ML20197G649

CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,981024-1120

ML20197G649
Person / Time
Site:	Three Mile Island
Issue date:	12/04/1998
From:	CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES
To:	NRC
Shared Package
ML20197G642	List: ML20197G638 ML20197G644 ML20197G649
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-99-2, NUDOCS 9812090174
Download: ML20197G649 (38)

Text

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S CNWRA PROGRAM MANAGER'S PERIODIC REPORT ON ACTIVITIES OF THE CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES l

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l l For the Fiscal Reporting Period October 24 - November 20,1998 l

PMPR No. 99-2 1

l December 4,1998 i

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9812090174 981207 S5 em eg11 L - . -

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TABLE OF CONTENTS Section F ge TABLES..........................................................................iv AB B REVIATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v EXECUTIVE

SUMMARY

-PERIOD 2 . . . . . . . . . . . . . . . . . . . . . . . .; . . . . . . . . . . . . . . . . . . . . . . . . . xi 1

TECHNICAL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . I 1.1 CNWRA Operations (COPS) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 1.2 Igneous Activity (IA) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 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 1.6 Thermal Effects on Flow (TEF) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 1.7. Repository Design and Thermal-Mechanical Effects (RDTME) . . . . . . . . . . . . . . . . . 7 8.8 Total System Performance Assessment and Integration (TSPAI) . . . . . . . . . . . . . . . . . 8 1.9 Activities Related to Development of the NRC High-Level Waste Regulations ( ARDR) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 1.10 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC) . . . . . . . . . . . 9 1.11 Radionuclide Transport (RT) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 1.12 Tank Waste Remediation Systems (TWRS) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 1.13 Three Mile Island Unit 2 Independent Spent Fuel Storage Installation (TMI-2 ISFSI) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 1.14 Dry Transfer System (DTS) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 1.15 Centralized Interim Storage Facility (CISF) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 1.16 Private Fuel Storage Facility (PFSF) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 1.17 Savannah River Site Aluminum-Based Spent Fuel (SRSASF) . . . . . . . . . . . . . . . . . . 13

( 2 MANAGEMENT ISSUES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 3

MAJOR PROBLEMS ........................................................ 14 4

SUMMARY

OF SCHEDULE CHANGES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 5

SUMMARY

OF FINANCIAL STATUS . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . 14 APPENDIX-Planned and Actual Costs, and Cost Variances Period 2-FY1999 iii

e TABLES -

Table Page 1 CNWRA Core Staff-Current Profile and Hiring Plan * (Period 2) . . . . . . . . . . . . . . . . . . . . 17 2 Summary of Schedule Changes (Period 2) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 3 Deliverables (Period 2) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 4 Financial Status (Period 2) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 5 Private Fuel Storage Facility License Fe Cost Recovery Status (Period 2) . . . . . . . . . . . . . . 21 iv

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ABBREVIATIONS i ID One-Dimensional CDS Compliance Deterrmnation Strztegy 2D Two-Dimensional CDTS Commission Decision Tracking System  !

3D Hrce-Dimensional CEB Center for Environmental Biotecimology AA Atomic Absorption CEC Commission of the European  :

AAI Average AnnualInfiltration Communities  !

ACD Advanced Conceptaal Design CFD Computauonal Fluid Dynamics  ;

ACF Alumina (in excess of alkali feldspar), CFR Code of Federal Regulation Calcium Oxide. Ferromagnesian Oxide CIAC Computer incident Advisory Capability  !

ACNW Advisory Committee on Nuclear Waste CISF Centralized Interim Storage Facility i ACRS Advanced Computer Review System CLST Container Life and Source Term  :

ADAMS Agencywide Documents Access and CM Configuration Management Management System CNWRA Center for Nuclear Waste Regulatory AECL Atomic Energy of Canada Limited Analyses  ;

AES Atomic Emission Spectrometry CNWRA OPS Operations Plan for the Repository AGU American Geophysical Union Program l Al Administrative item COI Conflict ofInterest ALTS Apache leap Test Site COPS CNWRA Operations AML Areal Mass leading CPP Cyclic Potentiodynamic Polarization ANS American Nuclear Society rQAM CNWRA Quality Assurance Manual ANSI American National Standards Institute CRG Center Review Group AO Annotated Outline CRM Contosion Allowance Material AP Administrative Procedure CRWMS Civilian Radioactive Waste APB Acid-Producing Bacteria Management System AR Assessment Report CSCS Constrained Stochastic Climate ARDR Activities Related to Development of Simulator the NRC High-level Waste Regulations CSH Calcium Silicate Hydrate ASCE American Society of Civil Engineers CSPE Corrosion Science and Process ASCII American Standard Code for Engineering information Interchange DAS Data Acquisition System ASLB Atomic Safety and Licensing Board DBE Design Basis Event ASME American Society of Mechanical DC Division of Contracts Engmeets DCAA Defense Contract Audit Agency ASBt American Society for Testing and DCB Double Cantilever Beam Materials DCF Dose Conversion Factor ASU Arizona State University DCM Dual Continuum Model ATDTS Automated Technical Data Tracking D&D Decommissioning and Decontamination System DECOVALEX Development of Coupled Models and BEG Bureau of Economic Geology neir Validation Against Experiments BFD Basis for Design in Nuclear Waste Isolation l

BM 3are Mountain DEIS Draft Environmental Impact Statement BMF Bare Mountain Fault DEM Digital Elevation Model BNFL British Nuclear Fuels Limited DF Dilution Factor ,

BIP Branch Technical Position DFCSS Division of Fuel Cycle Safety and l

! CAI Color Alteration Index Safeguards CAM Corrosion Resist Material DIE Determination ofImportance  ;

CAR Corrective Action Request Evaluation CCDF Complementary Cumulative DIMNS Division ofIndustrial and Medical Distribution Function Nuclear Safety l CCL Commitment Control leg DKM Dual Permeability Model  !

CCM Constant Capacitance Model DLG Digital Line Graph l CD-R CDROM Recordable DLM Diffuse Layer Model l CDF Cumulative Distribution Function DNAG Decade of Nonh American Geology l CDM Compliance Determination Method DNFSB Defense Nuclear Facilities Safety Board 4

CDOCS Consolidated document Management DOE U.S. Department of Energy

System DOE-DP DOE Defense Program CDROM Compact Disk Read Only Memory e

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l ABBREVIATIONS (cont'd)

DOE-RU U.S. Department of Energy Regulatory GET General Employee Training l GFM Geological Framework Model Unit Division of Regulatory Applications GliGC GeoHydrology and Geochemistry DRA GIA Generalizedimportance Analysis DST Dnft Scale Test Digital Terrain Elevation Data GIS Geographic Information System DTED DTS Dry Transfer System GILP Geology and Geophysics Division of Waste Management GMS Goundwater Modeling System DWM Engineered Bamer System GPS Global Positioning System EBS Engineered Barrier System GROA Geologic Repository Operations Area EBSER Expenmental Research GS Geologic Setting EBSPAC Engineered Barner System GSA Geologic Society of America GTFE Great Tolbachik Fissure Eruption Performance AssessmentCode ECM Equivalent Continuum Model GUI Graphics User Interface Office of the Executive Director for GWS! Groundwater System !ntegration EDO '

Operations GW'IT Groundwater Travel Time EDX Energy-Dispersive X-Ray Spec.roscopy llE Hydrogen Embrittlement EIS Environmental Impact Statement ilLUR High-level Waste and Uranium EM Element Manager Recovery Projects Branch EMPA Elec.ron MicroProbe Analysis HLW High-Ixvel Waste ENE East-Northeast HRTEM High-Resolution Transmission Electron ENFE Evolution of the Near-Field Microscopy Environment IA Igneous Activity ENGB Engineering and Geosciences Branch IBM International Business Machines EnPA Energy Policy Act of 1992 ICP Inductively Coupled Plasma ENS European Nuclear Society ICPP Idaho Chemical Processing Plant EPA U.S. Environmental Protection Agency IDLH 1mmediately Dangerous to Life and EPR Electrochemical Potentiokinetic Health Reactivation IHLRWMC International liigh-Level Radioactive EPRI Electric Power Research Institute Waste Management Conference and EQA ExternalQuality Assurance Exposition EROS Earth Resource Observation System IM Intermediate Milestone ESF Exploratory Studies Facility IME Industrial Mobilization Exemption ESP Environmental Simulation Program IMS Information Management Systems EW East-West INEEL Idaho National Engineering and EXAFS Extended X-Ray Absorption Fine Environmental Laboratory Structure INETER Instituto Nicaraguense de Estudios FAC Favorable Condition TERritonales FCRG Format and Content Regulatory Guide INTRAVAL Intemational Code Validation FDSilA Fault Displacement and Seismic Ilazard I/O Input / Output Analysis IPA Iterative Perforrr.ance Assessment FEHM Finite Element Ileat and Mass Transfer IR&D Internal Research & Development FEM Finite Element Method IRIS Interim Records Information System FEP Features Events, and Processes IRM Office of Information Resources FFRDC Federally Funded Research and Management Development Center IRSR Issue Resolution Status Report FFT Fast Fourier Transform ISA initial Safety Analysis l'IE Full-Time Equivalent ISFSI Independent Spent Fuel Storage l'IP File Transfer Protocol Installation FY Fiscal Year ISM Integrated Site Model FYTD Fiscal Year-to-Date IVM Interactive Volume Modeling GDF Ghost Dance Fault IWPE Integrated Waste Package Experiments GEM General Electrochemical Migration JC Job Code GEOTRAP Geologic Transport of RAdionuclide4 JPL Jet Propulsion Laboratory Predictions JRC Joint Roughness Coefficient GERT General Employee Radiological KTI Key TechnicalIssue Training KTU Key Technical Uncertainty vi

