ML20206J087

CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990313-0409

ML20206J087
Person / Time
Site:	Three Mile Island
Issue date:	04/22/1999
From:	CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES
To:	NRC
Shared Package
ML20206H925	List: ML20206H922 ML20206J087
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-99-7, NUDOCS 9905120111
Download: ML20206J087 (45)

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CNWRA PROGRAM MANAGER'S PERIODIC REPORT ON ACTIVITIES OF THE CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES For the Fiscal Reporting Period March 13,1999 - April 9,1999 PMPR No. 99-7 April 22,1999 512 990423

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TABLE OF CONTENTS Section Page TABLES.......................................................................iv 1 AB B REV IATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v l EXECUTIVE

SUMMARY

-PERIOD 7 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xi 1

TEC HNICA L . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 -

1.1 CNWRA Operations (COPS) .... .............................. ...... 1 ,

1.2 Igneous Activity (IA) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 l.3

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Structural Deformation and Seismicity (SDS) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3  ;

1.4 Evolution of the Near-Field Fnvironment (ENFE) . . . . . . . .................... 5 j 1.5 Container Life and Sou , ' an (CLST) . . . . . . . . . . . . . . . . . . . . ............. 6 j

1.6 Thermal Effects on Flo t rEF) . . . . . . . . ....................... ......... 7 1.7 Repository Design and Thermal-Mechanical Effects (RDTME) . . . . . . . . . . . . . . . . . 9 1.8 Total System Performance Assessment and Integration (TSPAI) . . . . . . . . . . . . . . . . 10 l 1.9 Activities Related to Development of the NRC High-Level Waste Regulations ( ARDR) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1 1.10 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC) . . . . . . . . . . 12 1.11 Radionuclide Transport (RT) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 1.12 Tank Waste Remediation Systems (TWRS) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 1.13 Three Mile Island Unit 2 Independent Spent Fuel Storage Installation (TMI-2 ISFSI) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 1.14_ Dry Transfer System (DTS) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 1.15 Centralized Interim Storage Facility (CISF) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 1.16 Private Fuel Storage Facility (PFSF) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 1.17 Savannah River Site Aluminum-Based Spent Fuel (SRSASF) . . . . . . . . . . . . . . . . . . 17 2 M ANAGEMENT ISS UES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 3 MAJOR PROBLEMS .................. ............. ...................... 17 4-

SUMMARY

OF SCHEDULE CHANGES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17  !

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SUMMARY

OF FINANCIAL STATUS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 APPENDIX-Planned and Actual Costs, and Cost Variances Period 7-FY1999 iii

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9 TABLES Table Page

-1 CNWRA Core Staff-Current Profile and Hiring Plan * (Period 7) . . . . . . . . . . . . . . . . . 23

-2' Deliverables (Period 7) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . 24

3 Financial S tatus (Period 7) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 4 Private Fuel Storage Facility License Fee Cost Recovery Status (Period 7) . . . . . . . . . . . . . . 26 -

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ABBREVIATIONS 1

ID One-Dimensional CDOCS Consolidated Document Management 2D . Two Dimensional System 3D ~ Dree Dimensional CDROM Compact Disk Read Only Memory AA Atomic Absorption CDS Compliance Determination Strategy AAI Average AnnualInfiltration CDTS Conunission Decision Tracking System ACD Advanced Conceptual Design CEB Center for Environmental Biotechnology ACF . Alumina (in excess of alkali feldspar), CEC Commission of the European Calcium Oxide Ferromagnesian Oxide Communities ACNW. Advisory Committee on Nuclear Waste CFD Computational Fluid Dynamics

'ACRS Advanced Computer Review System CFR Code of Federal Regulation ACS American Chemical Society CHn Calico Hills Nonwelded Tuff ADAMS Agencywide Docurnents Access and CIAC Computer Incident Advisory Capability Management System CISF Centralized Interim Storage Facility AECL Atomic Energy of Canada Limited CLST Container Life and Source Term AES. Atomic Emission Spectrometry CM Configuration Management

.AWF Antler Wash Fault CNWRA Center for Nuclear Waste Regulatory AGU American Geophysical Union Analyses Al Administrative item COI . Conflict ofInterest 4 ALTS Apache Leap Test Site COPS CNWRA Operations

'AML Areal Mass leading CPP Cyclic Potentiodynamic Polarization

.ANS American Nuclear Society CQAM CNWRA Quality Assurance Manual ANSI American National Standards Institute CRG Center Review Group -

AO Annotated Outline CRM Corrosion Resistant 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 j the NRC High-Level Waste Regulations CSH Calcium Silicate Hydrate j ASCE American Society of Civil Engineers

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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 4 Engineers DCAA Defense Contract Audit Agency ASTM 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 BDCF Biosphere Dose Conversion Factor Heir Validation Against Experiments BEG Bureau of Economic Geology in Nuclear Waste Isolation BFD Basis for Design DEIS Draft Environmental Impact Statement BM Bare Mountain DEM Digital Elevation Model BMF Bare Mountain Fault DF Dilution Factor BNFL British Nuclear Fuels Limited DFCSS Division of Fuel Cycle Safety and BTP Branch Technical Position .

Safeguards CAI Color Alteration Index DIE Determination ofimportance CAM Corrosion Allowance Material Evaluation

. CAR Corrective Action Request DIMNS Division ofIndustrial and' Medical

.CCDF Complementary Cumulative Nuclear Safety Distribution Function DKM Dual Permeability Model CCL Commitment Controlleg DLG Digital Line Graph CCM Constant Capacitance Model DLM Diffuse Layer Model CD-R CDROM Recordable DNAG Decade of North Amencan Geology CDF Cumulative Distribution Function DNFSB Defense Nuclear Facilities Safety Board

.CDM Compliance Determination Method DOE U.S. Department of Energy v

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ABBREVIATIONS (cont'd) ,

I DOE-DP U.S. Department of Energy Defense ' GEM General Electrochemical Migration I Program GEOIRAP Geologic Transport of Radionuclides DOE-RU U.S. Department of Energy Regulatory Predictions ]

Unit GERT General Employee Radiological  !

.DRA Division of Regulatory Applications Training DST. Drift Scale Test GET General Employee Training DTED . DigitalTerrain Elevation Data GFM Geological Framework Model ]

DTS . Dry Transfer System GHGC GeoHydrology and Geochemistry - q DWM Division of Waste Management GIA Generalizedimportance Analysis j EBS Engineered Barrier System GIS Geographic Information System l

EBSER Engineered Barrier System GLGP Geology and Geophysics Experimental Research GMS Goundwater Modeling System EBSPAC Engineered Barrier System GPS Global Positioning System Performance Assessment Code GROA Geologic Repository Operations Area ECM Equivalent Continuum Model GS Geologic Setting ECRB- Enhanced Characterization of Repository GSA Geologic Society of America Block GIFE Great Tolbachik Fissure Eruption EDO Office of the Executive Director for GUI Graphics User Interface Operations GWB Geochemist's Workbench EDX Energy-Dispersive X-Ray Spectroscopy GWSI Groundwater System Integration EIS _ EnvironmentalImpact Statement GWIT Groundwater Travel Time ,

EM Element Manager HE Hydrogen Embrittlement '

l EMPA Electron MicroProbe Analysis - HLUR High-Ixvel Waste and Uranium ENE East-Northeast . Recovery Projects Branch ENFE Evolution of the Near-Field HLW High-Level Waste Environment HR*lEM High-Resolution Transmission Electron ENGB Engineering and Geosciences Branch - Microscopy EnPA Energy Policy Act of 1992 IA .lgneous Activity ENS European Nuclear Society IBM International Business Machines EPA U.S. Envirpnmental Protection Agency ICP Inductively Coupled Plasma EPR . Electrochemical Potentiokinetic ICPP Idaho Chemical Processing Plant Reactivation ICRP International Commission Radiological EPRI Electric Power Research Institute Protection EQA Extemal Quality Assurance IDLH Immediately Dangerous to Life and ,

EROS Earth Resource Observation System Health

.ESF Exploratory Studies Facility IHLRWMC International Hign-level Radioactive  ;

ESP Environmental Simulation Program Waste Management Conference and EW East-West Exposition EXAFS Extended X-Ray Absorption Fine IM Intermediate Milestone Structure IME Industrial Mobilization Exemption FAC Favorable Condition IMS Information Management Systems FCRG Format and Content Regulatory Guide INEEL Idaho National Engineering and FDSHA Fault Displacement r.nd Seismic Hazard Environmental Laboratory ,

Analysis - INEIER Instituto Nicaraguense de Estudios i FEHM Finite Element Heat and Mass Transfer TERritoriales FEM Finite Element Method INTEC Idaho National Technology and FEP Features. Events, and Processes Engineering Center FFRDC' Federally Funded Research and INTRAVAL Intemational Code Validation Development Center 1/O Input / Output FFF. Fast Fourier Transform IP Inspection Procedure FOC Field Operations Center IPA lterative Performance Assessment FTE Full-Time Equivalent IR&D Internal Research & Development FIP File Transfer Protocol IRIS Interim Records Information System FY - Fiscal Year IRM Office ofInformation Resources FYTD Fiscal Year-To-Date Management GDF Ghost Dance Fault IRSR issue Resolution Status Report VI

ABBREVIATIONS (cont'd)

ISA Initial Safety Analysis NEl Nuclear Energy Institute ISFSI Independent Spent Fuel Storage NFS Network File Server Installation NIOSH National Institutes Of Safety and Health ISM Integrated Site Model NIR Near-Infrared IVM Interactive Volume Modeling NIST NationalInstitute of Standards and IWPE Integrated Waste Package Experiments Technology JC Job Code NMSS Office of Nuclear Material Safety and JPL Jet Propulsion Laboratory Safeguards JRC Joint Roughness Coefficient NNE North-Northeast KESA Key Elements of Subsystem Abstraction NNW North-Northwest KTl - Key Technicalissue NOAA National Oceanographic and KTU Key Technical Uncertainty Atmospheric Administration LA License Application NRC Nuclear Regulatory Commission LAAO License Application Annotated Outlir.e NS North-South LAN Local Area Network NSRRC Nuclear Safety Research Review LANL les Alamos National Laboratory Committee LARP License Application Review Plan NTS Nevada Test Site LAW Low-Activity Waste NUREG NRC Technical Report Designation LBNL Lawrence Berkeley National Laboratory NWPA Nuclear Waste Policy Act, as amended LBT Large Block Test NWTRB Nuclear Waste Technical Review Board LHS Latin Hypercube Sampling OBES Office of Basic Energy Sciences LITC Lockheed Information Technology OCRWM Office of Civilian Radioactive Waste Company Management

. LLC Limited Liability Company OGC Office of General Counsel LLNL Lawrence Livermore National OITS Open-Item Tracking System Laboratory OMB Office of Management and Budget LLW Low-Level Waste OPS Operations Plans for the Repository .

