ML20196L161
| ML20196L161 | |
| Person / Time | |
|---|---|
| Site: | 07200020 |
| Issue date: | 05/20/1999 |
| From: | CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES |
| To: | NRC |
| Shared Package | |
| ML20196L159 | 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-99-8, NUDOCS 9905270040 | |
| Download: ML20196L161 (43) | |
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I CNWRA PROGRAM MANAGER'S PERIODIC REPORT ON ACTIVI, TIES OF THE CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES i
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For the Fiscal Reporting Period April 10,1999 - May 7,1999 PMPR No. 99-8 May 20,1999 i
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TABLE OF CONTENTS hection Page
' TABLES........................................'.................................iv I
i A B B REV IATIONS...... -..............................................
............ y EXECUTIVE SUMM ARY-PERIOD 8...........................................
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1 TECH N ICA L.............................................................
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1.1 CNWRA Operations (COPS)........................................... 1 i
1.2 Igneou s Activity (IA)................................................... 2 l.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)................ 10 1.9 Activities Related to Development of the NRC High-Level Waste
'l Regulations ( ARDR)................................................... 1 1 1.10 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC)........... I1 1.11 Radionuclide Transport (RT)...........................................
13 1.12 Tank Waste Remediation Systems (TWRS)..............................
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- 1.13 Three Mile Island Unit 2 Independent Spent Fuel Storage Installation (TMI-2 ISFSI).............................................. 15 1.14 Dry Transfer System (DTS)... -.......................................... 15 1.15 Centralized interim Storage Facility (CISF)................................ 15 1.16 Private Fuel Storage Facility (PFSF)....................................... 16 1.17 Savannah River Site Aluminum-Based Spent Fuel (SRSASF).................. 16 2
M ANAGEMENT IS S UES.....................................................
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' 3' M AJ OR PROB LEM S....................................................... 16 4
SUMM ARY OF SCHEDULE CHANGES....................................... 16
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5 SUMM ARY OF FINANCIAL STATUS.........................................
16 APPENDIX-Planned and Actual Costs, and Cost Variances Period 8-FY1999 i
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d TABLES-1 Table Page 1
CNWRA Core Staff-Current Profile and Hiring Plan * (Period 8) 21 2
Summary of Schedule Changes (Period 8)..................................
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Deliverables (Period 8) 4 23 4-Financia1 Status (Period 8)...................................................... 24 5'
Private Fuel Storage Facility License Fee Cost Recovery Status (Period 8)............. 25 i
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' Jn ABBREVIATIONS
[D One-Dimensional CDOCS Consolidated Document Management 2D Two-Dimensional System 3D Three-Dimensional CDROM Compact Disk Read Only Memory AA Atomic Absorption CDS Compliance Determination Strategy AAI Average Annualinfihration CDTS Commission Decision Tracking System ACD Advanced Conceptual Design CEB Center for Environmental Biotechnology ACF Alumina (in excess of alkali feldspar).
CEC Commission of the European i
Calcium Oxide, Ferromagnesian Oxide Communities ACNW Advisory Committee on Nuclear Waste CFD Computational Fluid Dynamics ACRS Advanced Computer Review System CFR Code of Federal Regulation ACS American Chemical Society CHn Calico Hills Nonwelded Tuff ADAMS Agencywide Documents Access and CIAC Computerincident Advisory Capability Management System CISF Centralized Intenm Storage Facility AECL Atomic Energy of Canada Limited CLST Container Life and Source Term AES Atomic Emission Spectrometry CM Configuration Management AWF Antler Wash Fault CNWRA.
Center for Nuclear Waste Regulatory 3
AGU American Geophysical Union Analyses Al-Administrative item COI Conflict ofinterest ALTS Apache Leap Test Site COPS CNWRA Operations AML Areal Mass Loadmg CPP Cyclic Potentiodynamic Polarization ANS Amencan Nucistr Society CQAM CNWRA Quality Assurance Manual
' ANSI American National Standards Institute CRG Center Review Group AO Annotated Outline CRM Corrosion Resistant Material t
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AP Administrative Procedure CRWMS Civilian Radioactive Waste APB Acid-Producing Bactena Management System AR Assessment Report CSCS Constrained Stochastic Climate ARDR Activities Related to Development of Simulator the NRC High Level Waste Regulations CSH Calcium Silicate Hydrate ASCE American Society of Civil Engineers CSPE Corrosion Science and Process ASCII American Standard Code for Engineering Information interchange DAS Data Acquisition System ASLB~
Atomic Safety and Licensing Board DBE Design Basis Event ASME American Society of Mechanical DC Division of Contracts Engineers DCAA Defense Contract Audit Agency ASTM American Society for Testing and DCB Double Cantilever Beam Materials DCF Dose Conversion Factor
'ASU Arizona State University DCM Dual Continuum Model ATDTS Automated Technical Data Tracking D&D Decommissioning and Decontamination l
System DECOVALEX Development of Coupled Models and BDCF Biosphere Dose Conversion Factor Their Validation Against Experiments BEG Bureau of Econonne Geology in Nuclear Waste Isolation BFD Basis for Design DEIS Draft Environmental Impact Statement BM Bare Mountain DEM Digital Elevation Model BMF Bare Mountain Fault DF Dilution Factor BTT' Branch Technical Position DFCSS Division of Fuel Cycle Safety and CAI Color Alteration Index Safeguards i
CAM Corrosion Allowance Material DIE Determination ofimportance CAR Corrective Action Request Evaluation CCDF Complementary Cumulative DIMNS Division ofIndustrial and Medical Distribution Function Nuclear Safety
- CCL Commitment Controlleg DKM Dual Permeability Model CCM Constant Capacitance Model DLG Digital Line Graph CD-R CDROM Recordable DLM Diffuse Layer Model i
CDF Cumulative Distnbution Function DNAG Decade of North American Geology CDM Compliance Determination Method DNFSB Defense Nuclear Facilities Safety Board
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DOE U.S. Department of Energy i
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ABBREVIATIONS (cont'd)
DOE-DP U.S. Department of Energy Defense GEM General Electrochemical Migration Program GEOTRAP Geologic Transport of R Adionuclides 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 Digital Terrain Elevation Data GFM Geological Framework Model DTS Dry Transfer System GHGC GeoHydrology and Geochemistry DWM Division of Waste Management GIA Generalized importance Analysis EBS Engineered Barrier System GIS Geographic Information System EBSER Engineered Barrier System GLGP Geology and Geophysics Experimental Research GMS Goundwater Modeling System EBSPAC Engineered Barrier System.
GPS Global Positioning System Performance Assessment Code GROA Geologic Repository Operations Area ECM Equivalent Continuum Model.
GS Geologic Setting ECRB
- Enhanced Charactenzation of Repository GSA Geologic Society of America Block GTFE Great Tolhachik Fissure Eruption EDO Office of the Executive Director for.
GUI Graphics User Interface Operations -
GWB Geochemist's Workbench EDX Energy-Dispersive X Ray Spectroscopy GWS1 Groundwater System lntegration EIS Environmental Impact Statement GWTT Groundwater Travel Time EM Element Manager HE Hydrogen Embnttlement EMPA Electron MicroProbe Analysis HLUR High-level Waste and Uranium ENE East Northeast.
