Text

2 to EN-RW-104, Scaling Factors.
	ML16132A506
Person / Time
Site:	Waterford
Issue date:	04/02/2015
From:	Miller R; Entergy Operations
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML16132A496	List: ML16132A494; ML16132A506; ML16132A507; ML16132A508; ML16132A509; ML16132A510; W3F1-2016-0038, UNT-005-014, Rev. 306, Offsite Dose Calculation Manual.;
References
	W3F1-2016-0038 EN-RW-104, Rev 12
	Download: ML16132A506 (18)
	v • d • e

NUCLEARMANAGEMENTMANUAL N ON-QUALITY RELATEDEN-RW-104REV. 12 INFORMATIONAL U SEPage 1 of 18Scaling FactorsProcedure Contains NMM ECH eB REFLIBForms: YES NOProcedure Revision Type: New NO N-EditorialEditorial TCCancellationHQN EffectiveDateProcedure Owner:Title: Site:Roy MillerManager, RPGGNSGovernance Owner:Title: Site:David MooreManager, Fleet RPHQN4/2/15 SiteSite Procedure ChampionTitle ANODonnie MarvelManager, RP BRPN/AN/A CNS Bob BeilkeManager, RPGGNSRoy MillerManager, RP IPECFrank MitchellManager, RP JAFRobert HeathManager, RP PLPDoug WatkinsManager, RP PNPSAlan ZelieManager, RP RBSBrad ColeManager, RP W3Daniel FreyManager, RPHQNDavid MooreManager, Fleet RPFor site implementation dates see ECH eB REFLIB using site tree view (Navigation panel).Site and NMM Procedures Canceled or Superseded By This Revision NoneProcess Applicability Exclusion:All Sites:Specific Sites: ANO BRP CNS GGNS IPEC JAF PLP PNPS RBS W3Change StatementEditorial revision to remove reference to specific version of RADMAN software per CR-HQN-2015-00069 Removed VY from coversheet Changed title of section 5.6 as recommended by CR-HQN-2015-00069 Reworded steps 5.3[2](b) and 5.4[3](b) to align with change being made to title of section 5.6Associated PRHQN #:

2015-00080Procedure Writer:Ron SchwartzContains Proprietary Information:

YES NO__________________________________________________________________________

NUCLEARMANAGEMENTMANUAL N ON-QUALITY RELATEDEN-RW-104REV. 12 INFORMATIONAL U SEPage 2 of 18Scaling FactorsTABLE OF CONTENTSSection Title Page1.0 PURPOSE

32.0REFERENCES

.................................................................................. 33.0DEFINITIONS .................................................................................... 34.0RESPONSIBILITIES.......................................................................... 45.0DETAILS 45.1PRECAUTIONSANDLIMITATIONS ................................................. 45.2GENERALREQUIREMENTS ............................................................ 55.3INDEPENDENTLABORATORYANALYSIS ..................................... 75.4WASTESTREAMSAMPLEDATASCREENING ............................... 85.5WASTESTREAMSAMPLEDATAEVALUATIONUSINGRADMANVERSION8.2..................................................................................... 85.6WASTESTREAMSAMPLEDATAEVALUATIONUSINGCURRENTVERSIONOFRADMAN .................................................................. 106.0INTERFACES .................................................................................. 127.0RECORDS 128.0SITESPECIFICCOMMITMENTS .................................................... 129.0ATTACHMENTS ............................................................................. 12 ATTACHMENT9.110CFRPART61WASTE STREAM SAMPLE SCREENING AND EVALUATION ..................................................................................... 13 ATTACHMENT9.2QUARTERLY TRENDING DOCUMENTATION ........................... 18__________________________________________________________________________

NUCLEARMANAGEMENTMANUAL N ON-QUALITY RELATEDEN-RW-104REV. 12 INFORMATIONAL U SEPage 3 of 18Scaling Factors 1.0 PURPOSEThis procedure provides instruction for developing scaling factors for difficult to measureradionuclides, including waste stream identification, waste stream sampling frequency,independent laboratory waste stream sample screening and evaluation, and independentlaboratory waste stream sample disposition.