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l ABBREVIATIONS (cont'd)

LA License Application NSRRC Nuclear Safety Research Review LAAO License Application Annotated Outline Committee LAN local Area Network NTS Nevada Test Site LANL Los Alamos National Laboratory NUREG NRC Technical Rvort besignation LARP License Application Review Plan NWPA Nuclear Waste Policy Act, as amended LAW Low-Activity Waste {

NWIRB Nuclear Waste Technical Review Board 1 LBNL Lawrence Berkeley National Laboratory OBES Office of Basic Energy Sciences l LBT Large Block Test OCRWM '

Office of Civilian Radioactive Waste LHS Latin Hypercube Sampling Management LITC lockheed Information Technology OGC Office of General Counsel Company OITS Open-Item Tracking System '

LLNL Lawrence Livermore National OMB Office of Management and Budget Laboratory j l ORR Operations Readiness Review j LLW Low-Level Waste ORS Overall Review Strategy '

LMAES lockheed Martin Advanced OWFN One White Flint North Environmental Systems PA Performance Assessment LSS Licensing Support System PAAG Performance Assessment Advisory LSSPP Licensing Suppon System Pilot Project Group i LSSTB Licensing Support System Test Bed PAC Potentially Adverse Condition LWR Light Water Reactor PAHT Performance Assessment and I M Molar Hydrologic Transport {

Ma Million Years Ago PASP Performance Assessment Strategic Plan l MAI Mean AnnualInfiltration PC Personal Computer '

MC Monte Carlo PC/TCP Personal Computer / Transmission f METRA Mass and Energy Transport Control Protocol MGDS Mined Geologic Disposal System PDF Probabit;ty Distribution Function I MH Mechanical-Hydrological PDR Public Document Room MIC Microbially influenced Corrosion PEL j

Permissible Exposure Limit MINC Multiple Interacting Continua PEM Program Element Manager MIT Massachusetts Institute cf Technology PER Prelicensing Evaluation Repon MM Major Milestone PEST Parameter Estimation MO Management and Operations PFD Probabilistic Fault Displacement MOU Memorandum of Understanding PFDHA Probabilistic Fault Displacement MPC Multi-Purpose Canister Hazard MRS Monitored Retrievable Storage PFS Private Fuel Storage MSS MultiSpectral Scanner PFSF Private Fuel Storage Facility MTU Metric Ton of Uranium PHA Preliminary Hazard Analysis NAS National Academy of Sciences PI Principal Investigator NAWG Na' ural Analogue Working Group PMDA Program Management Policy NCR Nonconformance Report Development and Analysis Staff NEA Nuclear Energy Agency PMPR Program Manager's Periodic Report NEl Nuclear Energy Institute PMT Photo-Multiplier Tube NFS Network File Server PNNL Pacific Northwest National Laboratory NIOSH National Institutes of Safety and Health PO Project Officer NIR Near-Infrared PPA Proposed Program Approach NIST National Institute of Standards and PPE Prepassivated Platinum Eletrode Technology PP.A Probabilistic Risk Assessment NMSS Office of Nuclear Material Safety and PRT Peer Review Team Safeguards PSAG Probabilistic System Assessment Group NNE North-Northeast PSHA Probabilistic Seismic Hazard Analyses NNW North-Northwest IrIFE Polytetrafluoroethylene NOAA National Oceanographic and PTn Paintbrush Nonwelded Tuff Atmospheric Administration PVHA Probabilistic Volcanic Hazards NRC Nuclear Regulatory Commission Assessment NS North-South PVHVIEW Probability of Volcanic Hazards VIEW i Yll i ..

ABBREVIATIONS (cont'd) - .

Parallel Virtual Machine SNF Spent Nuclear Fuel PVM PWR Pressurized Water Reactor SNL Sandia National Laboratories Quality Assurance SOTEC Source Term Code QA QAP Quality Assurance Procedure SOW Statement of Work Quality Requirements Application SPCR Software Problem Correction Report QRAM Matrix SRA Systematic Regulatory Analysis Request for AdditionalInformation SRB Sulfate-Reducing Bacteria RAI Regional AquiferSystem SRBS Shafts, Ramps. Boreholes, and heir RASA Andysis Seals RDCO Repodtory Design, Construction, fRD Software Requirements Description and Oprations SRS Savannah River Site RDTME Repository Design and Thermal- SRSASF Savannah River Site Aluminum-Mechanical Effects Based Spent Fuel REE Rare Earth Element SS Stainless Steel REECO Reynolds Electrical and Engineering S~lT.M Scanning Transmission Electron Company, Inc. Microscopy RES Office of Nuclear Regulatory Research STP Staff Technical Position RFP Request for Proposal SUFLAT Stochastic Analyses of Unsaturated RH Relative Humidity Flow And Transport RIP Repository Integration Program SVF Springerville Volcanic Field ROC Repository Operations Criteria SwRI Southwest Research Institute RPD Regulatory Program Database SZ Saturated Zone RRT Regulatory Requirement Topic TA Technical Assistance RSRG Real Space Renormalization Group TBD To Be Determined RT Radionuclide Transport 111M nnnel Boring Machine RTS Radwaste Treatment System TCP/IP Transmission Control SAP Standards ApprovalPackage Protocol /Intemet Protocol SAR Safety Analysis Report TDEM Time-Domain Electro-Magnetic SCA Site Characterization Analysis TDI Technical Document Index SCC Substantially Complete - TDOCS Technical Document Reference Containment Database System SCCEX Sulatantially Complete TEF nermal Effects on Flow Containment Example TEM Transmission Electron Microscopy SCE Standard Calomel Electrode DiC nermal-Hydmlogic-Chemical SCFF Southern Crater Flat Fault DIMC nermal-Hydrologic-SCM Surface Complexation Models Mechanical-Chemical SCP Site Characterization Plan T-L Transverse-lengitudinal SDMP See Decommissioning TLM Triple-Layer Model Management Plan TM nermal-Mechanical SDS Structural Deformation and Seismicity B(H nermal-Mechanical-Hydrologic SECY Secretary of the Commission, Office of Bil-2 nree Mile Island Unit 2 the (NRC) TMS ne Minerals, Metals, and Materials

! SELM Spectral Element Method Society l SEM Scanning Electron Microscopy 'IDP Technical Operating Procedure SER Safety Evaluation Report TP Technical Position SFPO Spent Fuel Project Office TPA Total-system Performance Assessment SFVF San Francisco Volcanic Field 1Pi Time Period of Regulatory Interest SGI Silicon Graphics Inc. 'IR2 DOE Seismic Topical Report No. 2 SGML Standard Generalized Markup TRG Technical Review Group Language TSAR Topical Safety Analysis Report SHE Standard Hydrogen Electrode TSPA Total System Performance SHT Single Heater Test Assessment SIP Scientific Investigation Plan TSPAl Total System Performance SKI Swedish Nuclear Power Inspectorate Asseasment and Integration S-L Short Transverse-Longitudinal TSw-Chnv Topopah Spring Welded-Calico SLAR Sidelooking Airborne Radar Hills Nonvitric viii

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TVD Total Variation Diminishing TWFN, 'Two White Flint North "lWINS Tank Waste Information Network System TWRS Tank Waste Remediation System UA University of Arizona UACll Universidad Aut6nomade Chihuahua UCLA University of California Los Angeles UDEC Universal Distinct Element Code UK United Kingdom UNM University of New Mexico UR Uranium Recovery i U.S. United States USDA U.S. Department of Agriculture USGS l U.S. Geologic Survey UTM UniversalTransverse Mercator USFIC Unsaturated and Saturated Flow Under Isothermal Conditions UZ Unsaturated Zone VA Viability Assessment VCS Version Control System VF Vitrification Facility VSIP Vertical Slice Implementation Plan WAN Wide Area Network WAPDEG Waste Package Degradation WBS Work Breakdown Structure WCIS Waste Containment and Isolation Strategy WFO Work for Others I WGB Western Great Basin WIPP Waste Isolation Pilot Plant l WMB Waste Management Branch WNYNSC Western New York Nuclear Service Center WOL Wedge-Opening leading WP Waste Package WSE1 Waste Systems Engineering and Integration WSRC Westinghouse Savannah River Company WSS Waste Solidification Systems WI30 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 YMSCO Yucca Mountain Site Characterization Office YMR Yucca Mountain Region YTD Year-to-Date i

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EXECUTIVE

SUMMARY

-PERIOD 2 In the Division of Waste Management (DWM) Job Code (JC), the Center for Nuclear Waste Regulatory Analyses (CNWRA) delivered a briefing on the CNWRA Five-Year Strategic Plan, the FY1999 CNWRA Operations Plans for the Repository Program, attended a Nuclear Regulatory Commission (NRC) Center Review Group meeting, and presented the FY1998 CNWRA Annual Program Review. The staff continued work on various deliverables and prepared for and engaged in several meetings, including program review meetings at NRC, the 1999 Materials Research Society Sympotium, and the American Geophysical Union Fall A1.nual Conference. The staff also prepared articles / papers for acceptance in peer-reviewed joumals together with presentations at meetings mentioned previously.