Recovery Projects Branch ENFE Evolution of the Near-Field HLW liigh-level Waste Environment HRTEM liigh-Resolution Transmission Electron ENGB Engineering and Geosciences Branch Microscopy EnPA Energy Policy Act of 1992 IA Igneous Activity ENS European Nuclear Society IBM International Business Machines
' EPA U.S. Environmental Protection Agency 1CP Inductively Coupled Plasma EPR Electrochemical Potentiokinetic ICPP Idaho Chemical Processing Plant Reactivation ICRP International Commission Radiological EPRI Electric Power Research Institute Protection EQA Extemal Quality Assurance IDLH Immediately Dangerous to Life and EROS Earth Resource Observation System Health ESF Exploratory Studies Facility IHLRWMC International liigh-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 INETER Instituto Nicaraguense de Estudios FEHM Finite Element lleat and Mass Transfer TERritoriales FEM Finite Element Method INTEC Idaho National Technology and FEP Features. Events, and Processes Engineering Center FFRDC Federally Funded Research and INTRAVAL Intemational Code Validation Development Center 1/O Input / Output FFT Fast Fourier Transform IP Inspection Procedure FOC Field Operations Center IPA Iterative Performance Assessment FTE Full-Time Equivalent IR&D Intemal Research & Development FIP File Transfer Protocol IRIS Interim Records Information System FY Fiscal Year IRM Office ofInformation Resources IYII)
Fiscal Year-To-Date Management GDF -
Ghost Dance Fault IRSR lssue Resolution Status Report VI
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ABBREVIATIONS (cont'd)
I ISA Initial Safety Analysis NEl Nuclear Energy Institute ISFSI Independent Spent Fuel Storage NFS Network File Server Installation NIOSil National Institutes Of Safety and licalth ISM Integrated Site Model NIR Near-infrared IVM Interactive Volume Modeling NIST National Institute of Standards and IWPE Integrated Waste Package Expenments Technology JC Job Code NMSS Office of Nuclear Material Safety and JPL Jet Propulsion Laboratory Safeguards JRC Joint Roughness Coefficient NNE North-Northeast KESA Key Elements of Subsystem Abstraction NNW North-Northwest KTl Key Technical issue NOAA National Oceanographic and KRJ Key Technical Uncertainty Atmospheric Administration LA License Application NRC Nuclear Regulatory Commission LAAO License Application Annotated Outline NS North-South LAN local Area Network NSRRC Nuclear Safety Research Review LANL Los Alarrms fiational Laboratory Committee LARP License Application Review Plan NTS Nevada Test Site LAW low-Activity Waste NUREG NRC Technical Report Designation LBNL Lawrence Berkeley National Laboratory NWPA Nuclear Waste Policy Act, as amended LBT Large Block Test NWTRB Nuclear Waste Technical Review Board Lils Latin flypercube Sampling OBES Office of Basic Energy Sciences LITC Lockheed Information Technology OCRWM Office of Civilian Radioactive Waste Company Management LLC Limited Liability Company OGC Office of General Counsel LLNL Lawrence Livermore National OITS Open-Item Tracking System Laboratory OMB Office of Management and Budget LLW low-level Waste OPS Operations Plans for the Repository LMAES Lockheed Martin Advanced Program Environmental Systems ORR Operations Readiness Review LSS Licensing Support System ORS Overall Review Strategy LSSPP Licensing Support System Pilot Project OWFN One White Flint North LSSTB Licensing Support System Test Bed PA Performance Assessment LWR Light Water Reactor PAAG Performance Assessment Advisory M
Molar Group Ma Million Years Ago PAC Potentially Adverse Condition MAI Mean AnnualInfiltration PAllT Performance Assessment and MAP Mean Annual Precipitation Hydrologic Transport I
MAT Mean AnnualTemperature PASP Performance Assessment Strategic Plan l
MC Monte Carlo PC Personal Computer METRA Mass and Energy Transport PC/TCP Personal Computer / Transmission MGDS Mined Geologic Disposal System Control Protocol Mil Mechanical-flydrological PDF Probability Distribution Function MIC Microbially influenced Corrosion PDR Public Document Room MINC Multiple INtcracting Continua PEL Permissible Exposure Limit MIT Massachusetts Institute of Technology PEM Program Element Manager MM Major Milestone PER Prelicensing Evaluation Report MO Management and Operations PEST Parameter Estimation MOU Memorandum Of Understanding PFD Probabilistic Fault Displacement MPC Multi-Purpose Canister PFDilA Probabilistic Fault Displacement l
MRS Monitored Retrievable Storage Hazard
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MSS MultiSpectral Scanner PFS Private Fuel Storage MTU Metric Ton of Uranium PFSF Private Fuel Storage Facility NAS National Acaderny of Sciences P11A Preliminary llazard Analysis NAWG Natural Analogue Working Group Pl Principal Investigator NCR NonConformance Report PMDA Program Management, Policy NEA Nuclear Energy Agency Development and Analysis Staff Vii
ABBREVIATIONS (cont'd)
PMPR '
Program Manager's Periodic Report SECY Secretary of the Commission Office of PMT Photo-Multiplier Tube the (NRC)
PNNL Pacific Northwest Natmnal Laboratory SELM Spectral Element Method PO Project Officer SEM Scanning Electron Microscopy PPA _
Proposed Program Approach SER Safety Evaluation Report PPE Prepassivated Platinum Electrode SFPO Spent Fuel Project Office PRA Probabilistic Risk Assessment SFVF San Francisco Volcanic Field PRT Peer Review Team SGI Silicon Graphics Inc.
PSAG Probabilistic System Assessment Group SGML Standard Generalized Markup PSHA Probabilistic Seisriue Hazard Analyses Language PTFE Polytetrafluoroethylene SHE Standard Hydrogen Electrode PTn Paintbrush Nonwelded Tuff SHT Single Heater Test PVHA Probabilistic Volcanic Hazards SIP Scientific Investigation Plan Assessment SKI Swedish Nuclear Power Inspectorate PVilVIEW Probability of Volcanic Hazards S-L Short Transverse-Longitudmal VIEW SLAR Side Looking Airborne Radar PVM Parallel Virtual Machine SNF Spent Nuclear Fuel PWR Pressurized Water Reactor SNL Sandia National Laboratories QA Quality Assurance SOTEC Source Term Code QAP Quality Assurance Procedure SOW Statement Of Work QRAM Quahty Requirements Application SPCR Software Problem Correction Report Matrix SRA Systematic Regulatory Analysis RAI Request for AdditionalInformation SRB Sulfate-Reducing Bacteria RASA Regional Aquifer System Analysis SRBS Shafts, Ramps, Boreholes, and heir RDCO Repository Desi n, Construction, Seals F
and Operations SRD Software Requirements Description RDTME.
Repository Design and Thermal.
SRS Savannah River Site Mechanical Effects SRSASF Savannah River Site Aluminum-REE Rare Earth Element Based Spent Fuel REECO Reynolds Electrical and Engineenng SS Stainless Steel Company, Inc.
SSC Structures, Systems, and Components RES Office of Nuclear Regulatory Research S~mM Scanning Transmission Electron RFP Request For Proposal Microscopy RH Relative Humidity STP Staff Technical Position RIP Repository Integration Program SUFLAT Stochastic Analyses of Unsaturated ROC Repository Operations Criteria Flew And Transpon RPD Regulatory Program Database SVF Springerville Volcanic Field RRT Regulatory Requirement Topic SwRI Southwest Research Institute RSRG Real Space Renormalization Group SZ Saturated Zone RT Radionuclide Transport TA Technical Assistance RTS Radwaste Treatment System TAN Test Area North SAIC Science Application International TBD To Be Determined Corporation TBM Tunnel Boring Machine SAP Standards Approval Package TCP/IP Transmission Control Protocol /
SAR Safety Analysis Report Internet Protocol SCA Site Characterization Analysis TDEM Time-Domain Electro-Magnetic SCC Stress Corrosion Cracking TDI Technical Document Index SCCEX
. Substantially Complete Containment TDOCS Technical Document Reference Example Databuse System SCE Standard Calomel Electrode
'EDE Total Effective Dose Equivalent SCFF Southern Crater Flat Fault TEF nermal Effects on Flow SCM.
Surface Complexation Models TEM Transmission Electron Microscopy SCP Site Characterization Plan THC
%ermal-Hydrologic-Chemical SDMP Site Decommissioning Management Plan THMC Rennal-Hydrologic-Mechanical.
SDS'
- Structural Deformation and Seismicity Chemical T.L Transverse lengitudinal Viii
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I ABBREVIATIONS (cont'd)
TE,M Triple-Layer Model WOL Wedge-Opening Leading
'l TM Thermal-Mechanical WP Waste Package TMil Thermal Mechanical flydrologic WSEI Waste Systems Engmeering and i
TMI.2 Three Mile Island Unit 2 Integration TMS The Minerals, Metals, and Materials WSRC WestinF ouse Savannah River h
Society Company
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TOP Technical Operating Procedure WSS Waste Solidification Systems i
"IT' Technical Position WTSO Washington Technical Support Office TPA Total system Performance Assessment WVDP West Valley Demonstration Project TPI Time Period of ReFulatory Interest WVNS West Valley Nuclear Services TR2 DOE Seismic Topical Report No. 2 WWW World Wide Web TRG Technical Review Group XPS X-ray Photoelectron Spectroscopy TSAR Topical Safety Analysis Report XRD X-Ray Diffractometry TSPA Total System Performance Assessment YM Yucca Mountain TSPA-VA Total System Performance Assessment-YMP Yucca Mountain Project Viability Assessment YMR Yucca Mountain Region TSPAl Total System Performance Assessment YMRP Yucca Mountain Review Plan and Integration YMSCO Yucca Mountain Site Charactenzation TSw-Chnv Topopah Spring Welded-Calico Office Ilills Nonvitric YTD Year-To-Date TVD Total Variation Diminishing TWFN Two White Flint North TWINS Tank Waste Information Network System TWRS Tank Waste Remediation System UA University of Arizona UACll Universidad Aut6 noma de Chihuahua UCLA University of California les Angeles UDEC Universal Distinct Element Code l
UK United Kingdom UNLV University of Nevada. Las Vegas UNM University of New Mexico UR Uranium Recovery U.S.
United States USDA U.S. Department of Agriculture USGS U.S. Geological Survey UTM Universal Transverse Mercator USFIC Unsaturated and Saturated Flow Under Isothermal Conditions UZ Unsaturated Zone VA Viability Assessment VCS Version Control System VF Vitnfication Facility VSIP Vertical Slice Implementation Plan WAN Wide Area Network WAPDEG Waste Package Degradation WBS Work Breakdown Structure WCIS Waste Containment and Isolation Strategy WFO Work For Others WGB Western Great Basin WIPP Waste Isolation Pilot Plant WMB Waste Management Branch WNYNSC Western New York Nuclear Service Center ix
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SUMMARY
-PERIOD 8 In the Division of Waste Management (DWM) Job Code (JC), the Center for Nuclear Waste Regulatory Analyses (CNWRA) demonstrated CNWRA capabilities and activities to Commissioner Greta Joy Dieus.
Moreover, staff gave a presentation on observation audit techniques to the Nuclear Regulatory Commission (NRC) staff and delivered input to the Evolution of the Near-Field Environment Issue Resolution Status Report, Revision 2-Letter Report. The staff produced three journal papers: A Discrete-Fracture Boundary Integral Approach to Simulating Coupled Energy and Moisture Transport in a Fractured Porous Medium.
Experimental and Modeling Study ofIon Exchange Between Aqueous Solutions and the Zeolite Mineral Clinoptilolite, and Abstraction of Mechanistic Sorption Model Results for Performance Assessment Calculations at Yucca Mountain, Nevada. These papers have been or will be submitted for acceptance in recognized technicaljournals. Staff also participated in workshops, symposia, and other technical meetings.
The DWM JC year-to-date (YTD) cost variance was 16.5 percent. Spending fell from the previous period as a result of decreased activity in specific key technical issues.
