ML20210G965

CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990605-0702

ML20210G965
Person / Time
Site:	Three Mile Island
Issue date:	07/15/1999
From:	CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES
To:	NRC
Shared Package
ML20210G951	List: ML20210G947 ML20210G965
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, REF-WM-11 HLWR, PMPR-99-10, NUDOCS 9908030244
Download: ML20210G965 (44)

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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 June 5,1999 - July 2,1999 PMPR No. 99-10 July 15,1999 80 0 990715 WM-11 PDR

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TABLE OF CONTENTS Section Page TA B LES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ................. ..... . ... . iv ABBREVIATIONS . . . . . . . . .................. . . ...... .. ... ... . ... ., ,y EXECUTIVE

SUMMARY

-PERIOD 10 . . . . . . . . . . . . . . . ... .... . ..... .. . . xi 1 TECHNICAL . . . . . . . . . . . . .... ........................ ..... ............ I 1.1 CNWRA Operations (COPS) . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . .. ... . I

1. Igneous Activity (IA) . . . . .................... .. . ...... .... . . 3 1.3 Structural Deformation and Seismicity (SDS) .............. ..... . .. ... . 4 1.4 Evolution of the Near. Field Environment (ENFE) . . . . ......... . ....... .. 5 1.5 Container Life and Source Term (CLST) . . . . . . . . . . . . . . . . .... .... ...... 6 1.6 Thermal Effects on Flow (TEF) . . . . . . . . ......... .......... . ...... .8 1.7 Repository Design and Thermal-Mechanical Effects (RDTME) . . . . . . . . .....,. 9 1.8 Total System Performance Assessment and Integration (TSPAI) . . . . ... . .. . I1 1.9 Activities Related to Development of the NRC High. Level Waste Regulations (ARDR) . . ................. ................ . ....... 12 1.10 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC) ....... . 13 1.11 Radionuclide Transport (RT) . . . . . . . . . . . . ......................... . .. 14 1.12 Tank Waste Remediation Systems (TWRS) . . . . . . . ........ ........... .. 16 1.13 Three Mile Island Unit 2 Independent Spent Fuel Storage Installation (TMI.2 ISFSI) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 1.14 Dry Transfer System (DTS) . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. ......... 17 1.15 Centralized Interim Storage Facility (CISF) . . . . . . . . . . . . . . .... ......... 17 1.16 Private Fuel Storage Facility (PFSF) . . . . . . . . . . . . . . . . . . . . . . . . ...... . . 17 1.17 Savannah River Site Aluminum-Based Spent Fuel (SRSASF) . . . . ... . ..... 17 2 M ANAGEMENT ISSUES . . . . . . . .. . . . . . . . . . . . . . . . . . ..... . .... . ... . ... 18 3 MAJOR PROBLEMS ... .............. ...... .. ... ...... ..... 18 4

SUMMARY

OF SCHEDULE CHANGES .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 5

SUMMARY

OF FINANCIAL STATUS . . . . . . . . .. ..... ........... ......... 18 APPENDIX-Planned and Actual Costs, and Cost Variances Period 10-FYl999 l

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TABLES Table Page 1 CNWRA Core Staff-Current Profile and Hiring Plan * (Period 10) . . . . . . . . . . . . . . . . . . . 22 2 CNWRA Core Staff-Summary by Area of Concentration (Period 10) . . . . . . . . . . . . . . ... 23 3 Summary of Schedule Changes (Period 10) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . 24

.4 Deliverables (Period 10) . ..... .. .... .............. .................. . .. 25 5 Financial S tatu s (Period 10) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26 6- Private Fuel Storage Facility License Fee Cost Recovery Status (Period 10) . . . . . . ...... 27 iv l I

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ABBREVIATIONS ID One Dimensional CDROM Compact Disk Read Only Memory 2D Two-Dimensional CDTS Commission Decision Tracking System 3D Three-Dimensional CEB Center for Environ mental Biotechnology AA Atomic Absorption CEC Commission of the European AAl 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 Clin Calico liills Nonwelded Tuff ACNW Advisory Committee on Nuclear Waste CIAC Computer incident Advisory Capabihty ACRS Advanced Computer Review System CISF Centrahzed Interim Storage Facihty ACS American Chemical Society CLST Container Life and Source Term ADAMS Agencywide Documents Access and CM Configuration Management i

Management System CNWRA Center for Nuclear Waste Regulatory J AECL Atomic EnerFy of Canada Limited Analyses AES Atomic Emission Spectrometry COI Conflict ofInterest AWF Antler Wash Fault COPS CNWRA Operations AGU American Geophysical Union CPP Cyclic Potentiodynamic Polarization Al Administrative item CQAM CNWRA Quality Assurance Manual ALTS Apache Leap Test Site CRG Center Review Group AML Areal Mass Loading CRM Corrosion Resistant Material ANS Amencan Nuclear Society CRWMS Civilian Radioactive Waste ANSI American National Standards Institute Management System AO Annotated Outline CSCS Constrained Stochastic Climate AP Administrative Procedure Simulator APB Acid-Producing Bacteria CSH Calcium Silicate flydrate AR Assessment Report CSPE Corrosion Science and Process ARDR Activities Related to Development of Engineenng the NRC High-Level Waste Regulations DAS Data Acquisition System ASCE American Society of Civil Engineers DBE Design Basis Event ASCII American Standard Code for DC Division of Contracts i information Interchange DCAA Defense Contract Audit Agency I ASLB Atomic Safety and Licensing Board DCB Double Cantilever Beam ASME American Society of Mechanical DCF Dose Conversion Factor Engineers DCM Dual Continuum Model ASTM Amencan Society for Tesi :and D&D Decommissioning and Decontammation Materials DECOVALEX Development of Coupled Models and ASU Arizona State University "Dicir Validation Against Experiments ATDTS Automated Technical Data Tracking in Nuclear Weste Isolation System DEIS Draft Environmental Impact Statement BDCF Biosphere Dose Conversion Factor DEM - Digital Elevation Model BEG Bureau of Economic Geology DF Dilution ? actor BFD Basis for Design DFCSS Division of Fuel Cycle Safety and BM Bare Mountain Safeguards BMF Bare Mountain Fault DIE Determination of importance BTP Branch Technical Position Evaluation l cal Color Aheration Index DIMNS Division of Industnal and Medical CAM Corrosion Allowance Material Nuclear Safety CAR Corrective Action Request DKM Dual Permeability Model l

CCDF Complementary Cumulative DLG Digital Line Graph Distribution Function DLM Diffuse Layer Model l CCL Commitment Control log DNAG Decade of North Amencan Geology CCM Constant Capacitance Model DNFSB Defense Nuclear Facilities Safety Board CD-R CDROM Recordable DOE U.S. Department of Energy CDF Cumulative Distnbution Function DOE-DP U.S. Department of Energy Defense CDOCS Consolidated Document Management Program System V

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.+ 3 ABBREVIATIONS (cont'd)

DOE-RU U.S. Department of Energy Regulatory GET General Employee Training Unit GFM Geological Framework Model DRA Division of Regulatory Applications GHGC GeoHydrology and Geochemistry DST Drift Scale Test GIA Generalized Importance Analysis DTED Digital Terrain Elevation Data GIS Geographic Information System DTS Dry Transfer System GLGP Geology and Geophysics DWM Division of Waste Management GMS Goundwater Modeling System DWPF . Defense Waste Processing Facility GPS Global Positioning System EA Environmental Assessment GROA Geologic Repository Operations Area EBS Engineered Barrier System GSA Geologic Society of America ECM Equivalent Continuum Model GTFE Great Tolbachik Fissure Eruption ECRB Enhanced Charactenzation of Repository GUI Graphics User Interface Block GWB Geochemist's Workbench EDO Office of the Executive Director for GWS1 Groundwater System Integration Operations GWTT Groundwater Travel Time EDX Energy-Dispersive X Ray Spectroscopy . HE Hydrogen Embrittlement EIS Environmental Impact Statement HLW High-Level Waste EM Element Manager HRTEM High-Resolution Transn.;ssion Electron EMPA Electron MicroProbe Analysis Microscopy ENE East-Northeast IA Igneous Activity ENFE Evolution of the Near-Field IBM International Business Machhes Environment ICP Inductively Coupled Plasma EnPA Energy Policy Act of 1992 ICPP Idaho Chemical Processing Plant ENS European Nuclear Society ICRP International Commission on EPA U.S. Environmental Protection Agency Radiological Protection EPR Electrochemical Potentiokinetic IDLH Immediately Dangerous to Life and Reactivation Health EPRI Electric Power Research Institute IHLRWMC International High-Level Radioactive EQA External Quality Assurance Waste Management Conference and EROS Earth Resource Observation System Exposition ESF Exploratory Studies Facility IM Intermediate Milestone ESP Environmental Simulation Program IME Industrial Mobilization Exemption EW East West IMS Information Management Systems EWDP Early Warning Drilling Project INEEL Idaho National Engineenng and EXAFS Extended X Ray Absorption Fine Environmental Laboratory Structure INETER lustituto Nicaraguense de Estudios FCRG Format and Content Regulatory Guide TERritoriales FDSHA Fault Displacement and Seismic Hazard INTEC Idaho National Technology and Analysis Engineering Center

- FEHM Finite Element Heat and Mass Transfer 1/O Input / Output FEM Finite Element Method IP Inspection Procedure FEP Features, Events, and Processes IPA Iterative Perfonaance Assessment ITRDC Federally Funded Research and IR&D Internal Research & Development Development Center IRIS Interim Records information System FIT Fast Fourier Transform IRM Office ofInformation Resources FOC Field Operations Center Manacement FTE Full-Time Equivalent ISI Integrated Subissue FTP File Transfer Protocol IRSR issue Resolution Status Report FY Fiscal Year ISA Intregated Safety Analysis FYTD Fiscal Year-To-Date ISFSI Independent Spent Fuel Stotage GDF Ghost Dance Fault Installation GEM General Electrochemical Migration ISM Integrated Site Model GEOTRAP Geologic Transport of Radionuclides IVM Interactive Volume Modeling Predictions JC Job Code GERT General Employee Radiological JPL Jet Propulsion Laboratory Trainirj JRC Joint Roughness Coefficient Vi t

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ABBREVIATIONS (cont'd)

