ML20196K598
| ML20196K598 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/26/1999 |
| From: | CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES |
| To: | NRC |
| Shared Package | |
| ML20196K593 | List: |
| 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-99-6, NUDOCS 9904020195 | |
| Download: ML20196K598 (44) | |
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CNWRA PROGRAM MANAGER'S PERIODIC REPORT ON ACTIVITIES OF THE CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES l
For the Fiscal Reporting Period February 13,1999 - March 12,1999 PMPR No. 99-6 March 26,1999 Q4 MIE "
g, WM-11
O TABLE OF CONTENTS Section Page TABLES.........................................................................iv AB B REVIATIONS............................................................... v EXECUTIVE S UMM ARY-PERIOD 6................................................ xi 1
TEC HNIC AL............................................................... 1 1.1 CNWRA Operations (COPS)..........................................
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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)........................................ 7 1.7 Repository Design and Thermal-Mechanical Effects (RDTME)................. 8 1.8 Total System Performance Assessment and Integration (TSPAI)................. 9 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)........... I1 1.11.
Radionuclide Transport (RT)............................................
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1.12 Tank Waste Remediation Systems (TWRS)..............................
14 1.13 Three Mile Island Unit 2 Independent Spent Fuel Storage Installation (TMI-21SFSI).............................................
15 l.14 _ 3ry Transfer System (DTS)............................................
15 1.15 Centralized Interim Storage Facility (CISF)...............................
16 1.16 Private Fuel Storage Facility (PFSF)......................................
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1.17 Savannah River Site Aluminum-Based Spent Fuel (SRSASF)..................
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2 MANAGEM ENT IS S UES...................................................
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3 MAJOR PROBLEMS 17 4
SUMMARY
OF SCHEDULE CHANGES.......................................
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SUMMARY
OF FINANCIAL STATUS........................................
17 APPENDIX-Planned and Actual Costs, and Cost Variances Period 6-FY1999 i
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TABLES Table Page 1
CNWRA Core Staff-Current Profile and Hiring Plan * (Period 6).................... 22 2
Summary of Schedule Changes (Period 6)........................................ 23 3
Deliverables (Period 6)..................................................... 24 4
Financial Status (Period 6).................................................. 25 5
Private Fuel Storage Facility License Fee Cost Recovery Status (Period 6).............. 26 iv -
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ABBREVIATIONS ID One-Dimensional CDROM Compact Disk Read Only Memory 2D Two-Dimensional CDS Compliance Deternunation Strategy 3D Three-Dimensional CDTS Commission Decision Tracking System AA Atomic Absorption CEB Center for Environmental Biotechnology AAI Average AnnualInfiltration CEC Commission of the European ACD Advanced Conceptual Design Communities ACF Alumina (in excess of alkali feldspar).
CFD Computational Fluid Dynamics Calcium Oxide, Ferromagnesian Oxide CFR Code of Federal Regulation ACNW Advisory Committee on Nuclear Waste Clin Calico liills Nonwelded Tuff ACRS Advanced Computer Review System CIAC Computer Incident Advisory Capability ADAMS Agencywide Documents Access and CISF Centralized Interim Storage Facility Management System CLST Container Life and Source Term AECL Atomic Energy of Canada Limited CM Configuration Management AES Atomic Emission Spectrometry CNWRA Center for Nuclear Waste Regulatory AGU American Geophysical Union Analyses Al Administrative item CNWRA OPS Operations Plan for the Repository ALTS Apache Leap Test Site Program I
AML Areal Mass leading CO!
Conflict ofInterest ANS American Nuclear Society COPS CNWRA Operations ANSI American National Standards im te CPP Cyclic Potentiodynamic Polarization AO Annotated Outline CQAM CNWRA Quality Assurance Manual AP Administrative Procedure CRG Center Review Group APB Acid-Producing Bacteria CRM Corrosion Resistant Material AR Assessment Report CRWMS Civilian Radioactive Waste ARDR Activities Related to Development os Management System the NRC High-Level Waste Regulations CSCS Constrained Stochastic Climate ASCE American Society of Civil Engineers Simulator ASCII American Standard Code for CSil Calcium Silicate flydrate Information Interchange CSPE Corrosion Science and Process ASLB Atomic Safety and Licensing Board Engineering ASME American Society of Mechanical DAS Data Acquisition System Engineers DBE Design Pasis Event ASTM American Society for Testing and DC Division of Contracts Materials DCAA Defense Contract Audit Agency ASU Arizona State University DCB Double Cantilever Beam ATDTS Automated Technical Data Tracking DCF Dose Conversion Factor System DCM Dual Continuum Model BDCF Biosphere Dose Conversion factor D&D Decommissioning and Decontamination BEG Bureau of Economic Geology DECOVALEX Development of Coupled Models and BFD Basis for Design Their Validation Against Experiments BM Bare Mountain in Nuclear Waste Isolation BMF Bare Mountain Fault DEIS Draft Envimnmental Impact Statement BNFL British Nuclear Fuels Limited DEM Digital Elevation Model Bl?
Branch Technical Position DF Dilution Factor CAI Color AlterationIndex DFCSS Division of Fuel Cycle Safety and CAM Corrosion Allowance Material Safeguards CAR Corrective Action Reques.
DIE Determination ofImportance CCDF Complementary Cumulative Evaluation Distribution Function DiMNS Division ofIndustrial and Medical CCL Commitment Controlleg Nuclear Safety CCM Constant Capacitance Model DKM Dual Permeability Model CD-R CDROM Recordable DLG Digital Line Graph CDF Cumulative Distribution Function DLM Diffuse Layer Model CDM Compliance Determination Method DNAG Decade of North American Geology CDOCS Consolidated Document Management DNFSB Defense Nuclear Facilities Safety Board System DOE U.S. Dept.rtment of Energy V
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ABBREVIATIONS (cont'd)
DOE-DP U.S. Department of Energy Defense GEM General Electrochemical Migration Program GEOTRAP 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 GilGC GeoHydrology and GeoCheruistry DWM Division of Wam Management GIA GeneralizedImportance Analysis EBS Engineered BA. System GIS Geographic Information System EBSER Engineered Barnei System GLGP Geology and Geophysics Experimental Reser i 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 GTTE Great Tolbachik Fissure Eruption EDO Office of the Executive Director for
- MI Graphics User interface Operations GWB Geochemist's Workbench EDX Energy-Dispersive X-Ray Spectroscopy GWSI Groundwater System Integration EIS Environmental Impact Statement GWTT Groundwater Travel Time EM Element Manager HE Hydrogen Embrittlement EMPA Electron MicroProbe Analysis HLUR High-Level Waste and Uranium ENE East-Northeast Recovery Projects Branch ENFE Evolution of the Near-Field HLW High-level Waste Environment HRTEM High-Resolution Transmission Electron ENGB Engineering and Geosciences Branch Microscopy EnPA Energy Palicy Act of 1992 IA Igneous Activity ENS European Nuclear Society IBM Intemational Business Machines EPA U.S. Environmental 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 ExternalQuality Assurance IDLH Immediately Dangerous to Life and EROS Earth Resource Observation System Health ESF Exploratory Studies Facility IHLRWMC International High-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 and Seismic Hazard Environmental Laboratory Analysis INEIER Instituto Nicaraguense de Estudios FEHM Finite Element Heat and Mass Transfer TERritoriales FEM Finite Element Method INTEC Idaho hational Technology and FEP Features, Events, and Processes Engineering Center FFRDC Federally Funded Research and INTRAVAL International Code Validation Development Center 1/0 Input / Output FFT Fast Fourier Transform IP Inspection Procedure FOC Field Operations Center IPA Iterative Performance Assessment FTE Full-Time Equivalent IR&D Internal Research & Development FTP 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
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ABBREVIATIONS (cont'd)
ISA initial Safety Analysis NIOSH National Institutes Of Safety and llealth ISFSI Independent Spent Fuel Storage NIR Near-infrared Installation NIST National Institute of Standards and ISM Integrated Site Model Technology IVM Interactive Volume Modeling NMSS Office of Nuclear Material Safety and IWPE Integrated Waste Package Experiments Safeguards JC Job Code NNE North-Northeast JPL Jet Propulsion Laboratory NNW North-Northwest JRC Joint Roughness Coefficient NOAA National Oceanographic and KESA Key Elements of Subsystem Abstraction Atmospheric Administration KTl Key TechnicalIssue NRC Nuclear Regulatory Commission KTU Key Technical Uncertainty NS North-South LA License Application NSRRC Nuclear Safety Research Review LAAO License Application Annotated Outline Committee LAN local Area Network NTS Nevada Test Site LANL Los Alamos National Laboratory NUREG NRC Technical Report Designation LARP License Application Review Plan NWPA Nuclear Waste Policy Act, as amended LAW Low-Activity Waste NWIRB Nuclear Waste Technical Review Board LBNL Lawre.cc Berkeley National Laboratory OBES Office of Bas:c Energy Sciences LBT Large Block Test OCRWM Office of Civilian Radioactive Waste LHS Latin Hypercube Sampling Management LITC Lockheed Information Techno:ogy OGC Office of General Counsel Company OITS Open-Item Tracking System LLC Limited Liability Cotepany OMB Office of Management and Budget LLNL Lawrence Livermore National ORR Operations Readiness Review Laboratory ORS Overall Review Strategy LLW lew-level Waste OWFN One White Flint North LMAES lockheed Martin Advanced PA Performance Assessment Environmental Systems PAAG Performance Assessment Advisory LSS Licensing Support System Group LSSPP Licensing Support System Pilot Project PAC Potentially Adverse Condition LSSTB Licensing Support System Test Bed PAHT Performance Assessment and LWR Light Water Reactor Hydrologic Transport M
Molar PASP Performance Assessment Strategic Plan Ma Million Years Ago PC Personal Computer MAI Mean AnnualInfiltration PC/TCP Personal Computer / Transmission MC Monte Carlo Control Protocol METRA Mass and Energy Transport PDF Probability Distribution Function MGDS Mined Geologic Disposal System PDR Public Document Room MH Mechanical-Hydrological PEL Permissible Exposure Limit MIC Microbially influenced Corrosion PEM Program Element Manager MIhC Multiple Interacting Continua PER Prelicensing Evaluation Report MIT Massachusetts Institute of Technology PEST Parameter Estimation MM Major Milestone PFD Probabilistic Fault Displacement MO Management and Operations PFDHA Probabilistic Fault Displacement MOU Memorandum of Understanding Hazard MPC Multi Purpose Canister PFS Private Fuel Storage MRS Monitored Retrievable Storage PFSF Private Fuel Storage Facility MSS MultiSpectral Scanner PHA PreliminaryHazard Analysis MTU Metric Ton of Uranium PJ PrincipalInvestigator NAS National Academy of Sciences PMDA Program Management, Policy NAWG Natural Analogue Working Group Developnent and Analysis Staff NCR NonConformance Report PMPR Program Manager's Periodic Report NEA Nuclear Energy Agency PMT Photo-Multiplier Tube NEl Nuclear Energy Institute PNNL Pacific Northwest National Laboratory NFS Network File Server PO Project Officer Vii
ABBREVIATIONS (cont'd)
PPA Proposed Program Approach SFPO Spent Fuel Project Office PPE Prepassivated Platinum Electrode SFVF San Francisco Volcanic Field PRA Probabilistic Risk Assessment SGI Silicon Graphics Inc.