In the Tank Waste Remediation System (TWRS) JC, staff delivered the draft report, Low-Activity Waste Auxiliary Support Systems II-Process Systems Hazard and Safety Issues Report for TWRS-Letter Report; minor revisions on the Hanford TWRS High-Level Waste Chemistry Manual (NUREG/CR-575 !) to address NRC editorial staff comments, along with change pages; and a revised report on the BNFL, Inc. Design Safety Features. Preparation continued on the Quality Assurance Inspection Program for Radioactive Waste Treatment / Nuclear Material Production Facilities. In addition, staff started developing a presentation on the Vitrification of Radioactive Wastes to the Regulatory Unit of the Department of Energy. The YTD cost variance was 25.2 percent. Spending increased from last period and the cumulative percentage variance decreased to the level of period 6.
In the Three Mile Island Unit 2 (TMI-2) Independent Spent Fuel Storage Installation (ISFSI) JC, the staff provided input to the Spent Fuel Project Office lessons learned process and to the NRC Project Officer in response to Environmental Defense Institute comments on the TMI-2 ISFSI flooding issue. The YTD cost variance for the TMI-2 ISFSI was -4.0 percent. The cumulative variance decreased, as expected.
In the Dry Transfer System (DTS) JC, staff submitted Second Round Request for Additional Information, DTS-Draft Letter Report. Staff pursued preparation of the final version of the second round request for additional information (RAI) and development of the safety evaluation report (SER). The YTD cost variance was 2.5 percent, reflecting a substantial rise in spending from last period.
In the Centralized Interim Storage Facility (CISF) JC, staff continued its detailed technical review of the Topical Report on HI-STAR /HI-STORM cask system deployment at high-seismic sites, began development of the first round RAI, and pursued work on the computer code RISKIND. The YTD cost variance for the CISF was 27.3 percent. Periodic spending increased substantially from the previous period.
In the Private Fuel Storage Facility (PFSF) JC, staff reviewed and evaluated site characterization reports, prepared the draft SER, and revised the NRC draft position on five Group I contentions. The YTD cost variance was -9.1 percent. Although spending declined from the previous two periods, the cost overrun is expected to continue for several periods.
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SUMMARY
-PERIOD 8 (cont'd)
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. In the Savannah River Site Aluminum-Based Spent Fuel JC, staff reviewed U.S. Depanment of Energy documents to complete Review of the U.S. Department of Energy Preliminary Evaluation of Aluminum-
- Based Spent Nuclear Fuel-Final Report. The.YTD cost variance was 74.9 percent, a slight decrease in percentage terms from last period.
Current spending estimates in all JCs are based on the assumption that staffing is consistent with the aggressive CNWRA hiring plan. A revised staffing plan was presented in conjunction with the delivery of the CNWRA Management Plan, Revision 7, Change 0. Current staffing remains below authorized levels, and recruitment continues.
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CNWRA PROGTiAM MANAGER'S PERIODIC REPORT ON ACTIVITIES OF THE CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES IITLE 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 i
JOB CODES: D1035, J5164, J5186, J5206, J5226,35210 1
NRC CNWRA PROGRAh! h1ANAGER: John J. Linehan,(301)415-7780 NRC CNWRA DEPUTY PROGRAM MANAGER: Deborah A.DeMarco,(301)415-7804 CNWRA PRESIDENT: Wesley C. Patrick,(210) 522-5158 ESTIMATED BUDGET: $87,611,477 PERIOD OF PERFORMANCE: 09/27/97-09/27/02 PERIOD OF THIS REPORT: 04/10/99-05/07/99 1
TECHNICAL i
1.1 CNWRA Operations (COPS)
In addition to a wide range of day-to-day activities, accomplishments in the management and planning area included (i) presenting an overview of CNWRA capabilities and activities to Commissioner Greta Joy Dieus:(ii) reviewing the status of CNWRA spending, scheduling, and staffing with NRC management: (iii) providing information concerning the development of NRC budgets for the next two fiscal years; (iv) addressing COI-related topics among the NRC, SwRI, and CNWRA management staffs; and (v) participating in weekly HLW Management Board meetings.
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The status of CNWRA staffing is indicated in table 1. During period 8, intensive recruitment continued and several sources were used to identify potential candidates. A materials scientist willjoin the staffin period 9, and a hydrologist and a health physicist are considering offers of employment.
Computer system support activities encompassed (i) continuing the use of consultants to develop and modify software and perform systems administration for the Sun Microsystems, Silicon Graphics, and Windows NT servers:(ii) installing and upgrading the standardized desktop computer systems; (iii) examining the need to revise the CNWRA Security System (firewall);(iv) transmitting the Assessment of Need for" ADAMS" Client 1
r Installations at the CNWRA;(v) participating, as requested,in the monthly NRC/CNWRA Computer Coordination meeting; and (vi) maintaining LAN operations.
QA activities were directed to (i) presenting Training Module on Observation Audit Techniques to the NRC staff April 19,1999; (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 COI by reviewing SwRI RFPs: (v) performing QA verification checks on each CNWRA deliverable; (vi) providing QA indoctrination for new CNWRA staff members and consultants; and (vii) preparing for the CNWRA annual audit scheduled forJune 8-11,1999.The QA Audit team leader has been selected, as have the technical specialists and auditors. The Audit Plan was issued this period.
In the next period, the CNWRA staff expects to (i) prepare f'or an NRC/CNWRA management meeting; (ii) continue to offer input to and participate in various NRC/CNWRA discussions / meetings relative to budget and resource requirements for FY1999, 2000, and 2001; (iii) aggressively pursue recruitment for unfilled core staff positions; (iv) continue use of consultants to mitigate staff attrition, oversee administration of server hardware and systems / applications software, develop new and modify existing databases and spreadsheets, and examine the LAN configurations, including the CNWRA firewall, for necessary modifications to maintain effectiveness; and (v) provide CNWRA LAN operation and maintenance support.
In addition, the staff will (i) perform scheduled and unscheduled QA surveillances; (ii) conduct QA indoctrinations for CNWRA staff and consultants; (iii) review SwRI RFPs for potential COI; (iv) perform QA verification checks on each CNWRA outgoing deliverable;(v) schedule the second presentation ofTraining Module on Observation Audit Techniques to appropriate NRC staff, likely July 1999; and (vi) complete preparations for the June 1999 CNWRA audit, including the audit checklist.
1,2 Igneous Activity (IA)
Staff completed revisions to the Input to IA IRSR, Revision 2-Letter Report during this period. The focus of this revision was to evaluate the technical basis for IA dose calculations presented in the DOE TSPA-VA. Probability models in the TSPA-VA are not consistent with currently available tectonic models and geophysical data. Staff concludes 4
that an annual probability of 10 provides a reasonably conservative measure for volcanic disruption of the proposed repository site. The low radiological doses calculated for volcanic events in the TSPA-VA depend primarily on WP and waste form resilience.
Continued review oflimited available information does not support significant resilience of these systems when entrained into an actively empting volcano. Additional analyses presented in this IRSR show WP failure is likely during igneous event. oue to thermal i
loading effects, and that ascending magma systems likely have sufficient ciriving pressure j
to propagate upward through drift walls.
Final revisions of two articles on probabilistic volcanic hazards assessments for YM are being prepared for the Journal of Geophysical Research. The journal editor requested the papers be condensed into a single manuscript, which the authors agreed to do. Also, staff 2
f was requested to submit to Natural Hamrds (journal) a manuscript on probabilistic volcanic hazard assessments for nuclear facilities.
The development of physical analog and numerical models for magma-repository interactions continued. Staff participated in the second National Research Council meeting to review the USGS volcanic hazards program and plans to write the probabilistic volcanic hazards portion of this review. YMRP development continued in this period, with staff helping to integrate current acceptance criteria into proposed review plan outlines. Staff prepared presentations for the YM special session at the AGU Spring meeting and for the TSPA-VA technical exchange.
In the next period, staff will present the results of ongoing 1A risk calculations at the AGU Spring meeting. Staff will prepare ar.d present technical bases for TPA models and evaluations of TSPA-VA models at the DOE /NRC technical exchange. Staff will hold informal discussions with ACNW staff to focus presentations planned for the June 1999 ACNW meeting in San Antonio, Texas. Refinement of the experimental apparatus and development of numerical models for magma-repository interactions will continue at the University of Bristol. Staff from the University of Bristol will visit CNWRA during the coming period to report on results ofinitial numerical experiments. Staff will prepare for field investigations at the Big Pine volcanic field to evaluate relationships between mapped faults, locations of basaltic volcanoes, and ongoing GPS strain-rate studies.
1.3 Structural Deformation and Seismicity (SDS)
Staff participated in a DOE-UNLV meeting on April 19,1999, to discuss the planned UNLV analyses of fluid inclusions from YM. The UNLV analyses are part of a DOE-funded grant that will allow UNLV researchers to collect up to 200 new calcite samples from the ESF and the Cross Drift for fluid inclusion analyses. The goal of the study is for the USGS, State of Nevada, DOE, and UNLV scientists to reach a consensus on the interpretation of fluid inclusion data from YM. As part of the grant proposal, UNLV plans to hold quarterly meetings to collect and discuss data and results and to update all interested parties on the progress of the study. This meeting in Las Vegas, Nevada, was the first of these quarterly meetings. A staff member presented an overview of preliminary results from a study of calcite in faults within the ESF.
Staff planned for upcoming field work (May 12-20,1999) that will examine the structural and sedimentological architecture of the alluvial aquifer. The field work is part of the augmented work for the SDS KTI. Staff also prepared for the upcoming AGU Spring J
meeting. Preparation started on the paper, Three-Dimensional Geometry of the Bare i
Mountain Fault (Nevada): Implications for Fault Kinematics and Basin Evolution.
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Staff helped revise a USFIC deliverable, Input to NRC Working Group on Viable SZ Conceptual Flow Models which summarizes the work of the Structural Effects on Flow Working Group. Staff added refinements to the northern part of a 3D structural model for the Amargosa Desert, which will be documented in Resolve Selected Field Relationships for 3D Structural Model of Amargosa Desert for input to USFIC-CNWRA Report.
