ML20249C519
| ML20249C519 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 06/19/1998 |
| From: | CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES |
| To: | NRC |
| Shared Package | |
| ML20249C511 | List: |
| References | |
| CON-FIN-D-1035, CON-FIN-J-5164, CON-FIN-J-5186, CON-FIN-J-5190, 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-98-9, NUDOCS 9806300227 | |
| Download: ML20249C519 (39) | |
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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 May 9,1998 - June 5,1998 PMPR No. 98-9 June 19,1998
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TABLE OF CONTENTS Section ' Page TABLES ......... ... ... .... . . ... .. .. . ... . .. iv i ABBREVIATIONS . . . . . . . . . .. . . ..... . .. ... . . .. .. v l
1 EXECUTIVE
SUMMARY
-PERIOD 9 . . . . . .. .. .. . .... . . xi 1 TECHNICAL . . . . . . ...... .. . . .. .... . .. . ... . .. 1 1.1 CNWRA Operations (COPS) . . . .. . .. . . .. . .... . .. I 1.2 Igneous Activity (IA) . .. ... ......... . . ... ...... .. .2 1.3 Structural Deformation and Seismicity (SDS) .. ......... . ..... . ...... 3 1.4 Evolution of the Near Field Environment (ENFE) . . . . . . . . . . . . . ... ... .. 4 1.5 Container Life and Source Term (CLST) .... . ...... .. .. ... ....... 5 1.6 Thermal Effects on Flow (TEF) . . .... .. .. ........ . .... .... .. 5 1.7 Repository Design and Thermal-Mechanica' Effects (RDTME) . . .. . .... 6 1.8 Total System Performance Assessment and integration (TSPAI) . . . . . . 7 1.9 Activities Related to Development of the NRC High-Level Waste Regulations (ARDR) . . .. .. . ........ ........ ..... . ........ 8 1.10 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC) ......... 9 1.11 Radionuclides Transport (RT) . . . . . . . . . . ... .... ........ .. .. . .... 11 1.12 Tank Waste Remediation Systems (TWRS) .. .. .... . . .. . ... 11 1.13 Three Mile Island Unit 2 Independent Spent Fuel Storage Installation (TMI-2 ISFSI) . . . . . . . . .. .......... . .. . .... .... . 12 1.14 Dry Transfer System (DTS) . . . . . . . . . . . .
. ........ . ...... . ....... 12 1.15 Centralized Interim Storage Facility (CISF) . ... . ... . . .. . . . 12 1.16 Private Fuel Storage Facility (PFSF) . . .. .... . ..... . .... .... 13 1.17 West Valley Demonstration Project (WVDP) . . . . . . . . . . . ..... . ..... 13 1.18 Savannah River Site Aluminum-Based Spent Fuel (SRSASF) . . . . . . . . . . . . . . 13 2 MANAGEMENT ISSUES . . . . . . . . . . . . . . ..... .. ........ . .. .... .. .... 13 3 MAJOR PROBLEMS ....................... . .. ..... ............ 13 4
SUMMARY
OF SCHEDULE CHANGES . . . ................ ......... ...... 13 5
S UMMARY OF FINANCIAL STATUS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 APPENDIX-Planned and Actual Costs, and Cost Variances Period 9-FY98 iii
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TABLES Table 'Page-1 CNWRA Core Staff-Current Profile and Hiring Plan * (Period 9) . . . . . . . . . . . . . . . . . . . . 17 2 Summary of Schedule Changes (Period 9) . . . . . . . . . . . . . . . . . . . . .... ...... ....... 18 3 Deliverables (Period 9) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 4 Financial Status (Period 9) . . . . . . . . . . . . . . . . . .... ............................. 21 5 Private Fuel Storage Facility License Fee Cost Recovery Status (Period 9) . . . . . . . . . . . . . 22 iv
S ABBREVIATIONS ID One-Dimensional CEC Commission of the European 2D Two-Dimensional Communities 3D Three-Dimensional CFD Computational Fluid Dynamics AA Atomic Absorption CFR Code of Federal Regulation AAI Average AnnualInfiltration CIAC ComputerIncident Advisory Capability ACD Advanced Conceptual Design CISF Centralized Interim Storage Facility ACF Alumina (in excess of alkali feldspar), CLST Container life and Source Term Calcium Oxide. Ferromagnesian oxide CM Configuration Management ACNW Advisory Committee on Nuclear Waste CNWRA Center for Nuclear Waste Regulatory ACRS Advanced Computer Review System Analyses ADAMS Agencywide Documents Access and COI Conflict of Interest Management System COPS CNWRA Operations AECL Atomic Energy of Canada Limited CPP Cyclic Potentiodynamic Polarization AES Atomic Emission Spectrometry CQAM CNWRA Quality Assurance Manual AGU American Geophysical Union CRO Center Review Gmup Al Administrative Item CRM Corrosion Allowance Material AL13 Apache leap Test Site CRWMS Civilian Radioactive Waste AML Areal Mass Loading Management System f ANS American Nuclear Society CSCS Constrained Stochastic Climate i ANSI American National Standards Institute Simulator AO Annotated Outline CSH Calcium Silicate Hydrate f
AP Administrative Procedure CSPE Corrosion Science and Process s APB Acid Producing Bacteria Engineering j AR Assessment Report DAS Data Acquisition System l ARDR Activities Related to Development of DBE Design Basis Event )
the NRC High-Level Waste Regulations DC Division of Contracts ASCE American Society of Civil Engineers DCAA Defense Contract Aud;t Agency ASCII American Standard Code for DCB Double Cantilever Beam Information Interchange DCF Dose Conversion Factor ASME American Society of Mechanical DCM Dual Continuum Model j Engineers D&D Decommissioning and Decontamination I ASTM American Society for Testing and DECOVAIIX Development of Coupled Models and Materials lheir Validation Against Experiments ASU Arizona State University in Nuclear Waste Isolation ATDTS Automated Technical Data Tracking DEIS Draft Environmental Impact Statement j System DEM Digital Elevation Model !
BEG Bureau of Economic Geology DF Dilution Factor .
DFD Basis for Design DFCSS Division of Fuel Cycle Safety and BM l Bare Mountain Safeguards '
BMF Bare Mountain Fault DIE Determination ofimportance BNFL British Nuclear Fuels Limited Evaluation BIP Branch Technical Position DIMNS Division ofIndustrial and Medical CAI Color AlterationIndex Nuclear Safety CAM Corrosion Resist Material DKM Dual Permeability Model CAR Corrective Action Request DLO Digital Line Graph CCDF Complementary Cumulative DLM Diffuse layer Model Distribution Function DNAG Decade of North American Geology CCL Commitment ControlImg DNFSB Defense Nuclear Facilities Safety Board
. CCM Constant Capacitance Model DOE U.S. Department of Energy CD-R CDROM Recordable DOE-DP DOE Defense Program CDF Cumulative Distribution Function DOE-RU U.S. Department of Energy Regulatory CDM Compliance Determination Method Unit CDOCS Consolidated Document Management DRA Division of Regulatory Applications System DST Drift Scale Test CDROM Compact Disk Read Only Memory DIED DigitalTerrain Elevation Data CDS Compliance Determination Strategy DTS Dry Transfer System CDTS Commission Decision Tracking System DWM Division of Waste Management CEB Center for Environmental Biotechnology EBS Engineered Barrier System V
l ABBREVIATIONS (cont'd)
EBSER Engineered Barrier System GTFE Great Tolbachik Fissure Eruption Experimental Research GUI Graphics User Interface EBSPAC Engineered Barrier System GWSI Groundwater System Integration Performance AssessmentCode GWTT Groundwater Travel Tune ECM Equivalent Continuum Model HLUR High-Level Waste and Uranium EDO office of the Executive Director for Recovery Projects Branch Operations HLW High-Level Waste EDX Energy-Dispersive X-Ray Spectroscopy HRTEM High-Resolution Transmission Electron EIS EnvironmentalImpact Statement Microscopy EM Element Manager IA Igneous Activity EMPA Electrcn MicroProbe Analysis IBM International Business Machines ENE East-Northeast ICP Inductively Coupled Plasma ENFE Evolution of the Near-Field ICPP Idaho Chemical Processing Plant Environment IDLH Immediately Dangerous to Ijfe and ENGB Engineering and Geosciences Branch Health EnPA Energy Policy Act of 1992 IHLRWMC International High-Level Radioactive ENS European Nuclear Society Waste Management Conference and EPA U.S. Environmental Protection Agency Exposition EPR Electrochemical Potentiokinetic IM Intermediate Milestone Reactivation IME Industrial Mobilization Exemption EPRI Electric Power Research Institute IMS Information Management Systems EQA External Quality Assurance INEEL Idaho National Engineering and EROS Earth Resource Observation System Environmental Laboratory ESF Exploratory Studies Facility INETER Instituto Nicaraguense de Estudios ESP Environmental Simult. tion Program TERritoriales EW East-West INTRAVAL International Code