2.0 REFERENCES

[1] Title 10 of the Code of Federal Regulations, Part 61[2] Title 10 of the Code of Federal Regulations, Part 20 Appendix G[3] Title 49 of the Code of Federal Regulations, Parts 107, 171-177[4] Branch Technical Position on Radioactive Waste Classification, 11 May 1983[5] Final Branch Technical Position on Concentration Averaging and Encapsulation,Revision in Part to Waste Classification Technical Position, issued 17 Jan. 1995[6] RADMAN-A Computer Code to Classify and Document Package LLW in accordancewith 10CFR Part 61, Main Topical Report, May 1983[7] RADMAN Operating Procedure, WMG-P-065 (version 8.2)[8] RC-101 Introduction to RADMAN and Regulatory Compliance[9] RADMAN Operating Procedure, WMG-P-103 (version 9.0)3.0 DEFINITIONS[1] Annual - Once per calendar year (based on sample date)[2] Biennial - Once every second calendar year (based on sample date)[3] Difficult to Measure Radionuclide - Isotopes such as alpha and low energy betaemitters, which are beyond the capability of routine plant analysis[4] Plant or Process Change - Changes to the plant or waste stream process that mayalter the waste stream characteristics. This can include, but is not limited to changesto filter media or process equipment[5] Radioactive Liquid Waste - Radioactive waste that exists primarily in a liquid form andincludes, but is not limited to, such items as water, oils, EHC fluids, etc.

NUCLEARMANAGEMENTMANUAL N ON-QUALITY RELATEDEN-RW-104REV. 12 INFORMATIONAL U SEPage 4 of 18Scaling Factors3.0 continued[6] Radioactive Solid Waste - Radioactive waste that exists primarily in a non-liquid formand includes, but is not limited to, such items as dry materials, metals, resins, filtermedia, and sludge[7] Scaling Factors - Known ratios of radionuclides in waste streams which are used tocalculate the quantity of difficult to measure radionuclides[8] Surrogate Waste Stream - A substitute waste stream that has essentially the sameradionuclide concentration or distribution as an existing waste stream.[9] Primary Waste Stream- For PWRs this is defined as Primary System resin and/orfilters and for BWRs this is defined as the Reactor Water Clean Up System resinand/or filters[10] LLD- Lower limit of detection. For the purposes of this procedure, LLD is the a priorivalue representing the lowest value a counting system can detect based oninstrument setup, calibration, background, decay time and sample volume.[11] Real- Isotope was determined to be above the LLD and is present in the waste[12] Not present- isotope was not seen above the LLD4.0 RESPONSIBILITIES

[1]Vice President, Operations Support (VPOS) is responsible for the maintenance andinterpretation of this procedure, and must approve any deviations from the provisionsof this procedure.

[2]Each Site Senior Nuclear Executive (SNE) is responsible for ensuring thatnecessary site documents are established and implemented to comply with regulatoryrequirements and the intent of this procedure.

[3]Radwaste Focus Group is responsible for periodic reviews and revisions of thisprocedure.[4] Each Site'sRadwaste Group (Radiation Protection) is responsible for implementingthe site-specific requirements of this procedure.5.0 DETAILS5.1 PRECAUTIONS AND LIMITATIONS None NUCLEARMANAGEMENTMANUAL N ON-QUALITY RELATEDEN-RW-104REV. 12 INFORMATIONAL U SEPage 5 of 18Scaling Factors5.2 GENERAL REQUIREMENTSNOTEAn equivalent form may be used in place of Attachment 9.1, "10CFR Part 61 Waste StreamSample Screening and Evaluation" & Attachment 9.2 "Quarterly Trending Documentation",however the form must contain as a minimum the information contained in the attachment[1] The following are examples of the various waste streams used in the determination ofwaste stream scaling factors. This list is not exhaustive and surrogate waste streamsmay be used.

