ML20196D261

CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990508-0604

ML20196D261
Person / Time
Site:	Three Mile Island
Issue date:	06/17/1999
From:	CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES
To:	NRC
Shared Package
ML20196D223	List: ML20196D217 ML20196D261
References
CON-FIN-D-1035, CON-FIN-J-5164, CON-FIN-J-5186, CON-FIN-J-5206, CON-FIN-J-5210, CON-FIN-J-5226, CON-NRC-02-97-009, CON-NRC-2-97-9, REF-WM-11 HLWR, PMPR-99-9, NUDOCS 9906240243
Download: ML20196D261 (43)

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CNWRA PROGRAM MANAGER'S PERIODIC REPORT ON ACTIVITIES OF THE CENTER FOR NUCLEAR W'ASTE REGULATORY ANALYSES For the Fiscal Reporting Period l

May 8,1999 - June 4,1999 i

PMPR No. 99-9 i

June 17,1999 g62 g990617 WM-11 PDR a

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J TABLE OF CONTENTS t

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Section Page i

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TABLES...........................................................

I AB B REVIATIONS :.............................................

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' EXECUTIVE S UMMARY-PERIOD 9................................................. x i}

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1 TEC HNICAL................................................................ I 1.1 CNWRA Ooerations (COPS).............................................. I 1.2 Igneous Aui vity (IA) '................................................... 2 l

1.3' Structural Deformation and Seismicity (SDS)

.............................. 3 1.4 Evolution of the Near Field Environment (ENFE).........................

.4 1.5 '

Container Life and Source Term (CLST)................................. 5 l

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)................ 10 i

1.92 Activities Related to Development of the NRC High-Level Waste Regulations (ARDR)...................................................

1 1 l

1.10 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC).......... 12 j '

1.11 Radionuclide Transpon (RT)........ :................................... 13 A

1.12 Tank Waste Remediation Systems (TWRS)................................. 15 j

1.13 Three Mile Island Unit 2 Independent Spent Fuel Storage l

Installation (TMI-2 ISFSI)..............................................

15 1.14 Dry Transfer System (DTS)............................................

16 1.15 Centralized Interim Storage Facility (CISF)................................

16 1.16 Private Fuel Storage Facility (PFSF)......................................

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

16 2-MAMAGEMENT ISS UES..................................................... 17 3-M AJOR PROB LEMS......................................................,. 17 4

SUMMARY

OF SCHEDULE CHANGES.......................................

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SUMMARY

OF FINANCIAL STATUS......................................... 17 APPENDIX-Planned and Actual Costs, and Cost Variances Period 9-FY1999 I

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TABLES Table Page 1

CNWRA Core Staff-Current Profile and Hiring Plan * (Period 9)................... 21 2

CNWRA Core Staff-Summary bh Area of Concentration (Period 9)................. 22 3

Summary of Schedule Changes (Period 9)....................................... 23 4

Deliverables (Period 9)...............................................

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Financial S tatus (Period 9).................................................... 25 6

Private Fuel Storage Facility License Fee Cost Recovery Status (Period 9).........

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ABBREVIATIONS

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ID One Dimensional CDROM Compact Disk Read Only Memory 1

2D Two-Dimensional CDTS Commission Decision Tracking System i

3D Three-Dimensional CEB Center for Environmental Biotechnology l

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 CHn Calico flills Nonwelded Tuff ACNW Advisory Committee on Nuclear Waste CIAC Computer incident Advisory Capability ACRS Advanced Computer Review System CISF Centralized Interirn Storage Facihty ACS American Chemical Society CLST Contamer Life and Source Term ADAMS Agencywide Documents Access and CM Configuration Management Management System CNWRA Center for Nuclear Waste Regulatory AECL Atomic Energy of Canada Limited Analyses j

AES Atomic Emission Spectrometry Col Conflict of Interest AWF Antler Wash Fault COPS CNWRA Operations AGU American Geophysical Union CPP Cyclic Potentiodynamic Polarization Al Administrative item CQAM CNWRA Quality Assurance Manual l

AL*TS Apache Leap Test Site CRG Center Review Group AML Areal Mass Loading CRM Corrosion Resistant Material ANS American 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 Ilydrate AR Assessment Report CSPE Corrosion Science and Process ARDR Activities Related to Development of Engineering 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 Information Interchange DCAA Defense Contract Audit Agency 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 American Society for Testing and D&D Decommissioning and Decontamination Materials DECOVALEX Development of Coupled Models and ASU Arizona State University Their Validation Against Experiments ATDTS Automated Technical Data Tracking in Nuclear Waste Isolation System DEIS Draft Environmental Impact Statement BDCF Biosphere Dose Conversion Factor DEM Digital Elevatic n Model BEG Bureau of Economic Geology DF Dilution Factor BFD Basis for Design DFCSS Division of Fuel Cycle Safety and BM Bare Mountain Safeguards BMP Bare Mountain Fault DIE Determination ofImportance BTP Branch Technical Position Egluation CAI Color Alteration Index DIMNS Division ofIndustrial and Medical CAM Corrosion Allowance Material Nuclear Safety' CAR Corrective Action Request DKM Dual Permeability Model CCDF Complementary Cumulative DLG Digital Line Graph Distribution Function DLM Diffuse Layer Model CCL Commitment Control Log DNAG Decade of North American Geology CCM Constant Capacitance Model DNFSB Defense Nuclear Facilities Safety Board CD-R CDROM Recordable DOE U.S. Department of Energy CDF Cumulative Distribution Fanction DOE-DP U.S. Department of Energy Defense CDOCS Consolidated DOCumen'. Management Program System v

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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 Geollydrology 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 t

DWPF Defense Waste Processing Facility GPS Global Positioning System

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EA Environmental Assessment GROA Geologic Repository Operations Area EBS-Engineered Barner System GSA Geologic Society of America ECM Equivalent Continuum Model GTFE Great Tolbachik Fissure Eruption f

ECRB Enhanced Characterization of Repository GUI Graphics User interface Block GWB Geochemist's Workbench EDO Office of the Executive Director for GWS!

Groundwater System 1ntegration Operations GWTT Groundwater Travel Time EDX Energy-Dispersive X-Ray Spectroscopy HE Hydrogen Embrittlement EIS EnvironmentalImpact Statement ilLW High-level Waste EM Element Manager HRTEM High-Resolution transmission Electran EMPA Electron MicroProbe Analysis Microscopy ENE East Northeast IA Igneous Activity ENFE Evolution of the Near-Field IBM International Business Machmes 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 Engineering and EXAFS Extended X-Ray Absorption Fine Environmental Laboratory Structure INETER Instituto Nicaraguense de Estudios FCRG Format and Content Regulatory Guide

'IERritoriales FDSHA Fault Displacement and Seismic Hazard INTEC Idaho National Technology and Analysis Engineering Center FEHM Finite Element Heat and Mass Transfer I/O Input / Output FEM Finite Element Method IP Inspection Procedure FEP Features, Events, and Processes IPA Iterative Performance Assessment FFRDC Federally Funded Research and IR&D Internal Research & Development Development Center IRIS Intenm Records Information System FIT Fast Fourier Transform IRM Office of Information Resources FOC Field Operations Center Management FIE Full-Time Equivalent ISI Integrated Subissue FTP File Transfer Protocol IRSR

!ssue Resolution Status Report FY Fiscal Year ISA Intregated Safety Analysis FYTD Fiscal Year-To-Date ISFSI Independent Spent Fuel Storage 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 Employ:e Radiological JPL Jet Propulsion Laboratory Training JRC Joint Roughness Coefficient vi L.

t ABBREVIATIONS (cont'd)

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 betwork NWPA Nuclear Waste Policy 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 12boratory Management LBT Large Block Test OGC Office of General Counsel LilS Latin flypercube Sarnpling OITS Open Item Tracking 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 L,ivermore National ORR Operations Readiness Review Laboratory OPS Overall Review Strategy LLW l.ow-Level Waste OWFD 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 Persod Computer M

Molar PC/IO' Personal Computerffransmission Ma Million Years Ago Control Protocol MAI Mean AnnualInfiltration PCT Product Consistency Test MAP Mean Annual Precipitation PDF Probability Distnbution Function MAT Mean AnnualTemperature PDR Public Document Room MC Monte Carlo PEL Permissible Exposure Limit METRA Mass and Energy Transport PEM Program Element Manager MGDS Mined Geologic Disposal System PER Prelicensing Evaluation Report Mil Mechanical 41ydrological PEST Parameter Estimation MIC Microbially influenced Corrosion PFD Probabilistic Fault Displacement MINC Multiple Interacting Continua PFD}{A Probabilistic Faul: Di> placement MIT Massachusetts institute of Technology liAzard '