Validation EXAFS Extended X-Ray Absorption Fine I/O Input / Output Structure IPA Iterative Performance Assessment FAC Favorable Condition IR&D Internal Research & Development FCRG Format and Content Regulatory Guide IRIS Interim Records Information System FDSHA Fault Displacement and Seismic Hazard IRM Office ofInformation Resources Analysis Management FEHM Finite Element Heat and Mass Transfer IRSR Issue Resolution Status Report FEM Finite Element Method ISA Initial Safety Analysis FEP Features, Events, and Processes ISFSI Independent Spent Fuel Storage FFRDC Federally Funded Research and Installation Development Center ISM Integrated Site Model FFT Fast Fourier Transform IVM Interactive Volume Modeling F1E Full-Time Equivalent IWPE Integrated Waste Package Expenments i FIP File Transfer Protocol JC Job Code FY Fiscal Year JPL Jet Propulsion Laboratory FYID Fiscal Year-to-Date JRC Joint Roughness Coefficient GDP Ghost Dance Fault K"Il Key TechnicalIssue GEM General Electrochemical Migration KTU Key Technical Uncertainty GEOTRAP Geologic Transport of Radionuclides LA License Application Predictions LAAO License Application Annotated Outline GERT General Employee Radiological LAN Iocal AreaNetwork Training LANL Ies Alamos NationalLaboratory GET General Employee Training LARP License Application Review Plan GFM Geological Framework Model LAW Iow-Activity Waste GHGC GeoHydrology and Geochemistry IENL Lawrence Berkeley National Laboratory GIA GeneralizedImportance Analysis LBT Large Block Test GIS Geographic Information System LHS Latin Hypercube Sampling
'GLGP Geology and Geophysics LITC Imckheed Information Technology GPS Global Positioning Satellite Company GROA Geologic Repository Operations Area LLNL Lawrence livermore National GS Geologic Setting Laboratory GSA Geologic Society of America LLW Iow-Level Waste vi
ABBREVIATIONS (cont'd)
LMAES
- Ieckheed Martin Advanced PAHT Performance Assessment and Environmental Systems Hydrologic Transport LSS Licensing Support System PASP Performance Assessment Strategic Plan LSSPP Licensing Support System Pilot Project PC Personal Computer LSSTB Licensing Support System Test Ded PC/TCP Personal Computer / Transmission LWR Light Water Reactor Control 6tncol Ma Million Years Ago PDF Probability Distribution Function MC Monte Carlo PDR Public Docurrent Room METRA Mass and Energy Transport PEL Permissible Exposure Limit MGDS Mined Geologic Disposal System PEM Program Element Manager MH Mechanical 4 hydrological PER Relicensing Evaluation Report MIC Microbially Influenced Corrosion PFD Probabilistic Fault Displacement MINC Multiple Interacting Continua PFDHA Probabilistic Fault Displacement MIT Massachusetts Institute of Technology 18Azard MM Major Milestone PFS Private Fuel St(rage MO Management and Operations PFSF Private Fuel Storage Facility MOU Memorandum of Understanding PHA Preliminary Hazard Analysis MPC Multi-Purpose Canister PI PrincipalInvestigator MRS Monitored Retrievable Storage PMDA Program Management, Policy MSS MultiSpectral Scanner Development and Analysis Staff MTU Metric Ton of Uranium PMPR Program Manager's Periodic NAS National Academy of Sciences Report NAWG Natural Analogue Working Group PMT Photo-Multiplier Tube NCR NonConformance Report PNNL Pacific Northwest National Laboratory NEA Nuclear Energy Agency PO Project Officer NFS Network File Server PPA Proposed Program Approach NIOSH NationalInstitutes of Safety and Health PPE Prepassivated Platinum Electrode NIR Near-Infrared PRA Probabilistic Risk Assessment NIST NationalInstitute of Standards and PRT Peer Review Team Technology PSAG bbabilistic System Assessment Group NMSS Office of Nuclear Material Safety and PSHA Nbabilistic Seismic Hazard Analyses Safeguards l'ITE Polytetrafluoroethylene NNE North-Northeast PTo Paintbrush Nonwelded hff NNW North-Northwest PVHA Probabilistic Volcanic Hazards NOAA National Oceanographic and Assessment Atmospheric Administration PVHVIEW Probability of Volcanic Hazards NRC Nuclear Regulatory Commission VIEW NS North-South PVM Parallel Virtual Machine NSRRC Nuclear Safety Research Review PWR Pressurized Water Reactor Committee QA Quality Assurance NTS Nevada Test Site QAP Quality Assurance Procedure NUREG NRC Technical Report Designation QRAM Quality Requirements Application NWPA Nuclear Waste Policy Act, as amended Matrix NWIRB Nuclear Waste Technical Review Board RAI Request for Additional OBES Office of Basic Energy Sciences Information OCRWM Office of Civilian Radioactive Waste RASA Regional Aquifer System i
Management Analysis OGC Office of General Counsel RDCO Repository Design, Construction.
OITS Open-Item Tracking System and Operations OMB Office of Management and Budget RDB1E Repository Design and hermal-OPS operations Plans Mechanical Effects ORR Operations Readiness Review REE Rare Earth Element ORS Overall Review Strategy REECO Reynolds Electrical and Engineering OWFN One White Flint North Company, Inc.
PA Performance Assessment RES Office of Nuclear Regulatory Research PAAG Performance Assessment Advisory RFP Request for Nposal Group RH Relative Humidity PAC Potentially Adverse Condition RIP Repository Integration Program vii
ABBREVIATIONS (cont'd)
ROC Repository Operations Criteria SUFLAT Stochastic Analyses of Unsaturated RPD Regulatory Program Databaae Flow And Transport RRT Regulatory Requirement Topic SVF Springerville Volcanic Field RSRG Real Space Renormalizstion SwRI Southwest Research Institute Orcup SZ Saturat.x1 Zone RT Radionuclides Transport TA Technical Assistance RTS Radwaste Treatment System TBD To Be D6termined 3AP Standards Approval Package TBM Tunnel Boring Machine SAR Safety Analysis Report 'ICP/IP Transmbsion Control SCA Site Characterization Analysis Protocol /Internet Protocol SCC Substantially Complete TDI Technical Document lndex Containment TIXX'S Technical document Reference SCCEX Substantially Complete Database System Containment Example TEF Thermal Effects on Flow SCE Staadard Calomel Electrode TEM Transmission Electron Microscopy SCFF Soutacrn Crater Flat Fault THC ThermabHydrologic-Chemical SCM Surface Complexation Models THMC Thermai-Hydrologic.
SCP Site Characterization Plan Mechanical-Chemical SDMP Site Decommissioning TL Transverse-longitudinal Management Plan TLM Triple-Layer Model SDS Structural Deformation and TM Rermal-Mechanical Seismicity TMil nermal-Mechanical-Hydrologic SECY Secretary of the Commission. Office of TMI-2 nree Mile Island Unit 2 tbc (NRC) TMS ne Minerals, Metals, and Materials SEI.M Spectral Element Method Society SEM Scanning Electron Microscopy TOP Technical Operating Procedure SER Safety Evaluation Report TP Technical Position SF Spent Fuel TPA Total system Performance Assessment SFPO Spent Fuel Project Office TPI Time Period of Regulatory SFVF San Francisco Volcanic Field Interest SGI Silicon Graphics Inc. TR2 DOE Seis nic Topical Report No. 2 SGML Standard Generalized Markup TRG Technical Review Group Language TSAR Topical Safety Analysis Report SHE Standard Hydrogen Electrode TSPA Total System Performance SHT Single Heater Test Assessment SIP Scientific Investigation Plan TSPAI Total System Performance SKI Swedish Nuclear Power Inspectorate Assessment and Integration SL Short Transverse-Longitudinal TSw-Cbnv Topopab Spring Welded-Calico SLAR Side Looking Airborne Radar Hills Nonvitric SNF Spent Nuclear Fuel TVD Total Variation Diminishing SNL Sandia National Laboratories 'lWFN Two White Flint North SOTEC Source "IErm Code TWINS Tank Waste Information SOW Statement of Work Network System SPCR Software Problem Correction Report TWRS Tank Waste Remediation System SRA Systematic Regulatory Analysis UA Universityof Arizona SRB Sulfate Reducing Bacteria UACH Universidad Aut6nomade SRBS Shafts, Ramps. Boreholes, and Reir Chihuahua Seals UCLA University of California-IAs SRD Software Requirements Angeles Description UDEC Universal Distinct Element Code SRS Savannab River Site UK United Kingdom SRSASF Savannab River Site Aluminum- UNM University of New Mexico Based Spent Fuel UR Uranium Recovery SS Stainless Steel U.S. United States STEM Scanning Transmission Electron USDA U.S. Depar' ment of Agriculture Microscopy USGS U.S. Geologic Survey STP Staff Technical Position UTM Universal Transverse Mercator i
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.l ABBREVIATIONS (cont'd) l USFIC Unsaturated and Saturated Flow Under !