PRT Peer Review Team SGML Standard Generalized Markup PSAG Probabilistic System Assessment Group Language PSHA Probabilistic Seismic Hazard Analyses SHE Standard Hydrogen Electrode l'IFE Polytetrafluoroethylene SHT Single Heater Test l'Tn Paintbrush Nonwelded Tuff SIP Scientific Investigation Plan PVHA Probabilistic Volcanic Hazards SKI Swedish Nuclear PowerInspectorate Assessment S-L Short Transverse-Imngitudinal PVHVIEW Probability of Volcanic Hazards SLAR Side looking Airborne Radar VIEW SNF Spent Nuclear Fuel PVM Parallel Virtual Machine SNL Sandia National Laboratories PWR Pressunzed Water Reactor SOTEC Source Term Code QA Quality Assurance SOW Statement of Work QAP Quality Assurance Procedure SPCR Software Problem Correction Report QRAM Quality Requirements Application SRA Systematic Regulatory Analysis Matrix SRB Sulfate-Reducing Bacteria RAI Request for AdditionalInformation SRBS Shafts, Ramps Boreholes,andneir RASA Regional Aquifer System Analysis Seals RDCO Repository Design, Construction, SRD Software Requirements Description and Operations SRS Savannah River Site RDTME Repository Design and Hermal-SRSASF Savannah River Site Aluminum-Mechanical Effects Based Spent Fuel REE Rare Earth Element SS Stainless Steel REECO Reynolds Electrical and Engineering STEM Scanning Transmission Electron Company, Inc.
Microscopy RES Office of Nuclear Regulatory Research STP Staff Technical Position RFP Request for Proposal SUFLAT Stochastic Analyses of Unsaturated RH Relative Humidity Flow AndTransport RIP Repository Integration Program SVF Springerville Volcanic Field ROC Repository Operations Criteria SwRI Southwest Research Institute RPD Regulatory Program Database SZ Saturated Zone RRT Regulatory Requirement Topic TA Technical Assistance RSRG Real Space Renormalization Group TAN Test Area North RT Radionuclide Transport TBD To Be Determined RTS Radwaste Treatment System TBM Tunnel Boring Machine SAIC Science Applicationinternational TCP/IP Transmission Control Protocol /
Corporation Internet Protocol SAP Standards ApprovalPackage TDEM Time-Domain Electro-Magnetic SAR Safety Analysis Report TDI Technical Document Index SCA Site Characterization Analysis TDOCS Technical Document Reference SCC Stress Cctrosion Cracking Database System SCCEX Substantially Complete Containment TEDE Total Effective Dose Equivalent Example TEF nermal Effects on Flow SCE Standard Calomel Electrode TEM Transmission Electron Microscopy SCFF Southern Crater Flat Fault THC Thermal-Hydrologic-Chemical SCM Surface Complexation Models THMC Thermal-Hydrologic-Mechanical.
SCP Site Characterization Plan Chemical SDMP Site Decommissioning Management Plan T-L Transverse-lengitudinal SDS Structural Deformation and Seismicity TLM Triple-Layer Model SECY Secretary of the Commission, Office of TM nermal-Mechanical the (NRC) nfH Thermal-Mechanical-Hydrologic SELM Spectral Element Method 3 11-2 nree Mile Island Unit 2 SEM Scanning Electron Microscopy TMS ne Minerals, Metals, and Materiate SER Safety Evaluation Report Society viii
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ABBREVIATIONS (cont'd)
'IDP Technical Operating Procedure WTSO Washington Technical Support Office TP Technical Position VVDP West Valley Demonstration Project
' IPA Total system Performance Assessment WVNS West Valley Nuclear Services l
TPI Time Period of RegulatoryInterest WWW World Nide Web TR2.
DOE Seismic Topical Report No. 2 XPS X-ray Photoelectron Spectroscopy
'IRG Techmcal Review Group XRD X-ray Diffractometry i
TSAR Topical Safety Analysis Report YM Yucca Mountain TSPA Total System Performance Assessment YMP Yucca Mountain Project TSPA-VA Total System Performance Assessment.
YMR Yucca Mountain Region Viability Asr.essment YMRP Yucca Mountain Review Plan TSPAl Total System Performance Assessrnent YMSCO Yucca Mountain Site Characterization and Integration Office l
TSw-Chnv Topopah Spring Welded-Calico YID Year-to-Date Hills Nonvitric TVD Total Variation Diminishing TWFN Two White Flint North "IWINS Tank Waste information Network l
System TWRS Tank Waste Remediation System UA University of Arizona
.UACH
. Universidad Aut6 noma de Chihuahua UCLA University of Califomia 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. Department of Agriculture USGS U.S. Ga.ologic Survey Uni Universal Transverse Mercator USFIC Unsaturated and Saturated Flow Under Isothermal Conditions UZ Unsaturated Zone -
VA Viability Assessment VCS Version Control System VF Vitrification Facility VSIP Vertical Slice Implementation Plan WAN Wide Area Network WAPDEG Waste Package Degradation WBS Work Breakdown Structure WCIS
. Waste Containment and Isolation Strategy WPO-Work for Others WGB Western Great Basin WIPP Waste !salation Pilot Plant WMB Waste Management Branch WNYNSC Westem New York Nuclear Service Center WOL Wedge-Opening I.oading WP Waste Package WSEI Waste Systems Engineering and Integration WSRC Westinghouse Savannah River j
Company WSS Waste Solidification Systems IX
e EXECUTIVE
SUMMARY
-PERIOD 6 In the Division of Waste Management (DWM) Job Code (JC), the Center for Nuclear Waste Regulatory l
Analyses.(CNWRA) delivered a letter repon entitled Review of Final Viability Assessment and Preparation of Comments for Commission Paper, a draft version of the Total-system Performance Assessment (TPA)
Version 3.2 User) Guide, a letter report outlining the general parameter tree approach and the feasibility of implementing this pmd= = part of a TPA post-processor, revisions to the previously issued report, Information and Analyses to Support Selection of Critical Groups and Reference Biospheres for Yucca Mountain Exposure Scenarios, and a letter report on Formal Review of DOE UZ Studies. In addition to preparing abstracts for presentation iater this year, the staff produced journal papers on Grain Boundary Chemistry and Intergranular Corrosion in Alloy 825, Effect of Environmental Variables on Localized Corrosion of Carbon Steel and Implications on its Use in HLW Disposal, the general parameter tree approach and the feasibility ofimplementing this procedure as part of a TPA post-processor, and Importance Measure.
for Nuclear Waste Repositories, Stochastic Analysis of Early Tracer Arrivals in a Multiple Fracture Pathway.
These papers have been or will be submitted for acceptance in recognized technical journals. Staff panicipated in workshops, symposia, and other technical meetings.
The DWM JC year-to-date (YTD) cost variance was 17.7 percent. Spending rose 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 Hanford TWRS HLW Chemistry Manual, to be published as NUREG/CR-5751 and a repon 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 repons. The YTD cost variance was 25.8 percent. Despite this activity, spending fell from last period, but the cumulative percentage variance also declined.
In the Three Mile Island Unit 2 (TMI-2) Independent Spent Fuel Storage Installation (ISFSI) JC, the staff submitted the TMI-2 Final Safety Evaluation Report (SER) and continued to assist the NRC staff to prepare TMI-2 ISFSI Materials License No. SNM-2508. The YTD cost variance for the TMI-2 ISFSI was -5.4 percent.The cumulative variance decreased substantially despite an increase in spending because of a change in the period 6 spending plan.
