Soil Disturbed:

ISO ml* 1.6036 MT/bnandlorglcnt(Obtafnedfrolm-section2.1.4.1ofthel999E.A.)240.540 kg

FugitIve Dust Assessment for BLEU Complex Constructlon:

Nuclkle Con.c * oisturbe ' . Emilslons * Factror TEDE(pCI/g) (Cl) (a) (mrem/lC) (mrem)

U-234 2.0E3-01 4.S IE-03 1.921 0) 1.921-0.3 8.09E1-02 1.6E.03U-235 I.3; -OO 3.13C-04 1.25C 10 1.25E-04 7.64E+02 9.6E-OSU-23S 3871-o 3.9013.04 3.56E-10 3S(6.l04 7.20nE*02 2.61'44Tc.0') tL5l-.Il I 0613.04 6.251i- 1 i t.23141i 2.Sol*.tI)

Th-22' 3.513.id 9.1l-'41- 3.6611-40 3.66134t4 1.113-03 S.41.-tTh-230l 3.*1' 1.3s- t5~l .t 10 5.391.-0m l.S5 01 ,Lsl;Th-232 4.01: *-t 9.t.21204 3.8E.1tl 3.S3il414 I.631t-; 3

Pu-23S 1.31:-It) 3.13L 04 1.2;1- 1'.23414 2.Sl-03 3.(1.- 4l'u-239!-t40 1.31:-11 3.131E-03 1.2SE-09 1.2i13.03 3.21E 03 4.013*03

Pu-241 I.Sk' *O 4.33E-03 1.731E09 1.731:.)3 6.46E,01 1.1 E-04Ain-241 F.I E -0 1.9513-03 7.79E-10 7.791404 3.30r303 2.61:-03

Sunt 0.X 1 2

Airbonc Rckasc rracti:muRespirable Fractionu

Total Emisiskn Perid:

4.01E-07I .010

(Obtmincd fmm Section '.1.4.1 of tlh I93M E.A.)

34102File: TVA Project (ISA Rad Source Ternus & Eftluctts).xi;

Shect: Fupitivc Itissions

Summary of NFS Ball Field Soil Sample Results Associated witl Transmittal Letter EAS-O1-119

Radlonuclide Result Result Result Result Result Result Result Result Rcsult Ri Std Dev ';Mlntinltt. Maximum(rtC,/) (P LVE) (pCUg) fpCq) jpt3/R) (pCl/g) (r ( lgl I(^lCl -(P(-I/) (&gi pU) (pCI/g) (Cg

Pu-239/240 3.4E+00 2.2E+00 3.0E+00 1.OE+01 1.61.+01 2.81X+01 2.31.+t)1 5.1t410 8.6E+00 3.1E+01 r3n401 . 83.45% 2.2E+00' 3.1E+01IPu-238 8.5E401 1.2E+00 6.1E-01 1.0E+00 1.41-+00 2.3E1+00 1.61.3 1. I +fxl 6.11.4)1 2.42+00 1.3E+00 48.6S% 6.1E401 2.4E+00Pu-241 -3.4E+00 1.4E+0U -3.0E1+00 2.3E+01 2.8+01 4.Xl0I40 2.41 0111 7.91W1fH) 2.91.+01 2.6E+01 1.8E+01 93.01% -3.4E+00 4.SE+0OPu-242 5.8E401 3.5E+00 1.l3E-UI 1.lE+00 3.21+U0 1.414(8) 5.11 F I l. I 1 ) 1.E01 1.9E+00 1.4E+00 85.35% .IE401 3.5E+00Am-241 3.5E400 4.2E+00 4.4 1+00 1.0£+01 X.012410 1.3140(1 1.31 tll (s.41.ttIx 7.014-00 I.IE+01 8.1E+00 43.97% 3.5E+00 1.3E+01

Th.228 2.9E+00 4.0E+00 2.7E+00 4.1C+00 4.t31+00 4.21:+0() 4.41-40( 2.51.4(K) 3.11.+00 5.3E+00 3.8E+00 23.74% 2.5s+00 5.3E+00Th-230 5.914+00 6.0E+00 5.11,+00 7.42+00 5,.43100 7.11:400 5.31140(1 3.81140', 5.21.+00 4.5E+00 5.6E+00 19.49% 3.8E+00 .- 7.4E+00Th-232 2.81.+00 3.511+00 2.71+00 5.21+00 4.21.(1o 4.71:f(X) 4.91i.00 2.71.mt 4.21.4100 5.1E+00 4,0E+00 25.14% 2.7E4+00 5.2E+00

U-233/234 7.42+00 1.4E+O1 7.1E+00 2.0E+01 1.8X+01 3.111+01 1.31 +01 1.611+t( 1.7E1+01- 5.3E+01 2.0E+01 67.66% 7.JE+00 5.iE+01U-235/236 6.6E410 1.2E+00 7.04-01 1.6E+00 1.2E+00 1.61E+O0 1.524+o0 1.21+0)t 1.0E+00 2.8E+00 1.3E+00 46.85% 6.6E41I i8E+00U.238 2.7E+00 2.6E+00 2.3E+00 4.6E+00 3.S1I+00 4.6E+00 2.41.+0U 3.0t1.4f) 3.731+00 6.8E+00 3.7E+00 .37:76% 2.3E+00 6.8E+00Tc.99 1.5E401 1.6E-01 9.1E402 5.4E413 3.011-0l 8.914)3 3.91-0l 4.SI.-0'I 1.73-01 3.4E+00 6.5E-01 152.95% 9.1E402 3.4E+00

Note: The depths ofthese samples were taken within 0.3 inches ofthe surrace.

Site Descriptionr

* Contaminated area is in northwest corner, nearrailroad and southern NFS boundary

* Total area impacted is approximately.. 1,072 sqmeters

/ / A/! /e /R.y

* Excavation is currently between 0.5 to 1.5 feetdeep

12/7/01

l

2

. Napier, Jimmy D.

,Om: * Holman, Charlie [[email protected]]ant: . Tuesday, December 11,2001 1:59 PM

* To: Napier, Jimmy D.Subject: RE: Additional Information

Jim,Below are the answers to your questions. I will be looking at theinformation in your second message this afternoon.

Charlie HolmanFramatome ANP, Inc.509!-375-8049charlie [email protected]

•-----Original -Message-• From: Napier, Jimmy D. [SMTP:JDNapier~naxs.net1> Sent: Friday, December 07, 2001 9:28 AM> To: 'Charlie Holmanonfuel.com'> Cc: Griffith, Joyce M.> Subject: Additional Information

> Charlie>I have a few questions>* How long will excavation of the site occur?

(Holman, Charlie] A total of approximately 3 months from thesummer

2002 through the spring of 2003.

, * Can you provide a discussion of transportation impacts notaddressed> in the DOE/EIS?

[Holman, Charlie] The impacts are specifically addressed inTVA'sROD in the Federal Register, 66(23): 57997-58002. Here are someexcerpts(edit and use as necessary):Impact of Blendstock Selection (Provisions 1 and 2)

DOE evaluated a number of different options for providing uraniumblendstock to blend the HEU (FEIS pages 2-4 & 2-14). These includeddepleted uranium and natural uranium both in the form of UF6 anduranium oxide powder. The natural or depleted UF6 to be provided to TVAalready exists in DOE inventory at the USEC. Transfer to TVA would beaccomplished at the USEC site by a "book transfer"' to the TVA -

inventory already in storage at USEC. Therefore, no environmentalimpact would result from this transfer action. Since a UNH blendingprocess will be utilized both at SRS and NFS, UF6 must be convertedinto uranium oxide powder for dissolution into UN solution. TVAevaluated the alternative of converting the UF6 to uranium oxide at oneof its commercial fuel fabricators versus procuring uranium oxidepowder directly on the commercial uranium market. The total cost ofshipping the UF6 (either natural or depleted uranium), conversion touranium oxide powder, and shipping the powder to NFS for dissolutionwas greater than procuring the powder directly. Furthermore, theenvironmental impact of the UF6 conversion to powder would be greater.

proximately 50-70 shipments of depleted or natural UF6 from the USECCilities in Paducah, Kentucky, or 50 shipments of depleted UF6 from

oak Ridge, Tennessee, would be required. The FEIS evaluated shippingUF6 to the GE (now Global Nuclear Fuel--GNF) plant in Wilmington, NorthCarolina, from Paducah (a distance of 1,278 km) or from Oak Ridge (a