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KESA Key Elements of Subsystem Abstraction NRC Nuclear Regulatory Commission KTl Key Technicalissue NS North-South LA License Application NTS Nevada Test Site LAAO License Application Annotated Outline NUREG NRC Technical Report Designation LAN Local Area Network NWPA Nuclear Waste Pohey Act, as amended LANL Los Alamos National Laboratory NWTRB Nuclear Waste Technical Review Board LARP License Application Review Plan OBES Office of Basic Energy Sciences LAW low-Activity Waste OCRWM Office of Civilian Radioactive Waste LBNL Lawrence Berkeley National Laboratory l Management '

LBT Large Block Test OGC Office of General Counsel LilS Latin flypercube Sampling OITS Open-Item Trackmg System LITC Lockheed Information Technology OMB Office of Management and Budget Company OPS Operations Plans for the Repository LLC Limited Liability Company Program LLNL Lawrence Livermore National ORR Operations Readmess Review l

Laboratory ORS Overall Review Strategy LLW Low-Level Waste OWFN One White Flint North LMAES lockheed Martin Advanced PA Performance Assessment Environmental Systems PAAG Performance Assessment Advisory LSS Licensing Support System Group LWR Light Water Reactor PC Personal Computer M Molar PCITCP Personal Computerfrransmission  ;

Ma Million Years Ago Control Protocol MAI Mean AnnualInfiltration PCT Product Consistency Test MAP Mean AnnualPrecipitation PDF Probability Distribution Function MAT Mean AnnualTemperature PDR Pubhc Document Room MC Monte Carlo PEL Permissible Exposure Limit METRA Mass and Energy TR Ansport PEM Program Element Manager MGDS Mined Geologic Disposal System PER Prelicensing Esaluation Report MH Mechanical-Hydrological PEST Parameter Estimation i

MIC Microbially Influenced Corrosion PFA Per0uoroalkoxy MINC Multiple Interacting Continua PFD Probabilistic Fault Displacement MIT Massachusetts Institute of Technelogy PFDHA Probabilistic Fault Displacement MM Major Milestone Hazard M&O Management and Operations PFS Private Fuel Storage MOU Memorandum of Understandmg PFSF Private Fuel Storage Facility MPC Multi-Purpose Canister PHA Prelimisiary Hazard Analysis MRS Monitored Retrievable Storage PI Pnneipal Investigator MSS MultiSpectral Scanner PMDA Program Management. Policy MTU Metric Tonnes of Uranium Development and Analysis Staff NAS National Academy of Sciences PMPR Program Manager's Periodic Report NAWG Natural Analogue Working Group PMT Photo-Multiplier Tube NCR NonConformance Report PNNL Pacific Northwest National Laboratory NEA Nuclear Energy Agency PO Project Officer NEl Nuclear Energy Institute PPE Prepassivated Platinum Electrode NFS Network File Server PRA Probabilistic Risk Assessment NIOSH National Institutes Of Safety and Health PRT Peer Review Team NIR Near-infrared PSAG Probabihstic System Assessment Group NIST National Institute of Standards and PSHA Probabilistic Seismic Hazard Analyses Technology FTFE Polytetrafluoroethylene NMSS Office of Nuclear Matenal Safety and PTn Paintbrush Nonwelded Tuff Safeguards PVIIA Probabilistic Volcanic Hazards NNE North-Northeast Assessment NNW North-Northwest PVHVIEW Probabihty of Volcanic Hazards NOAA National Oceanographic and VIEW Atmospheric Administration PVM Parallel Virtual Machine Vii

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ABBREVIATIONS (cont'd)

, a PWR Pressurized Water Reactor SRD Software Requirements Description

. QA Quality Assurance SRS Savannah River Site QAP Quality Assurance Procedure SRSASF Savannah River Site Aluminum-QRAM Quality Requirements Application Based Spent Fuel Matrix SS Stainless Steel RAI Request for AdditionalInformation SSC Structures, Systems, and Components RASA Regional Aquifer System Analysis STEM Scanning Trrinsmission Electron RDCO Repository Design, Construction, Microscopy and Operations STP Staff Technical Position RDTME Repository Design and Therrnal. SUFLAT Stochastic Analyses of Unsaturated Mechanical Effects Flow And Transport REE Rare Earth Element SVF Springerville Volcanic Field REECO Reynolds Electrical and Engineering SwRI Southwest Research Institute Company, Inc. SZ Saturated Zone RES Omce of Nuclear Regulatory Research TA Technical Assistance RFP Request For Proposal TAN Test Area North RH Relative Humidity TBD To Be Determined RSRG Real Space Renormalization Group TBM Tunnel Bonng Machine RT Radionuclide Transport TCP/IP Transmission Control Protocol /

RTS Radwaste Treatment System Internet Protocol SAIC Science ApplicationInternational TDEM Time-Domain Electro-Magnetic Corporation TEDE Total Effective Dose Equivalent SAP Standards Approval Package TEF Thermal Effects on Flow SAR Safety Analysis Report . TEM Transmission Electron Microscopy SCA Site Characterization Analysis TFE Tetrafluoroethylene SCC Stress Corrosion Cracking TilC Thermal-Hydrologic-Chemical SCCEX Substantially Complete Containment TilMC Thermal-liydrologic-Mechanical-Example ' Chemical SCE Standard Calomel Electrode T-L Transverse Longitudmal SCFF Southern Crater Flat Fault TLM Triple-Layer Model SCM Surface Complexation Models TM Thermal-Mechanical SCP Site Characterization Plan TMH Thermal-Mechanical-Hydrological SCR Software Change Report TMI2 Three Mile Island Unit 2 SDMP Site Decommissioning Management Plan TMS The Minerals Metals, and Matenals SDS Structural Deformation and Seismicity Society

$ECY Seccary of the Commission, Office of *1DP Technical Operating Procedure the (NRC) TP Technical Position SELM Spectral Element Method TPA Total-system Performance Assessment SEM Scanning Electron Microscopy TPI Time Period of Regulatory Interest SER Safety Evaluation Report TR2 DOE Seismic Topical Report No. 2 SFPO Spent Fuel Project Office TRG Technical Review Group SFVF San Francisco Volcanic Field TSAR Topical Safety Analysis Report SGI Silicon Graphics Inc. TSPA Total System Performance Assessment SGML Standard Generalized Markup TSPA-VA Total System Performance Assessment-Language Viabihty Assessment SHE Standard Hydmgen Electrode TSPAl Total System Performance Assessment SHT Single Heater Test and Integration SKI Swedish Nuclear Power Inspectorate TSw-Chnv Topopah Spring Welded-Calico S-L Short Transverse Lonptudinal liills Nondtric SLAR Side Looking Airborne Radar TVD Total Variation Diminishing SNF Spent Nuclear Fuel TWFN Two White Flint Nonh SNL Sandia National Laboratories TWINS Tank Waste information Network SOW Statement Of Work System SRB Sulfate-Reducing Bacteria TWRS Tank Waste Remediation System SRBS Shafts, Ramps, Borcholes, and Their UA University of Arizona Seals Viii l

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ABBREVIATIONS (cont'd)

.UACH Universidad Aut6nomade Chihuahua UCLA University of California, Los Angeles UDEC Umversal Distinct Element Code UK United Kingdom UNLV University of Nevada. Las Vegas UNM University of New Mexico

. UR Uranium Recovery .

'U.S. United States USDA ~ U.S. Department of Agriculture USFIC Unsaturated and Saturated Flow Under Isothermal Conditions USGS- U.S. Geological Survey UTM Universal Transverse Mercator 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 WFO Work For Others WGB Western Great Basin

-WIPP Waste Isolation Pilot Plant '

WNYNSC . Westem New York Nuclear Service Center WOL Wedge-Opening Loading .

WP Waste Package WSRC Westinghouse Savarmah River Company WSS Waste Solidification Systems WTSO Washington Technical Support Office WVDP West Valley Demonstration Project WVNS West Valley Nuclear Services WWW World Wide Web XPS X-Ray Photoelectron Spectroscopy

.XRD X-Ray Diffractometry YM Yucca Mountain l' YMP Yucca Mountain Project YMR Yucca Mountain Region YMRP . Yucca Mountain Review Plan YMSCO Yucca Moimtain Site Characterization l Office

-YTD ' Year-To-Date l

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SUMMARY

-PERIOD 10 In the Division of Waste Management (DWM) Job Code (JC), the Center for Nuclear Waste Regulatory Analyses (CNWRA) staff transmitted PeSa Blanca Natural Analog Data in Performance Assessment Models-Journal Paper; Dripping into Cavities from Unsaturated Fractures Under Evaporative Conditions; j Flow in Unsaturated Fractured Porous Media: Hydraulic Conductivity of Rough Surfaces: Review and Analysis of Hydraulic and Tracer Testing at the C Holes Complex Near Yucca Mountain, Nevada: Uranium Chemistry and Isotopy in Waters and Rocks at PeSa Blanca-Journal Paper; Stochastic Analysis of Early Tracer Arrivals in a Multiple-Fracture Pathway-Journal Paper; and input to RT IRSR, Revision 1-Letter Report. The staff produced papers and posters for presentation at various technical meetings. These papers l have been or will be submitted for acceptance in recognized technical journals. Staff also participated in workshops, symposia, and other technical meetings.

The DWM JC year-to-date (YTD) cost variance was 10.7 percent. Spending rose from the previous period as a result of increased activity in snecific key technical issues, and the cumulative cost variance decreased again this fiscal period.

In the Tank Waste Remediation System (TWRS) JC, staff delivered a final report on Hanford Tank Waste i Remediation System Pretreatment Chemistry and Technology and a revision of the Nuclear Regulatory Commission Procedure for Inspection of TWRS-P Quality Assurance Program Implementation, which i incorporated NRC comments. The YTD cost variance was 21.0 percent. Spending again decreased from last l period; the cumulative variance has been relatively constant for four periods.

In the Three Mile Island Unit 2 (TMI-2) Independent Spent Fuel Storage Installation (ISFSI) JC, the annual CNWRA Quality Assurance audit considered this project. This project now is closed.The YTD cost variance for the TMI-2 ISFSI was -2.7 percent. '

In the Dry Transfer System (DTS) JC, staff continued developing the DTS draft safety evaluation report and conducted preparatory work for the U.S. Depanment of Energy and the NRC meeting on the Second Round Request for Additional Information. The YTD cost variance was 7.1 percent, reflecting a substantial rise in spending from last period.