I In the Dry Transfer System (DTS) JC, staff delivered the revised Spent Fuel Project Office Operations Plan, which included an accelerated schedule for the DTS project activities. Additional activities included staff E
review of the U.S. Depanment of Energy (DOE) response to the NRC first round request for additional
- informasion (RAI), development of a second round RAI, and preparation of the draft SER. Spending rose significantly from last period reflecting these activities. The YTD cost variance was 4.6 percent.
In the Centralized htterim 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. The YTD cost variance for the CISF was 42.1 percent. This underspending resulted from staff awaiting tasking to revise the computer code RISKIND and instruction to update the draft assessment repon.
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 repons, preparation of a draft SER, and l
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revision of the NRC draft position on five Group I contentions. Spending increased as a result of these activities. The YTD cost variance was -21.1 percent.
In the Savannah River Site Aluminum-Based Spent Fuel JC, the staff began revisions to a letter report.
Additional documents from the DOE were received for review. The YTD cost variance was 74.6 percert.
Although spending rose compared with the previous period, the cumulative variance increased due to lack' of additional tasking in this project.
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 presented in conjunction with the NRC/CNWRA Management Meeting held in March,1999, and revision to this staffing plan will be made later this fiscal year with the delivery of the CNWRA Management Plan. Current staffing remains below authorized levels and recruitmeri continues.
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F CNWRA PROGRAM MANAGER'S PERIODIC REPORT l
ON ACTIVITIES OF THE l
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: D1035,J5164,35186,35206,J5226,J5210 NRC CNWRA PROGRAM MANAGER: John J. Linehan,(301) 415-7780 NRC CNWRA DEPUTY PROGRAM MANAGER: Deborah A.DeMarco,(301)415-7804 l
CNWRA PRESIDENT: Wesley C. Patrick,(210) 522-5158 ESTIMATED HUDGET: $87,611,477 PERIOD OF PERFORMANCE: 09/27/97-09/27/02 EERIOD OF THIS REPORT: 02/13/99-03/12/99 1
TECHNICAL 1.1 CNWRA Operc$ns (COPS)
In addition to a wide range of day-to-day activities, accomplishments in the management and planning area included (i) participating in an NRC/CNWRA management meeting; (ii) demonstrating CNWRA/SwRI capabilities and activities to Commissioner Merrifield; (iii) interacting through telephone and video teleconference meetings with NRC management staff concerning tasking, spending, and hiring for the CNWRA during the balance of FY1999; (iv) further addressing COI-related topics among the NRC, SwRI, and CNWRA management staffs; and (v) participating in weekly HLW Management Board meetings.
Status of CNWRA staffing is indicated in table 1. A revised staffing plan continues to be developed and will be transmitted later this year as part of the modified CNWRA Management Plan. An interim plan was submitted to NRC management during the March 5, 1999, NRC/CNWRA Management Meeting. During period 6, intensive recruitment continued as additional database-and university-related sources were used to identify potential candidates. A IMS specialist resigned during this period, decreasing the total CNWRA staff.
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Computer system support activities encompassed (i) continuing the use of consultants to assist in development and implementation of the database retrieval system (replacement for CDOCS) and modification of existing databases and spreadsheets for management reporting; (ii) monitoring and modifying, as required, the SUN Microsystems and Silicon Graphics hardware and software associated with the GIS and IMS computing facilities and testing components in the Silicon Graphics hardware (iii) pursuing the installation and upgrade of standardized desktop computer systems; (iv) panicipating, as requested, in the monthly NRC/CNWRA Computer Coordination meeting; and (v) maintaining LAN operations.
QA activities focused on (i) preparing initial draft materials for training NRC staff to panicipate in observation audit teams; (ii) conducting surveillances, issuing nonconformance reports, as required, and working with cognizant staffin response to these reports; (iii) supporting the application of configuration control for CNWRA scientific and engineering software ready for release; (iv) preventing organizational COls by reviewing SwRI RFPs; (v) performing QA verification checks on each CNWRA deliverable; (vi) providing QA indoctrination for new CNWRA staff members; and (vii) determining potential audit areas for the CNWRA annual audit.
In the next period, the CNWRA staff expects to (i) provide to F. Miraglia, Deputy Executive Director of Operations, a review of CNWRA activities; (ii) revise the CNWRA Operations Plans for the Repository Program; (iii) continue to offer input to and participate in various NRC/CNWRA discussions / meetings relative to budget and resource requirements for FY1999,2000, and 2001; (iv) aggressively pursue hiring for unfilled core staff positions; (v) continue monitoring computer hardware and software for GIS and IMS computing facilities, routinely develop new, and modify existing, databases and spreadsheets, and examme the LAN configurations, including the CNWRA fire wall, 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 a draft outline of the Technical Specialist Audit Observation Training to cognizant NRC staff for their review, and (vi) possibly participate in a fact finding visit with the DOE representatives in Las Vegas as early as mid-April 1999.
1.2 Igneous Activity (IA)
Staff conducted field investigations this period at the Cerro Negro volcano, in Nicaragua, to provide an independent technical basis to confirm the quantity of airborne particles resuspended over young basaltic fall deposits. The quantity of resuspended, contaminated -
ash particles directly controls the radiological dose that could be received following a repository-penetrating volcanic event. Current TPA calculations constrain this parameter from deposits that have a limited analogy m i asaltic fall deposits. Staff measured airborne particle concentrations for static and distur'ad conditions on the 1995 Cerro Negro fall deposit. Concentrations were measured using a variety of filter assemblies, which trap 2
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particles in the 10-100 pm, 4-10 pm, and 1-4 pm size ranges. These size ranges correspond to inhalable, thoracic, and respirable particles, which are deposited in different areas of the respiratory tract and thus often have different dose conversion factors. Samples collected are still being analyzed for particle concentrations.
The surface layer of the 1995 Cerro Negro fall deposit appears significantly depleted in fine ash relative to fresh samples collected during the emption. The Cerro Negro area received
>3 m of rainfall during November 1998 as a result of Hurricane Mitch. Fine ash likely was washed into deeper layers of the very permeable fall deposit, leaving a surface layer that is ielatively rich in coarse, nonsuspendable particles. Very little resuspended ash was
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observed on filters that sampled static, undisturbed conditions, further indicating the surface
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layer was significantly depleted in resuspendable fines. Samples collected during surface disturbing activities such as walking, however, have visible resuspended ash, indicating that fines depletion did not extend more than about 5 cm below the surface. Granulometric analyses will be conducted on these fall deposit samples to quantify the amount of fines depletion that occurred due to environmental effects.
A detailed topographic map of the 1995 Cerro Negro cone also was made using differential GPS. This map wil! be used to refine volume calculations for the 1995 eruption and examine mechanisms to explain unusual near-veut accumulations of fall deposit during the 1995 and 1992 eruptions. In addition, this is the first map to accurately characterize the morphology of Cerro Negro and will provide an important reference during the next eruption.
Staff also began to respond to reviewers' comments on Xenolith Formation and the Development of Basaltic Volcanic Conduits During the 1975 Tolbachik Eruptions, Kamchatka, with Implications for Volcanic Hazards Assessments at Yucca Mountain, Nevada, which was submitted for publication in the Journal of Volcanology and GeothermalResearch. Design modifications were completed and construction commenced on the fluid physical analog laboratory at SwRI, and construction of the experimental apparatus for magma-repository interactions began at the University of Bristol.
In the next period, staff will analyze samples and data collected at Cerro Negro volcano, participate in planning tiie YMRP, and begin writing Rev. 2 of the IA KTI IRSR.
Modifications to the physical analog laboratory at SwRI will be completed. Construction of the experimental apparatus for magma-repository interactions will continue at the University of Bristol.
1.3 Structural Deformation and Seismicity (SDS)
Staff prepared for and participated in a DOE /NRC Appendix 7 meeting held at the FOC near YM and in Las Vegas, Nevada. The meeting included a one-half-day trip to view the Solitario Canyon fault exposed in the ECRB. The meeting focused on (i) characterization and application of fault and fracture data collected from surface exposures and in the ESF and ECRB; (ii) analyses of possible anomalous GPS strain rates using inferometry data; (iii) updates on the DOE PSHA, including estimations of the damping factor kappa; and (iv) discussion of YM tectonic models and their application as technical bases for both 3
probability estimations and performance evaluations. Staff also attended EARTHVISION training held at the NRC offices in Rockville, Maryland.
Staff held an informal one and one-half-day kickoff meeting with NRC staff on the augmented work to investigate the structure and sedimentological features of the alluvial aquifer in Fortymile Wash and the Amargosa desert.The meeting focused on available data that will help model the alluvial aquifer and on defining the specific structural and sedimentological traits of the alluvium that are critical to resolution of uncertainties about groundwater flow.
Staff submitted an abstract entitled Three-Dimensional Geometry of the Bare Mountain Fault (Nevada): Implications for Fault Kinematics and Basin Evolution. Preparation continued on. 3D Structural Modei of Northern Amargosa Desen for Input to USFIC-CNWRA Report and on Structural Evolution of Yucca Mountain and Crater Flat-Journal Article. The DOE PSHA and related documents were reviewed for Input to SDS IRSR, Revision 2, as were analyses of new TPA results on the sensitivity of repository performance to faulting. Staff also submitted an AI that summarized the SDS inputs to the KESA review of the DOE VA.
