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{{#Wiki_filter:U.S. Nuclear Regulatory CommissionTechnical Evaluation for the U.S. Department of Energy West Valley Waste Incidental to Reprocessing Determination DeterminationNishka Devaser, Leah Parks (NRC)AHi(ND)Amy Hixon (Notre Dame)Thomas Crandall (DOE)ANS2013WinterMeetingWashington DCANS 2013 Winter Meeting, Washington
, DC(not presented)
Overview*WestValleyOperations
*West Valley Operations*Waste Incidental to Reprocessing*NRC Review Approach*Conclusions 2
West Valley Site
===Background===
Background*3,340-acre site located approximately fff30 miles south o f Buffalo, NY*Owned by the New York State Energy Research and Development Authority (NYSERDA)onbehalfoftheStateof (NYSERDA) on behalf of the State of New York*Established in the 1960s as a nuclear complex that would include spent lflidtnuclear fuel reprocess ing and waste disposal facilities *Reprocessed spent nuclear fuel, recoveringapproximately620metric recovering approximately 620 metric tons of uranium and approximately 1,926 kilograms of uranium *Used the PUREX (plutonium uranium tti)dTHOREXThe WVDP Area of the Center in 2006 (WVDP photo) extraction) and THOREX processes 3
West Valley OperationsProcessingofHLW Processing of HLWPretreatmentProcessVitrificationProcess Pretreatment Process*In 1988, DOE constructed the integrated radioactive waste tttttVitrification Process*The high activity waste was vitrified into borosilicate glass.
treatment system to remove most of the radioactivity in the liquid supernatant from the undergroundHLWtanks underground HLW tanks, concentrate the liquid, and blend it with cement. 
*Thisseparatedthelowactivity
*This separated the low activity stream from the high activity
stream. VitrificationProcessFloDiagram(forinformationnotto Vitrification Process Flow Diagram (for information
, not to scale)4 West Valley OperationsConcentratorFeedMakeupTankandMelterFeedHoldTank Concentrator Feed Makeup Tank and Melter Feed Hold Tank*Vessels are used in the vitrification process to prepare and temporarily store, respectively, slurry consisting of ttdHLWdlpre-treated HLW and glass formers that was supplied to the vitrification melter. Hbdtidth*Have been determined to have radionuclide concentrations that do not exceed limits for ClassCLLWandpackagedfor Class C LLW, and packaged for shipment to an offsite LLW disposal facility.The Concentrator Feed Makeup Tank (left) and the Melter Feed Hold Tank Installed in the Vitrification Cell (WVDP photo) 5 West Valley OperationsResidualInventory Residual InventoryInventory as Percentage of the §61.55 WtClifitiLiit*Thevesselscontainboth Waste Classification LimitsThe vessels contain both short-lived fission products, as well as long-lived transuranicisotopesVesselNuclideTable 1 PercentTable 2 PercentCs137193%transuranic isotopes. *The predominant radionuclides are Cs-137 CFMTCs-1371.93%Am-2414.34%Total6.50%2.00%
and Am-241. *Inventories are well within thelimitofthe
§6155Table MFHTCs-1371.58%Am-2414.01%Total6.30%1.60%
the limit of the §61.55 Table 1 and Table 2 Waste
Classification Limits.
6 Waste Incidental to ReprocessingDOEWasteDeterminationProcess DOE Waste Determination Process*The Waste Incidental to Re processing (WIR) Evaluation assesses whether the pg()vitrification components meet the WIR criteria of DOE Order 435.1* to dispose of the components at a facility offsite as LLW-such as the Nevada National Security Site (NNSS, formerly the Nevada Test Site) in Nevada ortheWasteControlSpecialists(WCS)facilityinTexasfordisposal or the Waste Control Specialists (WCS) facility in Texas for disposal.*DOE made the final determination after consideration of NRC, state, and public comments on the WIR Evaluation