MM Major Milestone PFS Pnvate Fuel Storage M&O Management and Operations PFSF Private Fuel Storage Facility MOU Memorandum Of Understandmg Pila Preliminary llazard Analysis MPC Multi-Purpose Canister Pl Pnncipal Investigator MRS Monitored Retrievable Storage PMDA Program Management. Policy MSS MultiSpectral Scanner Development and Analysis Staff MTU Metric Tonnes of Uranium PMPR Program Manager's Periodic Report NAS National Academy of Sciences PMT Photo-Multiplier Tube NAWG Natural Analogue Working Group PNNL Pacific Northwest National Laboratory NCR NonConformance Report PO Project Officer NEA Nuclear Energy Agency PPE Prepassivated Pladnum Electrode NEl Nuclear Energy Institute PRA Probabilistic Risk Assessment NFS Network File Server PRT Peer Review Team NIOSil National Institutes Of Safety and llcalth PSAG Probabilistic System Assessment Group NIR Near Infrared PSilA Probabilistic Seismic flazard Analyses NIST National Institute of Standards and IqFE Polytetrafluoroethylene Technology I'Tn Paintbrush Nonwelded Tuff NMSS Office of Nuclear Material Safety and PVilA Probabilistic Volcanic flazards Safeguards Assessment NNE North-Northeast PVilVIEW Probabihty of Volcanic flazards NNW North-Northwest VIEW NOAA National Oceanographic and PVM Parallel Virtual Machine l

Atmospheric Administration PWR Pressurized Water Reactor l

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ABBREVIATIONS (cont'd)

QA Quality Assurance SRS Savannah River Site QAP Quality Assurance Procedure SP.SASF Srvannah 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 Scanr.ing Transmission Electron RDCO Repository Design, Construction, Microscopy and Operations STP Staff Technical Position RDTME Repository Design and Thermal.

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 Ofnce 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 Boring Machine RT Radionuclide Transport TCP/IP Transmission Control Protocol /

RTS Radwaste Treatment System Internet Protocol SAIC Science Application International TDEM Time-Domain Electro-Magnetic Corporation

'EDE 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 THC Thermal-Hydrologic Chemical SCC Stress Corrosion Cracking THMC nermal-Hydrologic-Mechanical.

SCCEX Substantially Complete Containment Chemical Example T-L Transverse-Longitudinal SCE Standard Calomel Electrode TLM Triple-Layer Model SCFF Southern Crater Flat Fault TM Thermal-Mechanical SCM Surface Complexation Models TMH Rermal-Mechanical-Hydrological SCP Site Characterization Plan TMI-2 nree Mile Island Unit 2 SCR Software Change Report TMS The Minerals, Metals, and Materials SDMP Site Decommissioning Management Plan Society SDS Structural Deformation and Seismicity TOP Technical Operating Procedure SECY Secretary of the Commission, Office of TP Technical Position the (NRC)

TPA Total-system Performance Assessment SELM Spectral Element Method TPI Time Period of Regulatory Interest SEM Scanning Electron Microscopy TR2 DOE Seismic Topical Report No. 2 SER Safety Evaluation Report TRG Technical Review Group SFPO Spent Fuel Project Ofnce TSAR Topical Safety Analysis Report SFVF San Francisco Volcanic Field TSPA Total System Perfortnance Assessment SGI Silicon Graphics Inc.

TSPA-VA Total System Performance Assessment-SGML Standard Generalized Markup Viability Assessment Language TSPAl Total System Performance Assessment SHE Standard Hydrogen Electrode and Integration SHT Single Heater Test TSw-Chnv Topopah Spring Welded-Calico SKI Swedish Nuclear Power inspectorate Hills Nonvitric S-L Short Transverse-lengitudinal TVD Total Variation Diminishing SLAR Side Imoking Airborne Radar TWFN Two White Flint North SNF Spent Nuclear Fuel TWINS Tank Waste Information Network SNL Sandia National Laboratones System SOW Statement Of Work

'lWRS Tank Waste Remediation System SRB Sulfate-Reducing Bacteria UA University of Arizona SRBS Shafts Ramps, Boreholes, and their UACH Universidad Aut6 noma de Seals Chihuahua SRD Software Requirements Description UCL/,

University of California, Los Angeles viii

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e ABBREVIATIONS (cont'd)

UDEC Universal Distinct Element Code UK United Kingdom UNLV University ofNevada 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. Geo!;gical Survey UTM Universal Transverse Mercator UZ Unsaturated Zone VA Viability Assesstnent 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

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-WNYNSC Western New York Nuclear Service Center WOL Wedge-Opening Loading WP Waste Package WSRC Westinghouse Savannah River Company WSS Waste Solidification Systems

%TSO 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 YMP Yucca Mountain Project YMR Yucca Mountain Region YMRP Yucca Mountain Review Plan YMSCO Yucca Mountain Site Characterization Office YTD Year-To-Date l

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EXECUTIVE

SUMMARY

-PERIOD 9 In the Division of Waste Management (DWM) Job Code (JC), the Center for Nuclear Waste Regulatory Analyses (CNWRA) staff transmitted Input to TEF IRSR, Rev. 2-Letter Report and input to USFIC IRSR, Rev. 2-Letter Report. The staff produced ajournal paper, Pe5a Blanca Natural Analog Data in Performance Assessment Modela, as well as other papers and posters for presentation at various technical meetings. These papers have been or will be submitted for acceptance in recognized technicaljournals. Staff also participated in workshops, symposia, and other technical meetings.

The DWM JC year-to-date (YTD) cost variance was 13.9 percent. Spending rose significantly from the previous period as a result of increased activity in specific key technical issues, and the cumulative cost variance decreased for the first time this fiscal year.

In the Tank Waste Remediation System (TWRS) JC, staff completed minor revisions to the Hanford TWRS HLW Chemistry Manual (NUREG/CR-5751) to address Nuclear Regulatory Commission (NRC) editorial comments, and the NUREG/CR was published. Staff delivered the NRC Procedure for Inspection of TWRS-P Quality Assurance Program Implementation. The YTD cost variance was 23.0 percent. Spending decreased from last period; the cumulative variance has been essentially constant for three periods.

In the Three Mile Island Unit 2 (TMI-2) Independent Spent Fuel Storage Installation (ISFSI) JC, the staff conducted preparatory work for the annual CNWRA Quality Assurance audit that will take place during the next reporting period. The YTD cost variance for the TMI-2 ISFSI was -3.0 percent.

In the Dry Transfer System (DTS) JC, staff submitted Second Round Request for Additional Information, DTS-Final Letter Report and delivered the Outline of DTS-Draft Letter Report. The YTD cost variance was 12.8 percent, reflecting a substantial fall in spending from last period.

In the Centralized Interim Storage Facility (CISF) JC, staff developed the first round request for additional information (RAI) and submitted same as HOLTEC HI-STAR and HI-STORM TR RAI Report-Letter Report. The YTD cost variance for the CISF was 23.8 percent. Spending decreased from the previous period, and the cumulative variance was close to that of period 4.

In the Private Fuel Storage Facility JC, staff reviewed and evaluated site characterization reports, prepared the draft safety evaluation report, and revised the NRC draft positions on five Group I contentions. The YTD cost variance was -4.0 percent. Periodic spending continued to decline along with the cost variance.

In the Savannah River Site Aluminum-Based Spent Fuel JC, staff initiated preparation of Review of the U.S. Department of Energy Evaluation of Aluminum-Based Spent Nuclear Fuel-Final Report. The YTD cost variance was 73.3 percent, a decrease from last period.

Current spending estimates in all JCs are based on the assumption that staffing is consistent with the aggressive CNWRA hiring plan. A revised staffing plan was presented in conjunction with the delivery of the CNWRA Management Plan, Revision 7, Change 0. Current staffing remains below authorized levels, and recruitment continues.