ResinsRadioactive LiquidsDry Active Waste (DAW)Mechanical Filters[2] Frequency for sampling of existing waste streams:(a) Noted exceptions to Class A, B & C waste sample frequenciesResin media - if there is not sufficient volume in the tank or there is nointended shipment to be made, then no sample is required. The resinmedia (tank containing the waste stream) will be sampled prior to thenext shipment after a sufficient volume (tank level) is attained orshipment is scheduled. The results of the sample taken will be used tocharacterize all waste (in the tank) generated since the previouslydocumented 10CFR61 results.Filters -IF there is not sufficient volume in the container OR there is nointended shipment to be made,THEN no sample is required. Samplingof filters will occur within the periodicity noted unless it is discovered thatthe waste stream information does not match the plant conditions.

IFthis situation occurs,THEN additional methods for sampling will beemployed (filter smears, clippings OR running flow of the waste streamthrough a Millipore filter of similar micron size as the filter in service) toobtain an official sample. The 10CFR61 waste stream analysis resultswill be used to characterize all filters generated since the previouslydocumented waste stream results.(b) Class A Waste - at least biennially (within two years from the datethe lastofficial 10CFR61sample was taken).

NUCLEARMANAGEMENTMANUAL N ON-QUALITY RELATEDEN-RW-104REV. 12 INFORMATIONAL U SEPage 6 of 18Scaling Factors5.2[2] continued(c) Class B & C Waste - at least annually (within one year from the date the lastofficial 10CFR61sample was taken).NOTESpecific examples of significant equipment or process changes include: changes in oxidationreduction methods such as zinc injection, hydrogen water chemistry, media specialization,media distribution ion/cation ratios, fuel leaks and other changes in reactor coolantchemistry, sustained, unexplained changes in the routinely monitored Beta/Alpha ratios asdetermined by Radiation Protection, extended Reactor shutdown (>90 days), changes toliquid waste processing such as bypassing filters, utilizing filters or a change in ion exchangemedia, or when there are changes to waste stream that could change biogas generation rate.(d)IF there is a reason to believe that an equipment or process change hassignificantly altered the previously determined scaling factors by a factor of 10,THEN samples should be taken in addition to the annual/biennial samplingfrequency. The waste stream sample should be analyzed, re-evaluatedAND ifnecessary, shipped to a vendor laboratory for additional analysis.

[3] Trending(a) Once per quarter, each site shall compare one of the following listed ratios tothe previous four quarter average of that same ratio for the primary wastestream. The ratios are taken from the Chemistry reactor water sample for thestation for one of the desired combinations.Cs-137 to Co-60 I-134 to Co-60Dose equivalent Iodine (DEI) to Co-60I-133 to I-131Cs-134 to Cs-137(b) Calculate an average of the ratios for the last four quartersAND compare theaverage to the current quarter.(c)IF the comparison is less than a factor of ten,THEN no action is required.

NUCLEARMANAGEMENTMANUAL N ON-QUALITY RELATEDEN-RW-104REV. 12 INFORMATIONAL U SEPage 7 of 18Scaling Factors5.2[3] continued (d)IF the comparison is more than or equal to a factor of ten higher,THEN theprimary waste stream is to be sampled, analyzed, evaluated for change(increase) in waste class prior to the next shipment.(e)IF the change is more than or equal to a factor of ten lower,THEN the primarywaste stream should be evaluated for a change (reduction) in waste class priorto the next shipment. Once it has been determined that the primary wastestream needs to be resampled prior to the next shipment, no further quarterlytrending is necessary until the new data is obtained and accepted for update ofthe waste stream.(f)Document quarterly trending on Attachment 9.2.[4] For non-routine waste streams, generate scaling factors on a case by case basis5.3 INDEPENDENT LABORATORY ANALYSIS[1] Obtain a sample from the appropriate waste stream and perform an in-house gammaspectral analysis of the waste stream sample.[2] Enter the in-house gamma spectral analysis results into the RADMAN Samplesmodule.(a)IF using RADMAN version 8.2,THEN reference RADMAN OperatingProcedure, WMG-P-065.(b)IF using the current version of RADMAN,THEN reference RADMAN OperatingProcedure WMG-P-103[3] Ship the waste stream sample to the independent laboratory for 10 CFR 61 sampleanalysis per the vendor's instructions and in accordance with, EN-RW-102,Radioactive Shipping Procedure.