*WestValleyoriginallyoperatedunderanNRClicensetothe StateofNewYorkWest Valley originally operated under an NRC license to the State of New York, (currently in abeyance). Under the West Valley Demonstration Project (WVDP) Act, DOE will manage the WVDP until the NYSERDA license is reinstated at the end of the WVDP.*NRC serves as a consultant to DOE with respect to DOE's incidental WIR Determinations*DOE Order 435.1 is the DOE directive under its Atomic Energy Act authorities for the management of radioactive waste.
7 Waste Incidental to Reprocessing CriteriainDOEManual43511Chapter2(B)(2
)Criteria in DOE Manual 435.1-1, Chapter 2 (B)(2)Waste[determinedtobe]incidental toreprocessing[][w]ill beWaste [determined to be] incidental to reprocessing
[...] [w]ill be managed as LLW and meet the following criteria:1.Have been processed, or will be processed, to remove key radionuclides to themaximumextentthatistechnicallyandeconomicallypractical;and the maximum extent that is technically and economically practical; and2.Will be managed to meet safety requirements comparable to the performance objectives set out in 10 CFR Part 61, SubpartC, Performance Objectives;andObjectives
; and 3.Are to be managed, pursuant to DOE's authority under the Atomic Energy Act of 1954, as amended provided the waste will be incorporated in a solid physicalformataconcentrationthatdoesnotexceedtheapplicable physical form at a concentration that does not exceed the applicable concentration limits for Class C LLW as set out in 10 CFR 61.55, Waste Classification; or will meet alternative requirements for waste classification and characterization as DOE may authorize.
8 Waste Incidental to ReprocessingNRCReviewProcess NRC Review Process*Reviewfortechnicaladequacytodemonstratecriteriain435.1 Review for technical adequacy to demonstrate criteria in 435.1 are met applying relevant review procedures in NUREG1854*.*NRC review included:-Assessmentastowhethermethodologyhassoundtechnicalassumptions, Assessment as to whether methodology has sound technical assumptions, analysis, projections, and conclusions and -The following general topics as they relate to the criteria in 435.1*Waste characterization, form stability, classification; *Removal of radionuclides;Otilditittid
*Operational radiation protection; and*Quality assurance.*NRC review did not include
:-The long-term performance or long-term stability of the disposal site
-Sufficiency of the waste acceptance criteria for the disposal site-Sufficiency of the performance assessment for the disposal site, including adequacy of the estimated dose values-Other matters covered by other sections of 435.1 9*The NRC publication NUREG-1854, "NRC Staff Guidance for Activities Related to U.S. Department of Energy Waste Determinations, Draft Final for Interim Use "dated August 2007 Waste Incidental to ReprocessingNRCReview ProcessNUREG1854 NRC Review Process -NUREG 1854Review To picNUREG-1854 Cha pter435.1 Criterion ppCriterionWaste characterizationChapter 3:  Radionuclide Removal and Concentration Limits1Waste form stabilityChapter 7:  Site Stability, Waste Stability, and Facility Stability2, 3Waste Cht3RdilidRldCttiLiit 3classification Chapter 3:  Radionuclide Removal and Concentration Limits3Removal of radionuclidesChapter 3:  Radionuclide Removal and Concentration Limits3 Operational radiation protectionChapter 6:  Protection of Individuals During Operations2 10 Waste Incidental to ReprocessingRemovaloftheKeyRadionuclides Removal of the Key Radionuclides*DOE full y evaluated the yfollowing cleaning options for technical and economicalpracticality:
economical practicality:
*flushing vessel internals with water using high-pressure
spray; *mechanicalremoval
*mechanical removal through ball milling; and *chemical 11decontamination.Evacuated Canister Removing Residual Glass from the Vitrification Melter (DOE, 2011 Melter WD)