In the next period, staff will conduct field investigations of fracture exposures at YM. Staff will also prepare for and attend two DOE sponsored meetings, the Devil's Hole workshop on April 6-8,1999, and the Death Valley structure and tectonics workshop on April 9-11, 1999. Staff will also continue reviews of the DOE PSHA and VA in preparation for writing the SDS IRSR, Revision 2.
1.4 Evolution of the Near-Fleid Environment (ENFE)
Staff pursued debugging, testing, and documenting MULTIFLO Version 1.2. Errors in calculation of the Jacobian matrix in the implicit time-stepping formulation were corrected, resulting in factors-of-ten increase in convergence speed for some problems. Trials of the new mesh generation capabilities and the unstructured grid options in MULTIFLO were initiated. Coding of the open-drift ventilation model continued.
Advances have been made in MULTIFLO simulations of coupled THC processes in the proposed repository environment. Pseudothermodynamic parameters for four different YM glasses were estimated for 25 *C conditions, and progress is being made to characterize glass thermodynsmic and kinetic properties at elevated temperatures for repository modeling. Benchmarking chemistry results between MULTIFLO and EQ3/6 models also advanced. A detailed test case has been developed to compare the evolution of redox states and secondary mineral precipitation calculated by the two codes during the nonisothermal, kinetic, oxidative dissolution of uraninite. An abstract regarding this effort was prepared for the upcoming AGU meeting to be held on May 31-June 4,1999, in Boston, Massachusetts.
Staff continued review of the TSPA-VA Technical Basis Document and the DOE VA.
Statements concerning the status of issue resolution at the stafflevel are being prepared in 4
collaboration with visiting NRC staff relative to Input to ENFE IRSR, Rev. 2-Letter Report.
Staff participated in a DOE /NRC Appendix 7 meeting at the CNWRA on March 8,1999, to discuss natural analog work at Pena Blanca, Mexico. It was attended by approximately 12 representatives from the DOE and its contractors and 8 representatives from the NRC/CNWRA. The DOE desires to initiate analog work at the site with particular interest in underground studies. Preparations were made to attend the 8th European Commission Natural Analogue Working Group Workshop, to be held March 23-25,1999, in Strasbourg, France. A presentation was provided for NRC Commissioner Mernfield on CNWRA l
natural analog studies.
Aggressive efforts continued by several consultants and SwRI staff to advance activities on subjects supporting the ENFE KTI. Evaluation of the potential effects of microbial activity continued with development of a draft report, which is currently under review by CNWRA staff, Aqueous actinide chemistry review advanced. Staff produced a draft report on the progress of a literature study and experimental work on the performance of cement at elevated temperatures. Efforts continued ta initiate a subcontract with the University of Aberdeen forconductingadditional cement studies. A contract was placed with a consultant to assist with augmented work at the Nopal 1 natural analog site.
In the next period, staff will participate in the 8th European Commission Natural Analogue Working Group Workshop to be held March 23-25,1999, in Strasbourg, France, and give three presentations. A literoture study and experiments on the performance of cement at elevated temperature will continue. Staff will complete author draft and technical reviews of Input to ENFE IRSR, Rev. 2-Letter Report focusing on review of the TSPA-VA Technical Basis Document and the DOE VA Staff will continue debugging and benchmarking the MULTIFLO code and using the code to simulate the proposed repository near field. Near-field radioelement solubility modeling and aqueous actinide chemis'.ry studies, and sensitivity studies on the effects of cementitious matcrials wiU continue.
j 1.5 Container Life and Source Term (CLST)
Staff has continued preparing fne 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, ir.cluding carbon and SS, nickel-base alloys, and titanium alloys. Degradation processes of Zircaloy cladding and cer mic coatings also will be included.
Electrochemical co:Tosion testing continued to confirm the applicability of repassivation and corrosion potentials as predictive parameters for the long-term, localized corrosion of corrosion-resistant container materials !n chloride-containing solutions at 95 *C.The staff recently initiated three long-term tests with Alloy 22 specimens. Two tests using Alloy 825 specimens were continued, including a creviced specimen held at 100 mVscr. (50 mV less than the repassivation potential) in a 1,000 ppm chloride solution at 95 *C. No evidence of
!ocalized corrCon has been observed for a total test time of 1,278 days. A second Alloy 5
825 test specimen has been immersed in an air-saturated 1,000 ppm chloride solution at open circuit for a total test time of 1,132 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. All three Alloy 22 specimens have attached crevice forming devices and 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 monitcred.
Other Alloy 22 specimens are held at applied poten*ials of 400 and 700 mVseg to determine the time required for crevice corrosion ir.itiation as a function of potential. Although the staff does not anticipate that the corrosion potential of the material will approach such high potentials under open circuit conditions in air-saturated solutions, the purpose of these tests is to determine the initiation time for crevice corrosion of Alloy 22 in concentrated Nacl as a function of potential and the applicability of the repassivation potential to predict localized corrosion initiation.
l The passive dissolution rate of Alloy 22 has been measured in solutions containing 0.028 to 4 M chloride. Tests were conducted in both alkaline and acidic solutions. Additional tests will be performed with thermally aged and welded specimens in order to cuermine the possible effects of welding and repository thermal loading cn the passive dissolution rate.
Welded specimens have been received and are being prepared for testing. These tests will be conducted in autoclaves in 0.5 to 4 M chloride solutions at temperatures ranging from 95 to 175*C. The results will be compared to previous repassivation potential neasurements obtained with nonwelded specimens.
SCC tests cont nued on Alloy 22 and type 316L SS. Fatigue precracked, wedge-loaded I
i DCB specimens of each material have been immersed in a deaerated 5 percent Nacl l
solution, acidified to pH 2.7 by the addition of hcl, and heated to 90 *C to duplicate the conditions used at the LLNL. Tests on Alloy 22 used an initial stress intensity of 33 8
MPa m, while the type 316L SS specimens were tested at an initial stress intensity of 25 MPa m"2. No cracking was observed under these conditions for a cumulative test time of i
17 wk. In addition, no crack growth was observed in Alloy 22 specimens tested in 40 percent Mg,Cl at i 10 *C for 6 and 17 wk. On the contrary, significant crack growth was 2
observed in a 316L specimen using an initial stress intensity of 22 MPa mic fter 2 days of a
testing at the open circuit potential in 30 percent MgCl at 110*C, Additional tests with 2
316L specimens under applied potential conditivns will be performed in 30 percent MgCl2 at 110*C in order to determine the relationship between crack growth rate and potential. A modified WOL specimen design has been reviewed that will allow SCC tests to be performed with higher initial stress irtensities.
A [ n er titled Grain Boundary Chemistry and Intergranular Corrosion in Alloy 825 has been sent for approval as an IM. The paper will be submitted for publication in Metallurgical and Materials Transactions. The paper described and analyzed the results of research performed in previous years and was completed using a small expenditure of staff time during this FY.
The staff is examining the key environmental variables affecting the corrosion behavior of A516 carbon steel and the critical values of these variables in determining the occurrence of localized corrosion. In particular, the pH, chloride concentration, temperature, end redox 6
F l..
potential are being examined. Work continued on examining whether localized corrosion of A516 can occur under open circuit conditions in air-saturated solutions. Experiments designed to determine the repassivation potential ofcreviced A516 specimens as a function l
of environment were completed and further tests examining boldly exposed specimens were initiated. A paper entitled Effect of Fnvironmental Variables on Localized Corrosion of Carbon Steel and Implications on its Use in HLW Disposal was accepted for presentation at the 1999 NACE International Annual Corrosion Conference and will be submitted with additionni information for publication in Corrosion. It is under CNWRA review prior to submission as an IM.
A meetir(3 was held to discuss plans and methods on ways to monitor the chemical and electrochemical conditions of candidate WP construction materials under heat transfer conditions in a simulated repository heater test. A second meeting is scheduled for late March to discuss the preliminary findings on feasibility and possible approaches.
In the next period, staff will pursue long-term corrosion tests of Alloys 825 and C-22, together with SCC tests using Alloy C-22 and type 316L SS. Moreover, they will continue limited testing of A516 carbon steel.
I.6 Thermal Effects on Flow (TEF)
Numerical analysis of the DST continued during this reporting period. The DST is being 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. These results will be compared with other modeling results that have no loss through the bulkhead.
The second phase of the laboratory-scele boiling isotherm depression heater experiment continued during this period. Continued moisture and temperature evolution in the test cell suggests that a steady state was not attained during 4 mo of heating, as was the case in the first phase of the experiment. The second phase will proceed indefinitely to observe the continued heat and mass evolu* ion. Infiltration and drainage water was collected for conducting chemical analyses.
Staff continued the mountain-scale repository analyses. A non-structured grid has been generated to represent the new 2D vertical section. The ability of the MULTIFLO code to accommodate the modified grid is being assessed.
The status repcrt on evaluation of thermal-hydrologic model concepts, data, and DOE test results has been prepared and is undergoing CNWRA reviews. This status report will be submitted during the next reporting period as an IM.
l l
Staff participated in a DOE /NRC Appendix 7 meeting on Natural Analog Studies at Pena Blanca in San Antonio, Texas on March 8,1999. Data and analysis results collected by the i
l NRC and CNWRA were presented to the DOE at the meeting.