1 In the Centralized Interim Storage Facility (CISF) JC, staffcontinued detailed technical reviews of the topical report on HI-STAR /H1-STORM cask system dep!oyment at high-seismic sites and literature related to the computer code RISKIND. The YTD cost variance for the CISF was 23.8 percent. Spending again decreased from the previous period, but the cumulative percentage variance has remained relatively constant over the last three periods.

In the Private Fuel Storage Facility JC, staff engaged in exterm.ve interactions with NRC staff to prepare the NRC final positions on five Group I contentions. The YTD cost variance was 5.0 percent. Spending estimates rose along with actual spending.

In the Savannah River Site Aluminum-Based Spent Fuel JC, staff nearly completed reviews of the DOE reports on dissolution of Al-based spent fuel, fuel processing, and disposability assessment and continue to prepare Review of the U.S. Department of Energy Evaluation of Aluminum-Based Spent Nuclear Fuel-Final Report. The YTD cost variance was 18.4 percent, following an adjustment to estimated spending.

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l CNWRA PROGRAM MANAGER'S PERIODIC REPORT ON ACTIVITIES OF THE CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES TITI,E Center for Nuclear Waste Regulatory Analyses (CNWRA)

CONTRACTOR: Southwest Researct, Institute (SwRI) 6220 Culebra Rond, San Antonio, Texas 78238-5166 CONTRACT NO: NRC-02-97-009 JOH CODES: D1035, J5164,35186, J5206,15226, 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 PERiOn OI' THIS REPORT: 06/05/99-07/02/99 I TECHNICAL 1.1 CNWRA Operations (COPS)

In addition to a wide range of day-to-day activities, accomplishments in the management and planning area included (i) meeting with an NEI representative and also conducting a tour of CNWRA laboratory facilities;(ii) participating in the NRC/CNWRA management and ACNW meetings; (iii) reviewing the status of CNWRA spending, scheduling, and staffing with NRC management; (iv) providing information concerning the development of NRC budgets for the next two FYs; (v) addressing COI-related topics among the NRC, SwRI, and CNWRA management staffs; and (vi) participating in weekly HLW Management Board meetings.

For the first time since an annual budget of $3,000 was allocated for CNWRA nonexempt staff overtime several years ago, spending for such overtime will exceed this amount.

Expenditures for nonexempt staff overtime have been associated primarily with IMS-related activities that should not be accomplished during normal working hours: (i) backup of data on UNIX-based servers,(ii) maintenance of hardware / software in UNIX- and NT-based servers and certain " walk-up" clients, (iii) installation and reconfiguration of failed disks on specific servers / clients and router s, and (iv) adjustments to hardware / software affecting LAN operation. Other overtime for CNWRA clerical staff has been related to completion of OPS deliverables. Spending on overtime will be monitored to ensure the prudent expenditure on necessary operational activities.

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. J. ,l, The status of CNWRA staffing is indicated in table 1. During period 10, intensive recruitment continued and several sources were used to identify potential candidates A nuclear engineer joined the staff this period as a core staff member. A limited-term geotechnical engineer and a geochemist will begin work in period 11.

Computer system support activities encompassed (i) continuing the use of consultants to develop and modify software and perform systems administration for the Sun Microsystems, Silicon Graphics, and Windows NT servers; (ii) installing and upgrading the desktop compt.ters for basic system standardization and Y2K compliance;(iii) pursuing the request for revision of the CNWRA Security System (firewall); (iv) updating all hardware / software inventory records; (v) participating, as requested, in the monthly NRC/CNWRA Computer Coordination meeting; (vi) initiating the development of the CNWRA Computer Requirements for FY2000-Letter Report; and (vii) maintaining LAN operations.

QA activities included (i) coordinating the annual CNWRA QA audit; (ii) conducting surveillances, issuing nonconformance reports and corrective action requests, as required, and working with cognizant staff in response to these reports; (iii) supporting the application of configuration control for CNWRA scientific and engineering software ready for release; (iv) preventing organizational col through SwRI RFP reviews: (v) performing QA verification checks on each CNWRA deliverable; (vi) providing QA indoctrination for new CNWRA staff members and consultants; and (vii) planning for an August 1999 presentation of the Training Module on Observation Audit Techniques at the NRC. The annual CNWRA QA audit was completed this period and was observed by several NRC staff.

In the next period, the CNWRA staff expects to (i) begin developing the OPS for FY2000; (ii) continue to offer input to and participate in various NRC/CNWRA discussions / meetings relative to budget and resource requirements for FY1999,2000, and 2001 together with participation in discussions / meetings related to the FY2000 OPS: (iii) aggressively pursue recruitment for unfilled core staff positions;(iv) continue use of consultants to mitigate staff attrition, oversee administration of server hardware and systems / applications software and changes in client hardware / software, develop new and modify existing databases and spreadsheets, continue development of the CNMM Computer Requirements for FY2000-Letter Report, and examine the LAN configurvions, including the pursuit of CNWRA firewall changes, for necessary modifications to maintain effectivenes.s; and (v) provide CNWRA LAN operation and maintenance suppet.

In addition, the staff will (i) participate in the response to the CARS that resulted from the annual CNWRA QA audit; (ii) deliver the FY1999 CNWRA QA Audit-Letter Report; (iii) perform scheduled and unscheduled QA surveillances;(iv) conduct QA indoctrinations for CNWRA staff and consultants;(v) review SwRI RFPs ior potential col;(vi) perform QA verification checks on each CNWRA outgoing deliverable; and (vii) prepare to conduct the second presentatica of the Training Module on Observation Audit Techniques to appropriate NRC staffin August 1999.

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l 1.2 Igneous Activity (IA)

The 110* ACNW meeting was held at the CNWRA in San Antonio, Texas, this period.

Staff presented the ACNW with results of volcanism risk analyses, a synopsis of volcanism probability models, an evaluation of realism and conservatism in current NRC-TSPA l

analyses, and status on post-VA progress for issue resolution with the DOE. Current risk j analyses show that volcanic disruption contributes a maximum expected annual dose of J around I mrem /yr at about 1,000 yr following closure of the proposed repository. These analyses have appreciable uncertainties influenced by likely underestimates of the number of WPs disrupted during volcanic events and likely overestimates of the airborne particle concentrations through time. Annual probabilities of volcanic disruption for the proposed repository site on the order of 104are more consistent with available site data than estimates of a 104or s 10-8. Although many parameters and models in current NRC-TSPA igneous activity calculations are realistically constrained, models for magma interactions i with the EBS are based on conservative interpretations oflimited data. Technical bases are needed to evaluate possible underestimates in the number of WPs disrupted during volcanic events, and possible overestimates in ? %ne particle concentrations through time. The

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presentation concluded that although stati have technical concerns with analyses presented I by the DOE in the TSPA-VA, informal post-VA interactions with DOE staff are l

contributing effectively to subissue resolution. All participants agreed that the DOE license l application will need a clear and credible treatment ofigneous activity.

1 Acceptance criteria and review methods for the KTI subissue on probability of igneous '

disruption are being addressed in the YMRP section on scenario analysis. The consequence subissue is addressed in the model abstractions, volcanic disruption of the WP, airbome transport of radionuclides, and dilution of radione Ules in soil due to surface processes integrated subissues.

Development continued of essentially nonoscillatory numerical models for magma-repository interactions. The model now uses air as the gas species in the drift prior to injection of the magma into the drift and in front of the shock wave. At the University of Bristol, progress was made on physical analog models for magma-repository interactions.

A physical analog model for ash plume dispersion was constructed and preliminary tests of the model conducted. This model will be used to assess the dispersion of mixtures of high- and low-density material in the atmosphere, such as mixtures of volcanic ash and HLW. Results of this physical analog model will be compared to the results of numerical codes used in PA. The model will be modified in the future to include an electromagnetic method of monitoring rates of sediment accumulation in the tank.

Coding for a magnetic inversion model using Bayesian inversion techniques progressed.

This code will be used to model and evaluate magnetic anomalies identified in the YMR by staff and the DOE. This code also will be useful for modeling geophysical anomalies associated with subsurface geologic structures in Fortymile Wash and the Amargosa Desert, which are used in hydrogeologic models.

Two QA audits of IA were performed during this period and no nonconformance was identified. Staff participated in a 3-day meeting of the National Research Council panel reviewing the U.S. Geological Survey volcanic hazards program. Preparations were made for field work in Owen's Valley, California, to perform geophysical surveys to correlate 3

D '9; volcanic and seismic hazard rates to the rate of the GPS strain. These preparations included developing and documenting several hardware components for the ground . magnetic surveying system. The SwRI differential GPS surveying system documentation was completed. Java applets for modeling geophysical data in the field were prepared and documented. The staffintegrated computer codes used to gather real-time geophysical data and post-process these data under TOP-018 Software QA requirements. Staff revised sections of the TSPAI-KTI IRSR, Revision 2, on scenario analyses, model abstractions, volcanic disruption of the WP, and airborne transport of radionuclides. Preparations also began for multiple presentations at the International Union of Geodesy and Geophysics meeting in Birmingham, England.

In the next period, staff will travel to the University of Bristol to evaluate the results of ongoing numerical and analog experiments of magma-repository interactions, focus on remaining activities, and resolve details of planned investigations at the CNWRA during the remainder of the FY. Staff will present ongoing work at the International Union of Geodesy and Geophysics meeting in Birmingham, England, and participate in the external review of TPA during next period. Review will continue on the YMRP and development

- of the FY2000 OPS.

1.3 Structural Deformation and Seismicity (SDS)

Period 10 activities focused mainly on preparing the IRSR KTI, Stmetural Deformation and Seismicity, Revision 2. This included completion of sensitivity studies of direct WP rupture from faulting in the repository using the FAULTO module of the TPA code, review of several new attenuation functions and their effects on the classification of faults, continued structural analysis of the DOE GFM 3.1 using cross sections and fault displacement data, incorporation of new data and concepts on fracturing at YM, and reanalysis of crustal conditions. A number of new and revised sections were incorporated into the working draft of the IRSR Revision 2.

Staff began organizing and analyzing of the field data collected last period to study the structural and sedimentological architecture of the alluvial aquifer. This included electronic construction of photo mosaics from digital photographs of the alluvium exposures in the banks of Fortymile Wash.

Staff continued studying strain partitioning in the Volcanic Tablelands near Bishop, California. This study will determine the effects of strain rate on seismicity and volcanism and also addresses concerns raised by the Wernicke GPS study of strain rate in the YMR.