LMAES Lockheed Martir. Advanced Program Environmental Systems ORR Operations Readiness Review -l 13 S Licensing Support System ORS Overall Review Strategy I LSSPP Licensing Support System Pilot Project OWFN One White Flint North LSSTB Licensing Support System Test Bed PA Performance Assessment LWR Light Water Reactor PAAG Performance Assessment %ory l M Molar Group Ma Million Years Ago PAC Potentially Adverse Condition MAI Mean AnnualInfiltration PAHT Performance Assessment and MAP Mean AnnualPrecipitation Hydrologic Transport MAT Mean AnnualTemperature PASP Performance Assessment Strategic Plan MC Monte Carlo PC Personal Computer METRA Mass and Energy Transport PCfrCP Personal Computer /fransmission MGDS Mined Geologic Disposal System Control Protocol MH Mechanical-Hydrological PDF Probability Distribution Function MIC Microbially Influenced Corrosion PDR Public Document Room MINC Multiple Interacting Continus PEL Permissible Exposure Limit i MIT Massachusetts Institute of Technology PEM Program Element Manager l MM Major Milestone PER Prelicensing Evaluation Report MO Management and Operations PEST Parameter Estimation t MOU Memorandum Of Understanding PFD Prebabilistic Fauk Displacement MPC Multi-Purpose Canister PFDHA Probabilistic Fault Displacement MRS Moaitored Retrievable Storage Hazard MSS MultiSpectral Scanner PFS Paivate Fuel Storage MT11 Metric Ton of Uranium PFSF Private Fuel Storage Facility NAS National Academy of Sciences PHA Preliminary Hazard Analysis NAWG Natural Analogue Working Group Pl PrincipalInvestigator NCR NonConforman:e Report PMDA Program Management, Policy NEA Nuclear Energy Agency Development and Analysis Staff vii

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ABBREVIATIONS (cont'd)

PMPR Program Manager's Periodic Report SECY Secretary of the Commission, Offce of PMT Photo-Multiplier Tube the (NRC)

PNNL Pacific Northwest National Laboratory SELM Spectral Element Method PO Project Officer SEM Scanning Electron Microscopy PPA Proposed Program Approach SER Safety Evaluation Report PPE Prepassivated Platinum Electrode SFPO Spent Fuel Project Office PRA Probabilistic Risk Assessment SFVF San Francisco Volcanic Field PRT Peer Review Team SGI Silicon Graphics Inc.

PSAO Probabilistic System Assessment Group SGML Standard Generalized Markup PSHA Probabilistic Seismic Hazard Analyses Language IrITE Polytetrafluoroethylene SHE Standard Hydrogen Electrode PTn Paintbrush Nonwelded Tuff SHT Single Heater Test PVHA Probabilistic Volcanic Hazards SIP Scientific Investigation Plan Assessment SKI Swedish Nuclear Power Inspectorate PVHVIEW Probability of Volcanic Hazards S-L Short Transverse-Longitudinal VIEW SLAR Side Looking Airborne Radar PVM Parallel Virtual Machine SNF Spent Nuclear Fuel PWR Pressurized Water Reactor SNL Sandia National Laboratories QA Quality Assurance SOTEC Source Erm Code QAP Quality Asstance Procedure SOW Statement Of Work QRAM Quality Requirements Application SPCR Software Problem Correction Report Matrix SRA Systematic Regulatory Analysis RAI Request for AdditionalInformation SRB Sulfate-Reducing Bacteria RASA Regional Aquifer System Analysis SRBS Shafts, Ramps, Boteholes, and Their RDCO Repository Design, Construction, Seals and Operations SRD Software Requirements Description RDTME Repository Des!gn and Thermal- SRS Savannah River Site Mechanical Effects SRSASF Savannah River Site Aluminum-REE Rare Earth Element Based Spent Fuel REECO Reynolds Electrical and Engineering SS Stainless Steel Company,Inc. STEM Scanning Transmission Electron RES Office of Nuclear Regulatory Research Microscopy RFP Request For Proposal STP Staff Technical Position RH Relative Huinidity SUFLAT Stochastic Analyses of Unsaturated RIP Repository Integration Program Flow And Transport ROC Repository Operations Criteria SVF Springerville Volcanic Field RPD Regulatory Program Database SwRI Southwest Research Institute )

RRT Regulatory Requirement Topic SZ Saturated Zone RSRO Real Space Renormalization Group TA Technical Assistance RT Radionuclide Transport TAN Test Area North RTS 'Radwaste Treatment System TBD To Be Determined SAIC Science Application International TBM Tunnel Boring Machine Corporation TCP/IP Transmission Control Protocol /

SAP Standards Approval Package Internet Protocol SAR Safety Analysis Report TDEM Time-Domain Electro-Magnetic SCA Site Characterization Analysis TDI Technical Document Index SCC Stress Corrosion Cracking TDOCS Technical Document Reference SCCEX Substantially Complete Containment Database System Example "IT!DE Total Effective Dose Equivalent SCE Standard Calomel Electrode - TEF Dermal Effects on Flow SCFF Southern Crater Flat Fault TEM Transmission Electron Microscopy SCM Surface Complexation Models THC Thermal-Hydrologic-Chemical SCP - Site Characterization Plan THMC nermal-Hydrologic-Mechanical-SDMP Site Decommissioning Management Plan Chemical SDS Structural Deformation and Seismicity T-L Transverse-Longitudinal TLM Triple-Layer Model Viii l

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4 ABBREVIATIONS (cont'd)

- 'IM Thermal-Mechanical WSEI Waste Systems Engineering and TMH Thermal-Mechanical Hydrologic Integration TMI Three Mile Island Unit 2 .

WSRC Westinghouse Savannah River i TMS The Minerals, Metals, and Materials Company 1 Society WSS Waste Solidification Systems

' TOP. Technical Operating Procedure WTSO Washington Technical Support Office 17 Technical Position WVDP West Valley Demonstration Pmject

' TPA Total system Performance Assessment WVNS West Valley Nuclear Services 171 Time Period of Regulatory Interest WWW World Wide Web TR2 DOE Seismic Topical Report No. 2 XPS X-ray Photoelectron Spectroscopy TRO Technical Review Group XRD' X-Ray Diffractometry

-TSAR Topical Safe:y Analysis Report YM Yucca Mountain i TSPA Total System Performance Assessment YMP Yucca Mountain Project TSPA VA Total System Performance Assessment. YMR Yucca Mountain Region Viability Assessment YMRP Yucca Mountain Review Plan TSPAl TotalSystemPerformance Assessment YMSCO Yucca Mountain Site Characterization and Integration Office TSw Chnv Topopah Spring Welded-Calico YTD Year-To-Date Hills Nonvitric .

. lYD Total Variation Diminishing '

TWFN Two White Flint North

- TWINS , Tank Waste Information Network System TWRS Tank Waste Remediation System UA Universityof Arizona UACH 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

- U.S. United States USDA U.S. Departn'ent of Agriculture -

USGS U.S. Geological Survey -

LTI'M 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 -

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Strategy  !

, WPO Work For Others WGB Westem Great Basin WIPP Waste isolation Pilot Plant  !

WMB Waste Management Branch WNYNSC Western New York Nuclear -

Service Center .  ;

WOL Wedge-Opening loading WP Waste Package -

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i EXECUTIVE

SUMMARY

-PERIOD 7 In the Division of Waste Management (DWM) Job Code (JC), the Center for Nuclear Waste Regulatory Analyses (CNWRA) demonstrated CNWRA capabilities and activities to F. Miraglia, Deputy Executive Director of Operations. A geophysics / volcanology laboratory was established primarily to conduct fluid physical analog experiments in confirmation of results from numerical modeling, and develop improved methods for kinematic and differential Global Positioning System surveys. Moreover, staff delivered a revision to the CNWRA Operations Plans for the Repository Program, the CNWRA Management Plan, Revision 7, Change 0, a report entitled Evaluation of Thermal-Hydrological Model Concepts, Data, and DOE Thermal Test Results-Status Report, the version of the Total-system Performance Assessment (TPA) code created by merging the Parallel Virtual Machine, Personal Computer, and SUN Solaris versions of the TPA Version 3.2 code, and the Formal Review of DOE SZ Studies-Letter Report. In addition to preparing abstracts and posters for presentation during this year, the staff produced journal papers on Magmatic and Hydromagmatic Conduit Development During the 1975 Tolbachik Eruption, and the Effect of Environmental Variables on Localized Corrosion of Carbon Steel and Factors Important in its Use in the HLW Disposal. <

These papers have been or will be submitted for acceptance in recognized technical journals. Staff participated in workshops, symposia, and other technical meetings.

The DWM JC year-to-date (YTD) cost variance was 16.5 percent. Spending rose slightly from the previous period as a result ofincreased activity in specific key technical issues.