The DWM JC year-to<iate (YTD) cost variance was 7.5 percent. Spending rose from the previous period.

In the Tank Waste Remediation System (TWRS) JC, the staff continued preparation of various reports and incorporation of NRC comments on others. The YTD cost variance was 17.2 percent. Spending declined over last period because existing commitments from FY1998 have been paid.

In the Three Mile Island Unit 2 (TMI-2) Independent Spent Fuel Storage Installation (ISFSI) JC, the staff continued preparation of the draft safety evaluation report (SER), including evaluation of the U.S. Department of Energy response to the NRC second round request for additional information. The YTD cost variance for the TMI-2 ISFSI was -31.8 percent resulting from continued efforts preparing the draft SER during the last two periods.

In the Dry Transfer System (DTS) JC, the staff visited the Idaho National Engineering and Environmental Laboratory (INEEL) to observe DTS prototype testing and began preparation of the draft SER.The YTD cost variance was -73.0 percent. Spending rose significantly over last period as the result of the INEEL visit and related activities.

In the Centralized Interim Storage Facility (CISF) JC, staff submitted a draft assessment report (AR). The YTD cost variance for the CISF was - 10.9 percent. This overspending resulted from concentrated efforts in the last two periods to prepare the draft AR.

In the Private Fuel Storage Facility (PFSF) JC, the staff prepared draft position papers on the first group of PFSF contentions. The YTD cost variance was 4.5 percent, consistent with spending related to preparation of these papers.

In the Savannah River Site Aluminum-Based Spent Fuel JC, the staff delivered the FY1999 Operations Plan for Technical Assistance on Department of Energy Aluminum Based Spent Nuclear Fuels Disposition together with a letter report conceming the criticality evaluation of direct codisposal and melt-dilute Al-clad fuels. The YTD cost variance was 52.6 percent. Spending marginally rose over the previous period due to continued efforts to complete these deliverables.

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

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CNWRA PROGRAM MANAGER'S PERIODIC REPORT l ON ACTIVITIES OF THE l CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES l 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 D1035,J5164,J5186,J5206,J5226,J5210  :

NRC CNWRA PROGRAM MANAGER: John J. Linehan,(301) 415-7780 NRC CNWRA DEPUTY PROGRAM MANAGER: Deborah A. DeMarco,(301) 415-7804 CNWRA PRESIDENT: Wesley C. Patrick,(210) 522-5158 1

1 ESTIMATED BUDGET: $87,611,477 '

PERIOD OF PERFORMANCE: 09/27/97-09/27/02 l l

PERIOD OF THIS REPORT: 10/24/98-11/20/98 -1 1 TECHNICAL I I

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) attending an NRC CRG meeting concerning the CNWRA  ;

semiannual performance evaluation, (ii) presenting a briefing on the CNWRA Five-Year Strategic Plan at the 1998 CNWRA Annual Program Review and participating in a NRC/CNWRA Management meeting subsequent to this review;(iii) submitting the FY 1999 j CNWRA OPS for the Repository Program; (iv) providing revised spending estimates for FY1998 and reconciling carryover monies for the next FY; (v) further addressing COI-related issues among the NRC, SwRI, and CNWRA management staffs; and l (vi) participating in weekly HLW Management Board meetings.

l Status of CNWRA s:affing is indicated in table 1, consistent with the revised staffing plan submitted as part of the CNWRA Annual Program Review and subsequent meetings with l NRC management. During period 2, intensive recruitment efforts and interviews continued for the approved open positions. Three limited-term positions have been filled. Drs. Yi Ming Pan, a material scientist, and Lauren Browning, a geochemist, along with Ms. Melissa Hill, a hydrologist, will join the staff in period 4. Also joining the CNWRA in that period as permanent core staff will be Dr. Oswaldo Pensado, a material scientist, and Mr. Paul Bertetti, a geochemist.

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1 Computer system support activities encompassed (i) continuing the use of consultant support to assist the recently-hired UNIX administrator with installation of SUN

• I Microsystems and Silicon Graphics hardware and software associated with the GIS and IMS computing facilities; (ii) pursuing the installation and upgrade of standardized desktop computer systems:(iii) participating, as requested, in the monthly NRC/CNWRA Computer Coordination meeting; and (iv) maintaining LAN operations. i 1

QA activities focused on (i) completing revision of QAP-016, Procurement Control, to correctly describe CNWRA procurement practices in response to one of the QA audit CARS; (ii) completing the update of the FY1999 QRAM forms; (iii) conducting surveillances, issuing nonconformance reports as required, and working with cognizant staff in response to these reports; (iv) leading the configuration control effort of the CNWRA scientific and engineering software determined ready for release; (v) controlling issued documents and maintaining QA records; (vi) preventing organizational COls by reviewing l l

SwRI RFPs; (vii) performing QA verification checks on each CNWRA deliverable; and (viii) evaluating potential changes to the CNWRA Quality Assurance Manual, which may l be required as flow-down QAPs are revised. l l

In the next period, the CNWRA staff expects to (i) complete reconciliation of revised i

spending estimates for FY1998 and carryover monies for FY1999; (ii) agree on scope and timing for modifications to the FY1999 CNWRA OPS for the Repositary Program; (iii) pursue aggressively the hiring for open core staff positions; (iv) continue installation of computer hardware and software for GIS and IMS computing facilities, as well as confirm the replacement for the CDOCS software; and (v) provide CNWRA LAN operation and maintenance support.

In addition, the staff will(i) complete the close out of the second CAR from the FY1998 CNWRA QA Audit, (ii) proceed with scheduled QA surveillances, (iii) perform QA indoctrinations for new CNWRA staff and consultants, (iv) input internal documentation and record copies of delivered documents into QA records, (v) review SwRI RFPs for potential COI, (vi) perform QA verification checks on each CNWRA outgoing deliverable, and (vii) obtain signatures of ems, technical director, and QA director on completed Q. RAM fcrms that detail QA requirements for technical tasks in the FY1999 CNWRA OPS.

1.2 Igneous Activity (IA)

GPS survey studies by Wernicke and others suggest that the rate of crustal extension in the YMR is an order of magnitude higher than indicated by previous studies. Wernicke and others conclude that earthquake and volcano recurrence rates thus may be underestimated by an order of magnitude. A technical comment on this study by Connor and others was published this month in the journal Science. Connor and others contend that three alternative interpretations are possible for these strain-rate data, none of which require an increase in earthquake or volcano recurrence rates. In addition, Connor and others conclude that if Wemicke and others' model was correct, there is a 90-98 percent likelihood that an additional volcano younger than the 0.1 Ma Lathrop Wells volcano should be present in the YMR. The absence of this young volcano greatly reduces confidence in the link between anomalously high strain-rates and volcano recurrence since the formation of Lathrop Wells volcano. Wernicke and others responded that the three alternative interpretations are plausible but speculative. They also contend that the anomalously young ages for Lathrop 2

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Wells volcano (20 ka) are plausible and thus the likelihood of having a volcano younger than Lathrop Wells in the YMR is between 80-98 percent. l l

To address uncertainties on the relationships between c:ustal strain-rates and volcano  ;

recurrence rates, staffis evaluating these relationships for a range of Quaternary volcanic l fields in western North America. In this period, staff developed an initial data set for the <

l Portrillo volcanic field, New Mexico. At least 100 basaltic volcanoes formed in the Portrillo I  !

field during the Quaternary. This activity occurred, h wever, in a tectonic setting

• characterized by relatively low rates (<1 mm/yr) of crustal extensia. Nearby areas of high l apparent crustal extension, associated with the Rio Grande Rift, lack Quaternary volcanic  !

activity. This relationship is not intuitive if crustal strain-rates dinctly affect volcano  !

recurrence rates.

Also during this period, staff prepared for and participated in the CNWRA Annual Program Review in San Antonio, Texas. Preparations also continued for presentations at the AGU Fall Annual Conference. Staff continued to work with consultants at the University of Bristol on the design of experimental apparatus for magma-repository interaction studies.

Staff also submitted one proposal for the augmented spending program.

In the next period, staff will complete review of the VA in support of a Commission paper identifying the DOE licensing vulnerabilities. Initial designs for the magma-repository interaction experiments will be completed and construction of the experimental apparatus will begin at the University of Bristol. Staff will conduct reconnaissance investigations at the Portrillo volcanic field. Staff also will prepare presentations for the AGU Fall Annual Conference in early December.

1.3 Structural Deformation and Seismicity (SDS) I The staff submitted an Al on the Input to Review of DOE Geological Framework Model 3.0 EarthVision. Staff also prepared presentations for the upcoming AGU Fall Annual Conference. These presentations include an analysis of fault-block rotations from paleomagnetic data and the evolution of crossing faults and their role in development of anisotropic flow parameters such as permeability and porosity. Staff continue to work on an EarthVision model of the stmetural framework of the Amargosa trough, identified as 3D Structural Model of Amargosa for Input to USFIC--CNWRA Report. The model will be used as input to saturated flow models by the USFIC KTI. Staff continued writing Structural Evolution of Crater Flat, Nevada-Journal Article. l Staff began to process data recently collected from the Volcanic Tablelands of eastern California. The work is part of an evaluation of alternative models of crustal strain accumulation to explain the recently acquired anomalous GPS strain rates by Wernicke et al. in a 1998 Science article. Review continued on the DOE draft probabilistic seismic and fault displacement hazard analyses report. SDS staffinitiated sensitivity studies of faulting based on recent TPA Version 3.2 code results. Staff also prepared for and participated in i the CNWRA Annual Program Review and submitted two proposals for the augmented spending program.