7 1
r Staff participated in a teleconference meeting with the NRC and the DOE on March 11, 1999 to prepare an agenda for the DOE /NRC Appendix 7 meeting on thermal testing to be held in Las Vegas, Nevada on April 28,1999.
Staff met to discuss a future coupled materials / thermal-hydrological laboratory-scale experiment. It is currently envisioned that the laboratory-scale heater test apparatus will be modified to provide a credible environment to observe and measure corrosion processes.
Staff continued, at a low level of activity, a review ofliterature to identify potential analog sites for the evaluation of water seepage from fractures into open drifts in the UZ.
Investigation of capillary diversion at the drift walls continued during this period. The laboratory-scale experiment designed to resolve the distinction between capillary diversion and dripping continued during this period. A profilometer is being used to map the topography of the fracture surface. It appears that the profilometer has sufficient resolution j
to provide meaningful detailed mapping of the fracture topography.
Formulation of an analytical / numerical solution to represent groove flow down a fracture through heated porous media continued.
Staff continued the review of the TSPA-VA Technical Basis Document, and the detailed review findings are being included in the next version of the TEF KTIIRSR.
In the next period, staff plans to (i) continue the second phase of the toiling isotherm penetration laboratory-scale experiment, (ii) continue a literature search for identification of potential dripping analog sites, (iii) test the MUL.TIFLO-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) prepare a subcontract with Columbia University to investigate dripping / fracture correlations, (vi) continue the revision of the TEF IRSR, and (vii) continue preparation of the journal article on the laboratory-scale heater test.
1.7 Repository Design and Thermal-Mechanical Effects (RDTME)
Staff continued the TM study of drift stability in the area where the transition from strong to weak rock occurs.Tiie objective of this study is to determine whether a synergistic effect exists that could adversely affect drift stability in ti.is area under thermal conditions. Two UDEC models were developed for this study. One model simulates a transition zone at the center of an emplacement drift and the second model simula'es a transition zone along the centerline of a pillar between two emplacement drifts.
During this period, staff continued the UDEC analyses to predict the size ar.d extent of rockfall under seismic loads in the repository thermal environment, and they are evaluating the fundamental process of damping and wave transmission through jointed medium handled by the UDEC code. In addition, staff pursued comparing the dynamic enalyses 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 in progress.
8
F The ABAQUS modeling of WPs ccntinued to investigate the thermal stress of WPs and also assess WP responses when subjected to the impact of falling rocks at various times.
Degradation of WPs with time will be ii.:luded 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 integnty.
Staff pursued the development of the review plan for preclosure aspects of design, construction, and operation.s of the repository using the integrated safety assessment methodology. A draft outline for the YMRP is being developed jointly by the NRC and CNWRA staffs.
Staff studied the behavior of the rock mass surrounding the emplacement drifts under heated conditions at the repository scale using the ABAQUS code. This study emphasizes rock mass behavior beyond the preclosure period and effects of thermal load on permeability changes in the surrounding rock mass.
Staff reviewed literature on concrete performance at high temperature to provide valuable information to assess the DOE design of the concrete liner for use at high temperature.
One staff member attended the DOE Enhanced Design Alternatives Workshop in Las Vegas, Nevada on March 8-9, 1999. Staff participated in a DOE /NRC teleconference meeting on March 11,1999 to prepare an agenda for the NRC/ DOE Appendix 7 meeting on thermal testing to be held in Las Vegas, Nevada on April 28,1999.
In the next period, staff plans to (i) investig.ae rock mass behavior under heated conditions on both repository and drift scales with an emphasis on long-term degradation of rock mass material properties and strengths, (ii) conduct rockfall simulations, (iii) use the AB AQUS code to model WPs, (iv) develop the standard review plan, and (v) attend the DECOVALEX meeting in Kalmar, Sweden.
1.8 Total System Performance Assessment and Integration (TSPAI)
The letter report entitled Review of Final Viability Assessment and Preparation of Comments for Commission Paper was submitted. The report documented staff concerns regarding the transparency and traceability of TSPA-VA calculations, major differences between DOE and NRC TSPA modeling approaches, input parameters, and major assumptions.
Staff made cosmetic code changes to the TPA Version 3.2 code and ran a suite of specialized test cases in preparation for the public release of the code. Five copies of the executable for the PC version of the code and one copy of the executable for the UNIX version of the code were submitted. A revised TPA Verrion 3.2 User's Guide, which is clearly marked as a draft document, was sent to the NRC for forwarding to the DOE and placement in the PDR.
I i
Staff pursued the data generation for sensitivity analyses using the TPA Version 3.2 code and conducted code testing on an as-needed basis. Activities relt.ted to comparing NRC and l
9
DOE cesults continued using the TPA code, NRC data, DOE data, and DOE published results. Staff continued implementing sensitivity analysis methods for data analyses.
Because of staff shonage and to accommodate inputs from various KTIs, the delivery date of the IM associated with this work has been rescheduled to July 12,1999.
Staff continued to merge the PVM, PC, and SUN Solaris versions of the TPA Version 3.2 code into a single code to reduce the costs of code maintenance.
The letter report outlining the general parameter tree approach and the feasibility of implementing this procedure as part of a TPA post-processor was delivered. A journal anicle detailing the parameter tree approach was submitted as an attachment to the letter repon.
A jot.inal article entitled Importance Measures for Nuclear Waste Repositories was submitted to fulfill an IM. This version of the journal anicle, which incorporates revisions suggested by the NRC, will be submitted to Reliability Engineering and System Safety for publication.
Suppon was provided to the NRC staff in resolving comments from the NRC technical editor and in making changes to volume I of the sensitivity studies report prior to its publication as a NUREG.
The NRC and CNWRA held discussions on the scope and schedule for revision 2 of the TSPAI IRSR. A joint brainstorming meeting was held on developing a general approach for the multiple barriers concept.
Staff traveled to the Cerro Negro volcano in Nicaragua to collect and analyze suspended ash particle size distributions. The collected data will be used in refm' ing 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 extrusive volcanism.
i The eight candidates who will serve as external reviewers of the TPA Version 3.2 code have been sent formal letters of invitation and paperwork for establishing consulting contracts. Despite attempts at avoiding scheduling conflicts, two of the reviewers will be unable to panicipate in the meeting scheduled for the week of April 26-30,1999. Because it is difficult to find replacement reviewers on short notice, the meeting may be postponed until the Summer of this year.
During the visit of Commissicner Merrifield to the CNWRA offices in San Antonio, 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.
A staff member has been transferred to the PA element from the CSPE element to fill one of the open PA modeler positions. In addition, it is expected than an offer will soon be extended to an outside candidate for the other PA modeler position. Recruiting continues for the health physics and risk analyst positions.
10
i i
In the next period, the staff will focus on (i) comparing the TSPA-VA and the TPA Version j
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 will include contributions from other KTIs; and (iv) preparing revision 2 of the IRSR.
l Recruitment will continue for the two PA modelers, the health physicist, and a risk analyst.
1.9 Activities Related to Development of the N RC High Level Waste Regulations (ARDR)
I Detailed modeling continued to evaluate the effects of well characteristics and plume dimensions on the accuracy of estimates of doses from the groundwater transport pathway.
Following evaluation of the BICFLOW code for simulating groundwater flow, software bugs were identified for correction and verification in accordance with QA requirements.
Assuming no further complications, a report will be completed by the end of June 1999.
Investigation intensified on topics pertaining to calculation of age-specific doses at YM.
Detailed age-specific dose modeling was completed with the GENII-S code and results were summarized for the NRC project manager to aid preparation for a public meeting in Nevada. Additional refinements to the analyses will continue.
l Continuing support for the VA review effort this period included completion of confirmatory BDCF calculations using the GENII-S code and DOE VA input parameter information.The resulting new set of B DCFs was provided for use in new TPA calculations based on DOE data.
Revisions to the previously issued report,Information and Analyses to Support Selection of Critical Groups and Reference Biospheres for Yucca Mountain Exposure Scenarios, were reviewed. Staff delivered a report entitled Improvement to Approach for Modeling Dose. It is expected the report will be issued as a NUREG/CR-a key reference document for the rulemaking effort and TSPAI activities.
i In the next period, staff will conduct detailed flow and mass transport calculations for the borehole dilution study. Refinements to assessment of age-specific DCFs will be comple'ed. As a joint effort, staff also will begin investigating the feasibility of an improved (stochastic) dose module for the TPA code to replace the lookup table approach currently in use. If the draft EPA Standard is published, staff will assist the NRC with reviewing it and preparing comments.
1.10 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC)
Formal Review of DOE UZ Studies-Letter Report, was submitted. This document provides a detailed technical review of the DOE approach to modeling infiltration, deep percolation, drift seepage, UZ flow and transport beneath the proposed repository at YM, and methods of abstracting UZ process models for TSPA analyses.The report also provides a review of alternative conceptual models for infiltration, flow, and transport in the UZ.
Staff collaborated with the NRC working group on SZ flow. Some of the findings of the working group are beirg documented in Input to NRC Working Group on Viable SZ 11
Conceptual Flow Models, presently in preparation. Progress of the working group during this period ir.cludes development of a 2D site-scale flow model for the SZ at YM. This model will be used to investigate the importance of major structural features and horizontal anisotropy. Model development, using the Micro-Fem Version 3.0 suite of flow and tra ; sport modeling software, has been led by an NRC staff member on staff exchange at the CNWRA.
