ML20199G328

CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,981121-1218

ML20199G328
Person / Time
Site:	Three Mile Island
Issue date:	01/07/1999
From:	CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES
To:	NRC
Shared Package
ML20199G314	List: ML20199G311 ML20199G322 ML20199G328
References
CON-FIN-D-1035, CON-FIN-J-5164, CON-FIN-J-5186, CON-FIN-J-5206, CON-FIN-J-5210, CON-FIN-J-5226, CON-NRC-02-97-009, CON-NRC-2-97-9, REF-WM-11 HLWR, PMPR-99-3, NUDOCS 9901220258
Download: ML20199G328 (40)

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CNWRA PROGRAM MANAGER'S PERIODIC REPORT ON ACTIVITIES OF THE CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES For the Fiscal Reporting Period November 21 - December 18,1998 PMPR No. 99-3 January 7,1999 i go12ggsg9901N WM-11 PDR _-

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TABLE OF CONTENTS i Section Page TAB LES . . . . . . . . . . . . . . . . . . . . . . . . ... ....... ...... .. .... . .... ..... . . . iv ABBREVIATIONS . . . ... ..... .. ..... .. . . ....... .. ........ . . .... v EXECUTIVE S UMMARY-PERIOD 3 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xi 1 TECHNICAL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .............. ...... I 1.1 CNWRA Operations (COPS) . . . . . . . . . . . ... . ........ .... .... .... I 1.2 Igaecus Activity (IA) . . . . . . . . . . . . . . ... ............ .. . . .......... 2 1.3 Stmetural Deformation and Seismicity (SDS) . . . .... .. ......... ... ... . 3 1.4 E"olution of the Near. Field Environment (ENFE) . ...... ... ....... . .... 4 1.5 Container Life and Source Term (CLST) . . . . . . . .. ....... ... .. ...... 5 1.6 Thermal Effects on Flow (TEF) . .. .. ...... ................. ...... 6 1.7 Repository Design and Thermal-Mechanical Effects (RDTME) . . . . . ....... .... 7 1.8 Total System Performance Assessment and Integration (TSPAI) . . . . . . . . . . . ...... 8 1.9 Activities Related to Development of the NRC High-Level Waste Regulations (ARDR) . . . . . . . . .......... ... ...... ... .. ....... .. 9 1.10 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC) . . . .. . 10 1.11 Radionuclide Transport (RT) . . . . . . .. ..................... .. .. .. 12 1.12 Tank Waste Remediation Systems (TWRS) . ... ...... .. ....... . .... 13 1.13 Three Mile Island Unit 2 Independent Spent Fuel Storage Installation (TMI-2 ISFSI) . . . . . . . . . . . . . .. .......... .. ..... ....... 14 1.14 Dry Transfer System (DTS) . . . ........ .. ........... .... . ...... 14 1.15 Centralized Interim Storage Facility (CISF) . . . . . . ............ .......... 15 1.16 Private Fuel Storage Facility (PFSF) . . . . ...... ......... ................. 15 1.17 Savannah River Site Aluminum-Based Spent Fuel (SRSASF) . . . . ...... . .... 15 2 MANAGEMENTISSUES .. .................... ... . .... ...... ......... 15 3 MAJOR PROBLEMS .. .. ....... ......... ........ .. ....... . ... 15 4

SUMMARY

OF SCHEDULE CHANGES . . . . . . .................... ......... 15 5

SUMMARY

OF FINANCIAL STATUS . . . . . . . . . . . ........ . . .. .. 15 APPENDIX-Planned and Actual Costs, and Cost Variances Period 3-FY1999 111

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1 Table Page I 1' CNWRA Core Staff-Current Profile and Hiring Plan * (Period 3) . . . . . . . . . . . . . . . . . . . . 20 j 2 .- Sununary of Schedule Changes (Period 3) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 l

-3 Deliverables (Period 3) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . 22 l t

i 4 Financial Status (Period 3) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23  ;

i' 5: Private Fuel Storage Facility License Fee Cost Recovery Status (Period 3) . . . . . . . . . . . . . . 24 I

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.y ABBREVIATIONS ID One-Dimensional CDS Compliance Determination Strategy 2D Two-Dimensional CDTS Commission Decision Tracking System 3D hree-Dirnensional CEB Center for Environmental Biotechnology AA Atomic Absorption CEC Commission of the European AAI Average AnnualInfiltration Communities ACD Advanced Conceptual Design CFD Computational Fluid Dynamics ACF Alumina (in excess of alkali feldspar). CFR Code of Federal Regulation Calcium Oxide, Ferromagnesian Oxide CIAC Computer Incident Advisory Capability ACNW Advisory Committee on Nuclear Waste CISF Centralized Interim Storage Facility ACRS Advanced Computer Review System CLST Container Life and Source Term ADAMS Agencywide Documents Access and CM Configuration Management Management System CNWRA Center for Nuclear Waste Regulatory AECL Atomic Energy of Canada Limited Analyses AES Atomic Emission Spectrometry CNWRA OPS Operations Plan for the Repository AGU American Geophysical Union Program Al Administrative item COI Conflict of Interest ALTS Apache bap Tes Site COPS CNWRA Operations AML Areal Mass loading CPP Cyclic Potentiodynamic Polarization ANS Amencan Nuclear Society CQAM CNWRA Quality Assurance Manual ANSI American National Standards institute CRG Center Review Group AO Annotated Outline CRM Corrosion Allowance Material AP Administrative Procedure CRWMS Civilian Radioactive Waste APB Acid-Producing Bacteria Management System AR Assessment Report CSCS Constrained Stochastic Climate ARDR Activities Related to Development of Simulator the NRC High-kvel Waste Regulations CSH Calcium Silicate Hydrate ASCE American Society of Civil Engineers CSPE Corrosion Science and Process ASCll American Standard Code for Engineering Information Interchange DAS Data Acquisition System ASLB Atomic Safety and Licensing Board DBE Design Basis Event ASME American Society of Mechanical DC Division of Contracts Engineers DCAA Defense Contract Audit Agency ASTM Amencan Society for Testing and DCB Double Cantilever Beam Materials DCF Dose Conversion Factor ASU Arizona State University DCM Dual Continuum Model ATDTS Automated Technical Data Tracking D&D Decommissioning and Decontamination System DECOVALEX Development of Coupled Models and BEG Bureau of Economic Geology neir Validation Against Expenments BFD Basis for Design in Nuclear Waste Isolation BM Bare Mountain DEIS Draft Environmental Impact Statement BMF Bare Mountain Fault DEM Digital Elevation Model BNFL British Nuclear Fuels Limited DF Dilution Factor BTP Branch Techmcal Position DFCSS Division of Fuel Cycle Safety and CAI Color Alteration Index Safeguards CAM Corrosion Resist Material DIE Determination ofimportance CAR Corrective Action Request Evaluation CCDF Complementary Cumulative DIMNS Division ofIndustrial and Medical Distribution Function Nuclear Safety CCL Commitment Control Log DKM Dual Permeability Model CCM Constant Capacitance Model DIE Digital Line Graph CD-R CDROM Recordanie DLM Diffuse Layer Model CDF Cumulative Distnbution Function DNAG Decade of North American Geology CDM Compliance Determination Method DNFSB Defense Nuclear Facilities Safety Board CDOCS Consolidated document Management DOE U.S. Department of Energy System DOE-DP DOE Defense Program CDROM Compact Disk Read Only Memory v

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l DOE-RU U.S. Department of Energy Regulatory GET General Employee Training l l Unit GFM Geological Framework Model r

! DRA Division of Regulatorv Applications GHGC GeoHydrology and Geochemistry j

DST Drift Scale Test GIA GeneralizedImponance Analysis  ;

). D'IED Digital Terrain Elevation Data GIS GeographieInformation System  !

DTS Dry Transfer System GLGP Geology and Geophysics  !

j DWM Division of Waste Management GMS Goundwater Modeling System  ;

4 EBS Engineered Banier System GPS Global Positioning System i EBSER Engineered Barrier System GROA Geologic Repository Operations Area i Experimental Research GS Geologic Setting 4

EBSPAC Engineered Barrier System GSA Geologic Society of America i

Performance Assessment Code G'ITE Great Tolbachik Fissure Eruption ,

ECM Equivalent Continuum Model GUI Graphics User Interface  !

EDO Office of the Executive Director for GWB Geochemirt's Workbench  ;

Operations GWSI Groundwater System lntegration j EDX Energy-Dispersive X Ray Spectroscopy GWTT Groundwater Travel Time EIS Environmentalimpact Statement HE Hydrogen Embrittlement EM Element Manager HLUR High-Level Waste and Uranium  ;

EMPA Electron MicroProbe Analysis Recovery Projects Branch ENE East-Nonheast HLW High-level Waste ENFE Evolution of the Near-Field HRTEM High-Resolution Transmission Electron t l

Environment Microscopy  ;

) ENGB Engineenng and Geosciences Branch IA Igneous Activity l

! EnPA Energy Policy Act of 1992 IBM Intemational Business Machines <

, ENS Buropean Nuclear Society ICP Inductively Coupled Plasma  :

EPA U.S. Environmental Protection Agency ICPP Idaho Chemical Processing Plant l EPR Electrochemical Potentiokinetic ICRP Intemational Commission Radiological I i Reactivation Protection j EPRI Electric Power Research Institute IDLil Immediately Dangerous to Life and i EQA ExternalQuality Assurance Health [

EROS Earth Resource Observauon System IHLRWMC International High-level Radioactive {

ESF Exploratory Studies Facility Waste Management Conference and l ESP Environmental Simulation Program Exposition  !

FW East-West IM Intermediate Milestone EXAFS Extended X-Ray Absorption Fine IME Industrial Mobilization Exemption l Structure IMS Information Management Systems FAC Favorable Condition INEEL Idaho National Engineering and .

FCRG Format and Content Regulatory Guide Environmental Laboratory +

FDSHA Fault Displacement and Seismic Har.ard INE'IER Instituto Nicaraguense de Estudios l Analysis TERritoriales }

FEHM Finite Element Heat and Mass Transfer IN'IRAVAL International Code Validation FEM Finite Element Method I/O Input / Output FEP Features. Events, and Processes IP inspection Procedure FFRDC Federally Funded Research and IPA Iterative Performance Assessment i Development Center IR&D Internal Research & Development FFT Fast Fourier Transform IRIS Interim Records Information System ,

FIE Full-Time Equivalent IRM Office ofInformation Resources 4 ITP File Transfer Protocol Management FY Fiscal Year IRSR !ssue Resolution Status Report FYTD Fiscal Year-to-Date ISA Imtial Safety Analysis ,

GDP Ghost Dance Fault ISFSI Independent Spent Fuel Storage GEM General Electrochemical Migration Installation  ;

GEOTRAP Geologic Transpon of Radionuclides ISM Integrated Site Model  !