Analysis continued on the structural evolution of Yucca Mountain and Crater Flat, which will be reported in Strain Distribution and Tectonic Setting of Yucca Mountain and Crater Flat-Joumal Article.
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Additional sensitivity studies of direct WP rupture from faulting in the repository were conducted using the FAULTO module of the TPA code.These sensitivity studies will.be in the revision to the SDS IRSR.
In the next period, staff will conduct field work to study the structural and stratigraphic framework of the alluvial aquifer. Staff will also concentrate on Revision 2.0 to the SDS IRSR.
1.4 Evolution of the Near Field Environment (ENFE)
Input to ENFE IRSR, Revision 2-Letter Report was transmitted during this period. This deliverable was focused on a review of the TSPA-VA based on general acceptance criteria and a new statement on issue resolution at the staff level. ENFE and NRC staffs will continue to collaborate and provide contributions to Revision 2 of the ENFE IRSR, as requirements are specified.
ENFE staff prepared a trip report and continued writing papers for submission to the proceedings of the 8* European Commission Natural Analogue Working Group Workshop held in Strasbourg, France, March 23-25,1999. One of these papers is proposed (table 2) as a new deliverable titled PeSa Blanca Natural Analog Data in Performance Assessment Models-Journal Paper.
Studies of the Nopal I natural analog site continued. Preparations were made to respond to the DOE request for samples from Nopal I. The DOE wishes to resolve their interpretation (from limited earlier analyses) of 400,000 yr of closed-system U evolution with the contrasting CNWRA model of open-system, episodic release, and transport. Final culling and shipping of samples awaits formal NRC direction. In addition, studies progressed on the time scales and magnitude of U release at Nopal I, including (i) sample selection for new CNWRA U-series dating of secondary carbonate and opal (timing of U release pulses) and jarosite (timing of U mineral oxidation) and (ii) plans for field studies, including mapping and sampling of such secondary deposits.
Staff participated in the NRC review of the DOE Disposal Criticality Analysis Methodology Topical Report. The CNWRA staff review will emphasize (i) geochemical models of waste form degradation relative to fissile materials and (ii) models of accumulation of fissile materials in the near field external to the WP. Staff attended a May 5,1999, DOE /NRC technical exchange in Las Vegas, Nevada, that primarily covered criticality model formulation and validation.
Staff continued debugging and testing the MULTIFLO code, Version 1.2. The METRA flow module was successfu;1y benchmarked against published results for multiphase flow in the vicinity of a strongly heated repository. Minor variances attributable to differences 3
in the numerical algorithms were noted for some combinations of parameters. The unstructured grid capabilities of METRA were successfully tested on single. and dual-continuum applications in two and three dimensions. Staff are developing a 1 D steady-state now and reactive transport model of YM using the dual-continuum formulation in MULTIFLO in an attempt to model ambient pore water geochemistry. Design concepts for simulation of hydrogeochemical processes in the near-field environment at YM were crafted into GEM and METRA files that run successfully in stand-alone mode. In its current 4
form, this model describes a dual matrix-fracture continuum with 12 hydrogeologic units.
each containing a combination of 9 kinetically reacting minerals. Constructing the initial framework for the input involved discretizing the grid, as well as constraining the geometric, chemical, and hydrologic properties of the model. Steady-state flow calculated using the METRA module was coupled with preliminary simplified geochemistry in the GEM module, however, some problems still exist with regard to boundary conditions.
Staff pursued a literature review and experimental studies on the performance of cement at elevated temperatures. A subcontract is in progress with the University of Aberdeen for conducting additional cement studies. Development of thermodynamic properties ofcement minerals at elevated temperatures continued.
An abstract on near-field water-rock interactions was prepared and is in internal review for an invited presentation for the meeting Interactions Fluides-Mineraux Dans La Croute, Paris, France October 14-15,1999.
In the next period, staff will participate in a technical exchange on PA, scheduled for May 25-28,1999, in San Antonio, Texas. Revision of the ENFE IRSR will continue. Papers for the proceedings for the NAWG workshop will be submitted. Preparations will be made for a QA audit of the CNWRA ENFE KTI to be held in period 9. A literature study and experiments on the performance of cement at elevated temperature will progress. Staff will debug and benchmark the MULTIFLO code, using the code to simulate the proposed repository near field. Near-field radioelement solubility modeling and aqueous actinide chemistry studies together with sensitivity studies on the effects of cementitious materials will continue.
1.5 Container Life and Source Term (CLST)
CNWRA and NRC staffs discussed the revisions to the IRSR, and the CNWRA prepared an outline. Comments received from the NRC staff, including those on the content of the IRSR manual style and format, are being considered for implemention in the IRSR, Revision 2.
CNWRA staffcontinued preparing Assessment of Performance issues Related to Alternate EBS Materials and Design Options, due June 18,1999. This report will summarize the materials, characteristics, and corrosion processes that may affect the major classes of materials considered for construction of the containers for the various WP designs,
{
including carbon steel and SS, nickel-base alloys, and titanium alloys. Degradation processes of Zircaloy cladding and ceramic coatings also will be included.
Electrochemical corrosion testing continued to confirm the applicability of repassivation and corrosion potentials as predictive parameters for the long-term, localized corrosion of corrosion-resistant container materials in chloride-containing solutions at 95 *C. The tests 3
were interrupted during this reponing period so that the test specimens could be inspected i
for signs of localized corrosion. After inspection, tests using Alloy 825 specimens continued, including a creviced specimen held at 100 mVscr (50 mV less than the
]
repassivation potential) in a 1,000-ppm-chloride solution. No evidence of localized
{
corrosion was observed for a total test time of 1,323 days. A second Alloy 825 test j
specimen has been immersed in an air-saturated 1,000-ppm-chloride solution at open circuit 1
5 l
l l
J
for a total test time of 1,177 days. Crevice corrosion was observed on this specimen several times during the test when the corrosion potential exceeded the repassivation. potential.
Three Alloy 22 specimens with attached crevice-forming devices are being tested in 4M Nacl solution at pH 8. One specimen is tested under open circuit conditions in an air-saturated solution so that the time-dependent changes in the corrosion potential can be monitored. No localized corrosion was detected on an Alloy 22 specimen held at an applied potential of 400 mV ct. Extensive pitting and crevice corrosion were observed, however, 3
- on this specimen when held at an applied potential of 700 mVsct. The specimen tested at 700 mV cc was replaced with a new Alloy 22 specimen, now being tested at an applied.
3 potential of 500 mVsco to determine the time required for crevice corrosion to begin as a function of potential.
The passive dissolution rate of Alloy 22 was measured in solutions of various pHs (0.7,2, and 8) containing 0.028-4 M chloride at 25 and 95 *C. Tests are now being conducted on specimens thermally aged for 24 hr at 800 *C. Under such aging conditions, the formation of p phase is expected at the grain boundaries. It should be noted that the formation of intermetallic phases including p-phase,' may occur as a result of WP fabrication and welding processes. The passive dissolution rate of Alloy 22 was significantly increased as a result of the thermal aging treatment. Severe intergranular corrosion of the thermally aged
- specimen was observed at an applied potential of 400 mVsce in 4 M chloride solution at
' 95 *C. Measurements of the repassivation potentials of welded specimens continued using an autoclave in 0.5-4M chloride solutions at temperatures ranging from 95 to 150 *C.
Marked localized corrosion preferentially developed at the welds was observed in the welded specimens, which also exhibit lower repassivation potentials than those measured.
in nonwelded specimens.
Staff continued SCC tests of Alloy 22 and type 316L SS specimens. Fatigue precracked, wedge-loaded DCB specimens of each material were immersed in a deaerated 5 percent Nacl solution, acidified to pH 2.7 by the addition of hcl, and heated to 90 *C to duplicate the conditions used at the LLNL. Tests on Alloy 22 used an initial stress intensity of 33 MPa m"2,~while the type 316L SS specimens were tested at an initial stress intensity of 25 MPa m'8. No cracking of the two alloys was observed under these testing conditions for a cumulative test time of 21 wk. Testing under open-circuit potential conditions in MgCl2 solutions (30 and 40 percent) at i 10 *C shows significant crack growth in the SS specimens after a short exposure period. A crack growth rate of 1,7 x 10 m/sec was measured at K = 22 MPa m'*, A much longer exposure period was required to begin and propagate i
cracks at an applied potential of -340 mVscs, which is slightly above E,(-390 mVset). No substantial crack growth was observed on Alloy 22 specimens tested for 10 and 21 wk in 40 percent MgCl at 110 *C under open-circuit conditions. Signs of secondary cracking 2
along many grain boundaries, however, were detected near and beyond the tip of the fatigue precrack: This suggests that SCC may have begun and propagated following surfaces or planes with orientations that differ from that defined by the fatigue precrack. The specimens
. are being reexposed for an additional 5 wk to verify such crack advance. More tests using 316L SS specimens under applied potential conditions are planned to determine the relationship between crack growth rate and potential. These experiments are needed to confirm whether the repassivation potential may be used as a threshold criterion for
_ precracked specimens as os previously demonstrated for smooth specimens in slow strain rate tests.
6 v
I Staff is examining the key environmental variables affecting the corrosion behavior of A516 carbon steel and the critical values of these variables to determine the occurrence of localind corrosion. Based on this work, a critical pH, chloride concentration, and potential have been identified fo.e the onset oflocalimd corrosion on carbon steel. Furthermore, these parameters were verified using longer-term tests that were also able to demonstrate that localized corrosion of carbon steel can occur under free corrosion conditions in air-saturated solutions. This work was recently presented at the Corrosion '99 NACE conference. NRC comments on Effect of Environmental Variables on Localized Corrosion of Carbon Steel and Factors Important in its Use in HLW Disposal are being reviewed. This
' paper subsequently will be submitted for publication in thejournal Corrosion. Further work l
examining the potential effects of a reverse VA WP design on carbon steel corrosion has been conducted and the results are being evaluated.