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

CONTRACTOR: Southwest Research Institute (SwRI) 6220 Culebra Road, San Antonio, Texas 78238-5166 CONTRACT NO: NRC-02-97-009 JOB CODES: D 1035, J5164, J5186, J5206, J5226, J5210 NRC CNWRA PROGRAM MANAGER: John J.Linehan,(301) 415-7780 NRC CNWRA DEPUTY PROGRAM MANAGER: Deborah A. DeMarco, (301) 415-7804 CNWRA PRESIDENT: Wesley C. Patrick,(210) 522-5158 ESTIMATED HUDGET: $87,611,477 PERIOD OF PERFORMANCE: 09/27/97-09/27/02 PERIOD OF THIS REPORT: 05/08/99-06/04/99 1

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) preparing for an NRC/CNWRA Management Meeting; (ii) reviewing the status of CNWRA spending, uneduling, and staffing with NRC J

management; (iii) providing information concerning the development of NRC budgets for I

the next two FYs; (iv) addressing COI-related topics among the NRC, SwRI, and CNWRA l

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

The status of CNWRA staffing is indicated in table 1. During period 9, intensive recruitment continued and several sources were used to identify potential candidates. A materials scientistjoined the staff this period and an existing limited-term geologist became a regular full-time staff member. A nuclear engineer will begin work in period 10, and an engineering geologist, a geochemist, and a hydrologist are considering offers of employment.

i Computer system support activities encompassed (i) continuing the use of consultants to l

develop and modify software and perform systems administration for the Sun l

Microsystems, Silicon Graphics, and Windows NT servers;(ii) installing and upgrading the Q

desktop computers for basic system standardization and Y2K compliance; (iii) examining the need to revise the CNWRA Security System (firewall); (iv) updating all l

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hardware / software inventory records; (v) participating, as requested, in the monthly NRC/CNWRA Computer Coordination meeting; and (vi) maintaining LAN operations.

- QA activities included (i) preparing for the annual CNWRA QA audit; (ii) conducting surveillances, issuing nonconformance reports, as required, and working with cognizant staff in response to these reports; (iii) supporting the application of configuration control j

for CNWRA scientific and engineering software ready for release; (iv) preventing organizational COI 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 NRC.The CNWRA Audit Checklist was completed this period and was sent to NRC staff members who will observe the audit.

In the next period, the CNWRA staff expects to (i) participate in NRC/CNWRA management and ACNW meetings:(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; (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, develop new and modify existing databases and spreadsheets, and examine the LAN configurations, including the CNWRA firewall, for necessary modifications to maintain effectiveness; and (v) provide CNWRA LAN operation and maintenance support.

In addition, the staff will (i) participate in the annual QA audit; (ii) perform scheduled and unscheduled QA surveillances; (iii) conduct QA indoctrinations for CNWRA staff and consultants; (iv) review SwRI RFPs for potential COI; (v) perform QA verification checks on each CNWRA outgoing deliverable; (vi) and finalize the schedule for the second presentation of the Training Module on Observation Audit Techniques to appropriate NRC staff.

1.2 Igneous Activity (IA)

Staff participated in the DOE /NRC TSPA-VA technical exchange in San Antonio, Texas, this period. Several presentations discussed the demonstrable contribution of volcanic events to TSPA risk calculations. Although staff have technical concerns with analyses presented by the DOE in the TSPA-VA, post-VA interactions with the DOE staff contributed to subissue resolution. Current evaluations of volcanism risk have appreciable ure-rtainties influenced by likely underestimates of the number of WPs disrupted during vcu aic events and likely overestimates of the airborne particle concentrations through time. l'echnical bases for these processes will need development to meaningfully reduce uncertainties.

Numerical modeling of magma-repository interactions continued during this period.

Dr. Onno Bokhove (University of Bristol) completed a preliminary model for two compressible, inviscid fluids, simulating a two-phase melt containing 1-3 percent volatiles intersecting a repository drift. This is a ID isothermal model. Preliminary results indicate that the melt-volatile mixture expands rapidly, filling a 100-m-long tunnel in 3-5 sec. Shock waves amplify by approximately a factor of 10 after reflection off the end of the tunnel, and force acting on a canister-end in the tunnel is on the order of 10' N, acting over a period of 2

o, approximately I sec. This model also shows a rarefaction wave propagating down the dike after intersection with the tunnel. During a one week visit to the CNWRA, the staff agreed that Dr. Bokhove's future activities will include (i) comparison of the model results with simple analytical solutions and physical analog experiments for shock wave propagation, (ii) development of a time-varying cross section of the dike-drift intersection to capture gradual opening of the dike-drift interface, and (iii) assessment of variation in the tunnel cross-sectional area with distance along the drift to model the effects of canisters on flow.

Staff presented the results of current volcanism risk assessments at the YM special session of the AGU spring meeting. This presentation outlined the technical bases for current expected annual dose calculations. Comments received on the presentation focused on the

- programmatic implications of volcanism risk rather than evaluating the technical bases for

-- the underlying calculations. No new information was presented on the DOE modeling approaches for igneous events.

The staff pursued bringing together computer codes used to gather real-time gdophysical data and post-process these data under TOP-018 Software QA requirements. Staff completed written input to the National Research Council review of the USGS volcanic hazards program, and wrote the section on modern methods in long-term volcanic hazard assessment for the National Research Council report. Preparations began for a presentation on igneous activity risks at the June 1999 ACNW meeting in San Antonio, Texas. Final revisions continued to an article on probabilistic volcanic hazards assessments for YM for the Journal of Geophysical Research.

In the next period, staff will present the results of ongoing risk assessments at the June 1999 ACNW meeting in San Antonio, Texas. Staff will begin preparing presentations for the International Union of Geodesy and Geophysics meeting and for the external review of TPA. Refinement of the experimental apparatus and development of numerical models for magma-repository interactions will continue at the University of Bristol.

1.3 Structural Deformation and Seismicity (SDS)

Staff prepared for and presented two papers at the AGU spring meeting. The first was an invited paper in the Yucca Mountain Session entitled Incorporation of Tectonic Processes in Probabilistic Risk Assessments of the Proposed High-Level Radioactive Waste Repository at Yucca Mountain, Nevada: Nuclear Regulatory Commission Staff Approach.

This paper was ajoint NRC and CNWRA effort. The second paper was Three-Dimensional Geometry of the Bare Mountain Fault (Nevada): Implications for Fault Kinematics and Basin Evolution, given at a special Tectonics session on faulting.

At the NRC headquarters in Rockville, Maryland, staff participated in a two-day technical exchange on Version 3.1 of the DOE Geologic Framework Model (GFM3.1).

Representatives from the DOE and associated contractors were included in this technical exchange. Participants discussed the DOE planned use of the GFM3.1, model abstraction methods, model horizon stratigraphy, model fault placement and geometry, data utilization and qualification, and model development techniques.

Staff conducted field work that initiated analyses of the structural and sedimentological I-architecture of the alluvial aquifer. As part of the augmented work for the SDS KTI, this 3

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study included exwinations ofexposed alluvial sections in the channel of Fonymile Wash, source areas for sediment incorporated into the alluvium and other valley fill material, and core and cutting samples from the Nye County wells in the YM sample management facility.

Staff continued revising the USFIC deliverable, Input to NRC Working Group on Viable SZ Conceptual Flow Models, which summarizes the work of the Structural Effects on Flow

. Working Group. Additiona! sensitivity studies of direct WP rupture from faulting in the repository were conducted using the FAULTO module of the TPA code. These sensitivity studies will be included in the revised SDS IRSR.

In the next period, staff will concentrate on revision 2.0 to the SDS IRSR and conduct field work to study the fracture systems at YM. CNWRA staff and selected consultants will attend the next ciuanerly meeting of the DOE and UNLV group studying the thermochronology of YM.

I 1.4 Evolution of the Near Field Environment (ENFE)

CNWRA and NRC staffs continued their collaboration and CNWRA staff provided contributions to Revision 2 of the ENFE IRSR.

Staff panicipated in a DOE /NRC TSPA VA technical exchange in San Antonio, Texas, May 25-27,1999. A presentation was given on ahernative source-term mc,dels based on natural analog oxidation rate constraints and uranyl mineral solubility and coprecipitation models.

The staffcompleted papers for inclusion in the proceedings of the 8* European Commission Natural Analogue Working Group Workshop held in Strasbourg, France, March 23-25, 1999. This planned submittal was proposed in the period 8 PMPR as a new deliverable titled Pena Blanca Natural Analog Data in Performance Assessment Models-Journal Paper.

In response to a DOE request and at the direction of the NRC,12 rock samples from the Nopal I natural analog site were sent to LANL. In accordance with the request, the samples were selected on.the basis of their potential for yielding uranium-series isotopic characteristics reflecting recent, open-system radionuclide release and transpon. LANL investigators will perfonn high-precision uranium-series analyses in an attempt to reconcile differing LANL-CNWRA interpretations of existing data.

Augmented studies of Nopal I continued toward understanding radionuclide release rates.