Waste Incidental to ReprocessingRemovaloftheKeyRadionuclides Removal of the Key Radionuclides Condition CFMT Remaining Inventory (Ci)
CFMT Decontamination FactorMFHT Remaining Inventory (Ci)
MFHT Decontamination FactorBeforeFlushing630NA540NABefore Flushing630NA540NAAfter All Flushes95.36.697.15.6The activity in each vessel before flushing began was estimated in the following manner: a)the residual material (dried slurry) coating observed on the vessel interior surfaces before flushing was assumed to average 0.64-cm (0.250-inch) thickness over the upperonethirdofthevesselsbasedonpreflushvisualinspectionresults;and upper one-third of the vessels, based on pre-flush visual inspection results; and b)the Cs-137 concentration in this material was assumed to be a representative, decay corrected concentration of 5.0x10 3Ci/cm3.12 Waste Incidental to ReprocessingRemovaloftheKeyRadionuclides Removal of the Key Radionuclides*DOE evaluated a reasonable range *Additional radionuclide removal of technologies that included methods to remove volumes of
waste;*DOEhasappropriatelyconsideredwould have negligible impact on the long-term dose in comparison to
the social costs.
*DOE has appropriately considered the impacts of uncertainty in the inventory as it relates to the
radionuclide removal demonstration,*Ceasing removal activities for the MFHT and CFMT after the direct andindirectflushingactivitiesthatTheConcentratorFeedMakeupTanktheMelterFeedHoldTank and indirect flushing activities that were carried out was reasonable.*Further radionuclide removal would not significantly reduce worker The Concentrator Feed Makeup Tank, the Melter Feed Hold Tank , and the Melter in preparation for shipment (WVDP photo) .otsgcatyeduceoedoses at the disposal facility 13 Waste Incidental to ReprocessingRequirementsComparableto10CFRPart61 Requirements Comparable to 10 CFR Part 61*TheNRCconsiderstheDOE
'sconclusionstobeadequateand The NRC considers the DOEs conclusions to be adequate and reasonable such that the DOE can meet the NRC-reviewed portions of Criterion 2 of DOE Manual 435.1-1 related to safety requirementsassociatedwiththePerformanceObjectivesof requirements associated with the Performance Objectives of 10CFR61, Subpart C. This is based on the following specific topical conclusions. 
*TheNRCstaffagreeswithDOE
'sassessmentthattheresidual
*The NRC staff agrees with DOEs assessment that the residual wastes remaining in the CFMT and MFHT meet the applicable safety requirements for protection of individuals during operations operations
.  *As specified in the Interagency Agreement, the NRC staff's review focuses on waste form stability and does not include a review of the disposal site stability.
14 Waste Incidental to ReprocessingRequirementsComparableto10CFRPart61 Requirements Comparable to 10 CFR Part 61Crosswalk TopicsDOENRCTexas RuleAnnual Air Emission Limit for Individual Member10mrem10mrem10mremAnnual TEDE for Adult Workers5rem5rem5remAny Individual Organ or Tissue Annual Dose Limit for Adult Workers50rem50rem50remAnnual Dose Limit to the Lens of the E ye for Adult 151515yWorkers15rem15rem15remAnnual Dose Limit to the Skin of the Whole Body and to the Skin of the Extremities for Adult Workers50rem50rem50remLimitonSolbleUranimIntake 24mg/week10mg/week10mg/weekLimit on Soluble Uranium Intake2.4mg/week10mg/week10mg/weekDose Equivalent to Embryo/Fetus0.5rem0.5rem0.5remDose Limit for Individual Member of the Public (Total Annual Dose)100mrem100mrem100mremDose Limit for Individual Members of the Public (Dose Rates inUnrestricted Areas)0.05mrem/hr2mrem/hr2mrem/hrDose Limits for Members of the Public with Access to Controlled Areas0.1rem0.1rem0.1remAsLowAsReasonablyAchievable