A trip report was prepared to document the effons and preliminary results of the geophysical surveys conducted during the last period in the Amargosa Region and Fortymile Wash. Results of this survey will also be included in Input to NRC Working Group on Viable SZ Conceptual Flow Models.
Investigations continued on the problem of drift seepage and capillary diversion of deep percolation away from open drifts. An unstructured grid has been created for the isothermal drift seepage model. This grid is being tested against results from a structured grid for the same problem to work the errors out of the mesh generation algorithm. A quasi-linearized series solution for seepage exclusion from a circular cylindrical drift with a non-smooth wall is being developed. Effon is also being made to fm' d a simpler solution for the boundary layer problem with the same geometry.
Staff continued the analysis of C-Wells hydraulic and tracer testing. Data reduction and interpretation are nearing completion and preparation of Modeling and Analysis of C-Well Tests-Letter Repon has begun. The NRC PEM has requested that the delivery date for this milestone be extended to June 18,1999, so that information gained during an upcoming Appendix 7 meeting on C Wells testing can be incorporated into the report.
Revisians were made to Fcnnal Review of DOE SZ Studies-Letter Repon which is presently undergoing internal review. This repon reflects the current CNWRA status of understanding of the DOE approach to modeling SZ flow and transport at YM.
Abstracts for the Spring 1999 AGU meeting were submitted on the topics of(i) Assessing Changes in Deep Percolation Over a Glacial Cycle Due to Linked Changes in Climate, Soils, and Vegetation at Yucca Mountair., Nevada; (ii) Dripping into Subterranean Cavities From Unsaturated Fractures; (iii) The Effect of Cavity Wall Roughness on Seepage into Underground Openings; (iv) Hydrogeological Inferences From Thermal and Chemical Measurements; (v) Using Barometric and Earth-Tide Responses to Infer Vertical Connectivity in the Tuff Aquifer; and (vi) Geophysical and Hydrogeological Studies Along a Fault Zone.
Evaluation of hydrologic effect of heterogeneity in the nonwelded units, PTn and CHn, continues for the UZ flow and transpon characterization. Dampening of episodic flow and the potential for nonuniform flow leading to fast pathway movement through the PTn are the focus of a stochastic modeling exercise in the nonwelded unit above the repository.
Addressing the uncenainty of the flow paths for radionuclide transpon through the variably I
altered, partially welded to nonwelded CHn is the focus of the characterization and modeling of flow below the repository. Characterization includes an analysis of 12
I 4
1 geochemical, mineralogical, and hydrological data in order to better understand the development of the perched water bodies.
Progress continues on the inclusion of vegetation and soil modules into the YM infiltration model. This model is used to help estimate infiltration under future climate ch mges.
Shallow 'nfiltration directly translates to percolation rate at the repository horizon in the current conceptualization of flow in the UZ. In addition, the effect of surface runoff and lateral subsurface flow on the focusing ofinfiltration continues to be evaluated for current i
and future climate conditions. A new IM, Infiltration Abstractions for Shallow Soil Over f
Fractured Bedrock in a Semi-Arid Climate-Journal Paper, documenting some of this work l
is proposed in table 2 of this PMPR.
In the next period, USFIC activities will include (i) continued development of the site-scale model of the YM tuff aquifer to investigate viable conceptual models for SZ flow, (ii) preparation of Modeling and Analysis of C-Well Tests-Letter Report, j
(iii) panicipation in an Appendix 7 meeting on C-Wells Testing,(iv) observation of a DOE-sponsored workshop on m.~Jeling flow and transport in the UZ, (v) preparation of Input to NRC Working Group on Viable SZ Conceptual Flow Models, (vi) continued investigation of models for seepage and dripping in underground cavities, and (vii) participation in the development of the YMRP.
i 1.11 Radionuclide Transport (RT)
Preparations were made for a presentation at a special session on the Pe5a Blanca analog site at the 8th European Commission Natural Analogue Working Group Workshop, to be held March 23-25,1999, in Strasbourg, France. The presentation will present an overview of the history of uranium alteration, mobi'ization, and transport at Pe5a Blanca, based on CNWRA chemical and isotopic studies. Implications of the results for performance assessment will be stressed. Molecular dynamics simulation and surface complexation modeling of radionuclide sorption nn mineral mixtures continued during this reponing period. These activities will be described in two presentations, Molecular Dynamics I
Simulation of ' Uranyl Adsorption on Quartz Surfaces and Experimental and Modeling i
Studies of Uranyl Adsorption onto Binary Mixtures ut Silicate Minerals, at the American Chemical Society national meeting March 21-25,1999, in Anaheim, California.
l CNWRA staff completed the manuscript Stochastic Analysis of Early Tracer Arrivals in a Multiple Fracture Pathway. This paper is proposed as a new deliverr.ble in table 2 of this PMPR, Stochastic Analysis of Fracture Transport-Journal Paper.
Benchmarking between the codes GWP and EQ3 was performed to compare the results of U speciation calculations as a function of pH at 25 'C. Nine species were considered in this test, and the resulting calculated speciation generally compares well between the two codes.
However, the pH sensitivities of UO CO (aq) vary somewhat, and the cause(s) are being 2
3 examined.
Preparation is underway of materials for Np sorption experiments on alluvium materials.
Initial experiments will use two sources of calcite (i) reagent-grade calcite that is 13
recrystallized to provide a more uniform crystal form and grain size, and (ii) crushed natural calcite crystals (Iceland spar) from Mexico. The recrystallization of the reagent-grade calcite is in progress. Initial experiments will be conducted under atmospheric CO (8) 2 panial pressures in solutions at equilibrium with calcite over a range of pH from about 7 to 8.5. Experiments will then be expanded to include a range of CO (8) Partial pressures that 2
adequately bound those found in the subsurface at YM. As data are collected on sorption of Np in solutions at equilibrium with calcite, additional experiments will investigate solution conditions where calcite dissolves and precipitates.These experiments will provide a range of Np retardation data that can be used under a wide variety of geochemical conditions. Uranium sorption experiments on mixed minerals (clinoptilolite and quanz) also continued during this period. Experiments with 20.0 g/L clinoptilolite were completed.
Glove box experiments continued to ir vestigate sorption on mineral mixtures under limited CO (g) conditions.
2 Efforts were undertaken to establish a consulting agreement to provide support in molecular dynamics simulations and stochastic fracture transport modeling, and to initiate work on ion exchange modeling with a current CNWRA subcontractor.
In the next period, staff will present technical assistance results at the American Chemical I
Society national meeting, and at the 8th European Commission Natural Analogue Working Group Workshop. Staff will continue sorption experiments on alluvium minerals, including calcite. Revision of the RT IRSR 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, NRC staff comments were received on the draft report titled Low-Activity Waste Feed Makeup, Solidification, and Offgas Treatment Process System Hazard and Safety Issues Report for TWRS-Letter Report and will be incorporated in the final report to be delivered on July 30,1999. Staff has continued to work on the draft report titled Low-Activity Waste Auxiliary Support Systems II-Systems Hazard & Safety Issues Report for TWRS-Letter Repon. Its current scheduled delivery date is April 30,1999.
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 repon is currently due May 28,1999, and a final version, with changes to address additional NRC comments,is scheduled for submission July 30,1999.The Hanford TWRS HLW Chemistry Manual, to be published as NUREG/CR-5751, was submitted on February 26,1999.
In subtask 2.1, a report titled Review of Hanford Immobilized Low-Activity Tank Waste Performance Assessment was delivered. The NRC staff comments on the report titled Review of British Nuclear Fuels Limited, Inc. Design Safety Features Deliverable:
Hydrogen Control in High-Level Waste Storage Tanks were received via e-mail and are beirg incorporated in a revised report. The revised repon will be delivered on April 9, 1999.The CNWRA received BNFL,Inc. Design Safety Featurcs February 1999 deliverable and the staff has reviewed 9 out of 10 examples presented in volume II of the package.
14
7 1..
Draft comments were e-mailed to the NRC PO as they were generated. A final report will be delivered to the NRC on April 9,1999. Based on discussions with the NRC staff, this subtask will be augmented with a task to develop a Microsoft Access database for TWRS.
The database will include information relevant to the BNFL, Inc. process equipment design and safety features. NRC staff will participate in the CNWRA/NRC staff exchange and work with the staff to develop the database. No deliverable will be due on this task in FY1999.
In subtask 2.2, NRC staff comments were received on the repon titled Integrated Design Inspection Program for Radioactive Waste Treatment / Nuclear Material Production Facilities and will be incorporated in the final report to be delivered on April 9,1999.
Based on discussions with the NRC staff, IM 1403-202-910 will be changed to Quality Assurance Inspection Program for Radioactive Waste Treatment / Nuclear Material Production Facilities scheduled for delivery on May 28,1999, and IM 1403-202-920, Revised Inspection Procedure for 36000 Series (Final), will be removed from the FY1999 j
Operation Plan for TWRS.
1 In the next period, in subtask 1.2, staff will continue work on Low-Activity Waste Auxiliary
{
Support System II-Process System Hazard and Safety Issues Report for TWRS-Letter i
Report. In subtask 1.6, the staff will incorporate NRC comments on the pretreatment report.