Isothermal Conditions l UZ Unsaturated Zone VA VCS Viability Assessment Version Control System l
VF Vitrification Facility I VSIP Vertical Slice implementation 1 Plan WAN . Wide Area Network i WAPDEG Waste Package Degradation l
WBS Work Breakdown Structure I WCIS Waste Containment and Isolation Strategy WFO Work for others WGB Westem Great Basin P'IPP Waste Isolation Pilot Plant WMB Waste Management Branch i
. WNYNSC W stem New York Nuclear Service Center i l
WOL Wedge-Opening leading l WP Waste Package WSEI Waste Systems Engineering and
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Integration WSRC Westinghouse Savannah River Company WSS Waate Solidification Systems WTSO Washington Technical Support Office WVDP West Valley Demonstration Project WVNS West Valley Nuclear Services WWW World Wide Web XPS X-ray Photoelectron Spectroscopy XRD X-ray Diffractometry YM Yucca Idountain
'YMP Yucca Mountain Project YMSCO Yucca Mountain Site Characterization Office YMR Yucca Mountain Region l YTD Year-to-Date '
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EXECUTIVE
SUMMARY
-PERIOD 9 In the Division of Waste Management (DWM) Job Code (JC), the Center for Nuclear Waste Regulatory Analyses (CNWRA) continued work on numerous analyses and revisions to issue resolution status reports (IRSRs). In addition, staff delivered Input to Igneous Activity IRSR Rev.1-Letter Report, Input to Structural Defonnation and Seismicity IRSR, Rev.1-Letter Report. Input to Evolution of the Near-Field Environment IRSR, Rev.1-Letter Report, and input to Unsaturated and Saturated Flow Under Isothermal Conditions IRSR, Rev.1-Saturated Zone Topics-Letter Report. A paper, Laboratory Experiment on Ventilation Effects on Repository, documenting the ventilation test results and analyses has been sent to the International Journal ofHeat and Mass Transfer. CNWRA statidelivered Evaluation of U.S. Department j of Energy (DOE) nermal Test Data-Progress Report along with the Total-system Performance Assessment '
(TPA) Beta Version 3.2 code durmg this period. Moreover, the revised dose conversion factor (DCFs) and an analysis of the magnitude of changes from prior DCFs were sent with the beta version of the TPA code. l The DWM JC year-to-date (YTD) cost variance was 12.5 percent. Although the cumulative variance increased in dollars since the previous month, this variance decreased in percentages (by5.3 percent) as work accelerated in several areas.
In the Tank Waste Remediation System (TWRS) JC, the repon, Final High-Level Waste Chemistry Manual !
(IM 1403-106-805), was transmitted. The YTD cost variance for tne TWRS was 8.9 percent. This variance i fell from last period as a result of completing this manual and other activities. l In the Bree Mile Island Unit 2 (TMI-2) Indeperident Spent Fuel Storage Installation (ISFSI) JC, a draft report entitled Second Round Request for Additional Information(RAI)/ Outline of Safety Evaluation Report (SER)-Draft Letter Report was accepted. The YTD cost variance for the TMI-2 ISFSI was 37.4 percent-reflecting decreased activity primarily related to the CNWRA anticipated receipt of the DOE j response to the Nuclear Regulatory Commission (NRC) second round RAI. ;
in the Dry Transfer System (DTS) JC, the staff worked on the First Round Request for Additional Information-Draft Letter Repon. The YTD cost variance for the DTS was 36.1 percent, down from last period. The staff remains involved in the continuation of the safety review of the DTS Topical Safety l Analysis Repoa. '
In the Centralized Interim Storage Facility (CISF) JC, the staff pursued identification of technical issues specific to one or more of the cask designs proposed for use at the CISF. The YTD cost variance for the CISF was 32.2 percent. This variance increased despite accelerated activity and can be attributed to additional funding under the revised CISF Operations Plan.
In the Private Fuel Storage Facility (PFSF) JC, the CNWRA staff engaged in review and evaluation of the DOE responses to the NRC first round RAI and participated in a site visit on the Reservation of the Skull Valley B and of Goshute Indians in Utah and attended the PFSF EIS scoping meeting. The YTD cost variance for the PFSF was 7.1 percent as spending increased substantially over last period.
In the West Valley Demonstration Project (WVDP) JC, no activity was recorded during this period. The CNWRA responded to an NRC request for a proposal to conduct WVDP decommissioning work under the Industrial Mobilization Exemption.
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i EXECUTIVE
SUMMARY
-PERIOD 9 In the Savannah River Site Aluminum-Based Spent Fuel (SRSASF) JC, the staff submitted the report, Review of the Technical Issues Related to Interim Storage and Permanent Disposal of Al-based Spent ,
Nuclear Fuel. The YTD cost variance for the SRSASF JC was 21.1 percent. The variance increased this period because CNWRA is awaiting DOE response to its earlier comments.
It should be noted that the current spending estimates in all JCs are based on the assumption that staffing is at authorized levels. Carrent staffing remains below authorized levels and recruitment continues at an accelerated pace.
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CNWRA PROGRAM MANAGER'S PERIODIC REPORT l ON ACTIVITIES OF THE CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES l
TITLE Center for Nuclear Waste Regulatory Analyses (CNWRA)
CONTRACTOR: Southwest Research Institute (SwRI) 6220 Culebra Road, San Antonio, Texas 78238-5166 CONTRACT NO: NRC-02-97-(X)9 JOB CODES: D1035, J5164,35186, J5206, J5190, J5226, J5210 NRC CNWRA PROGR AM M ANAGER: John J. Linehan, (301) 415-7780 NRC CNWRA DEPtTI'Y PROGRAM MANAGER: Deborah A. DeMarco, (301) 415-78(M
- CNWRA PRESIDENT: Wesley C. Patrick,(210) 522-5158 ESTIM ATED BUDGET: $87,611,477 PERIOD OF PERFORMANCE: 09/27/97-09/27/02 PERIOD OF THIS REPORT: 05/09/98-06/05/98 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) delivering Revision 10, Change 2, of the CNWRA l Operations Plans; (ii) clarifying information on CNWRA carryover monies; (iii) engaging '
in the DWM budget-related deliberations with the HLW Management Board; (iv) addressing further COI-related issues among NRC, SwRI, and CNWRA management staffs; and (v) participating in weekly HLW Management Board meetings.
Status of CNWRA staffing is indicated in table 1, consistent with the revised staffing plan submitted as part of the revision to the CNWRA Management Plan. During period 9, recruitment efforts and interviews continued for the approved open positions. Dr. David A.
Farrelljoined the GHGC staff as a research scientist. Two new staff members will begin workin the next two periods.
Computer system support activities encompassed (i) developing specifications for upgrading hardware and software associated with the GIS computing facility, (ii) pursuing a replacement for the CNWRA-developed CDOCS software, (iii) participating in the monthly NRC/CNWRA Computer Coordination meeting, and (iv) maintaining LAN operations.
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QA activides focused on (i) distributing Technical Operating Procedure-018,(li) preparing for the CNWRA QA audit; (iii) conducting surveillance, issuing nonconformance notices as required, and working with cognizant staff in response to these notices; (iv) leading the configuration control effort of the CNWR A scientific and engineering software determined ready for release; (v) cor. trolling issued documents and maintaining QA records; (vi) working to prevent organizational COls by review of SwRI RFPs; (vii) performing Q A verification checks on each CNWRA deliverable; (viii) completing the Quality Requirements Application Matrix for CNWRA NRC projects; and (ix) revising the CQAM.
In the next period, the CNWRA staff expects to (1) participate in NRC/CNWRA discussions concerning development of guidance for OPS development; (ii) maintain dialog with the NRC deputy program manager on COPS activities; (iii) pursue hiring for open core staff positions; (iv) pursue a replacement for the CDOCS software; (iv) provide CNWRA LAN operation and maintenance support; and (v) proceed with scheduled QA surveillance, perform QA indoctrinations for new CNWRA staff, input internal documentation and record copies of delivered documents into QA records, review RFPs for potential COI, perform QA verification checks on each CNWRA outgoing deliverable, and conduct the CNWRA annual QA audit June 23-26,1998.
1.2 Igneous Activity (IA)
Staff activities this period focused on completion and delivery ofInput to Igneous Activity I IRSR Rev.1-Letter Report (IM 1402-461-830). This revision provides the framework for resolution of I A consequence subissues. Although staff are progressing toward consequence subissue resolution, recent changes in the DOE-PA modeling approaches require additional consideration before resolution status can be determined. 'Ihe resolution approach to l probability subissues remains unchanged in this IRSR resision.