§8352§201003§3362As Low As Reasonably Achievable
§835.2§20.1003§336.215 Waste Incidental to ReprocessingNottoExceedClassCConcentrationLimits Not to Exceed Class C Concentration Limits*DOEaveragedovertheweightofthe
*DOE averaged over the weight of the vessels and the volume not including voids. CffO'*The NRC staff concludes that the D OE's assessment that the CFMT and MFHT is ClCidititith Class C, considering uncertainty in the volume of the vessels and uncertainty in the ittitthithill inventory estimates therein, technically sufficient.
16 Waste Incidental to ReprocessingNottoExceedClassCConcentrationLimits Not to Exceed Class C Concentration LimitsCFMTActivityClass C Limit CFMT CttiPercentMFHTActivityClass C Limit MFHT CttiPercentNuclideyConcentration(Ci)(Ci/m 3)(nCi/g)(Ci/m 3)(nCi/g)Table 1Table 2 C-14NA8K-40NAMn-54NACo-600.00410.00173 yConcentration(Ci)(Ci/m 3)(nCi/g)(Ci/m 3)(nCi/g)Table 1Table 2 0.00039880.0002970.004%
0.001540.001150.001670.001250.001580.00118Ni-63NA700Sr-903.97,0001.050.052%Zr-95NATc-990.001830.00390.060%
Cs-137954,60089.11.936%Eu-1540.0560.0483 0.01897000.01410.002%
5.347,0003.990.057%
0.03720.02780.00083430.0006220.021%
97.14,60072.51.575%
0.0318Np-2370.0000561000.007810.007%Pu-2380.00691000.6080.809%Pu-2390.00151000.1640.176%Pu-2400.00151000.1250.176%Pu-2410.0143,5001.810.047%Pu-242NA1000.00007261000.006720.007%
0.009191000.8510.851%
0.002281000.2110.211%
0.001741000.1610.161%
0.05883,5005.440.156%
NA100Am-2410.0371002.914.338%Am-242mNA100Am-2430.000331000.02990.039%
Cm-2420.0003920,0000.01150.000%
Cm-2430.00321000.01820.375%
Cm-2440.00321000.4710.375%
0.04331004.014.009%
NA1000.0003931000.03640.036%
0.00034220,0000.03170.000%
0.0002841000.02630.026%
0.007361000.6810.681%
Cm-245NA100Sum of Fractions6.5%2.0%NA100Sum of Fractions6.3%1.6%
17 Conclusions
*OnFebruary22013theDirectoroftheWestValley On February 2, 2013 the Director of the West Valley Demonstration Project (WVDP) signed the WIR Determination for the WVDP CFMT and MFHT.  *Accordingl y, pursuant to Section II.B of DOE Manual 435.1-1, Radioactive Waste Management Manual, the CFMT and the MFHT are not HLW and may be disposed of as LLW either the Nevada National Security Site Area 5 Radioactive Waste Management Site or the Waste Control Specialists (WCS) radioactive waste disposal facility in Texas.*DOE is considering the WCS Site in Texas for the disposal site for the CFMT and MFHT.
18 Backup Slide 1 19 Backup Slide 2RequirementsComparableto10CFRPart61 Requirements Comparable to 10 CFR Part 61Crosswalk TopicsDOENRCTX (Texas Rule)Annual Air Emission Limit for Individual MemberDOE Order5400.5 10mrem§20.1101(d) 10mrem§336.30410mrem10mrem10mrem10mremAnnual TEDE for Adult Workers
§835.202(a)(1)5rem§20.1201(a)5rem§336.3055remAny Individual Organ or Tissue Annual Dose Limit for Adult Workers
§835.202(a)(2)50rem§20.1201(a)50rem§336.30550remAnnual Dose Limit to the Lens of the E ye for Adult
§835.202(a)(3)§20.1201(a)§336.305yWorkers§()()15rem§()15rem§15remAnnual Dose Limit to the Skin of the Whole Body and to the Skin of the Extremities for Adult Workers
§835.202(a)(4)50rem§20.1201(a)50rem§336.30550remLimit on Soluble Uranium IntakeDOE Order440.1A2.4mg/week
§20.1201(e)10mg/week
§336.30510mg/weekDose Equivalent to Embryo/Fetus
§835.206(a)0.5rem§20.1208(a)0.5rem§336.3120.5remDose Limit for Individual Member of the Public (Total Annual Dose)DOE Order5400.5100mrem§20.1301(a)100mrem§336.313100mremDose Limit for Individual Members of the Public (Dose
§835.6020005mSv/hr§20.1301(a)§336.313Rates inUnrestricted Areas) 0.005mSv/hr (0.05mrem/hr)2mrem/hr2mrem/hrDose Limits for Members of the Public with Access to Controlled Areas
§835.2080.1rem§20.1301(b)0.1rem§336.3130.1remAs Low As Reasonably Achievable§835.2§20.1003§336.2 20}}