In the next period, staff will make four presentations at the AGU conference. Staff will (i) continue review of the DOE probabilistic seismic and fault displacement hazard analyses l report,(ii) prepare the EarthVision 3D model of the Amargosa trough,(iii) develop a paper 3

on the structural evolution of Crater Flat Nevada, and (iv) continue sensitivity studies of faulting on repository performance. Staff will also continue evaluation of geolo'gic and' geophysical data from the Volcanic Tablelands, California, and initiate preparation for the upcoming NRC/CNWRA workshop on fractures and faulting in the repository.

1.4 Evolution of the Near-Field Environment (ENFE)

Staff continued debugging, testing, and documenting the MULTIFLO code Version 1.2p.

The 3D transport capabilities of the module GEM were successfully benchmarked against an analytical solution. Implementation of the operator splitting algorithm in GEM was completed and is being tested. Staff started work on the software requirements document for MULTIFLO code Version 2.0. As part of this effort, a model for heat and moisture transport in an open drift was developed for use in METRA. This model accounts for radiative transfer from the hot WP to the drift wall. Heat and moisture losses through natural or forced ventilation are also included in the model.

Application of MULTIFLO to coupled THC processes for the proposed repository environment advanced by testing kinetic phenomena with consideration of the carbonate and silica systems. Reaction kinetics of amorphous silica precipitation with a linearly increasing thermal load were modeled under saturated no-flow conditions to facilitate benchmarking MULTIFLO nonisothermal, kinetic chemistry results with EQ3/6 modeling.

Staff began testing the EBSFILT module of the TPA Version 3.2 code together with performing sensitivity analyses related to the potential effect of cementitious materials.

Staff also completed a paper on PA sensitivity studies related to the dependence of the source term on near-field environmental conditions, which is scheduled for presentation at the 1999 Materials Researth Society Symposium, Boston, Massachusetts, November 30

-December 3,1998. Preparations also began for presentation of the sensitivity studies paper at this meeting.

Staff continued review of the LLNL near-field and altered-zone models report and the draft DOE TSPA-VA Technical Basis document, particularly chapter 4, Near-Field Geochemical Environment. Initial planning and work assignments began in preparation for writing revision 2 of the ENFE IRSR.

Staff participated in the TEF KTI program review at NRC on October 29,1998, and delivered a presentation focusing on coupled THC effects on flow in the proposed repository. Staff also participated in the CNWRA Annual Program Review November 17

-19,1998,in San Antonio, Texas.

Aggressive efforts were undertaken to promote activities by several consultants and SwRI staff on a variety of subjects in support of the ENFE KTI, including evaluation of potential effects of microbial activity, aqueous actinide chemistry, solubilities of radioelements, effects of alteration of engineered materials on the near-field chemical environment, and properties of altered tuff materials.

In the next period, staff will continue review of the draft DOE TSPA-VA Technical Basis document. Debugging and benchmarking of the MULTIFLO code will continue.Near-field radioelement solubility modeling and aqueous actinide chemistry studies will advance. Staff 4

l: .

will participate in the 1999 Materials Research Society Symposium, co-chair sessions on cementitious materials and natural analogs, and review submitted manuscripts.

1.5 Container Life and Source Term (CLST) l 1 1

Staff initiated the review of chapters 5 and 6 of the TSPA-VA Technical Basis document. I Concurrent with review of the DOE reports, staff conducted sensitivity analyses using the TPA Version 3.2 code. Thus far, the effects of various container related parameters, such as critical relative humidity, repassivation potentials, and passive current density on system performance as well as container life, have been examined. These results will be documented in a report that will be compiled with the NRC staff analyses.

Electrochemical corrosion testing, performed to confirm the applicability of repassivation  ;

and corrosion potentials as predictive parameters for the long-term, localized corrosion of Alloy 825 in chloride-containing solutions at 95 *C, continued. The specimens were  !

removed from the test cells, examined for signs oflocalized corrosion, and weighed. After  !

l inspection, all long-term tests were restarted. The mechanism of repassivation was  !

l examined by conducting simulated single-pit experiments on pure iron, nickel, chromium, '

l and type 308 SS. The results were incorporated in a conference paper presented at the

) Critical Factors in Localized Corrosion symposium at the Electrochemical Society fall ,

meeting on November 2-6,1998. Plans are to continue the mechanistic studies and extend them to more complex alloys, such as Alloy C-22. I i

l l Stress corrosion cracking tests were initiated on Alloy C-22. For comparison, tests are I

conducted simultaneously on type 316L SS because the susceptibility of this alloy to stress

! corrosion cracking in hot chloride solutions is well established. Two specimens of each l material were fatigue precracked, wedge loaded, and exposed to the aqueous environment.

Alloy C-22 tests are being conducted using an initial stress intensity of 33 MPa m'8, while  !

the type 316L SS specimens are tested at an initial stress intensity of 25 MPa m8 Specimens of each material are 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. For further comparison, one specimen of each material is immersed in j 40 percent MgCl 2at 110 *C, a more aggressive environment in which stress corrosion cracking of Alloy 825 and type 316L SS was previously studied at the CNWRA.

l Localized corrosion testing of Alloy C-22 in solutions with chloride concentrations of 0.5, 1.0, and 4.0 M continued using an autoclave system at temperatures ranging from 95 to 175 *C The purpose is to identify the range of temperatures, chloride concentrations, and potentials within which Alloy C-22 could be susceptible to localized corrosion under repository conditions. The results thus far indicate that significant localized corrosion can occur even at 95 *C at chloride concentrations equal to or greater than 1 M and at relatively I low repassivation potentials. In addition, passive current density r- asurements under

) potentiostatic control were conducted over a range of environmental conditions to predict l the long-term uniform corrosion rate of Alloy C-22. The results of these studies are being analyzed and will be presented at the 1999 Materials Research Society Symposium and in the 1999 NACE Intemational Annual Corrosion Conference as well as included in the proceedings of both conferences.

The interdependence of solution chemistry, temperature, and potential on localized corrosion of A 516 carbon steel is being investigated in simulated repository environments i

! 5 i

4 containing bicarbonate and chloride anions. The effects of pH and potential have been extensively examined and the influence on localized corrosion of preoxidation in air at-200 *C for various exposure times is currently being evaluated. The results are being analyzed and documented in a paper to be presented at the 1999 NACE Intemational Annual Corrosion Conference and included in its proceedings.

Staff also prepared for and participated in the CNWRA Annual Program Review on November 17- 19,1998,in San Antonio, Texas. A at of three mini-proposals was prepared for the augmented work in activities corresponding to glass waste form, stress corrosion cracking and HE of new container materials, and issues related to welding and weld corrosion of container materials.

The efforts to increase staffing in the Corrosion Science and Process Engineering Elerr.ent continued. Offers were made and accepted by two materials science candidater.

In the next period, long-term corrosion tests of Alloy 825 will continue, as will localized corrosion testing of A 516 carton steel and Alloys C-22 and 625, together with stress corrosion cracking tests using Alloy C-22 and type 316L SS. Activities related to sensitivity analyses, review of TSPA-VA documents, and review of alternate materials and design options will continue.

1.6 Thermal Effects on Flow (TEF) l Staff continued the preliminary modeling of the drift-scale heater test in two dimensions using the dual-continuum concept. These numerical analyses have been run in the background with minimal effort to refine the model at this time.

The second phase of the laboratory-scale boiling isotherm depression heater experiment continued during the reporting period. Dripping onto the sensors in the drift was observed at several locations, although there has been a decline in frequency. The modified and enhanced data acquisition system proved reliable providing hourly temperature measurements and drip sensor measurements every quaner hour.

Five CNWRA staff from three KTis made presentations at the TEF KTI program review at TWFN on October 29,1998. Three staff discussed the TEF KTI and two discussed interactions between the TEF KTI and the CLST and ENFE KTIs. Progr ess in the TEF KTI during FY1998 was also discussed in the review.

Mountain-scale repository analyses have been initiated. These analyses are extensions of earlier repository-scale nonisothermal analyses of perched water. The current analyses will investigate an east-west trending vertical 2D geologic section midway through the

( repository block. The analyses will be conducted using MULTIFLO with a dual-continuum conceptual model.

The investigation of capillary diversion at the drift walls has been initiated. This effort is being conducted in conjunction with the USFIC KTI.

Staffinitiated the review for the TSPA-VA Technical Basis document for TEF during this reporting period.

l l

A workshop on dripping has been planned for December 21-22,1998, at the CNWRA.

Staff (NRC and CNWRA) from several KTIs expressed interest in attending. Several consultants have been invited to attend this workshop. The first day of the workshop will be video-conferenced with TWFN if there is interest.

Several candidates for providing consulting services to the TEF KTI are being identified and evaluated. These individuals will provide additional resources to the KTI if their expertise and availability are appropriate.

I One TEF KTI staff gave a presentation at the CNWRA Annual Program Review on '

November 17-19,1998, in San Antonio, Texas.