Predictions IVM Interactive Volume Modeling GERT General Employee Radiological IWPE Integrated Waste Package Experiments Training JC Job Code i

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,f ABBREVIATIONS (cont'd)

JPL Jet Propulsion Laboratory NOAA National Oceanographic and JRC Joint Roughness Coefficient Atmospheric Administration KESA KeyElementsofSubsystems Abstraction NRC Nuclear Regulatory Commission KTl Key TechnicalIssue NS North-South KTU Kcy Technical Uncertainty NSRRC Nuclear Safety Research Resiew LA License Apphcation Committee LAAO Li:ense Application Annotated Outline NTS Nevada Test Site LAN Lccal Area Network NUREG NRC Technical Report Designation LANL ks Alamos National Laboratory NWPA Nuclear Waste Policy Act, as amended LARP Li ense Application Review Plan NWTRB Nuclear Waste Technical Review Board LAW h w-Activity Waste OBES Office of Basic Energy Sciences LBNL Lawrence Berkeley National Laboratory OCRWM Office of Civilian Radioactive Waste LBT trrge Block Test Management LIIS La tin Ilypercube Sampling OGC Office of General Counsel LITC leckheed Information Technology OITS Open-Item Tracking System Company OMB Office of Management and Budget LLNL Lawrence Livermore National ORR Operations Readiness Review Laboratory ORS Overall Review Strategy LLW low-Level Waste OWFN One White Flint North LMAES Lockheed Martin Advanced PA Performance Assessment Environmental Systems PAAG Periormance Assessment Advisory LSS Licensing Support System Group LSSPP Licensing Support System Pilot Project PAC Potentially Adverse Condition LSSTB Licensing Support SystemTest Bed PAHT Performance Assessment and LWR Light Water Reactor Hydrologic Transport M Molar PASP Performance Asses; ment Strategic Plan Ma Million Years Ago PC Personal Computer MAI Mean AnnualInfiltration PC/TCP Personal Computer / Transmission MC Monte Carlo Control Protocol MEIRA Mass and Energy Transport PDF Probability Distribution Function MGDS Mined Geologic Disposal System PDR Public Document Room MH Mechanical-Hydrological PEL Permissible Exposure Limit MIC Microbially influenced Corrosion PEM Program Element Manager MINC Multiple Interacting Continua PER Prelicensing Evaluation Report MIT Massachusetts Institute of Technology PEST Parameter Estimation MM Major Milestone PFD Probabilistic Fault Displacement MO Management and Operations PFDHA Probabilistic Fault Displacement MOU Memorandum of Understanding Hazard MPC Multi-Purpose Canister PFS Private Fuel Storage MRS Momtored Retrievable Storage PFSF Private Fuel Storage Facility MSS MultiSpectral Scarmer PHA Preliminary Hazard Analysis MIU Metric Ton of Uranium PI Principal Investigator NAS Neional Academy of Sciences PMDA Program Management, Policy NAWG Nat aral Analogue Working Group Development and Analysis Staff NCR Nouconformance Report PMPR Program Manager's Periodic Report NEA Nuclear Energy Agency PMT Photo-Multiplier Tube NEI Nuclear Energy Institute PNNL Pacific Northwest National Laboratory NFS Network File Server PO Project Officer NIOSil National Institutes of Safety and Health PPA Proposed Program Approach NIR Near-Infrared PPE Prepassivated Platinum Electrode NIST National Institute of Standards and PRA Probabilistic Risk Assessment Technology PRT Peer Review Team NMSS Office of Nuclear Material Safety and PSAG Probabilistic System Assessment Group Safeguards PSHA Probabilistic Seismic Hazard Analyses NNE North-Northeast I'lTE Polytetrafluoroethylene NNW North-Northwest irrn Paintbrush Nonwelded Tuff Vii

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PVHA Pr)babilistic Volcanic Hazards SLAR Side looking Airbome Radar Assessment SNF Spent Nuclear Fuel PVHVIEW Probability of Volcanic Hazards SNL Sandia National Laboratories VIEW SOTEC Source Term Code PVM Parallel Virtual Machine SOW Statement of Work PWR Pr:ssurized Water Reactor SPCR Software Problem Correction Report QA Quality Assurance SRA Systematic Regulatory Analysis QAP Quality Assurance Procedure SRB Sulfate-Reducing Bacteria QRAM Quality Requirements Application SRBS Shafts. Ramps, Boreholes, and Their Matrix Seals RAI Request for AdditionalInformation SRD Software Requirements Description RASA Regional Aquifer System Analysis SRS Savannah River Site RDCO Repository Design. Construction. SRSASF Savannah River Site Aluminum-ard Operations Based Spent Fuel RDTME Repository Design and nermal- SS Stainless Steel Mechanical Effects STEM Scanning Transmission Electron REE Rare Earth Element Microscopy REECO Reynolds Electrical and Engineering STP Staff Technical Position Company, Inc. SUFLAT Stochastic Analysen of Unsaturated RES Office of Nuclear Regulatory Research Flow AndTransport RFP Request for Proposal SVF Springerville Volcanic Field RH Relative Humidity SwRI Southwest Research it.stitute RIP Repository Integration Program SZ Saturated Zone ROC Repository Operations Criteria TA Technical Assistance RPD Regulatory Program Database TBD To Be Determined RRT Regulatory Requirement Topic TBM Tunnel Boring Machine RSRG Real Space Renormalization Group TCP/IP Transmission Control Protocol /

RT Radionuclide Transport Internet Protocol RTS Radwaste Treatment System TDEM Time-Domain Electro-Magnetic SAP Standards Approval Package TDI Technical Document Index SAR Safety Analysis Report TDOCS Technical Document Reference SCA Site Charactenzation Analysis Database System SCC Substantially Complete Containment TEDE Total Effective Dose Equivalent SCCEX Sut stantially Complete Containment 1EF Rermal Effects on Flow Example TEM Transmission Electron Microscopy SCE Standard Calomel Electrode THC Hermal-Hydrologic-Cherrucal SCFF Southern Crater Flat Fault THMC Thermal. Hydrologic-Mechanical.

SCM Surface Complexation Models Chemical SCP Site Characterization Plan T-L Transverse-lengitudinal SDMP Site Decommissioning Management Plan TLM Triple-Layer Model SDS Structural Deformation and Seismicity TM Thermal-Mechanical SECY Secretary of the Commission Office of TMll Thermal-Mechanical Hydrologic the (NRC) TMI-2 Three Mile Island Unit 2 SELM Spectral Element Method TMS Re Minerals, Metals, and Materials SEM Scanning Electron Microscopy Society SER Safety Evaluation Report TOP Technical Operating Procedure SFPO Spent Fuel Project O!! ice TP Technical Position SFVF San Francisco Volcanic Field TPA Totai system Performance Assessment SGI Silicon Graphics Inc. TPI Time Period of ReFulatory Interest SGML Standard Generalized Markup TR2 DOE Seismic Topical Report No. 2 Language TRG Technical Review Group SHE Standard Hydrogen Electrode TSAR Topical Safety Analysis Report SHT Single Heater Test TSPA Total System Performance Assessment SIP Scientific Investigation Plan TSPAl Total System Performance Assessment SKI Swedish Nuclear Power Inspectorate and Integration S-L Short Transverse-Longitudinal Viii

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ABBREVIATIONS (cont'd) 13w-Chnv Topopah Spring Welded-Calico Hills Nonvitric TVD Total Variation Diminishing

'IWFN Two White Flint North TWINS Tank Waste Information Network System 1WRS Tank Waste Remediation System UA . Universityof Arizona UACH Universidad Aut6nomade Chihuahua UCLA University of California Ims Angeles UDEC Universal Distinct Element Code UK United Kingdom UNM University of New Mexico UR Uranium Recovery U.S. United States USDA U.S. Department of Agriculture USGS ' U.S. Geologic Survey UTM Universal Transverse Mercator USF1C Unsaturated and Saturated Flow Under Isothermal Conditions UZ Unsaturated Zone VA Viability Assessment VCS Version Control System VF Vitrification Facility VSIP Vertical Slice implementation Plan WAN Wide Area Network WAPDEG Waste Package Degradation WBS Work Breakdown Structure WCIS Waste Containment and Isolation Strategy WFO Work for Otiiers WGB Western Great Basin WIPP Waste Isolation Pilot Plant WMB Waste Management Branch

. WNYNSC Western New York Nuclear Service Center WOL' Wedge-Opening leading WP Waste Package WSEI Waste Systena Engineering and Integration

-WSRC Westinghouse Savannah River Company WSS Waste Solidification Systems WTSO Washington Technical Support Office

.WVDP West Valley Demonstration Project 3 WVNS West Valley Nuclear Services WWW World Wide Web XPS X-ray Photoelectrr.en Spectroscopy XRD X-ray Diffractoiretry YM Yucca Mounain YMP Yucca Me,ontain Project YMSCO Yucca Mountain Site Characterization Oike YMR Yucca Mountain Region YTD Year-to-Date ix

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'1 EXECUTIVE

SUMMARY

-PERIOD 3 In the Division of Waste Management (DWM) Job Code (JC), the Center for Nuclear Waste Regulatory Analyses (CNWRA) delivered the FY1999 CNWRA Operations Plans for the Repository Program Revision 12, Change 0, the PC version of the TPA Version 3.2 code, the PVM implementation of the TPA Version 3.2 code, and a journal paper entitled Estimation of Infiltration in Ephemeral Channels in Solitario Canyon. Several s:aff participated in the 1998 Materials Research Society Symposium, the American Geophysical Unior Fall Annual Conference, and other technical meetings and workshops. Staff also made presentations at ttese events. In addition, papers have been or will be submitted for acceptance in peer-reviewed journals.

The DWM JC year-to-date (YTD) cost variance was 13.0 percent. Spending fell from the previous period as a result of the holidays.

In the Tank Waste Remediation System (TWRS) JC, the staff continued preparation of various reports and incorporation of NRC comments on others. The YTD cost variance was 22.1 percent. Spending rose over last period because of payments to consultants.

In the Three Mile Island Unit 2 (TMI-2) Independent Spent Fuel Storage Installation (ISFSI) JC, the staff submitted the draft safety evaluation report (SER) and completed the r: view of the new Appendix E-On Site Fuel Transponation of TMI-2. The YTD cost variance for the TMI-2 ISFSI was - 37.3 percent resulting from continued efforts to prepare the draft SER. This effort consumed about 80 percent of FY 1999 funding during the last three periods.

In the Dry Transfer System (DTS) JC, the staff submitted a trip report on the DTS staff visit of INEEL to observe DTS prototype testing and also continued preparing the draft SER. The YTD cost variance was

-52.7 percent. Spending fell significantly over last period as the result of decreased staff utilization.

In the Centralized Interim Storage Facility (CISF) JC, staff submitted a mini-proposal to revise the computer code RIS KIND. The YTD cost variance for the CISF was 6.4 percent. This underspending resulted from lack of tasking relative to the revision of this computer code.

In the Private Fuel Storage Facility (PFSF) JC, the staffbegan preparation of the draft SER and electronically submitted to the NRC PEM draft position papers for five contentions. The YTD cost variance was 6.4 percent, consistent with reduced activity relative to the previous period.

In the Savannah River Site Aluminum-Based Spent Fuel JC, the staff awaited receipt of additional documents from the DOE for review. The YTD cost variance was 62.7 percent. Spending fell substantively over the previous period due to lack of tasking in this project.

It should be noted that the current spending estimates in all JCs are based on the assumption that staffing is at authorized levels. Current staffing remains below authorized levels and recmitment continues.

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CNWRA PROGRAM MANAGER'S PERIODIC REPORT ON ACTIVITIES OF THE  !

CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES TITLE Center fvr Nuclear Waste Regulatory Analyses (CNWRA)

! CONTRACTOR Southwest Research Institute (SwRI) j 6220 Culebra Road, San Antonio, Texas 78238-5166  ;

l CONTRACT NO: NRC-02-97-009 JOB CODES: D1035, J5164,' J5186, J5206,'J5226, J5210 NRC CNWRA PROGRAM MANAGER: John J. Linehan,(301) 415-7780 )

NRC CNWRA DEPUTY PROGRAM MANAGER: Deborah A. DeMarco;(301)415-7804 CNWRA PRESIDENT: Wesley C. Patrick,(210) 522-5158 ESTIMATED BUDGET: $87,611,477 PERIOD OF PERFORMANCE: 09/27/97-09/27/02 PERIOD OF THIS REPORT: 11/21/98-12/18/98 l

l 1 TECHNICAL 1.1 CNWRA Operations (COPS) l l

l In addition to a wide range of day-to-day activities, accomplishments in the management l l and planning area included (i) conveying the CNWRA Operations Plans for the Repository Program-Revision 12, Change 0; (ii) reconciling the carryover monies for FY1999; (iii) submitting revised spending estimates for FY1998 in connection with settlement of award fee amounts: (iv) funher addressing COI-related issues among the NRC, SwRI, and  ;

< CNWRA management staffs; and (v) participating in weekly HLW Management Board meetings.