An SOW for field investigations at the site was issued to a consultant. These investigations will focus on mapping and sampling young secondary deposits that may yield data on U release rates. In addition, sample selection and preparation continued in new efrons to date U-rich caliche and opal from the Nopal I site. A number of caliche and opal samples have been culled from the CNWRA collection. Staffinitiated physical removal of the secondary

. deposits from their tuff substrates and began compiling information about the Nopal I analog site into a form suitable for use on an internet web page.

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N Staff continued debugging and testing the MULTIFLO code, Version 1.2p. The METRA flow module was successfully benchmarked agairist a well-known analytical solution for drawdown in a confined aquifer. Work began on a 1D benchmark problem designed to test the fully coupled mode of operation, including p:rmeability modification due to mineral dissolution. Testi.ig of the unstructured grid capnbilities continued.

Staff completed a I D dual continuum reactive transport model of the ambient and thermally loaded pore water geochemistry at YM to address the importance of initial and boundary conditions on the thermally perturbed system. Results from this model were presented at the AGU Spring Meeting in Boston, Massachusetts, May 31-June 4,1999, in the special session Innovative Applications of Geochemical Modeling to Groundwater Contamination Problems.

Staff reviewed the literature and performed experimental studies on cement at elevated ter1.ntures and continued the development of thermodynamic properties of cement minerals at elevated temperatures. A subcontract for conducting additional cement studies was conveyed to the University of Aberdeen for their approval.

Uranophane was synthesized for use in solubility and coprecipitation experiments by reacting uranyl acetate, sodium metasilicate, and calcium acetate at 150 *C in a Parr Model 4522 stirred reaction vessel. The reagents were mixed in the stoichiometric ratio Ca:U:Si =

2:1:1. XRD analysis indicates that the solid produced in the synthesis is alpha-uranophane.

No other mineral phases were detected by XRD. Optical examination of the uranophane indicates that it is composed of very fine, acicular crystals.

In the next period, a QA audit of the CNWRA ENFE KTI will be conducted as part of the annual CNWRA QA audit. Staff will prepare a progress report on a literature study and experiments on the performance of cement at elevated temperature. They will continue to debug and benchmark the MULTIFLO code, using the code to simulate the proposed repository near field. Staff will continue near-field radioelement solubility modeling and aqueous actinide chemistry studies together with sensitivity studies on the effects of cementitious materials. Interactions with NRC staff will be undertaken to help define the scope of the review of the DOE Disposal Criticality Analysis Methodology Topical Report.

Sample preparation and initial semi-quantitative gamma spectroscopy measurements will be conducted on samples from Nopal I to identify U-rich caliche and opal.

1.5 Container Life and Source Term (CLST)

Staff initiated their input to CLST IRSR, Revision 2 following discussions between CNWRA and the NRC staff on the annotated outline.

CNWRA staff continued preparing Assessment of Performance Issues Related to Alternate EBS Materials and Design Options, originally due June 18, 1999. This report will summarize the materials, characteristics, 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. Because of the higher priority of the IRSR and the upcoming Appendix 7 meeting at LLNL, the delivery date for this report was changed to August 13,1999.

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II Electrochemical corrosion testing continued to confirm the applicability of repassivation and corrosion potentials as predictive parameters for the long-term, localized corrosion of corrosion-resistant container materials in chloride-containing solutions at 95 *C. During this reporting period, the tests were interrupted to allow the test specimens to be inspected for signs of localized corrosion. 'After inspection, tests using Alloy 825 specimens continued, including a creviced specimen held at 100 mV3cs (50 mV less than the repassivation potential) in a 1,000-ppm-chloride solution. No evidence of localized corrosion was observed for a total test time of 1,351 days. A'second Alloy 825 test specimen has been immersed in an air-saturated 1,000-ppm-chloride solution at open circuit for a tutal test time of 1,205 days. Crevice corrosion was observed on this specimen several times during the test when the corrosion potential exceeded the repassivation potential.

Three Alloy 22 specimens.with attached crevice-forming devices are being tested in 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 an Alloy 22 specimen held at an applied potentials of 400 and 500 mV3cs.

The passive dissolution rate of Alloy 22 was measured in soluuons of various pHs (0.7,2, and 8) containing 0.028-4 M chloride at 25 and 95 *C. Tests are now being conducted on specimens thermally aged for 4,8, and 12 hr at 800 *C. Higher passive dissolution rates and an increased susceptibility to intergranular corrosion were observed with an Alloy 22 specimen thermally aged for 24 hr at 800 'C. Measurements of the repassivation potentials of welded specimens continued using an autoclave in 0.5-4M chloride solutions at temperatures ranging from 95 to 150 *C. Marked localized corrosion preferentially developed at the welds was observed in the welded specimens, which also exhibits lower repassivation potentials than those measured in nonwelded specimens.

SCC tests of Alloy 22 and type 316L SS specimens continued. Fatigue precracked, wedge-loaded DCB specimens of each material we e 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 33 MPa m", while the type 316L SS specimens were tested at an initial stress intensity of

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25 MPa m". No cracking of the two alloys was observed under these testing conditions for a cumulative test time of 26 wk. Testing under open-circuit potential conditions in MgCl2

- solutions (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 10-8 m/see was measured at K = 22 MPa m". A much longer exposure period was required to initiate SCC i

at an applied potential of -340 mV3cs, which is slightly above E,(-390 mVsce) with an average crack growth rate of 2.5 x 104 m/sec. No substantial crack growth was observed on Alloy 22 specimens tested for 15 and 26 wk in 40 percent MgCl at i 10 *C under open-2 circuit conditions. Secondary cracks, observed along grain boundaries near the tip of the fatigue precrack, did not propagate after an additional 5 wk of exposure. More tests using 316L SS specimens under applied potential conditions are planned to determine the relationship bet.veen 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.

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~1 Effect of Environmental Variables on Localized Corrosion of Carbon steel, was sent for review by the NRC for future publication in Corrosion journal. This is a revision of an earlier report and incorporates NRC staff comments. Further work related to the potential

' effects of a reverse VA WP design on carbon steel corrosion has been conducted and the results are being evaluated.

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.

The effect of chloride concentration and pH on the critical potentials for localized corrosion as well as the environmental effects on the passive dissolution ofTi-Grade 7 are the current focuses.

During the last period, Dr. Charles Greene (NRC) conducted an experimental investigation of the effect of pH, chloride, and temperature on the corrosion behavior of Zircaloy-4 as part of a staff exchange. The objective of the study was to refine the models for the performance of zircalloy cladding in the TPA code. The investigation indicated that pH had little effect on the critical potentials for localized corrosion of Zircaloy-4. Temperature and chloride concentration both influenced the critical potentials with higher temperatures and higher chloride concentrations leading to decreases in the critical potentials. Preliminary results also suggested that under fully air-saturated conditions, localized corrosion of zircalloy did not occur, even when 5 mM hydrogen peroxide was added to the solution. On the addition of 10 mM ferric chloride, however, some corrosion was observed. Analysis is progressing on the effect of rock fall on the mechanical failure of Zircaloy-4 cladding in spent fuel assemblies. This analysis uses a fracture mechanics approach to consider the effects of flaws and other cladding defects from reactor operation and post-operation handling.

Staff initiated confirmatory testing of glass wasteform during the last period. Staff

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completed the 7-day testing on the standard EA glass and two simulated waste glasses i

(DWPF Blend I and WVNS Reference 6) using the ASTM PCT, Method A. This permits the staff to calibrate its equipment and ensure proper working procedures are in place.

Long-term tests on these three glasses were conducted in deionized water and concentrated FeCl and FeCl solutions (0.25 and 0.0025 M). These tests will continue for 6 mo, with 2

3 solution replacement twice a week. Leachate compositions are to be analyzed using ICP.

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, i

Also during the last period, a new CNWRA staff memberjoined the CLST KTI team. He is engaged in the development and implementation of suitable corrosion potential and chemistry (chloride and pH) sensors that can be used under heat transfer conditions. A small group of candidate sensor designs was selected for laboratory evaluation from a large array of possible sensor technologies. This work will lead to the instrumentation and i

emplacement of sample WP coupons in the sinaulated drift experiments coordinated by the j

TEF KTI team.

In the next period, staff will continue revision of the IRSR, the long-term corrosion tests of Alloys 825 and C-22, and the SCC tests using Alloy C-22 and type 316L SS. Limited

• l testing of A516 carbon steel should be completed to satisfy some outstanding concerns. The 7

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Ti alloy test program will be fully implemented including initiation oflong-term corrosion

. tests. In addition, staff will continue examining the effect of the environment on the corrosion behavior of Zircaloy-4 and identifying the sensors to be used in the TEF KTI simulated drift experiments. Glass dissolution tests will continue.