In the next period, TEF KTI staff plans to (i) continue the second phase of the boiling isotherm penetration laboratory-scale experiment, (ii) analyze results from the first phase ,

of the laboratory-scale heater test, (iii) test the MULTIFLO-DCM numerical code in modeling the DOE DST, (iv) evaluate the conceptual model of refluxing, (v) conduct an i

NRC/CNWRA workshop on dripping, and (vi) continue review of the TSPA-VA Technical '

Basis document for TEF.

1.7 Repository Design and Thermal-Mechanical Effects (RDTME)

The staff continued the UDEC analyses to predict the size and extent of rockfall under I seismic loads in the repository thermal environment. This simulation is expected to provide a technical basis for determining the magnitude of the dynamic impact load on the WPs resulting from rockfall. Also, the results will be used as input to the SEISMO module in the TPA Version 3.2 code for the assessrmnt of rockfall effects on WP integrity. The solution to the problem identified in UDEC temperature calculations during period I has been provided by the vendor and analysis has resumed.

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

This study emphasizes (i) rock mass behavior beyond the preclosure period and (ii) effects of thermal load on permeability changes in the surrounding rock mass. Several cases regarding the effect of lining stiffness on rock mass behavior were analyzed.

The investigation of drift-scale rock mass behavior and its effect on concrete lining stability using UDEC progressed during this reporting period. Staff continued the literature review on concrete performance at high temperature.The review will provide valuable information to assess the DOE design of the concrete liner for use at high temperature.

l A finite element mesh for ABAQUS was constructed for investigating the thermal stress

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

One RDTME KTI staff gave a presentation at the CNWRA Annual Program Review on November 17-19,1998,in San Antonio, Texas.

In the next period, RDTME KTI staff plans to (i) review the literature collected on concrete performance at high temperature, (ii) investigate rock mass behavior under heated 7

conditions on both repository and drift scales with an emphasis on long-term degradation of rock mass material properties and strengths, (iii) conduct rockfall simulations, (iv) use' the ABAQUS code to model WPs, (iv) participate in DOE workshop on Ground Control, and (v) conduct reactive activities including review of design documents.

1.8 Total System Performance Assessment and Integration (TSPAI)

The TPA Version 3.2 code was made available to all KTI team members so they can become familiar with the use of the code prior to conducting sensitivity analyses evaluating the TSPA-VA. A study was undertaken using the TPA Version 3.2 code to determine the minimum number of realizations required to achieve stability in the peak of the mean dose versus time curve. Because computer resources for conducting sensitivity analyses are limited, optimizing the use of the TPA code is important. Data from several 1,000-vector TPA runs were made available to KTIs for analysis purposes.

NRC and CNWRA staff continued joint work on total-system level sensitivity analyses using the TPA Version 3.2 code. Initial results from step wise regression and differential analysis were provided to all KTIs for further analysis and explanation. Work continued on developing new approaches for interpreting TPA results, especially the parameter-tree method for determining the importance of individual parameter ranges and subsets of parameters to overall performance. The KTI teams may employ some of these methods in conducting sensitivity analyses of the TPA Version 3.2 code and quantitatively evaluating the TSPA-VA.

Approximately 60 replies have been received in response to the nomination letter for conducting the formal external review of the TPA Version 3.2 code. Names of nominees were compiled, ranked on the basis of number of nominations, and sent to the NRC staff for review and comments.

Progress was made in preparing for the delivery of(i) the PC version of the TPA Version 3.2 code, (ii) the Java-based post-processor for the TPA Version 3.2 code, and (iii) the PVM implementation of the TPA Version 3.2 code. Surveillance was conducted to ensure that the full suite of QA procedures was implemented in developing and testing.

Preparations continued for the documentation that will accompany the codes. Staff provided the NRC with a prerelease demonstration of the post-processor and the l'C version of the TPA Version 32 code and requested the software and hardware requirements for its installation. Delivery of these add-on products will be by the end of the first week of December.

A presentation reviewing accomplishments in the TSPAI KTI during FY1998 was made at the CNWRA Annual Program Review on November 17-19,1998,in San Antonio, Texas.

In the next period, the PA staff will focus on (i) preparing and mailing letters of invitation to participate in the review of the TPA Version 3.2 code, (ii) completing and delivering the PC and PVM versions of the TPA Version 3.2 code as well as the Java-based post-processor for the TPA Version 3.2 code, (iii) preparing and providing guidance to the KTI teams on the conduct of system-level sensitivity analyses with the TPA Version 3.2 code and on review of the TSPA-VA,(iv) contributing to the draft Commission paper on the VA, and (v) initiating work on revision 2 of the IRSR. Efforts will continue on recruiting for the PA modeler, health physicist, and risk assessment positions.

8

i:

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

Work continued on modeling and evaluating the effects of well characteristics and plume dimensions on the accuracy of estimates ofdoses from the groundwater transpon pathway, which are needed to support development of attributes of the critical group to be used in 10 CFR Part 63. The modeling approach adopted incorporates spatially variable material propenies, complex imtial and boundary conditions, and multiple pumping wells with variable pumping rates. This period, efforts focused on development of geostatistical models for generating conditional synthetic random hydraulic conductivity fields for the alluvial aquifer.

In response to issues brought forward at a recent DOE /NRC technical exchange, the investigation on issues pertaining to calculation of age-specific doses at YM continued. A large body of age-specific intake information was identified in a draft EPA report, but because the report is a draft, the original sources of data are being investigated.

Staff panicipated in the CNWRA Annual Program Review, November 17-19,1998,in San Antonio, Texas, and presented a summary of the ARDR activities for FYl998.

At the end of this period, the revisions to the previously issued repon, Information and Analyses to Support Selection of Critical Groups and Reference Biospheres for Yucca Mountain Exposure Scenarios, were submitted for CNWRA internal review of the revised sections. The revised repon will be to be issued as a NUREG/CR-a key reference document for the rulemaking effon and TSPAI activities.

In the next period, staff will complete development of flow models for the alluvial aquifers as part of the borehole dilution study. Assessment of age-specific DCFs will continue and the initial results made available to the NRC. If the EPA publishes the draft standard, staff will assist the NRC with reviewing it and preparing comments. The revised repon, Information and Analyses to Support Selection of Critical Groups and Reference Biospheres for Yucca Mountain Exposure Scenarios, will undergo CNWRA technical  !

review during the next period. Effons will begin to investigate the feasibility and options for updating the dose module in the TPA code to allow stochastic dose calculations.

1.10 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC)

Characterization continued of nonwelded vitric layers below the potential repository horizon. Flow through the nonwelded units below the repository is expected to significantly affect dose to receptors. Surface outcrops and cores from four boreholes were examined to gain a familiarity with lithologic variations of the nonwelded units in the UZ below the proposed repository horizon. Also, preliminary estimates of minimum nonwelded vitric and representative nonwelded vitric thicknesses were made for each repository subarea.

Updated tables of unit thicknesses for each subarea were prepared for future TPA sensitivity analyses using the different estimates of thicknesses.

Final revisions were completed and technical reviews began on Estimation of Infiltration in Ephemeral Channels in Solitario Canyon-Joumal Paper. Preparation continued of a manuscript on the potential hydrologic impact to YM UZ and SZ modeling that may result from the replacement of native plants by bromus grasses originating in Eurasia. A paper J titled Time Scales for Dissolution of Calcite Fracture Fillings and Implications for 9

Saturated Zone Radionuclide Transport at Yucca Mountain, Nevada, is currently in technical review and is intended for presentation at the 1999 Materials Research' Society' Symposium at Boston, Massachusetts, November 30-December 3,1998.

A new deliverable, Revised Hydrologic Parameters for TPA Code, is proposed in table 2 of this PMPR.

Technical review continued of chapters 2 (UZ flow),7 (UZ transport), and 8 (SZ flow and transport) of the draft DOE TSPA-VA Technical Basis document continued during this period.

Investigations continued on the problem of capillary diversion of deep percolation away from open drifts. This work includes analytical studies, numerical modeling of a fractured continuum in 2 and 3 dimensions with homogeneous and heterogeneous propenies, and seasitivity studies. These investigations are preliminary and results to date have tended to confinn how poorly such processes are understood. Results of the numerical modeling will be used to evaluate the DOE approach to modeling drift seepage in the TSPA-VA.

Efforts to constmct and calibrate a site-scale 3D model of the SZ continued. The GMS software was verified against a test problem as part of TOP-018 compliance. Calibration of the site-scale model will be performed with inversion routines in the PEST code using existing water table data from wells at YM.

i One USFIC KTI staff gave a presentation at the CNWRA Annual Program Review on ,

November 17-19,1998,in San Antonio, Texas.

In the next period, USFIC activities will include (i) interpretation of data from CNWRA field studies at YM, (ii) progress on alternative conceptual models for flow and transport from the potential repository to the water table,(iii) progress on approaches for modeling future infiltration, (iv) contmued development of conceptual models for seepage into drifts, (v) review of the DOE UZ model of YM,(vi) preparation of a 3D subregional site-scale flow and transport model, (vii) continued efforts toward interpreting data from C-Well hydraulic and tracer tests, and (viii) continued review of chapters 2,7, and 8 of the draft  ;

DOE TSPA-VA Technical Basis document.

1.11 Radionuclide Transport (RT)

Two manuscripts were completed for the proceedings volume of the 1999 Materials Research Society Symposium at Boston, Massachusetts, November 30-December 3,1998.