Staff developed input to the FY99 OPS for IA issues. In addition to production and resiew of numerous licensing support documents, IA staff will conduct technicalinvestigations to reduce uncertainties in models and parameters used for PA. These investigations include (i) determining mass-loading parameters associated with basaltic tephra-fall deposits for use in airborne dose calculations, (ii) modifying tephra-dispersion models to calculate directly the transport of HLW particles during a volcanic eruption, (iii) conducting field-based investigations with SDS staff to evaluate the relationship between scales of crustal strain I and effects on volcano recurrence rate, and (iv) evaluating with CLST staff the interactions between ascending basaltic magma and WPs.
M and NRC staffs continued discussions on proposed changes to 10 CFR Part 63 which focused on the difficulties in accounting for ground-surface dose from a low probability event in a standard designed primarily for undisturbed repository operations. Staff continued to work with PA staff to explore methodologies to calculate the annual risk effected by potential volcanic disruption of the proposed reposito y.
IA staff prepared for technical investigations in the San Rafael volcanic field, Utah. These investiga2ons are designed to provide important data on subsurface geometries of basaltic volcanoes like those in the YMR. Investigations in the San Rafael field will focus on (i) detailed mapping of subsurface conduit and intrusion geometries using the differential GPS at 20 cm resolution, (ii) explicit ground-magnetics mapping to examine the 3D 2
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stmeture of shallow (500-1000 m) basaltic subvolcanic systems, and (iii) sample collection for anisotropy of magnetic suscep:1bility studies, which will measure magma flow directions in these intrusions based on alignment of magnetic minerals. The results of these investigations will be used to bound the volume of HLW that can be potentially entrained during a volcanic eruption.
PVHVIEW development continued at a slower pace this period because oflimited staff availability. Additional mapping and display modules were ported successfully from the Khoros programming environment to Microsoft Windows NT, along with compledon of initial verification of program accuracy. Display functions now include the ability to overlay volcano locations, line coverages, and probability surfaces on digital elevation model base maps.
In the next period, staff will conduct field investigations in the San Rafael volcanic field, Utah, to evaluate subsurface areas of disruption associated with basalde igneous events. !
Additional probability functions in PVHVIEW will be transferred to the Windows NT platform. Also staff will meet with consultants to develop Subsurface Area of Disruption for Basaltic Volcanoes-Journal Article (IM 1402-461-860) and advance GPS investigations. Work . will continue on Probability Models for Yucca Mountain Region-Journal Article (IM 1402-461-850). 1 l
1.3 Structural Deformation and Seismicity (SDS)
Staff delivered Input to Structural Deformation and Seismicity IRSR, Rev.1-Letter Report (IM 1402-471-820). Dis revision to the IRSR includes development of acceptance criteria for all SDS KTI subissues with concomitant technical bases. Also included in this revision of the IRSR are summaries of the technical bases and PA sensitivity studies that allow the SDS KTI to resolve the faulting subissue.
Also staff participated in a DOE /NRC technical exchange on the DOE GFM 3D site model .
l . which was constructed using the EARTHVISION software. We technical exchange was l
held in Rockville, Maryland, at the NRC headquarters on May 28-29,1998.
l A new set of tasks to investigate the significance of recently determined crustal strain rates i to volcanic and seismic hazard assessments was developed. %e higher than expected strain !
rates were detected by GPS measurements of the YMR recently published in Science and discussed at the International High-Level Radioactive Waste Management Conference in u Las Vegas, Nevada. Anticipated activities include both FY98 and FY99 tasks. He focus of FY98 proposed work will be an assessment of the relative contributions of seismic and aseismic deformation mechanisms to the overall strain budget.
Staff pardcipated in joint SDS and USFIC field investigations of the YMR. These field
-investigations used gravity measurements to further define the subsurface structural l framework of the northern Amargosa Valley and Fortymile Wash. He results will be applied to development of the regional 3D EARTHVISION models that can be used by the USFIC KTI for saturated tiow modeling. Ren, results and models will be incorporated in 3D Structural Model of Amargosa for Input to USFIC-Letter Report (IM 1402-471-860) for submittal at the end of this FY.
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. ,e In conjunction with the NRC PEM, staff developed input to the FY99 OPS for SDS issues.
A one-day meeting was held with a consulting seismologist to discuss plans for the review of the DOE PSHA for YM.
In the next period, staff willinvestigate fault and fracture patterns and geometries in the YMR. Staff will work with the NRC PEM to incorporate the contents of Input to Structural Deformation and Seismicity IRSR, Rev.1-Letter Report (IM 1402-471 -820)into the NRC Issue Resolution Report for transmittal to the DOE.
1.4 Evolution of the Near Field Environment (ENFE)
Input to Evolution of the Near-Field Environment IRSR, Rev.1-Letter Report (IM 1402-561-800) was sent during this period.
Preparations were made to present two invited talks at the ACNW Working Group Meeting on the Near-Field Environment and Performance of Engineered Barriers in the YM Repository scheduled for June 10-11,1998. Subjects of the talks are a plenary overview ofnear-fieldchemistryissuesandasummaryofNRC/CNWRAnear fleidmodelingstudies.
Source term solubility computations were initiated to examine a suite of possible near-fleid solution chemistries and solubility controlling phases An abstract on natural analog-based PA sensitivity studies completed both NRC and CNWRA reviews and will be submitted for presentation at the Materials Research Society Symposium on the Scientific Basis for Nuclear Waste Management XXII scheduled for Boston, Massachusetts, November 30-December 3,1998.
Progress continues on testing and debugging Version 1.2 of MULTIFLO and completing the user's manual. De MINC implementation in the code still does not work correctly. A bug was found in METRA that had been causing oscillations in saturation during a phase change from pure gas to gas plus liquid. Coupling METRA and GEM was initiated in the DCM and testing is ongoing. One difficulty noted in the current implementation of coupling METRA and GEM is the requirement for GEM time stepping to match exactly a METRA time step, often resulting in unnecessary time step reductions in GEM. Finally, a saturation cutoff was introduced for the case when complete dryout occurs to enable storage of the total aqueous solute masses and their release when rewetting commences. This is an approximate approach that does not require knowing which salts would actually precipitate from solution as dryout occurred. The user's manual is being updated for the DCM and .
MINC options in the METRA module. 'Ihis manual will be a portion of Expanded l Independent Coupled Process Modeling Capability, M ULTIFLO-Letter Report (IM 1402-561-810).
A CNWRA consultant attended the International Workshop on the Uses of Backfill in Nuclear Waste Repositories in Carlsbad, New Mexico, May 5-8,1998. 'Ihe consultant gave an invited presentation on The Performance of Backfills Based on Ca(OH)2 and Cement.
A copy of materials distributed and a meeting summary written by the consultant were conveyed.
I 4 :
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e CNWRA staff prepared a draft agenda for a DOE /NRC technical exchange on cementitious materials.
In the next period, samples from the Paiute Ridge area, near YM, will be prepared for petrographic examination. Presentations to the ACNW will be made on near-field environmental chemistry and modeling. CNWRA staff will assist the NRC in continuing changes to the Evolution of the Near-Field Environment IRSR. CNWRA staff will conduct technical reviews of abstracts on cementitious materials submitted to the Materials Research Society Symposium on the Scientific B asis for Nuclear Waste Management XXII.
A written review of the DOE reports on cementitious materials will be prepared by a CNWRA consultant. Future MULTIFLO work will focus on completing the user's manual for MULTIFLO and internal documentation of the source code for QA.
1.5 Container Life and Source Term (CLST) l The report, Input to Container Life and Source Term IRSR, Rev.1-Letter Report (IM 1402-571-820), was prepared and is undergoing CNWRA internal reviews.
Electrochemical corrosion testing continued for another 28 days to confirm the applicability of repassivation and corrosion potentials as predictive parameters for the long-term, localized corrosion of Alloy 825 in chloride-containing solutions. The staff initiated confirmatory testing of Alloy C-22 stress corrosion cracking and reviewed the design of the stress corrosion cracking test specimens used at LLNL. Crack growth rate specimens have been received and the test system is undergoing assembly.
l Re effect of environmental factors on thelocalized corrosion of A516 carbon steelis being examined using relatively short-term tests. The objective is to determine the conditions leading to localized corrosion. The stability of pit growth in carbon steel is being examined using a 1D simulated pit electrode.
In the next period, the Input to Container Life and Source Term IRSR, Rev.1-Letter Report (IM 1402-571-820) will be transmitted. Long-term corrosion tests of Alloy 825, together with localized corrosion testing of carbon steel and Alloys 625 and C-22 will continue.