1


21 G-02-0087GOV-01-55.04

ACF-02-0063

Attachment V

Monitoring Wel and Piezometer Locations with Proposed B)LEU Facility


21G-02-0087GOV-01-55-04

ACF-02-0063

Attacbment VII

Monitoring Well Data


21G-02-0087GOV-.01-55-04

ACF-02-0063

Attachment VI

100 year Flood Plain Map for the INFS Site

Groundwater Monitoring Data

I Well 98ASampling Gross Alpha Gross Beta U-234 U-235 U-238 Tc-99

Period pCll Error+t pCI!l Error +. pCI/l Error+I pCi/A Error+f. pCIt Error+/ . pCI/I Error+l-3rd Qtr-1997 15.65 2.77 34.28 8.02 9.37 1.17 0.53 0.21 10.13 1.24 1 20.00 10.004th Qtr-1997 12.96 3.01 29.52 13.66 7.41 0.41 0.23 0.06 7.73 0.42 IU 4.60 . 6.90Ist Qtr-1998 8.61 1.96 16.11 8.27 ND ND ND ND ND ND JU 5.70 18.002ndQtr 199S 28.91 3.51 42.79 11.05 20.49 0.58 1.11 0.12 20.58 0.58 ND ND3rdQtr. 1998 13.46 2.75 27.95 8.74 ND ND ND ND ND ND ND . ND4th Qtr.1998 14.20 2.80 19.23 8.10 ND ND ND ND ND ND ND NDIstQtr-1999 10.78 3.03 31A9 9.44 ND ND ND ND ND ND ND ND2nd Qtr-1999 13.00 6.00 10.00 3.00 ND ND ND ND ND ND ND ND3rd Qtr.1999 9.00 6.00 15.00 5.00 ND ND ND ND ND ND ND . ND4th Qtr.1999 1I.00 7.00 15.00 5.00 9.03 1.59 0.34 0.23 7.39 1.37 ND NDIst Qtr-2000 17.00 7.00 10.00 4.00 7.S2 0.43 031 0.08 7.75 0.43 U 32.00 7.002nd Qtr-2000 54.00 8.00 26.00 5.00 28.37 1.22 1.23 0.17 22.09 1.01 124.00 7.003rd Qtr-2000 9.00 6.00 15.00 5.00 8.36 0.46 0.51 0.11 7.63 0.44 U 32.00 7.004th Qtr-2000 16.00 6.00 12.00 4.00 8.58 0.47 0.94 0.17 7.66 0.44 < 80.00 7.00IstQtr-2001 18.00 6.00 15.00 4.00 8.51 0.45 0.48 0.11 6.68 0.40 < 80.00 7.00Apr.2001 12.00 6.00 9.00 4.00 9.01 0.74 0.70 0.20 7.03 0.65 < 80.00 7.00May-2001 9.00 6.00 10.00 4.00 7.85 0.42 0.49 0.10 6.69 0.39 < 80.00 . 7.00Jun-2001 11.00 6.00 9.00 4.00 7.75 0.42 0.26 0.08 6.98 0.40 U 26.00 7.00lu1-2001 11.00 5.00 11.00 4.00 7.56 0.48 0.43 0.14 5.73 0.41 < 80.00 7.00.Aug-2001 17.00 6.00 16.00 5.00 14.97 0.61 1.32 0.17 12.98 0.56 U 36.00 7.00Sep-2001 13.00 6.00 . 13.00 5.00 6.68 0.40 0.44 0.11 5.71 0.37 < 80.00 7.00Oct-2001 10.00 6.00 13.00 4.00 7.21 0.56 0.76 0.18 4.76 OA5 U 22.00 7.00Nov-2001 7.00 6.00 U 6.00 5.00 7.33 0.41 J 0.51 0.11 5.68 0.36 U 38.00 7.00Dec-2001 8.00 6.00 9.00 4.00 ND ND ND ND ND ND < 80.00 7.00

Mean 14.86 17.31 10.37 0.62 9.01 52.96Std Dev 9.SC 9.57 S.77 0.34 5.01 34.37

J - Estimated ResultU - Below Lab Detection Limits< .- ss than detection limit '. '.n

ND - No Data Produced by: / A1 7/f % KV

Printed: 03/13(2002 NFS-EDMS


Well 98ASampling Pu-238 Pu-239 Th-228 Th-230 Th-Z32

Period pCUI Error +/. pCI/I Error+I- pCI/I Error+l- pCI/I Error+/- pCIM Error+/.3rd Qtr-1997 JU 0.00 0.00 JU 0.00 0.00 JU -0.15 0.11 JU 0.00 0.00 IU -0.15 0.114th Qtr-1997 IU 0.00 0.02 IU 0.00 0.00 JU 0.00 0.00 JU 0.00 0.02 JU 0.00 0.002nd Qtr-199S IU 0.01 0.01 JU 0.00 0.00 JU 0.02 0.05 IU 0.12 0.06 IU 0.00 0.004th Qtr.1999 U 40.01 0.03 U 0.00 0.00 U 0.02 0.20 U -0.02 0.06 U -0.03 0.03IstQtr-2000 U -0.14 0.07 U 0.00 0.00 U 0.02 0.03 U 0.11 0.05 U -0.04 0.032nd Qtr-2000 0.09 0.15 U 0.00 0.00 U 0.06 0.06 U -0.03 0.03 U 0.06 0.043rd Qtr-2000 0.25 0.08 U 0.03 0.03 U 0.09 0,05 0.23 0.07 U 0.00 0.004th Qtr-2000 U 0.00 0.04 U 0.00 0.00 U 0.06 0.06 0.31 0.11 U 0.00 0.001st Qtr-2001 0.25 0.10 0.03 0.03 0.08 0.04 0.56 0.11 U 0.04 0.03Apr-2001 0.12 0.06 U -0.03 0.03 U -0.02 0.02 0.16 0.06 U .0.04 0.03May-2001 U -0.05 0.03 U -0.02 0.02 U 0.02 0.04 0.07 0.04 U 0.00 0.00Jun-2001 U 0.07 0.09 U 0.03 0.03 U 0.06 0.08 0.17 0.07 U 0.00 0.00Jul-2001 0.11 0.05 U 0.00 0.00 0.09 0.05 U 0.07 0.05 U -0.02 0.02Aug.2001 U 0.00 0.00 U 0.00 0.00 U -0.03 0.06 0.08 0.05 U 0.00 0.00Sep-2001 U 0.11 0.10 0.08 0.05 U -0.05 0.05 U 0.05 0.12 U 0.00 0.00Oct-2001 U -0.04 0.10 U 0.00 0.00 1.15 0.23 U 0.04 0.07 U 0.09 0.06Nov.2001 U 0.00 0.05 U 0.04 0.06 U 0.02 0.04 0.13 0.06 U 0.05 0.03

Mean 0.04 0.01 0.08 0.12 -0.00Std Dev 0.10 0.03 0.28 0.14 0.05

J1 Estimated ResultU = Below Lab Detection Limits

ProducedPbyted 0100 NFS-EDMS

Printed: 03/13/2002 NFS-EDMS


F--~Sampling Gross Alpha

Period pCUlI Error +/.

3rd Qtr.1997 1.13 0.004thQtr-1997 1.40 0.00Ist Qtr-1998 1.08 0.842nd Qtr-1998 1.10 0.003rd Qtrf 998 1.44 0.004thQtrd199S 1.17 0.00lstQtr-1999 -0.03 0.002nd Qtr-1999 2.00 7.003rd Qtr-1999 -1.00 7.004th Qtr-1999 0.00 8.00IstQtr.2000 2.00 8.002nd Qtr-2000 2.00 8.003rd Qtr.2000 0.00 7.004th Qtr.2000 0.00 6.001st Qtr-2001 2.00 7.002nd Qtr-2001 1.00 7.003rd Qtr.2001 U 1.00 6.00 U4th Qtr.2001 U -1.00 7.00 U

Mean 0.8SStd Dev 0.97

Gross BetapcI/ Error+I-

7.91 5.56-0.21 0.005.74 0.006.98 0.006.45 7.154.82 0.004.48 0.005.00 4.007.00 5.007.00 5.00

4.00 5.004.00 4.005.00 5.007.00 5.008.00 5.006.00 4.006.00 5.004.00 5.00

5.511.94

Well 99AU-234

pCI/I Error +/-1.19 0.370.25 0.06 JUND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND ND

0.75 0.15 J

0.730.47

U-235pCi/l Error +/-

0.28 0.16 JU0.00 0.00

ND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND ND

0.52 0.12 U

0.260.26

lU-238 Tc-99

pCIt Error +1- pCI/I Error +1-

0.00 0.13 JU 10.00 10.000.08 0.03 JU -1.30 5.70ND ND JU . 0.10 9.00ND ND ND NDND ND ND NDND ND ND NDND ND ND NDND ND ND NDND ND ND NDND ND ND NDND ND ND NDND ND ND .NDND ND . ND NDND ND ND NDND ND ND ND'ND ND ND NDND ND ND .ND

0.06 0.04 U 36.00 7.00

0.05 11.200.04 . 17.28

.

J - Estimated ResultU - Below Lab Detection Limits

' ND -No DataProduced by: A II/l/. t- j/J

P 3.

Pninted: 03/1312002 NFS-EDMS


Well 99A

Sampling Pu-238 Pu.239 Th-228 Th-230 Th-232

Period pCI/I Error+/- pC/I Error+1- pCIA Error +/- pCWI Error+/- pCI/I Error+/-

3rd Qtr-1997 JU -0.13 0.14 JU -0.13 0.14 JU 0.12 0.28 JU 0.00 0.17 JU -0.37 0.22

4thQtr 1997 JU 0.00 0.02 JU 0.02 0.02 0.08 0.04 LU -0.03 0.04 JU 0.00 0.00

4th Qtr-2001 U 0.04 0.07 0.16 0.08 U 0.00 0.03 0.07 0.04 U -0.02 0.02

Mean -0.03 0.01 0.07 0.01 -0.13

Std Dev 0.09 0.14 0.06 0.05 0.21

3 - Estimated ResultU = Below Lab Detection Limits

Produced by0:/112J0 NFS-ED

Printed: 03113/2002 NFS-EDMS


I_Sampling

Period

Jul-1997Aug- 1997Sep.!997Oct-1997Nov-1997Dec-1997Jan-1998Feb-1998Mar.1998Apr.1998May-1998Jun-1998Jul-1998Aug-1998Sep.1998Oct-1998Nov-1998Dec-1998Jan-1999Feb-1999Mar.1999Apr.1999May-1999Jun-1999Jul-1999Aug-1999

Gross AlphapCIi Error +/-3.03 1.663.34 1.413.59 1.644.98 1.66ND NDND ND

5.47 1.955.82 1.656.05 1.781.83 0.005.07 1.834.00 1.795.56 2.113.23 1.523.06 1.732.81 1.263.11 2.115.16 2.153.57 1.512.25 1.214.73 1.705.10 2.492.89 0.002.00 7.003.00 7.003.00 11.00

Gross BetapCI/I Error+/.