The first manuscript, Sorption Modeling for PA-Materials Research Society Manuscript, with publication title, Radionuclide Sorption at Yucca Mountain, Nevada-Demonstration of an Altemative Approach for PA, outlines an approach for developing site-specific constraints on Ko PDFs for PA abstractions and provides a discussion of spatial j distributions of calculated Ko in the vicinity of YM. The second manuscript, UZ Chemistry i at a Natural Analog Site-Materials Research Society Manuscript, with publication title, Unsaturated Zone Waters from the Nopal I Natural Analog, Chihuahua, Mexico-Implications for Radionuclide Mobility at YM, focuses on geochemical modeling and U-series interpretation of Nopal waters. Staff prepared graphics and slides for the two nral presentations. j 10 i

F l

I Sensitivity analyses were initiated with the TPA Version 3.2 code using 1,000-vector base-case mns at 10,000 and 50,000 yrs. Correlation coefficients among americium, neptunium, plutonium, thorium, and uranium sorption parameters based on detailed sorption models were used for sorption in the alluvium in the TPA Version 3.2 code. Examination of the output files for the base case indicates the code correctly implemented the correlation i

coefficients during the sampling routines. In antrast, sorption parameters in other parts of the TPA Version 3.2 code exhibit no correlation.

Installation testing of the computer software Geochemist's Workbench was conducted in preparation for placing the software under TOP-018 configurations control. The software has the capability to simulate sorption reactions using surface complexation models and it will be used in RT KTI activities related to simulation of radionuclide sorption and transport. The software uses the same thermodynamic data used in EQ3/6 geochemical calculations. In the process ofinstallation testing, it was determined that the thermodynamic data for uranium species in the EQ3 database (data 0.com.R2) at temperature >. other than 25

• C are incorrect. Staff at 11NL confirmed this determination and noted that a corrected version is available at the LLNL ftp site.

CNWRA technical and programmatic reviews were completed for a manuscript on the application of sorption modeling for PA calculations. This paper is proposed as a new deliverable in table 2 of this PMPR, Abstraction of Mechanistic Sorption Models for Performance Assessment Calculations at Yucca Mountain, Nevada. Another manuscript including an evaluation of data (published literature and unpublished CNWRA results) on ion exchange between aqueous solutions and the zeolite mineral clinoptitolite was completed. This paper is proposed as a new deliverable in table 2 of this PMPR, Experimental and Modeling Study of lon Exchange Between Aqueous Solutions and the Zeolite Mineral Clinoptitolite.

Uranium-233 sorption experiments on quartz continued,with open-to-atmosphere as well as capped vials to minimize carbon dioxide availability. The sorption step on open-to-atmosphere containers was completed. Acid / base adjustments for the capped vials were recalculated due to the limited buffering capacity of the solutions. Sample preparation for liquid scintillation analysis continued.

Staff continued to assist the NRC staffin finalizing the RT IRSR. Staff also prepared for and participated in the CNWRA Annual Program Review on November 17-19,1998, in San Antonio, Texas. They prepared mini-proposals for augmented work for FY1999.

In the next period, staff will make presentations at the 1999 Materials Research Society Symposium. CNWRA internal reviews will be completed on Abstraction of Mechanistic Sorption Models for Performance Assessment Calculations at Yucca Mountain, Nevada.

Laboratory analyses will continue, including multiple-nuneral experiments. RT staff will assist in the PA abstraction process, and continue sensitivity analyses using the TPA Version 3.2 code to investigate the effects of correlation of sorption parameters on performance.

t I

11

1.12 Tank Waste Remediation System (TWRS) . .

In subtask 1.2, staff is continuing to work on the Low-Activity Waste Feed Makeup, Solidification, and Offgas Technology and Process System Hazard and Safety Issues Repon for TWRS-Letter Report.

In subtask 1.4, staff received the NRC staff comments on the draft report titled Consequence Criteria for TWRS.The staffis evaluating the resolution of these comments.

In subtask 1.6, internal technical review of the draft report titled Chemistry of Hanford Tank Waste Pretreatment Technology was initiated. The NRC staff comments on the draft repon were received at the end of the period. Based on guidance from the NRC project officer, the amount of time and resources required to incorporate the NRC-recommended changes into the final report, currently due on December 28,1998, will be evaluated. It is expected submittal of the final report will be delayed due to the extensive changes required.

In subtask 2.1, formerly subtask 1.8, based on guidance for reviewing the DOE-RU Evaluation of the BNFL Initial Safety Analysis and Safety Requirements document, the CNWRA issued the final report, Assessment of DOE Regulatory Unit Initial Safety Evaluation Repon of the BNFL,Inc., ISA Package Open Items--Part III, on November 10, 1998. The CNWRA received NRC acceptance on Parts I and II reports with minor changes.

The changed pages, incorporating the NRC staff comments, will be sent during next period.

Also, in this subtask, CNWRA has requested a meeting with the NRC to discuss scope of the Review of Hanford Immobilized Low Activity Tank Waste Performance Assessment, of review. In addition, one CNWRA staff member attended a 3-day course, Engineering Design for Process Safety Management, along with three NRC staff.This course was given by the Center for Chemical Process Safety of the American Institute of Chemical Engineers.

In subtask 2.2,_a draft inspection manual chapter for TWRS was sent for comrnents.

In the next period, activities in subtask 1.2 will continue on the Low-Activity Waste Feed Makeup, Solidification, and Offgas Technology and Process System Hazard and Safety Issues Report for TWRS-letter Repon. In subtask 1.4, staff will continue to resolve the NRC staff comments and include assessment of 10 CFR Part 70 changes on the TWRS facility as they become available. In subtask 1.6, time and resources required to incorporate the NRC staff comments on the pretreatment chemistry and technologies report will be evaluated. In subtask 2.2, staff will start working on Inspection Procedures and incorporate the NRC staff comments on the draft inspection manual chapter for TWRS. In addition, staff will incorporate the NRC staff comments on the FY1999 Operations Plan for Technical Assistance Related to TWRS Licensing, Revision 2, Change 0.

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

The staff continued preparation of the dra'ft SER, including evaluation of the DOE response to the NRC second round RAI. The draft SER will be documented as Safety Evaluation Report-Draft Letter Report and will be submitted on November 30,1998. The review of the new Appendix E-On Site Fuel Transportation of TMI-2 was initiated during this reporting period. One TMI-2 ISFSI staff gave a presentation at the CNWRA Annual Program Review on November 17-19,1998,in San Antonio, Texas.

12

In the next period, TMI-2 ISFSI staff plans to complete preparation of the draft SER, review Appendix E of TMI-2 S AR, and prepare final SER.

1.14 Dry Transfer System (DTS)

Three DTS staff visited INEEL on November 18-19,1998, to observe DTS prototype testing and are preparing a trip report on this visit. The preparation of the draft SER was initiated during this reponing period. One DTS staff gave a presentation at the CNWRA Annual Program Review on November 17-19,1998, in San Antonio, Texas.

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

1.15 Centralized Interim Storage Facility (CISF)

Preparation of the draft AR was completed.This draft AR was documented as Assessment Repon-Draft Letter Repon and submitted on November 20,1998. One CISF staff gave a presentation at the CNWRA Annual Program Review on November 17-19,1998, in San Antonio, Texas.

In the next period, CISF staff plans to begin work to revise the computer code RISKIND.

1.16 Private Fuel Storage Facility (PFSF)

Work continued on the first group of PFSF contentions during this period. Draft position papers were prepared for five contentions.

i One PFSF staff gave a presentation at the CNWRA Annual Program Review on November 17-19,1998, in San Antonio, Texas.

In the next period, PFSF staff plans' to continue activities related to the PFSF proceeding before the ASLB and initiate preparation of draft SER.

1.17 Savannah River Site Aluminum Based Spent Fuel (SRSASF)

The criticality evaluation ofdirect codisposal and melt-dilute Al-clad fuels was transmitted as a letter report, Evaluation of the U.S. Department of Energy Aluminum Based Spent Fuel Criticality.The FY1999 Operations Plan forTechnical Assistance on Department of Energy Aluminum Based Spent Nuclear Fuels Disposition Program, Revision 1, Change 0, was transmitted with other HLW OPS plans.

One SRSASF staff gave a presentation at the CNWRA Annual Program Review on November 17-19,1998, in San Antonio, Texas.

In the next period, repons sent by the DOE will be reviewed.

2 MANAGEMENT ISSUES None to repon.

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3 MAJOR PROBLEMS . .

None to report.

4

SUMMARY

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

5

SUMMARY

OF FINANCIAL STATUS Table 4 summarizes the CNWRA financial status in the context of authorized funds. Total commitments are $238,493.The appendix lists planned and anual 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 10 KTIs, TWRS JC, TMI-2 ISFSI JC, DTS JC, CISFJC, PFSF JC, and SRS ASF JC. The planned costs per period are based on the revised spending plans contained in the CNWRA OPS for the Repository Program Revision 11, Change 0, for the DWM JC; TWRS OPS, Revision 2, Change 0, for the TWRS JC SFPO OPS, Revision 1, Change 6, for the TM 2 ISFSI, DTS, CISF, and PFSF JCs; and SRSASF OPS, Revision 1, Change 0, for the SRSASF JC.