3DStress software development resumed. Several minor concerns were debugged and version 1.3.1 was submitted for copyright.

A CNWRA consultant attended the quarterly meeting of the DOE and UNLV group studying thermochronology of YM. Results ofinitial petrographic studies of samples from material filling faults intersected by the ESF were presented to the group by the consultant.

Fieldwork at Live Yucca Ridge was completed. This included additional mapping as well as rechecking of previous mapping. Mapping was aided by the GPS determination of locations. Checks of previous mapping using the GPS system relocated all previous 4

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. I fractures that were searched for. The goal of the mapping is to better document the fracturing process and fracture interval over a larger area than the cleared DOE pavements l

previously mapped by DOE and CNWRA. j Staff participated in the 110* ACNW meeting and an NEI meeting, both held at the CNWRA in San Antonio, Texas. This included a tour of the Physical Analog Modeling Laboratory and a demonstration of the 3DStress software capabilities.

In the next period, staff will concentrate on revision 2.0 to the SDS IRSR. In addition, analysis will continue of Fortymile Wash alluvial structures and assessment of strain partitioning in the Volcanic Tablelands. Modifications and additions to the 3DStress

software leading to version 2.0 will begin, following TOP-018 procedures.

i l 1.4 Evolution of the Near-Field Environment (ENFE)

Staff contributed to the 110th ACNW meeting at the CNWRA in San Antonio, Texas, l June 28-30,1999. A presentation was given on ENFE KTI work with technical emphasis i on newly developed, coupled THC model results using the MULTIFLO code and on recent l

calculations of the sensitivity of repository performance to source-term models for vanous near-field environmental conditions. l The deliverable, Pena Blanca Natural Analog Data in Performance Assessment Models-Journal Paper, was transmitted. This paper summarizes applications of data from Pena Blanca in recent PA results published by NRC, DOE, and EPRI.

Augmented studies of the Nopal 1 deposit at Pena Blanca continued toward understanding radionuclide release rates. A consultant began field investigations at the site, focusing on mapping and sampling young secondary deposits that may yield data on U release rates. In addition, arrangements were made for high-precision U-Th isotopic analyses to be performed at the University of Texas for dating U-rich caliche and opal from the Nopal I site.

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CNWRA and NRC staffs collaborated in the review of the DOE Disposal Criticality Analysis Methodology Topical Report. The review schedule has been accelerated and the scope narrowed. ENFE efforts during this period resulted in input to a preliminary draft RAI to be submitted by the NRC. ENFE-related issues raised in this preliminary document focused on the approach to and validation of geochemical models affecting fissile material release and near-field transport.

I Staff continued debugging and testing the MULTIFLO code, Version 1. . A new analytical solution for coupled flow and transport including permeability modification due to mineral i dissolution was developed to test the fully coupled mode. Coupling between METRA and I GEM was debugged and successfully benchmarked. Efforts continued to refine parameters l

needed to model ambient YM conditions with ID dual matrix / fracture continuum simulations using MULTIFLO.

Staff prepared for participation in the 1999 Materials Research Society Symposium on the i Scientific Basis for Nuclear Waste Management with submission for programmatic review l of three abstracts: (i) an invited presentation on natural analogs and PA,(ii) thermodynamic l

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interpretations of water chemistry analytical data from YM, and (iii) an evaluation of PA transport modeling using data from the Akrotiri analog site. Contributions to the second abstract involved aqueous speciation calculations usmg EQ3 to establish thermodynamic consistency for over 60 analytical pore water analyses from boreholes SD-7, SD-9. and SD-12 at YM and from centrifuged pore water samples from the Topopah Spring Unit collected in association with the Drift-Scale Heater Test.

Literature review continued as did development of thermodynamic properties of cement minerals at elevated temperatures. Experimental studies were conducted on cement behavior at elevated temperatures. Staff began preparing a progress report on thermodynamic modeling of the temperature dependence of cement mineral solubilities. In addition, a separate progress report on the cement experiments was prepared.

The ENFE KTI was an object of the annual CNWRA QA audit on June 8-11,1999. No significant QA-related deficiencies were identified.

In the next period, an abstract for the annual meeting of the GSA will be conveyed for programmatic review.The abstract addresses field and laboratory studies of hydrothermal alteration of tuff associated with an igneous intrusion at the NTS. Staff will participate in the program organizing meeting for the Materials Research Society Symposium on the Scientific Basis for Nuclear Waste Management. Staff will prepare and contribute presentations to the panel of experts conducting the external review of the TPA computer code. Moreover, staff will complete a progress repon on experiments on the performance of cement at elevated temperature, and they will continue preparing a progress report on the solubility cf cement minerals at elevated temperature. Staff will debug and benchmark the MULTIFLO code, using the code to simulate the proposed repository near field. Staff also will continue modeling near-field radioelement solubility and studying aqueous actinide chemistry.

1.5 Container Life and Source Term (CLST)

Staff continued preparing input to the CLST IRSR, Revision 2, following discussions with the NRC staff on the annotated outline and the modified draft for revision 2. The staff made presentations and provided laboratory tours for the ACNW.

Staff continued preparing Assessment of Performance Issues Related to Alternate EBS Materials and Design Options (IM 20-1402-571-910). This report will summarize the materials, charactenstics, and corrosion processes that may affect the major classes of materials considered for construction of the containers for the various WP designs, including carbon steel and SS, nickel-base alloys, and titanium alloys. Degradation processes of Zircaloy cladding and ceramic coatings also will be included. The report will be updated on the basis of the most recent information from the DOE to be provided in the upcoming Appendix 7 meeting at LLNL, scheduled for July 7-8,1999.

Staffis preparing input to the evaluation of criticality inside WPs and other aspects related to the potential for criticality in the repository (joint effort with the RT and ENFE KTIs).

A report entitled Center Input to Request for Additional Information on DOE's Disposal Criticality Topical Report, added to the list of deliverables, will be completed in the next reporting period.

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Electrochemical corrosion testing continued to confirm the applicability of repassivation and corrosion potentials as predictive parameters for the long-term, localized corrosion of i

corrosion-resistant container materials in chloride-containing solutions at 95 *C. Tests using Alloy 825 specimens continued, including a creviced specimen held at 100 mV sco (50 mV less than the repassivation potential)in a 1,000-ppm chloride solution. No evidence oflocalized corrosion was observed for a total test time of 1,379 days. A second Alloy 825 )

test specimen has been immersed in an air-saturated 1,000-ppm chloride solution at open circuit for a total test time of 1,233 days. Crevice corrosion was observed on this specimen ,

several times during the test when the corrosion potential exceeded the repassivation i potential.Three Alloy 22 specimens with attached crevice-forming devices are being tested in a 4M Nacl solution at pH 8. One specimen is tested under open circuit conditions in an air-saturated solution so that the time-dependent changes in the corrosion potential can be monitored. No localized corrosion was detected on the Alloy 22 specimens held at applied potentials of 400 and 500 mVset.

The passive dissolution rate of Alloy 22 was measured in solutions of various pHs (0.7,2, and 8) containing 0.028-4M chloride at 25 and 95 *C. Tests are now being conducted on specimens thermally aged for 4,8, and 12 hr at 870 *C. Higher passive dissolution rates and an increased susceptibility to intergranular corrosion were observed with Alloy 22 specimens thermally aged for 4 and 8 hr at 870 *C. Measurements of the repassivation potentials of welded specimens continued using an autoclave in 0.5 to 4M chloride solutions at temperatures ranging from 95 to 150 *C. Noticeable localized corrosion, preferentially developed at the welds, was observed in the welded specimens, which also exhibit lower repassivation potentials than those measured in nonwelded specimens.

Staff continued SCC tests of Alloy 22 and type 316L SS specimens. Fatigue precracked, wedge-loaded DCB specimens of each material were 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. Tests on Alloy 22 used an initial stress intensity of v2 33 MPa m , whereas the type 316L SS specimens were tested at an initial stress intensity of 25 MPa m"2. No cracking of the two alloys was observed under these testing conditions for a cumulative test time of 31 wk. Testing under open-circuit potential conditions in  ;

MgCl 2solutions (30 and 40 percent) at 110 *C shows significant crack growth in the SS  !

specimens after a short exposure period. An average crack growth rate of 1.0 x 104 m/sec u2 was measured at Ki = 22 MPa m . A much longer exposure period was required to initiate SCC at an applied potential of-340 mVset, which is slightly above E,(-390 mVset). At 4

this potential, the average crack growth rate was about 2.5 x 10 m/sec. Testing under an applied potentialof-360 mVsce is in progress. Crack growth was observed at this potential after an exposure period of 8 days. In contrast, no crack growth was observed on Alloy 22 specimens tested for 20 and 31 wk in 40 percent MgCl2 at 110 *C under open-circuit conditions. More tests using 316L SS specimens under applied potential conditions are planned to determine the relationship between crack growth rate and potential. These experiments are needed to confirm whether the repassivation potential may be used as a threshold criterion for precracked specimens as was previously demonstrated for smooth specimens in slow strain rate tests.

The effects of solution chemistry on the corrosion behavior at 95 *C of Ti-Grade 7, identified by the DOE as a possible candidate material for drip shield, are being examined in long-term tests. The effect of chloride concentration and pH on the critical potentials for 7

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P localized corrosion as well as the environmental effects on the passive dissolution of Ti-Grade 7 are the current focuses. No localized corrosion of Ti has been observed in the long-term tests at potentials below the previously measured repassivation potential in neutral, acidified, and alkaline solutions. In experimen' ' aimed at measuring the passive current density, there has been little observed effect of pH and applied potential over the range of 8-11 in pH and -250 to +250 mV set in potential. Current work is examining the acidified pH regime.

Staff examined the corrosion behavior of Zircaloy-4. In the last period, tests were performed to study the effects of solution chemistry on localized corrosion. In particular, tests were conducted in chloride-containing solutions instead of solutions based on J-13 well water. No significant differences in the results were observed. The effects of pretest heat treatment at 200 *C in air were also examined. In this case, the repassivation potential of creviced Zircaloy-4 specimens was unaffected by the heat treatment, but the crevice potential did increase. Furthermore, the sites of localized corrosion became much more pronounced and hemispherical in shape as a result of the heat treatment. Current focus examines the effects of longer pretest heat treatment times.