1.6 Thermal Effects on Flow (TEF)

Analysis of the second test of the laboratory-scale boil'ing isotherm depression heater experiment continued during this period. Multiple samples of the blocks were collected for saturation and sorptivity testing. Preliminary measurements of saturation clearly indicate the moisture redistributions in the concrete matrix at the end of the test. Moreover, initial calculations suggest a 10-fold reduction of sorptivity due to the application of the sealant prior to the second test. Staff is preparing a journal paper based on this activity.

Development and evaluation of a repository-scale test model continued. An east-west section through Antler Ridge was extracted from the DOE 3D geMogical framework model.

The section will be discretized using unstructured gridding and a dual continuum model and analyzed using METRA.

Staff continued preparation of a proposed laboratory-scale coupled corrosion / heater experiment in support of the activities related to the TEF and CLST KTIs. Media preparation and sensorevaluation are ongoing Welded ttff from the Apache Leap Test site.

which is available at CNWRA, is being prepared for use in the laboratory-scale heater test.

Staff presented a paper titled Formation of a Dry-Out Zone Around a Heat Source in a Fractured Porous Medium at the 2"' International Symposium on Two-Phase Flow Modeling and Experimentation in Pisa, Italy, May 22-26,1999.

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 is near completion. Numerical investigation of the diversion mechanism continued. An unstructured grid option to the MULTIFLO code has been successfully implemented. The effect of grid discretization of the unstructured grid is under investigation.

The technical approach for measuring dripping into a drift opening was developed and preliminary measurements and observations were made of dripping from laboratory analogs of open fracture faces. 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 poster entitled Dripping into Subterranean Cavities from Unsaturated Fractures was presented at the AGU spring meeting, highlighting the changes in the model brought about by the initial laboratory observations. A report on the model development is currently undergoing CNWRA technical and programmatic reviews.

Revision 2 of the TEF KTIIRSR was submitted as Input to TEF IRSR, Revision 2-Letter Repon.

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In the next period, staff plans to (i) complete the journal article on the boiling isotherm l

penetration laboratory-scale experiment,(ii) test the MULTIFLO DCM numerical code in modeling the DOE DST and mountain-scale nonisothermal flow (iii) integrate a groove / film flow modelinto the mechan; tic fracture flow model,(iv) continue analysis of a 60 MTU/ acre repository, (v) initiate sensitivities analyses of the REFLUX 3 module in TPA Version 3.2, and (vi) participate in the ACNW meeting at CNWRA in San Antonio, Texas.

1.7 Repository Design and Thermal-Mechanical Effects (RDTME)

I Staff continued the TM study of drift stability in the area where the transition from strong to weak rock occurs. The objective of this study is to determine whether a synergistic effect exists that could adversely affect drift stability in this area under thermal conditions. The modeling results using the UDEC computer program are being analyzed further to idendfy the region with a potential failure problem. Staffis 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 half. A UDEC study has begun on the behavior of the emplacement drifts in the lithophysal region considering the enhanced alternative design Nr. 2.

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 the KDYNA 3D. This problem 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 pursued development of a review plan for the raclosure aspects of design, construction, and operations of the repository using the.ategrated safety assessment methodology. An outline for the preclosure review plan is being prepared. Several meetings involving the NRC and CNWRA team members were conducted to discuss the format of the outline. One consultant and one subcontractor visited the CNWRA to work on the development of acceptance criteria and review methods for the preclosure review plan using l

integrated safety analysis methodology.

j 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 l

from the repo.itory-scale model. The key focus is the effect of long-term degradation of rock mass properties on stability of the emplacement drifts arid hydrologic behavior in the surrounding area.

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4 Staff reviewed the literature on concrete performance at high temperature to provide 1

valuable information to assess the proposed DOE design alternative that would use a

- concrete liner at high temperature.

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 propenies 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) participate in the ACNW meeting at CNWRA in San Antonio, Texas.

1.8 Total System Performance Assessment and Integration (TSPAI)

Staff have continued preparing the sensitivity studies report for the TPA Version 3.2 code.

This report both documents the specific results obtained from applying a variety of sensitivity analysis methods and explains their 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. Because the scope of the report was reduced, NRC staff determined that ISI leads from the KTIs will review the document after its delivery.

The DOE /NRC TSPA-VA technical exchange was held May 25-27,1999, at the CNWRA in San Antonio, Texas. Staff conducted numerous TPA runs, analyzed results, and compared DOE and NRC results as part of preparing presentation materials for the technical exchange. Presentations were made by PA staff on the overall stmeture of the TPA Version 3.2 code, base case results from the TPA Version 3.2 code, and comparisons of results from the TPA Version 3.2 code using input parameter data from the TSPA-VA.

In addition, a presentation was made on the degree to which the TSPA-VA meets the NRC expectations for transparency and traceability.

Development of an SRD for the post-processor was completed and will be delivered to NRC for review during the next period. A limited feasibility study on the development of the post-processor was conducted in support of the SRD. The paperwork for a consultant to assist in the further development of a processor for systematic analysis of TPA results is currently underway.

YMRP development continued in collaboration with NRC staff. Refinements were made to the YMRP outline. Preparation began of acceptance criteria and review methods for the individual review plan sections. CNWRA staff began reviews of existing NRC regulatory guidance and review plans for other regulatory programs to identify material that can be incorporated into the YMRP.

Review materials were sent to external experts panicipating in the July 27-29,1999, meeting on the TPA Version 3.2 code. A review plan and agenda for the meeting were developed and submitted for comments.

This period, CNWRA QA staff kept up to date with the activities performed and reponed on by the DOE. There were di cussions with NRC staff on the DOE YM QA corrective actions.

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I Staff initiated the development of the TPA Version 3.3 code and implemented modifications approved by the NRC staff.

Preparation continued of Revision 2 to the TSPAl IRSR in which particular focuses are (i) multiple barriers, (ii) transparency and traceability, and (iii) updates to the descriptions of the model abstractions.

l A CNWRA staff member attended the NEA Workshop on Scenario Development held in i

. Madrid, Spain, and made a presentation on the NRC approach to scenario development. The results of the workshop will be described in a future PAAG report.

Staff continued to interview candidates for the unfilled positions of health-physicist and nuclear engineer. R6 sum 6s continue to be gathered for other open positions. A new staff member willjoin the CNWRA next period.

In the next period, the staff will focus on (i) developing the sensitivity analysis report; (ii) preparing revision 2 of the IRSR; (iii) preparing the YMRP;'(iv) comparing the TSPA-VA and the TPA Version 3.2 code results; (v) planning and preparing presentation materials for the ACNW meeting; and (vi) planning and preparing presentation materials for the external review. Recruitment will continue for the two PA modelers, the two health physicists, and a risk analyst.

1.9 Activities Related to Development of the NRC High 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.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 early next period. A final verification review was completed. 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, i

but software licensing issues require resolution prior to starting work.

i A copy of the draft proposed EPA HLW standard was obtained during period 9. CNWRA began review of the draft proposed standard, which will continue at a low level during the next period.

A new task-compiling and analyzing GIS data related to selection of potential receptor groups-started. This period, existing data at NRC and CNWRA were investigated and compiled for further analysis. Initial scoping discussions were also conducted.

No major progress was made on other new tasks due to staff emphasis on existing priorities (e.g., the DOE /NRC TSPA-VA technical exchange). These new tasks include reviewing 11

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f information supponing' plant uptake factors for selected radionuclides in the TPA Version 3.2 code, detennining whetherthe 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 will continue. 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 resolve software licensing issues related to investigating the feasibility of an improved (stochastic) dose module for the TPA code.

Increased effort on analysis of GIS data related to selection of potential receptor groups and review of information supporting plant uptake factors in the TPA Version 3.2 code are expected in period 10. Review of the draft EPA Standard is expected to begin at a low level along with other new tasks related to parameter improvements, implementation of human

. intmsion in TPA, and investigation of radionuclide buildup effects from irrigation. The

~ hiring of a new staff member with a health physics background should help to reduce staff availability limitations to some extent next period.