- The effects of solution chemistry on the corrosion behavior at 95 *C of Ti-Grade 7, identified by the DOE as a possible candidate material for WP, drip shield construction, or both, are being examined. Current focus is on the effect of chloride concentration and pH on the critical potentials for localind corrosion as well as the environmental effects on the passive dissolution of Ti-Grade 7.
Analysis is progressing on the effect of rock fall on the mechanical failure of Zircaloy
~ ladding in spent fuel assemblies. This analysis uses a fracture mechanics approach as a c
failure criterion to consider the effects of flaws and other cladding defects from reactor operation and post-operation handling. Staff began experiments on localized corrosion of zirconium.
In the next period, staff will continue long-term corrosion tests of Alloys 825 and C-22, together with SCC tests using Alloy C-22 and type 316L SS. Limited testing of A516 carbon steel will be completed to satisfy some outstanding issues. The Ti alloy test program will be fully implemented. The draft report on alternate materials and designs will be completed, followed by an internal technical review. Preparations for the review of the CLST IRSR will continue.
- 1.6 Thermal Effects on Flow (TEF)
Staff conducted a sensitivity analysis of mass loss through the thermal bulkhead of the DST using sink terms of various magnitudes to simulate the loss. Results of this analysis were compared with preliminary analyses of the DST by LLNL and LBNL. These results demonstrated that thermal bulkhead losses may potentially prevent detection of the type of heat transfer occurring during the test. This work was presented at the DOE /NRC Appendix 7 meeting on Thermal Testing held in Las Vegas, Nevada, April 28,1999. In addition to attending the 8* Thermal Testing Workshop, staff also visited the ESF, ECRB, Busted Butte, and the EBS pilot-scale testing facility.
The second phase of the laboratory-scale boiling isotherm depression heater experiment was completed during this period. The heat load was slowly decreased to permit observation of the collapse of the boiling isotherm into the drift during the cooling phase. The concrete blocks were disassembled for the posttest examination. Multiple samples of the blocks were collected for saturation and sorptivity testing. Ajournal paper based on this activity is being prepared.
7
Development and evaluation of a repository-scale test model continued.The model is similar to one based on equivalent continuum and reFular gridding. The current model uses unstructured gridding and a dual continuum approach. It is being used to evaluate the provisions available in METRA for performing analyses with such models. The isothermal steady-state case with a net infiltration rate of 10 mm/yr has been completed and the results are being evaluated.
Staff continued preparation of a proposed laboratory-scale coupled corrosion / heater experiment in support of the TEF and CLST KTIs. Media preparation and sensor evaluation are ongoing. Modification of the TEF KTI laboratory-scale heater test apparatus will provide a credible environment to observe and measure corrosion processes.
I Staff continued review of the literature 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 staff pursued the laboratory-scale experiment designed to resolve the distinction between capillary diversion and dripping. An analytical solution for seepage into a spherical opening with a periodic internal boundary condition is near completion. Numerical investigation of the diversion mechanism continued. An unstructured grid option to the MULTIFLO code has been successfully implemented. The effect of grid discretization of the unstructured grid is under investigation.
Staff pursued formulation of an analytical / numerical solution to represent groove flow down a fracture through heated porous media. A draft journal article describing this progress was completed and is undergoing internal technical and programmatic reviews.
Analysis of dripping into a drift opening began this period. The technical approach for this investigation is under development. It is anticipated to be different from the groove / film flow model. A paper titled A Discrete-Fracture Boundary Integral Approach to Simulating Coupled Energy and Moisture Transport in a Fractured Porous Medium was transmitted on May 7,1999. This paper also has been submitted for publication in the Proceedings of the Witherspoon Symposium on Flow and Transport in Fractured Rocks.
The author-final Revision 2 of the TEF KTl IRSR is undergoing internal reviews.
j In the next period, staff plans to (i) complete the journal article on the boiling isotherm penetration laboratory-scale experiment, (ii) continue a literature search for identification of potential dripping analog sites, (iii) test the MULTIFLO-DCM numerical code in modeling the DOE DST and mountain-scale nonisothermal flow, (iv) integrate a groove / film now model into the mechanistic fracture flow model, and (v) initiate a series of nonisothermal analyses for a 60 MTU/ acre repository.
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. The objective of this study is to determine whether a synergistic effect exists that could adversely affect drift stability in this area under thermal conditions. The preliminary results indicate that the existence of a transitional zone increases the amount of 8
I
p 1
joint shearing along the sub-horizontal joints around the drift. This effect is greater on the weaker side of the transition. Also, the amount of shearing is increased on the wall of the drift on the weaker side of the transition. Other observations include an increase in the tensile zone along the drift where the transition takes place compared to both strong and weak rock base cases where no transition exists.
During this period, staff continued the UDEC analyses to predict the size and extent of rockfall under seismic loads in the repository thermal environment. Staff compared the dynamic analyses using UDEC and KDYNA 3D to examine rockfall, as this effort will increase confidence in UDEC results. Construction of the mesh model for KDYNA 3D is near completion. A problem has been encountered in placing slide line geometry into the model. The staff has made an effort to identify the source of the problem. A study has begun on how wave propagation through a fractured medium is handled by UDEC.
The AB AQUS modeling of WPs continued to investigate the thermal stress of WPs and also assess WP responses when subjected to the impact of falling rocks at various times. This analysis will develop a reasonable failure criterion for use in the SEISMO module to assess the effect of rockfall on WP integrity.
j Staff pursued development of a review plan for the preclosure aspects of design, construction, and operations of the repository using the integrated safety assessment i
methodology.
Staff studied the behavior of the rock mass surrounding the emplacement drifts under heated conditions at the repository scale using the ABAQUS code. They made ABAQUS calculations of several drift-scale models and analyzed these results to compare with those from the repository-scale model. Preliminary results suggest the rock mass surrounding emplacement drifts with a low rock mass rating (weak) could have a different response to thermal loading from that with a high rock mass rating (strong). Under weak rock conditions, the failure of rock mass tends to occur more in the vicinity of the drift while, for a strong rock, rock failure appears to take place in the middle region of the pillar between drifts.
A staff member attended three meetings in Las Vegas: the YMP Drift Stability Workshop April 13-15, the DOE Thermal Testing Workshop April 27, and the DOE /NRC Appendix 7 Meeting on Thermal Testing April 28.
Staff reviewed the literature on concrete performance at high temperature to provide valuable information to assess the DOE design of the concrete liner that will be used at high temperature.
In the next period, staff plans to (i) investigate rock mass behavior under heated conditions on both repository and drift scales with an emphasis on long-term degradation of rock mass material properties and strengths, (ii) conduct rockfall simulations, (iii) use the AB AQUS code to model WPs, (iv) develop input to the YMRP, and (v) begin development of the RDTME IRSR.
9
1 1,8 Total System Performance Assessment and Integration (TSPAI)
Using the TPA Version 3.2 code, staff generated output data and continued applying newly implemented methods to assess the sensitivity of TPA model output to changes in model parameter values. The sensitivity analysis report that will document these results is being prepared by the CNWRA and NRC staffs. The scope of the report will be scaled down and will exclude comparisons between TPA and TSPA-VA. The report, however, will document results obtained from the TPA Version 3.2 code and data, as originally planned.
Activities comparing DOE and NRC results continued using the TPA code, DOE and NRC data, and DOE published results as a part of the preparation for the DOE /NRC technical exchange on TSPA-VA review to be held May 25-27,1999.
Staff responded to DOE questions resulting from their review of the TPA Version 3.2 code and the User's Guide. Preparing responses to DOE questions involved interactions with other KTIs, code executions, and hand calculations.
NRC and CNWRA staffs continued discussion on the development of a processor for systematic analysis of TPA results and they identified a consultant to assist in the development of a methodology for this analysis. Development of an SRD for the post-processor began.
Staff supported the NRC making final changes to volume I of the sensitivity studies report prior to its publication as a NUREG.
The NRC and CNWRA held followup discussions to determine the scope of the YMRP.
Staff discussed the initial match-up ofIRSR acceptance criteria with the YMRP outline and provided feedback on the NRC revised draft outline.
The external experts panicipating in the review of the TPA code were notified of the changes to the schedule. A search began to replace candidates who would not be available because of the new meeting schedule and to replace those affected by a COI.
CNWRA QA staff helped prepare the proceedings of meetings between DOE and M&O contractor staffs. The meetings focused on the QA corrective actions raised by the NRC HLW QA Task Force. This period, CNWRA QA staff participated in a DOE /NRC videoconference meeting emphasizing QA and the corrective action process. During the visit of Commissioner Dieus to the CNWRA, staff made a brief presentation on the PA approach adopted by the NRC and also demonstrated the use of the TPA code results in reviewing the TSPA-VA.
Two candidates were interviewed for the unfilled positions of health-physicist and nuclear engineer. An offer was made to one of these individuals. R6 sum 6s continue to be gathered for other open positions.
In the next period, the staff will focus on (i) comparing the TSPA-VA and the TPA Version 3.2 code results; (ii) participating in the DOE /NRC technical exchange meeting on TSPA-VA review; (iii) developing the sensitivity analysis report, which may include 10
p L,
contributions from other KTIs; and (iv) preparing Revision 2 of the IRSR. Recruitment will l
continue for the two PA modelers, the two health physicists, and a risk analyst.
1.9 Activities Related to Development of the NRC High Level Waste Regulations ( ARDR)
Modeling the effects of well characteristics and plume dimensions on the accuracy of the dose estimates from the groundwater transport pathway continued, although at a reduced level to accommodate work on another flow modeling exercise. This Al should, nonetheless, be completed in a timely manner.