1.6 Thermal Effects on Flow (TEF) he staff conducted preliminary testing of the DCM capability in the MULTIFLO code. A
! ID model continues to be the focus of this effort. The importance and relevance of the fracture / matrix transfer term are being investigated.
A paper documenting ventilation test results and analyses has been sent to the International Journal of Heat and Mass Transfer. This paper was delivered to fulfill Laboratory ,
Experimeht on Ventilation Effects on Repository-Journal Paper or Presentation (IM 1402- 1 661-820).
Preparation for the next phase of the boiling isotherm depression heater experiment is underway. The cement blocks will be coated with a sealant to impede imbibition of water l and several candidate scalants are being evaluated. The sorptivity of the original cement i
5 j i
'l
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.' i blocks is being measured and will be compared with the sorptivity of the sealed blocks. It is anticipated the sealed blocks will act more like a fractured porous medium than the original blocks, which responded similar to single continuum.
l Revision 1 of TEF IRSR is undergoing CNWRA internal reviews and will be transmitted as Input to Thermal Effects on Flow IRSR, Rey,1-Letter Report (IM 1402-661-810).
\
Numerical modeling of the LBT, DST, and drift-scale repository advanced. Current results of these activities were documented in a report and submitted as Evaluation of DOE Rermal Test Data-Progress Report (IM 1402-661-830).
An analytical model to describe heat conduction, two-phase flow, and gravity-driven fracture film flow was developed. De analytical model will assess the refluxing I phenomenon for nonisothermal conditions. The model code has been revised and is undergoing testing.
In the next period, TEF KTI staff plans to (i) initiate the next phase of the boiling isotherm penetration laboratory-scale experiment; (ii) proceed with refinement of the LBT, DST, and drift-scale repository numerical model; (iii) maintain testing of the MULTIFLO-DCM numerical code; (iv) evaluate conceptual models of refluxing; and (v) complete Revision 1 of TEF IRSR entitled Input to hermal Effects on Flow IRSR, Rev.1-Letter Report (IM 1402-661-810).
1.7 Repository Design and Thermal Mechanical Effects (RDTME)
Preparation of the RDTME IRSR progressed during this reporting period-<1eveloped jointly by the NRC and the CNWRA RDTME KTI staff members. This IRSR will be submitted during the next reporting period as Input to Repository Design and nermal-Mechanical Effects IRSR, Rev.1-Letter Report (IM 1402-671-810).
ne UDEC analysis to predict rock fall under seismic load in the repository thermal environment continued this period. Results of this simulation work are expected to provide a technical basis for determining the magnitude of dynamic impact load on the WPs due to rock fall and also will be used as input to the SEISMO module in the TSPA code for disruptive scenario assessment. Investigation of rock block size distribution at YM using joint pattern information collected from the ESF is being performed. The UDEC model is being constructed using the same joint pattern for investigating the seismic effects on rock fallin emplacement drifts.
Investigation advanced on repository-scale rock mass behavior under elevated temperature using the AB AQUS code. The analysis results indicate that long-term degradation of rock strength properties may have significant effect on near-field rock behavior. Emplacement drifts may become unstable at the later stage of the waste emplacement operation and collapse of emplacement drifts following permanent closure is possible.
De staff progressed on the investigation of drift-scale rock mass behavior and its effect on concrete lining stability under high temperature using AB AQUS. The AB AQUS model will include all components necessary for studying concrete liner behavior and model development is near completion. Initially, rock mass behavior of openings without liner 6
s support will be analyzed. This will be followed by the analysis of lined openings to obtain a better understanding of how liners function as supports.
The investigation of ddft-scale rock mass behavior and its effect on concrete lining stability using UDEC was initiated during this reporting period. This investigation will be coordinated closely with the drift-scale study using ABAQUS as discussed in the previous paragraph so differences in results between distinct numerical techniques can be better l
understood and quantified. The outcome of the investigations using these two numerical tools should provide valuable insight in developing acceptance criteria for review of the DOE license application regarding underground facility design.
The literature review on concrete performance under high temperature continued. It will provide valuable information to assess the DOE design of concrete liner under high temperature.
l RDTME activities for the remainder of FY98 will include (1) completion of the RDTME l IRS R, (ii) literature review on the behavior of unreinforced and reinforced concrete (liners) under long duration high temperature conditions, (iii) study of drift scale rock mass behavior and its effect on liner performance under high temperature, (iv) analysis of repository-scale rock mass behavior during elevated temperature, (v) revision of conceptual model for the SEISMO module, (vi) simulation of rock fall under seismic load to provide l input to SEISMO, and (vil) review of Seismic Topical Report No. 3.
In the next period, RDTME KTI staff plans to (i) review the literature collected on concrete performance during high temperature, (ii) investigate rock mass behavior under heated conditions on both repository and drift scales with an emphasis on long-term degradation
- of rock mass material properties and strengths, (iii) conduct rock fall simulations and prepare the IRSR, and (iv) conduct reactive activities including review of design documents.
1.8 Total System Performance Assessment and Integration (TSPAI)
The 1PA Version 3.1.4 User's Guide underwent substantial revision in response to formal technical, editorial, and programmatic reviews. Delivery of User's Guide for TPA Version 3.1.4-Letter Report (IM 1402-762-800) is scheduled for June 19,1998.
The TPA Beta Version 3.2 code was submined June 5,1998. All modifications to the code outlined in the SRD were implemented and the code was compiled and run on the CRADAL system. Testing began to ensure the correctness of the *.res files produced by the'IYA Beta Version 3.2 code. Submission of the TPA 3.2 code will fulfill, in part, User's Guide for TPA Version 3.2-Letter Report (IM 1402-762-810).
Interpretation progressed on system-level sensitivity results using measures based on differential analysis, stepwise-regres sion, stepwise rank regression, and the K-S test. These results will be reported in input to TPA Version 3.1 Sensitivity Studies Report-Letter Report (IM 1402-761-810).
GIA approach development advanced. Modifications continue on a test version of the TPA code to allow the user to specify which subsystems of the engineered and geologic barriers 7
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l are intact and functioning. Discussions are ongoing concerning if this approach is suitable for demonstrating or testing the defense-in-depth concept for a geologic repository: The GIA approach will be documented in a paper to be submitted to a conference on PA.
Effons have begun on (i) a PC version of the TPA Version 3.2 code, (ii) a Java-based post processor for the TPA Version 3.2 code, and (iii) a PVM implementation of the TPA Version 3.2 code.
A draft version of the TSPAI 1RSR section on scenario analysis was prepared. To allow )
more time for a thorough revision to the section model abstraction, delivery of Input to -
Total System Performance Assessment IRSR, Rev.1-Letter Report (IM 1402-761-800) has been postponed until period 12.
In the next period, the PA staff will focus on (i) preparing the first volume of the Input to l TPA Version 3.1 Sensitivity Studies Report-Letter Report (IM 1402-761-810), based on chapters 1, 2, 4, and 9 and appendix A of the TPA Version 3.1.4 User's Guide; (ii) completing the second volume of the Input to TPA Version 3.1 Sensitivity Studies Report-Letter Report (IM 1402-761-810), which reflects actual results of the sensitivity study; (iii) revising the Input to Total System Performance Assessment IRSR, Rev.1-Letter Report (IM 1402-761-800); (iv) documenting the GIA technique; and (v) continuing development of the PC and PVM versions of TPA Version 3.2 and the Java-based post processor for the TPA Version 3.2 code. In addition, recruitment continues for the unfilled PA modeler and risk assessment positions.
1.9 ActivitisRelatedtoDevelopmentof theNRCHigh LevelWasteRegulations(ARDR)
Revisions to incorporate the NRC comments into the previously issued report, Information and Analyses to Support Selection of Critical Groups and Reference Biospheres for Yucca Mountain Exposure Scenarios (CNWRA 97-009), were completed last period; however,the NRC staff raised an issue pertaining to default data (i.e., internal dose factors) in the GENII-S dose code. Therefore, delivery of the report was suspended pending resolution of this issue. This period involved investigation of technical issues regarding selection of internal dose factors relevant to the expected chemistry of biosphere contamination, review of available dose factor library updates, and subsequent revisions to the calculated DCFs using updated internal dose factor libraries for the GENII-S code. De revised DCFs and an analysis of the magnitude of changes from prior DCFs were delivered with the beta version of the TPA code. As a result of this work, some revisions to the text and tables of the CNWRA 97-009 report are needed but have not yet been completed. Rese revisions should be completed next period. The revised report is expected to be issued as a NUREG/CR and will be a key reference document for the rulemaking effort and TSPAI activities.