1.10 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC)

Staff prepared and delivered several posters and oral presentations at the AGU Spring Meeting in Boston, Massachusetts, May 31-June 4,1999. These presentations covered a variety of topics, including (i) assessment of changes in deep percolation over a glacial cycle due to linked changes in climate, soils, and vegetation at YM; (ii) evaluation of dripping into subterranean cavities from unsaturated fractures: (iii) investigations of cavity wall roughness effects on seepage into underground openings; (iv) analysis of hydrogeologic inferences from thermal and chemical measurements in the SZ; (v) use of barometric and eanh-tide responses in wells to infer vertical connectivity in the tuff aquifer; and (vi) studying geophysical and hydrogeologic aspects along a fault zone.

Investigations continued on the process of drift seepage and capillary diversion of deep percolation away from open drifts. Analysi' of the effect of cavity wall irregularities on seepage into drifts yielded sonw preliminary results using a quasi-linearized porous media continuum approach. These preliminary results, suggesting that threshold percolation flux may be reduced an order of magnitude by 10-15 cm asperities at the drift wall crown, were presented at the DOE /NRC TSPA-VA technical exchange in San Antonio, Texas, on May 25-27,1999, and at the AGU Spring Meeting in Boston, Massachusetts, May 31-June 4,1999.

Staff continued work on a model of coupled heat and fluid flow in the SZ. Preliminary calculations using the computer code MULTIFLO and a 3D unstructured grid honoring the complex hydrogeology of the area were completed. These calculations reproduced high-and low-temperature features observed from borehole logs. The high-temperature features had previously been attributed to upward flow from the carbonate aquifer, but were

- reproduced in the simulations without this upwelling. Future work will attempt to refine the calibration to better estimate groundwater velocities in the YM vicinity.

One CNWRA staff member panicipated in a workshop on groundwater modeling in the Death Valley region, hosted by the USGS, May 24-25,1999, in Amargosa Farms, Nevada.

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Staff, working in close collaboration with the NRC PEM, delivered a major milestone report, Input to USFIC IRSR, Revision 2-Letter Report. This document reflects staff I

conclusions and concerns regarding status of the USFIC subissues following review of the l

DOE TSPA-VA and supporting documents.

l l-Preparation continued on Input to NRC Working Group on Viable SZ Conceptual Flow Models and on Modeling and Analysis of C-Well Tests-Letter Report.

In the next period, USFIC activities will include (i) preparation of Input to NRC Working Group on Viable SZ Conceptual Flow Models;(ii) completion of Modeling and Analysis of C-Well Tests-Letter Report; (iii) investigation of models for seepage and dripping in underground cavities; (iv) analysis of processes affecting deep percolation; (v) participation in development of the YMRP; (vi) collaboration with the NRC on final edits to revision 2 of the USFIC IRSR;(vii) participation in a Program Review on Infiltration and Conceptual Models to be hosted by the NRC in Beltsville, Maryland; and (viii) participation in a public Workshop 'on Groundwater Modeling Related to Dose Assessments scheduled at NRC headquarters in Rockville, Maryland.

1.11 Radionuclide Transport (RT)

Preparation continued on a paper titled Urana.: Chemistry and Isotopy in Waters and Rocks at Peaa Blanca, to be included in the proceedings volume of the 8* European Commission Natural Analogue Working Group Workshop, held in Strasbourg, France, March 23-25,1999. The paper is a history of U at the Nopal I natural analog using existing CNWRA data. The final paper was proposed as a new deliverable Uranium Chemistry and Isotopy in Waters and Rocks at Pena Blanca-Journal Paper in table 2 of the period 8 PMPR.

CNWRA programmatic review was completed for Stochastic Analysis of Early Tracer Arrivals in a Multiple-Fracture Pathway-Journal Paper. The deliverable is intended for publication in the Journal of Geophysical Research. An abstract titled The Role of Radionuclide Sorption in High-Level Waste Performance Assessment: Approaches for the Abstraction of Detailed Models was prepared for an invited presentation at the Soil Science Society of America Annual Meeting to be held in Salt Lake City, Utah, October 31-November 4,1999.

CNWRA staff continued to prepare for colloid sampling from tunnels in Rainier Mesa as an analog test of colloidal transport in fractured, unsaturated tuff. This included successfully completing Underground Worker Training and Radiation Worker II training for the NTS.

CNWRA staff traveled to Nevada to participate in the May sampling event for wells associated with the Nye County EWDP. Staff observed sampling practices and retrieved samples from two wells. As part of the sampling event, officials from Nye County coordinated a group of individuals from several organizations (including Nye County, USGS, DOE, LANL, the State of Nevada, University of Nevada, Las Vegas, and CNWRA).

Efforts were made to ensure each interested party had ample opportunity to collect water samples from each well that could be sampled. Purging requirements generally limited the number of wells, or zones within a well, that could be sampled in any one day. CNWRA 13

4 staff collected samples from both hydrologically isolated zones in well NC-EWDP-Is and from the deepest of four isolated zones in well NC-EWDP-9s. Samples were collected by CNWRA for analysis of major cations and stable isotopes of O and H. Four liters of water were collected for each sample. Two liters were filtered through 0.45 pm filtration apparatus and preserved using HNOp one liter was preserved using HNO but not filtered, 3

and one liter was collected without filtration or preservation. On-site analyses included pH, temperature, turbidity, oxygen reduction potential, conductivity, and alkalinity. Preliminary

- analysis revealed good agreement between on-site measurements and indications from inline probes operated by LANL staff at the time of sample collection.

The investigation is ongoing of Np sorption on alluvium minerals, crushing, and sieving natural calcite samples. Effons continued to prepare a 60-200 mesh size fraction, remove fine particles, and stabilize the surface of each grain by equilibrating the calcite in 0.02 M NaHCO.

3 Staff completed U sorption experiments on 60-100 mesh size fraction quartz with iron impurities and compared the resultant data with those for quartz without iron impurities.

Though more sorptive iron oxides were present in the untreated samples, they did not exhibit enhanced sorption behavior. Also, silica and aluminum analyses were conducted on experimental solutions from mixed mineral sorption experiments.

Staff continued the evaluation of published experimental data on ion exchange between aqueous solutions, the zeolite mineral clinoptilolite, and development of thermodynamic parameters for predicting ion-exchange equilibria. They conducted a literature search of data on the chemistry of SZ groundwater in the YMR. Of panicular interest are chemistry data on reduced groundwater reported by the DOE. The implication of reduced groundwater on the transport of Tc-99 and on repository performance will be investigated using the GWB and TPA Version 3.2 codes.

CNWRA staff made a presentation on geochemical radionuclide sorption models for PA and panicipated in the DOE /NRC TSPA-VA technical exchange held in San Antonio, Texas, May 25-27,1999. Staff continued to help prepare the YMRP outline. Activities included mapping the acceptance criteria from the RT IRSR onto the proposed outline for the YMRP. The author-final draft of major milestone Input to RT IRSR, R evision 1-Letter Repon was placed in CNWRA technical review.

In the next period, staff will continue sorption experiments on alluvium minerals. Sorption experiments to evaluate the effects of trace iron oxyhydroxides on U sorption will be continued and results interpreted. Microscopic analysis of well cuttings from NC-EWDP-2d will continue. CNWRA staff will prepare to analyze water samples from Nye County wells NC-EWDP-Is and NE-EWDP-9s. CNWRA reviews will be completed on input to RT IRSR, Revision.1-Letter Repon and it will be submitted. 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.

CNWRA will participate in colloid sampling in the tunnels in Rainier Mesa.

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'a 1.12 Tank Waste Remediation System (TWRS)

In subtask 1.2, the NRC staff comments on the Low Activity Waste Auxiliary Support i

Systems II-Process Systems Hazard and Safety Issues Report for TWRS-Letter Report were received and are being addressed. Also, staff is working on a presentation on the Vitrification of Radioactive Wastes to the Regulatory Unit of the Department of Energy.

j The presentation will consist of two 4-hr sessions sununarizing work on this subtask during the last 2 yr, in subtask 1.6, technical and editorial reviews of the report on the Chemistry of Hanford Tank Waste Remediation System Pret eatment Technology were completed. All chapters are undergoing a programmatic review. With the concurrence of the NRC PO, the current due date of the draft final report-June I l-was changed to June 18,1999. A final version, which addresses additional NRC comments, is currently scheduled for submission July 30, 1999.The extension of the submittal date for the draft report will delay the final report. The new date for transmittal of the final report will be discussed with NRC staff during the CNWRA staff visit to NRC in July. Minor revisions to the Hanford TWRS HLW Chemistry Manual (NUREG/CR-5751) to address NRC editorial staff comments were completed and the NUREG/CR was published.

In subtask 2.2, the NRC Procedure for Inspection of TWRS-P Quality Assurance Program Implementation was delivered on May 26,1999.