Status of CNWRA staffing is indicated in table 1, consistent with the revised staffing plan l submitted as part of the CNWRA Annual Program Review and subsequent meetings with NRC management. During period 3, intensive recruitment effons continued as additional sources, database and university-related, were used to identify potential candidates. Three individuals-a geochemist, a hydrologist, and a materiais scientist-joined the stafflate in period 3 or early in period 4. Although interviews were conducted for the approved open positions, no new offers were made.

I Computer system suppon activities encompassed (i) continuing the use of consultant suppon to assist in development and implementation of the database retrieval system i

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(replacement for CDOCS); (ii) completing the installation and of SUN Microsystems and .

Silicon Graphics hardware and software associated with the GIS and IMS computing facilities;(iii) pursuing the installation and upgrade of standardized desktop computer systems; (iv) participating, as requested, in the monthly NRC/CNWRA Computer Coordination meeting; and (v) maintaining LAN operations.

QA activities focused on (i) distributing the latest revision of QAP-016 Procurement Control, to describe CNWRA procurement practices in closing the last CAR of the FY1998 QA audit; (ii) conducting surveillances, issuing nonconformance reports as required, and working with cognizant staff in response to these reports; (iii) supporting the application of configuration control for CNWRA scientific and engineerin g software ready for release; (iv) preventing organizational COls by reviewing swr 1 RFPs; (v) performing QA verification checks on each CNWRA deliverable; and (vi) evaluating potential changes to the CQAM.

In the next period, the CNWRA staff expects to (i) review and revise, if required, estimates of spending and hiring for FY1999; (ii) pursue aggressively hiring for open core staff positions; (iii) complete installation of computer hardware and software for GIS and IMS computing facilities, as well as initiate a new database retrieval system as the replacement for the CDOCS software; and (iv) provide CNWRA LAN operation and maintenance support.

In addition, the staff will (i) perform scheduled and unscheduled QA surveillances, (ii) conduct QA indoctrination > for new CNWRA staff and consultants, (iii) review SwRI RFPs for potential COI, and (iv) perform QA verification checks on each CNWRA outgoing deliverable.  ;

1.2 Igneous Acilvity (IA)

Staff completed a review ofIA conceptual models and input parameters in the TPA Version 3.2 code in support of the TSPA-VA review. The most important modeling topics related to IA are (i) subsurface characteristics of igneous events, (ii) WP and HLW responses during igneous events,(iii) timing of future igneous events,(iv) characteristics of past YMR basaltic volcanic eruptions, and (v) characteristics of tephra-fall deposits through time.

Each of these topics has been addressed in Revision 1 of the IA IRSR. In addition, IA sensitivity analyses on these models and associated parameters conducted with the TPA Version 3.1.4 code are valid for the TPA Version 3.2 code, because no changes were made to IA KESAs between these code versions. Although significant uncertainties exist regarding EBS response during igneous events, current risk calculations are conservative beer devant EBSs are assumed to fail during igneous events. Available models and inpu- . eters in the TPA Version 3.2 code provide a sufficient technical basis to review the dre . 00E TSPA-VA Technical Basis document. Potential future enhancements to the TPA code include (i) developing a module for computing the number of WPs dismpted by explicitly calculating the extent of magma-repository interactions, (ii) modifying the  !

existing module to account for the number of WPs potentially disrupted but not directly erupted into the accessible environment during an igneous evern, and (iii) incorporating into 2

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the existing module expressions to account for availability of fine paniculates through tirne as the tephra deposit is exposed to surface conditions.

Staff presemed the results of ongoing research at the AGU Annual Fall Conference. An important parameter for IA risk assessments is the amount of HLW potentially ejected l during an eruption.The size of the subvolcanic conduit exerts the first-order control on the l amount of HLW potentially entrained during igneous events. Using data from analog 3 volcanic eruptions and subvolcanic intrusions, staff presented a technical basis for the 50-m l d4ameter conduit currently used as an upper bound in TPA calculations. Staff also gave an I irivited presentation regarding probabilistic volcanic hazard and risk assessments for  !

n2 clear facilities. Consistent methodologies are needed at these facilities for low- I probability, but potentially high-consequence, volcanic events. Using probabilistic methods, )

hizard and risk assessments can be best quantified with complementary cumulative l probability distributions rather than single estimates of risk. This presentation emphasized l the need for long-term risk assessments at nuclear facilities due to the deleterious effects j of relatively long-lived contaminated volcanic deposits. j 1

Also during this period, staff responded to peer review comments on Volcanic Hazards at l the Proposed Yucca Mountain, Nevada, High-Level Radioactive Waste Repository 1: )

Geologic Factors Controlling Pattems of Small-Volume Basaltic Volcanism, submitted to the Journal of Geophysical Research. Staff continued to work with consultants at the  ;

University of Bristol on the design of experimental apparatus for magma-repository I interaction studies. Work on PVHView continued at a low level of effort because of limited I staff availability.

In the next period, staff will initiate review of the VA in support of a Commission paper identifying significant DOE licensing vulnerabilities. Initial designs for the magma-repository interaction experiments will be completed and construction of the experimental apparatus will begin at the University of Bristol.

1.3 Structural Deformation and Seismicity (SDS)

The staff made four presentations at the AGU Annual Fall Conference in San Francisco, California: (i) paleomagnetic analysis of vertical axis rotations from normal faulting; (ii) evolution of crossing faults and their role in development of anisotropic flow parameters such as permeability and porosity; (iii) petrographic examination of fault-deformation mechanisms in fault zones from the ESF; and (iv) fracture, fault, and seismic scaling relationships as a test of anomalous GPS results from YM.

Staff continued reviewing the DOE probabilistic seismic and fault displacement hazard analyses report in anticipation of the upcoming Appendix 7 meeting with DOE in early l March,1999, and preparing the IRSR (Revision 2.0). Staff also continued work on the 3D l Structural Model of Amargosa for Input to USFIC-CNWRA Report, Structural Evolution l of Crater Flat, Nevada-Journal Article, and analyses of new TPA results for sensitivity studies of faulting on repository performance.

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9 Staff prepared for and participated in the NRC/CNWRA meeting on progress of the .

Structural Effects on Flow Working Group and the NRC/CNWRA workshop on dripping ,

-in the proposed repository drifts. Preparations began for an upcoming NRC/CNWRA i meeting with consultants on fractures and faulting in the repository. A workshop on fracturing and faulting in the repository was postponed until after the VA review is  :

completed. Staff also continued to process data recently collected from the Volcanic Tablelands of eastern California. These data are used in evaluating alternative models of cmstal strain accumulation to e). plain the anomalous GPS strain rates recently measured by Wernicke, et al. and published in a 1998 Science article.

In the next period, staff will continue to (i) review the DOE probabilistic seismic and fault displacement hazard analyses report; (ii) construct the EarthVision 3D model of the A margosa trough; (iii) produce a paper on the structural evolution of Crater Flat, Nevada; (iv) analyze the sensitivity studies of faulting on repository performance; and (v) evaluate geologic and geophysical data from the Volcanic Tablelands, California. In addition, the staff will begin a detailed review f the VA. t i

1.4 Evolution of the Near Field Environment (ENFE) ,

Staffcontinued debugging, testing, and documenting the MULTIFLO Version 1.2 . Testing continued on the operator splitting transport algorithm for the reactive-transport module GEM.The operator splitting transport algorithm is necessary for 2D and 3D applications i' involving several chemical components. Implementation of a TVD algorithm began. The TVD algorithm is required to reduce numerical dispersion, an important numerical artifact i for advection-dominated systems, amplified by chemical reactions. Revision I of the software requirements description for MULTIFLO Version 2.0 was completed and placed in CNWRA internal review (Revised MULTIFLO V2.0 Software Requirements Description-Letter Report). ,

r Application of MULTIFLO to coupled THC processes for the proposed repository environment advanced by testing kinetic phenomena with consideration of the carbonate and silica systems. Benchmarking MULTIFLO nonisothermal, kinetic chemistry results

- with EQ3/6 models progressed with detailed attention to development of comparable input parameters.

i Staff centinued testing the EBSFILT module of the TPA Version 3.2 code and performing l sensitivity analyses related to the potential effect of cementitious materials.

Staff participated in the 1998 Materials Research Society Symposium, held in ,

Boston, Massachusetts. They co-chaired sessions on cementitious materials, waste ,

treatment, and natural analogs and also reviewed submitted manuscripts. In addition, staff made a presentation on sensitivity studies using natural analog and uranyl mineral solubility data to constrain alternate source term models. A draft trip report was prepared describing presentations at the meeting.

Staff continued review of the TSPA-VA Technical Basis document. The VA was received (via the www) and review initiated. j 4  !

i

'f Aggressive effons were undertaken to advance activities by several consultants and SwRI staff on a variety of subjects in support of the ENFE KTI, including evaluation of potential effects of microbial activity, aqueous actinide chemistry, solubilities of radioelements, effects of alteration of engineered materials on the near-field chemical environment, and propenies of altered tuff materials. A draft outline was prepared for a study to evaluate the impact of prolonged high temperature (> 100 *C) on cement properties and TSPA at YM.

In the next period, staff will continue review of the TSPA-VA Technical Basis document and the VA. Debugging and benchmarking of the MULTIFLO code will continue. Near-field radioelement solubility modeling and aqueous actinide chemistry crudies will advance and sensitivity studies on the effects of cementitious materials will continue. ENFE Sensitivity Studies-Journal Paper will be completed. Staff will participate in a NRC/CNWRA workshop on dripping in the proposed repository drifts, December 21-22, 1998, San Antonio Texas.

1.5 Container Life and Source Term (CLST)

Staff continue review of chapters 5 and 6 of the draft DOE TSPA-VA Technical Basis document. Concurrent with review of this document and related DOE reports, staff conducted sensitivity analyses using the TPA Version 3.2 code. Thus far, the staff examined the effects of various container related parameters, such as critical relative humidity, repassivation potentials, pit growth, and passive current density on system performance as well as on container life. The influence of cladding protection on limiting radionuclide release and the dose to the receptor group h?.s also been evaluated. Additional study was conducted with the TPA code using the value of some of the parameters proposed by the DOE (e.g., uniform corrosion rates for inner container) to examine system performance. These results will be documented in a report compiled with the NRC staff analyses.

Electrochemical corrosion testing continued to confirm the applicability of repassivation and corrosion potentials as predictive parameters for the long-term, localized corrosion of Alloy 825 in chloride-containing solutions at 95 C. The initiation oflong-term testing of Alloy C-22 is planned. In addition, repassivation will be analyzed by conducting simulated single-pit experiments. Mechanistic studies will be conducted to examine the effects of alloying elements, such as Mo (one of the main alloying elements of Alloy C-22), on localized corrosion.

Stress corrosion cracking tests continued on Alloy C-22. For comparison, tests are conducted simultaneously on type 316L SS because the susceptibility of this alloy to stress errosion cracking in hot chloride solutions is well established. Two fatigue precracked, wedge-loaded specimens of each material have been immersed in a deaerated 5 percent Nacl solution, acidified to pH 2.7 by the addition of hcl, and heated to 90 *C to duplicate the conditions used at the LLNL. The Alloy C-22 tests use an initial stress intensity of 33 u2 MPa m , while the type 316L SS specimens are tested at an initial stress intensity of 25 MPa muz For further comparison, one specimen of each material was immersed in 40 percent MgCl2at 110 *C, a more aggressive environment in which stress corrosion cracking of Alloy 825 and type 316L SS was previously studied ai the CNWRA. The staff 5

S observed crack propagation on type 316L SS after two weeks testing in the MgCl 2 solution, accompanied by significant branching of the main crack and growth of secondary cracks in the arms of the specimen. No crack growth, however, was detected in the Alloy C-22 specimen.