11.44 0.0015.88 0.0027.78 0.0010.74 8.35

ND NDND ND

15.08 0.0010.76 0.0010.17 0.00

9.38 6.305.28 0.00

15.59 6.7212.06 11.44.

9.71 0.0019A3 21.7710.75 0.0011.85 0.0010.86 0.00 J8.51 0.007A3 8.218.27 7.72

40.13 16.6029.80 0.00

5.0O 5.00 J3.00 4.00

17.00 9.00

Well lOOAU-234

pCI/I Error +I-6.58 0.772.92 0.51 IU3.21 0.225.36 0.34ND NDND ND

5.50 0.325.90 032

11.28 0.604.07 0.22

19.68 0.573.04 0.24 JU3.50 0.211.85 0.131.71 0.372.84 0.42 IU2.28 0.182.88 0.31 IU3A3 0.262.82 0.255.24 0.392A5 0.183.41 0.225.77 0.332.74 0.181.99 0.15

U-235 U-238 Tc-99pCII Error+/- pCI/I Error +1- pCIII Error +1-

0.00

0.130.140.20NDND

0.230.510.970.150.640.130.220.090.710.240.470.180.320.180.380.060.430.700.170.18

0.00

0.10

0.040.06NDND

0.060.090.15

0.040.090.070.050.030.25 JU0.140.080.08

0.080.070.10

0.030.070.11

0.050.05

0.98 0.24 JU 4.00 10.001.53 0.35 JU 2.00 10.001.74 0.15 JU 0.00. 10.002.33 0.20 JU -6.10 5.10ND ND JU -2.80 7.20ND ND JU . 3.00 6.10

2.57 0.20 ND ND2.11 0.18 . ND . ND3.00 0.28 ND ND2.29 0.16 ND ND2.27 0.17 ND ND'1.69 0.18 ND- ND1.93 0.15 ND ND0.84 0.09 ND ND0.21 0.16 ND ND0.18 0.10 ND ND0.80 0.10 ND 'ND1.31 0.21 ND ND1.25 0.15 ND ND1.10 0.15 ND ND:1.86 0.22 . 75.09 9.061.21 0.13 13BU 6.23 6.66IA0 0.13 BJU 2.82 6.632A9 0.21 U -5.65 8.441.11 0.11 18.80 8.010.99 0.10 U 5.05 7.52'

B = Sample Result < 5 times activity detected in the blankJ - Estimated ResultU - Below lab Detection Umits< - Less than detection limitND - No Data

Produced by. )Wa i&)

Printed: 03/13/2002 NFS-EDMSPrinted: 03/13no200 NFS-EDMS


Well IOOASampling Gross Alpha Gross Beta U-234 U-235 U-238 Tc-99

Period pClIl Error+l- pCUlI Error+f- pCI/I Error +/- pCIUI Error 1- pCVI Error+l- pcll Erroral-Sep-1999 3.00 7.00 9.00 4.00 2.28 0.17 0.42 0.07 0.96 0.11 U 9.02 6.88Oct.1999 7.00 7.00 10.00 S.00 ND ND ND ND ND ND 14.84 7.22Nov-1999 9.00 7.00 12.00 4.00 8.40 0.41 0.60 0.10 3.71 0.25 U . 11.69 7.24Dec.1999 9.00 7.00 13.00 4.00 ND ND ND ND ND ND U. 2.75 8.08Jan-2000 13.00 7.00 8.00 5.00 9.92 0.84 U 0.46 0.20 4.24 0.55 21.10 7.24Feb-2000 8.00 8.00 9.00 5.00 9.28 0.41 1.13 0.12 4.50 0.26 U 12.65 8.55Mar-2000 14.00 8.00 11.00 4.00 14.22 0.56 3.92 0.25 5.26 0.29 U 10.09 7.91Apr.2000 10.00 8.00 7.00 4.00 6.22 0.39 0.31 0.09 2.63 0.24 < 80.00 * 7.00May-2000 1.00 8.00 7.00 4.00 4.12 OA7 U 0.29 0.17 1.32 0.28 < 80.00. 7.00Jun-2000 11.00 7.00 10.00 4.00 ND ND ND ND ND ND < 80.00 7.00Jul-2000 6.00 8.00 6.00 5.00 ND ND ND ND ND ND < 80.00 7. 00Aug.2000 5.00 7.00 8.00 4.00 ND ND ND ND ND ND < 80.00 7.00Sep.2000 3.00 6.00 10.00 4.00 2.78 0.27 0.28 0.09 1.57 0.20 U 30.00 . 7.00Oct-2000 8.00 7.00 19.00 5.00 4.93 0.34 0.51 0.11 1.87 0.21 U 20.00 7.00Nov.2000 14.00 6.00 18.00 6.00 11.22 0.55 1.21 0.19 5.65 0.39 < 80.00 7.00Dec.2000 21.00 6.00 13.00 5.00 17.77 0.71 1.83 0.23 7.91 0.47 < 80.00 7.00Jan-2001 24.00 6.00 9.00 5.00 20.33 0.76 1.50 0.20 8.35 0.47 * 83.00 7.00Feb.2001 12.00 6.00 13.00 4.00 12.51 0.54 0.68 0.12 6.65 0.39 < 80.00 . 7.00Mar.2001 13.00 6.00 14.00 4.00 10.43 0.51 0.60 0.12 4.58 0.34 < 80.00 7.00Apr-2001 9.00 6.00 14.00 5.00 7.13 0.65 0.40 0.15 3.00 0.41 < 80.00 7.00May-2001 14.00 6.00 12.00 5.00 9.93 0.50 0.62 0.12 4.71 0.34 < 80.00 7.00.Jun.2001 13.00 6.00 17.00 5.00 12.15 0.53 1.02 0.15 5.75 0.36 U . 26.00 *7.00Jul-2001 13.00 7.00 21.00 6.00 13.66 0.55 0.50 0.11 6.92 0.39 < 80.00- 7.00Aug.2001 10.00 6.00 11.00 4.00 10.04 0.49 0.52 0.11 4.49 0.32 U 26.00- 7.00Sep-2001 7.00 6.00 14.00 5.00 2.72 0.24 0.19 0.06 1.04 0.15 U * 22.00 7.00Oct.2001 10.00 7.00 15.00 5.00 9.09 0.47 1.62 0.20 3.38 0.28 U 20.00 7.00

8- Sample Result < 5 times activity detected in the blankJ - Estimated ResultU - Below Lab Detection Limits Produced by-< -Less than detection limit Poue y /CJJt i~iv/ND- No Data



I Well 100A

Sampling Gross Alpha Gross Beta U-234 U-235 U-238 Tc-99

Perlod pCUI Error +1- pCI/I Error- pCIII Error+/l pCItl Error +/- pCltl Error+l- pCI/I Error+l-

Nov-2001 14.00 7.00 11.00 6.00 13.06 0.57 J 0.71 0.14 5.35 0.36 U '36.00 7.00

Dec.2001 j 51.00 6.00 J 39.00 6.00 16.91 0.62 1.03 0.14 8.16 042 U 37.00 700

Mean 8.17 13.19 7.22 0.59 2.96 36.11

Std Dev 7.82 7.34 5.10 0.65 2.20 33.98

B - Sample Result < S times activity detected in the blankI Estimated ResultU - Below tab Detection Limits P u b '

< -Less than detection limit Producedby.

ND - No Data



Well lOOASampling Pu-238 Pu-239 Th-228 Th-230 Th-232

Period pCill Error +l- pCifl Error+f- pCUI Error+/- pCI/I Error+/. pCI/I Error+J.Jul-1997 0.00 0.10 0.00 0.00 -0.08 0.08 0.00 0.11 0.00 0.12Aug-1997 JU 0.03 0.05 0.06 0.03 JU 0.08 0.08 0.24 0.14 IU 0.00 0.00Sep-1997 JU -0.02 0.03 JU 0.00 0.00 JU 0.00 0.00 JU 0.04 0.04 IU 0.00 0.00Oct-1997 JU 0.03 0.02 JU 0.16 0.02 JU 0.05 0.05 JU 0.04 0.03 JU -0.02 0.02Jan-l 998 JU -0.03 0.03 JU 0.00 0.00 JU 0.04 0.04 JU 0.07 0.07 JU 0.04 0.04Feb-1998 J.U 0.00 0.00 JU 0.00 0.00 JU 0.08 0.06 JU 0.08 0.06 JU 0.00 0.00Mar-1998 JU 0.00 0.00 JU 0.00 0.00 JU 0.00 0.00 JU 0.04 0.03 JU 0.00 0.03Apr 1998 JU 0.00 0.22 JU 0.00 0.00 JU 0.01 0.03 JU 0.11 0.05 JU 0.02 0.02May-1998 JU 0.00 0.00 JU 0.01 0.01 JU 0.03 0.03 JU 0.00 0.03 JU 0.00 0.00Jun-1998 IU 0.03 0.03 JU 0.00 0.00 0.10 0.05 0.15 0.07 JU 0.00 0.00Jul-1998 JU *0.01 0.01 JU 0.00 0.00 JU 0.00 0.00 JU 0.20 0.11 JU 0.03 0.03Aug-1998 JU 0.00 0.02 JU 0.01 0.02 0.11 0.04 0.04 0.02 JU *0.01 0.01Sep-1998 U 2.56 1.34 U 0.37 0.42 0.04 0.02 0.10 0.03 JU 0.01 0.01Oct-1998 2.18 0.68 U 0.47 0.20 B 0.06 0.02 0.14 0.04 JU -0.01 0.01Nov-1998 U 1.68 0.56 U 0.11 0.17 U 0.04 0.03 U 0.12 0.05 U 0.02 0.02Dec-1998 U 0.60 0.52 U 0.08 0.16 0.19 0.06 0.05 0.03 U 0.00 : 0.02Jan-1999 2.98 0.59 U 0.20 0.18 0.12 0.06 0.12 0.06 U 0.00 0.00Feb-1999 U 1.81 0.63 U 0.47 0.20 U 0.06 0.04 U 0.20 0.09 U 0.06 0.07Mar-1999 U -1.18 0.77 U 0.11 0.23 U 0.08 0.05 0.21 0.07 U 0.00 0.00Apr-1999 1 -0.30 0.78 U -0.50 0.23 U 0.06 0.06 0.17 0.06 U 0.00 0.00May-1999 U 0.07 0.07 U 0.00 0.00 0.18 0.09 0.78 0.19 U . 0.00 0.00Jun-1999 2.08 OAS U OAO 0.15 U 0.08 0.06 OA9 0.10 U 0.02 0.02Jul-1999 U 0.00 0.04 U 0.02 0.02 U 0.02 0.03 OA2 0.09 U 0.00 0.00Aug-1999 U 0.05 0.08 U 0.09 0.06 U -0.04 0.03 0.56 0.11 0.06 0.04