Revision as of 12:32, 3 July 2018

NRC Presentation - U.S. Nuclear Regulatory Commission Technical Evaluation for the U.S. Department of Energy West Valley Waste Incidental to Reprocessing Determination
ML13337A199
Person / Time
Site: West Valley Demonstration Project, P00M-032
Issue date: 12/03/2013
From: Crandall T, Devaser N J, Parks L L
NRC/FSME/DWMEP/EPPAD/PAB, Univ of Notre Dame, US Dept of Energy (DOE)
To:
References
Download: ML13337A199 (20)
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U.S. Nuclear Regulatory CommissionTechnical Evaluation for the U.S. Department of Energy West Valley Waste Incidental to Reprocessing Determination DeterminationNishka Devaser, Leah Parks (NRC)AHi(ND)Amy Hixon (Notre Dame)Thomas Crandall (DOE)ANS2013WinterMeetingWashington DCANS 2013 Winter Meeting, Washington

, DC(not presented)

Overview*WestValleyOperations

  • West Valley Operations*Waste Incidental to Reprocessing*NRC Review Approach*Conclusions 2

West Valley Site

Background

Background*3,340-acre site located approximately fff30 miles south o f Buffalo, NY*Owned by the New York State Energy Research and Development Authority (NYSERDA)onbehalfoftheStateof (NYSERDA) on behalf of the State of New York*Established in the 1960s as a nuclear complex that would include spent lflidtnuclear fuel reprocess ing and waste disposal facilities *Reprocessed spent nuclear fuel, recoveringapproximately620metric recovering approximately 620 metric tons of uranium and approximately 1,926 kilograms of uranium *Used the PUREX (plutonium uranium tti)dTHOREXThe WVDP Area of the Center in 2006 (WVDP photo) extraction) and THOREX processes 3

West Valley OperationsProcessingofHLW Processing of HLWPretreatmentProcessVitrificationProcess Pretreatment Process*In 1988, DOE constructed the integrated radioactive waste tttttVitrification Process*The high activity waste was vitrified into borosilicate glass.

treatment system to remove most of the radioactivity in the liquid supernatant from the undergroundHLWtanks underground HLW tanks, concentrate the liquid, and blend it with cement.

  • Thisseparatedthelowactivity
  • This separated the low activity stream from the high activity

stream. VitrificationProcessFloDiagram(forinformationnotto Vitrification Process Flow Diagram (for information

, not to scale)4 West Valley OperationsConcentratorFeedMakeupTankandMelterFeedHoldTank Concentrator Feed Makeup Tank and Melter Feed Hold Tank*Vessels are used in the vitrification process to prepare and temporarily store, respectively, slurry consisting of ttdHLWdlpre-treated HLW and glass formers that was supplied to the vitrification melter. Hbdtidth*Have been determined to have radionuclide concentrations that do not exceed limits for ClassCLLWandpackagedfor Class C LLW, and packaged for shipment to an offsite LLW disposal facility.The Concentrator Feed Makeup Tank (left) and the Melter Feed Hold Tank Installed in the Vitrification Cell (WVDP photo) 5 West Valley OperationsResidualInventory Residual InventoryInventory as Percentage of the §61.55 WtClifitiLiit*Thevesselscontainboth Waste Classification LimitsThe vessels contain both short-lived fission products, as well as long-lived transuranicisotopesVesselNuclideTable 1 PercentTable 2 PercentCs137193%transuranic isotopes. *The predominant radionuclides are Cs-137 CFMTCs-1371.93%Am-2414.34%Total6.50%2.00%

and Am-241. *Inventories are well within thelimitofthe

§6155Table MFHTCs-1371.58%Am-2414.01%Total6.30%1.60%

the limit of the §61.55 Table 1 and Table 2 Waste

Classification Limits.

6 Waste Incidental to ReprocessingDOEWasteDeterminationProcess DOE Waste Determination Process*The Waste Incidental to Re processing (WIR) Evaluation assesses whether the pg()vitrification components meet the WIR criteria of DOE Order 435.1* to dispose of the components at a facility offsite as LLW-such as the Nevada National Security Site (NNSS, formerly the Nevada Test Site) in Nevada ortheWasteControlSpecialists(WCS)facilityinTexasfordisposal or the Waste Control Specialists (WCS) facility in Texas for disposal.*DOE made the final determination after consideration of NRC, state, and public comments on the WIR Evaluation

  • WestValleyoriginallyoperatedunderanNRClicensetothe StateofNewYorkWest Valley originally operated under an NRC license to the State of New York, (currently in abeyance). Under the West Valley Demonstration Project (WVDP) Act, DOE will manage the WVDP until the NYSERDA license is reinstated at the end of the WVDP.*NRC serves as a consultant to DOE with respect to DOE's incidental WIR Determinations*DOE Order 435.1 is the DOE directive under its Atomic Energy Act authorities for the management of radioactive waste.