In the Tank Waste Remediation System (TWRS) JC, the staff delivered the revised Design Safety Features Deliverable: Hydrogen Control in High-Level Waste Storage Tanks, the BNFL, Inc. Design Safety Features, a Febmary 1999 deliverable, and the Integrated Design Inspection Program for Radioactive Waste Treatment / Nuclear Material Production Facilities. Work continued on the Hanford TWRS HLW Chemistry Manual, to be published as NUREG/CR-5751, and a report titled Review of Hanford Immobilized Low-Activity Tank Waste Performance Assessment. In addition, staff continued incorporating Nuclear Regulatory Commission (NRC) comments on other previously submitted reports. The YTD cost variance was 28.0 percent. Despite the high-level of activity, spending again fell from last period, end the cumulative percentage variance increased to the level of period 5.

In the Three Mile Island Unit 2 (TMI-2) Independent Spent Fuel Storage Installation (ISFSI) JC, the staff continued to assist the NRC staff prepare TMI-2 ISFSI Materials License No. SNM-2508. The YTD cost variance for the TMI-2 ISFSI was -4.6 percent. The cumulative variance decreased, as expected, due to a substantial decline in spending.

In the Dry Transfer System JC, staff pursued development of the second round request for additional information (RAI) and preparation of the draft SER. The YTD cost variance was 8.4 percent, despite a substantial rise in spending from last period.

In the Centralind Interim Storage Facility (CISF) JC, staff performed a detailed technical review of the Topical Report on HI-STAR / HI-STORM cask system deployment at high-seismicity sites and initiated revision of the computer code RISKIND . The YTD cost variance for the CISF was 41.1 percent. This underspending resulted from staff awaiting tasking to update the draft assessment report.

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EXECUTIVE

SUMMARY

-PERIOD 7 (cont'd)

In the Private Fuel Storage Facility (PFSF) JC, staff continued the review and evaluation of the PFS response to the NRC second round RAI, review of site characterization reports, preparation of a draft SER, and revision of the NRC draft position on five Group 1 contentions. Spending decreased along with the cumulative variance. The YTD cost variance was - 16.0 percent.

In the Savannah River Site Aluminum-Based Spent Fuel JC, the staff delivered revisions to the letter report Review of Criticality Evaluation of Direct Co-disposal and Melt-Dilute Fuels, and reviewed the Department of Energy reports on creep and dissolution of Al-based spent fuel towards completion of the report, Review of the U.S. Department of Energy Preliminary Evaluation of Aluminum-Based Spent Nuclear Fuel-Final Report. The YTD cost variance was 73.9 percent. Although spending increased relative to last period, it remained well below projections. The cumulative variance increased in absolute terms, but decreased slightly on a percentage basis.

It should be noted thit 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 presented in conjunction with the delivery of the CNWRA Management Plan, Revision 7, Change 0. Current staffm' g 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, J5186,35206, J5226, J5210 NRC CNWRA PROGRAM MANAGER: John J. Linehan,(301) 415-7780 NRC CNWRA DEPUTY PROGRAM MANAGER: Deborah A. DeMarco,(301) 415-7804 CNWRA PRESIDENT: Wesley C. Patrick, (210) 522-5158 ESTIMATED BUDGET: $87,611,477 PERIOD OF PERFORMANCE: 09/27/97-09/27/02 PERIOD OF THIS REPORI: 03/13/99-04/09/99 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) revising the CNWRA OPS; (ii) delivering the CNWRA Management Plan, Revision 7, Change 0; (iii) demonstrating CNWRA capabilities and activities to F. Miraglia, Deputy Executive Director of Operations; (iv) participating in the development of NRC budgets for the next two fiscal years; (v) interacting through telephone and video teleconference meetings with NRC management staff concerning tasking, spending, and hiring for the CNWRA during the balance of FY1999; (vi) further addressing COI-related topics among the NRC, SwRI, and CNWRA management staffs; and (vii) participating in weekly HLW Management Board meetings.

The status of CNWRA staffing is indicated in table 1. A revised staffing plan has been submitted along with Revision 7, Change 0, to the CNWRA Management Plan. During period 7, intensive recmitment continued and several sources were used to identify potential candidates. An operational heath physicist resigned and a mechanical engineer joined the staff during this period, maintaining the staff the same as last period.

Computer system support activities encompassed (i) continuing the use of consultants to assist in development and implementation of the database retrieval system (replacement for 1

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CDOCS) and modification of existing databases and spreadsheets for management i reporting, and to substitute for IMS staff lost through attrition;(ii) monitoring, modifying, j and securing, as required, the SUN Microsystems and Silicon Graphics hardware and j software associated with the GIS and IMS computing facilities as well as testing l components in the Silicon Graphics hardware: (iii) pursuing the installation and upgrade of standardized desktop computer systems; (iv) examining the need for revision of the CNWRA Security System (firewall); (v) evaluating the cost / benefit of the CNWRA using the NRC ADAMS under specific access restraints; (vi) participating, as requested, in the t monthly NRC/CNWRA Computer Coordination meeting; and (vii) maintaining LAN operations.

Specific QA activities were directed to the areas of (i) completing preparation of the materials for Presentation of Training Module on Observation Audit Techniques to the NRC staff; (ii) conducting surveillances, issuing nonconformance reports, as required, and working with cognizant staff in response to these reports; (iii) supporting the application of configuration control for CNWRA scientific and engineering software ready for release; (iv) preventing organizational COI by reviewing SwRI RFPs; (v) performing QA verification checks on each CNWRA deliverable;(vi) providing QA indoctrination for new CNWRA staff members and consultants; and (vii) identifying audit areas for the CNWRA annual audit set for June 8-11,1999.

i In the next period, the CNWRA staff expects to (i) provide a review of CNWRA activities I to Commissioner Greta Joy Dieus; (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 hiring for unfilled core staff positions; (iv) continue monitoring computer hardwr.re and software for GIS and IMS computing facilities, routinely develop new, and modify existing, databases and spreadsheets, and examine the LAN configurations, including the CNWRA firewall, for any modifications necessary to maintain usefulness and effectiveness; and (vi) provide CNWRA LAN operation and maintenance support.

In addition, the staff will (i) perform scheduled and unscheduled QA surveillances, (ii) conduct QA indoctrinations for new CNWRA staff and consultants, (iii) review SwRI RFPs for potential COI, (iv) perform QA verification checks on each CNWRA outgoing deliverable, (v) provide the Training Module on Observation Audit Techniques to appropriate NRC staff, and (vi) complete preparations for the June 1999 CNWRA audit.

1.2 Igneous Activity (IA)

Revisions to the IA IRSR commenced during this period. Staff are addressing significant technical concems with volcanism models and data in the DOE TSPA-VA. Recent discussions with the DOE staff indicate the most significant of these concerns can be resolved before licensing if the DOE undertakes planned technical investigations. The revised IRSR also will include initial results of numerical models for magma-repository interactions and updated sections on volcanism risk to reflect an expected annual dose standard proposed in 10 CFR Part 63.

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Staff panicipated in development of the YMRP during this period. Acceptance criteria from the IRSR were integrated into the draft YMRP outline. Although many of these acceptance criteria address post-closure performance sections of 10 CFR Part 63,IA acceptance criteria also are needed to evaluate site characterization and pre-closure performance sections of 10 CFR Part 63.

IA staff panicipated in the first National Research Council meeting to review the USGS volcanic hazards program. Appointed by the' NAS, panel members will provide recommendations on future directions for the entire USGS volcanic hazards program.

CNWRA staff will write sections for the final NAS report related to the development of probabilistic volcanic hazards assessments and the use of expert judgement during volcanic crises.

Staff completed revisions to the journal paper Magmatic and Hydromagmatic Conduit Development During the 1975 Tolbachik Eruption, Kamchatka, with Implications for Hazards Assessment at Yucca Mountain, Nevada. This paper has been accepted for publication in the Journal of Volcanology and Geothermal Research.

Construction was completed on the geophysics / volcanology laboratory at SwRI. This facility will be used to conduct fluid physical analog experiments in confirmation of results from numerical modeling. Construction of the primary experimental apparatus for magma-repository interactions continued at the University of Bristol. The new SwRI lab also contains GPS equipment, which is being used to develop improved methods for kinematic and differential GPS surveys. These surveys are pan of ongoing investigations with the SDS KTI to constrain relationships between crustal strain-rate and volcanic hazard rates.

Staff completed a numerical model for conductive cooling of cinder cones. The cooling rates measured at recently active basaltic cinder cones can be modeled using a purely I conductive cooling model, assuming a low bulk thermal conductivity.' Results of this investigation may be used to model cooling of fragmented basaltic magma in nonbackfilled repository drifts.

In the next period, staff will complete the author final draft and begin review of the IA KTI IRSR, Revision 2. Staff will continue to participate in development of the YMRP. I Construction of the experimental apparatus and development of numerical models for magma-repository interactions will continue at the University of Bristol. Staff will prepare for field investigations at the Big Pine volcanic field in period 9, to evaluate relationships between mapped faults, locations of basaltic volcanoes, and ongoing GPS strain-rate studies. Staff also will prepare presentations for the YM special session at the AGU Spring meeting and attend the second National Research Council meeting to review the USGS volcanic hazards program.

1.3 - Structural Deformation and Seismicity (SDS)

Staff participated in two DOE- and USGS-sponsored meetings on the geology and hydrology of the Amargosa area. The underlying impetus for both meetings was development of more representative groundwater models of the region. The first meeting, 3

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m held on April 6-8,1999, was the annual Devils Hole Workshop. The workshop focused on groundwater issues, especially related to flow at Devils Hole, Nevada. The Yucca Mountain groundwater system plays a critical role in the hydrology of Devils Hole. At this workshop, CNWRA staff made a 45 minute oral presentation summarizing its identification of buried structural features in the northern Amargosa desert based on recent geophysical investigations. The second nneting focused on the geology of Death Valley, California.

CNWRA staff presented t':<o posters at the meeting: one summarizing the geophysical work in the Amargosa desert and Crater Flat and the other evaluating Neogene tectonics of the region based on paleomagnetic results. Both meetings included 1-day field trips.

Staff conducted field work examining fracture exposures at YM. The field investigations will form the basis for an upcoming milestone on fractures titled Models of Faults and Fractures at Different Scales in Analysis and Evaluation of Fracture Data--CNWRA Report. The information will also be used in support of acceptance criteria established in the SDS IRSR.