Sep-1999 U 0.17 0.21 U 0.00 0.12 U 0.05 0.08 U 0.32 0.15 U 0.00 * 0.09

B = Sample Result < 5 times activity detected in the blankJ - Estimated ResultU - Below Lab Detection Limits ;°

PrnoducedtbYe 03/3/ .S-EDMS

Printed: 0311312002 NFS-EVMS


Well IOOASampling Pu-238 Pu-239 Th-228 Th-230 Th-232

Period pCi/i Error+/- pCI/I Error+/- pCi/l Error +1- pCO/I Error+l- pCIn Error+41-

Nov.1999 U 0.00 0.11 U 0.00 0.00 U 0.05 0.04 0.12 0.04 U 0.02 0.02

Jan.2000 U 0.00 0.09 0.14 0.08 0.46 0.19 0.68 0.23 U 0.15 0.11

Feb-2000 U 0.01 0.01 U 0.03 0.02 0.21 0.08 0.24 0.09 U 0.00 0.00

Mar-2000 U -0.23 0.18 U 0.00 0.00 0.21 0.07 0.36 0.09 U 0.02 0.02

Apr-2000 U 0.19 0.08 U 0.04 0.03 U 0.02 0.04 U 0.16 0.07 U 0.00 0.00

May-2000 U 0.00 0.04 U 0.00 0.00 U 0.08 0.08 U 0.15 0.09 U 0.00 0.00

Sep-2000 OA6 0.13 U 0.00 0.00 0.20 0.11 0.26 0.13 U -0.07 . 0.07

Oct-2000 0.33 0.09 U 0.02 0.02 U 0.07 0.06 0.10 0.05 U 0.00 0.00

Nov-2000 U 0.00 0.00 U 0.05 0.05 U 0.06 0.11 U 025 0.15 U 0.06. 0.06

Dec-2000 U 0.00 0.04 U 0.00 0.00 U 0.05 0.05 0.23 0.07 U 0.00 0.00

Jan-2001 U 0.00 0.00 U 0.00 0.00 0.11 0.05 0.22 0.07 U 0.02 . 0.02

Feb-2001 U 0.00 0.10 U 0.00 0.00 U 0.02 0.02 0.18 0.06 U 0.00 0.00

Mar-2001 U 0.16 0.08 U 0.00 0.00 U 0.02 0.02 0.73 0.12 U 0.02 0.02'

Apr.2001 U 0.00 0.00 U 0.00 0.00 U 0.08 0.14 U 0.55 0.26 U 0.00 . 0.00

May-2001 U 0.00 0.03 U 0.02 0.02 0.08 0.04 U 0.08 0.05 U 0.04 0.03

Jun-2001 U 0.12 0.07 U 0.00 0.00 U 0.00 0.00 0.12 0.05 U 0.00 0.03

Jul-2001 U 0.03 0.05 U 0.03 0.03 U 40.11 0.05 0.09 0.05 U 0.02 0.b2

Aug-2001 U 0.04 0.13 U 0.00 0.00 U 0.02 0.04 U 0.05 0.05 U 0.00 0.03

Sep-2001 U 0.05 0.06 U 0.00 0.00 U 0.04 0.03 U -0.02 0.02 U 0.00 0.00

Oct-2001 0.89 025 U 0.00 0.00 U 0.03 0.05 U 0.09 0.07 U -0.03 0.03

Nov-2001 U -0.08 0.10 U 0.00 0.00 U 0.02 0.04 0.10 0.05 U 0.00 0.00

Dec-2001 O.10 0.05 U 0.03 0.03 U -0.04 0.03 U 0.00 0.00 U 0.04 0.03

Mean 0.32 0.05 0.06 0.20 0.01Std Dev 0.80 0.15 0.09 0.19 0.03

B Sample Result < 5 times activity detected in the blankJ Estimated ResultU Below Lab Detection Limits P by A / 1Produced byi 03/13/2002 N

Pninted: 03/13/2002 NiFS-EDMS


I Well 52 - BackgrounSampling

Period

Jul-1997

Aug.1997

Sep-1997

Oct-1997

Nov-1997

Dec-1997

Jan-I 998

Feb-1998

Mar.1998

Apr.1998

May-1998

Jun-1998

Jul-1998Aug-1998

Sep-1998

Oct-1998

Nov-1998

Dec-1998

Jan-1999

Feb-1999

Mar.1999

Apr-1999

May-1999

Jun-1999

Jut-1999

Aug-1999

Gross AlphapCI/I Error +-0.88 0.000.30 0.000.64 0.001.37 1.010.31 0.000.28 0.000.62 0.001.12 0.000.92 0.001.01 0.00 <0.99 0.001.37 0.000.50 0.000.53 0.000.69 0.001.17 0.001.40 0.001.78 0.000.87 0.000.52 0.001.02 0.001.33 0.001.94 0.003.00 6.000.00 6.00

-1.00 7.00

Gross BetspCI/I Error+t-

-0.79 0.00

7A.I 0.00

12.46 0.00

7.97 8.12

0.80 0.77

2.91 0.00

4.53 0.00 a

5.34 0.00

10.09 0.00

-0.53 0.00

-3.91 0.00

4.19 0.005.51 0.00 B

8.01 0.00 a3

7.03 6.275.78 0.00 JU

5.56 6.14

5.64 0.00 J

11.72 0.00

7.89 0.00

4.31 0.00

9.18 0.00

7.30 8.26

5.00 4.000.00 4.00

1.00 4.00

U-234pCII Error +t-0.42 0.180.75 0.360.43 0.07 JU2.37 0.27 JUND ND

0.53 0.080.50 0.092.66 0.300.38 0.070.20 0.06 JU0.43 0.08 IU0.69 0.17 JU1.02 0.14 JU1.71 0.20 JU0.30 0.11 IU0.06 0.19 JU0.17 0.040.53 0.12 JU2.41 0.520.87 0.22 U0.33 0.08 U1.45 0.27 U0.44 0.13ND NDND NDND ND

d Well IU-235 U-238 Tc-99

pCI/ Error+l- pCltl Error +1- pCiII Error+/-0.00

0.00

0.04

0.03ND

0.050.040.260.110.010.03

-0.07o.n90.050.070.060.020.041.090.130.04

-0.090.12NDNDND

0.070.000.03 JU0.05 JUND

0.020.020.10 JU0.040.02 IU0.03 JU0.07 JU0.05 JU0.030.05 JU0.10 JU0.02 IU0.040.38 U0.10 U0.05 BU0.07 U0.07 UNDNDND

0.10

0.00

-0.01

0.03ND

0.040.100.070.070.000.010.070.040.090.070.000.020.110.220.090.020.230.04NDNDND

0.07 JU0.00 lU0.02 JU

0.03 IU

ND IU0.020.04 JU

0.050.030.000.030.050.030.050.050.000.010.060.160.060.030.120.04NDNDND

4.0010.008.003.608.30

16.005.60NDNDND

. NDNDNDNDNDNDNDNDNDNDNDNDNDNDNDND

10.00

10.00

8.00

7.507.405.205.00NDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDND

B - Sample Result < S times activity detected in the blankJ - Estimated ResultU - Below Lab Detection Limits<- Less than detection limitND- No Data

Produced by. - "I4A ,{"2^, c'i/

rnnieo: WI J..3IZUUI NFS-EDMSPrinted: 0~134200 NFS-EDMS


I ng Well 52 - Backrround Well JU-234 U-235 U-238 Tr-99

pCinl Error+/- pCi1 Error+l. pCi/ Error+/- pCin Error+/-Sampling

Period

Sep-1999Oct.1999Nov.1999Dec.1999Jan.2000Feb-2000Mar-2000Apr-2000May-2000Jun-2000Jul2000Aug-2000Sep-2000Oct-2000Nov-2000Dec-2000Jan-2001Feb-2001Mar.2001Apr-2001May-2001Jun-2001Jul-2001Aug.2001Sep-2001Oct-2001