7 Waste Incidental to Reprocessing CriteriainDOEManual43511Chapter2(B)(2

)Criteria in DOE Manual 435.1-1, Chapter 2 (B)(2)Waste[determinedtobe]incidental toreprocessing[][w]ill beWaste [determined to be] incidental to reprocessing

[...] [w]ill be managed as LLW and meet the following criteria:1.Have been processed, or will be processed, to remove key radionuclides to themaximumextentthatistechnicallyandeconomicallypractical;and the maximum extent that is technically and economically practical; and2.Will be managed to meet safety requirements comparable to the performance objectives set out in 10 CFR Part 61, SubpartC, Performance Objectives;andObjectives

and 3.Are to be managed, pursuant to DOE's authority under the Atomic Energy Act of 1954, as amended provided the waste will be incorporated in a solid physicalformataconcentrationthatdoesnotexceedtheapplicable physical form at a concentration that does not exceed the applicable concentration limits for Class C LLW as set out in 10 CFR 61.55, Waste Classification; or will meet alternative requirements for waste classification and characterization as DOE may authorize.

8 Waste Incidental to ReprocessingNRCReviewProcess NRC Review Process*Reviewfortechnicaladequacytodemonstratecriteriain435.1 Review for technical adequacy to demonstrate criteria in 435.1 are met applying relevant review procedures in NUREG1854*.*NRC review included:-Assessmentastowhethermethodologyhassoundtechnicalassumptions, Assessment as to whether methodology has sound technical assumptions, analysis, projections, and conclusions and -The following general topics as they relate to the criteria in 435.1*Waste characterization, form stability, classification; *Removal of radionuclides;Otilditittid

  • Operational radiation protection; and*Quality assurance.*NRC review did not include
-The long-term performance or long-term stability of the disposal site

-Sufficiency of the waste acceptance criteria for the disposal site-Sufficiency of the performance assessment for the disposal site, including adequacy of the estimated dose values-Other matters covered by other sections of 435.1 9*The NRC publication NUREG-1854, "NRC Staff Guidance for Activities Related to U.S. Department of Energy Waste Determinations, Draft Final for Interim Use "dated August 2007 Waste Incidental to ReprocessingNRCReview ProcessNUREG1854 NRC Review Process -NUREG 1854Review To picNUREG-1854 Cha pter435.1 Criterion ppCriterionWaste characterizationChapter 3: Radionuclide Removal and Concentration Limits1Waste form stabilityChapter 7: Site Stability, Waste Stability, and Facility Stability2, 3Waste Cht3RdilidRldCttiLiit 3classification Chapter 3: Radionuclide Removal and Concentration Limits3Removal of radionuclidesChapter 3: Radionuclide Removal and Concentration Limits3 Operational radiation protectionChapter 6: Protection of Individuals During Operations2 10 Waste Incidental to ReprocessingRemovaloftheKeyRadionuclides Removal of the Key Radionuclides*DOE full y evaluated the yfollowing cleaning options for technical and economicalpracticality:

economical practicality:

  • flushing vessel internals with water using high-pressure

spray; *mechanicalremoval

  • mechanical removal through ball milling; and *chemical 11decontamination.Evacuated Canister Removing Residual Glass from the Vitrification Melter (DOE, 2011 Melter WD)

Waste Incidental to ReprocessingRemovaloftheKeyRadionuclides Removal of the Key Radionuclides Condition CFMT Remaining Inventory (Ci)

CFMT Decontamination FactorMFHT Remaining Inventory (Ci)