Staff also presented two papers at the annual meeting of the American Association of Petroleum Geologists, held in San Antonio.The two presentations summarized recent work on analog modeling experiments of pull-apart basins and the evolution of cn echelon normal fault systems. Staff presented a paper at the Society forIndustrial and Applied Mathematics conference in San Antonio on the abstraction of faulting in the FAULTO module of the  !

TPA 3.2 code.

Staff prepared input to a USFIC deliverable titled Input to NRC Working Group on Viable SZ Conceptual Flow Models-CNWRA Report, which summarizes the work of the Structural Effects on Flow Working Group activities. Staff also continued to develop a 3D ,

structural model of Northern Amargosa, which will be documented in Resolve Selected Field Relationships for 3D Structural Model of Amargosa Desert for Input ' to USFIC-CNWRA Report, and the structural evolution of Yucca Mountain and Crater Flat, which will be reported in Strain Distribution and Tectonic Setting of Yucca Mountain and Crater Flat-Journal Article. Staff also continued to assess and modify parameters used in the FAULTO module in anticipation of upcoming sensitivity studies.

Staff participated in development of the YMRP during this period. Acceptance criteria from the IRSR were integrated into the draft YMRP outline. Although many of these acceptance criteria address post-closure performance sections of 10 CFR Part 63, SDS acceptance criteria also are needed to evaluate site characterization and pre-closure performance sections of 10 CFR Part 63.

In the next period, staff will attend the first quarterly meeting of the Thermochronological Evolution of Calcite Formation working group held at the University of Nevada at Las Vegas. Staff will conduct sensitivity studies of faulting and seismicity in preparation for writing the SDS IRSR, Revision 2.0. Staff will also continue reviews of the DOE PSHA, fracture studies, tectonic investigations, and VA in preparation for writing the SDS IRSR, Revision 2.

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1.4 Evolution of the Near Fleid Environment (ENFE)

ENFE staff panicipated in the Natural Analogue Working Group Workshop in Strasbourg, France, March 23-25,1999, and presented three talks on Pena Blanca analog studies. Work was initiated on papers to be published in the workshop proceedings. Several contacts with European scientists were made at.the workshop in regard to the possibility of organizing 1 a European Commission-sponsored intemational project focused on Pe5a Blanca. CNWRA I

staff met with NRC staff to refine plans for augmented studies at the Nopal I natural analogue site at Pena Blanca. The key objective of the work is to obtain information on the timing and magnitude of uranium release as expressed in secondary fracture-filling ]

minerals, especially opal and calcite. New mapping and sampling at the site will provide data on the mass of uranium mobilized, and new and existing samples will be age-dated by the uranium series method. The products of this investigation will be new estimates of shorter-term uranium release rates for comparison with rates used in PA. In addition, new age data will be obtained on uranium minerals and jarosite for constraining the time scale of oxidation of the spent fuel analog mineral uraninite.

Staff pursued debugging, testing, and documenting the MULTIFLO code, Version 1.2p, and continued trials of the unstructured grid options using the new mesh generation capabilities. l They identified and are correcting errors in the MULTIFLO initialization routines for j unstructured grids. Coding of the open-drift ventilation model continued. l I

Advances have been made in both developing a coupled THC model for the proposed repository environment and benchmarking chemistry results between MULTIFLO and  !

EQ3/6 models. Estimates of the YM glass pseudothermodynamic and kinetic properties at i elevated temperatures were completed. Modifications were made successfully to the j MULTIFLO database to accommodate the new glass phase and also to aid in benchmarking j exercises involving the EQ3/6 v7.2b database. Staff has verified the capabilities of MULTIFLOtotreatisothermalUO dissolutionandaqueousspeciationproblems.

2 Attempts to benchmark the nonisothermal, kinetic oxidative dissolution of UO 2are underway, and have revealed the possibility of a significant bug involving MULTIFLO treatment of redox reactions, which is currently being explored.

In collaboration with NRC staff, CNWRA staff completed reviewing a draft of Input to ENFE IRSR, Revision 2-Letter Report, which consists of a complete restatement of the status ofissue resolution at the stafflevel. In this revision, acceptance criteria presented in the previous revision of the IRSR were applied in a review of the TSPA-VA.

Development of a literature review and experimental work on the performance of cement at elevated temperatures continued. A subcontract with the University of Aberdeen for conducting additional cement studies is still being processed. A summary of potential effects of microbial activity on repository performance is being developed.

In the next period, staff will submit Input to ENFE IRSR, Revision 2-Letter Report. A literature study and experiments on the performance of cement at elevated temperature will continue. Staff will continue debugging and benchmarking the MULTIFLO code and using the code to simulate the proposed repository near field. Near-field radioelement solubility 5

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modeling and aqueous actinide chemistry studies, and sensitivity studies on the effects of j cementitious materials, will continue. Staff will attend the DOE in-drift geochemical  ;

processes and EBS transport workshop. Papers will be prepared for submission to the proceedings of the Natural Analogue Working Group Workshop.

1.5 ' Container Life and Source Term (CLST)

Staff discussed with the NRC staff the revisions to the IRSR and prepared an outline. Based >

on this outlina, a decision will be made by the NRC staff on the type of changes to be made in IRSR, Revision 2.

Staff have continued preparing the report Assessment of Performance Issues Related to Alternate EBS Materials and Design Options due on 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.

Electrochemical corrosion testing continued to confirm the applicability of repassivation I and corrosion potentials as predictive parameters for the long-term, localized corrosion of corrosion-resistant container materials in chloride-containing solutions at 95 *C.Two tests  :

using' Alloy 825 specirnens continued, including a creviced specimen held at 100 mV 3cs (50 mV less than the repassivation potential) in a 1,000 ppm chloride solution. No evidence oflocalized corrosion has been observed for a total test time of 1,306 days. A second Alloy 825 test specimen has been immersed in an air-saturated 1,000 ppm chloride solution at open circuit for a total test time of 1,160 days. Crevice corrosion has been observed on this specimen several times throughout the duration of 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 at pH 8. One specimen is tested at open circuit so that the time-dependent changes in the corrosion potential can be monitored. The other Alloy 22 specimens are held at applied potentials of 400 and 700 mV 3ce to determine the time required for crevice corrosion initiation as a function of potential. The tests will be interrupted so that the specimens may be examined prior to the next reporting period.

The passive dissolution rate of Alloy 22 has been measured in solutions containing 0.028 to 4 M chloride. Tests are now being conducted on thermally aged specimens. These tests are designed to determine the effects of both long-range ordering and the formation of intermetallic phases, which may occur as a result of WP fabrication and welding processes, on the passive dissolution rate of Alloy 22. Repassivation potentials of welded specimens presently are being measured in autoclaves in 0.5 to 4M chloride solutions at temperatures ranging from 95 to 175 *C. Initial tests, conducted in 4M chloride solutions at both 95 and 125 *C, resulted in marked preferential localized corrosion at the welds. Lower repassivation potentials also were observed for the welded specimens compared to

. nonwelded specimens.

SCC tests continued on Alloy 22 and type 316L SS. Fatigue precracked, wedge-loaded DCB specimens of each material have been immersed in a deaerated 5 percent Nacl 6

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 in 33 MPa m , while the type 316L SS specimens were tested at an initial stress intensity of u2 25 MPa m . No cracking was observed under these conditions for a cumulative test time of 20 wk In addition, no crack growth was observed in Alloy 22 specimens tested in 40 percent MgCl2 at i10*C for 9 and 20 wk. However, cracking was observed on a 316L specimen with an initial stress intensity of 22 MPa m" under an applied potential of

-340 mV 3cc exposed in 30 percent MgCl2 at i10 *C after 10 days. Initial measurements with 316L indicate that the repassivation potential in this solution is approximately

-390 mVscs. After the crack length was documented, the specimen was re-exposed for an additional 10 days in order to document crack advance. Additional tests with 316L under applied potential conditions are planned to determine the relationship between crack growth rate and potential, j

l The staff is examining the key environmental variables affecting the corrosion behavior of l

A516 carbon steel and the critical values of these variables in determining the occurrence oflocalized corrosion. In particular, the pH, chloride concentration, temperature, and redox potential are being examined. Work continued on examining whether localized corrosion 1

of A516 can occur under open circuit conditions in air-saturated solutions. Experiments

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designed to determine the repassivation potential of creviced A516 specimens as a function  !

of environment were completed and further tests examining boldly exposed specimens were initiated. A paper entitled Effect of Environmental Variables on Localized Corrosion of Carbon Steel and Factors Important in its Use in HLW Disposal was subndtted for approval as an IM. The paper will subsequently be submitted for publication in Corrosion. Further work examining the potential effects of a reverse VA WP design on carbon steel corrosior, l has been initiated, j

i The effects of solution chemistry at 95 *C on the corrosion behavior of Ti-Grade 7, which  !

h m been identified by the DOE as a possible candidate material for WP and/or drip shield I construction are being examined. Preliminary work is focusing on the effect of chloride l concentration and pH on the critical potentials for localized corrosion.

In the next period, staff will pursue long-term corrosion tests of Alloys 825 and C-22, j

together with SCC tests using Alloy C-22 and type 316L SS. Moreover, they will continue -

limited testing of A516 carbon steel and expand testing of Ti alloys. CNWRA staff will also attend the Waste Package Degradation and Modeling Abstraction Workshop to be held ,

April 20-21.1999 in Las Vegas, Nevada. I 1.6 Thermal Effects on Flow (TEF) '

Numerical analysis of the DST continued during this reporting period. The DST is being l modeled to evaluate the sensitivity of moisture redistribution in the fracture and matrix  !

continua to loss of heat and water mass through the thermal bulkhead. A 3D DCM model of the DST has been successfully run. The sensitivity of the DCM to changes in the matrix / fracture interaction factor is being investigated.