In subtask 2.1, the staff will complete editorial, technical, and programmatic reviews of the report titled Review of BNFL,Inc. Design Safety Features February 1999 Submittal and incorporate NRC comments on the repon titled Review of British Nuclear Fuels Limited, Inc. Design Safety Features Deliverable: Hydrogen Control in High-Level Waste Storage Tanks. In subtask 2.2, the staff will revise Integrated Design Inspection Program for Radioactive Wane Treanner.t/ Nuclear Material Production Facilities and continue work on Quality Assurance Inspection Program for Radioactive Waste Treatment / Nuclear Material Production Facilities analysis.
1.13 Three Mile Island Unit 2 Independent Spent Fuel Storage Installation (TMI 2 ISFSI)
The TMI-2 final SER was submitted to the NRC on February 26,1999. Interactions between the NRC and the CNWRA staffs continued to assist the NRC staff to prepare TMI-2 ISFSI Materials License No. SNM-2508. This license is scheduled to be issued during the next reporting period.
In the next period, TMI-2 ISFSI staff plans to assist the NRC staff to prepare TMI-2 ISFSI Materials License No. SNM-2508, 1.14 Dry Transfer System (DTS)
Review and evaluation of the DOE response to the NRC first round RAI and development of the second round RAI continued. The revised SFPO Operations Plan, which included an accelerated schedule for the DTS project activities, was submitted during this reporting period. Preparation of an outline of the SER was initiated during this period.
t I
15
In the next period, DTS staff plans to continue review and evaluation of the DOE response to the NRC first round RAI, develop the second round RAI, and prepare the outline of the SER.
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 was initiated, !uring this reporting period. A CNWRA consultant attended the NRC/SAIC meeting at NRC headquarters on storage WP overpack on. March 10,1999.
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 while awaiting instruction to revise the draft AR and the computer coda RISKIND.
'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 l' contentions continued during this reporting period. Two PFSF staff attended the NRC/PFS meeting at NRC headquaners on site characterization reports on February 18,1999.
In the next period, the staff plans to review the PFS response and site characterization repons, pn., are the draft SER, and assist the NRC staff on ASLB hearing.
1.17 Savannah River Site Aluminum Based Spent Fuel (SRSASF)
Revisions to the letter report, Evaluation of the U.S. Depanment of Energy Aluminum-Based Spent Fuel Criticality have been initiated. New reports sent by DOE on Creep Analysis and Functional Performance Requirements were received.
The repon, Review of the U.S. Depanment of Energy Preliminary Evaluation of Aluminum-Based Spent Nuclear Fuel-Draft Report, has been merged with Review of the U.S. Depanment of Energy Preliminary Evaluation of Aluminum-Based Spent Nuclear Fuel-Final Repon due to budgetary constraints. The delivery date has been moved from September 30,1999, to August 6,1999, to enable completion of CNWRA and NRC reviews prior to FY2000.
In the next period, the revision of the letter report, Evaluation of the U.S. Department of Energy Aluminum-Based Spent Fuel Criticality, will be completed. Additional reports sent by the DOE will be reviewed.
2 MANAGEMENTISSUES None to report.
16
p l
l 3
MAJOR PROBLEMS 1
L None to report.
4.
SUMMARY
OF SCHEDULE CHANGES Schedule changes for IMs are included in table 2. Completed deliverables are noted on table 3.
5
SUMMARY
OF FINANCIAL STATUS Table 4 summarizes the CNWRA financial status in the context of authorized funds. Total commitments are $556,474. The appendix lists ple.nned and actual costs to date, as well as variances between these, without allowance for fee, on both a peoperiod and a cumulative basis. These data do not include commitments. Pertinent financial information is provided for the DWM JC, including l
COPS and ten KTIs, TWRS JC, TMI-2 ISFSI JC, DTS JC, CISF JC, PFSF JC, and SRS ASFJC. 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 i.c consistent with the aggressive CNWRA hiring plan. A revised staffing plan was presented during the November 1998 CNWRA Annual Program Review, and another revision was included in materials presented at the March 1999 NRC/CNWRA Management Meeting. Current staffing remains below authorized levels and dedicated recruitment continues.
Period 6 FY1999 CNWRA composite expenditures ro:,e 7.9 percent from the previous period, and this aggregate of all JCs was underspent by $1,123,965 or 18.0 percent. When comparing period 6 with last period, the DWM, TMI-2 ISFSI, DTS, CISF, PFSF, and SRSASF JCs evidenced higher f
spending levels while only the TWRS JC showed a 12wer level.
J The DWM JC was underspent by $943,306 or 17.7 percent. Overall expenditures increased 7.6 percent from the previous period as costs rose in the IA, ENFE, TEF, TSPA, and RT KTIs but declined in COPS and the SDS, CLST, RDTME, ARDR, and USFIC KTIs. Costs to date are 32 percent above those a year ago, and period 6 costs are 34 percent greater than the same period last year. Despite the FY 1999 budget being 24 percent greater than FY1998 and the FY1999 year-to-I date cumulative variance 55 percent higher than that for FY1998, initiation of the augmented scope
)
of work, coupled with the aggressive recruitment of core staff and the engagement of consultants and subcontractors, provides an encouraging outlook for the CNWRA to attain its spending targets by the end of FY1999.'
The TWRS JC was underspent by $118,752 or 25.8 percent. Alsough spending decreased from the previous period, staff have intensified securing SwRI and consultant support to accommodate augmented work scope and expected spending.
The TMI-2 ISFSI JC was overspent by $7,457 or -5.4 percent. Despite the rise in spending from last period, the cumulative variance fell significantly because of an adjustmer.t that was made in the l
spending plan for period 6. Costs reflect the delivery of the TMI-2 final SER and assistance to the
[
NRC staff in preparing TMI-2 ISFSI Materials License No. SNM-2508. About 99 percent of this l
17
.I
fiscal year's tasking was completed during the first six periods. Accordingly, the current cost overrun will decline as activities, too, diminish.
The DTS JC was underspent by $3,669 or 4.6 percent. Expenditures, again, increased significantiy from the previous period, consistent with delivery of the revised SFPO Operations Plan that included an accelerated schedule for the DTS project. Additional activities included staff review of the DOE response to the NRC first round RAI, developtnent of a second round RAI, and preparation of the draft SER.
The CISF JC was underspent by $40,678 or 42.1 percent. Notwithstanding an increase in the cumulative variance, spending rose compared with the previous penod because a detailed technical review of the Topical Report on HI-STAR /HI-STORM cask system deployment at high-seismic sites f
- was initiated. Staff awaits NRC instruction to revise the draft AR and the computer code RISKIND.
j I
The PFSF JC was overspent by $13,862 or -21.1 percent. Expenditures increased 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.
1 The SRS ASF JC was underspent by $38,879 or 74.6 percent. Spending rose from last period with l
the incorporation of NRC staff comments on a previously delivered report and initiation of new efforts related to review of other DOE documents. Costs are expected to continue to fall well below plan, at least in the near term, because of limited tasking.
Expenditures on SwRIlabor, consultants, and subcontractors as a proportion of composite spending on all JCs were 20.2 percent. Expense of consultants and subcontractors as a fraction of composite 3
spending on all JCs was 9.2 percent. The CNWRA remains committed to enhance, where appropriate, participation of consultants and subcontractors in the conduct of CNWRA work.
As shown in table 1, the CNWRA has 52 staff members, reflecting the resignation of a specialist in IMS. The available pool of approved consultants and subcontractors is 40.
This FYTD no capital or sensitive equipmem aas purchased with NRC funds (other than overhead, general and administrative expenses, and fee).
DWM JC The DWM JC cumulative cost variance was 17.7 percent. Expenditures in this JC increased by 7.6 percent compared with period 5. Specific explanations for over/ underspending for COPS and each KTI follow.
The cost variance for COPS was 18.1 percent: 16.6 percent for the Management, Planning, and Computer Support subtask (158) and 24.1 percent for the QA subtask (159). Total spending in subtask 158 rose relative to last period but fell for subtask 159. Spending on labor mirrored total
. spending in both tasks. Other Direct Costs declined in subtask 158 from the previous period but remained approximately the same in subtask 159. In the next period, spending in subtask 158 may remain close to this period's expenditure. Aggressive recruitment continues for a clerical and 18 1
l
technical staff member. Computer-related consultant (s) to upgrade the CNWRA IMS have been engaged. CNWRA management has encouraged eligible staff to participate in professional development activities. In subtask 159, spending should remain below estimates until the lead auditor-directed preparations begin, usually in period 7, for the annual QA audit. Preparations continue for scheduling training of the NRC technical staffin accordance with the augmented scope of work in subtask 159.
The cost variance for the IA KTI was 15.1 percent. Although spending rose compared to last period, the underspending is due to the spending plan augmentation that occurred in period 6. This perid'*
expenditures are consistent with expected spending in the next periods. In addition, field wo.:
expenses for the trip to the Cerro Negro will be posted in a later period.
The cost variance for the SDS KTI was 10.2 percent. Expenses declined from the previous period and the inclusion of augmented funding to be used in the characterizr. tion of the alluvium aquiter causeJ the cumulative variance to increase. As this work progresses, this variance will decrease.
The cost variance for the ENFE KTI was 16.9 percent. The significant reduction in variance from the last period is due largely to changes in the spending plan for period 6 associated with a reallocation of funds among KTIs. In the future, new work (on cement properties and Pe a Blanca studies) is anticipated to further reduce the variance. It remains uncertain when the contracts will be fully executed and at what dates the costs associated with this new work will be posted to the account; however, tlee matters are being pursued aggressively.