Staff participated in the NRC meetings key concepts and draft language for the revised NRC HLW rule and also in meetings to resolve key issues identified by both NRC and CNWRA staffs. Additional effort this period focused on preparing statements of consideration for the reference biosphere requirements in the draft rule, which will be completed early next period. The EPA Standard for YM has not been publicly issued, therefore, the review was put on hold pending public release of the standard, 8
E. .
r l
A draft report delivered last period on the sensitivity of peak dose with respect to several intermediate outputs using the TPA code was accepted by the NRC PEM. Calculations contained in this report are expected to provide technical insight useful in developing the revised NRC HLW rule. A final letter report for this deliverable will be prepared next period.
In period 10, the staff will assist the NRC in re11ning sections of the draft NRC HLW rule.
Emphasis will be on providing continued support to the NRC staffin resolving key issues and completing statements of consideration for the new HLW rule. If EPA publishes the j draft standard, staff will assist the NRC with reviewing the draft standard and preparing l comments. Needed revisions to the CNWRA 97-009 report resulting from the intcal dose factor issue resolution will be completed. De staff will begin new tasking to cc,nduct moic detailed analyses to assess the validity of the approach to dilution in the TPA code. De l final report on the sensitivity analysis of peak dose with intermediate calculations using the TPA code will be completed.
1.10 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC)
Input to Unsaturated and Saturated Flow Under Isothermal Conditions IRSR, Rev.1--Saturated Zone Topics-Letter Report (IM 1402-861-830) was delivered.
An analysis was performed in cooperation with RT staff to estimate time scales for dissolution of calcite fracture fillings in the YM SZ where groundwater are chemically undersaturated to calcite. The motivation for this analysis is that the presence of calcite in i the SZ may support interpretations of limited matrix diffusion. This analysis shows that the i
time scale for dissolution of calcite fracture fillinFs depends on the amount of calcite initially deposited, the distance from the nearest flowing fractures, the degree of disequillbdum, and the rate of diffusion. For scenarios with reasonably rapid matrix diffusion (D,,,= 2E-10 m 2/s) and with groundwater composition similar to J-13 well water, time scales for complete dissolution of calcite ranged from 10,000 yrs for a 2-:nm thick fracture filling 1 m from a flowing fracture to over 10,000,000 yrs for a 2-cm thick fracture l- filling located 100 m from the nearest flowing fracture system. Dese results suggest it is l possible for calcite fracture fillings to persist over geologic time scales in aquifers where flowing water is undersaturated with calcite. Thus, the presence of calcite at YM does not necessarily indicate limited matrix diffusion. Areas where calcite is abundant in the SZ, as at well G-2, may be indicative of areas where flowing fractures are on the order of hundreds of meters apart. An investigation into the abundance and distribution of calcite in the SZ in relation to known flowing fracture systems could prove usefulin constraining important i
matrix diffusion model parameters, namely, effective fracture spacing, effective diffusion coefficients, and mean groundwater velocity. Results of this analysis are planned for an abstract to be submitted for the Materials Research Society Symposium on the Scientific Basis for Nuclear Waste Management XXII scheduled for Boston, Massachusetts, November 30- December 3,1998.
l Field work near the YM crest identified characteristics of a single upper watershed j pertinent to watershed modeling, lateral subsurface flow, focused infiltration, and soil development. The small watershed is located in Split Wash, approximately over the path of the east-west drift currently under construction. Recent rainfall appeared to wet the entire l- colluvial profile in the small wash. Signs of recent overland rivulet and channel flows were 9
1
evident in the small wash, however, only one of the two channels exhibited signs of recent runoff (within the prior 2 weeks). Observations of soil moisture during previous trips to YM found dry profiles or proilles wet only to a small depth. Shallow infiltration measurements were made on colluvium, terrace deposits, alluvium, and bedrock fractures. Plant transects were completed to support broader photographic determinations of plant types and density.
The proliferation of bromus, a non-native and invasive grass, was prominent on all of the YM ridgetops and sideslopes. The bromus invasion has strong implications for shallow ,
J infiltration because its winter to summer cycle is being out of synchronization with most other plants at YM. A conceptual framework for modeling infiltration in the watershed was developed and field transects made to delineate and link the infiltration zones. Soil depth at YM exhibits strong control over both the DOE and the NRC maps of infiltration rates.
A conceptual model of soil genesis on the crest and sides' opes of YM was developed from observations in the small watershed. Soil depth profile transects were made at YM and Phinney Canyon, one of the analog sites for shallow infiltration at YM under pluvial conditions, to support soil depth models.
In collaboration with the IA and SDS staffs, electromagnetic and magnetic surveys were conducted near Yucca Crest to identify and map variations in moisture content and related properties across structural features important to infiltration. Preliminary interpretation of the data suggests that the electromagnetic measurements, when combined with magnetometer data, are able to delineate large features such as the Ghost Dance and Sundance faults as well as swarms of cooling joints. The lower limit of resolution of the electromagnetic measurements appears to be at or above the scale of individual cooling joint features. These electromagnetic measurements, however, seem to suggest variations in alluvial and colluvial covers on the crest of YM. Electromagnetic and magnetometer measurements near the C-Wells area identified previously mapped north-trending faults, but failed to establish the presence of northwest-trending strike-slip faults, possibly extending to Antler Wash.
USFIC field work was conducted in YMR in collaboration with the IA and SDS KTIs. Data were collected on three gravity lines in Amargosa Valley to provide input for further development of the 3D SZ model. These gravity data will be used for model geologic structure and depth to basement in Fortymile Wash. A total of 21 transient electromagnetic soundings were also performed, mainly on a N-trending line from southern Amargosa Valley into Fortymile Wash. Preliminary interpretation of these data indicate that the transient electromagnetic soundings successfully measured depth to the groundwater table; this depth varied from 50 m in southern Amargosa Desert to approximately 200 m in Fortymile Wash. Part of this variation is explained by topography and part of this variation appears to be related to geologic structures near Highway US 95. Data were collected for transects near Steve's Pass,in Fortymile Wash, and in Crater Flat. Interpretations of these data began.
Interpretation of the C-Wells hydraulic and tracer tests progressed. During this period, focus was on reviewing literature in preparation for future modeling work.
A presentation was made at the Spring American Geophysical Meeting, May 26--29,1998, Boston, Massachusetts, on estimating bulk hydraulic properties for various units at YM that when used for modeling tracers, emphasized preferential ilow pathways. Explanations of watershed modeling of rainfall and runoff in Solitario Canyon continued.
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In the next period, activities will include (i) interaction with NRC staff to nnalize the USFIC IRSR, Rev.1;(ii) continued development of a 3D, subregional site-scale flow and transport model; (iii) interpretation of data from field studies at YM; and (iv) interpretation of C-Wells data.
1.11 Radionuclides Transport (RT)
The author-Dnal version of Preliminary Alluvium Sorption Module for TPA 3.2-Letter Report (IM 1402-871-830) was completed during this period. This repon includes a description of an approach using geochemical sorption models to develop response surfaces that define sorption behavior as a function of system geochemistry.
Activity continued using GIS coverages to study spatial variation in predicted radionuclides sorption coefDcients based on ambient SZ water chemistry. Contour maps of sorption coefficients predicted with a surface complexation model have been prepared for U and Np.
Work continues to constrain alluvium mineralogy. Well logs were requested from the USGS offices in Carson City, Nevada. A literature review focused on identifying geochemical parameters likely to control transpon of Tc, I, Np, Pu, and Se. Background research was also initiated on colloid transpon of radionuclides.
Laboratory analysis for radionuclides sorption on mineral mixtures continued this period.
It included preparing mineral separates, obtaining laboratory materials necessary for the planned experiments, and performing general startup procedures.
During this period, an abstract titled Unsaturated Zone Waters From the Nopal I Natural Analog, Chihuahua, Mexico-implications for Radionuclides Mobility at Yucca Mountain was prepared for submittal to the Materials Research Society Symposium on the Scientific Basis for Nuclear Waste Management XXII, Boston, Massachusetts, November 30-December 3,1998. The planned presentation will focus on chemical and U-series isotopic data on perched and seep waters collected at the Nopal I analog site. The isotopic data are interpreted in terms of U mobilization in conjunction with previous U-series work on rock samples. The chemistry is compared to that from YM waters and thermodynamic interpretations are drawn regarding U and Si phase solubility relationships and reaction paths.
In the next period, progress will ensue on literature reviews of key geochemical parameters contro111ag scrption, colloid transpon, and alluvium mineralogy. Laboratory analysis will prepare for the planned experimental progra n. CNWRA Internal reviews will be completed for the report Preliminary Alluvium Sorption Module for TPA 3.2-Letter Report (IM 1402-871-830).
1.12 Tank Weste Remediation System (TWRS) l In subtask 1.2, the NRC staff comments on the final repon, Survey of Solidification Process Technologies Final Report (IM 1403-102-810), are being incorporated and a revised document in the form of changed pages will be issued to complete this mile-stone. The NRC staff comments on the annotated outline for the Low-Activity Waste Auxiliary Support Equipment and Process Control Tecimology System Hazard and Safety Issues Repon for 11 l l
l l
i I TWRS-Letter Report (IM 1403 102-833) were received and will be included in die draft report.