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The second phase of the laboratory-scale boiling isotherm depression heater experiment i continued during this period. The heat load has been slowly decreased to permit observation j of the collapse of the boiling isotherm into the drift during the cooling phase. A joamal paper based on this activity is being prepared.

l l Staffcontinued the mountain-scale repository analyses. A nonstructured grid was generated to represent the new 2D vertical section. The new grid is being implemented into the 2D 1 l cross section.

l lj The report entitled Evaluation of Thermal-Hydrological Model Concepts, Data, and DOE Thermal Test Results-Status Report has been submitted on March 29,1999. ,

i Staff have been preparing to attend the DOE /NRC Appendix 7 meeting on thermal testing i l to be held in Las Vegas, Nevada on April 28,1999. Staff also intend to participate in a field j trip to the Busted Butte facility and the east-west drift, attend the DOE quarterly thermal '

testing workshop, and visit the DOE Richard's barrier experiments at the Atlas Facility j during this visit to Las Vegas, Nevada.  !

I Staff attended the DOE Thermal Hydrology Coupled Processes Abstraction Workshop '

conducted March 24-25,1999 in Albuquerque, New Mexico. A trip report summarizing the activities of the workshop was prepared and submitted on April 13,1999. A summary j of the activities of the workshop was also presented at the YM team meeting on l April 7,1999. l Staff prepared a short description of a proposed laboratory-scale coupled corrosion / heater experiment for discussion by NRC/CNWRA staff working on the TEF and CLST KTIs. It j is currently envisioned that the TEF KTI laboratory-scale heater test apparatus will be 1 modified to provide a credible environment to observe and measure corrosion processes.

Staff continued, at a low level of activity, a review of literature to identify potential analog sites for the evaluation of water seepage from fractures into open drifts in the UZ. 1 Investigation of capillary diversion at the drift walls continued during this period. The laboratory-scale experiment designed to resolve the distinction between capil:ary diversion and dripping continued. A profilometer-generated map of the surface roughness of the Hele- l Shaw type glass plate fracture model at ten locations has been completed. Numerical  !

investigation of the diversion mechanism continued. A nonstructured grid option to the  !

MULTIFLO code has been successfully implemented.The effect of grid discretization of the unstructured grid is under investigation.

Staff pursued the formulation of an analytical / numerical solution to represent groove flow i down a fracture through heated porous media. A draft journal article describing this j progress was completed and is undergoing technical and programmatic review. '

Staff continued the review of the TSPA-VA Technical Basis Document, and the detailed review findings are being included in the next version cf the TEF KTIIRSR, which is in preparation.

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In the next period, staff plans to (i) complete the second phase of the boiling isotherm penetration laboratory-scale experiment, (ii) continue a literature search for identification of potential dripping analog sites, (iii) continue to test the MULTIFLO-DCM numerical code in modeling the DOE DST,(iv) continue the integration of a groove / film flow model into the mechanistic fracture flow model, (v) continue the revision of the TEF IRSR, (vi) continue preparation of the journal articles, (vii) continue the development of IRSR, and (viii) panicipate in the DOE /NRC Appendix 7 Meeting on Thermal Testing and associated activities in Las Vegas, Nevada.

1.7 Repository Design and Thermal Mechanical Effects (RDTME)

Staff continued the TM study of drift stability in the .a 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. Two cases are being studied. One case assumes that an emplacement drift is located in a strong rock condition and no strong-weak rock transition takes place, and the other case involves a strong to weak rock transition at the middle of an emplacement drift. The computer analyses for these two cases have been completed and the results are being analyzed.

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 analyss using UDEC and KDYNA 3D to examine rockfall, as this effort will increase confidence in UDEC results. Construction of the mesh model for KDYNA 3D is near completion. A UDEC model comparable to that of KDYNA 3D was constructed so that the UDEC and KDYNA 3D results can be reasonably compared. This UDEC model was also used to study the effect of dilation angle of rock joints on rockfall.

The ABAQUS modeling of WPs continued to investigate the thermal stress of WPs and also assess WP responses when subjected to the impact of falling rocks at various times. I Degradation of WPs with time will be included in the analysis. This activity will develop a reasonable failure criterion to be used in the SEISMO module to assess the effect of rockfall on WP integrity.

A CNWRA staff member attended the DECOVALEX II workshop in Kalmar, Sweden on March 23-25,1999. The scope of this workshop included preliminary discussion of the activities of DECOVALEX III scheduled to begin on July 1,1999. 1

. Staff pursued development of the review plan for preclosure aspects ofdesign, construction, and operations of the repository using the integrated safety assessment methodology.

CNWRA staff attended several meetings attempting to develop an acceptable outline for the YMRP so that development of a review plan can proceed.

Staff studied the behavior of the rock mass surrounding the emplacement drifts under heated conditions at the repository scale using the ABAQUS code. They conducted ABAQUS modeling of several drift scale models and analyzed these results to compare with those from the repository-scale model. This study emphasizes rock mass behavior beyond the preclosure period and effects of thermal load on permeability changes in the 9

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surrounding rock mass. The work progress associated with this study was reviewed by a CNWRA consultant. The staff is currently preparing responses to the review comments.

Further work in this area will be revised to addresses the concerns raised by the review. l 1

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Staff reviewed literature on concrete performance at high temperature to provide valuable j information to assess the DOE design of the concrete liner for use at high temperature.

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In the next period, staff plans to (i) investigate rock mass behavior under heated conditions l on both repository and drift scales with an emphasis on long-term degradation of rock mass j material properties and strengths, (ii) conduct rockfall simulations, (iii) use the ABAQUS code to model WPs, (iv) develop input to the YMRP, (v) initiate the development ofIRSR, and (vi) attend the DOE Drift Stability Workshop and NRC/ DOE Ap,.endix 7 Meeting on Thermal Testing. j 1.8 Total System Performance Assessment and Integration (TSPAI) ,

1 Using the TPA Version 3.2 code, staff generated new output data and applied newly j implemented analytical methods to assess the sensitivity of TPA model output to changes in model parameter values. Activities comparing NRC and DOE results continued using the i TPA code, NRC and DOE data, and DOE published results. A revised outline of the i sensitivity analysis report, which will document NRC sensitivity analyses using TPA Versic9 3.2 code ?s well as the differences between NRC and DOE results, was sent to the NRC to identify areas where other KTIs can make contributions.

The version of the TPA code that was created by merging the PVM, PC, and SUN Solaris versions of the TPA Version 3.2 code was delivered to the NRC for release to the DOE.

The code was successfully loaded and executed on a DOE computer.

Staff delivered draft outlines to the NRC for developing pre- and post-processors for the TPA code for review. Development of a GUI for the general parameter tree approach was discussed and a draft outline for the use ofintermediate outputs along with an SRD for this approach was developed.

' Staff provided support to the NRC staff in resolving comments from tne NRC technical editor and making changes to volume I of the sensitivity studies report prior to its j publication as a NUREG.

The NRC and CNWRA held discussions on the use of KES A as an approach for integrating the activities of various KTIs. A second joint brainstorming meeting was held on developing a general approach for the multiple barriers concept. Following a video conference to determine the scope of the YMRP, the staff conducted an initial match up of

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IRSR acceptance criteria with the YMRP outline. j l

Suspended volcanic ash samples collected by the staff at the Cerro Negro volcano m j' Nicaragua were analyzed for particle size distributions. The collected data will be used in refining the AML factor for the DCAGS module of the TPA Version 3.2 code, which is used in estimating inhalation doses due to radionuclides released by extmsive volcanism.

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CNWRA QA staff participated in the meetings, held at the NRC office in Las Vegas, Nevada, with DOE and their M&O contractor staff regarding the ongoing QA cornetive actions addressed by the NRC HLW QA Task Force, This was the second trip by CNWRA/ swr 1 QA staff in support of the NRC HLW QA Task Force.

The formal meeting scheduled for April 28-30,1999, for the extemal review of the TPA Version 3.2 code has been postponed to late July or early August because of difficulties in finding replacement reviewers on short notice. The external reviewers were notified of the changes to the external review schedule. A proposal for changes to the OPS to accommodate the revised date for the external review was submitted to the NRC for review.

During the visit of Deputy EDO Miraglia to the CNWRA offices in San Antonio, Texas, staff made a brief presentation on the PA approach adopted by the NRC and demonstrated the use of the TPA code and the JAVA-based TPA post-processor.

Interviews resumed for the open health-physicist position. Resumes continue to be gathered for other open positions.

In the next period, the staff will focus on (i) comparing the TSPA-VA and the TPA Version 3.2 code results; (ii) establishing a new schedule for the TPA Version 3.2 external review meeting; (iii) developing the content and structure of the sensitivity analysis report, which may include contributions from other KTIs; and (iv) preparing revision 2 of the IRSR.

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)

Detailed modeling continued for evaluating the effects of well characteristics and plume i dimensions on the accuracy of estimates of doses from the groundwater transport pathway.

Large-scale simulations with heterogenous material properties are working as intended and are nearing completion. Assuming no further complications, a report will be completed by the end of June 1999.

KTIinput to TSPA activitier this period included review of TPA sensitivity analysis results.

Emphasis was on assessing how the use of DOE Biosphere Dose Conversion Factors affect TPA results. Results will be included as KTI input to the TPA sensitivity analysis report during the next period.

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, were addressed and a camera-ready copy will be completed during the next period. 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 code is being investigated. This period, efforts were limited to initial planning and searching CNWRA QA and staff records for source code for the GENII dose assessment program.

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p In the next period, staff will complete the large-scale flow and mass transport calculations for the borehole dilution study. KTI input to the TPA sensitivity analysis will be completed.

A revised, camera-ready copy of the report Information and Analyses to Support Selection of Critical Groups and Reference Biospheres for Yucca Mountain Exposure Scenarios will be completed and delivered to address NRC comments. Staff will continue investigating the feasibility of an improved (stochastic) dose module for the TPA code. Additional efforts .

to discuss new tasking will continue. If the draft EPA Standard is published, staff will assist j the NRC with reviewing it and preparing comments.