NRC comments on the revisions to the previously issued report, Information and Analyses to Support Selection of Critical Groups and Reference Biospheres for Yucca Mountain Exposure Scenarios, have been incorporated into a camera-ready copy to be delivered next period. Staff expects the report will be issued as a NUREG/CR-a key reference document for the rulemaking effort and TSPAl activities.
The feasibility of an improved (stochastic) dose module for the TPA code is being investigated. The source code for the GENII dose assessment program was located, but software licensing issues need resolution prior to staning work.
Additional tasking was discussed with the NRC PM. New tasks beginning next period include compiling and analyzing GIS data related to selection of potential receptor groups and reviewing information supporting plant uptake factors for selected radionuclides in the TPA Version 3.2 code. Potentially, the staff may be tasked to de'. ermine whether the effects of multiyear radionuclide buildup from irrigation of soils needs to be modeled in the TPA Version 4.0 code. Additionally, the staff may be asked to evalnate the potential inclusion of stylized human intrusion calculations in the TPA Version 4.0 code.
In the next period, progress on borehole dilution will continc.e. A revised, camera-ready copy of Information and Analyses to Suppon Selection of Critical Groups and Reference Biospheres for Yucca Mountain Exposure Scenarios (incorporating NRC comments) will be delivered. Staff plan to resolve software licensing issues related to investigating the feasibility of an improved (stochastic) dose module for the TPA code. New tasking on analysis of GIS data related to selection of potential receptor groups and review of information supporting plant uptake factors in the TPA Version 3.2 code is expected to start.
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)
Investigations continued on the process of drift seepage and capillary diversion of deep i
percolation away from open drifts. An unstructured grid for modeling seepage into a circular drift has been benchmarked against an :malytical solution, with an error of approximately 0.5 percent. A semianalytical solution for the irregular drift wall has been derived where the coefficients of the Fourier series are integrated numerically. Staff tested various unstructured i.
grids for the irregular drift wall against this analytical solution and, again, difficulties in tinely discretizing the region of the drift wall were encountered, this time exacerbated by the I
irregularity of the drift wall boundary, 11
N The potential for near-surface lateral flow that may result in focused flow and fast pathways through the TCw and PTn is being analyzed. Three hillslope configurations near the crest and a high-infiltration environment at YM are being modeled to evaluate the validity of assuming ID flow for shallow in d: ration estimates. Based on sensitivity analyses, e
microtopography and soil depth emerged as imponant, but highly uncenain, parameters.
Staff presentation topics at the AGU Spring meeting in Boston, Massachusetts, May 31-June 4,1999, include (i) assessing changes in deep percolation over a glacial cycle due to linked changes in climate, soils, and vegetation at YM; (ii) dripping into subterranean cavities from unsaturated fractures; (iii) determining the effects of cavity wall roughness on seepage into underground openings; (iv) analyzing hydrogeologic inferences from thermal and chemical measurements: (v) using barometric and earth-tide responses to infer vertical connectivity in the tuff aquifer; and (vi) studying geophysical and hydrogeologic aspects along a fault zone.
Staff began work on a model of coupled heat and fluid flow in the SZ. A 3D unstructured grid honoring the coarse geological framework of the SZ was developed for the computer code MULTIFLO. The unstructured grid for the model area is based on the DOE Geologic Framework Model 3.01 in the YM vicinity The unstructured grid preserves the complex hydrogeology of the area. A preliminary calibration using available hydraulic head data was obtained for an isothermal case. Future work will attempt to refine the calibration using borehole temperature logs in combination with hydraulic head data. This forward model, when completed, will be used to perform inversion studies to better estimate the upward gradient from the carbonate aquifer.
Preparation continued on Modeling and Analysis of C-Well Tests-Letter.
Internal reviews began on the author-final draft Input to USFIC IRSR, Revision 2-Letter Report.This document reflects staff conclusions and concems regarding the status of USFIC subissues following review of the DOE TSPA-VA and supporting documents.
A manuscript on the potential effects of weedy brome grasses on infiltration and recharge rates in the vicinity of YM was prepared this period. This report provides a summary of brome grass ecology and the ongoing invasion of brome grasses, which are actively replacing native vegetation in the Amargosa Desert and surrounding regions. The hydrologic implications of brome grass dominance for repository performance are also discussed. This paper is proposed as a new deliverable in table 2 of this PMPR.
Findings of the NRC/CNWRA working group on SZ flow are being documented in Input to NRC Working Group on Viable SZ Conceptual Flow Models. A request is made in table 2 of this document to extend the due date for this deliverable to address concerns that arose during programmatic review at the CNWRA.
l In the next period, USFIC ac:ivities will include (i) preparation of Input to NRC Working Group on Viable SZ Conceptual Flow Models; (ii) completion of the author-final draft of
-Modeling and Analysis of C-Well Tests-Letter Report; (iii) investigation of models for seepage and dripping in underground cavities; (iv) analysis of processes affecting deep percolation;(v) panicipation in development of the YMRP; (vi) collaboration with NRC on Revision 2 of the USFIC IRSR.-including intemal review of Input to USFIC IRSR, 12
Revision 2-Letter Repon; and (vii) participation at the AGU Spring meeting in Boston, Massachusetts, May 31-June 4,1999.
l 1.11 Radionuclide Transport (RT)
Preparation began on a paper titled Uranium Chemistry and Isotopy in Waters and Rocks at Pena Blanca, to be submitted for the proceedings volume of the 8* European Commission Natural Analogue Working Group Workshop, which was attended during period 7 The paper is a history of U at the Nopal I natural analog using existing CNWRA data. The final paper is proposed as a new deliverable in table 2 of this PMPR, Uranium Chemistry and Isotopy in Waters and Rocks at Pena Blanca-Joumal.
CNWRA technical review was completed and programmatic review is underway for Stochastic Analysis of Early Tracer Arrivals in a Multiple-Fracture Pathway-Journal Paper.
CNWRA staff continued to use stochastic analyses to investigate altemative models of RT through allu vium near YM. The stochastic analysis takes into account spatial heterogeneities in chemical and hydrological properties and relies on existing CNWRA data on spatial variability in sorption propenies.
Page proofs for Experimental and Modeling Study of Ion Exchange Between Aqueous Solutions and the Zeolite Mineral Clinoptitolite-Joumal Paper were received from the Journal ofSolution Chemistry; the corrected proofs were mailed back to the publisher. The manuscript AbstractionofMechanisticSorptionModelResultsforPerformance Assessment Calculations at Yucca Mountain, Nevada-Journal Paper was accepted by Waste Management for publication with minor revisions.
CNWR A staff prepared for colloid sampling at Rainier Mesa. This included assembling field sampling equipment, arranging for underground worker and radiation safety training, and investigating applicable sampling procedures.
As part of the ongoing investigation of Np sorption on alluvium minerals, cmshing and sieving natural calcite samples continued. Efforts are underway to prepare a 60-200 mesh size fraction, remove fine panicles, and stabilize the surface of each grain by equilibrating the calcite in 0.02 M NaHCO. An infrared CO analyzer was received that will allow 3
2 monitoring of CO partial pressure during the experiment.
2 Sorption experiments on clinoptilolite with a low CO2 Partial pressure were completed.
Experiments to investigate U sorption onto quartz with trace iron oxide continued. Efforts to conduct sorption experiments under elevated CO partial pressums also continued.
2 Twenty well-cutting samples (one sample every 10 ft from the 200400-ft depth interval) from Well NC-EWDP-2d of the Nye County monitor well program were logged. Initial descriptions to develop a well log and descriptive " chip board" continued this period.
Thermodynamic modeling continued of radionuclide sorption using a surface complexation approach. Preliminary interpretations for sorption of americium, plutonium, and iodine were completed. Evaluation began of the data on ion exchange between aqueous solutions and the zeolite mineral clinoptilolite. Development of thermodynamic parameters for predicting ion exchange equilibria also began this period.The geochemical code, PHREEQC, Version 1.6, 13
was placed under CNWRA configuration control, anticipating the simulation of mixing and water-rock interaction in the SZ.
Staff helped prepare the YMRP outline. Activities included mapping the acceptance criteria from the RT 1RSR onto the proposed outline for the YMRP. CNWRA staff also worked with visiting NRC staff to develop Input to RT IRSR, Rev.1-Letter Report.
In the next period, staff will continue sorption experiments on alluvium minerals. Sorption experiments to evaluate the effects of trace iron oxyhydroxides on U sorption also will continue. Microscopic analysis of well cuttings from NC-EWDP-2d will continue. CNWRA staff will sample water from Nye County wells on May 17,1999. NRC and CNWRA staffs will continue to prepare Input to RT IRSR, Revision 1-Letter Repon. Staff will assist in the PA abstraction process and perform sensitivity analyses using the TPA Version 3.2 code to investigate the calculated effects on performance of the correlation of sorption parameters.
CNWRA staff will prepare ; presentation on radionuclide sorption in alluvium for the TSPA Technical Exchange scheduled May 25-26 in San Antonio, Texas.
1.12 Tank Waste Remediation System (TWRS)
In subtask 1.2, the draft report Low-Activity Waste Auxiliary Support Systems II-Process Systems Hazard and Safety Issues Report for TWRS-Letter Report was submitted to the NRC for review on April 30,1999. Also, staff started to work on a presentation on the Vitrification of Radioactive Wastes to the Regulatory Unit of the Department of Energy. The presentation will consist of two 4-hr sessions summarizing work on this subtask during the last 2 yr. A staff member attended the Nuclear Waste Symposium at the annual meeting of the American Ceramic Society, April 24-27,1999. A trip report on this symposium was delivered on May 7,1999.