In the next period, in subtask 1.2, staff will incorporate the NRC comments on these i

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. The last report was submitted in the previous FY, and the revised document will be included in the Low-Activity Waste System Hazard and Safety Issues-Final 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, programmatic review of the pretreatment chemistry report will be completed and the report will be transmitted. The staff will prepare a presentation for the NRC staff on this pretreatment chemistry report.

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

TMI-2 staff conducted preparatory work for the CNWRA annual QA audit will occur during the next reporting period.

In the next period, TMI-2 ISFSI staff will participate in the CNWRA annual QA audit on the TMI-2 project.

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c 1.14 Dry Transfer System (DTS)

Staff transmitted Second Round Request for Additional Information, DTS-Final Letter Report. Also, Outline of DTS SER-Draft Letter Report was submitted. The SER

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continued to be developed during this period at a slow rate.

i In the next period, DTS staff plans to continue development of the SER at a slow rate.

1.15 Centralized Interim Storage Facility (CISF)

Detailed technical review of the topical report on HI-STAR /HI-STORM cask system deployment at high-seismic sites continued during this reporting period. The first round RAI was submitted as HOLTEC HI-STAR and HI-STORM TR RAI Report-Letter Report.

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

In the next period, the staff plans to continue detailed technical review of the topical report on HI-STAR /HI-STORM cask system deployment at high-seismic sites and work on the computercode RISKIND while awaiting the DOE response to the SFPO RAI on the HI-STAR and HI-STORM topical report for high seismic sites and instructions to revise the draft AR.

1.16 Private Fuel Storage Facility (PFSF)

Review and evaluation of the site characterization reports, preparation of a draft SER, and revision of the NRC draft positions on five Group 1 contentions continued during this reporting period. NRC and CNWRA staffs engaged in extensive interactions to prepare the NRC final position on 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)

The staff made considerable progress in its review of the DOE reports on dissolution of Al-based spent fuel, fuel processing, and disposability assessment. Preparation began on Review of the U.S. Department of Energy Evaluation of Aluminum-Based Spent Nuclear Fuel-Final Report.

The operations plan for this project was revised to reflect the decreased scope of work and the decreased funding level.

In the next period, review of the DOE reports will be completed, along with writing the final repon.

16

2

. MANAGEMENTISSUES Further evaluations of spending, scheduling, and staffing will be reviewed next period at the NRC/CNWRA Management Meeting.

3 MAJOR PROBLEMS None to report.

4_

SUMMARY

OF SCHEDULE CHANGES S

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 $618,623.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 p

)

. COPS and ten KTIs, TWRS JC, TMI-2 ISFSI JC, DTS JC, CISF JC, PFSF JC, and SRS ASF JC. The planned costs per period are based on the revised spending plans contained in the current operations j

plans.

It should be noted that the current spending estimates in all JCs are based on the assumption 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. Current staffing remains below authorized levels because of slower than anticipated hiring and unexpected attrition; dedicated recruitment continues.

Period 9 FY1999 CNWRA composite expenditures rose 16.6 percent from the previous period, and this aggregate of all JCs was underspent by $1,400,270 or 14.7 percent. When comparing period 9

- with last period, the DWM and SRSASF JCs evidenced higher spending levels while the TWRS, TMI-2 ISFSI, DTS, CISF, and PFSF JCs showed lower levels.

Expenditures on SwRI labor, consultants, and subcontractors as a proportion of composite spending on all JCs were 24.7 percent. Expense of consultants and subcontractors as a fraction of composite

{

spending on all JCs was 14.8 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 52 staff members, reflecting addition of a materials scientist this period. 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 administrative expenses, and fees).

The DWM JC was underspent by $1,141,129 or 13.9 percent. Overall expenditures increased about 24.7 percent from the previous period as costs rose in COPS and the SDS, ENFE, CLST, RDTME, TSPAI, ARDR, USFIC, and RT KTIs but declined in the IA and TEF KTIs. Costs to date are 27 percent above those a year ago, and period 9 costs are 34 percent greater than the same period 17-

ast year. The FY1999 budget is 24 percent greater than FY 1998. Spending on the augmented scope ef 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 management staff continue to discuss current and expected levels of spending, aggressive recruitment efforts for core staff, and effective engagement of consultants and subcontractors. The CNWRA does not expect to attain the estimated spending in the currently approved OPS by the end of FY1999. A detailed assessment of anticipated spending has been provided to NRC, and updates to this assessment will be provided as required.

The cost variance for COPS was 15.9 percent: 17.0 percent for the Management, Planning, and Computer Support subtask (158) and 11.3 percent for the QA subtask (159). Spending this period in subtasks 158 and 159 rose relative to last period. Labor costs in subtask 158 decreased about 1.6 percent from last period, primarily the result of less staff utilization; however, such costs increased 60.7 percent in subtask 159. Other Direct Costs rose substantively in subtask 158 from the previous period, but declined moderately since the last period in subtask 159. In the next period, 1

spending in subtask 158 is expected to be less than estimates as staff are recruited in computer-related areas. Consultants will be used in the IMS area to mitigate staff lost through attrition and to support the revision of the CNWRA LAN, creation of new and revision of existing databases, and modification of the firewall. CNWRA management will continue to encourage eligible staff to participate in professional development activities. In subtask 159, spending again will increase in period 10 as the QA audit team (technical specialists and auditors) completes the annual audit and compiles their reports. Total spending for the balance of FY1999 will be less than estimated.

The cost variance for the IA KTI was 11.9 percent. Spending decreased slightly relative to last

. period, along with the cumulative percentage variance. Substantial consultant and subcontractor costs are outstanding; 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 thmmainder of FY1999.

The cost variance for the SDS KTI was 14.5 percent, although expenses rose from the previous period. The variance is due to the spending plan augmentation that occurred in period 6. Substantial consultant and subcontractor cocts are outstanding; 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 begin various projects: modifying the 3DStress code, studying the Fortymile Wash alluvium, and mapping and interpreting fractures at YM.

The cost variance for the ENFE KTI was 13.8 percent. This is a significant reduction in the cumulative percentage variance from period 8 (15.6 percent). Existing commitments to the ENFE KTI are approximately $168 K. Further reduction in the current variance is strongly dependent on timing of the receipt and payment of invoices corresponding to those substantial commitments.

The cost variance for the CLST KTI was -0.8 percent. Spending increased compared to period 8 because of the addition of one new staff member and several summer st'udents. At this time, the

.' projected cumulative spending at the end of the FY is expected to be about 5 percent above budget.

The cost variance for the TEF KTI was 1.6 percent. The small decline in spending from the previous period is due to lagging charges from consultants and subcontractors. Future actual expenditures are expected to follow the budget for this KTI.

I8

The cost variance for the RDTME KTI was 11.8 percent. Spending rose significantly this period, thus reducing the cumulative percentage variance. It has not reached the augmented budget level however. This cost undemm is due to temporary assignment of staff to other tasks 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 FY1999. The FY1999 total expenditures are expected to converge to the FY1999 allocation.

The cost variance for the TSPAI KTI was 20.2 percent. Spending increased significantly over the previous period, exceeding the period 9 planned expenditures, due in part to increased work on the YMRP, preparation of the sensitivity studies report, and conduct of the DOE /NRC TSPA-VA technical exchange. Total underspending should continue to decrease as a result of additional SwRI and consultant resources devoted to development of the TPA post-processor and TPA Version 3.3 code, the addition of new staff, and participation in the external review meeting. Spending is anticipated to be about 10-15 percent less than planned by the end of FY1999.

The cost variance for the ARDR KTI was 58.8 percent. Spending rose slightly relative to the previous period and the cumulative percentage variance increased. Arrival of the draft proposed EPA Standard and start of new tasking should help decrease underspending during the coming periods. Although new tasking should reduce the cumulative variance in future periods, this KTI is expected to be significantly underspent at the end of this FY.-

The cost variance for the USFIC KTI was 4.3 percent. Spending increased from the previous per;od, and the cumulative percentage variance decreased. Reduction in cumulative dollar variance from period 8 is a result of payment of significant travel and consultant costs. The cumulative variance

($38 K) is comparable to the existing commitment for the USFIC KTI ($35 K). It is possible that the variance may become negative as costs for field work are posted.

The cost variance for the RT KTI was 18.7 percent, a significant decrease in the cumulative variance from the previous period in both percent and dollars. Anticipated invoices from ongoing and planned work by consultants are expected to continue to reduce the variance in the coming periods.

Additional staffing and field activities to collect colloids at Rainier Mesa are also anticipated to reduce the variance. Total spending may be on the order of 5 percent less than the spending plan for FY1999.