Localized corrosion testing of Alloy C-22 in solutions with chloride concentrations of 0.5, 1.0, and 4.0 M continued using an autoclave system at temperatures ranging from 95 to 175 *C. The results, thus far, indicate that significant localized corrosion can occur even at 95 *C at chloride concentrations equal to or greater than 1 M and at relatively low repassivation potentials. Tests at lower temperatures are planned to determine the critical temperature for crevice corrosion of the alloy. In addition, the effects of environmental conditions on the passive current density of Alloy C-22 continue to be examined to aid in predicting the long-term uniform corrosion rate of Alloy C-22.The preliminary results from these studies were presented at the 1998 Materials Research Society Symposium in Boston, Massachusetts, and will be included in the proceedings of the symposium.

The interdependence of solution chemistry, temperature, and potential on localized corrosion of A 516 carbon steel is being investigated in simulated repository environments containing bicarbonate and chloride anions. The effects of pH and potential were extensively examined, and the influence on localized corrosion of preoxidation in air at 200 *C for various exposure times has been evaluated. Current work is aimed at examining whether localized corrosion of A516 can occur under free corrosion (open circuit) conditions in air saturated solutions. A paper detailing these results will be presented at the 1999 NACE International Annual Corrosion Conference and included in its proceedings.

The efforts to increase staffing in the Corrosion Science and Process Engineering Element continued. Two candidates were interviewed for one of the remaining open positions.

In the next period, long-term corrosion tests of Alloy 825 will continue and tests of Alloy C-22 will be initiated. Localized corrosion testing of A 516 carbon steel and Alloys C-22 and 625, together with stress corrosion cracking tests using Alloy C-22 and type 316L SS, will also continue. Most of the experimental activities planned for A 516 steel are expected to be completed in the next period. Procurement of Ti Grades 7 and 16 will be initiated.

Activities related to sensitivity analyses, review of the VA, and review of alternate material; and design options will continue.

1.6 Thermal Effects on Flow (TEF)

Analysis and improvement of continuum models of seepage into drifts continued during the reporting period. Staff continued to study the sensitivities of fracture continuum models to hydraulic properties and mesh refinement. Dual continuum modeling of the drift-scale heater test is ongoing with emphasis on appropriate boundary conditions, heater power, and spatial discretization.

The second phase of the laboratory-scale boiling isotherm depression heater experiment continued during this reporting period. A week-long event was observed in which the 6

I i

1 boiling isotherm was depressed at about four evenly spaced locations above the heater.The ,

bciling isotherm returned to the preevent location at the conclusion of the event. l Staff continued the mountain-scale repository analyses. These analyses are extensions of earlier repository-scale nonisothermal analyses of perched water.The current analyses will investigate an EW-trending, vertical 2D geologic section midway through the repository block. The analyses use MULTIFLO with a dual-continuum conceptual model. l 1

The investigation of capillaxy diversion at the drift walls continued. Preliminary analysis indicates that grid discretization has a significant effect on the predicted results. These l

l results suggest that a nonstmetured grid would reduce the effect of grid refinement. This i elfort is in conjunction with the USFIC KTI.

S'.aff continued review of the TSPA-VA Technical Basis document in preparation for I review of the VA.

l i

Preparations continued for the workshop on dripping planned for December 21-22,1998, at the CNWRA. The TEF KTI has the responsibility of organizing and conducting the workshop. Its objectives are to coordinate activities that address seepage and dripping and to focus these efforts toward performance issues. Staff (NRC and CNWRA) from several KTIs plan to attend. Several consultants were invited to participate in this workshop. The first day of the workshop will be video-conferenced with TWFN; the second day will be tele-conferenced.

Discussions continued with several candidates to provide consulting services to the TEF KTI. Tasks assigned to the consultants will be identified at the workshop on dripping.

l In the next period, TEF KTI staff plans to (i) continue the second phase of the boiling isotherm penetration laboratory-scale experiment, (ii) analyze results from the first phase of the laboratory-scale heater test, (iii) test the MULTIFLO-DCM numerical code in modeling the DOE DST, (iv) evaluate the conceptual model of refluxing, (v) provide focused assignments to consultants to assist in TEF KTI tasks, and (vi) initiate review of the VA.

l l

1.7 Repository Design and Thermal-Mechanimi Effects (RDTME) l The UDEC analyses to predict the size and extent of rockfall under seismic loads in the repository thermal environment continued during this reporting period. This simulation is  ;

expected to provide a technical basis for determining the magnitude of the dynamic impact load on the WPs resulting from rockfall. Also, the results will be used as input to the SEISMO module in the future version of the TPA code for the assessment of rockfall ,

effects on WP integrity. Preliminary results indicate that regularity of the joint pattern and block sizes are two of the major controlling factors for potential rockfalls.

Study of the behavior of the rock mass surrounding the emplacement drifts under heated conditions at the repository scale using ABAQUS continued during this reporting period.

This study emphasizes rock mass behavior beyond the preclosure period and effects of 7

th:rmal load on permeability changes in the surrounding rock mass. Several cases regarding ,

the effect of lining stiffness on rock mass behavior were analyzed.

The investigation of drift-scale rock mass behavior and its effect on concrete lining stability using ABAQUS was restarted. The key focus of this study is to examine the rock mass behavior where transition from strong rock condition to weak rock condition occurs.

S:aff continued the literature review on concrete performance at high temperature. The review will provide valuable information to assess the DOE design of the concrete liner for u;e at high temperature.

The ABAQUS modeling of WPs investigated the thermal stress of WPs and assessed WP responses when subjected to the impact of falling rocks at various times.The ultimate goal is to develop a reasonable failure criterion that will be used in the SEISMO module to assess the effect of rockfall on WP integrity.

! Development of the Review Plan for preclosure aspects of design, construction, and operations using integrated safety assessment methodology was initiated during the l

reporting period. An outline of the review plan is being developed.

One RDTME KTl staff member attended the DOE Drift Stability Workshop on December 9-11,1998,in Las Vegas, Nevada. A trip repon is under preparation for submission during the next reponing period. Several technical papers are in preparation for presentation at the 37* U.S. Rock Mechanics Symposium scheduled in Vail, Colorado, June 6-9,1999.

In the next period. RDTME KTl staff plans to (i) review the literature collected on concrete performance at high temperature, (ii) investigate rock mass behavior under heated conditions on both repository and drift scales with an emphasis on long-term degradation of rock mass material propertics and strengths, (iii) conduct rockfall simulations, (iv) use the ABAQUS code to model WPs, (vi) develop the standard review plan, and (vi) initiate review of the VA.

1.8 Total System Performance Assessment and Integration (TSPAI)

Archival runs were made using the TPA Version 3.2 code to assess the effects of new parameter values for the SNF gap fraction, the hydraulic and transport properties of the cor crete invert, and the faulting model. In addition, a series of TPA runs were made to evaluate how doses due to faulting are affected by altering the parameter that defines the fraction of fuel wetted in the flow-through model for SNF dissolution.

Staff have undertaken an extensive literature search on the effects of particle size l l

corrections on estimated inhalation doses. They developed a spreadsheet based on the information provided in ICRP 30 for particle size dose corrections. These correction factors use the lung compartment deposition fractions based on particle size, the DCFs in Federal Guidance 11, and the radionuclide-specific compartment absorption fractions. This information will be used to refine the model currently implemented in the TPA Version 3.2  ;

code for estimating inhalation doses due to radionuclides released by extrusive volcanism. l l

t Development continued of the parameter tree approach for interpreting the results of the TPA Version 3.2 code. Staff provided a draft manuscript outlining the general approach to the NRC staff for informal review. In addition, work began on implementing an event tree approach for illustrating the effects of repository subsystems on total system performance.

Names of the nominees for the external review of the TPA Version 3.2 code were submitted I for review and comment to NRC and CNWRA staffs. The CNWRA staff found that few reviewers having expertise in metallurgy, material sciences, volcanology, or seismicity were i listed among the nominees. Additional experts will be selected from lists of names provided by the CNWRA staff. During the next period, formal setters ofinvitation will be sent to the top nominees.

The PC version of the TPA Version 3.2 code, the Java-based post-processor for the TPA Version 3.2 code, and the PVM implementation of the TPA Version 3.2 code were delivered. Each software product was accompanied by a brief installation and execution l

guide to facilitate use. Formal installation of the PC version of the TPA Version 3.2 code will be delayed until NRC receives a new multi-processor PC.

In the next period, the PA staff will focus on (i) reviewing the VA, (ii) preparing and mailing letters of invitation for the review of the TPA Version 3.2 code (iii) contributing to the draft Commission paper on the VA, (iv) refining the event tree approach for interpreting TPA results, and (v) initiating work on revision 2 of the IRSR. Recruitment will continue for the PA modelers, health physicist, and risk analyst.

1.9 Activities Related to Development of the NRC Iligh-Level Waste Regulations (ARDR)

Work continued on detailed modeling to evaluate the effects of well characteristics and plume dimensions on the accuracy of estimates of doses from the groundwater transport pathway. Geostatistical analysis of hydraulic conductivity data obtained from pump tests was completed and conditional synthetic random hydraulic conductivity fields generated for the fractured tuff aquifer. Staffinitiated construction of the flow and transport models that will use these synthetic random hydraulic conductivity fields.

Investigation on issues pertaining to calculation of age-specific doses at YM continued. A large body of age-specific intake information was identified in a draft EPA report, but because the report is a draft, the original sources of data are being investigated.

Staff made revisions to sections of a draft NUREG on technical issues related to the characterization of a critical group for Yucca Mountain. This NUREG will be released at the same time 10 CFR Part 63 is formally released for public comment to provide background information.

Revisions to the previously issued report, Information and Analyses to Support Selection of Critical Groups and Reference Biospheres for Yucca Mountain Exposure Scenarios, are undergoing internal review. The revised report will be issued as a NUREG/CR-a key I

reference document for the miemaking effort and TSPAl activities.

9

?

In the next period, staff will complete development of transport models for the fractured .

tuff aquiferu as part of the borehole dilution study. Assessment of age-specific DCFs will continue. If the EPA publishes the draft standard, staff will assist the NRC with reviewing it and preparing comments. The revised report, Information and Analyses to Support Selection of Critical Groups and Reference Biospheres for Yucca Mountain Exposure Scenarios, will complete technical review during the next period.

1.10 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC)

Staff participated in the AGU Annual Fall Conference in San Francisco, California. A poster entitled Refinement of Deep Percolation Estimates at Yucca Mountain in a Regulatory Framework was presented at one of the sessions. This poster documents ongoing field and modeling investigations of potential changes in soil thicknesses and textures over time and corresponding changes in pereciation rates at the proposed repository horizon. Field investigations have shown that, in the past, the soil texture was significantly finer and the thickness of the soil layer varied. Using plausible soil profiles, MAI at glacial maximum is estimated to be smaller by more than a factor of two relative to predictions using present-day soil profiles. MAI may not respond linearly to climate change, as erosion and soil genesis processes operate at different time scales than climate change.

Staff participated in the 1998 Materials Research Society Symposium held in Boston, Massachusetts. A paper entitled Time Scales for Dissolution of Calcite Fracture Fillings and Implications for Saturated Zone Radionuclide Transport at Yucca Mountain, Nevada, was presented. This paper is proposed as a new intermediate milestone in table 2 of this PMPR.

! USFIC st af f attended two workshops: (i) the second annual workshop on Field Testing and l Assou m d Modeling of Potential High-Level Nuclear Waste Geologic Disposal Sites held at LE: L, Berkeley, California, December 11,1998 and (ii) the PA workshop on UZ flow and trusport at SNL, Albuquerque, New Mexico, December 14-16,1998.

During this period, technical review continued of chapters 2 (UZ flow),7 (UZ transport),

and 8 (SZ flow and transport) of the TSPA-VA Technical Basis document.