Staff pursued confirmatory testing of glass wasteform on the standard EA glass and two simulated waste glasses (DWPF Blend 1 and WVNS Reference 6) using the ASTM PCT, 1 Method A. Long-term tests on these three glasses were conducted in deionized water and concentrated FeCl2 and FeCl3 solutions (0.25 and 0.0025M) with solution replacement twice a week. These tests were terminated after a cumulative test time of 3 wk due to pitting corrosion of the SS vessels in contact with the concentrated FeCl 2 and FeCl 3 solutions.

Leachate compositions from three solution replacements were analyzed using ICP. Analysis of the ICP results is now underway. Long-term tests using PFA TFE-fluorocarbon vessels are planned. The objective is to determine the effect of salt solution on the dissolution rate of the reference glasses. The results also can provide the parameters needed to quantify the glass-dissolution models.

Staff continued developing and implementing suitable corrosion potential and chemistry (chloride and pH) sensors to be used under heat transfer conditions. A small group of candidate sensor designs are being combined into a compact array for monitoring corrosion and environmental corrosivity. This assembly will be used in the simulated drift experiments coordinated by the TEF KTI team.

In the next period, staff will continue revision of the IRSR and preparation of the report on alternative EBS materials and designs. Moreover, they will pursue the long-term corrosion tests of Alloys 825 and C-22, and the SCC tests using Alloy C-22 and type 316L SS, along with the Ti alloy test program, including examination of localized corrosion of welded specimens. In addition, staff will examine the effect of the environment on the corrosion behavior of Zircaloy-4 and identify the sensors to be used in the TEF KTI simulated drift experiments. They also will perform additional glass-dissolution tests.

1.6 Thermal Effects on Flow (TEF)

Analysis of the second test of the laboratory-scale boiling isotherm depression heater experiment continued during this period. Staff is preparing a journal paper based on this activity.

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Staff continued preparation of a proposed laboratory-scale coupled corrosion / heater experiment in support of the TEF and CLST KTIs. Media preparation and sensor evaluation are ongoing. Scoping experiments were conducted to identify the appropriate chemistry for the infiltration water. Consideration is being given to the prospect of conditioning the

. crushed tuff to blunt the effect the fresh fracture surfaces created during the crushing process.

Staff made a presentation on the TEF KTI activities and conducted a tour of the hydrology laboratory at the 110* ACNW meeting held at the CNWRA in San Antonio, Texas, on June 28-30,1999. Staff also conducted a tour of the hydrology laboratory for an NEl representative.

Investigation of capillary diversion at the drift walls continued during this period. The staff pursued the laboratory-scale experiment designed to resolve the distinction between capillary diversion and dripping. An analytical solution for seepage into a spherical opening with a periodic internal boundary condition has been documented in a draft journal paper now undergoing CNWRA internal reviews.

Development of the technical approach for measuring dripping into a drift openin, continued. The drip model uses flow input from the groove / film flow model, expressions for estimating drip volumes and detachment times as functions of groove geometry and flux rate along the fracture face, and modifications to account for evaporation. A report titled Dripping into Cavities from Unsaturated Fractures Under Evaporative Conditions was conveyed. Related work on flow along a fracture surface was documented in a report titled Flow in Unsaturated Fractured Porous Media: Hydraulic Conductivity of Rough Surfaces and transmitted. These two documents were also submitted for possible publication in the journal, Water Resources Research.

In the next period, staff plans to (i) prepare the journal article on the boiling isotherm penetration laboratory-scale experiment, (ii) continue scoping and planning analyses in conjunction with the ENFE and CLST KTIs for the third laboratory-scale heater test, (iii) integrate a groove / film flow model into the mechanistic fracture flow model, (iv) continue analysis of a LtdTU/ acre repository,(v) conduct sensitivity analyses of the REFLUX 3 module in TPA Version 3.2 code, and (vi) continue development of the laboratory-scale capillary diversion experiment.

1.7 Repository Design and Thermal-Mechanical Effects (RDTME)

Staff pursued the TM study of drift stability in the area where the transition from strong to weak rock occurs. The modeling results using the UDEC computer program are being analyzed further to identify the region with a potential failure problem. Staff are investigating the potential effect of the long-term degradation of rock mass properties on the stability of emplacement drifts by reducing the intact rock and joint strength properties to one-half. A repon documenting the findings is being prepared.

Staff continued a UDEC study on the behavior of emplacement drifts in the lithophysal region considering the enhanced alternative design No. 2. This alternative design is intended to take advantage that the temperature for 80 percent of the pillar area will remain .

below the boiling point so precipitation and condensed vapor water can flow through this l

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s, Iow-temperature region without entering the emplacement drifts (shedding mechanism).

Because data for the lithophysal region were not available, mechanical and strength properties for the TSwl thermal-mechanical unit were used for the analysis. The result of the UDEC run is currently under evaluation. Preliminary results for temperature distribution as a function of time indicate that if no ventilation is applied after waste emplacement, the temperature increase as a result of thermal decay from two adjacent drifts will coalesce about 50 yr after emplacement with temperature higher than 100 *C. It is clear that the shedding mechanism will not work if adequate ventilation is not provided. Depending on the amount of ventilation, as much as 50 percent of thermal flux could be removed through ventilation, so the temperature in the rock mass surrounding the emplacement drifts could be reduced substantially. A study of ventilation effects on rock mass temperature distribution began.

During this period, staff continued the UDEC analyses to predict the size and extent of rockfall under seismic loads in the repository thermal environment. Staff compared the dynamic analyses using UDEC and KDYNA 3D to examine rockfall, as this effort will increase confidence in UDEC results. Staff encountered a convergence problem for the slide line in KDYNA 3D. This problem has not been solved and is being investigated by adjusting contact properties. The study on how wave propagation through a fractured medium is handled by UDEC continued during this period.

The ABAQUS modeling of WPs continued to investigate the thermal stress of WPs and assess the WP responses when subjected to the impact of falling rocks at various times.

This analysis will develop a reasonable failure criterion for use in the SEISMO module to assess the effect of rockfall on WP integrity. Modeling of rockfall under three impact conditions has been completed. The simulations involved a 1-m diameter spherical rock impacting the WP at 90 ,45 *, and 30' angles. Staff are preparing a report to document the findings of the investigation.

An outline for the preclosure review plan is being prepared. One consultant and one subcontractor are currently assisting CNWRA staff to develop acceptance criteria and review methods for the preclosure review plan using the integrated safety analysis methodology.

Staff studied the behavior of the rock mass surrounding the emplacement drifts under heated conditions at the repository scale using the ABAQUS code. They made ABAQUS calculations of several drift-scale models and analyzed these results to compare with those from the repository-scale model. The key focus is the effect of long-term degradation of rock mass properties on stability of the emplacement drifts and flow into emplacement drifts.

Three CNWRA staff attended the 37'h U.S. Rock Mechanics Symposium in Vail, Colorado, June 5-10,1999. A trip report is in preparation. CNWRA and NRC staffs made a presentation on RDTME KTI activities at the 110'h ACNW meeting held at CNWRA in San Antonio, Texas, on June 28-30,1999.

Preparation of RDTME 1RSR Revision 2 continued during this period.This report will be submitted on July 30,1999, as an MM.

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• * .* a In the next period, staff plans to (i) investigate rock mass behavior under heated conditions on both repository and drift scales with an emphasis on long-term degradation of rock mass material properties and strengths, (ii) conduct rockfall simulations, (iii) use the AB AQUS code to model WPs, (iv) develop input to the YMRP, (v) develop the RDTME IRSR, and (vi) panicipate as observers in the Office of Civilian Radioactive Waste Management Quality Assurance Audit.

1.8 Total System Performance Assessment and Integration (TSPAI)

Staff continued preparing the sensitivity studies report for the TPA Version 3.2 code. The report is currently undergoing technical review by both NRC and CNWRA staffs. This report documents the specific results obtained from applying a variety of sensitivity analysis methods and explains the implications to future TPA code development, the direction of the NRC HLW program, and the areas of the LA review that may require the greatest focus. The delivery of this report will be postponed to resolve extensive technical review comments and because of staff time required to prepare for participation in the DOE /NRC technical exchange and ACNW briefing. 1 The SRD for the parameter-tree post-processor was delivered for review, and NRC submitted comments on the SRD, A limited feasibility study on the development of the parameter-tree post-processor was conducted in support of the SRD. A meeting on the post-processor was attended by a CNWRA consultant and staff from the ACNW, NRC, and CNWRA. CNWRA staff discussed the outline and provided technical details to the consultant for development of the post-processor.

YMRP development continued in collaboration with NRC staff. CNWRA KTI team leads and ISI leads continueJ preparing acceptance criteria and review methods. Drafts of the  ;

training and certification of personnel portions of the YMRP were written and presented to NRC staff for comment. Discussions were held with NRC staff on the YMRP schedule and content. Preparations began for panicipation in a YMRP Appendix 7 meeting to be held in Las Vegas Nevada, on July 13,1999.

Talking points were developed for presentations to the external experts participating in the July 27-29,1999, peer review of the TPA Version 3.2 code. These talking points were used to identify key personnel from other KTIs for participation in presentations and discussion.

Both CNWRA and NRC staffs will make presentations and panicipate in the discussions.

Staff continued development of the TPA Version 3.3 code and implemented modifications approved by NRC. In addition, they discussed and prioritized the process-level changes to l be made to the code for Version 3.3 and produced new fuel burn-up calculations to improve l the accuracy of the representation of the radionuclide inventory in future versions of the l TPA code. l l

Preparation continued on revision 2 of the TSPAI IRSR. New sections on multiple barriers l

and transparency and traceability are being developed and updates to the descriptions of the i model abstractions are being made.

A CNWRA staff member attended the Appendix 7 Meeting on Criticality at Las Vegas, ]

Nevada. A trip report will document staff observations, i

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• J 4 3 Staff provided technical support to the SDS KTI through TPA code execution and analysis of results for the preparation of Revision 2 of the SDS IRSR.

Staffinterviewed candidates for the unfilled positions of health physicist and performance assessment engineer. Resumes continue to be gathered for other open positions. A nuclear engineerjoined the CNWRA during this period.