It should be noted the current spending estimates in all JCs are based on the assumption that staffing is at authorized levels. Staffing remains below authorized levels and accelerated recruitment is in progress. An updated staffing plan was delivered as part of the November 18,1998, CNWRA Annual Program Review and subsequent meetings with NRC management.

Period 2 FY1999 CNWRA composite expenditures rose 4.4 percent from the previous period, and this aggregate of all JCs was underspent by $ 116,774 or 6.0 percent. When comparing period 2 with last period, the TWRS, TMI-2 ISFSI, and CISF JCs evidenced lower spending levels while the DWM, DTS, PFSF, and SRSASF JCs showed higher levels.

The DWM JC was underspent by $122,415 or 7.5 percent. Overall expenditures increased 8.9 percent from the previous period as costs rose in COPS and the IA, SDS, ENFE, CLST, TEF, and TSPA KTIs, but declined m the RDTME, ARDR, USFIC, and RT KTIs.

The TWRS JC was underspent by $23,399 or 17.2 percent. This underspending was primarily the result of completed payments to consultants and subcontractors from the previous FY.

The TMI-2 ISFSI JC was overspent by $19,053 or -31.8 percent. Although spending fell from last period, costs exceeded the period 2 estimate as CNWRA staff continued to focus on preparation of the draft SER.

The DTS JC was overspent by $15,476 or -73.0 percent. Expenditures increased from the previous period, reflecting spending related to the DTS prototype site visit. These costs, coupled with the relatively small initial funding for the first three periods of this FY, account for the overall cost overrun.

The CISF JC was overspent by $4,450 or - 10.9 percent. Despite a substantial decrease in spending from the previous period, the aggregate overspending has resulted from concentrated efforts in the last two periods to prepare the draft AR.

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The PFSF JC was underspent by $797 or 4.5 percent. Expenditures increased significantly over the last period as staff prepared draft position papers concerning the first group of PFSF contentions.

The SRS ASF JC was underspent by $9,142 or 52.6 percent. Spending increased over the previous period, as a result of staff preparation and delivery of a letter report related to the criticality evaluation of direct codisposal and melt-dilute Al-cad fuels and the FY1999 OPS.

Expenditures on SwRIlabor, consultants, and subcontractors as a proportion ofcomposite spending on all JCs were 20.0 percent. Expense of consultants and subcontractors as a fraction of composite spending on all JCs was 12.2 percent. The CNWRA remains committed to enhance, where appropriate, participation of consultants and subcontractors in the conduct of CNWRA work.

As shown in table 1, the CNWRA has 47 core and one limited-term staff members. The available pool of approved consultants and subcontractors is 47.

l l

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

1 DWM JC The DWM JC cumulative cost variance was 7.5 percent. Expenditures in this JC increased by 4.4 percent over last period. Specific explanations for over/ underspending for COPS and each KTI follow.

The cost variance for COPS was 13.5 percent: 12.3 percent for the Management, Planning, and Computer Support subtask (1402-158) and 18.4 percent for the QA subtask (1402-159). Spending 4 in both subtasks rose relative to last period. In the next period, expenses in both subtasks are l

expected to more closely follow estimates, but the holiday season may affect spending.  ;

The cost variance for the IA KTI was -6.2 percent. Spending is anticipated to remain stable in the next period as the FY1999 CNWRA OPS are implemented.

The cost variance for the SDS KTI was -8.5 percent. It is anticipated that spending in the next few periods of FY1999 will continue at the same rate.

The cost variance for the ENFE KTI was 25.9 percent. This variance is substantially reduced from period 1, but underspending is likely to persist until additional staff are available.

The cost variance for the CLST KTI was -35.8 percent. The overspending resulted from augmentation of activities related to sensitivity analyses, acceleration of localized and stress corrosion cracking testing of Alloy C-22 prompted by the need to have data sooner for the TSPA-VA Technical Basis document review, and participation in the workshop related to welding of Alloy C-22 sponsored by the Nickel Development Institute. The acquisition of a limited-term employee in the next reporting period together with the anticipated addition of two permanent staff members in the next quarter are expected to maintain the spending rate at the current level. The proposed augmented funding of activities is expected to alleviate the overspending.

The cost variance for the TEF KTI was 20.4 percent, significantly lower than that of the previous period. This variance will decline further during the next few periods as newly hired staff and consultants work on TEF KTI activities.

i l

15 l

The cost variance for the RDTME KTI was 6.7 percent. Actual expenditures are expected to continue following the budget for the next period as activities in this KTI remain fairly constant.

The cost variance for the TSPAl KTI was 11.9 percent. The cost variance and spending rate are expected to remain roughly the same during period 3 of FY1999.

The cost variance for the ARDR KTI was 51.1 percent. There is still no indication the draft EPA Standard will be released for review in the coming months, so underspending will continue and may even increase during period 3 of FY1999 unless new tasking is received.

The final cost variance for the USFIC KTI at the end of this period was -7.2 percent. This variance is reduced from period 1. Period 2 costs were 4.8 percent below the planned period costs. This trend is anticipated to continue and to further reduce the current variance.

The final cost variance for the RT KTI at the end of this period was 21.1 percent. This variance is likely to persist, and to increase slightly, until additional staff are available.

The cost variance for the TWRS project was 17.2 percent. The rate of spending decreased from the previous period due to the close out of subcontractor payments from the previous FY. Continuing activities in all the subtasks are expected to maintain the spending rate achieved in the current period for the next period.

The cost variance for the TMI-2 ISFSI project was -31.8 percent. This overspending is a result of concentrated efforts needed during periods I and 2 of FY1999 to prepare the draft SER. This cost overrun will decrease significantly during the next few periods because of reduced activities.

The cost variance for the DTS project was -73.0 percent. This cost overrun is due to the concentrated cost associated with the DTS prototype site visit and the allocation of funding for the first three periods of FY1999 compared to the total FY1999 budget for DTS.

The cost variance for the CISF project was -10.9 percent. This overspending is a result of concentrated efforts needed during periods I and 2 of FY1999 to prepare the draft AR. This cost overrun will decrease during the next few periods due to reduced activities.

The cost variance for the PFSF project was 4.5 percent. Actual expenditures are close to the budgeted amount.

The ecst variance for the SRSASF was 52.6 percent. Spending in the previous period increased slightly owing to completion of the review of criticality of direct codisposal fuels. The DOE is expected to transmit additional reports toward the beginning of the second quarter of FY1999, at which time the review activity is expece.:d to increase.

16

. = . -- . _ . - ..

i l

I l Table 1. CNWRA Core Staff-Current Profile and Hiring Plan * (Period 2) l =

Empertise/Esperiente PositionsOPen i Current No. Proteunenal Staff rygegg r ADMIN!STRAT10N 4 H GARCIA. W PATRICK J RUSSEIL B SAGAR

, CHEMICALPROCESSING 2 VJAIN. D.DARUWAllA  !

l ENGNG / PHYS CHEM CODE ANAL.YSIS/DEVELOPMfWT 2 RJ ANET7KE. R M ARTIN I DATA MANAGEMENT / PROCESSING. I P.MAIDONADO INCLUDING T1NANCI AL DOSE / RISK! HAZARD AN ALYSIS 0 1 EtrCTROCHEMISTRY I G CR AGNOtJNO ENGINEERING 2 R.CHEN. G.0FDEGBU GFDIDGYKiFDIDGICAL ENGNO l ENVIRONMENTAL SCIENCES 1 P tsPLANTE GEOCHEMISTRY 5 W. MURPHY. R.PABALAN, E.PEARCY. 3.PRIKRYL, l

D TURNER GEOHYDROIDGY/HYDROGEOIDGY 4 R ITDORS. R GREEN 1 WTNTERIE. D FARREll I GFDtDGY 2(In t_McKAGUE. M MIKIA3. P LAFFMINAt HYDROtDGlcTRANSPORT 1 A ARMSTRONG. 5 PAD (ITR. D HUGHSON INFORMATION MANAGEMENT 1 R KOTARA SYSTEMS M ATTRIAL SCIENCTS 1 D DUNN. N SRIDHAR. S BROSSIA I MECHANICAL. O I  ;

INCLUDING Dr$1GN & FABRICATION '

MINTNG ENGINEERING 1 S-M HSIUNG NUCt. EAR l'NGINIIRING I MJARZEMBA OPER AT10NAt HEAL 1H PHYSICS 2 J WEtI)Y.1.DEERE l PERf0RMANCE ASSESSMfNT 2 S MOH ANTY. G WITTMEYER 2 OUAtJ1Y ASSURANCE I R MABRTTO R ADIOttOTOPF GWTIEMISTRY l D PICKETT ROCK MECHANICS. 2 A.QiOWDHURY. A.GHOSH INCLUDINGCIVlf>STRUC ENGNG SOURCE-TT.RM/SPfNT FUEL DEGR AD 0 1 '

STRUCIURALGEOLOGY/ 3 D.FERRill. J.STAMATAKOS. D.SIMS i SEISMO-TFCTONICS SYSTEMS ENGINEERING 1 P.MACKIN {

VOICANOLDGY/lGNEOUS 2 C.CONNOR. B HILL PROCESSrs TOTAL 4WIM 8 l

l

• See staffing plan for details .

l t Limited term I i

a 17 i

Table 2. Summary of Schedule Changes (Period 2)

ORIGINAL REVISED 3

MILESTONE NUMBER TYPE DESCRII" TION DATE DATE RATIONALE FOR CHANGE 1402-761-900 IM Generalized importance 12/31/98 02/16/99 Principal author is unavailable-Analysis-Joumal Article 1402-861-970 IM Revised Hydrologic Parameters for 08/20/99 New deliverable established after consultation TPA Code with NRC PEM.