I USFIC staff continued sensitivity analyses with the TPA Version 3.2 code. Review of the 1,000-vector run results revealed no surprises when compared to last year's sensitivity analysis. An alternate conceptual model investigated with the TPA code revealed that l repository performance predictions of annual TEDE are quite sensitive to the layer thicknesses assumed for the vitric and zeolitic layers beneath the repository. An additional sensitivity analysis was conducted to look specifically at the TPA code parameters F, and F , which affect the amount of water predicted to contact a WP. Results of this analysis indicate an apparently nonlinear sensitivity of TEDE to these parameters.

Work continued on independent interpretation of data from the long-term pumping test conducted at the C-holes complex from May,1996, to March,1997. To support this interpretation, a new method was developed to correct well water level data for the 10

'a

• i i

fluctuations induced by changes in barometric pressure. This new method accounts for both I the instantaneous barometric effects due to the direct coupling of water level to the atmosphere through the bore hole and the delayed effects that result from low-frequency barometric fluctuations transmitted to the water table through the overlying formations. 4 This correction method resulted in much smoother time-drawdown plots for distant observation wells. Analysis of these new time-drawdown curves resulted in a reduction in j th: range of aquifer transmissivity values estirnated for each of four distant observation wells.These corrected pump-test data were subsequently interpreted using the Papadopulos m:thod for evaluating horizontal aquifer anisotropy. This analysis suggests that transmissivity in the tuff aquifer is directionally dependent-the direction of highest transmissivity oriented approximately N 30 E (azimuth 030). Due to limited observation well data, the ratio of maximum to minimum directional transmissivity remains poorly cc nstrained.

Staff pursued the problem of capillary diversion of deep percolation away from open drifts.

Independent numerical models were used to evaluate the DOE modeling approach used to support the TSPA-VA. Results highlight the shoncomings of fracture continuum models used to predict capillary diversion of flow around drifts.

Effons to construct and calibrate a site-scale 3D model of the SZ continued. Work is currently at the calibration phase. Calibration will be performed using the PEST parameter estimation code.

A follow-up study to the October, 1998, EM-31 survey was performed from December Il-13,1998, Crater Flat, Nevada. Preliminary interpretation of results of this ,

study indicates a temporal increase in the bulk electrical conductivity in the south of the l surveyed region. A temporal decrease in the bulk subsurface electrical conductivity is observed in some areas in the north of the survey region. Preparations are continuing for the EM-47 and resistivity geophysical survey planned for January 18-28,1999, in Forty Mile Wash and the northern Amargosa Farms region.

Estimation of Infiltration in Ephemeral Channels in Solitario Canyon-Journal Paper was j submitted. Staff continued preparation of two manuscripts: (i) the potential hydrologic 4 impact to YM UZ and SZ- modeling that may result from the replacement of native plants by bromus grasses originating in Eurasia and (ii) infiltration abstractions for shallow soil l over fractured bedrock in a semiarid climate.

In the next period, USFIC activities will include (i) interpretation of data from CNWRA field studies at YM, (ii) progress on alternative conceptual models for flow and transport from the potential repository to the water table, (iii) development of approaches for modeling future infiltration, (iv) continued development of conceptual models for seepage into drifts, (v) review of the DOE UZ model of YM,(vi) preparation of a 3D subregional site-scale flow and transport model, (vii) continued efforts toward interpreting data from C-Well hydraulic and tracer tests, (viii) review of the VA and continued review of the TSPA-VA Technical Basis document,(ix) panicipation in a workshop on drift seepage, and l (x) panicipation in the working group on attemate conceptual models for structural controls l on flow.

I

! 11

z 1,11 Radionuclide Transport (RT) -

Staff presented two papers at the Materials Research Society Symposium held in Boston, Massachusetts, November 30-December 3,1998. Two manuscripts were prepared for publication in the symposium proceedings volume. The first manuscript. Radionuclide Serption at Yucca Mountain, Nevada-Demonstration of an Alternative Approach for Performance Assessment, outlines an approach for abstracting detailed process models to develop site-specific constraints on Ko probability distribution functions for PA and provides a discussion of spatial distributions of calculated Ko in the vicinity of YM. The se:ond manuscript, Unsaturated Zone Waters From the Nopal I Natural Analog, Chihuahua, Mexico-Implications for Radionuclide Mobility at Yucca Mountain, provides initial results of equilibrium and reaction progress geochemical modeling and includes U-series in erpretation of Nopal waters. Model results suggest that uraninite dissolution under open-system, oxidizing conditions, such as may occur in the proposed YM repository, may initially lead to schoepite precipitation, allowing higher dissolved uranium contents in released waters than if uranyl silicates were controlling aqueous uranium. Staff also reviewed manuscripts contributed by other authors for publication in the symposium proceedings.

The TPA Version 3.2 code was used to conduct sensitivity analyses of PA results to radionuclide transport parameters. A 250-vector run was conducted without correlation among alluvial sorption parameters for different radionuclides for comparison against 250-vector basecase results at 10,000 and 50,000 yrs that include correlated transport parameters for americium, neptunium, plutonium, thorium, and uranium.

The geochemical computer software GWB was placed under TOP-018 configuration control. GWB has the capability to simulate sorption reactions using surface complexation models and will be used in RT KTI activities related to simulation of radionuclide sorption and transport. The software uses the same thermodynamic data as are employed in EQ3/6 geochemical calculations.

CNWRA internal reviews were completed for two manuscripts proposed as new deliverables in table 2 of the period 2 PMPR. The first manuscript, Abstraction of Mechanistic Sorption Model Results for Performance Assessment Calculations at Yucca Mountain, Nevada-Joumal Paper, provides details on an approach for using detailed sorption model results in PA calculations. The staff anticipates this manuscript will be submitted for publication in Waste Management. The second manuscript, Experimental and Modeling Study of Ion Exchange Between Aqueous Solutions and the Zeolite Mineral l

Clinoptilolite-Journal Paper, is planned to be submitted for publication in the Journal of I

Solution Chemistry and includes an evaluation of data (published literature and unpublished

CNWRA results) on ion exchange between aqueous solutions rnd the zeolite mineral I

clinoptitolite.

Sorption experiments continued on quartz-clinoptilolite mixtures. Initial results for open-to-atmosphere experiments at 1:0.035 quartz: clinoptitolite mass ratio indicate an enhancement in sorption relative to quartz-only experiments (maximum Koof about 140 mUg), but less than the maximum observed for clinoptitolite-only (about 800 mUg). Capped vial l

l 12 l

i experiments are proceeding more slowly due to difficulty maintaining pH conditions under l limited buffering capacity conditions. Sample preparation for liquid scintillation analysis )

continued. l 1

1 Two abstracts for the American Chemical Society national meeting in March 21-25,1999, '

Anaheim, California, were submitted for NRC programmatic review: (i) Molecular l Dynamics Simulation of Uranyl Adsorption on Quartz Surfaces, and (ii) Experimental and Modeling Studies of Uranyl Adsorption Onto Binary Mixtures of Silicate Minerals. l 1

Staff continued to assist the NRC strtff in finalizing the RT IRSR. Efforts continued to advance activities by several consultants and SwRI staff on a variety of subjects in support of the RT KTI. Plans were developed for a critical evaluation of actinide sorption data and development of parameters for a surface complexation model that can be used for predicting actinide sorption as a function of system chemistry.The staffinitiated molecular dynamics simulation of radionuclide sorption. In addition, they are formulating plans for development of computerized optimization techniques to constrain wetted surface areas and stochastic modeling of spatially variable sorption parameters.

1 In the next period, the staff will review the VA. Laboratory analyses will continue, including multiple-mineral experiments. Modeling of experimental results will begin. New CNWRA staff will start work during the next period and will begin to develop experimental protocols for sorption experiments on alluvium minerals, including calcite. RT staff will j assist in the PA abstraction process and will continue sensitivity analyses using the TPA Version 3.2 code to investigate the effects of correlation of sorption parameters on performance.

1.12 Tank Waste Remediation System (TWRS)

The FY1999 Operations Plan for Technical Assistance Related to TWRS Licensing, Revision 2, Change 1, was sent.

In subtask 1.2, the CNWRA staff have completed about 80 percent of the Low-Activity Waste Feed Makeup, Solidification, and Offgas Technology and Process System Hazard and Safety Issues Report for TWRS-Letter Report.

In subtask 1.4, the staff is evaluating the resolution of the NRC comments on the draft report, Consequence Criteria for TWRS.

In subtask 1.6, revision to the report titled Chemistry of Hanford Tank Waste Pretreatment Technology was initiated to address the NRC staff comments on a draft version of the report. Because of the significant amount of time and retources required to incorporate the NRC-recommended changes, submittal of the final report was postponed, with NRC staff concurrence, to May 28,1999, from its current delivery date of December 28,1998. A revised final report is currently scheduled for submission on July 30,1999.

In subtask 2.1, formerly subtask 1.8, based on guidance for reviewing the DOE-RU Evaluation of the BNFL Initial Safety Analysis and Safety Requirements document, the 13

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J - . '

a

. . l CNWRA issued change pages, incorporating the NRC staff comments, on the Assessment .

of DOE Regulatory Unit Initial Safety Evaluation Report of the BNFL, Inc.,ISA Package Open Items-Parts I & III. The NRC comments on Assessment of DOE Regulatory Unit Initial Safety Evaluation Report of the BNFL, Inc., ISA Package Open Items-Pan II were resolved with the NRC staff and no changes were viewed as necessary. Also, in this .

subtask, CNWRA has requested a meeting with the NRC to discuss the scope of the report ,

Review of Hanford Immobilized Low Activity Tank Waste Performance Assessment.

?

In subtask 2.2, the NRC comments were received on the draft inspection manual chapter, which will be a part of the Technical Manual for TWRS-type Facilities Final Repon  ;

(IM 1403-202-930). These comments were incorporated and a copy of the manual chapter was e-mailed to the NRC. In addition, the CNWRA requested the NRC forward additional information on the TWRS organization to complete the Revised Inspection Procedures (IP 35016 and 35060) for TWRS-type Facilities Final Report.

In the next period, activities in subtask 1.2 will consist of completing the internal review cycle on the Low-Activity Waste Feed Makeup, Solidification, and Offgas Technology and Process System Hazard and Safety Issues Report for TWRS-Letter Report. The scheduled ,

delivery date for this report is January 29,1999. In subtask 1.4, the staff will continue to  ;

resolve the NRC staff comments and include assessment of 10 CFR Part 70 changes on the TWRS facility as they become available. In subtask 1.6, staff will contir.ue to incorporate the NRC comments. Finally, after additional information is received, the staff will complete ,

IP 35016 and 35060 and forward draft procedures to the NRC staff for review.

1.13 Three Mile Island Unit 2 Independent Spent Fuel Storage Installation (TMI-2 ISFSI)

The staff completed preparation of the draft SER during this reportine period, documented as Safety Evaluation Repon-Draft Letter Report and submitten november 30,1998.

Review of the new Appendix E-On Site Fuel Transportation of TMI-2 was r Iso completed.  ;

NRC review comments on the draft SER have been received and the revision of the draft SER to incorporate NRC comments has begun. ,

In the next period. TMI-2 ISFSI staff plans to prepare the final SER by revising the draft SER and review the DOE proposed technical specification bases for the TMI-2 ISFSI.

1.14 Dry Transfer System (DTS) i A trip repon on the DTS staff visit of INEEL on November 18-19,1998, to observe DTS t

prototype testing was submitted on December 12,1998. The preparation of the draft SER continued this reponing period.  ;

In the next period. DTS staff plans to continue preparation of the draft SER while waiting for the DOE response to the first round RAI.

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• g 1.15 Centralized Interim Storage Facility (CISF)

N RC acceptance of the draft AR was received during this reporting period. Staff submitted a mini-proposal to revise the computer code RIS KIND. High Seismic Topical Report on HI-STAR /HI-STORM cask systems was received during this reporting period.