In subtask 1.6, revisions continued on Chemistry of Hanford Tank Waste Pretreatment Technology to address NRC staff comments on a draft version of the document. All chapters are undergoing technical reviews. With the concurrence of the NRC PO, the due date of the draft final report, currently May 28,1999, was changed to June 11,1999. A final version, with changes to address additional NRC comments, is scheduled for submission July 30, 1999. Minor revisions on the Hanford TWRS HLW Chemistry Manual (NUREG/CR-5751) to address NRC editorial staff comments were completed and change pages sent.
In subtask 2.1, NRC comments on the CNWRA review comment report on the BNFL,Inc.
Design Safety Features were incorporated and a revised report was delivered May 7,1999.
In addition, a staff member attended a short course on Calculating and Understanding Risk from Chemicals Released to the Environment.
In subtask 2.2, the staff continued to work on Quality Assurance Inspection Program for Radioactive Waste Treatment / Nuclear Material Production Facilities. A draft report will be e-mailed for review prior to the scheduled delivery of May 28,1999.
In the next period, in subtask 1.2, staff will incorporate NRC comments on these reports:
Low-Activity Waste Auxiliary Support Systems II-Process Systems Hazard and Safety Issues Report for TWRS-Letter Report; Low-Activity Waste Feed Makeup, Solidification, and Offgas Treatment Process System Hazard and Safety Issues Report for TWRS-Letter 14
c:
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Report; and Auxiliary Support and Process Control Technology System for Low-Activity Waste at Hanford-Hazard and Safety Issues Report. In addition, the staff will prepare a presentation on the Vitrification of Radioactive Wastes for the Regulatory Unit of the U.S. Department of Energy. On May 11,1999, staff members will discuss with the NRC staff the draft report, Low-Activity Waste Feed Makeup, Solidification, and Offgas i
Treatment Process System Hazard and Safety issues Report for TWRS-Letter Report. On May 12,1999, these staff members will accompany the NRC staff on a site visit to the GTS-Duratek to review their pilot melter operations. In subtask 1.6, the staff will complete editorial, technical, and programmatic reviews of the pretreatment chemistry report, which will be transmitted to the NRC. In subtask 2.2, the staff will continue work on Quality Assurance Inspection Program for Radioactive Waste Treatment / Nuclear Material ProduClion.
1.13 Three Mile Island Unit 2 Independent Spent Fuel Storage Installation (TMI 2 ISFSI)
TMI-2 staff provided input to the SFPO lessons leamed process on April 13,1999, when the NRC PO visited the CNWRA. The TMI 2 staff also provided input to the NRC PO in response to Environmental Defense Institute comments on the TMI-2 ISFSI flooding issue.
In the next period, TMI-2 ISFSI staff will perform new minor assignments as received from the NRC.
1.14 Dry Transfer System (DTS) i Staff completed and submitted Second Round Request for Additional Information, DTS-Draft Letter Report. NRC review comments on this draft version were received and the final version is in preparation. Compiling an outline for the SER and concurrently developing the SER continued during this period. A DTS staff member discussed the proposed format of the DTS SER with the NRC staff during a visit to the NRC May 6-7, 1999.
In the next period, DTS staff plans to complete the outline of the SER and the final version of second round RAI and develop 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 continued during this reporting period. Development of the first round RAI began. Ongoing activities for the computer code RISKIND include a i
literature review of the various parameters and their values that are used internationally to calculate dose from a loss-of-containment accident at a spent fuel storage facility. During l
a visit to the NRC May 6-7,1999, a CISF staff member discussed with NRC staff the format of the CISF final AR and NRC preliminary comments on the draft.
l in the next period, the staff plans to continue detailed technical review of the topical report l
on HI-STAR /HI-STORM cask system deployment at high-seismic sites, complete development of first round RAI, and work on the computer code RISKIND while awaiting instructions to revise the draft AR.
I 15
1.16 Private Fuel Storage Facility (PFSF)
Review and evaluation of the site characterization reports, preparation of a draft SER, and revision of the NRC draft position on five Group I contentions continued during this reporting period. A CNWRA staff member and a consultant attended a PFS/NRC meeting on flooding at the NRC May 7,1999.
In the next period, the staff plans to review the site characterization reports, prepare the draft SER, and assist NRC staff on ASLB hearing activities.
Savannah River Site Alunbnum Based Spent Fuel (SRSASF) 1.17 The staff reviewed the DOE reports on creep, dissolution of Al-based spent fuel, and fuel processing to support preparation of Review of the U.S. Department of Energy Preliminary Evaluation of Aluminum-Based Spent Nuclear Fuel-Final Report.
In the next period, further review of DOE reports will occur.
2 MANAGEMENTISSUES A further evaluation of spending, schedule, and staffing will be reviewed next period at the NRC/CNWRA Management Meeting.
3 MAJOR PROBLEMS None to report.
4
SUMMARY
OF SCHEDULE CHANGES Schedule changes for IMs are included in table 2. Completed deliverables are noted on table 3.
5
SUMMARY
OF FINANCIAL STATUS Table 4 summarizes the CNWRA financial status in the context of authorized funds. Total commitments are $557,292. The appendix lists planned and actual costs to date, as well as variances
- between these, without allowance for fee, on both a per-period and a cumulative basis. These data do not include commitments. Pertinent financial information is provided for the DWM JC, including COPS and ten KTIs, TWRS JC, TMI-2 ISFSI JC, DTS JC, CISF JC, PFSF JC, and SRSASF JC. The planned costs per period are based on the revised spending plans contained in the current operations plans.
It should be noted that the current spending estimates in all JCs are based on the assumption that staffing is consistent with the aggressive CNWRA hiring plan. A revised staffing plan was delivered as part of the CNWRA Management Plan, Revision 7, Change 0. Cunent staffing remains below authorized levels, because of slower than anticipated hiring and anexpected attrition, and dedicated reemitment continues.
Period 8 FY 1999 CNWRA composite expenditures fell 1.5 percent from the previous period, and this aggregate of all JCs was underspent by $1,427,534 or 16.9 percent. When comparing period 8 with 16
I last period, the TWRS, TMI-2 ISFSI, DTS, and CISF JCs evidenced higher spending levels while the I
D.WM, PFSF, and SRSASF JCs showed a lower level.
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 spending on all JCs was 8.2 percent. The CNWRA continues to enhance, where appropriate, participation of consultants and subcontractors in the conduct of CNWRA work.
As shown in table 1, the CNWRA has 51 staff members, reflecting the resignation of a nuclear eagineer. The available pool of approved consultants and subcontractors is 53.
This FYTD, no capital or sensitive equipment was purchased with NRC funds (other than overhead, general and administrative expenses, and fees).
The DWM JC was underspent by $1,197,138 or 16.5 percect. Overall expenditures decreased about 5.5 percent from the previous period as costs rose in COPS snd the IA, SDS, TEF, RDTME, and ARDR KTIs but declined in the ENFE, CLST, TSPA, and USIT -nd RT KTIs. Costs to date are 26 percent above those a year ago, and period 8 costs are 9 percent greater than the same period last year. The FY1999 budget is 24 percent greater than FY1998. Spending on the augmented scope of work has not met expectations in all areas. In various meetings with NRC senior management staff and other interested parties, CNWRA senior management discussed current and expected levels of spending, aggressive recmitment efforts for core staff, and effective engagement of consultants and subcontractors. The CNWRA does not expect to attain the estimated spending in the currently approved OPS by the end of FY1999. A detailed assessment of anticipated spending has been provided to NRC.
The cost variance for COPS was 18.4 percent: 18.2 percent for the Management Planning, and Computer Support subtask (158) and 19.1 percent for the QA subtask (159). Spending this period in subtasks 158 and 159 rose relative to last period. Labor costs in subtask 158 increased about 6.5 percent from last period, primarily the result of greater staff utilization; however, such costs increased 20.6 percent in subtask 159. Other Direct Costs declined in subtask 158 from the previous period, but more than doubled since the last period in subtask 159. In the next period, spending in subtask 158 is expected to be less than estimates as staff is recruited in the financial and computer-related areas. Consultants will be used in the IMS area to mitigate staff lost through attrition and to support the revision of the CNWRA LAN, creation of new and revision of existing databases, and modification of the firewall. CNWRA management will continue to encourage eligible staff to participate in professional development activities. In subtask 159, spending should substantially increase as the QA audit team technical specialists and auditors review operations plans and deliverables and prepare audit checklists. A substantial spike in subtask 159 spending for periods 9 and 10 is expected as preparation for the audit, the audit itself, and the report on the audit takes place.
Actual spending is expected to be about 10 percent less than the approved spending plan for FY 1999.
The cost variance for the IA KTI was 12.9 percent. Spending increased relative to last period, with the variance primarily due to spending plan augmentation that occred in period 6. Substantial consultant and subcontractor costs are outstanding; invoices are being expedited. Expenditures this period are consistent with expected spending in the next few periods. Total expenditures may exceed the spending plan by less than 10 percent for the remainder of FY1999.
I 17
\\
The cost variance for the SDS KTI was 14.8 percent, although expenses rose from the previous period. The variance is due to the spending plan augmentation that occurred in period.6. As t.he augmented work progresses. this variance will decrease and total expenditures may be slightly greater than the spending plan for the balance of FY1999. Spending likely will increase next period as a consultant and student will start a study of the alluvium in Fortymile Wash.
The cost variance for the ENFE KTI was 15.6 percent, a slight increase in percentage variance from period 7 (l4.5 percent). This variance is expected to increase in periods 9 and 10 as staff support field activities in the RT KTI. Existing commitments essentially balance the current underspending.
Nevertheless, this program area is projected to be slightly underspent by the end of FY1999. The largest uncertainty in the future spending for the ENFE KTI remains execution of a subcontract with the University of Aberdeen for cement related experiments. Aggressive efforts continue toward initiating this work.