In the next period, the staff will focus on (i) completing and delivering the sensitivity studies report; (ii) completing revision 2 of the IRSR; (iii) preparing the YMRP; (iv) comparing the TSPA-VA and the TPA Version 3.2 code results; (v) conducting the meeting for the extemal review of the TPA Version 3.2 code; and (vi) initiating the strategic plan for TPA code development. Recruitment will continue for the two PA engineers, the two health physicists, and a risk analyst.

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

Staff continued modeling the effects of well characteristics and plume dimensions on the accuracy of the dose estimates from the groundwater transport pathway obtained using the current TPA Version 3.2 code approach.This Alis expected to be completed by the end of FY1999.

NRC comments on the revisions to the previously issued report, Information and Analyses to Support Selection of Critical Groups and Reference Biospheres for Yucca Mountain Exposure Scenarios, have been incorporated into a camera-ready copy to be delivered next period. Delivery was postponed this period due to higher priority demands on staff. Staff expects the report will be issued as a NUREG/CR-a key reference document for the rulemaking effort and TSPAI activities.

The feasibility of an improved (stochastic) dose module for the TPA Version 3.3 code is being investigated. The source code for the GENII dose assessment program was located and ordered. Some software licensing issues remain to be resolved, but, to save time, initial work will begin under compliance with the existing license while the licensing issues related to later implementation are finalized.

Staff started a new task to compile and analyze GIS data related to selection of potential receptor groups.

No major progress was made on other new tasks because of staff emphasis on existing priorities (e.g., IRSR Development and Peer Review Preparation). These new tasks include reviewing information supponing plant uptake factors for selected radionuclides in the TPA Version 3.2 code, determining whether the effects of multiyear radionuclide buildup from irrigation of soils need to be modeled in the TPA Version 3.3 or 4.0 codes, and evaluating inclusion of stylized human intrusion calculations in the TPA Version 3.3 or 4.0 codes.

In the next period, progress on borehole dilution evaluations should increase following completion of a major report on structural controls on groundwater. A revised, camera-ready copy of Information and Analyses to Support Selection of Critical Groups and Reference Biospheres for Yucca Mountain Exposure Scenarios (incorporating NRC comments) will be delivered. Staff plan to obtain software and resolve software licensing 12

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issues related to investigating the feasibility of an improved (stochastic) dose module for the TPA code. Staff expect to increase effort on analysis of GIS data related to selection of potential receptor groups and review information supporting plant uptake factors in the I TPA Version 3.2 code. Review of the draft EPA Standard will commence at a low level, if it is released for public comment, as will other new tasks related to pararneter improvements, implementation of human intrusion in TPA, and investigation of radionuclide buildup effects from irrigation. Hiring a new staff member with a health physics background should help reduce staff availability limitations.

1.10 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC)

Field work was conducted at YM in collaboration with the 1A KTI, completing two important tasks to support watershed modeling in the upper Split Wash area. First, outcrop j

versus soil covered areas were delineated in relation to mapped joints and fractures on the i Live Yucca Ridge pavements, located in the northeastern portion of the watershed. These  !

pavements are where geophysical (EM and magnetics) measurements were made last summer as part of an investigation of near-surface stmetural features. The outcrop maps will be used to account for bias in the fracture mappings. Coolingjoint swaims and tectonic

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fractures at the surface in the upper Split Wash watershed were mapped to support '

watershed modeling of runoff, subsurface lateral flow, and infiltration. The distribution of cooling joint swarms and the variation in fracture patterns between lithologies will be used to refine the watershed modeling grid (e.g., modification of hydraulic properties). The second task completed was a survey of stream channel features in the south upper branch of the watershed. This survey was prompted by earlier modeling that indicated over half the  ;

infiltration in the watershed took place in one small reach of the southern branch. thus l suggesting a need for more detailed measurements in that area.

Two papers were completed in collaboration with the TEF KTI and sent to NRC. These papers, which are relevant to unsaturated flow in fractures and seepage into drifts, are titled:

Flow in Unsaturated Fractured Porous Media: Hydraulic Conductivity of Rough surfaces and Dripping into Cavities from Unsaturated Fractures Under Evaporative Conditions.

A manuscript titled The Effect of Cavity Wall Roughness on Seepage into Underground Openings was completed and placed in internal CNWRA review. A second manuscript, An Inverse Model for Three-Dimensional Flow in Variably Saturated Porous Media, was also completed and placed in internal CNWRA review.

A CNWRA staff member participated in a program review on Hydrology and Infiltration Conceptual Models, hosted by the NRC Office of Nuclear Research, June 21-22,1999, at the Beltsville Agricultural Research Center in Beltsville, Maryland, and also participated in the public Workshop on Groundwater Modeling in Related to Dose Assessments, held on June 23-24,1999, at NRC headquarters in Rockville, Maryland.

Modeling investigations continued on the process of drift seepage, the capillary diversion of deep percolation away from open drifts, and coupled heat and fluid flow in the SZ.

Preparation continued on Input to NRC Working Group on Viable SZ Conceptual Flow Models, which will be delivered during the next reporting period. Staff also continued close ,

collaboration with the NRC PEM on development of the USFIC IRSR, Revision 2. '

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. 1 The IM, Modeling and Analysis of C-Well Tests-Letter Report, was delivered. To better reflect its contents, the title of the report was changed to Review and Analysis of Hydraulic and Tracer Testing at the C-Holes Complex Near Yucca Mountain, Nevada.

Staffinitiated work on the USFIC input to development of the YMRP. This work involved a review of the current working draft of the YMRP outline and assessment of how the review methods and acceptance criteria from the USFIC KTI subissues and integrated subissues will best be incorporated into the YMRP.

The USFIC KTI was an object of the annual CNWRA QA audit on June 8-11,1999. No significant QA-related deficiencies were identified.

in the next period, USFIC activities will include (i) completion of Input to NRC Working Group on Viable SZ Conceptual Flow Models; (ii) initiation of work on Revised Hydrologic Parameters for TPA Code, a review and update of USFIC-related parameter values and distributions used for the basecase of the TPA Version 3.2 code; (iii) continued investigation of models for seepage and dripping in underground cavities; (iv) continued analysis of processes affecting deep percolation; (v) participation in development of the YMRP; (vi) collaboration with the NRC on final edits to the USFIC IRSR, Revision 2; and (vii) participation in the external review of the TPA Version 3.2 code.

1,11 Radionuclide Transport (RT)

The MM, Input to RT IRSR, Revision 1-Letter Report, was submitted on June 24,1999.

This represents the CNWRA input for the update of the RT IRSR and includes review methods and acceptance criteria for the remaining subissues. This IRSR remains one revision behind the other KTIs.

The deliverable, Uranium Chemistry and Isotopy in Waters and Rocks at Pena Blanca-Journal Paper was completed during this period. The paper is to be included in the proceedings volume of the 8* European Commission Natural Analogue Working Group Workshop, Strasbourg, France, March 23-25,1999. The paper provides an interpretation of the history of U transport behavior at the Nopal I natural analog using existing CNWRA data. CNWRA review was completed for Stochastic Analysis of Early Tracer Arrivals in a Multiple-Fracture Pathway-Journal Paper and the manuscript was conveyed during this period. It is also to be submitted for publication in the Journal of Geophysical Research.

The manuscript Abstraction of Mechanistic Sorption Model Results for Performance Assessment Calculations at Yucca Mountain, Nevada-Journal Paper was revised in response to reviewer comments and accepted for publication by Waste Management.

An abstract titled Technetium-99 Chemistry in Reduced Groundwaters: Implications for the Performance of a Proposed High-Level Nuclear Waste Repository at Yucca Mountain, Nevada, was submitted for presentation at the Materials Research Society Annual Meeting to be held in Boston, Massachusetts, November 29-Decembei 3,1999. CNWRA staff began to prepare two manuscripts for inclusion in the proceedings volume of the Seventh International Conference on the Chemistry and Migration Behavior of Actinides and Fission Products in the Geosphere (Migration '99), scheduled for Lake Tahoe, Nevada, September 26-October 1,1999.

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CNWRA staff continued to explore the implications of nonideal sorption behavior on RT in the alluvium. A stochastic transport model accounting for physical and chemical heterogeneities and rate-limited mass transfer between mobile and immobile regions was developed for the alluvium. The effects of these nonideal features have been observed in field-scale tracer experiments in similar heterogeneous formations. Radionuclide arrival times were found sensitive to subsurface heterogeneities and to deviations from equilibrium sorption caused by rate limitations in mass transfer processes.

Staff reviewed the literature on molecular simulations of adsorption on mineral surfaces.

Evaluation of public domain molecular simulation software began as did modeling of uranyl speciation in aqueous systems. Results of the simulation were compared with spectroscopic and x-ray diffraction data.

Staff continued the evaluation of published experimental data on ion exchange between aqueous solutions, the zeolite mineral clinoptitolite, and development of thermodynamic parameters for predicting ion-exchange equilibria. A literature search of thermodynamic data on the aqueous chemistry of Tc continued. The data are to be used to evaluate the speciation and solubility of Tc under ccnditions relevant to the SZ groundwater in the YMR, and to design experiments on Tc sorption. The implication of reduced groundwater in the YMR on the transport of"Tc and on repository performance will be investigated using geochemical process models and the TPA Version 3.2 code.

Underground worker, first aid, and radiological worker training was completed by CNWRA staff to permit access for sampling water from the E and T tunnels in Rainier Mesa to help characterize UZ colloid transport and other UZ water chemistry issues. Field work conducted with suppon of NTS personnel is presently unscheduled pending resolution of  ;

issues among federal agencies coordinating access to the tunnels. Splits of water samples collected by CNWRA staff from wells associated with the Nye County EWDP were sent to two commercial laboratories for stable isotope (S and 6"O) analysis.

A "Tc spike was prepared for use in proposed Tc sorption experiments. The spike, which contained an initial total activity of 10 pCi, was diluted to achieve a stock solution concentration of 2.96 x 104 m "Tc. Optimum parameters for counting "Tc solutions by liquid scintillation analysis (e.g., energy windows or efficiency) were determined by counting aliquots of the stock solution using different container materials and scintillation cocktails. Finally, a kinetics experiment was started to determine the time it takes for Tc solutions to reach pH and sorption equilibrium.

CNWRA staff participated in the 110'h KW mt% bd a & GMA b b Antonio, Texas, June 28-30,1999. Staff also conducted laboratory tours for representatives of the NEl during their visit to San Antonio on July 1,1999. Staff attended a short course on Problem Solving Using the Geochemist's Workbench. Staff continued to help prepare the YMRP outline. Activities included reviewing the current working draft of the YMRP outline, mapping the acceptance criteria from the RT IRSR subissues and integrated subissues onto the proposed outline, and developing review methods for the YMRP.