In the next period, CISF staff plans to begin preliminary work related to revision of the c omputer code RIS KIND, while waiting for instruction for reviewing High Seismic Topical Report on HI-STAR /HI-STORM cask systems.

1.16 Private Fuel Storage Facility (PFSF)

The staff began preparation of draft SER during this period. Draft position papers for five contentions were transmitted to the NRC PEM electronically.

In the next period, PFSF staff plans to continue preparation of the draft SER.

1.17 Savannah River Site Aluminum Based Spent Fuel (SRSASF)

The letter report, Evaluation of the U.S. Department of Energy Aluminum Based Spent Fuel Criticality, was accepted programmatically by the NRC staff. Technical comments will be conveyed separately for further revirion of the report. No significant technical activities were conducted in this reporting period, pending receipt of additional documents from the DOE for review.

In the next period, the letter report Evaluation of the U.S. Department of Energy Aluminum Based Spent Fuel Criticality, will be revised to incorporate the NRC staff technical comments. Addi*ional reports sent by the DOE will be reviewed.

2 MANA.GEMENT ISSUES None to report.

3 MAJOR PROBLEMS None to report.

4

SUMMARY

OF SCHEDULE CHANGES Schedule changes for IMs are included in table 2. Completed deliverables are noted on table 3.

5

SUMMARY

OF FINANCIAL STATUS Table 4 summarizes the CNWRA financial status in the context of authorized funds. Total l commitments are $212,794. The appendix lists planned and actual costs to date, as well as variances l between these, without allowance for fee, on both a per period and a cumulative basis. These data do not include commitments. Pertinent financial information is provided for the DWM JC, including 15

1 5 - ,

s ,

COPS and 10 KTIs, TWRS JC, TMI-2 ISFSI JC, DTS JC, CISF JC, PFSF JC, and SRSASF JC. The .

planned costs per period are based on the revised spending plans contained in the CNWRA OPS fot' the Repository Program, Revision 12 Change 0, for the DWM JC; TWRS OPS, Revision 2, Change 1, for the TWRS JC; SFPO OPS, Revision 1, Change 7, for the TMI-2 ISFSI, DTS, CISF, and PFSF JCs; and SRSASF OPS, Revision 1, Change 0, for the SRSASF JC.

It should be noted the current sper Mg estimates in all JCs are based on the assumption that staffing is at authorized levels. Staffing remains below authorized levels and accelerated recruitment is in progress. The CNWRA will continue to monitor and update the staffing plan delivered as part of the November 18,1998, CNWRA Annual Program Review and subsequent revisions.

Period 31T1999 CNWRA composite expenditures fell 21.6 percent from the previous period, and this aggrc gate of all JCs was underspent by $345,956 or 12.0 percent. When comparing period 3 with last period, the, DWM, TMI-2 ISFSI. DTS, CISF, PFSF, and SRSASF JCs evidenced lower spending levels while only the TWRS JC showed a higher level.

The DWM JC was underspent by $322,749 or 13.0 percent. Overall expenditures decreased 19.3 percent from the previous period as costs rose in the RDTME and ARDR KTIs but declined in the COPS and the IA SDS, ENFE, CLST, TEF, TSPA, USFIC, and RT KTIs.

The TWRS JC was underspent by $46,086 or 22.1 percent. Despite an increase in spending over the previous period, this underspending was primarily the result of a decreased allocation of labor resources relative to period 1.

The TM1-2 ISFSI JC was overspent by $26,322 or -37.3 percent. Although spending fell from last period, costs exceeded the period 3 estimate as CNWRA staff continued to focus on preparation of the draft SER-expending approximately 80 percent of the funding for FY1999.

The DTS JC was overspent by $16,770 or -52.7 percent. Expenditures decreased significantly from the previous period, reflecting the cost associated with the DTS prototype site visit and reduction in stafflabor costs.

The CISF JC was underspent by $3,416 or 6.4 percent. Spending decreased substantially as the result of lower labor costs as the staff awaits NRC instruction on the scope related to the revision of RISKIND computer code and the review of High Seisn.ic Topical Report on Hi-STAR /HI-STORM cask systems.

The PFSF JC was underspent by $1,596 or 6.4 percent. Expenditures decreased significantly over I the last period as spending for labor declined.

The SRSASF JC was underspent by $16,202 or 62.7 percent. Spending decreased over the previous penod as a result of no tasking in this area.

l Expenditures on SwRIlabor, consultants, and subcontractors as a proportiors of composite spending i

on all JCs were 16.7 percent. Expense of consultants and subcontractors as a fraction of composite spending on all JCs was 9.5 percent. The CNWRA remains committed to enhance, where appropriate, participation of consultants and subcontractors in the conduct of CNWRA work.

i t

16 I

s u .

(

As shown in table 1, the CNWRA has 5 I staff members. The available pool of approved consultants and subcontractors is 44.

This FYTD no capital or sensitive equipment was purchased with NRC funds (other than overhead, general and administrative expenses, and fees).

DWM JC The DWM JC cumulative cost variance was 13.0 percent. Expenditures in this JC decreascd by 19.3 percent over period 2. Specific explanations for over/ underspending for COPS and each KTI follow.

The cost varisce for COPS was 16.7 percent: 15.0 percent for the Management, Planning, and Computer Scppua 2otask (158) and 23.8 percent for the QA subtask (159). Spending in both subtasks fell relative to last period and reflects the lowest per-period expenditure since the beginning of this FY. Spending on labor declined from the previous period, but Other Direct Costs, primarily travel and consultants, increased. In the next period, expenses are expected to continue below planned levels, reflecting traditionally low spending during the holiday season. Subsequently, spending in Subtask 158 should remain close to estimates, contingent on acquisition of a clerical staff member, sustained use of computer-related consultant (s), and participation of eligible staff in professional development activities. In Subtask 159, spending should remain below estimates until preparations begin, usually in period 7, for the annual QA audit. The timing for spending associated with the augmented scope of work in subtask 159 will be dependent on the schedule for the training of the NRC staff. I 1

The cost variance for the IA KTI was - 1.1 percent. Higher than anticipated expenditures related to payment of subcontractors and late FY1998 field expenses caused this negative variance, which was nearly eliminated by reduced spending in period 3. Spending is anticipated to remain stable in the next period as the FY1999 CNWRA OPS are implemented.

The cost variance for the SDS KTI was -2.8 percent. Spending for period 3 was below the estimated period cost. The higher labor, travel, and consultant costs in period 2 resulted in aggregate overspending however. A continuing effort will be made in the next several periods to further reduce the cumulative variance. 1 The cost variance for the ENFE KTI was 32.6 percent. Existing commitments not yet posted to the account reduce this variance to 28 percent. In the next one to two periods, the variance is likely to increase. Beyond that time, new work related to cement properties is anticipated to significantly reduce the variance. It remains uncertain when the contracts for this work will be fully executed and at what dates the costs associated with this new work will be posted to the account, but these matters are being aggressively pursued.

The cost variance for the CLST KTI was -29.1 percent. The overspending in this KTI resulted from augmentation of activitics related to sensitivity analyses and assembly of equipment for localized corrosion and stress corrosion cracking testing of Alloy C-22. While the rate of spending decreased from the previous period, the VA review, the addition of another staff member, and the need to order 17

J - .

new materials to investigate corrosion of alternate materials are expected to maintain spending near *

• or above the budgeted amounts for the next three to four periods.

The cost variance for the TEF KTl was 25.6 percent, with spending this period lower than that of the previous period. The increase of cost underrun during the reporting period is due to temporary assignment of CNWRA staff from the TEF KTI to other projects. Currently, discussions are ongoing with several prospective consultants to participate in TEF KTI activities. The cost underrun will decrease during the next few periods because of the concentrated cost associated with the workshop on dripping and the expectation of newly hired staff and consultants working on TEF KTI activities.

The cost variance for the RDTME KTI was 3.9 percent. Spending rose over the previous period.

Two consultants, one subcontractor, and one SwRI staff were selected for the augmented activities of the RDTME KTI. The consultants and the SwRI staff have already initiated the RDTME augmented activities. Centractual paperwork is in progress for the subcontractor. Actual expenditures are expected to continue following the budget for this KTI, however, some cost underrun is expected daring periods 4 and 5 related to the holidays and lagging charges from the additional consultants and subcontractors.

The cost variance for the TSPAI KTI was 19.0 percent following a significant spending decrease in this period. Lower costs for labor and consultants due to completion of three software projects early in the period contributed to reduced spending. The cost variance and spending rate are expected to remain roughly the same during period 4 of FY1999. Increased expenditures associated l with reviewing the TSPA-VA and conducting the augmented scope of work should be seen beginning in period 5.

t The cost variance for the ARDR KTI was 52.1 percent. There is still no indication the draft EPA I Standard will be released for review in the coming months, so underspending will continue

( indefinitely. The augmented scope of work has the potential to control underspending, but timely actions regarding the public outreach program are essential to achievement of this goal.

l The cost variance for the USFIC KTI was 4.9 percent. Sharply reduced expenditures this period corrected the overspending experienced during periods 1 and 2. Underspending is expected to increase for period 4 owing to staff vacations and holidays during that period. Focused USFIC work on the VA review and related deliverables will tend to moderate this anticipated underspending.

Nevertheless, until another hydrologist can begin work, the positive variance is anticipated to I persist.

The cost variance for the RT KTI was 25.6 percent, with period 3 spending only two-thirds of expected expenses. This variance is likely to increase in period 4 as a result of staff holidays and vacations. In period 5, the addition of a new geochemist to the staff is anticipated to reduce the variance somewhat, although increased actual spending will be offset by an increase in the planned rate of spending that begins in period 4. Further reductions in the variance are envisioned with the implementation of a subcontractor to support actinide sorption work.The associated costs, however, will likely lag commencement of the work.

The cost variance for the TWRS project was 22.1 percent. Spending increased from the previous period, primarily attributed to payments to consultants. The spending is expected to be at a slightly 18

- .L lower level in the next period despite the expenditures related to delivery of a letter report and draft l

procedures because some of the staff time will be diverted to the high-priority review of the VA.

The cost variance for the TMI-2 ISFSI project was -37.3 percent. This overspending is a result of concentrated effons needed during the first three periods of FY1999 to prepare the draft SER. About 80 percent of the FY 1999 activities within the TMI-2 ISFSI project were completed during periods I through 3. As a result, the cost overmn will decrease significantly during the next few periods be-cause of reduced activities. FY1999 total expenditures are expected to converge to the FY1999 allocation.

The cost variance for the DTS project was -52.7 percent, significantly lower than that of the previous period. This cost overmn is due to the concentrated cost associated with the DTS prototype site visit a,d the low allocation of funding for the first three periods of FY1999 compared to the total FY1999 budget for DTS (i.e., $1DK versus $16K per period). This cost overmn will continue to decrease during the next three periods because spending is expected to be less than that allocated for the remaining periods of FY1999.

The cost variance for the CISF project was 6.4 percent, which reflects sharply decreased costs following transmittal of a key report.This cost underrun will continue until CNWRA receives NRC instruction on the desired scope for revising the computer code RISKIND and reviewing the High Seismic Topical Report on the HI-STAR /HI-STORM cask systems.

The cost variance for the PFSF project was 6.4 percent. This minor cost underrun is due primarily to reduced spending on labor. .Although expenditures will increase substantially to accommodate preparation of the draft SER, a temporary cost variance is expected to occur as activities and costs catch up to the higher per-period budget in the remaining periods of FY1999.

The cost variance for the SRSASF was 62.7 percent. Spending is expected to continue at a low level as staff waits for DOE repons to continue their review process. The DOE is expected to transmit additional reports toward the beginning of the second quaner of FY1999, at which time the review activity is expected to increase.

19

, 3 J

Table 1. CNWRA Core Staff-Current Profile and Hiring Plan * (Period 3) ,

. as  ?