1.10 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC) )

i Investigations continued on the process of drift seepage and capillary diversion of deep percolation away from open drifts. Staff have obtained an analytical solution for threshold percolation flux required to cause seepage into drifts that have a perturbed wall geometry

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described by a simple harmonic function. Preliminary indications are that drift wall shape has less effect on threshold flux than the effective alpha parameter of the formation at the ]

drift wall. An unstructured grid model of the cross-section of a circular drift has been J created and numerical simulations are being conducted to verify the analytical results. l l

Staff conducted a field survey of fractures, in collaboration with SDS staff, at Pavement 100 on Live Yucca Ridge. Spreadsheets and rose diagrams were created from field notes for comparison to designated cooling joints in the ESF. These data will be used to obtain statistical parameters to describe the frequency and preferred orientations of coolingjoints.

These parameters will be used to gain an improved understanding of the distribution of preferential zones of deep percolation in the UZ at YM.

Two-dimensional structural profile models constructed to interpret the results of a previously~ conducted ground magnetic survey in the vicinity of the C-Wells were interpreted. Based on these models, magnetic anomalies in this area are attributed to displacements of the reversely polarized Rainier Mesa and Tiva Canyon tuff units along the Bow Ridge, Paintbrush Canyon, and Midway Valley fault systems. The proposed NW.

trending, right-lateral, dip-slip AWF is not required for a good fit of the observed and calculated magnetic profiles. This result does not preclude the existence of the AWF, but suggests the fault does not significantly offset magnetic stratigraphy in this area. This structural modeling will be included in Modeling and Analysis of C-Well Tests-Letter Report currently being prepared. Also related to C-Wells work, two staff members participated in an Appendix 7 conference on C-Wells testing at the NTS.

Following the C-Wells Appendix 7 conference, staff participated in the Devil's Hole Workshop in Beatty, Nevada, and the Death Valt:y Workshop in Las Vegas, Nevada.

Although these workshops were not focused on YM characterization, several aspects of regional geology, geochemistry, and hydrogeology that are important to YM were discussed.

Staff participated in a NAS meeting on conceptual models of flow and transport in the fractured vadose zone. Experts in the fields of hydrogeology, geochemistry, and soil science 12

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l addressed field measurement and modeling of rapid preferential flow in the UZ and the need to resolve hypotheses explaining processes governing flow in these systems.

Staff also attended a DOE workshop on integration of geochemical, mineralogical, and hydrological data into the 3D inversion process of the mountain-scale UZ flow model. A  ;

large emphasis is being put on properly characterizing the flow and transport paths through

. the nonwelded units below the repository and evaluating the origin of the perched water bodies.

Work progressed on analysis of potential impacts of soil and vegetation responses to climatic change. The analysis suggests that, under climatic conditions that have a MAP twice present, a MAT 7 *C cooler than present, and present-day soil, then MAI increases by an order of magnitude. With the same climate change, however, with soils developed to a similar level seen at future-climate analog sites, the MAI increase is limited to a factor of 3 to 4 times present. Simple models bounding the rate of change of soil texture, soil depth, and vegetative changes are actively being developed to help refine MAI inputs to PA activities. In addition, surface and subsurface lateral flow for three hillslope configurations at YM are being analyzed to evaluate the effect of the assumption of 1D flow for shallow infiltration estimates. Initial estimates are that subsurface lateral flow is approximately 1 percent of the magnitude of surface runoff for the storms analyzed.

Previous estimates of MAI over the repository block were refined using a corrected procedure for fracture hydraulic conductivity. The new estimates use more appropriate weight estimates for fraction of fractures assigned as carbonate-filled, soil-filled, and unfilled. The preliminary results predict that, under current climate and soil conditions, repository MAI is 8.8 mm/yr. For current soil, twice the current MAP (MAP *2), and a 7 *C cooling, repcsitory MAIis 80 mm/yr. Using characteristics of Phinney Canyon soil (double thickness), MAP *2, and a 7 *C cooling, repository MAI is 29 mm/yr. Previously, the respective repository MAI estimates were 15,106, and 45 mm/yr. The difference is that units with a'small amount of soil-filled fractures (e.g.,10 percent) had previoust/ used zero for the soil-filled fraction, skewing the MAI estimates upward. Note that the new MAI estimates also include a heuristic algorithm for the reduction effect of vegetation. Also note that using a 30-m pixel (the Flint resolution) instead of the 7.5-m pixel as in the above estimates, present-day MAI is 5.6 mm/yr over the repository. The newer estimates provide a better fit to available data and are closer to DOE estimates, while still nominally higher than DOE calculations.

Staff continued the characterization and modeling of flow paths below the repository. The analysis incorporates geochemical, mineralogical, and hydrological data to better understand the flow paths through the variably altered, partially welded to nonwelded CHn.

Preparation ofInfiltration Abstractions for Shallow Soil Over Fractured Bedrock in a Semi-Arid Climate-Journal Paper (proposed in the period 6 PMPR as a new deliverable), is in the CNWRA review process. Brome grass can readily be incorporated into the vegetation model for infiltration; however, its larger impact will probably be on regional recharge rates for the SZ.

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Formal Review of DOE SZ Studies-Letter Report was submitted. This report, which reflects the current CNWRA understanding of DOE SZ flow and transport modeling at YM, will be used to support preparation of Input to USFIC IRSR, Revision 2-Letter Report.

Findings of the CNWRA/NRC working group on SZ flow are being documented in Input to NRC Working Group on Viable SZ Conceptual Flow Models, presently in preparation.

In the next period, USFIC activities will include (i) preparation of Input to NRC Working

' Group on Viable SZ Conceptual Flow Models, (ii) preparation of Modeling and Analysis of C-Well Tests-Letter Report, (iii) continued investigation of models for seepage and dripping in underground cavities, (iv) continued development of future estimates of percolation, (v) panicipation in the development of the YMRP, and (vi) preparation ofInput to USFIC IRSR, Revision 2-Letter Report.

1.11 Radionuclide Transport (RT)

Staff participated in the 8th European Commission Natural Analogue Working Group Workshop, held March 23-25,1999, in Strasbourg, France. A presentation titled Uranium chemistry and isotopy in waters and rocks at PeHa Blanca was made in a special session on the PeSa Blanca natural analogue. The talk was posed as a history of uranium mobilization and transport based on CNWRA chemical and isotopic studies and, in combination with two other CNWRA presentations, stressed applications to PA. CNWRA staff spoke with meeting participants about the potential for initiating an international study program at PeHa Blanca, and with DOE participants about their planned work at the site. Two papers were presented at the Symposium on Reactivity and Dynamics of Mineral Surfaces, one of the numerous symposia at the 217th ACS national meeting that was held on March 21-25, 1999,in Anaheim, California.The two papers were titled Molecular Dynamics Simulation of Uranyl Adsorption on Quartz Surfaces, and Experimental and Modeling Studies of Uranyl Adsorption onto Binary Mixtures of Silicate Minerals.

CNWRA technical and programmatic reviews were conducted for Stochastic Analysis of Fracture Transport-Journal Paper (proposed as a new deliverable in the PMPR for period 6). Work was initiated using stochastic analysis to investigate alternative models of RT through alluvium near YM. The stochastic analysis takes into account spatial heterogeneities in chemical and hydrological properties, and relies on existing CNWRA data on spatial variability in sorption properties.

The database for the geochemical' code PHREEQC (version 1.6) was modified to include radioclement thermodynamic data consistent with the EQ3 and MINTEQA2 (version 3.11) computer codes. Benchmarking between the codes PHREEQC and MINTEQA2 was performed to compare the results of U and Np speciation calculations as a function of pH and carbon dioxide partial pressure at 25 *C.The resulting calculated speciation generally compares well between the two codes. PHREEQC may be used to investigate mixing and water-rock interaction between well locations as a means of constraining plausible flow paths in the SZ.

14

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.. .. -.... .. . U -

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As part of the ongoing work to investigate Np sorption on calcite, preparation of reagent calcite continued. Natural calcite samples have been received and will be processed by crushing, sieving, and collecting a 60-200 mesh size fraction. The natural samples will then  !

be processed to remove fine particles and stabilize the surface ofeach grain by equilibrating the calcite in 0.02 M NaHCO3.

Staff continued the uranium sorption experiments on mixed minerals (clinoptilolite and  !

quartz) during this period. Final experiments involving U sorption on clinoptilolite/ quartz mixtures under conditions in equilibrium with CO 2and at less than atmospheric CO 2 conditions were initiated. Capped sorption (low CO2 Partial pressure) experiments on 1 clinoptitolite and chemical pretreatment of quartz for sorption experiments are contineing to investigate the effect of trace iron oxyhydroxides on sorption.

Twenty well cutting samples (one sample every 10 ft from the 200 ft to 400 ft depth interval) from well NC-EWDP-2d of the Nye County monitor well program were received during this period.

Staff were involved in preparing the YMRP. Activities included mapping the acceptance criteria from the RT IRSR onto the proposed outline for the YMRP.

Efforts continued to establish consulting agreements to support augmented work on molecular dynamics simulations and stochastic fracture transport modeling, and to initiate work on ion exchange modeling with a current CNWRA subcontractor.

In the next p' eriod, staff will continue sorption experiments on alluvium minerals, including calcite. Sorption experiments on clinoptilolite/ quartz mixtures will be completed, and the experirnents to evaluate the effects of trace iron oxyhydroxides on uranium sorption will  ;

continue. Well cuttings from NC-EWDP-2d will be examined by optical microscopy, and samples will be selected for analysis. CNWRA and NRC staff will continue preparation of Input to RTIRSR, Revision 1-Letter Report (MM 1402-871-930). The geochemical code PHREEQC will be placed under CNWRA configuration control and simulation of mixing and water-rock interaction in the SZ will begin. Staff will assist in the PA abstraction process and perform sensitivity analyses using the TPA Version 3.2 code to investigate the effects on performance of correlation of sorption parameters.