Gross Alpha Gross BetapCIn Error +l- pCi/I Error l--1.00 6.00 -1.00 4.002.00 7.00 7.00 4.001.00 6.00 4.00 3.000.00 7.00 1.00 3.001.00 7.00 2.00 4.000.00 7.00 4.00 3.001.00 7.00 3.00 3.00

-2.00 7.00 3.00 4.001.00 7.00 2.00 3.000.00 7.00 5.00 3.002.00 7.00 8.00 4.002.00 6.00 4.00 4.001.00 6.00 1.00 4.00

.1.00 6.00 1.00 4.000.00 6.00 2.00 4.000.00 6.00 2.00 4.00.1.00 6.00 0.00 4.002.00 6.00 9.00 4.003.00 6.00 2.00 4.001.00 6.00 7.00 4.000.00 6.00 2.00 4.000.00 6.00 4.00 4.001.00 5.00 4.00 3.001.00 5.00 1.00 4.00

U 1.00 6.00 U -1.00 4.00U .1.00 6.00 U 5.00 4.00

U

U

U

0.670.350.380.070.130.120.211.300.380.190.220.870.221.053.68OA40.521.251.083.841.250.280.670.730.790.91

0.08 U0.07 U0.07 U0.10 U0.04 U0.04 U0.06 U0.20 U0.07 U0.05 U0.05 U0.220.11 U0.24 U0.510.15 U0.22 U0.33 U0.160.370.18 U0.090.18 U0.180.20 U0.24 U

0.040.01

0.01

0.060.000.000.010.030.010.000.010.510.000.322AI0.110.230.080.07

0.170.000.05

0.100.230.160.00

0.02 U 0.070.02 U 0.060.01 U -0.010.08 J 0.170.00 0.070.00 0.100.02 U 0.020.03 0.090.01 U 0.030.02 U 0.020.02 0.040.16 U 0.050.09 U 0.040.15 0.16OAO 0.540.08 U 0.110.14 U 0.120.14 U 0.160.04 U 0.020.08 U 0.000.06 U 0.050.06 U 0.020.10 0.140.10 U 0.09

0.12 U 0.050.08 0.17

0.03 ND ND0.03 . ND ND

0.01 ND ' ND

0.14 ND ND0.03 14.36 7.160.03 U -8.70 7.190.02 U -7.33 -7.600.05 U 33.00 7.000.02 c 80.00 7.000.02 < 80.00 7.000.02 < 80.00 7.000.05 < 80.00 7.000.04 U 32.00 7.000.09 U 32.00 7.000.19 < 80.00 7.000.08 < 80.00 7.000.08 87.00 1.00

0.11 < 80.00 . 7.00

0.02 <. 80.00 7.000.00 < 80.00 7.000.03 < 80.00 7.000.02 < . 80.00 7.00

0.08 < 80.00 7.000.06 U 37.00. 7.000.05 < 80.00 7.000.10 < 80.00 7.00

B - Sample Result < S times activity detected in the blankJ - Estimated ResultU - Below Lab Detection Limits< - Lss than detection limitND - No Data

Prduced by : 7.A /

rnnreu: WII.SILU¶.U NFS.EDMSrnnmed: u311 nWU NFS-EDMS


Well 52 - Background Well

Sampling Gross Alpha Gross Beta U-234 U-235 U-238 Te-99

Period pCII Error+/- pCIA Error+I- pCIll Error+1- pCi/l Error+l- pCI/I Error+I- pCIII Error+/-

Nov.2001 U -1.00 6.00 U -5.00 4.00 1.30 0.27 U 0.05 0.09 U 0.00 0.00 U 70.00 7.00

Dec.2001 U -1.00 6.00 U 1.00 4.00 0.46 0.18 U 0.06 0.06 U 0.00 0.00 U 36.00 7.00

Mean 0.66 3.91 0.84 0.14 0.08 48.41

Std Dev 1.02 3.66 0.85 037 0.09 34.69

B, Samnple Result < 5 times activity detected in the blankJ - Estimated ResultU - Below Lab Detection Limits

Produced by-.

< - Less than detection limitNDu -No Data



Well 52 - Background WellSampling Pu-238 Pu-239 Th-228 Th-230 Th-232

Period pCni Error+/- pCIA/ Error+/- pCl/I Error+/. pCI/I Error+/- pClIt Error+l.Jul-1997 0.00 0.10 0.07 0.07 0.00 0.00 0.11 0.14 0.00 0.00Aug 1997 0.08 0.14 0.00 0.00 0.12 0.12 0.12 0.12 0.12 0.09Sep 1997 JU 0.02 0.02 J U 0.02 0.02 JU 0.00 0.00 IU 0.03 0.02 JU 0.01 0.01Oct-1997 JU 0.00 0.00 1U 0.03 0.03 JU 0.03 0.03 JU 0.00 0.00 IU 0.00 0.00Dec.1997 .U 0.00 0.00 JU 0.00 0.00 JU 0.00 0.00 IU .0.01 0.01 O U 40.01 0.01Jan.1998 JU 0.00 0.00 JU 0.02 0.02 JU 0.00 0.00 JU 0.00 0.00 JU 4.007 0.07.Feb-1998 JU -0.03 0.05 IU 0.06 0.04 0.19 0.09 JU 0.00 0.00 IU 0.05 0.05Mar-1998 JU 0.00 0.00 JU 0.02 0.02 IU 0.03 0.02 IU 0.08 0.04 JU 0.02 0.02Apr-1998 JU 0.01 0.01 JU 0.03 0.02 JU 0.16 0.06 0.23 0.08 JU 0.00 0.00May-1998 IU 0.03 0.02 LU 0.00 0.00 J 0.17 0.06 0.12 0.06 JU 0.06 0.04Jun-1998 LU 40.03 0.04 LU -0.01 0.01 0.07 0.03 0.06 0.03 LU 0.00 0.00Jul.1998 LU -0.02 0.02 JU 0.00 0.00 0.11 0.05 LU 0.13 0.08 JU 0.03 0.03Aug.1998 JU 40.03 0.03 JU 40.01 0.01 IU 0.07 0.04 0.20 0.06 LU 0.00 0.00'Sep-1998 U 1.96 0.85 U -0.10 0.24 0.06 0.02 0.05 0.02 LU -0.01 0.01Oct-1998 U 1.24 0.65 U 0.31 0.18 LU 0.02 0.05 0.11 0.04 LU 0.02 0.02Nov.1998 U 0.25 0.30 U 0.14 0.10 0.06 0.03 0.09 0.04 U 0.00 0.00Dec-1998 U -1.87 0.64 U 101.00 0.21 U 0.03 0.03 0.15 0.06 0.05 0.03Ian-1999 U -5.76 1.10 U 40.18 0.36 U 0.07 0.07 0.21 0.07 U 0.00 0.00Feb-1999 U -2.92 1.47 U OA7 0.48 U 0.10 0.10 U 0.10 0.10 U 0.05 0.05

Mar-1999 U -4.60 1.42 U -0.60 0.37 0.29 0.13 U 0.29 0.15 U O.OQ 0.00Apr-1999 J 0.54 0.38 U -0.12 0.11 U 0.09 0.06 0.53 0.15 U Q.09 0.06May.1999 U 0.09 0.40 U 0.04 0.11 0.06 0.03 0.10 0.04 U 0.03 0.02Sep-1999 U 0.00 0.00 U 0.00 0.00 U 0.00 0.01 0.07 0.03 U -0.01 .0.01

Oct-1999 U -0.02 0.02 U 0.03 0.02 J 0.03 0.02 J 0.07 0.03 I 0.02 0.01

Nov.1999 U 0.03 0.02 U 0.03 0.02 U 0.00 0.01 0.12 0.03 U 0.00 0.00

I Estimated ResultU - Below Lab Detection Limits

Produced by- 7.¾hAA 't_ /'G.4 z7



Well 52 - Background WellSampling Pu-238 Pu-239 Th-228 Th-230 Th-232

Period pCI! Error+/- pCIlA Error +t- pCI! Error+l- pCI/ Error +/- pCI/I Error +/-