NUCLEARMANAGEMENTMANUAL N ON-QUALITY RELATEDEN-RW-104REV. 12 INFORMATIONAL U SEPage 8 of 18Scaling Factors5.4 WASTE STREAM SAMPLE DATA SCREENING[1] Using Attachment 9.1, "10 CFR Part 61 Waste Stream Sample Screening andEvaluation", perform the waste stream sample data screening.(a)IF the waste stream sample data activities are reported in uCi/g,THEN theymust be converted to uCi/cc and nCi/g to perform the lower limit of detection(LLD) comparison.(b)IF the activities are reported in uCi/sample,THEN the LLD comparisons cannotbe performed.

[2]WHEN performing the nuclide elimination,THEN document the nuclides eliminated onAttachment 9.1 or on the independent laboratory waste stream sample analysis.[3] Upon completion of the waste stream sample screening process, enter the new wastestream data into the RADMAN Samples module (a)IF using RADMAN version 8.2,THEN enter data according to RADMANOperating Procedure, WMG-P-065.(b)IF using the current version of RADMAN,THEN enter data according toRADMAN Operating Procedure, WMG-P-103.[4] Complete the "entered by"AND "verified by" on Attachment 9.1.5.5 WASTE STREAM SAMPLE DATA EVALUATION USING RADMAN VERSION 8.2[1] Use Attachment 9.1 in conjunction with these instructions to perform the waste streamsample data evaluation.[2] Compare the independent laboratory results to the in-house gamma results for thesame sample using the Validate program in the RADMAN Samples module perRADMAN Operating Procedure, WMG-P-065. The comparisons performed arespecific activity (for samples results reported in uCi/g or uCi/cc) and fractionalabundance.

[3]IF the specific activity OR fractional abundance comparison exceeds therecommended variance,THEN:(a) Investigate to determine the reason for the variance OR re-sampleAND re-analyze the waste stream.(b) Document the results of the investigation OR the reason for re-sampling andre-analyzing the waste stream on Attachment 9.1.

NUCLEARMANAGEMENTMANUAL N ON-QUALITY RELATEDEN-RW-104REV. 12 INFORMATIONAL U SEPage 9 of 18Scaling Factors5.5[3] continued (c)IF the new waste stream sample data is determined acceptable with variancesgreater than what is recommended,THEN document the explanation for thevariance and disposition on Attachment 9.1.(d)IF the new waste stream sample data is determined to be unacceptable due tovariances greater than what is recommended OR the waste stream isresampled and analyzed,THEN initiate a Condition Report.NOTEExercising the Simulate Database Update function does not affect the existing waste stream10 CFR Part 61 database. This program is a useful tool for determining the appropriateoption (Retain old data and re-sample, Replace old data with new, or Combine old data withnew) for updating the 10 CFR Part 61 database.The NRC approved Topical Report for RADMAN contains flowcharts that can be used to helpexplain variances.For new waste streams being developed there will not be a sample in the database toupdate. In this case the parts of Attachment 9.1 concerning comparison to the database maybe marked as not applicable ("N/A").[4] Using the RADMAN Simulate Database Update function according to RADMANOperating Procedure WMG-P-065, compare the specific activity, fractional abundanceand scaling factors from the existing waste stream sample data to the newindependent laboratory sample data set.