Positions Open Essertime/ Ease r6snee Currens No. Professional Staff FYl9M i ADMINISTRA110N 4 H G ARCIA. W PATRICK. I RUSSEtt B S AG AR CHEMICAL PROCESSIbG 2 VJAN, D.DARUWAllA ENGNG/ PHYS CHEM CODE Am'YSIS/DEVILDPMENT 2 RJANEf7.KE. R.M AR11N I DAT' AAGEMENT/ PROCESSING, 1 P.MALDONADO i

INClouING FIN ANCIAL >

DOSFJRISK/HA7ARD ANALYSIS '0 1 [

r ELEC*TROCHEMIS11tY I G CRAGNOllNO ENGINEERING 2 RGEN, G.OIOBGBU  ;

GE01DGYKiEOLDGICal.ENGNO "

?

ENVIRONMENTAL. SCIENCES 1 P.taPIANTE GEOCHEMISTRY 6 W.MURPdY. R.PAB AIAN, E.PEARCY. J.PRIKRY1.

D TURNER.1. BROWNING p i

R.FEDORS, R. GREEN, J.WINTERIL DEARRELI. i GEOHYDROLDGY/HYDROGEOLDGY $

M Hill GFDIDGY 3 LMcKAGUE M MIKtAS.P.tAFEMINA HYDROtDGIC11t ANSPORT 3 A ARMSTRONG. S PAINTER. D HUGHSON I INIORMA110N MAN AGEMENT 1 R.KOTARA (

SYSTEMS MATERIAL SCIENCES 4 D DUNN. N SRIDHAR. S BROSSI A. Y.M PAN 1 MECHANICA1. 0 1 INCLUDING DESIGN & FABRICATION  :.

MINING ENGINEERING 1 S-M HSIUNG  !

NUCIEAR ENGINEERING 1 M JAR 7EMB A OPERAT10NAL HEAL 1H PHYSICS 2 J WELDY, l.DELRE PERf0RMANCE ASSESSMENT 2 5 MOHANTY. G WIT 1MEYER 2 f

OUALITY ASSUR ANCE I B MABRTfD R ADIOISOTOPF GEOCHEMISTRY I D PICKITT (

ROCK MECHANICS, 2 A,CHOWDHURY, A.GHOSH INCLUDING CIVIllSTRUC. ENGNG SOURCE-TERM / SPENT FUEL DFOR AD. O I S11tUCI11RALGEOLOGYI 3 D IT.RRILL J.STAMATAKOS, D.SIMS SEISMO-TECTONICS SYSTEMS ENGINEERING 1 P M ACKIN VOtrANOLOGY/lGNFOUS 2 C.CONNOR, B. Hill  !

PROCESSES i TOTAL 51 s j i

• See staffing plan fOr details  :

)

20 l i

f

ec Table 2. Summary of Schedule Changes (Period 3) .

, MILESTONE ' ORIGINAL REVISED -

NUMBER TYPE DESCRIFFION DATE DATE RATIONALE FOR CHANGE 1402-861-990 IM Time Scales for Dissolution of ' 03/05/99 New deliverable established after :

Calcite Fracture Fillings and consultation with NRC PEM.

Implications for Saturated Zone Radionuclide Transport at Yucca Mountain, Nevada- -MRS Manuscript U

f

_ __ __...m__ _____......__.m._.--_.m.-_.._m__.m__m_-_____.__.____.____m. .._mm. - - _m_ _--.--___m_.mm_..- m ___ _ _ _ . _- ____._ -m_a

I i

Table 3. Deliverables (Period 3)

ORIGINAL ACTUAL MILESTONE COMPLETION REVISED # OF COMPLETION REASON NO. TYPE DESCRIFTION DATE DATE REVISIONS DATE (IF DELAYED) 1402-871-910 IM Estimation of Infiltration in 12/11/98 12/9/98 Ephemeral Channels in Solitario l Canyon-Journal Paper 1402-871-910 IM Sorption Modeling for PA-MRS 12/18/98 12/16/98 ,

Manuscript 1402-871 920 IM UZ Chemistry at a Natural Analog 12/18/98 12/16/98 Site-MRS Manuscript I

I405-014-910 IM Safety Evaluation Report-Draft 11/30/98  !!/25/98 letter Report (TMI-2)

I to tu l

1 l

~

6 e

e Y b c

44

...-m-

.w. . 7 .-os . ~ ..m--m. ,. ,_.y.w. ,,,,.,,_._.._,,e _ r ___ - _ , ,-_-,%,. . - _ ,g_._., . , . , y c ,m. . _ , , _ , . . _ _ . , , . .__ r~, -

n s Table 4. Financial Status (Period 3)

Funds Funds Funds Project Names Authorised Cassed ta Date Unconted Commitments COPS 2.010.592 1.939 173 91.180 112 1A R59.061 892.127 2 946 21 921 SDS 1.145.148 1.145 658 (5111 17.612 F. NIT'. 984.875 911.4 ' d 73.458 116.501 CIST 260 RRO 906 19' ,

(45.319) 13.930 TEF 761.502 719.525 47.977 5.871 RDTME 580 N06 567 415 13.371 2.050 TSPA1 2.OR I .10R 1.R17.210 263 899 4.620 ARDR 296 197 241.244 $ 5.113 0 UST1C 1.261.269 1.219 521 25.745 6.155 RT 622.721 564 999 $7.722 100 DWM Cats I1.4R2 27R I0.896.907 9R5.77i DWM Award Fee 561.869 260.911 301.314 DWM Baw Fee 499.291 423.718 35.573 TUTAT. DWM 12.505.414 11.580 797 924.677 210.R72 TWRS Cmts 993.1R6 941.449 51.937 1.922 TWRS Award Fee 47 641 22 741 24 902 TWRS Rase Fee M739 16 699 3.016 TUTAL TWRS 1.0R0 764 1.000 kh4 79 N79 1.922 TMt.2 IST3I S AR Cmts 24R 991 212 441 I6.550 0 TMI-2 ISf31 SAR Award Fee 16.701 9.5R9 11.118 TMi-2 ISISI Base Fee 9.160 R.099 161 TOTAL TMI-2 ISFSt S AR 274.846 247.027 27.829 0 DTS Cats 199 912 i R t.226 14 706 0 DTS Award Fee 11.175 7.774 1 40I DTS Rase Fee 7 997 7.156 R42 TUTAL DTS 210.104 200 145 18 949 0 CISFChats 109.7R I 272569 17.212 0 CISF Award i+e 11 249 6.201 7 042 CISF Itaw Fee i1.191 10 510 662 TOTAL CISF 114.217 289 102 44 919 0 PI5F Cats 172044 11R 417 11 607 0 Pf3F Award Fee R 110 1 412 4 798 PF5F Baw Fee 9.6R2 9,148 134 TOTAL PF5F l R6.019 147.296 38.739 0 SRSASFCmts 94 102 75 914 1R 16R 0 SRSASF Award Fee 6 140 3351 2.9k9 SRS ASF Itaw Fee 1.764 2 9tR R26 TOTAL SRS ASF 141.206 82.224 21 982 0 Grand Total 14 704 616 13.947 650 1. t $6.066 212.794 Note: All authortred funds have been alkcated.

23

Table 5. Private Fuel Storage Facility License Fee Cost Recovery Status (Period 3)

LICENSE FEE COST RECOVERY STATUS JOB CODE: J5226 l TITLE: Private Fuel Storage Facility PERIOD: November 21-December 18,1998 l

TAC OR INSPECTION TASK DOCKET IDENTIFICATION PERIOD CUMULATIVE COSTS NUMBER FACILITY NAME NUMBER NUMBER COSTS CONTRACT TO DATE

(

l Private Fuel Storage 72-22 L22462 $6,439.50 $143,784.09 l 20-1405-04i Facility Note: Costs include 4 pe cen: actual base fee but not award fee, which is determined annually. l t

e 8

L .>

%4

O

g. O *w APPENDIX Planned and Actual Costs, and Cost Variances - '

Period 3-FY1999 l

l 1

I

. _ . , _.,J. _ , . _ , _ _ , _ . . . ~ . . .. . , _ _ , . . _ . . . . . _ . . _ - . . . _ , . _ . _ _ . . . . _ . , . . . _ , . - . ...--r_.- -._ , _ . . . - - . . . . . - . , - . - - - - . . , . - . .

9-3

~

9 CNVRA COMPOSFIT:. ,

TOT Al. I'5 TIM ATT: mTT 04 05 06 07 08 09 10 11 12 13 Tctal I IIIAI 01 02 03 1.096.894 1.085.782 1.063.267 1.072.805 1.028,837 t.062.252 1.027.057 2.890.489 E;a rd Cost 986.944 946.700 956.845 1.094.980 1.097.073 1.110.670 0 0 0 0 0 0 0 0 0 0 2.544.533 Act Pd Con 839.018 927.852 727.663 0 0 0 0 0 0 0 0 0 0 345.956 Vanance.$ 97.926 18.848 229.182 00% 00% 00% 00% 00% 00% 00% 00% 00% 00% 12.0 %

Vanance % 99% 2.0% 24 0 %

3.990.469 5.087.542 6.198.212 7.295.106 8.380.889 9.444.156 10.516.% l 13.545.798 12.608.050 13.635.107 -

Est fY Onoul 986.944 8.933.644 2.8 % .489 1,816.870 0 0 0 0 0 0 0 0 0 0 Act FY Cumet 889.018 2.544.533 00% 00% 00% 00% 00% 00% 004 00% 0.0% 00%

% Complete 6.5% 133% 18.7 %

116,774 0 0 0 0 0 0 0 0 0 0 CumulVw.S 97.926 345.956 00% 00% 0.0% 00% 00% 00% 00% 00% 00% 00%

Cumul Var. % 9.9% 60% 120%

DIVISION OF WASTE MAN AGEMENT(DWM) 14074 win 02 03 04 05 06 07 08 09 10 II I2 13 Total ril.M 01 949.826 9 9).810 960395 949.263  % I.691 947,859 964.331 946.971  % 9.966 946.113 2.479.623 Est PJ Cmt 817.M0 823.053 833.930 798,762 0 0 0 0 0 0 0 0 0 0 2.156.874 Act Pd Cat 726.516 638.597 0 0 0 0 0 0 0 0 0 0 322.749 Vanance.$ 91.124 31.291 200.334 00% 00% 00% 00% 00% 00% 00% 0.0% 00% 00% 130%

Vanance. % 11.1 % 38% 23 9 %

3.429.449 4.380.239 5.340.654 6.289.917 7.251.608 8.199.467 9.163.804 10.110.775 I I .080.741 12.026.854 Est FY Ormal 817.640 1.640.693 2.479.623 0 0 0 0 0 0 0 0 0 0 Act FY Cumet 726.5I6 1.518.278 2.156.874 00% 00% 00% 00% 00% 00% 00% 00% 00% 00%

f  % Complete 60% I26% 179%

0 0 0 0 0 0 0 0 0 0 C iul var. $ 91.124 122.415 322.749 130% 00% 00% 00% 00% 00% 00% 00% 00% 00% 00%

Cumul Ver. % II.1% 7.5 %

CNWRA OPERA 110NS (CDPS) 1402-150 04 05 06 07 08 09 10 Il 12 13 Total 111A1 01 02 03 j 147.195 147.030 147.285 146.% 2 147.528 146.868 147.561 146.484 148.400 146.294 432.513 Est Pd Cost 144.171 144.172 144.170 110.960 0 0 0 0 0 0 0 0 0 0 360.402 Act Pd Cost 187.636 131.806 Vanance,$ 33.210 0 0 0 0 0 0 0 0 0 0 72.111 26.535 12.366 Vanance, % 86% 23.0 % 00% 00% 00% 00% 00% 00% 00% 00% 00% 00% 16.7 %