In the next period, staff will continue sorption experiments on alluvium minerals.

Technetium sorption kinetics experiments will continue. Microscopic analysis of well cuttings from NC-EWDP-2d will continue. Staff will continue to help prepare the YMRP

l outline. Staff will assist in the PA abstraction process and perform sensitivity analyses using the TPA Version 3.2 code to investigate the calculated effects on performance of the correlation of sorption parameters. Staff will also participate in the external review of the TPA Version 3.2 code.

1,12 Tank Waste Remediation System (TWRS)

In subtask 1.2, the NRC staff comments on the Low-Activity Waste Auxiliary Support Systems II-Process Systems Hazard and Safety Issues Report for TWRS-Letter Report are being addressed. In addition, staff is working on preparation of Low Activity Waste System Hazard and Safety issues-Final Report. Volume I of this two-volume report will be delivered as scheduled on July 30,1999. As discussed with NRC, the delivery of Volume II has been rescheduled to August 20,1999. Staffis also working on a presentation on the Vitrification of Radioactive Wastes to the Regulatory Unit of the Department of Energy The presentation will consist of two 4-hr sessions summarizing work on this subtask during the last 2 yr.

In subtask 1.6, the final report on Hanford Tank Waste Remediation System Pretreatment Chemistry and Technology was delivered on June 18,1999. After discussions with the NRC, submission of a final version that would address additional NRC comments, currently scheduled for July 30,1999, has been postponed to September 17,1999.

In subtask 2.1, Dr. Srinivasan (NRC) spent 2 wk at the CNWRA. Dr. Srinivasan. along with the CNWRA staff, developed the framework for the TWRS-P Hazards Information Database. When appropriately developed, the database will provide the NRC staff with detailed information on potential hazards under various conditions of operation of the facility. Information can be selectively extracted for various SSCs relied on for safety. The initial framework will be refined further through interactions between CNWRA and NRC during the coming months.

In subtask 2.2, the NRC comments on the Inspection of TWRS-P Quality Assurance Program Implementation procedure were incorporated and the revised document transmitted.

In the next period,in subtask 1.2, staff will deliver the report, Low-Activity Waste System Hazard and Safety issues-Final Report. This report will incorporate the NRC comments on the following three reports: Low-Activity Waste Auxiliary Support Systems II-Process Systems Hazard and Safety Issues Report for TWRS-Letter Report: Low-Activity Waste Feed Makeup, Solidification, and Offgas Treatment Process System Hazard and Safety issues Report for TWRS-Letter Report; and Auxiliary Support and Process Control Technology System for Low-Activity Waste at Hanford-Hazard and Safety Issues Report.

In addition, the staff will prepare a presentation on the Vitrification of Radioactive Wastes for the Regulatory Unit of the U.S. Department of Energy. In subtask 1.6, the staff will prepare for and make a presentation to the NRC staff on the pretreatment chemistry report.

In subtask 2.1, efforts will continue in developing a test example for the TWRS-P Hazard Information Database.

16

____-_____-_______-___________a

1.13 Three Mile Island Unit 2 Independent Spent Fuel Storage Installation (TMI.2 ISFSI) l The annual CNWRA QA audit was conducted on the TMI-2 project during this period.This project is now complete.

In the next period, no activities will be conducted on the TMI-2 project.

1.14 Dry Transfer System (DTS)

The development of the DTS draft SER continued during this period with concentrated efforts.The DTS staff also prepared for the DOE /NRC meeting on Second Round RAI that will take place in San Antonio, Texas, next period.

In the next period, DTS staff plans to continue development of the draft SER and participate at the DOE /NRC meeting at San Antonio on DTS Second Round RAI.

1.15 Centralized Interim Storage Facility (CISF) l Detailed technical review of the topical report on HI-STAR /HI-STORM cask system deployment at high seismic risks sites continued at a low level during this reporting period.

Ongoing low-level activities for the computer code RISKIND include a literature review of the various parameters and also the values used internationally to calculate dose from a loss-of-containment accident at an SNF storage facility.

In the next period, the staff plans to continue literature review related to the computer code RISKIND at a low level while awaiting the instructions to revise the draft AR and the DOE response to the SFPO RAI on the HI-STAR and HI-STORM topical report for high seismic risk sites.

1.16 Private Fuel Storage Facility (PFSF)

Review and evaluation of the site characterization reports, preparation of a draft SER, preparation of a technical basis report regarding PFS seismic exemption application, and revisions of the NRC draft positions on five Group 1 contentions continued during this reporting period.The NRC and CNWRA staffs engaged in extensive interactions to prepare the NRC final positions on the five Group I contentions.

In the next period, the staff plans to review the site characterization reports, prepare the draft SER, review and evaluate the PFS request for an exemption from the requirements of 10 CFR 72.102(f), and assist the NRC staff on ASLB hearing activities.

1.17 Savannah River Site Aluminum-Based Spent Fuel (SRSASF)

J The staff has nearly completed its review of the DOE reports on dissolution of Al-based spent fuel, fuel processing, and disposability assessment. Development of the Review of the U.S. Department of Energy Evaluation of Aluminum-Based Spent Nuclear Fuel-Final Report has begun and is progressing.

17 l

l

4 . ..

n In the next period, review of the DOE reports will be completed, and the final report will be completed.

2 MANAGEMENT ISSUES Further evaluations of spending, scheduling, and staffing will be reviewed next period at the NRC/CNWRA Management Meeting. A third-quarter update on spending and carryover will also be provided to NRC management.

3 MAJOR PROBLEMS None to report.

4

SUMMARY

OF SCHEDULE CHANGES Schedule changes for IMs are included in table 3. Completed deliverables are noted on table 4.

5

SUMMARY

OF FINANCIAL STATUS Table 5 summarizes the CNWRA financial status in the context of authorized funds. Total commitments are $614,197. The appendix lists planned and actual costs to date, as well as variances 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 COPS and ten KTIs, TWRS JC, TMI-2 ISFSI JC, DTS JC, CIS F JC, PFSF JC, and SRS ASF JC. The planned costs per period are based on the revised spending plans contained in the current OPS.

It should be noted that the current spending estimates in all JCs are based on the assun:ption that staffing is consistent with the aggressive CNWRA hiring plan. A revised staffing plan was delivered as part of the CNWRA Management Plan, Revision 7, Change 0. Despite focused efforts on recruitment, current staffing remains below authorized levels.

Period 10 FY 1999 CNWRA composite expenditures rose 14.1 percent from the previous period, and this aggregate of all JCs was underspent by $1,192,429 or 11.3 percent. This is the lowest level since period 6. When comparing period 10 with last period, the DWM TMI-2 ISFSI, DTS, and PFSF JCs evidenced higner spending levels while the TWRS, CISF, and SRSASF JCs showed lower levels.

Expenditures on SwRIlabor, consultants, and subcontractors as a proportion of composite spending on all JCs were 26.8 percent. Expense of consultants and subcontractors as a fraction of composite spending on all JCs was 14.3 percent. The CNWRA continues to enhance, where appropriate, participation of consultants and subcontractors in the conduct of CNWRA work.

As shown in table 1, the CNWRA has 53 staff members, reflecting the addition of a nuclear engineer. The available pool of approved consultants and subcontractors is 56.

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

The DWM JC was underspent by $977,665 or 10.7 percent. Overall expenditures increased about 12.4 percent from the previous period as costs rose in COPS and the IA, SDS, ENFE, CLST, TEF, 18

g-te. .

)

1 I

TSPAI, ARDR, and USFIC KTIs but declined in the RDTME and RT KTIs. Costs to date are 30 percent above those a year ago, and period 10 costs are 44 percent greater than the same period last year. Spending on the augmented scope of work has not met expectations in all areas, however, progress is being made to accomplish the work associated with this augmentation. In various meetings with NRC senior management staff and other interested parties, CNWRA senior j management staff continue to discuss current and expected levels of spending, aggressive l reemitment effons for core staff, and effective engagement of consultants and subcontractors.

Although actual spending in the last two fiscal periods has exceeded estimates, the CNWRA does not expect to attain the estimated spending in the currently approved OPS by the end of FY1999.

l A detailed assessment of anticipated spending has been provided to NRC, and updates to this assessment will be provided as required.

I The cost variance for COPS was 11.5 percent: 15.0 percent for the Management, Planning, and l Computer Support subtask (158) and -2.3 percent for the QA subtask (159). Spending this period l in subtask 158 rose significantly relative to last period. In the next period, spending in subtask 158 is expected to be close to the estimated amount as consultants and temporary staff are used especially in the IMS area to mitigate staff lost through attrition arid to support the revision of the CNWRA LAN, the creation of new and revision of existing databases, and modification of the firewall. CNWRA management continues to encourage eligible staff to participate in professional development activities. In subtask 159, spending will decline in period 1 I since the QA audit team (technical specialists and auditors) has completed the annual audit and submitted their report. Total spending in the COPS element for the balance of FY1999 will be less than estimated.

The cost variance for the IA KTI was 6.1 percent. Spending increased significantly relative to last period, reducing the cumulative dollar and percentage variances. Substantial consultant and subcontractor costs are outstanding, and invoices are being expedited. Expenditures this period are consistent with expected spending in the next few periods. Total expenditures may exceed the spending plan by less than 10 percent for the remainder of FY1999.

The cost variance for the SDS KTI was 9.7 percent. Spending increased significantly from the previous period. Substantial consultant and subcontractor costs are outstanding, and invoices are being expedited. As the augmented work progresses, this variance will decrease and total expenditures may be slightly greater than the spending plan for the balance of FY1999. It is anticipated that spending will increase in the next period as consultants and students continue to work on various projects: modifying the 3DStress code, studying the Fortymile Wash alluvium, and mapping and interpreting fractures at YM. Failure to obtain PSilA input and output from Risk Engineering may result in underspending of some funds. Nevertheless, it is anticipated the total expenditures will exceed the spending plan.

The cost variance for the ENFE KTI was 10.8 percent. This is a significant reduction in the cumulative percentage variance from period 9 (13.8 percent) and continues the long-term decrease in the percentage variance over the past eight periods. Further reduction in the current variance is strongly dependent on timing of the receipt and payment ofinvoices corresponding to substantial commitments.