The final report on Comparison of Risk Assessment Techniques (IM 1403-103-810) was received from the subcontractor and reviewed by the CNWRA staff under subtask 1.3. In subtask 1.4, preparation continued on the Consequence Criteria Report for the TWRS (IM 1403-104-820).
Final High-Level Waste Chemistry Manual (IM 1403-106-805) was transmitted.
In the next period, activities will continue in subtask 1.2. Progress will be made on completing the LAW Feed Makeup, Solidification, and Offgas Treatment (IM 1403-102-832) and Low-Activity Waste Auxiliary Support Equipment and Process Control Technology System Hazard and Safety Issues Report for TWRS-Letter Report (IM 1403-102-833). Work will advance on the Consequence Criteria Report for the TWRS (IM 1403-104-820). In subtask 1.6, the literature review will progress on topics covered in the Final Report on Chemistry of the DOE Contractor Retreatment Activities (IM 1403-106-815).
1.13 Three Mile Island Unit 2 Independent Spent Fuel Storage Installation (TMI 2 ISFSI)
A draft report titled Second Round RAI/ Outline of SER-Draft Letter Report (IM 1405-014-820) documenting review and evaluation of the DOE responses to the NRC first round RAI, second round RAI, and an outline of the SER has been accepted.
In the next period, TMI-2 ISFSI staff plans to revise the draft version of the report on Second Round RAI/ Outline of SER to resolve the NRC comments,if any. This revised version will be submitted as Second Round RAl/ Outline of SER-Final Letter Report (IM 1405-014-830).
1,14 Dry Transfer System (DTS) he safety review of the DTS TS AR, reinitiated during period 6, continued this reporting period. A draft report documenting the first round RAI is undergoing CNWRA internal reviews. 'Ihis draft report will be delivered during next period as First Round Request for Additional Information-Draft Letter Report (IM 1405-021-810).
In the next period, DTS staff plans to revise the draft version of the repon on First Round RAI to resolve the NRC comments, if any. The revised version will be submitted as First Round Request for Additional Information-Final Letter Report (IM 1405-021-820).
1,15 Centralized Interim Storage Facility (CISF)
Activity regarding the identification of technical issues specific to one or more of the cask designs proposed for use at the CISF advanced during this reporting period. The specified issues will bc documented in a report for delivery as Recommendations for Cask Specific Issues to be Investigated (IM 1405-031-830).
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4 In the next period, CISF staff plans to identify cask specific issues that may need to be investigated by the NRC and review and evaluate the DOE responses to the NRC first round RAI and prepare the AR.
1.16 Private Fuel Storage Facility (PFSF)
The PFSF staff participated in a site visit on the Reservation of the Skull Valley Band of Goshute Indians in Utah and attended the PFSF EIS scoping meeting June 2,1998 'lhe DOE responses to the NRC first round RAI have been received at the CNWRA this period and review and evaluation of these responses begun.
In the next period, PFSF staff plans to continue review and evaluation of the DOE responses to the NRC first round RAI and initiate preparation of the second round of RAI for submission as Second Round Request for Additional Information-Final Letter Report (IM 1405-041-820) .
1.17 West Valley Demonstration Project (WVDP)
There were no expenditures or activities this period.
1.18 Savannah River Site Aluminum-Based Spent Fuel (SRSASF)
The report, Review of the Technical Issues Related to Interim Storage and Permanent Disposal of Al-based SNF (IM 1407-001-810), was transmitted. The report incorporated the NRC staff comments on the draft report.
In the next period, the staff will await a teleconference meeting with the DOE to discuss the review and obtain clarification as necessary.
2 MANAGEMENTISSUES None to report.
3 MAJOR PROBLEMS None to report.
i 1
4
SUMMARY
OF SCHEDULE CIIANGES 1 l
l Schedule changes for IMs are included in table 2. Completed deliverables are noted on table 3 and )
in the Executive Summary.
)
5
SUMMARY
OF FINANCIAL STA'ITJS Table 4 summarizes the CNWRA financial status in the context of authorized funds provided by the NRC. Total commitments of the CNWRA are $240,458. 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 10 KTIs, TWRS JC, TMI-2 ISFSI JC, DTS JC, 13 l
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CISF JC, PFSF JC, WVDP JC, and SRSASF JC. The planned costs per period are based on the spending plans contained in the CNWRA OPS, Revision 10, Change 2, for the DWM JC; TWRS l Operations Plan, Revision 1, Change 1, for the TWRS JC; SFPO Operations Plan, Revision 1, Change 5. for the TMI-2 ISFSI, DTS, CISF, and PFSF JCs; WVDP Operations Plan, Revision 8, Change 1, for the WVDP JC; and SRS ASF Operations Plan, Revision 0, Change 2, for the SRS ASF JC.
It should be noted the current spending estimates in all J Cs are based on the assumption that staffing is at authorized levels. Staffing remains below authorized levels and accelerated recruitment is in progress. An updated staffing plan has been submitted as pan of Revision 6, Change 3, to the CNWRA Management Plan.
Period 9 FY98 CNWRA composite expenditures declined slightly by 0.8 percent from last period and this aggregate of all JCs was underspent by $1,015,839 or 13.5 percent. De DWM, CISF, and PFSF JCs evidenced higher spending levels, while the TWRS, TMI-2 ISFSI, DTS, and S RS ASF JCs showed lower levels. The WVDP was inactive this period. In percentage, the PFSF JC registered sharp rises in expenses in contrast with a pronounced decline in expenditures for the DTS and TMI-2 ISFSI JCs. Specific explanations for these swings are provided in the individual sections of each JC, The DWM JC was underspent by $793,659 or 12.5 percent. Overall expenditures decreased 1.6 percent from the previous period as costs rose in the SDS, TEF, TSPAI, and USFIC KTIs, but declined in COPS and the IA, ENFE, CLST, RDTME, ARDR, and RT KTIs.
The TWRS JC was underspent by $49,339 or 8.9 percent. Expenditures decreased 6.6 percent over last period despite incorporation of comments on reports and completion of Final High-Level Waste Chemistry Manual.
The TMI-2 ISFSI JC was underspent by $44,710 or 37.4 percent. Costs fell 96.6 percent from last period-indicating minimal activity. The CNWRA is awaiting receipt of the DOE response to the NRC second round RAI.
The DTS JC was underspent by $57,114 or 36.1 percent. Spending declined 50.6 percent-reticcting a delay in the schedule.
The CISF JC was underspent by $48,510 or 32.2 percent. Expenses rose 9.3 percent from the previous period as the result of spending related to the continued identification of technicalissues specific to one or more of the cask designs proposed for CISF use. Despite this rise, the cunulative variance increased again owing augmented funding for this project from the previous period.
'The PFSF JC was underspent by $6,408 or 7.1 percent. Expenditures tripled over last pedod because of CNWRA involvement in a site visit, a scoping meeting, and activities related to the review and ,
evaluation of the DOE responses to the NRC first round RAI.
The WVDP JC was inactive this pedod. The project has been closed and a new contract is expected in the near future in accordance with the provisions of the IME.
The SRS ASF JC was underspent by $16,100 or 21.1 percent. Spending decreased by 39.9 percent over last period because CNWRA is awaiting DOE response to its earlier comments.
14 I
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1 The CNWRA expenditures on SwRI labor, consultants, and subcontractors as a percentage of composite spending on all JCs was 17.6. De CNWRA expense on consultants and subcontractors as a fraction of composite spending on all JCs was 10.1 percent. These percentages decreased from the previous period. The CNWRA remains committed to enhance, where appropriate, participation of consultants and subcontractors in the conduct of the CNWRA work.
1 As shown in table 1, the CNWRA has 48 core and one limited-term staff members. The CNWRA has updated the staffing plan portion of the Management Plan, which is reflected in table 1. The available pool of approved consultants and subcontractors decreased to 44.
This FYTD no capital or sensitive equipment was purchased with NRC funds (other than overhead, general and administrative expenses, and fees).
DWM JC he DWM JC cumulative cost variance through period 9 was 12.5 percent. Expenditures in this JC increased by 1.6 percent over the previous period. Specific explanations for over/ underspending for COPS and each KTI follow.
He cost variance for COPS was 8.1 percent: 5.8 percent for the Management, Planning, and Computer Support subtask (1402-158) and 18.6 percent for the QA subtask (1402-159). Spending in the 158 subtask fell and that for 159 rose relative to last period. Expenses in the Management, Planning, and Computer Support subtask are expected to remain near estimated levels for the next period and those associated with the QA subtask will substantially increase as the annual QA audit occurs.