184%

432.513 579.708 726.738 874.023 1.020.985 1.168.514 1.315.382 1.462.944 1.609.428 1.757.828 1.904.122 Est FY Cumul 144.171 288.343 2e9.442 360.402 0 0 0 0 0 0 0 0 0 0 Act FY Cumul 117.636 00% 00% 00% 00% 00% 00% 00% 00% 0.0% 00%

% Ccciplete 62% 13 1 % 18 9 %

72.111 0 0 0 0 0 0 0 0 0 0 Cu nut Var.$ 26.535 38.901 135% 167% 00% 00% 00% 00% 00% 00% 00% 00% 00% 00%

Cumui Var % 184%

sh

IGNEOUS ACITVITY (IA) 1402-460 04 05 06 07 08 09 10 11 12 13 Tczal ITIN 01 02 03 50.322 49.496 30.438 49.184 50.440 49.123 50.558 48.975 51.139 48.944 144.727 EtJ N Cret 48.257 48.370 48.100 Act N Cost 53.948 43.638 0 0 0 0 0 0 0 0 0 0 146.292 48.705 (5.578) 4.462 0 0 0 0 0 0 0 0 0 0 (l 565)

Vanance.$ (448) 49% -11.5% 9.3% 00% 00% 00% 00% 00% 00% 00% 00% 00% 00% -l.1%

Vanance. %

96.627 144.727 195.049 244.545 294.983 344.167 394.607 443.731 494.289 543.265 594.404 643.348 EJ FY Curnul 48.257 Act FY Cumul 48.705 102.653 146.292 0 0 0 0 0 0 0 0 0 Gg 7.6% 16 0 % 22.7% 00% 00% 00% 00% 00% 00% 00% 0.0% 0.0% 00%

% Comg&te 0 0 0 0 0 0 0 0 0 0 ChmulYr.$ (448) (6.026) (1.565) 49% -6.2% -I l% 00% 00% 00% 00% 00% 00% 00% 0.0% 00% 00%

CumulVs.%

STRUCTURAL DEIURMAllON AND SEISMICITY (SDS) 1402 470 04 05 06 07 08 09 10 11 12 I) Total IIEM 01 02 03 68.731 70.062 68.421 70 lZ3 68.338 70.218 68.244 70,563 68.211 203.270 Est N Cost 67.808 67.809 67.653 69.787 82.453 61.960 0 0 0 0 0 0 0 0 0 0 209.047 Act N Cost 64.634 5.693 0 0 0 0 0 0 0 0 0 0 (5.777)

Vanance. $ 3.174 (14.644) 4.7% -21 6 % 84% 00% 00% 00% 00% 00% 00% 00% 00% 00% 00% -2.8%

Vanance. %

203.270 273.057 341.788 411.850 480.271 550.394 618.732 688.943 757,186 827.749 895.959 l

>s Est FY (Nmul 67.808 135.617 Act FY Cumul 64.634 147.087 209.047 0 0 0 0 0 0 0 0 0 0 l N G Cbmplete 7.2% 16 4 % 23.3 % 00% 00% 0.0% 00% 00% 00% 00% 0.0% 00% 0.0%

(5.777) 0 0 0 0 0 0 0 0 0 0 CNmul Vs. $ 3.174 (11.470) 47% '8 5% 00% 00% 00% 00% 00% 00% 00% 00% 00% 00%

timul Vs. % -2 8%

EVOLUllON OF THE NEAR-ITEtD ENVIRONMENT (ENFE) 1402M 02 03 04 05 06 07 08 09 10 Il 12 13 Total ITEM 01 81.461 81.603 80.479 81.716 80.327 81.843 79.889 82.016 79.825 82.960 79.693 232.48 t Est N Cxst 73.428 77.592 0 0 0 0 0 0 0 0 0 0 156,729 Act N Ccet 40.961 70.893 44.876 6.699 36.585 0 0 0 0 0 0 0 0 0 0 75.752 Vanance. $ 32.467 Vanance. % 44.2 % 86% 44.9 % 00% 00% 00% 00% 0.0% 00% 00% 00% 00% 00% 32.6 %

l tist FY ttmut 73.428 15l.020 232.481 314,084 394.563 476.279 556.606 638.449 718.338 800.354 880.179  % 3.139 1.042.832 Act FY Cumut 40.961 111.853 156.729 0 0 0 0 0 0 0 0 0 0

% Complete 39% 10.7 % 15.0 % 0.0% 00% 00% 00% 00% 0.0% 00% 0.0% 0.0% 0.0%

CNmui Var. $ 32.467 39.167 75.752 0 0 0 0 0 0 0 0 0 0 Cumul Var. % 44.2 % 259% 32 6 % 00% 00% 00% 00% 00% 00% 00% 00% 00% 00%

4, 4

m i

94 '

e CONTAINER LEE AND SOURCE TERM (CEST) .s ,

I402 570 I HD1 DI 02 03 04 05 06 07 08 09 10 II 12 13 Taal 63.460 85.848 85.152 85.973 85.092 86.011 85.0W) 86.072 85.057 86329 84,847 ' 168.550 Est N Cbst 62.502 62.588 Act N Cmt 78J64 91.542 73.352 0 0 0 0 0 0 0 0 0 0 243,458 Vanance. $ (l5.862) (28.954) (10.092) 0 0 0 0 0 0 0 0 0 0 (54.908)

Vananct. % -25.4% 46 3 % .l59% 00% 00% 00% 00% 00% 00% 00% 00% 00% 00% :29.1%  ;

Ea t'Y Cumut 62.502 125.090 188.550 274.398 359.550 445.523 530.615 6l6.626 701.716 37.788 872.845 959.174 I.044.022 Act W CNmut 78364 169.906 243.458 0 0 0 0 0 0 0 0 0 0

% Complete 7.5% 16.3 % 23 3 % 00% 00% 00% 00% 00% 00% 00% 00% 00% 00%

0%mul var. $ (15.862) (44.816) (54.908) 0 0 0 0 0 0 0 0 0 0 j Cumul Var. % -25 4 % -35 8 % -29 l % 00% 00% 00% 00% 0.0% 00% 00% 00% 00% 00%

I 111ERM AL EI1ECTS ON 11DW (TEF) 1402M)

ITEM 01 02 03 04 05 06 07 08 09 10 Il 12 13 1ctal Est W Cost 52.306 52.308 54.269 57.046 56.424 57.220 56.391 57.221 56332 57.407 56J31 58.052 56.218 158.883 j Act N Cost 36.405 46.858 34.955 0 0 0 0 0 0 0 0 0 0 118.212 i i

Vanance. S 15.901 5.457 19.314 0 0 0 0 0 0 0 0 0 0 40.671 1 i

104% 356% 00% 00% 00% 00% 00% 0.0% 00% 00% 00% 00% 256% j Vanance. % 30 4 %

Est FY Cumul 52.306 104.614 158.883 215.929 272.353 329.573 385.964 443.185 499.517 556.924 613.255 671.307 727.524 0 0 0 0 0 0 0 0 0

>e Act FY Cumul 36.405 33.257 118.212 0 ta  % Complete 50% 18.4 % 16.2 % 00% 00% 00% 00% 00% 00% 00% 00% 00% 00% t CumulVar$ 15.901 21.357 40.671 0 0 0 0 0 0 0 0 0 0 CumulVar % 30 4 % 20.4 % 256% 00% 00% 0.0% 00% 00% 0.0% 0.0% 00% 00% 00% i REPOSHURY Dl'. SIGN AND T1tERMAL-MECl{ANICAL LITECTS (RDBIE) l 1407-670 02 03 04 05 06 07 08 09 10 11 12 13 Total HDt 01  ;

Est N Cost 49.201 49317 49.I03 74.929 74.292 75.013 74.292 75.291 74.290 75.406 74.289 75.778 74.288 147.621 Act N Cest 47.865 44.034 49.942 0 0 0 0 0 0 0 0 0 0 141.841 Vanance. $ l.336 5.283 (839) 0 0 0 0 0 0 0 0 0 0 5.780 i Vsnance. % 2.7% 10.7 % - 1.7% 00% 00% 00% 00% 00% 00% 00% 00% 00% 00% 3.9% j Est W Cumut 49.201 98.518 147.621 222.550 296.842 371.855 446.147 521.438 595.728 671.134 745.423 821.208 895.490 I

Act W Cumul 47.865 91.899 141.841 0 0 0 0 0 0 0 0 0 0 '

% Complete 53% 103% 15 8 % 00% 00% 00% 00% 0.0% 0.0% 00% 00% 00% 00%  ;

4 Cumut var. 5 1.336 6.6l9 5.780 0 0 0 0 0 0 0 0 0 0 00% 00% 00% 00% 00% 00% 00% 00% ,,00% 00%

, Cumut var. % 2.7% 67% 39%

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DRY TRANSER SYS1EM (D13) 1405 420 03 04 05 06 07 08 09 10 11 12 13 Total fl134 01 02 16,604 16,451 16.880 16.365 16.993 16.206 17.3I1 16.206 17.341 16.048 31.803 Est N Cat 10.601 10.601 10.601 11,895 0 0 0 0 0 0 0 0 0 0 48,573 i Act N Ost 12.332 24.347 (13,746) (1,794) 0 0 0 0 0 0 0 0 0 0 (16,770)

Vanance $ (1.738)

Vanance, % -I6.3% 129.7 % -12.2% 00% 00% 00% 0.0% 0.0% 00% 0.0% 00% 0.0% 00% -52.7%

EQIT Omul 10.601 21,202 31.803 48.407 64.858 88.738 98.103 115.096 131.302 148.613 164.819 182.130 198.I79 Act FY Ormel 12,332 36.678 48.573 0 0 0 0 0 0 is 0 0 3

% Compine 6.2% 18.5 % 24 5 % 00% 00% 0.0% 00% 00% 00% 00% 00% 0.0% 00%

(15.476) (16.770) 0 0 0 0 0 G 0 0 0 0 Cumut ver. $ (1.731)

Ormul Var. % -16.3% -73.0% -52.7% 00% 00% 00% 00% 00% 00% 00% 00% 00% 0.0%

CENTRALIZED IN1TiRIM STORAGE FACIL2TY (CESF) 14054 v) 01 02 03 04 05 06 07 08 09 10 18 12 13 Total IIEM 13,122 12,687 14,538 13.888 14.614 13,504 14.933 13,531 15.109 13.416 15.222 13.416 53.5 %

Est N Cat 27.787 Act N Cost 18.855 4.821 0 0 0 0 0 0 0 0 0 0 50.183 26.505 Vanance $ (5,733) 7,866 0 0 0 0 0 0 0 0 0 0 3.416 I.282 4.6% -43.7% 62.0 % 0.0% 00% 0.0% 00% 00% 00% 00% 00% 00% 00% 64%

Vanance. %

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% Owpine 133 % 23.1 % 25.6% 0.0% 0.0% 0.0% 00% 00% 00% 00% 00% 00% 00%

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Osmul Var. %

PRIVATE ITJEL STORAGE FAClllTY (PT3F) 1405 440 01 02 03 04 05 06 07 08 09 10 11 12 13 Total TTEM 10,748 6.997 13,622 13.187 14.024 13.186 14.216 13.040 I4,249 12.844 14.249 12.731 24.757 Est N Cost 7.012 5,023 6,198 0 0 0 0 0 0 0 0 0 0 23,161 Act N Cost II,940 Vanance, $ 5,725 (4.928) 799 0 0 0 0 0 0 0 0 0 0 1.5%

vanance, % 53.3 % -70.3% 11 4 % 00% 00% 00% 00% 00% 00% 00% 0.0% 00% 00% 6.4%

51.566 65.590 78.776 92.992 106.032 120.28I 133.I25 147,374 160,106 Est FY Cumul 10.748 17.760 24.757 38,179 ,

Act FY Cumul 5.023 16.% 3 23.161 0 0 0 0 0 0 0 0 0 0

% Complete 31% 106% 14.5 % Or% 00% 0.0% 0.0% 0.0% 00% 0.0% 0.0% 0.0% 00%

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