Dec.1999 U 0.05 0.06 U 0.03 0.06 U 0.38 0.28 U 0.02 0.06 U -0.01 0.01

Jan-2000 027 0.12 U 0.05 0.05 U 0.01 0.02 0.11 0.04 U 0.03 0.02

Feb-2000 U 0.05 0.06 U 0.00 0.00 U 0.04 0.03 U 0.05 0.03 U 0.00 0.02

Mar-2000 U 0.00 0.03 U 0.00 0.00 U 0.01 0.02 0.02 0.03 U 0.01 0.01

Apr.2000 0.21 0.07 U -0.02 0.02 U 0.02 0.02 0.13 0.04 U 0.00 0.00

May-2000 U 0.00 0.02 U 0.00 0.00 U -0.03 0.03 0.20 0.06 U 0.00 0.00

Jun.2000 U 0.00 0.02 U 0.02 0.02 U 0.00 0.00 0.09 0.03 U 0.00 0.00

Jul.2000 U .0.13 0.07 U 0.09 0.06 U 0.01 0.01 U 0.07 0.03 U 0.00 0.00

Aug-2000 U 0.00 0.07 U 0.00 0.00 U 0.03 0.02 0.05 0.03 U 0.00 0.00

Sep.2000 U 0.44 0.21 U 0.00 0.09 U 0.01 0.02 0.13 0.04 U .0.01 0.01

Oct.2000 0.89 0.25 U 0.07 0.07 U 0.00 0.07 0.29 0.08 U 0.02 0.04

Nov-2000 0.21 0.10 U 0.00 0.00 U 0.05 0.05 0.19 0.08 U 0.0 0.02

Dec-2000 U 0.05 0.09 U 0.00 0.00 U -0.05 0.08 0.21 0.09 U 0.05 0.04

Jan.2001 U 0.17 0.12 U 0.00 0.00 U 0.05 0.05 0.18 0.06 U -0.02 0.02

Feb.2001 0.47 0.17 U 0.00 0.00 U -0.02 0.04 0.21 0.07 U 0.00 0.00

Mar-2001 U 0.13 0.15 U -0.06 0.06 U 0.04 0.03 0.70 0.12 U 0.04 0.03

Apr-2001 U 0.08 0.08 0.12 0.07 0.07 0.04 U 0.05 0.03 U 0.02 0.02

May-2001 U 0.07 0.08 0.14 0.07 U -0.02 0.02 0.11 0.05 U 0.00 0.00

Jun-2001 U -0.02 0.07 U 0.00 0.00 U 0.00 0.05 U 0.04 0.03 U 0.00 0.00

Jul-2001 0.24 0.08 U 0.00 0.00 U 0.05 0.05 U 0.00 0.00 U 0.03 0.03

Aug-2001 U 0.13 0.15 0.58 0.17 U -0.02 0.04 0.06 0.04 U 0.00 0.00

Sep-2001 U 0.19 0.19 U 0.00 0.00 U 0.03 0.05 0.50 0.12 U 0.00 0.00

Oct.2001 0.27 0.11 U 0.00 0.00 U .0.33 0.25 U 0.66 0.31 U 0.11 0.11

Nov.2001 U -0.10 0.12 U 0.05 0.05 U -0.11 0.05 U 0.11 0.06 U 0.02 0.02

J Estimated ResultU - Below Lab Detection Limits

ProducedPby 7ne:013.0 02 NFS



Well 52 - Backaround WellSampling Pu.238 Pu-239 Th-228 Th-230 Th-232

Period pCI/I Error+I pCI/l Error +/- pCI/I Error+1. pCI/I Error +/- pCI/I Error+1-

Dec-2001 0.22 0.12 U 0.07 0.07 U 0.04 0.04 0.12 0.07 U 0.00 0.00

Mean -0.14 2.05 0.04 0.14 0.02Std Dev 1.22 14.28 0.10 0.15 0.03

J - Estimated ResultU - Below Lab Detection Limits A

Produced by*. , /,A <A °e



ISampling

Period

Jul.1997Aug-1997Sep.1997Oct-1997Nov-1997Dec-1997Jan-1998Feb.1998Mar-1998Apr.1998May-1998Jun-1998Jul-1998Aug-1998Sep- 1998Oct-1998Nov.1998Dec-1998Jan.1999Feb-1999Mar-1999Apr-1999May-1999Jun-1999Jul-1999Aug-1999

Gross AlphapCI/I Error +I-1.68 1.471.78 1.151.14 1.302.37 1.22ND ND

0.45 0.561.68 1.471.65 0.992.50 1.331.83 1.492.29 1.441.32 1.401.32 1.511.57 1.301.11 1.393.16 1.321.70 1.922.88 1.811.62 1.222.63 1.694.12 0.004.65 2.420.47 0.005.00 9.006.00 8.005.00 13.00

Well 10lAGross Beta U-234

pCI/I Error +/- pCII Error+/-5.97 0.00 2.63 0.68

21.24 0.00 1.67 0.40 JU4.83 0.00 1.69 0.15

10.74 8.35 2.17 0.21 JUND ND 6.53 0.47

5.40 0.00 ND ND7.90 0.00 ND ND6.02 0.00 ND ND4.38 0.00 ND ND7.45 6.14 ND ND3.92 0.00 ND ND

11.74 0.00 ND ND14.17 0.00 ND ND10.81 7.01 ND ND30.52 0.00 ND ND628 7.39 ND ND9.48 0.00 ND ND5.64 0.00 ND ND8.84 0.00 ND ND

13.77 0.00 ND ND6.79 0.00 ND ND

19.66 14.54 ND ND31.27 21.26 ND ND24.00 5.00 ND ND15.00 6.00 ND ND54.00 13.00 ND ND

U-23SpCI/I Error +/-0.130.060.120.080.30NDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDND

0.130.170.040.040.09NDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDND

U-238 Te-99pCUI Error +1- pCM/I Error +1-0.66 0.40 JU. *2.00 10.000.39 0.16 JU * -1.00 10.000.42 0.07 JU -5.10 6.00.0.21 0.06 JU 0.00 5.702.37 0.26 JU 7.60 .. 6.00ND ND LU 1.00 6.10ND ND JU -0.80 7.60.ND ND ND NDND ND ND NDND ND ND NDND ND ND NDND ND ND NDND ND ND NDND ND ND NDND ND ND NDND ND ND NDND ND ND NDND ND ND NDND ND ND ND--ND ND * ND NDND ND 66.17 8.96ND ND JU -4.56 6.55ND ND JU -6.09 6,54ND ND ND NDND ND U -6.18 7.70ND ND 14.31 7.63

B " Sample Result < S times activity detected in the blankJ - Estimated ResultU - Below Lab Detection Limits< - Less than detection limitND - No Data

Produced by. - Il(IAt f 6 24

Printed: 03/1312002 NFS-EDMSPrntsed: 03/13/2002 NFS-EDMS


r

SamplingPeriod

Sep.1999Oct-1999Nov-1999Dec.1999Jan-2000Feb-2000Mar-2000Apr-2000May-2000Jun-2000Jul.2000Aug-2000Sep-2000Oct-2000Nov-2000Dec-2000Jan-2001Feb-2001Mar-2001Apr-2001May-2001Jun-2001Jul-2001Aug-2001Sep.2001Oct-2001

Gross AlphspCiI Error +/-3.00 7.005.00 8.005.00 9.004.00 8.004.00 8.002.00 9.000.00 9.00

5.00 8.001.00 9.001.00 9.003.00 9.003.00 7.005.00 7.001.00 8.006.00 7.004.00 7.003.00 7.001.00 7.001.00 7.00

2.00 7.004.00 7.003.00 7.000.00 8.002.00 7.00

U 5.00 8.00U 4.00 8.00

Gross BetapCi/I Error +1-

17.00 6.0022.00 5.0032.00 6.0017.00 5.0019-00 6.0016.00 6.0024.00 6.0022.00 5.0018.00 6.0028.00 6.0021.00 6.0027.00 6.0022.00 6.0031.00 6.0029.00 7.0026.00 7.0017.00 6.0020.00 5.0019.00 5.0019.00 6.0017.00 6.0016.00 5.0024.00 7.0018.00 6.0016.00 6.0032.00 7.00

Well 1O0AU-234

pCI/I Error+IND NDND NDND NDND NDND NDND NDND NDND ND

2.87 0.31 UND NDND NDND NDND NDND NDND NDND NDND NDND ND

1.92 0.211.73 0.28 U1.97 0.301.92 0.21 U1.68 0.20 U2.08 0.25 U3.30 0.442.76 0.27

U-235pCi/I Error +4.

U-238pCI/I Error+1.

Tc-99.pCI/I Error +

111111]I.-

NDNDNDNDNDNDNDND

0.19

NDNDNDNDNDNDNDNDND

0.260.090.310.120.090.150.680.46

NDNDNDNDNDNDNDND

0.09 B

NDNDNDNDNDNDNDNDND

0.080.060.120.060.060.100.210.12

NDNDNDNDNDNDNDND

0.22NDNDNDNDNDNDNDNDND

0.280.170.450.610.430.510.340.58

ND 12.47 6.92ND 20.37 7.35SND 17.40 7.31ND U -27.23 8.09ND 18.44 7.21ND U -26.04 8.10ND U 4.99 7.85ND U 32.00 7.00

0.08 < 80.00 7.00ND < 80.00 7.00ND . < 80.00 7.00ND < 80.00 7.00ND U 38.00 .7.00ND < 80.00 7.00ND < 80.00 7.00ND < 80.00 7.00ND 89.00 7.00ND < 80.00 7.00.

0.08 < 80.00 7.000.09 < 80.00 7.000.14 < 80.00. 7.000.12 < 80.00 .7.000.10 < 80.00 7.000.12 U 50.00 7.000.14 U- 22.00' 7.000.12 U *21.00 7.00

B - Sample Result < 5 times activity detected in the blankJ - Estirnated ResultU - Below Lab Detection Limits<- Less than detection limitND - No Data

Produced by: All

1'ilnted: U3IUIZOUZ NFS.EDMSFnnted: 0311312OU2 NFS-EDMS


I _Well lOlA

Sampling Gross Alpht Gross Beta U-234 U-235 U-238 Tc-99

Period pCIA Error+t- pCIfl Error+I- pCIA Error+/- pCIlI Error+I. pCInI Error+/f pCIti Error+I-

Nov.2001 U 3.00 7.00 35.00 7.00 2.02 0.21 1 0.35 0.09 0.62 0.11 < 80.00 7.00

Dec.2001 6.00 7.00 3S.00 6.00 2.67 0.24 0.29 0.08 0.41 0.09 U 24.00 7.00

Mean 2.75 18A7 2.48 0.23 0S4 36.99

Std Dev 1.66 10.09 1.19 0.17 O.SI 38.12

B = Sample Result < 5 times activity detected in the blank1 - Estimated ResultU - Below Lab Detection Limits< -LUss than detection limit

Poue y f.L/

ND - No Data



Well 1O0ASampling Pu-238 Pu-239 Th-228 Th-230 Th-232

Period pCiA Error +1. pCiAI Error +1- pCi/A Error +1- pCIA Error +- pCII Error +/-