[5]IF the specific activity, fractional abundance OR scaling factor comparison exceedsthe recommended variance,THEN:(a) Perform an investigation to determine a reason for the variance OR resampleand reanalyze the waste stream.(b) Document the results of the investigation OR the reason for resampling andreanalyzing the waste stream on Attachment 9.1.(c)IF the new waste stream sample data is determined acceptable with variancesgreater than what is recommended,THEN document the explanation for the varianceAND disposition on Attachment 9.1.

NUCLEARMANAGEMENTMANUAL N ON-QUALITY RELATEDEN-RW-104REV. 12 INFORMATIONAL U SEPage 10 of 18Scaling Factors5.5[5] continued (d)IF existing sample data is to be retainedAND not replaced OR combined dueto unacceptable new waste stream sample data,THEN document thereason(s) on Attachment 9.1AND initiate a Condition Report.

[6]WHEN the independent laboratory waste stream sample data (scaling factors) hasbeen accepted,THEN replace the existing waste stream sample data with the newsample data OR combine the existing waste stream sample data with new sample data.[7] Record the waste stream update verification on Attachment 9.1.[8] Transmit a copy of the independent DAW Laboratory Analysis to the appropriate RPdepartment personnel (e.g., Dosimetry, Instrumentation etc.)[9] Transmit a copy of all new waste stream data to the Chemistry/Environmentalpersonnel responsible for site effluent data.5.6 WASTE STREAM SAMPLE DATA EVALUATION USING CURRENT VERSION OF RADMAN[1] From the RADMAN home page, select the "Distribution" tab.[2] Select "Nuclide Distribution Listing."[3] Select the distribution to be updated.[4] From the Commands window, select "Update Distribution."[5] Select the sample to be used for the update.[6] From the Commands window select "Replace Report,"THEN print the followingreports: Scaling FactorsFractional (%) AbundanceData Values NUCLEARMANAGEMENTMANUAL N ON-QUALITY RELATEDEN-RW-104REV. 12 INFORMATIONAL U SEPage 11 of 18Scaling Factors5.6 continuedNOTEThe Combine Report shows what the result will be if the Combine Existing Data action isexecuted. This shows what the effect of combining the old sample data with the new samplewill be (in effect, a rolling average of past data).[7] From the Commands window select "Combine Report,"THEN print the followingreports: Scaling FactorsFractional (%) AbundanceData Values[8] Compare the results of "Replace Report" to the results of "Combine Report."

[9]IF the specific activity, fractional abundance OR scaling factor comparison exceedsthe recommended variance,THEN:(a) Perform an investigation to determine a reason for the variance OR resampleand reanalyze the waste stream.(b) Document the results of the investigation OR the reason for resampling andreanalyzing the waste stream on Attachment 9.1.(c)IF the new waste stream sample data is determined acceptable with variancesgreater than what is recommended,THEN document the explanation for the varianceAND disposition on Attachment 9.1.(d)IF existing sample data will be retained and not replaced or combined due tounacceptable new waste stream sample data,THEN document the reason(s)on Attachment 9.1AND initiate a Condition Report.

[10]WHEN the independent laboratory waste stream sample data (scaling factors) hasbeen accepted,THEN replace the existing waste stream sample data with the newsample data OR combine the existing waste stream sample data with new sample data.[11] Record the waste stream update verification on Attachment 9.1.