The cost variance for the TWRS project was 23.0 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 I 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 -3.0 percent, a slight decrease in the cumulative variance from the previous period. This overspending resulted from concentrated efforts during the first six periods of FY1999 to prepare the draft and final SER and to assist NRC staff with TMI-2 ISFSI Materials License No. SNM-2508. Approximately 99.9 percent of the FY1999 tasking within the TMI-2 ISFSI project was completed during periods 1-8, spending about 99.4 percent of the i

FY1999 allocation. Thus, the FY1999 total expenditures are within the FY1999 allocation.

19

~

The cost variance for the DTS project was 12.8 percent. Spendin;; declined significantly during this period due to temporary assignment of staff to other activities, thus increasing the cumulative variance. Expenditures are expected to remain close to the augmented FY1999 allocation as a result of developing a draft SER through use of CNWRA and SwRI staffs together with subcontractors.

The FY1999 total expenditures are expected to converge to the FY1999 allocation.

The cost variance for the CISF project was 23.8 percent. Expenditures for the next few periods are expected to be about 50 percent more than those of this period to review the HI-STAR /HI-STORM cask system topical report, develop the computer code RISKIND, and prepare the final AR. The FY1999 total expenditures are expected to converge to the FY1999 allocation.

The cost variance for the PFSF project was -4.0 percent. Expenditures during the next few periods will be about $40,000, so the cost overrun will continue as staff review the site characterization reports, prepare the draft SER, review the PFS seismic exemption request, and revise the NRC draft positions on five Group I contentions. At the instmetion of the NRC, the PFSF Operations Plan will be revised during the next period to increase the funding for FY1999 by about $100,000 to accommodate the increased scope of work.

The cost variance for the SRSASF was 73.3 percent, a slight decrease in percentage terms from the last period. Spending increased from last period. The variance is anticipated to decrease due to the budget reduction in the project and increased spending on report preparation.

20 l

w:

1..

Table 1. CNWRA Core Staff--Current Profile and Hiring Plan * (Period 9) i 1

Peeltlens Open Essertise&.sserience Current No.

Profess 6onal Staff FYl#99

{

ADMINIS11tATION 4'

H GARCIA. W. PATRICK. J RUSSELL B S AGAR I

CHEMICAL PROCESSING 2

VJAIN. D.DARUWAMA ENONG/ PHYS CHEM CODE ANA!.YSIS/DEVELDPMENT 7

R JANETZKE. R MARTIN 1

DATA MANAGEMENT / PROCESSING.

I P.MALDONADO INCLUDING FINANCIAL DOSFJRISIUHAZARD ANALYSIS 0

t EUiCTROCHEMISTRY I-G CR AGNOLINO ENGINEERING 2

R.OIEN, G.OfDEGBU l

l GEOLOGYAGE01IGCAL ENGNG ENVIRONMENTAL SCIENCES I

P l.aPIANTE GEOCHEMISTRY 7

P.BERTL'ITI, LBROWNING. W. MURPHY, R.PABA1AN, i

E PEARCY. J PRIKRYL D TURNER GEOHYDROI.OGY/HYDROGEOLOGY 5

D.FARRELL R.FEDORS R. GREEN, M. HILL J WINTERIE GEOIDGY 3

P 1AFEMIN A. LMcKAGUE, M MIKIAS HYDROIDGIC TR ANSPORT 3

A ARMSTRONG. D.HUGHSON 5 PAINTER I

INIURMATION MANAGLMENT 0

1 SYSTEMS MATERIALSCIENCES 5

S.BROSSIA, D.DUNN, O.MOGHISSI, Y-M. PAN, I

N SRIDHAR MECHANICAL.

1 D.GUTE INCLUDING DESIGN & FABRICAT10N MINING ENGINEERING 1

S-M HSIUNG I

NUCIIAR ENGINEERING 0

I OPER AT10N AL HEALTH PHYSICS 1

1 WEIDY I

L.

PERIORMANCE ASSESSMENT 3

S.MOHANTY, O. PENS ADO-RODRIGUEZ, 2

G %TTTMEYER OUAtJrY ASSURANCE I

B MABRITO RADIOISOTOPE GEOCHEMISiltY I

D PICKETT ROCK MECHANICS, 2

A.CHOWDHURY. A.GHOSH INC11!DINGCIVit/S11 TOC ENGNG SOURrE-TERM / SPENT FUEL DEGRAD 0

i STRUCTURAL GEOLDGY/

3 D.FERRILL D. SIMS, J.STAMATAKOS SEISMO TECTONICS SYSTEMS ENGINEERING 1

P M ACKIN VOLEANOLDGY/lGNEOUS 2

C.CONNOR, B. HILL PROCESSES TDTAL

$2 12

• See staffmg plan for details i

l l

21

r^

Table 2. CNWRA Core Staff-Summary by Area of Concentration (Period 9)

Positions Area of Concentration Actual Planned Open ADMINISTRATION, QUALITY ASSURANCE, AND 6

7 1

INFORMATION M ANAGEMENT GEOCHEMISTRY 8

9 i

HYDROLOGY / CLIMATOLOGY 8

9 1

MATERIAL SCIENCES 6

8 2

MECHANICAL, CHEMICAL, NUCLEAR, AND SYSTEMS 4

5 1

ENGINEERING PERFORMANCE ASSESSMENT 6

11 5

ROCK MECHANICS, MINING, AND GEOLOGICAL 5

6 0

ENGINEERING STRUCTUR AL GEOLOGY, TECTONICS AND VOLCANISM 9

9 1

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Table 5. Financial Status (Period 9)

Funds Funds Funds Project Names Authorised Costed to Date Uncested Commitments COPS 3.476.342 2.689.529 786.813 3.232 1A -

1.345.062 1.136.514 208.548 119.739 SDS 1.825.699 1.487.413 338.286 42.252 ENFE 1.781.331 1.324.650 456.680 167.643 CLST I,704.8 I 8 1.458.801 246.717 11.709 7EF' l.322.606 1.053.962 268.645 10.724 RDTME 1.319.682 951.083 368.599 61.691 L

TSPAl 3.577.966 2.615.600 962.366 48.469 ARDR 697.208 316.060 381.148 4.819 USFIC 2.288.030 1.819.602 468.428 35.325 RT 1.369.634 940.086 429.548 87.200 l

DWM Costs 20.708.378 15.792.60i 4.915.777 l

DWM Award Fee 1.1 %.006 493.569 702.437 DWM Base Fee 828,335 615.920 212.415 suFAL DWM 22.732.719 16.902.091 5.830,629 592.804 l

TWRS Costs 1.583.378 1,304.101 279.277 3.519 TWRS Award Fee 93.654 46.214 47.440 TWRS Base Fee 63.335 53.002 10.333 sul AL'IWRS 1.740.367 1.403.317 337.050 3.519 TMI-2 ISFSI SAR Costs 282.197 281.751 447 1.341 l-TMI-2 ISFSI SAR Award Fee 15.223 7.711 7.512 TMI-2 ISFSI Base Fee 11.288 11.022 266 TOTAL TMI-2 ISFSI S AR 308.708 300.484 8.225 1.341 DTS Costs 309.952 293.131 16.822 1.155 DTS Award Fee

- 19.480 7.924 11.556 1

DTS Base Fee 12.398 11.664 734 j

TOTAL DTS 341.830 312.718 29.112 1.155 l

CISP Costs 409.053 328.232 80.821 1.341 CISF Award Fee -

24.338 12.848 l 1.490 l-CISP Base Fee 16,362 13.190 3.172 m ALCISF 449.753

' 354.270 95.483 1,341 PFSF Costs -

275.068 250.309 24,759 18.463 PFSF Award Fee 16.185 6.827 9.358 PFSF Base Fee i1.003 10.171 832

'IT)TAL PFSF 302.255 267.307 34.948 18.463 SRSASF Costs 113.185 87.053 26.132 0

SRSASF Award Fee 7.110 3.992 3.118 SRSASF Base Fee 4.527 3.723 804 Tu1 AL SRSASF 124.823 94.769 30.054 0

Grand Total 26.000.456 19.634.955 6,365.500 618.623 Note: All authorized funds have been allocated through modification #127. Funds costed to date for each award fee program represent the award fee for FY1998. Funds uncosted for each award fee program represent the award fee reserved from the last authorizations based on the Operations Plans for FY1999.

I 25 t

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APPENDIX Planned and Actual Costs, and Cost Variances Period 9-FY1999 l

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