The cost variance for the IA KTI was 2.4 percent. Spending is anticipated to increase in the next several periods owing to field investigations and plaimed use of consultants.
The cost variance for the SDS KTI was -7.8 percent. This reflects an increase in work to meet the KTI augmented budget, he cost variance for the ENFE KTI was 18.2 percent as the result of decreased spending this period, Future variances are anticipated to decrease as travel and consultant costs are posted.
he cost variance for the CLST KTI was 5.8 percent. The positive cost variance decreased from last period and will further decline with augmentation of activities in various tasks related to corrosion testing.
The cost variance for the TEF KTI was 15.8 percent-lower than tlat dilic incylous period. It is expected to abate further during the next few periods because of initiation of the next phase of experimental analyses, in addition to hiring new CNWRA staff.
De cost variance for the RDTME KTI was 17.9 percent. His variance is anticipated to decrease as additional non-CNWRA staff, including several summer student employees, are added to work on KTI activities.
The cost variance for the TSPAI KTI was 15.0 percent. This spending rate is expected to remain roughly constant during period 10. Increased use of SwRI staff on tasks related to development of 15
i the post processor for the TPA code and PVM and PC versions of TPA Version 3.2 will enhance '
spending during the ensuing months.
The cost variance for the ARDR KTI was 50.5 percent. This variance is slightly higher than the variance for last period. Expanded spending is anticipated resulting from taskmg recently hired staff member with the new dilution analyses and the continued effort from the CNWRA team to assist h
the NRC with revising the HLW rule. Furthermore, following HLW Management Board recommendations for key issues in CFR 10 Part 63, it is anticipated that additional tasking to support the definition of the critical g oup may be forthcoming.
He cost variance for the USFIC KTI was 13.1 percent. This variance is lower than the 16.8 percent variance of the previous period because of recently completed fieldwork. De variance is expected to decrease in coming periods as travel and consultant costs associated with the field studies are I posted to this account.
The cost variance for the RT KTI was 24.9 percent, lower than that of the previous period. This variance is expected to continue declining in coming periods as consultant costs are posted.
De cost variance for the TWRS project was 8.9 percent. The positive cost variance decreased slightly from the last period. It is anticipated that the spending rate in the next period will remain at about the same level as activities on other milestones continue.
The cost variance for the TMI-2 ISFSI project was 37.4 percent. This cost underrun will continue until the CNWRA receives the DOE response to the NRC second round RAI and resources are allocated for preparing the SER by acquiring core staf f to be used on this project.
The cost variance for the DTS project was 36.1 percent, lower than that of the previous period. As activities progress, consultants employed, and staff acquired, this cost variance will decrease.
The cost variance for the CISF project was 32.2 perecct, primarily the result of augmented funding in the revised CISF Operations Plan. This cost undernm will decrease as the activities progress and the CNWRA hires staff that will also support this project.
The cost variance for the PFSF project was 7.1 percent, lower than that of the previous period. This cost underrun will decrease as the CNWRA reviews and evaluates the PFS Limited Liability Company response to the first round RAI and employs staff to support this and other activities.
De WVDP JC was inactive this period. The project has been closed and a new contract will be initiated in the next period in accordance with the provisions of the IME.
De cost variance for the SRSASF was 21.1 percent. He positive cost variance increased slightly from the last period through the completion of the main task in the project.
16
Table 1. CNWRA Core Staff-Current Profile and Hiring Plan * (Perk >d 9)
Expertin/ Experience Current No. Profenlan al Staff Postuuns Open FY98 ADMINISTRATION 4 Il GARG A. W P ATltlCK. J RUSSFJ L B.S AGAR GIEMICAL PROCESSINO 2 VJ AN. D.DARUWAILA ENGNO1PifYS CIIEM CODB ANAIYSIS/DEVEIDPMINT 3 RJANFI7Kf!. k M ARTIN, J B ANOS
)
l DATA MAN AOEMINT4'ROCESSING, P.MAIDONADO INdUDING TlNANCI AL 1
)
j DOSIVRISK/IIAZARD ANAIYSIS 0 1 EfFr*!1tOO!EMISTRY 1 0 CRAGNO!JNO .
ENGINEERNO 2 R.OIEN, O.OICEGBU OllOLOGYKJHOIDOICAL ENGNO.
ENVIRONMENTAL SCIENCES 1 P tmPLANTT!
000 CHEMISTRY $ W, MURPHY, RfAB ALAN. BSEARCY,1PPIKRYL.
DWRNER GEOffYDROIDGY/IIYDROGEOIDGY 4 R.ITIDORS. R.GRIJN J.WINTERIE. DFARREIL 1 GFDIDGY 2(11t t.McKAGUE, M.MIKIAS. P.lAFTMNAt liYDROIDG1C Dt ANSPORT 1 A.ARMSTRONG 2 INFORMATION MANAGEMENT 1 R. KCTTARA SYSTEMS MA1 TRIAL SCIENCFS 3 D DUNN, N SRIDH AR, S BROSSI A 1 1
MECHANICAL. 0 1 INGUDING DPSIGN & FABRICATION MINNG ENGINEERING 1 S-M.IISIUNO -
NUCIEAR ENGINEERING 1 MJAR7F.MBA l l
OPERATIONAL 1IEAI.Til PHYSICS 2 J WFIDY,I.DEERf1 l PERIORMANCB ASSFSSMENT 3 R.B ACA. S MOIIANTY, O Wr!TMEYER 1
)
QUAffrY ASStfR ANCE 1 B M ABRTTO )
R ADIO!S(YrOPE OBOGIIMSTRY 1 D PICKiffT kOCKMBCHANICS, 2 A.CHOWDHURY. A.GilOSH INGUDING QVII/S11tUC TNONG.
SOURCE-1TRM/SPINT FUf1DBGR AD. 1 P1JCITINER STRUCTURALGBOLOGY/ 3 DRiRRILL LSTAMATAKOS, D.SIMS SEISMO-TECTONICS SYSTEMS ENGINEERING 1 P.M ACKN VolfANOLOGYAGNEOUS 2 C.CONNOR, B. HILL PROCPSSPS TOTAL 4 tt11t 7 l
- See staffing plan for details l
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Table 4. Financial Status (Period 9)
Funds Funds Fands Project Names Authertzed Costed to Date t'ncosted Comndtments COPS 1.626.360 1,034.402 591 958 4.512 IA 619.186 404.758 214.428 12.024 SDS 784 930 615.799 169.131 10.644 ENFE 922.779 519.775 403.004 675 CLST 715,548 409.507 306.041 9.910 11 7 736,729 406.551 330.178 2.528 RD1MF 483.829 236.818 247.011 1.250 l TSPAI 1.738.058 945.392 792.666 2.907 ARDR 463.756 I32.209 331.547 0 USFIC 1.113.397 635,328 478.069 20.422 RT 477,466 212.437 265.029 79.200 DWM Costs 9.682.038 5.552.975 4.129.063 DWM Award Fee 563.865 260.531 303.334 DWM Base Fee 375.910 215.697 160.213 TOTAL DWM 10.621.812 6.029.202 4.592.610 144.072 NRS Costs 821.90I $04.633 317.268 72.932 NRS Award Fee 47.643 22.741 }
24902 NRS Base Fee 31,762 19.604 12.158 TOTALNRS 901.305 546.978 354.327 92.932 TMI 2 ISFSI S AR Costs l
157.704 74.964 82.740 3.454 TMI-2 ISFSI SAR Award Fee 9.191 5.585 3.606 1MI-2 ISFSI Base Fee 6.127 2.893 3.235 TOTAL 1MI-2 fSFSI S AR 173,023 83.442 89 981 3.454 17TS Costs 192.277 100 957 91.320 0 DTS Award N 11.175 7.774 3.401
!YTS Base Fee 7,451 3.896 3.554 TOTAL [YTS 210,903 112.628 98.275 0 CISP Ccuts 228.022 102.283 125,739 0 ;
CISP Award Fee 13.245 6.203 7.042 CISP Base N 8.831 3.942 4.889 l TOTAL CISF 250 098 112.428 137.670 0 l PFSF Canis 142.880 83.713 59.167 0 l
PFSF Award Fee 8.310 3.512 4.798 I PFSF Base N 5.540 3.226 2.314 TCYTAL PFSF 156.730 90.451 66.279 0 WVDP Costs 34.495 34.266 229 0 WVDP Award Fee 2.287 1,896 301 WVDP Base Fee 1.331 1,331 0 TOTAL WVDP 38 112 37.492 620 0 SRS ASF Coat: 108.826 60.327 48.499 0 SRSASP Award Fee 6.340 3.351 2.989 SRS ASP Base Fee 4.227 2.335 1.892 TOTAL SRS ASP 119.393 66.012 $3.380 0 Orand Tel 12,47 L376 7.078.634 5.192,742 240,458 Note:All authwized funds have been allocated.
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