Jul1997 -0.30 0.21 0.15 0.15 0.00 0.00 o0.14 0.14 -0.14 0.14

Aug.1997 IU 0.03 0.03 IU 0.06 0.04 LU -0.12 0.12 JU -0.12 0.33 LU 0.00 0.00

Sep-1997 IU 0.00 0.00 JU 0.02 0.02 JU 0.00 0.00 JU 0.00 0.00 IU 0.03 0.02Oct.1997 JU 0.00 0.04 JU 0.00 0.00 0.05 0.03 IU 0.04 0.03 IU 0.00 0.00

Nov-1997 IU 0.05 0.05 IU -0.10 0.07 IU 0.00 0.00 LU 0.00 0.05 LU 0.04 0.04

May-2000 0.13 0.06 U 0.00 0.00 U 0.06 0.05 U 0.08 0.05 U 0.00 0.00

Mar-2001 U -0.05 0.13 U -0.05 0.08 U 0.00 0.00 0.59 0.11 U 0.00 0.00

Apr-2001 U -0.05 0.08 U 0.00 0.00 U 0.03 0.05 0.13 0.06 U 0.03 0.05

May-2001 0.24 0.11 U 0.00 0.00 U -0.02 0.04 0.11 0.06 U 0.00 0.00

Jun-2001 U .0.03 0.07 U 0.00 0.00 U 0.04 0.04 U 0.02 0.04 U 0.02 0.02

Jul.2001 U 40.06 0.14 U 0.00 0.00 U -0.11 0.10 U 0.07 0.05 U 0.00 0.00

Aug-2001 U -0.06 0.11 U -0.13 0.09 U 0.03 0.03 039 0.11 U 40.03 0.03

Sep-2001 U -0.05 0.16 U 0.00 0.00 U 0.08 0.14 OA2 0.19 U 0.08 0.08

Oct-2001 U 0.00 0.07 U 0.03 0.03 U 0.00 0.04 U 0.14 0.10 U 0.00 0.00.

Nov.2001 U 0.05 0.06 U 0.16 0.07 U 0.17 0.11 U 0.04 0.04 U 0.00 0.00

Dec-2001 U 0.07 0.06 U 0.04 0.03 U 0.04 0.05 U 0.04 0.04 U 0.00 0.00

Mean .0.00 0.01 0.02 0.11 0.00Std Dev 0.11 0.07 0.07 0.19 0.05

J Estimated ResultU = Below Lab Detection Limits

Produced by: 1,/Y fiA p-Vl{d)



ISampling

Period

Jul.1997Aug-1997Sep-1997Oct-1997Nov-1997Dec-1997Jan-1998Feb-1998Mar-1998Apr.1998May-1998Jun-1998Jul-1998Aug-1998Sep.1998Oct-1998Nov.1998Dec-19981St Qtr.19992nd Qtr-19993rd Qtr-1999Nov-1999Dec-1999Jan-2000Feb-2000Mar.2000

Gross AlphapCiA Error +1.

1.01 0.00

1.11 1.020.38 0.001.15 0.000.43 0.000.46 0.001.01 0.00

0.87 0.000.98 0.000.62 0.001.13 0.000.48 0.001.02 0.001.11 0.00

1.30 0.000.94 0.860.91 0.00

1.02 0.93-0.18 0.00

1.00 7.00*1.00 7.000.00 7.001.00 7.003.00 7.00-1.00 7.00

-3.00 7.00

Gross BetapCin Error+/-1.32 0.005.12 0.004.51 0.007.97 8.122.36 0.003.59 0.00

10.44 0.00*0.55 0.006.77 0.00

-3.00 0.00.5.95 0.007.79 0.004.32 0.009.10 0.00

21.52 0.009.59 0.000.29 0.005.90 0.00

-1.15 0.003.00 3.003.00 4.002.00 3.008.00 4.008.00 5.003.00 4.004.00 4.00

Well 102AU-234

pCI/I Error+/-3.96 0.572.09 0.45 IU0.24 0.08 JU3.80 0.30ND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND ND

. I

U-235 U-238 Tc-99pCI/I Error+/- pCaIn Error+/- pcan -Error +l-

0.12-0.250.02O.17NDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDND

0.120.20 JU0.03 JU0.06NDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDND

0.120.120.080.05

NDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDND

0.08 JU 7.000.12 IU 4.000.04 JU 1.90.0.03 JU .3.90ND JU o.40ND JU -5.30ND IU -1:40ND NDND NDND NDND NDND NDND -1.00ND NDND NDND NDND NDND NDND 56.14ND U 0.59ND 40.50ND U 10.78ND U .0.30ND 22.84ND U -14.84ND * U 10.84

10.0010.00

6.306.206.10

*6.006.30NDNDNDNDND

10.00NDNDND

, NDND

8.85-7.797.267.238.04

.7.268.247.92

J - Estimated ResultU - Below Lab Detection Limits<- Less than detection limitND - No Data Producedby. byi A A ' - -

rnntee: uai i .�i�uvi NFS-EDMSPrnted: U31 131ZUUZ2 NFS-EDMS


IF�� -- - - -Sampling

Period

Apr.2000May-2000Jun-2000lul-2000Aug-2000Sep.2000Oct-2000Nov-2000Dec-2000Jan.2001Feb-2001Mar.2001Apr-2001May-2001Jun-2001Jul-2001Aug-2001Sep-2001Oct.2001Nov-2001Dec.2001

MeanStd Dev

Gross AlphapCifl Error +/-

1.00 7.00

2.00 8.002.00 7.00

2.00 7.000.00 6.002.00 6.00.1.00 6.003.00 6.001.00 6.000.00 6.000.00 6.003.00 6.00

-1.00 6.000.00 6.000.00 6.00

-3.00 6.001.00 6.00

U 0.00 6.00U -1.00 7.00U 1.00 7.00U 1.00 6.00

0.611.24

.

Gross BetapCUI Error+/-7.00 3.002.00 4.00 U4.00 4.006.00 3.002.00 4.000.00 4.007.00 4.007.00 4.008.00 4.002.00 5.009.00 4.007.00 4.00S.00 4.003.00 4.00S.00 4.002.00 4.00

5.00 4.00 U3.00 4.007.00 4.00

-3.00 5.006.00 4.00

4.554.37

Well 102AU-234

pCI/I Error +/-

ND ND0.30 0.14 UND NDND NDND NDND NDND NDND NDND NDND NDND ND

0.40 0.10 U14.34 0.970.48 0.12 U0.47 0.11 U1.IS 0.32 U

0.54 0.22 U2.64 0.40 U0.46 0.11 U1.77 0.42 UND ND

2.333.69

iU-235 U-238 Tc-99

pCI/I Error +/. pCVI Error +/- . pCI/I Error +1.

ND ND ND ND U 36.00 7.000.05 0.05 U 0.10 0.07 < 80.00 7.00ND ND ND ND < 80.00 7.00ND ND ND ND c 80.00 7.00ND ND ND ND < .80.00 7.00ND ND ND ND U 36.00 7.00ND ND ND ND < 80.00 7.00ND ND ND ND < 80.00 . 7.00ND ND ND ND < 80.00 7.00ND ND ND ND 95.00 7.00ND ND ND ND < 80.00 7.00

-0.02 0.02 0.12 0.05 < 80.00 7.000.48 0.17 U 0.12 0.09 < '80.00 7.000.16 0.08 0.20 0.07 < 80.00 7.00'0.05 0.04 0.13 0.06 < 80.00 7.000.09 0.09 U 0.18 0.13 < 80.00 7.000.00 0.13 0.27 0.12 < 80.00 7.000.23 0.14 0.28 0.13 U 22.00 7.00

-.0.02 0.02 0.09 0.04 U 54.00 7.000.00 0.20 0.30 0.17 U 31.00 7.00ND ND ND ND U 50.00 7.00

0.08 0.15 . 42.470.16 0.08 36.22

U

U

I - Estimated ResultU Bclow Lab Detection Limits< - Less than detection limit Produced by. Z.a23iIAA ,"_W& 1ND-NoData i



Well 102ASampling Pu-238 Pu-239 Th-228 Th-230 Th-232

Period pCUI Error 4- pCIVI Error+{- pClUI Error+l- pCI/I Error+/- pCI/I Error+l-

Jul-1997 0.00 0.00 0.00 0.00 -0.06 0.06 0.06 0.06 0.00 0.00

Aug-1997 JU 0.00 0.00 JU 0.00 0.00 JU 0.00 0.00 LU -0.12 0.17 IU -0.06 0.06

Sep-1997 JU 0.00 0.00 JU 0.00 0.00 JU -0.05 0.03 JU 0.03 0.02 JU 0.00 0.00

Oct-1997 JU 0.02 0.02 JU 0.00 0.00 JU 0.00 0.00 JU 0.02 0.02 JU 0.00 0.00

May-2000 U 0.11 0.07 U -0.03 0.03 U 0.02 0.04 0.30 0.08 U 0.00 0.00

Mar.2001 U -0.21 0.10 U 0.00 0.00 0.09 0.05 0.70 0.13 0.09 0.05

Apr-2001 U -0.16 0.08 U -0.08 0.06 U -0.06 0.04 U 0.00 0.04 U 0.00 0.00

May-2001 U -0.03 0.07 U 0.00 0.00 U 0.00 0.00 U 0.04 0.03 U 0.00 0.00

Jun.2001 0.38 0.10 U 0.03 0.03 U 0.05 0.03 U 0.05 0.06 U 0.00 0.00

Jul-2001 0.13 0.08 U 0.04 0.04 U 0.00 0.00 0.59 0.18 U -0.09 0.07

Aug-2001 U .0.31 0.28 0.00 0.15 U 0.09 0.07 U 0.23 0.12 U 0.00 ON0Sep.2001 U -0.07 0.16 U -0.07 0.07 U 0.25 0.19 U 1.25 0.33 U 0.00 0.00