The cost variance for the CLST KTI was 7.1 percent. The allocation of additional funding to the CLST KTI at the beginning of period 6 resulted in cumulative underspending for the first time this FY. It is anticipated that the increased staffing and the activities dercribed in Section 1.5 of this PMPR will result in meeting the budget target at the end of the FY.
The cost variance for the TEF KTI was -0.2 percent. This cumulative overspending is the result of higher spending during period 6, payment made during period 6 oflagging charges from consultants and subcontractors, and a one-time reduction of FY 1999 allocation for the TEF KTI. Future actual expenditures are expected to continue following the budget for this KTI.
The cost variance for the RDTME KTI was 19.0 percent. 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 continue during the next two periods. However, the FY1999 total expenditures are expected to converge to the FY1999 allocation, due to reassignment of staff to this KTI's activities and a new hire.
The cost variance for the TSPAI KTI was 26.4 percent, little changed from the previous period despite a substantive increase in spending. The cost variance for period 7 is likely to remain the same unless the staff begins the augmented work on development of a TPA post-processor.
The cost variance for the ARDR KTI was 49.4 percent.This variance is lower than the last period and reflects a reallocation of funding to other KTIs. There is still no indication the draft EPA Standard will be released for review in the coming months, so underspending will continue indefinitely. Additional emphasis will be placed on developing new tasking during the next period.
19
The cost variance for the USFIC KTI was 9.1 percent, continuing the trend in reduction of percentage variance in the last two periods and the reallocation of funding. Existing commitments not yet posted to the account further reduce the current variance to 5.3 percent. In the near term, the variance is expected to increase slightly until additional staff join the CNWRA and costs for upcoming field work are realized.
The cost variance for the RT KTI was 32.0 percent. This decrease in percentage variance relative to period 5 spending r esulted as funds were reallocated to other areas and commitments were posted.
The planned addition of a laboratory technician during the next period together with additional invoices from ongoing and planned work by consultants are anticipated to reduce the variance somewhat in coming periods.
The cost variance for the TWRS project was 25.8 percent. It is anticipated that spending will continue at this rate in the next period. Based on the discussions with the NRC staff, an additional task was included in subtask 2.1 to augment current spending. The staff effort is being augmented through thejudicious use of consultants and SwRI staff to achieve timely completion of milestones.
The cost variance for the TMI-2 ISFSI project was -5.4 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 percent of the FY 1999 tasking within the TMI-2 ISFSIproject was completed during periods 1-6.
As a result, the cost overrun will decrease sign 7 antly in the next few periods because of reduced activities. FY1999 total expenditures are expected to converge to the FY1999 allocation.
The cost variance for the DTS project was 4.6 percent. It is significantly lower than that of the previous period and is consistent with the delivery of the revised SFPO Operations Plan. Despite an increase in this period's spending compared to the last three periods, this cost underrun is due to delay in receiving the DOE response to the NRC first round RAI. Now that this has been received, expenditures are expected to increase significantly and remain close to the increased FY1999 allocation to review and evaluate the DOE response, develop the second round RAI, prepare an outline for SER, and prepare the draft SER. The FY 1999 total expenditures are expected to converge to the FY1999 allocation.
1 The cost variance for the CISF project was 42.1 percent, which reflects continued low expenditures relative to the plan. Now that the review of the HI-STAR /HI-STORM cask system Topical Report has been initiated, this cost underrun will decrease in the near term. However, this cost undemm will increase again until the CNWRA receives instruction from the NRC on the desired scope for revising the computer code RISKIND and revising the draft AR.
The cost variance for the PFSF project was -21.1 percent. Although the per period expenditures during the next few periods will be lower than that of period 6, the cost overrun will continue 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 I contentions. The FY1999 total expenditures are expected to converge to the FY1999 allocation for this project.
The cost variance for the SRSASF was 74.6 percent. Spending increased from the previous period and is expected to continue as the staff reviews additional DOE reports in the next period. The 20
budgeted amount for this project is expected to decrease substantially. 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 l
21 1
Table 1. CNWRA Core Staff--Current Profile and Hiring Plan * (Period 6)
Pe.Ri 0,
EmertiseFamerience Current No.
Professional Staff FY1999 ADMINISTRAT10N 4
H GARCIA. W PATRICK. J RUSSEIL B SAGAR CHEMICAL PROCESSING 2
VJAIN. D.DARUWA11A ENGNG / PHYS. CHEM-G)DE ANALYS!$/DEVEIDPMENT 2
R JANE 17.KE. R MARITN 1
DATA MAN AGEMENT/ PROCESSING.
I P.MA1DONADO INCI UDING FIN ANCIAL DOSE /RISIUHAZARD ANALYSIS 0
I E11C!1tOCHEMISTRY l
G CRAGNOlJNO ENGINEERING 2
R.CHEN. G.OFOEGBU GEOLOGY 0FDLOGICAL ENGNO ENVIRONMENTAL SCIENCES I
P laPIANTE GEOCHEMISTRY 7
P.BERTETTI. LBROWNING. W. MURPHY. R.PAB ALAN, E PEARCY. I PRIKRYL D 1URNER j
GEOHYDROLOGY/HYDROGEOLOGY 5
D.FARRE1J R.FEDORS.R. GREEN.M. HILL J WIN 1 ERIE I
GEOIDGY '
3 F IAFEMIN A. LMcKAGUE. M MIKLAS HYDROIDGIC TRANSPORT 3
A ARMSTRONG. D HUGHSON. S PAIN 1ER 1
INIORMATION MANAGEMENT 0
1 SYSTEMS
~
M ATERIAL SCIENCES 4
5 BROSSIA. D DUNN. Y-M PAN. N SRIDHAR 2
MECHANICAL.
0 1
INCLUDING DESIGN & FABRICATION MINING ENGINEERING I
S-M HSIUNG NUCIIAR ENG'.NEERING I
M J ARZFMB A OPERA 110NAL HEALTM PHYSICS 2
II;EERE. J WEIDY PERFORMANCE ASSESSMENT 3
S.MOHANTY. O. PENS ADO-RODRIGUEZ.
1 0 %TITMEYER OUAIIlY ASSURANCE 1
B MABRITO RADIOISOTOPE GEOCHEMLTIRY I
D PICKFTT ROCK MECHANICS.
2 A.CHOWDHURY. A.GHOSH INCLUDING CIVII/STRUC FNGNG SOURCE-TERM / SPENT FUF1 DEGR AD 0
1 STRUCTURALGEOLDGYI 3
D.FERRIIL D. SIMS. J.STAMATAKOS SEISMO-1TflDNICS SYSTEMS ENGINEERING 1
P.MACKIN VOIfANOLOGY/lGNEOUS 2
C.CONNOR B. Hill PROCESSES TOTAL 52 9
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_c Table 4. Financial Status (Period 6)
Funds Funds Funds Project Nannes Authorised Casted to Date Uncosted Conunitinents COPS 3,476,342 2,295.702 1.180,640 1,812 IA 1.345 % 2 994.695 350,367 124.937 SDS 1.825.699 1.330.411 495,288 38.207 ENFE I.781,331 1.104.679 676,652 98.366 CLST 1,704.818 1.157.329 547,489 31.583 TEF 1.322.606 891.287 431,320 22.514 RDTME 1,319.682 726.842 592.839 19.429 TSFAI 3,577,966 2.154.986 1.422,980 3,950 ARDR 697,208 282.762 414.446 0
USFIC 2.288.030 1.495.633 792,397 28,866 RT 1,369.634 701,744 667.890 103.122 DWM Costs 20,708.378 13.136.069 7,572.309 DWM Award Fee 1,196.006 493.569 702.437 DWM Base Fee 828.335 511.663 316.672 TOTAL DWM 22.732,719 I4,141.301 8,591,418 472,786 TWRS Costs 1.583.378 1.123.165 460.213 1,922 TWRS Award Fee 93.654 46.214 47.440 TWRS Base Fee 63.335 44.308 19.027
'IDTAL TWRS 1,740.367 1.213.687 526.680 1.922 TMI 2 ISFSI SAR Costs 282.197 280,619 1.578 21,671 TMI-2 ISFS1 SAR Award Fee 15,223 7,711 7,512 TMI-2 ISFSI Base Fee 11.288 10.918 370 TOTALTM1-2 ISFSI S AR 308,708 299,248 9.460 21,671 DTS Costs 309,952 213.311 95.641 19.845 DTS Award Fee 19,480 7.924 11.556 DTS Base Fee 12.398 8.409 3.990 7DTAL DTS 341,830 229.644 112.186 19,845 CISF Costs 409,053 278.340 130.713 20.032 CISF Award Fee 24.338 12,848 11,490 CISF Base Fee 16.362 11.001 5,362 TOTAL CISF 449.753 302.189 147,565 20.032 PFSF Costs 275.068 194.728 80,340 20,218 PFSF Award Fee 16,185 6.827 9.358 PFSF Base Fee 11,003 7.766 3,237
'IDTAL PFSF 302,255 209.321 92,935 20.218 SRSASF Costs 113.185 79.570 33,615 0
i SRSASF Award Fee 7,110 3.992 3,118 SRSASF Base Fee 4.527 3.257 1.271 TOTAL SRSASF 124.823 86.819 38.004 0
GRAND TOTAL 26,000,456 16,482.208 9,518,248 556,474 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 each award fee program represent award fee reserved from last authorizations based on Operations Plans for FY1999.
25
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