MFHT Decontamination FactorBeforeFlushing630NA540NABefore Flushing630NA540NAAfter All Flushes95.36.697.15.6The activity in each vessel before flushing began was estimated in the following manner: a)the residual material (dried slurry) coating observed on the vessel interior surfaces before flushing was assumed to average 0.64-cm (0.250-inch) thickness over the upperonethirdofthevesselsbasedonpreflushvisualinspectionresults;and upper one-third of the vessels, based on pre-flush visual inspection results; and b)the Cs-137 concentration in this material was assumed to be a representative, decay corrected concentration of 5.0x10 3Ci/cm3.12 Waste Incidental to ReprocessingRemovaloftheKeyRadionuclides Removal of the Key Radionuclides*DOE evaluated a reasonable range *Additional radionuclide removal of technologies that included methods to remove volumes of

waste;*DOEhasappropriatelyconsideredwould have negligible impact on the long-term dose in comparison to

the social costs.

  • DOE has appropriately considered the impacts of uncertainty in the inventory as it relates to the

radionuclide removal demonstration,*Ceasing removal activities for the MFHT and CFMT after the direct andindirectflushingactivitiesthatTheConcentratorFeedMakeupTanktheMelterFeedHoldTank and indirect flushing activities that were carried out was reasonable.*Further radionuclide removal would not significantly reduce worker The Concentrator Feed Makeup Tank, the Melter Feed Hold Tank , and the Melter in preparation for shipment (WVDP photo) .otsgcatyeduceoedoses at the disposal facility 13 Waste Incidental to ReprocessingRequirementsComparableto10CFRPart61 Requirements Comparable to 10 CFR Part 61*TheNRCconsiderstheDOE

'sconclusionstobeadequateand The NRC considers the DOEs conclusions to be adequate and reasonable such that the DOE can meet the NRC-reviewed portions of Criterion 2 of DOE Manual 435.1-1 related to safety requirementsassociatedwiththePerformanceObjectivesof requirements associated with the Performance Objectives of 10CFR61, Subpart C. This is based on the following specific topical conclusions.

  • TheNRCstaffagreeswithDOE

'sassessmentthattheresidual

  • The NRC staff agrees with DOEs assessment that the residual wastes remaining in the CFMT and MFHT meet the applicable safety requirements for protection of individuals during operations operations

. *As specified in the Interagency Agreement, the NRC staff's review focuses on waste form stability and does not include a review of the disposal site stability.

14 Waste Incidental to ReprocessingRequirementsComparableto10CFRPart61 Requirements Comparable to 10 CFR Part 61Crosswalk TopicsDOENRCTexas RuleAnnual Air Emission Limit for Individual Member10mrem10mrem10mremAnnual TEDE for Adult Workers5rem5rem5remAny Individual Organ or Tissue Annual Dose Limit for Adult Workers50rem50rem50remAnnual Dose Limit to the Lens of the E ye for Adult 151515yWorkers15rem15rem15remAnnual Dose Limit to the Skin of the Whole Body and to the Skin of the Extremities for Adult Workers50rem50rem50remLimitonSolbleUranimIntake 24mg/week10mg/week10mg/weekLimit on Soluble Uranium Intake2.4mg/week10mg/week10mg/weekDose Equivalent to Embryo/Fetus0.5rem0.5rem0.5remDose Limit for Individual Member of the Public (Total Annual Dose)100mrem100mrem100mremDose Limit for Individual Members of the Public (Dose Rates inUnrestricted Areas)0.05mrem/hr2mrem/hr2mrem/hrDose Limits for Members of the Public with Access to Controlled Areas0.1rem0.1rem0.1remAsLowAsReasonablyAchievable

§8352§201003§3362As Low As Reasonably Achievable

§835.2§20.1003§336.215 Waste Incidental to ReprocessingNottoExceedClassCConcentrationLimits Not to Exceed Class C Concentration Limits*DOEaveragedovertheweightofthe

  • DOE averaged over the weight of the vessels and the volume not including voids. CffO'*The NRC staff concludes that the D OE's assessment that the CFMT and MFHT is ClCidititith Class C, considering uncertainty in the volume of the vessels and uncertainty in the ittitthithill inventory estimates therein, technically sufficient.