Oct-2001 U 0.21 0.10 U 0.00 0.00 U -0.02 0.02 0.07 0.04 U 0.02 0.02

Nov.2001 U 0.03 0.06 0.16 0.07 U 0.00 0.05 U 0.08 0.08 U 0.00 0.00

Mean 0.01 0.00 0.02 0.24 .0.00Std Dev 0.17 0.06 0.08 037 0.04

J Estimated ResultU - Below Lab Detection Limits

Produced by '# 7 '



.I.Sampling

Period

Jul-1997

Aug-1997Sep-1997Oct.1997Nov.1997Dec.1997Jan-1998Feb.1998Mar.1998Apr-i 998May-1998Jun-1998Jult1998Aug.1998Sep.1998Oct.1998Nov.1998Dec-I 9981St Qtr-1 9992nd Qrr 19993rd Qtr-19994th Qtr-1999Ist Qtr-20002nd Qtr-20003rd Qtr.20004th Qtr-2000

Gross AlphapCIA Error +/-

ND ND1.33 1.070.38 0.00.0.25 0.001.06 0.000.46 0.001.13 0.000.77 0.781.59 0.001.26 0.001.13 0.000.61 0.001.02 0.000.66 0.000.81 0.00

1.08 0.00

0.91 0.00

1.17 0.00

-0.33 0.003.00 7.000.00 7.00

2.00 8.001.00 8.00

2.00 8.002.00 6.003.00 7.00

Gross BetspCII Error+1-

ND ND8.20 0.000.04 0.008.90 0.00 B5.79 0.00-0.26 0.0012.55 0.00-0.55 0.002.14 0.009.34 0.001.20 0.00

13.18 0.00-7.22 0.008.82 6.85

12.51 0.004.95 0.006.08 0.007.79 0.00

6.25 0.007.00 4.001.00 4.003.00 4.003.00 4.006.00 4.006.00 4.004.00 5.00

Well 103AU-234

pCIan Error+/-0.92 0.382.52 0.801.79 0.23 JU0.36 0.08ND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND NDND ND

U-235pCIa Error +/-

. - I

0230.180.120.05NDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDND

0.230.180.06 JU0.03 JUNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDNDND

U-238 Tc-99pCM Error +/- pCI/I Error +/-0.57 0.31 JU 3.00 10.000.72 0.37 JU 1.00 10.000.00 0.04 JU -4.70 *7.200.02 0.02 JU -1.10 5.20ND ND JU -1.70' 6.10ND ND LU 1.60 6.10ND ND JU 9.50 6.50ND ND ND NDND ND ND NDND ND ND NDND ND ND NDND ND ND NDND ND ND NDND ND ND NDND ND ND NDND ND ND NDND ND ND NDND ND ND .NDND ND ND . NDND ND ND NDND ND ND NDND ND ND. NDND ND ND .NDND ND ND -NDND ND ND *NDND ND ND ND

B - Sample Result < 5 times activity detected in the blankJ - Estimated ResultU - Below Lab Detection LimitsND - No Data Producedby, $X,1C t/i 0/Z

Printed: 03(13fl002 NFS-EDMSPrinted: O3/13/2002 NFS-EDMS


Well 103ASampling Gross Alpha Gross Bets U-234 U-235 U-238 Tc-99

Period pCIA Error+l- pCIA Error+l- pCI/I Error+/- pCIn Error +l- pCIA Error+/- pCIA Error+l-

1st Qtr-2001 2.00 6.00 6.00 4.00 ND ND ND ND ND ND ND ND

2nd Qtr-2001 2.00 6.00 8.00 4.00 ND ND ND ND ND ND ND ND

3rd Qtr-2001 U 0.00 7.00 U 3.00 5.00 ND ND ND ND ND ND ND ND

4thQtr-2001 U l1.00 7.00 U 1.00 5.00 0.88 0.18 U 0.06 0.08 U 0.06 0.04 U 30.00 7.00

Mean 1.06 5.09 1.29 0.13 0.27 4.70

Std Dev 0.92 4.50 0.86 0.08 0.34 11.03

B - Sample Result < S times activity detected in the blankJ - Estimated ResultU- Below Lab Detection ULmits L AA/./)i.ND - No Data Produced by-. 7p. I,/ i-'V lA- )



Well 103ASampling Pu-238 Pu-239 Th-228 Th-230 Th-232

Period pCbl Error 4/- pCIJi Error +1- pCi/i Error+/- pCi/i Error+/1 pCi/i Error +1-

Jul-1997 0.00 0.13 0.00 0.00 0.00 0.10 0.07 0.07 0.07 0.07Aug.1997 JU 0.00 0.00 JU 0.10 0.10 LU 0.00 0.10 0.20 0.12 JU 0.00 0.00

Sep-1997 JU 0.00 0.00 IU 0.00 0.00 LU 0.02 0.02 LU 0.02 0.02 JU 0.00 0.00

Oct-1997 LU 0.06 0.04 JU 0.00 0.00 JU 0.00 0.02 JU 0.03 0.02 JU 0.00 0.00

4th Qtr.2001 U 0.00 0.12 0.20 0.10 U 0.00 0.03 0.07 0.04 U -0.02 0.02

Mean 0.01 0.06 0.00 0.08 0.01Std Dev 0.03 0.09 0.01 0.07 0.04

l - Estimated ResultU - Below Lab Detection Limits I

Produced by-. -0 tt - -fJ /g/

Printed: 03/13/2002 NiFS-EDMS


Well 28Sampling Gross Alpha Gross Beta U-234 U-23S U-238 Tc-99

Period pCI/I Error+l- pCiai Error+/- pCI/i Error+/- pCa Error+f- pCIaI Error+I- pCi/l Error+I-IstQtr-1998 21.10 3.00 16.38 8.29 22.36 0.68 1.46 0.13 5.41 0.27 ND ND

2nd Qtr.1998 48.56 4.59 50.23 8.52 26.72 0.79 1.21 0.14 6.19 0.33 78.39 10.88

Mean 34.83 33.31 24.54 1.33 5.80 78.39Std Dev 19.42 23.94 3.08 0.18 0.55 0.00

ND No Data

Produced by. , / JI ,/ g,

Printed: 0311412002 NFS-EDMS


Well 28Sampling Pu-238 Pu-239 Th-228 Th-230 Th-232

Period pCI/! Error+/- pClf Error +I. pCIA Error+/- pCI1 Error+/- pCI/I Error+/-

IstQtr- 1998 U -0.04 0.03 JU 0.02 0.02 JU 0.06 0.04 0.61 0.13 JU 0.06 0.04

2nd Qtr-I 998 JU -0.02 0.02 JU 0.00 0.00 0.20 0.05 0.28 0.06 JU 0.01 0.01

Mean -0.03 0.01 0.13 0.44 0.03

Std Dev 0.01 0.02 0.10 0.23 0.03

J Estimated ResultU - Below Lab Detection Limits P b i I { /

Produced by0. 3/A4200 lN(SED

Pninted: 03/14/2002 NFS-EDMS


21G-02-0087GOV-0 1-55-04

ACF-02-0063

Attachiment VIII.

Letteq from TDEC to T.S. Baer, NPDES Permit No. TNR050873 Nuclear Fuel Services Storm

Water Monitoring for Magnesium, dated December 2, 1999

ISN990216*.. GOV-05

,-.-- - .l :SNPDES. . T . H e 1NR050873

UEG 6 1999STATE OF TENNESSEE

DEPARTMENT OF ENVIRONMENT AND CONSERVATION

- L & C Annex, ;6 Floor401 Church Street

Nashville, Tennessee 37243-1534

DISTRIBUTION: SP 1I l(/1q9AMM BMM BULLETINBRD DJC

December 2, 1999 JEG KDH KDS NJN REG SVS REK

Mr. Thomas S. Baer, Ph.D. RL RPD TSBNuclear Fuel Services, Inc.1205 Banner Hill RoadErwin, Tennessee 37650

Re: NPDES Permit No. TNRO50873Nuclear Fuel ServicesStorm Water Monitoring for Magnesium

Dear Mr. Baer:

In response to your letter of February 18, 1999, we agree with your request, and grant that NFS is exempted frommagnesium sampling in the fourth year of the permit (year 2000).

It seems obvious that background magnesium concentrations in your area are much higher than the permit cutoffconcentration in our TMSP permit. The concentrations of magnesium you have found in your storm waterdischarges appear to be the result of background levels and not the result of your industrial activities.

Also, the magnesium cutoff concentration of 0.0636 mg/I seems unnecessarily low, and we are consideringmodifying the TMSP to change this number. In the meantime, you are exempted from monitoring magnesiumfor the the year 2000.

Please keep a copy of this letter in your files as record ofourdecision. If you have anyquestions about thismatter, you may call Robert Haley at 615-532-0669, ore-mail at rs .t

Sincerely,

~ay.SQualls, P.E.

Manager, Permit SectionDivision of Water Pollution Control

Cc: Environmental Assistance Center-Johnson CityCentral Office Storm Water File 0873

Rlheoznprqrktr 91 q124 ,uwcar tucls masnsan,

nuclear fuel services, inc. p o. box 337, ms 123 (423) 743 ... · restricted to collecting the...

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