1402-871-940 IM Abstraction of Mechanistic Sorption 02/12/99 New deliverable established after consultation Models 'or Performance Assessment with NRC PEM.

Calculations at Yucca Mountain.

Nevada-Journal Paper 1402-871-950 IM Experimental and Modeling Study of 02/05/99 New deliverable established after consultation ion Exchange Between Aqueous with hitC PEM.

Solutions and the Zeolite Mineral Clinoptitolite-Journal Paper E

i i

l i

4 i

en r=, -.w,4+ s.. - , . . , , , - ~ . + - - - ,

-,v,w -.y.-., .-- , , - - . , - ,,, . ,y,y.- ,,-n .,, ,.wv,.-,, y- --,, -.,-.--4-.--,, -w,.e.- , , - - .rse-+- -- y- ,,-- ,e 3~ -y, , .r,,w,.w,,,,,-_ , , _ _ , , -w4.- . . ,

Table 3. Deliverables (Period 2)

ORIGINAL ACTUAL MILESTONE COMPLErlON REVISED #OF COMPLETION REASON NO. TYPE DESCRIFI1ON DATE 'DATE REVISIONS DATE (IF DELAYED) 1402-158-910 D! Briefing on CNWRA Five-Year i1/1768 11/1768 Strategic Plan 1402-158-940 MM FY1999 CNWRA Operations Plans 10/3068 10/3068 1403-201-920 IM Assessment of DOE RU Initial Safety 11/1088 11/09/98 Evaluation Repon of the BNFl Inc ISA Package Open items-Part III 1405-031-910 IM Assessment Report-Dr.ft Letter 11/20f98 11/1968 Report (CISF) 1407-001-905 IM Review of Criticality Evaluation of 11/27/98 11/2G98 Direct Co-Disposal and Melt-Dilute g Fuels i

A Table 4. Financial Status (Period 2) .

Funds Funds Funds Costed to Date Unconted Comm6tments Project Names Authartred i R28.212 202 340 R.392 COPS 2.010.552 ROR 40 46.574 20 157 IA 895 063 1.081 692 61.449 41.520 SDS 3.145.148 118.331 121,372 OR4.R75 R66 547 ENIT 812 647 28.231 14.997 860.RR0 Cl.ST 6RO570 82.912 R220 761.502 TTF 0 580 R0h 517 491 61.314 Rf>TMF 1.722.% 9 358 139 1.420 TSPAl 2.OR I IOR 69.748 0 2 % 3 57 226.610 ARDR 3 950 1.261.265 1.16R 713 92.553 USFIC 521 968 100.751 5.200 RT 622.721 11.4R2.278 10.257 9Ii 1.224367 DWM Cmts 461 ft69 260.511 303314 DWM Award Fee 4%9.291 102.901 60390 DWM Base Fee 10.917 341 1.5 R R .091 229.222 1DT A1.DWM 12.405 414 A94 606 98780 4 116 491.1R6 TV'RS Costs 47.643 22.741 24 902 TWRS Awnrd Fee 39.719 34 864 4 872 TWRS Base Fee 942.211 128.541 4 316 TOTA!.TWR S 1.ORO 764 f 2.846 0 227370 214 524 TMl-2 ISf51 S AR Costs 9.191 5.585 3.606 l TMI-2 ISF31 S AR Award Fee R 296 (il R.295 TMi-2 IST5! Base Fee 16.491 0 244 856 228404 1DTA!.TMI-2 ISTSI S AR 173333 27,755 3.235 201.089 DTS Cmts 7 774 1.401 11.175 DTS Award Fee 6 691 153 6 241 DTS Base Fee 1130R 3 235 TOTAL, D15 219 104 187.7 %

12.012 400 279 ?Rl 267.748 CISF Cmts 6 201 7.042 CISF Award Fee 13.249 10 141 R49 CISF Base l'ee 11.191 19 921 500 104.217 284.294 TOTAL. CISF 9 805 1.200 142.044 132.218 PFSF Costs 1.512 4 798 R.110 PFSF Award Fee 5106 575 PTSF Base Fee 5.682 140 R57 15.178 1.200 TOTAL. Pf5F 156 015 19 SSR 0 94 102 74 544 SRSA'.F Cmte 6340 3 191 2.989 SRSASF Award I+e 3764 2.885 879 SRS ASF Base Fee R0.780 23 426 0 TOTA 1. SRS ASF 104.206 f 2.791 Asq 1 g22.931 23R 401 Crand Tmf 14 614 615 Note: All authorized funds have tan alkrated.

20

.n Table 5. Private Feel Storage Facility License Fee Cost Recovery States (Period 2)

LICENSE FEE COST RECOVERY STATUS JOB CODE: J5226 TITLE. Private Fuel Storage Facility PERIOD: October 24-November 20,1998 TAC OR INSPECTION TASK DOCKET IDENTIFICATION PERIOD CUMULATIVE COSTS NUMBER FACILITY NAME NUMBER NUMBER COSTS CONTRACT TO DATE 20-1405-04I Private Fuel Storage 72-22 L22462 $12,401.79 $137,344.59 Facility Note: Costs include 4 percent actual base fee but not award fee, which is determined annually.

t, APPENDIX Planned and Actual Costs, and Cost Variances Period 2-FY1999 i

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CONTAINER Um AND SOURCE Tt.RM (CLST) e 14n2 570 ITLM 01 02 03 68 05 06 07 08 09 to 11 12 13 Taal Est Pd Cost 62.502 62.588 63.460 75.729 75.033 75.854 74 973 75.890 74.971 75.950 74.918 76.208 74.727 125.090 Act Pd Cost 78.364 91.542 0 0 0 0 0 0 0 0 0 0 0 169.906 Vanance.5 (15.862) (28.954) 0 0 0 0 0 0 0 0 0 0 0 144.816)

Vanance. % -25.4% -46.3% 00% 00% 00% 00% 00% 00% 00% 00% 00% 00% 00% -35 8 %

Est FY (bmul 62.502 125.090 188.550 264.279 339.312 415.166 490.139 566.029 641.000 716.950 791.888 868.096 942.823 Act FY (Nmel 78.364 169.906 0 0 0 0 0 0 0 0 0 0 0

% Complete 8.3% 180% 00% 00% 00% 00% 00% 00% 00% 00% 00% 00% 00%

Ommi Yar. $ (15.862) (44.816) 0 0 0 0 0 0 0 0 0 0 0 Ormu! Var. % -25 4 % 35 8 % 00% 00% 00% 00% 00% 00% 00% 00% 0.0% 00% 00%

Tilt.RMAL1ITTCTS ON T1.DW (TLF) 14024M T!! M 01 02 03 04 05 06 07 08 09 10 11 12 13 Total Est Pd Cost 52.306 32.308 54.269 57.046 56.424 57.220 56.391 57.221 56.332 57.407 56.331 58.052 56.218 104.614 Act Pd Cost 36.405 46.851 0 0 0 0 0 0 0 0 0 0 0 83.257 Vanance.$ 15.901 5.457 0 0 0 0 0 0 0 0 0 0 0 21.357 Vansme. % 30 4 % 104% 004 0.0% 00% 00% 00% 00% 00% 00% 00% 00% 0.0% 20 4 %

E.2 FY Cumul 52.306 104.6 t 4 158.883 215.929 272.353 329.573 385.964 443.185 499.517 556.924 613.255 671.307 727.524

(

W Act fY Cumul

% Complete 36.405 50%

83.257 ll 4% 00%

0 00%

0 00%

0 00%

0 00%

0 00%

0 00%

0 00%

0 00%

0 00%

0 00%

0 Cumul Var. S 15.001 21.357 0 0 0 0 0 0 0 0 0 0 0 Cumul Var. % 30 4 % 204% 00% 00% 00% 00% 00% 00% 00% 00% 00% 00% 00%

REPOSITORY DE5tGN AND THERMAL MECHANICALITTTITS 4' DIME) 1402470 Ill.M 01 02 03 04 05 06 07 08 09 to 11 12 13 Taal Est Pd Cost 49.201 49.317 49.103 60.421 59.784 60.505 59.784 60.782 59.782 60.8 % 59.782 61.267 59.781 98.518 Act Pd Cnst 47.865 44.034 0 0 0 0 0 0 0 0 0 0 0 91.899 Vmame. $ I.336 5.283 0 0 0 0 0 0 0 0 0 0 0 6.619 Vessnce. % 2_7% 10.7 % 00% 00% 00% 00% 00% 00% 0.0% 00% 00% 0.0% 00% 6.7%

Est FY Cumut 49.203 98.518 747.621 208.042 267.826 328.331 388.115 448.897 508.679 569.575 629.357 690.624 750.405 Act FY CLmul 47.865 91.899 0 0 0 0 0 0 0 0 0 0 0

% Complete 64% 12.2 % 00% 00% 00% 00% 00% 00% 0.0% 00% 00% 00% 00%

Cumul var. 5 I.336 6.619 0 0 0 0 0 0 0 0 0 0 0 Cumul Var. % 2.7% 6.7% 0.0% 00% 00% 00% 00% 00% 00% 00% 00% 00% 00%

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