1.12 Tank Waste Remediation System (TWRS)

In subtask 1.2, staff continued work on the draft report titled Low-Activity Waste Auxiliary Support Systems II-Systems Hazard & Safety Issues Report forTWRS-Letter Report.The current scheduled delivery date is April 30,1999. Also, staff started work on a presentation on the Vitrification of Radioactive Wastes to the Regulatory Unit of the Department of Energy. The presentation will consist of two 4-hr sessions and will summarize the work conducted under this subtask in the last two years.

In subtask 1.6, revisions continued on Chemistry of Hanford Tank Waste Pretreatment Technology to address NRC staff comments on a draft version. The draft final report is 15

currently due May 28,1999, and a final version, with changes to address additional NRC comments, is scheduled for submission July 30,1999.

In subtask 2.1, NRC comments on the Design Safety Features deliverable: Hydrogen Control in High-Level Waste Storage Tanks were incorporated and a revised repo.c was delivered on April 9,1999. Also, the CNWRA review comment report on the BNFL,Inc.

Design Safety Features was delivered on March 31,1999.

In subtask 2.2, NRC staff comments were incorporated in the report titled Integrated Design Inspection Program for Radioactive Wr.ste Treatment / Nuclear Material Production Facilities and the fina.1 report was deliven:d on March 25,1999. Also, staff has continued to work on Quality Assurance Inspection Program for Radioactive Waste Treatment /

Nuclear Material Production Facilities. A draft report will be delivered by e-mail for review prior to scheduled delivery on May 28,1999.

In the next period, in subtask 1.2, the staff will complete editorial, technical, and programmatic reviews of the report titled Low-Activity Waste Auxiliary Support System II-Process System Hazard and Safety Issues Report for TWRS-Letter Report and continue preparing a presentation on the Vitrification of Radioactive Wastes to the Regulatory Unit of the Department of Energy. In subtask 1.6, the staff will incorporate NRC comments on the pretreatment report. In subtask 2.2, the staff will continue work on Quality Assurance Inspection Program for Radioactive Waste Treatment / Nuclear Material Production Facilities.

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

Along with interactions between the NRC and the CNWRA staffs, the CNWRA staff continued to assist the NRC staff to prepare TMI-2 ISFSI Materials License No.

SNM-2508. This license was issued on March 19,1999.

In the next period, TMI-2 ISFSI staff plans to provide input to the NRC lessons leamed process.

1.14 Dry Transfer System (DTS)

The development of the second round RAI continued. A report will be submitted during the next period as Second Round Request for Additional Information, DTS-Draft Letter j Report. Preparation of an outline of the SER and the development of the SER continued concurrently during this period.

In the next period, DTS staff plans to complete the development of the seco S round RAI, prepare the outline of the SER, and develop the SER.

I 16  ;

4

)

1 L_ - d

1 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. A technical l direction to revise the computer code RISKIND was received and this work was initiated. f 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 revise i the computer code RISKIND while awaiting instruction to revise the draft AR.

1.16 Private Fuel Storage Facility (PFSF)

The review and evaluation of the PFS response to the NRC second round RAI, review of site characterization reports, preparation of draft SER, and revision of the NRC draft position on five Group I contentions continued during this reporting period. Several NRC/PFS/CNWRA teleconference meetings took place to discuss the deficiency of PFS site characterization data.

In the next period, the staff plans to review the PFS response and site characterization reports, prepare the draft SER, and assist the NRC staff on ASLB hearing related activities.

1.17 Savannah River Site Aluminum Based Spent Fuel (SRSASF)

Revisions to the letter report, Review of Criticality Evaluation of Direct Co-Disposal and Melt-Dilute Fuels were completed. The revised report was accepted by the NRC staff.

The staffinitiated review of the DOE reports on creep and dissolution of Al-based spent fuel towards completion of the report, Review of the U.S. Department of Energy Preliminary Evaluation of Aluminum-Based Spent Nuclear Fuel-Final Report.

In the next period, further review of the DOE reports will be conducted.

2 MANACEMENT ISSUES Spending continues to trail the revised plans, although it has increased substantially relative to last year. A detailed quarterly evaluation of costs and estimate to completion will be coordinated with NRC management next period.

3 MAJOR PROBLEMS None to report.

4

SUMMARY

OF SCHEDULE CHANGES No schedule changes for IMs were made this period. Completed deliverables are noted on table 2.

17

5

SUMMARY

OF FINANCIAL STATUS Table 3 summarizes the CNWRA financial status in the context of authorized funds. Total commitments are $558,410.The appendix lists planned and actual costs to date, as well as variances between these, without allowance for fee, on both a per-period and a cumulative basis. These data do not include commitments. Pertinent financial information is provided for the DWM JC, including COPS and ten KTIs, TWRS JC, TMI-2 ISFSI JC, DTS JC, 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 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, and dedicated recruitment continues.

Period 7 FY1999 CNWRA composite expenditures fell 1.7 percent from the previous period, and this aggregate of all JCs was underspent by $1,266,627 or 17.3 percent. When comparing period 7 with last period, the DWM, DTS, CISF, and SRSASF JCs evidenced higher spending levels while the TWRS, TMI-2 ISFSI, and PFSF JCs showed a lower level.

The DWM JC was underspent by $ 1,040,520 or 16.5 percent. Overall expenditures increased about 1.0 percent from the previous period as costs rose in the ENFE, CLST, RDTME, USFIC, and RT KTIs but declined in COPS and the IA, SDS, TEF, TSPA, and ARDR KTIs. Costs to date are 29 percent above those a year ago, and period 7 costs are 13 percent greater than the same period last year. The FY1999 budget is 24 percent greater than FY1998. Spending on the augmented scope of work has not mer expectations in all areas. Notwithstanding the aggressive recmitment of core staff, unexpected attrition has precluded attainment.of the target staffing levels at this time.

Furthermore, the engagement of consultants and subcontractors has been delayed by legal and procedural restraints. 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 will be provided to NRC next period.

The TWRS JC was underspent by $154,526 or 28.0 percent. Although spending has decreased substantially for two successive periods, staff have delivered and are working on several reports with SwRI and consultant support. Nevertheless, given minimal tasking in the reactive tasks, which are heavily funded this year, spending is likely to fall short of the plan at the year end.

The TMI-2 ISFSI JC was overspent by $6,356 or -4.6 percent. As expected, spending declined ~

significantly as limited staff effort focused on assisting the NRC staff in preparation of the TMI-2 ISFSI Materials License No. SNM-2508. About 99.5 percent of this fiscal year's tasking was completed during the first seven periods.

The DTS JC was underspent by $9,547 or 8.4 percent. Expenditures, again, increased markedly from the previous period, consistent with activities related to development of a second round RAI, and preparation of the SER.

18

e l

The CISF JC was underspent by $45,341 or 41.1 percent. Notwithstanding an increase in the l cumulative variance, spending rose compared with the previous period. Staff pursued the detailed technical review of the Topical Report on HI-STAR /HI-STORM cask system deployment at high-seismic sites and revision of the computer code RISKIND. Staff awaits NRC instmction to revise the draft AR.

The PFSF JC was overspent by $13,871 or -16.0 percent. Expenditures decreased from the last period, in addition to staff preparing the draft SER, they engaged in review and evaluation of the PFS response to the NRC second round RAI, review of site characterization reports, and revision of the NRC draft position on five Group I contentions.

The SRSASF JC was underspent by $44,804 or 73.9 percent. Spending rose from last period with the incorporation of NRC staff comments on a previously delivered report and continuation of efforts related to review of other DOE documents.

Expenditures on SwRIlabor, consultants, and subcontractors as a proportion of composite spending on all JCs were 21.1 percent. Expense of consultants and subcontractors as a fraction of composite spending on all JCs was 10.9 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 the resignation of a health physicist and addition of a mechanical engineer. The available pool of approved consultants and subcontractors is 55.

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

DWM JC The DWM JC cumulative cost variance was 16.5 percent. Expenditures in this JC increased by about 1 percent compared with period 6. Specific explanations for over/ underspending for COPS and each KTI follow.

The cost variance for COPS was 19.0 percent: 17.7 percent for the Management, Planning, and Computer Support subtask (158) and 24.2 percent for the QA subtask (159). Spending this period in subtask 158 fell relative to last period but rose for subtask 159. Labor costs in subtask 158 decreased about 18 percent from last period, primarily the result of staff attrition; however, such costs increased approximately 11 percent in subtask 159. Other Direct Costs declined in subtask 158 from the previous period, but remained basically the same as last period in subtask 159. In the next period, spending in subtask 158 is expected to be less than estimates, as staff is recmited in the financial and computer-related areas. Consultants will be used in the IMS area to mitigate stafflost through attrition and support the revision of the CNWRA LAN and databases. CNWRA management will continue to encourage eligible staff to participate in professional development activities. In subtask 159, spending should increase as staff prepares for the annual QA audit. The staff is finalizing preparations for training of the NRC technical staff in accordance with the augmented scope of work in subtask 159. Actual spending is expected to be about 10 percent less than the approved spending plan for FY1999.

19

The cost variance for the IA KTI was 14.2 percent. Spending fell relative to last period, with the variance being primarily due to the spending plan augmentation that occurred in period 6.

Expenditures this period are consistent with expected spending in the next few periods. Total expenditures may exceed the spending plan by less than 10 percent for the remainder of FY1999.

The cost variance for the SDS KTI was 13.2 percent. Expenses declined from the previous period.

The variance is due to the spending plan augmentation that occurred in period 6. 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.

The cost variance for the ENFE KTI was 14.5 percent. Spending rose this period, thus reducing the 4 percentage cumulative variance, a trend that continues from period 3. Further reductions in variance are expected as costs from new work related to Pe Aa Blanca investigations are posted to the account.

The largest uncertainty in the future spending for the ENFE KTI remains execution of the ]

subcontract with the University of Aberdeen for cement-related experiments. Aggressive efforts continue toward initiating this work. Aggregate spending for the remainder of FY1999 may be I slightly less than the currently approved spending plan.