NUCLEARMANAGEMENTMANUAL N ON-QUALITY RELATEDEN-RW-104REV. 12 INFORMATIONAL U SEPage 12 of 18Scaling Factors5.6 continued[12] Transmit a copy of the independent DAW Laboratory Analysis to the appropriate RPdepartment personnel (e.g., Dosimetry, Instrumentation etc.)[13] Transmit a copy of all new waste stream data to the Chemistry/Environmentalpersonnel responsible for site effluent data.6.0 INTERFACES[1] EN-RW-102, "Radioactive Shipping Procedure"[2] EN-AD-103, "Document Control and Records Management Programs"[3] RADMAN Operating Procedure WMG-P-065[4] RADMAN Operating Procedure WMG-P-103 7.0 RECORDS[1] Attachment 9.1, "10CFR Part 61 Waste Stream Sample Screening and Evaluation"[2] Attachment 9.2, "Quarterly Trending Documentation"[3] RADMAN software output[4] Independent laboratory waste stream sample analysis results8.0 SITE SPECIFIC COMMITMENTS None9.0 ATTACHMENTS9.1 10CFR Part 61 Waste Stream Sample Screening and Evaluation9.2 Quarterly Trending Documentation NUCLEARMANAGEMENTMANUAL N ON-QUALITY RELATEDEN-RW-104REV. 12 INFORMATIONAL U SEPage 13 of 18Scaling Factors ATTACHMENT9.110CFRPART61WASTE STREAM SAMPLE SCREENING AND EVALUATIONSheet 1 of 5Date: _________________In-House Sample Identification Number:____________________Independent Lab Sample Identification Number____________________Waste Stream

Description:

___________________________________________________________Waste Stream Sample Data ScreeningThe screening process performs the following:Eliminate nuclides based on specific criteria,Record the status of 10 CFR 20 Appendix G radionuclides as LLD, Real or Not Present.Record the status of RADMAN base nuclides as LLD or Real.Determine that the values reported as an LLD for named 10 CFR Part 61 nuclides meet thelimits established by the NRC.The nuclides selected from the screening process will be evaluated for the purpose ofupdating the applicable RADMAN waste stream sample database.Nuclide EliminationEliminate the following nuclidesbased on the criteria listed below:List the nuclide(s) eliminatedandcomments if applicable.Nuclide is naturally occurring (i.e.Pb, Rn, K, Po, etc)Nuclide is a noble gas(i.e. Xe, Kr,etc.)Nuclide has a half life <8 days withexception of I-131 which has anextremely low RQ valueNuclide is lower than the detectablelimit and is not a base nuclide or 10CFR 20 Appendix G nuclideComments: _______________________________________________________________________________________________________________________________________________________________________________________________________________________________________________

NUCLEARMANAGEMENTMANUAL N ON-QUALITY RELATEDEN-RW-104REV. 12 INFORMATIONAL U SEPage 14 of 18Scaling Factors ATTACHMENT9.110CFRPART61WASTE STREAM SAMPLE SCREENING AND EVALUATIONSheet 2 of 510 CFR 20 Appendix G NuclidesStatusNuclideValue Real LLDLLD Limit1% of Table 1 Class C Limits forC-14, I-129, Tc-99 and 1% ofTable 2 Class A Limits for H-3 NotPresent C-14<8E-2 uCi/cc H-3<4E-1 uCi/cc I-129<8E-4 uCi/cc Tc-99<3E-2 uCi/ccComments: ____________________________________________________________________________________________________________________________________________________________________________________________________________________RADMAN Base Nuclides StatusNuclideValue Real LLDLLD Limit 1% of Table 2Class A Limits NotPresent Co-60< 7 uci/cc Cs-137< 1E-2 uCi/cc Ce-144< 7 uci/ccComments: ____________________________________________________________________________________________________________________________________________________________________________________________________________________

NUCLEARMANAGEMENTMANUAL N ON-QUALITY RELATEDEN-RW-104REV. 12 INFORMATIONAL U SEPage 15 of 18Scaling Factors ATTACHMENT9.110CFRPART61WASTE STREAM SAMPLE SCREENING AND EVALUATIONSheet 3 of 510 CFR 61.55 Listed Nuclides Status Table 1 Nuclides Nuclide ValueRealLLDLLD Limit 1% of Table 1Class C limits Not Present C-14<8E-2 uCi/cc C-14 in activatedmetal<8E-1 uCi/ccNi-59 in activatedmetal<2.2 uCi/ccNb-94 in activatedmetal<2E-3 uCi/cc Tc-99<3E-2 uCi/cc I-129<8E-4 uCi/cc Pu-241<35 nCi/gmCm-242<200nCi/gm TRUs > 5 year T 1/2< 1 nCi/gmComments: ____________________________________________________________________________________________________________________________________________________________________________________________________________________Table 2 Nuclides Nuclide ValueRealLLDLLD Limit 1% of Table 2Class A limits Not Present H-3 <4E-1 uCi/cc Co-60 <7 uCi/ccNi-63 <3.5E-2 uCi/ccNi-63 in activatedmetal <3.5E-1 uCi/cc Sr-90 <4E-4 uCi/cc Cs-137 <1E-2 uCi/ccComments: ____________________________________________________________________________________________________________________________________________________________________________________________________________________