16 Waste Incidental to ReprocessingNottoExceedClassCConcentrationLimits Not to Exceed Class C Concentration LimitsCFMTActivityClass C Limit CFMT CttiPercentMFHTActivityClass C Limit MFHT CttiPercentNuclideyConcentration(Ci)(Ci/m 3)(nCi/g)(Ci/m 3)(nCi/g)Table 1Table 2 C-14NA8K-40NAMn-54NACo-600.00410.00173 yConcentration(Ci)(Ci/m 3)(nCi/g)(Ci/m 3)(nCi/g)Table 1Table 2 0.00039880.0002970.004%

0.001540.001150.001670.001250.001580.00118Ni-63NA700Sr-903.97,0001.050.052%Zr-95NATc-990.001830.00390.060%

Cs-137954,60089.11.936%Eu-1540.0560.0483 0.01897000.01410.002%

5.347,0003.990.057%

0.03720.02780.00083430.0006220.021%

97.14,60072.51.575%

0.0318Np-2370.0000561000.007810.007%Pu-2380.00691000.6080.809%Pu-2390.00151000.1640.176%Pu-2400.00151000.1250.176%Pu-2410.0143,5001.810.047%Pu-242NA1000.00007261000.006720.007%

0.009191000.8510.851%

0.002281000.2110.211%

0.001741000.1610.161%

0.05883,5005.440.156%

NA100Am-2410.0371002.914.338%Am-242mNA100Am-2430.000331000.02990.039%

Cm-2420.0003920,0000.01150.000%

Cm-2430.00321000.01820.375%

Cm-2440.00321000.4710.375%

0.04331004.014.009%

NA1000.0003931000.03640.036%

0.00034220,0000.03170.000%

0.0002841000.02630.026%

0.007361000.6810.681%

Cm-245NA100Sum of Fractions6.5%2.0%NA100Sum of Fractions6.3%1.6%

17 Conclusions

  • OnFebruary22013theDirectoroftheWestValley On February 2, 2013 the Director of the West Valley Demonstration Project (WVDP) signed the WIR Determination for the WVDP CFMT and MFHT. *Accordingl y, pursuant to Section II.B of DOE Manual 435.1-1, Radioactive Waste Management Manual, the CFMT and the MFHT are not HLW and may be disposed of as LLW either the Nevada National Security Site Area 5 Radioactive Waste Management Site or the Waste Control Specialists (WCS) radioactive waste disposal facility in Texas.*DOE is considering the WCS Site in Texas for the disposal site for the CFMT and MFHT.

18 Backup Slide 1 19 Backup Slide 2RequirementsComparableto10CFRPart61 Requirements Comparable to 10 CFR Part 61Crosswalk TopicsDOENRCTX (Texas Rule)Annual Air Emission Limit for Individual MemberDOE Order5400.5 10mrem§20.1101(d) 10mrem§336.30410mrem10mrem10mrem10mremAnnual TEDE for Adult Workers

§835.202(a)(1)5rem§20.1201(a)5rem§336.3055remAny Individual Organ or Tissue Annual Dose Limit for Adult Workers

§835.202(a)(2)50rem§20.1201(a)50rem§336.30550remAnnual Dose Limit to the Lens of the E ye for Adult

§835.202(a)(3)§20.1201(a)§336.305yWorkers§()()15rem§()15rem§15remAnnual Dose Limit to the Skin of the Whole Body and to the Skin of the Extremities for Adult Workers

§835.202(a)(4)50rem§20.1201(a)50rem§336.30550remLimit on Soluble Uranium IntakeDOE Order440.1A2.4mg/week

§20.1201(e)10mg/week

§336.30510mg/weekDose Equivalent to Embryo/Fetus

§835.206(a)0.5rem§20.1208(a)0.5rem§336.3120.5remDose Limit for Individual Member of the Public (Total Annual Dose)DOE Order5400.5100mrem§20.1301(a)100mrem§336.313100mremDose Limit for Individual Members of the Public (Dose

§835.6020005mSv/hr§20.1301(a)§336.313Rates inUnrestricted Areas) 0.005mSv/hr (0.05mrem/hr)2mrem/hr2mrem/hrDose Limits for Members of the Public with Access to Controlled Areas

§835.2080.1rem§20.1301(b)0.1rem§336.3130.1remAs Low As Reasonably Achievable§835.2§20.1003§336.2 20

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