The cost variance for the CLST KTI was 0.5 percent. The rate of spending increased compared to period 6 because several new corrosion tests were initiated. It is anticipated that the rate of spending will remain slightly above the budgeted level for the rest of the FY as a result of augmented work and associated materials expenses. 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 2.2 percent. Spending declined substantially and the cumulative variance rose slightly during this period; this small underspending is due to lagging charges from consultants and subcontractors and delay in starting the TEF KTI work by Columbia University. It is expected that Columbia University willinitiate the TEF KTI activities during period

- 8. Future actual expenditures are expected to continue following the budget for this KTI.

The cost variance for the RDTME KTI was 22.2 percent. Although spending increased,it has not yet reached the augmented budget level. Consequently, the cumulative variance also rose during this period. This cost underrun is due to temporary assignment of staff to other tasks and lagging charges from consultants and subcontractors. This cost underrun is expected to decrease during the remaining periods of FY 1999 due to a new hire and reassignment of staff to this KTI activities. The FY1999 total expenditures are expected to be slightly less than the FY1999 allocation.

The cost variance for the TSPAI KTI was 24.2 percent, a slight decrease in percentage terms from the previous period. Although the departure of one PA staff member early in Period 8 will lead to a temporary increase in underspending, this underspending should be mitigated by the development of the TPA post-processor by analysts primarily from other SwRI divisions. Expected spending is anticipated to be about 15 percent less than planned expenditures at year end.

The cost variance for the ARDR KTI was 54.0 percent. Spending declined, relative to the previous period, and the cumulative variance rose. There is still no indication the draft EPA Standard will be released for review in the coming months, so underspending will continue indefinitely. Potential new tasks for this KTI were proposed during period 7 and will be discussed with the NRC PM 20 T

during the next period. Nevertheless, aggregate spending is anticipated to be nearly 45 percent below the approved spending plan for FY1999.

The cost variance for the USFIC KTI was 4.5 percent. Along with an increase in per period spending, the decrease in cumulm >e variance from period 6 was caused by posting a backlog of consulting costs to this account. Ir .he near periods, the variance is expected to increase somewhat and then to diminish to near zero by year end.

l The cost variance for the RT KTI was 27.5 percent. Along with an increase in per period spending, l the decrease in percentage variance relative to period 6 spending resulted as consulting and travel commitments were posted. The addition of a laboratory technician during this period also helped to reduce the variance. Anticipated invoices from ongoing and planned work by consultants should continue to reduce the variance in coming periods. 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 28.0 percent. It is anticipated that spending will increase slightly in the next period. The staff effort is being augmented through the judicious use 1 of consultants and SwRI staff to achieve timely completion of milestones. I The cost variance for the TMI-2 ISFSI project was -4.6 percent. This overspending resulted from concentrated efforts during the first six periods of FY1999 to prepare the draft and final SER and to assist the NRC staff to prepare TMI-2 ISFSI Materials License No. SNM-2508. Approximately 99.5 percent of the FY1999 tasking within the TMI-2 ISFSI project was completed during periods 1-7 with a spending of about 98.5 percent of the FY1999 allocation. Thus, the FY 1999 total expenditures are within the FY1999 allocation. l The cost variance for the DTS project was 8.4 percent. Despite an increase in spending this period compared to the last six periods, this cost undermn is primarily due to the time needed to accelerate the FY1999 DTS activities based on the revised SFPO Operations Plan with increased funding for the DTS project. Expenditures are expected to increase and remain close to the augmented FY1999 allocation as a result of developing the second round RAI, and preparing an outline and a draft of the SER through utilization of more CNWRA and SwRI staff, including a new hire. The FY1999 total expenditures are expected to converge to the FY1999 allocation.

The cost variance for the CISF project was 41.1 percent. Spending this period is significantly higher compared to the previous four periods. Expenditures are expected to increase further to review the HI-STAR /HI-STORM cask systemTopical Report, revise the computer code RIS KIND, 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 -16.0 percent. Although the per period expenditures during the next few periods will be similar to that of period 7, the cost overrun will continue for the next few periods as the staff review the PFS response, study the site characterization reports, prepare the draft SER, and revise the NRC draft position on five Group 1 contentions. The FY1999 total expenditures are expected to converge to the FY1999 allocation for this project.

The cost variance for the SRSASF was 73.9 percent. Spending increased from the previous period and is expected to continue as the staff reviews additional DOE reports in the next period. The large 21

variance does not reflect an anticipated substantial decrease in the budget for the project. However, with the changes in the deliverable described in Section 1.17 and the more limited scope of the DOE reports that have been received, it is anticipated that the new budget will be sufficient to complete the tasks.

l I

l 22 l

l

Table 1. CNWRA Core Staff-Current Profile and Hiring Plan * (Period 7)

Positions Open EssertheEsperience Current No. Professional Staff FY1999 ADMINISTRATION 4 H GARCIA. W. PATRICK.1 RUSSEtt B S AGAR CHEMICAL PROCESSING 2 VJAIN D.DARUWAllA ENGNG / PHYS. CHEM CODE ANALYSIS /DEVELDPMENT - 2 R JANETZKE. R MAR 11N 1 DATA MANAGEMENT / PROCESSING. I P.MALDONADO INCLUDING ITN ANCIAL DOSE / RISK / HAZARD ANALYSIS 0 1 E!ECTROCHEMISTRY l G CRAGNOLINO ENGINEERING 2 R.CHEN, G.Of0EGBU i GEOtDGYNIEOLOGICAL ENGNG ENVIRONMENTAL SCIENCES 1 P LaPLANTE GEOCHEMISTRY 7 P.BER1ETil, LBROWNING, W. MURPHY, R.PABAIAN, E PEARCY. J PRIKRYL D. TURNER GEOHYDROLOGY/HYDROGEOLOGY 5 DEARRElk R.FEDORS, R.GRFIN, M.H11L J WIN 1ERLE GEOLOGY 3 P LAFEMINA. LMcKAGUE. M MIKLAS HYDROLDGIC TRANSPORT 3 A. ARMSTRONG. D HUGHSON. S PAINTER I INFORMATION MANAGEMENT 0 i SYSTEMS MATERIAL SCIENCES 4 S BROSSIA. D DUNN. Y.M PAN. N.SRIDH AR 2 MECHANICAL. I D.GtTTE INCLUDING DESIGN & FABRICAllON MINING ENGINEERING 1 5-M.HSIUNG NUClIAR ENGINEERING 1 M JARZEMB A OPERA 110NAL HEAL 1H PHYSICS 1 J.WELDY I PERIORMANCE ASSESSMENT 3 S.MOHANTY, O. PENSADO-RODRIGUEZ. 2 G.WTI%1 EYER QUA11TY ASSURANCE I B MABRTTO RADIOISOTOPE GEOC HEMISTRY I D.PICKFTT ROCK MECHANICS, 2 A.CHOWDHURY, A.GHOSH INCLUDING CIVIL /STRUC ENGNO SOURCE-11ERM/SPEffr FUEL DEGR AD. O I STRUCIURALGEOLDGY/ 3 D.FERRIL1, D. SIMS, J.STAMATAKOS SEISMO-111Cf0NICS SYSTEMS ENGINEERING l P.MACKIN VOLCANOLOGY /lGNEOUS 2 C.CONNOR, B. Hill PROCESSES TOTAL $2 11

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Funds Funds Funds Project Nanws Authorized Costed to Date Uncosted Commitments COPS 3,476.342 2.407,901 1,068,441 1,432 IA ' l.345,062 1.039.798 305,264 120,769 j SDS 1,825,699 1,376,616 449,083 36.687 ENFE 1,781,331 1,182,682 598,649 93,304 CLST I,704,818 1,277,158 427,660 12,295

'!I!F 1,322,606 939,533 383,073 5,648 RDTME 1,319.682 772,736 546,946 21,988 TSPAl 3,577,966 2,302.116 1,275,850 45,232 ARDR 697,208 293,160 404,048 4.819 USFIC 2.288,030 1,620,169 667,862 30,243 RT 1.369,634 774,753 594.881 90,588 DWM Costs 20,708,378 13,986,621 6,721,757 DWM Award Fee 1,196,006 493.569 702,437 DWM Base Fee 828,335 544,781 283,554 TOTAL DWM 22.732,719 15.024,972 7,707.748 463.005 TWRS Costs 1,533,378 1,179,660 403.718 1,922 TWRS Award Fee 93.654 46,214 47,440 TWRS Base Fee 63,335 48,156 15,179 EAL'lWRS 1,740,367 1.274,030 466.337 1,922 TMI 2 ISFSI SAR Costs 282,197 280,953 1,244 1,341 TMI 2 ISFSI SAR Award Fee 7,711 7,512 15.223 TMI.2 ISFSI Base Fee 11,288 10.991 297 TOTAL TMI-2 ISFSI S AR 308,708 299,655 9.053 1.341 DTS Costs 309,952 240,257 69,695 36,741 DTS Award Fee 19,480 7,924 11.556 DTS Base Fee 12.398 9.616 2.782 TOTAL DTS 341,830 257,797 84,033 36,741 CISF Costs 409,053 287,481 121,572 19,140 CISF Award Fee 24,338 12.848 11.490 CISF Base Fee 16,362 11,600 4,762

'IOTAL CISF 449,753 311,929 137,824 19,140

,PFSF Costs 275,068 215,807 59,261 36,261 PFSF Award Fee 16,185 6,827 9,358 PFSF Base Fee 11,003 8,831 2,172 TOTAL PFSF 302,255 231,465 70.791 36,261 SRSASF Costs 113,185 82,094 31.091 0 SRSASF Award Fee 7,110 3,992 3,118 SRSASP Base Fee 4,527 3,532 996

'IUTAL SRS ASF 124,823 89.618 35,205 0 Grand Total 26,000,456 17,489,466 8.510,990 558,410 Note: All authorized funds have been allocated through modification #127, Funds costed to date for each award fee program represent award fee for FY1998. Funds uncosted for ea:h award fee program represent award fee reserved from last authorizations based on Operations Plans for FY1999, 25

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