The cost variance for the CLST KTI was -3.1 percent. Spending increased compared to period 9 because of the addition of one new staff member and several summer students. At this time, the projected cumulative spending at the end of the FY is expected to be about 5 percent above budget.

l 19 l

l l

k_

o .

li y The cost variance for the TEF KTI was 0.1 percent. Future actual expenditures are expected to follow the budget for this KTI.

The cost variance for the RDTME KTI was 9.6 percent. Although less than last period, actual spending during this period was higher than the estimate, thus reducing the cumulative percentage variance. This cost underrun is due to temporary assignment of staff to other tasks during several earlier periods of FY1999 and lagging charges from consultants and subcontractors. Now that the staff has been reassigned to the RDTME KTI activities, this cost underrun is expected to decrease significantly during the remaining periods of FY 1999.The FY1999 total expenditures are expected to converge to the FY1999 allocation.

The cost variance for the TSPAI KTI was.16.2 percent. Spending increased significantly over the previous period, exceeding the period 10 planned expenditures, due in part to increased work on the YMRP, preparation of the sensitivity studies report, and conduct of the ACNW meeting. Total spending should continue to increase as a result of additional SwRI and consultant resources devoted to development of the two TPA post-processors and the TPA Version 3.3 code, the addition of new staff, and participation in the external review meeting. Spending is anticipated to be about 5-10 percent less than planned by the end of FY1999.

The cost variance for the ARDR KTI was 59.6 percent. Formal receipt of the draft proposed EPA Standard and initiation of technical work to support responses to comments on draft 10 CFR Part 63 should help decrease underspending during the coming periods. Although new tasking should reduce the cumulative variance in future periods, this KTIis expacted to be significantly underspent at the end of this FY.

The cost variance for the USFIC KTI was 2.9 percent. This is a significant reduction in the cumulative percentage variance from period 9 (4.3 percent) and continues a trend from the previous period toward a reduced variance. Additional reductions in the variance are anticipated as outstanding commitments are processed and costs of recent field work are posted. It is possible that the variance may become negative as costs for field work are posted.

The cost variance for the RT KTI was 14.4 percent. This represents a sustained higher level of spending, and the corresponding reduction in the variance during the last two periods. Anticipated invoices from ongoing and planned work by consultants are expected to reduce the variance in the coming periods. Additional staffing, lab work, and field activities are also anticipated to reduce the variance. Total spending may be about 5 percent less than the spending plan for FYl999.

The cost variance for the TWRS project was 21.0 percent. The variance decreased slightly from last period due to expenditures related to the preparation of two IMs. The staff effort is augmented through thejudicious use of SwRI staff and consultants to achieve timely completion of milestones.

Due to the anticipated completion of the reports in task 1 and the lack of new privatization contractor reports to review in tasks 2.1 and 2.2, it is anticipated these tasks and the overall project will be underspent at the end of FY1999.

The cost variance for the TMI-2 ISFSI project was -2.7, however, relative to the total FY1999 allocation, the cost variance is 0.3 percent. The project was completed during this period, and, thus, the FY1999 total expenditures are within the FY1999 allocation. ,

l

)

l 20

g- b The cost variance for the DTS project was 7.1 percent. Spending increased significantly during this period as the result of concentrated efforts to develop a draft SER by CNWRA and SwRI staffs and subcontractors. The FY 1999 total expenditures are expected to converge to the FY 1999 allocation.

The cost variance for the CISF project was 23.8 percent. The cost underrun will increase until the instructions to revise the draft AR and the DOE response to the RAI on HI-STAR and HI-STORM topical report for high seismic sites are received.

The cost variance for the PFSF project was 5.0 percent. Expenditures during the next few periods will increase as staff review the site characterization reports, prepare the draft SER, review the PFSF seismic exemption request, and revise the NRC draft positions on five Group I contentions. This will reduce the cumulative cost variance. The FY1999 total expenditures are expected to converge to the FY1999 allocation.

The cost variance for the SRSASF, after a budget reduction in the project, was 18.4 percent.

Spending slightly decreased from the last period. Due to the anticipated completion of the report, it is anticipated the overall project will be underspent at the end of FY1999, i

l 21

U '); j 1

I Table 1. CNWRA Core Staff-Current Profile and Hiring Plan * (Period 10) l l

l Positions Open EmpertheNapertence Current No. Profeuianal Staff FY1999 l

ADMINISTRATION 4 H GARCIA, W PATRICK. J RUSSEIL B SAGAR '

1 CHEMICAL PROCESSING 2 V.J AIN. D DAR UW Al.LA FNGNG/ PHYS CHEM CODE AN Al.YSIS/DEVEIDPMENT l 2 R J ANET7KE. R MARTIN 1 DATA MANAG8%fENT4'ROCESSING. I P.MAIDONADO j INCL. TIDING Fi?4 ANCI Al.

l DOSF/ RISK /HA7ARD ANAL.YSIS 0 1 I:1.f CTROCHEMISTVY I G CR AGNOlJNO ENGINEERING 2 R.CHEN. G OFOEGBU 1 l GFOIDGYKiFOI OGICAl. I NGNG I I NVIRONMENTAE SCIENCES I P laPt AN'IT GEOCHE311STRY 7 P BER1Er!1, LBROWNING, W. MURPHY, R PABALAN, i E PEARCY. J PRIKRYt. D TURNER GEOHYDROLDGY/HYDROGEOLOGY 5 D FARRELL R.f1 DORS. R. GREEN, M. Hill, J WINTTRI.E GFO!OGY 1 P tAITMIN A 1. McKAGUE. M MIKIAS I I

HYDROI OGIC TR ANSPORT 1 A ARMSTRONG D HUGHSON S PAINTER I l

INIORMATION MANAGEMENT S i  !

SYSTTMS ,

MA11 RIAL SCIENCES 4 S.BROSSIA D DUNN. O.MOGHISSI. Y-M PAN. 1 N SRIDH AR MECHANICAL, 1 D GUTE INCIlfDING DESIGN & FABRICATION MINING ENGINEERING 1 S-M HSt.NG NtICIIAR ENGINEERING 1 M SMfDI o OPER ATION At HEALTH PHYSICS I J WEIDY I PERIORMANCE ASSESSMENT 3 S MOHANTY, O. PENSADO-RODRIGUEZ, 2 I' G WITTMI'YER QtIAlJT'Y ASStFR ANCE I R M ABR000 i R ADIO!SOTOPE GFOCHFMISTRY I D PICKFTT l ROCK MECHANICS. 2 A.CHOWDHURY, A.GHOSH INCL UDING CIVII/STRtfC ENGNG i

SOURCEJTT.RM5 PENT IUEI. DEGR AD 0 i STRUCTURAL GEOLOGY / 1 D IIRRILL D SIMS, J STAMATAKOS SEISMO-TTCTONICS SYSTTMS ENGINEERING I P M ACKIN VOlfANOIDGY/lGNEOUS 2 C CONNOR. B HILL PROCfSSES TOTAL 4 Ii

^

• See staffing plan for details 22

g.- t. .

i Table 2. CNWRA Core Staff-Summary by Area of Concentration (Period 10) i

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Positions Area of Concentration Actual Planned Open ADMINISTRATION, QUALITY ASSURANCE, AND 6 7 1 INFORMATION MANAGEMENT GEOCilEMISTRY R 9 1 IlYDROIDGY/CLIMA1DLOGY R 9 1 i M ATERIAL SCIENCES 6 R i MECilANICAL,CllEMICAL, NUCLEAR AND SYSTEMS 5 5 0 1 ENGINEERING

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y p Table 5. Financial Status (Period 10)

Funds Funds Funds Project Names Authorized Costed to Date Uncosted Commitments COPS 3.476.342 2.879.351 596.991 3.352 1A 1.345.062 1.212.334 132.728 118.187 SDS 1.825.699 1.581.224 244.474 64.146 ENFE 1.781.331 1.416.704 364.627 165.492 CLST 1.704.818 1.565.902 138.917 12.975 TEF 1.322.606 1.118.490 204.117 10.498 RDTME 1.319.682 1.032.603 287.079 62.14i TSPAl 3.577,966 2.816.281 761.685 43.330 ARDR 697.208 330.306 366.903 4.426 USFIC 2.288.030 1.933.372 354.659 21.817 RT 1.369.634 1.032.409 337.226 87.657 DWM Costs 20.708.378 16.918.975 3.789.403 DWM Award Fee 1.196.006 493.569 702.437 DWM Hase Fee 828.335 659.953 168.382 TOTAL DWM 22.732.719 18.072.497 4.660.223 594.022 TWRS Costs 1.583.378 1.355.4(M 227.973 0

'IWRS Award Fee 93.654 46.214 47.440 TWRS Ilase Fee 63.335 55.005 8.330 TOTAL TWRS 1.740.367 1.456.623 283.744 0 T1112 ISFSI S AR Costs 282.197 282.758 (561) 0 TMI 2 ISFS1 S AR Award Fee 15.223 7.711 7.512 TMI.2 ISFSI Base Fee 11.288 11.061 227 TOTAL TK11-2 ISFSI S AR 308.708 301.530 7.178 0 DTS Costs 309.952 336.080 (26.127) 0 DTS Award Fee 19.480 7.924 11.556 DTS Base Fee 12.398 13.339 (940)

TOTAL DTS 341.830 357.342 (15.512) O CISF Costs 409.053 339.803 69.250 0 CISF Award Fee 24.338 12.848 11.490 CISF Hase Fee 16.362 13.642 2.721 TOTAL CISF 449.753 366.293 83.461 0 PFSF Costs 334.272 281.903 52.370 20.176 PFSF Award Fee 16.185 6.827 9.358 PFSF Base Fee 13.371 11.402 1.969 TOTAL PFSF 363.828 300.132 63.697 20.176 SRS ASF Costs i13.185 89.838 23.348 0 SRSASF Award Fee 7.110 3.992 3.118 SRS ASF Hase Fee 4.527 3.831 696 j TOTAL SRSASF 124.823 97.661 27.162 0 {'

Grand Total 26 062_029 20.052.077 5 too os2 614 107 Note: All authorized funds have been allocated through modification #127. Funds costed to date for each award fee program represent the award fee for FYl998. Funds uncosted for each award fee program represent the award fee reserved from the last I authorizations based on the Operations Plans for FYl999.

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