NUCLEARMANAGEMENTMANUAL N ON-QUALITY RELATEDEN-RW-104REV. 12 INFORMATIONAL U SEPage 16 of 18Scaling Factors ATTACHMENT9.110CFRPART61WASTE STREAM SAMPLE SCREENING AND EVALUATIONSheet 4 of 5RADMAN Waste Stream Sample Data Set EntryWith the exception of the nuclides eliminated during the screening, enter the followingnuclides into RADMAN as a sample data set and attach a hard copy of sample data entered. 10 CFR 20 Appendix G nuclides (indicate real, LLD, or not present) RADMAN Base nuclides (indicate real or LLD) 10 CFR 61.55 nuclides that have a real valueSample data entered by: ________________________________Date__________________Sample data entry verified by: ______________________________Date________________Sample EvaluationUsing RADMAN perform the Validate program in the Samples module and attach the hardcopy. This program compares the independent laboratory results to the in-house gammaresults for the same sample. Two comparisons are performed specific (for samples reportedin uCi/cc or uCi/g) and total activity, and fractional abundance.Document the variances identified by the Validate program and disposition.______________________________________________________________________________________________________________________________________________________________________________________________________________________________Using RADMAN, compare existing waste stream data to a new independent laboratorysample data set attaching the software output hard copy. Comparisons are made for specificactivity, fractional abundance and scaling factors. Based on the comparisons from thesimulation, determine which option should be used to update the RADMAN waste streamPart 61 database: Retain old data and resample Replace old data with new sample Combine old data with new data NUCLEARMANAGEMENTMANUAL N ON-QUALITY RELATEDEN-RW-104REV. 12 INFORMATIONAL U SEPage 17 of 18Scaling Factors ATTACHMENT9.110CFRPART61WASTE STREAM SAMPLE SCREENING AND EVALUATIONSheet 5 of 5Document the variances identified by the softwareAND the action taken to address each variance:Specific Activity Variances:________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________Fractional Abundance Variances: (2 for base nuclides Co-60, Cs-137, and 5 for Ce-144)________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________

Scaling Factor Variances:________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________Based on the above variances, the waste stream sample is dispositioned as:______ Retain old data and resample______ Replace old data with new sample______ Combine old data with new dataReason for the above disposition:________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________Waste Stream Evaluation Performed by: _______________________Date______________Waste Stream Evaluation Reviewed by: _______________________Date______________Waste Stream Update Verified by: ____________________________Date______________

NUCLEARMANAGEMENTMANUAL N ON-QUALITY RELATEDEN-RW-104REV. 12 INFORMATIONAL U SEPage 18 of 18Scaling Factors ATTACHMENT9.2 QUARTERLY TRENDING DOCUMENTATIONSheet 1 of 1Document the radionuclide ratio utilized per 5.2[3]:Current quarter average:Four quarter average:A - Current quarter average valueB - Previous four quarters' average value (not including current quarter average, e.g. wholeyear prior to current quarter)A & B - same selected nuclide ratios utilizedB / A = Variance ( C ) as well as 1 / C if value of C is < 1.0 Variance ( C )Based on the above variance, the waste stream sample is dispositioned as: < a factor of 10 - no action taken - current quarter > a factor of 10 - schedule re-sample of primary waste stream - prior to next shipmentComments:Performed by: _______________________Date________________Reviewed by: _______________________Date________________