The cost variance for the CLST KTl was 0.3 percent. Spending decreased compared to period 7 despite the initiation of new corrosion tests. At this time, the projected cumulative spending at the end of the FY is expected to be about 5 percent above budget.
The cost variance for the TEF KTI was 1.4 percent. Spending increased from the previous period, thus reducing the cumulative variance. The small underspenoitig is due to lagging charges from consultants and subcontractors. Future actual expenditures are expected to continue following the budget for this KTI.
The cost variance for the RDTME KTl was 20.2 percent. Spending rose significantly this period, thus reducing the percentage cu mulative variance. It has not reached the augmented budget level, however.
This cost underrun is due to temporary assignment of staff to other tasks and lagging charges from consultants and subcontractors. In acidition $15,443.77 was misallocated to other accounts; this error will be corrected next period. Now that the staff has been reassigned to the RDTME KTl activities, this cost underrun is expected to decrease significantly during the remaining periods of FY1999. The FY1999 total expenditures are expected to be slightly less than the FY1999 allocation.
The cost variance for the TSPAI KTI was 23.5 percent. Spending declined from the previous two periods. The underspending should decrease due to additional SwRI and consultant resources being devoted to the development of the TPA post-processor. Spending is anticipated to be about 15 p' rcent e
less than planned expenditures by the end of FY1999.
The cost variance for the ARDR KTl was 57.0 percent. Spending rose slightly relative to the previous period and the cumulative percent variance increased. Recent indications suggest the draft EPA Standard will be released for review soon; underspending will decrease when this occurs. New tasks for this KTl were discussed with the NRC PM and will be started next period. Although this new tasking should reduce the variance in future periods, this KTI is expected to be significantly underspent at the end of this FY.
The cost variance for the USFIC KTl was 5.3 percent. This percentage variance is a relatively small increase over the period 7 variance (4.5 percent). When costs for field work planned for period 9 are posted, the variance is expected to diminish. Future spending is expected to slightly exceed estimated FY spending.
18
The cost variance for the RT KTI was 27.5 percent, unchanged from the previous period on a percentage basis, although it increased substantially in dollar terms. Anticipated invoices from ongoing and planned work by consultants are expected to reduce the variance in the coming periods.
Field activities to collect water samples from the Nye County wells and colloid sampling at Rainier Mesa are also anticipated to reduce the variance. Total spending may be on the order of 5 percent less than the spending plan for FY1999.
The cost variance for the TWRS project was 25.2 percent. The variance decreased from last period due to expenditures related to the preparation of two IMs. The staff effort is being augmented through the judicious use of SwRI staff and consultants to achieve timely completion of milestones. Due to the reactive nature of work in tasks 2.1 and 2.2 and lack of new privatization contractor reports to review, it is anticipated that these tasks and the overall project will be underspent at the end of the FY.
The cost variance for the TMI-2 ISFSI project was -4.0 percent, a slight decrease from the previous period. This overspending resulted from concentrated efforts during the first six periods of FY1999 to prepare the draft and final SER and to assist the NRC staff to prepare TMI-2 ISFSI Materials License No. SNM-2508. Approximately 99.8 percent of the FY1999 tasking within the TMl-2 ISFSI project was completed during periods 1-8 with a spending of about 99.2 percent of the FY1999 allocation. Thus, the FY1999 total expenditures are within the FY1999 allocation.
The cost variance for the DTS project was 2.5 percent. However, an amount of $4,935.44 was charged to this project incorrectly, and will be credited to this project during the next reporting period. Spending rose during this period, thus reducing the cumulative percent variance. This cost underrun is primarily due to the time needed to accelerate the FY1999 DTS activities based on the revised SFPO Operations Plan with increased funding for the DTS project. Expenditures are expected to remain close to the augmented FY1999 allocation as a result of developing the second round RAI and preparing an outline and a draft of the SER through utilization of CNWRA and SwRI staff, and subcontractors. The FY1999 total expenditures are expected to converge to the FY1999 allocation.
The cost variance for the CISF project was 27.3 percent. However, an amount of $5,254.17 was charged to this project incorrectly, and will be credited to this project during the next reporting period. Spending this period is significantly higher compared to the presious five periods to accommodate concentrated effort needed to review the HI-STAR /HI-STORM cask systems. Per period expenditures for the next few periods are expected to remain close to those of this penod to review the HI-STAR /HI-STORM cask system Topical Report, work on the computer code RIS KIND, and prepare the final AR. The FY1999 total expenditures are expected to converge to the FY1999 allocation.
The cost variance for the PFSF project was -9.1 percent. However, an amount of $5,254.16 was charged to this project incorrectly, and will be credited to this project during the next reporting period. The per period expenditures during the next few periods will be similar to that of period 6, so the cost overrun will continue as staff review the site characterization reports, prepare the draft SER, and revise the NRC draft position on five Group I contentions. Additional funding of about
$100K will be needed in FY1999 to accommodate the increased scope of work.
The cost variance for the SRSASF was 74.9 percent, a slight increase from the last period. Spending is expected to increase as the staff reviews additional DOE reports in the next period. The large variance does not reflect an anticipated substantial decrease in the budget for the project. However, 19
with the changes in the deliverables 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. Total spending is ' expected to be close to the budgeted amount.
20
T l
Table 1. CNWRA Core Staff-Current Profile and Hiring Plan * (Period 8)
I Positions Open Essertimefuserience Current No.
Professionni Staff n'19eo ADMINISTRATION -
'4 H GARCIA. W PATRICK.1 RUSSEIL B SAGAR CHEMICAL PROCESSING -
2 VJAIN, D.DARUWALLA ENGNG/ PHYS CHEM i
CODE ANALYSIS /DEVE!DPMENT 2'
R J ANE'I7KE, R M ARTIN i
DATA MAN AGEMENT/ PROCESSING.
1 P.MAIDONADO.
INCI.UDING FIN ANCIAl.
DOSF1 RISK / HAZARD ANALYSIS 0
t I'l FCIROCHEMISTRY 1
G CR AGNOt.fNO ENGINEERING 2
R.CHEN, G OFOEGBU i
GEO!IXiY/ GEOL OGICA!. FNGNG ENVIRONMENTAL. SCIENCES 1
P.laPLANTE GEOCHEMISTRY
~7 P.BERTETTI, LBROWNING, W. MURPHY, R.PABAIAN.
E PEARCY. J PRIKRYL D TURNER GEOHYDROLOGYAlYDROGEOLOGY D.FARRELL. REEDORS, R. GREEN. M. Hila 1WINTERif GEOIDGY 3
P LAFEMIN A. I.McKAGUE. M MIKIAS HYDROff)GIC TR ANSPORT 3
A ARMSTRONG. D HUGHSON. S PAINTER I
INFORMATION MANAGEMENT 0
1 SYSTEMS M A1 TRIAL SCIENCES 4
S BROSSIA. D.DUNN. Y-M PAN, N SRIDH AR 2
MECHANICAL, 1
D.GlTI'E INCt.UDING DESIGN & FABRICATION MINING ENGINEERING l
S-M HSTUNG NUCLEAR ENGINEERING 0
1 OPER ATION AL HEALTH PHYSICS I
J WEIDY 1
PERIORMANCE ASSESSMENT 3
S.MOHANTY, O. PENSADO-RODRIGUEZ, 2
G %TrTMEYER OUA1.rrY ASSURANCE I
B MABRrTO RAD 10!SOTOPE GEOCHEMISTRY l
D. PICKETT l
ROCK MECHANICS, 2
A.CHOWDHURY, A.GHOSH INCt.UDING CIV111STRUC l'NGNG 1
SOURCE. TERM / SPENT FUEL. DEGR AD 0
t STRUCIURALGEOLDGW 3
D.FERR!!L D. SIMS, J.STAMATAKOS SEISMO TECTONICS
{
SYSTEMS ENGINEERING -
1 P M ACKIN VOlfANotDGY/lGNEOUS PROCESSES 2
C CONNOR. B Hill TOTAL 51 12
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Table 4. Financial Status (Period 8)
Funds Funds Funds Project Names Authorised Costed to Date Uncosted Commitments COPS 3.476.342 2,535.438 940,904 832 IA 1.345.% 2 1.088.849 256.213 119.139 SDS-1,825.699 1.427.598 398.100 36,632 ENFE 1.781.331 1,245.770 535.560 89.161 CLST 1,704,818 1.364,359 340.460 18.414
'llIF 1.322.606 998.991 323.615 6.274 RDTME 1,319,682 841.703 477,979 13.844 TSPAl 3.577.966 2.440,032 1.137.934 44.869 ARDR 697.208 304.263 392.945 4.819 USFIC 2.288.030 1.713.648 574.383 33.064 RT l.369.634 829.596 540.038 108,434 DWM Costs 20,708.378 14,790.247 5.918,132 DWM Award Fee 1.196,006 493.569 702.437 DWM Base Fee 828.335 576.860 251.476 TOTAL DWM -
22,732,719 15.860,675 6.872.N4 475.482 TWRS Costs 1.583.378 1.243.204 340,173 6.410 TWRS Award Fee -
93,654 46.214 47.440 7WRS Base Fee 63,335 50.623 12.712 TOTALTWRS 1.740.367 1,340.N2 400.325 6.410 TMI-2 ISFSI S AR Costs 282.197 281.586 611 1,341 TMI-2 ISFSI S AR Award Fee 15.223 7.711 7.512 TMI-2 ISFSI Base Fee 11.288 11.016 272 TOTAL'IMI-2 ISFSI S AR 308.708 300.313 8,395 1,341 DTS Costs '
309.952 279.648 30.305 27.371 DTS Award Fee 19.480 7.924 11.556 DTS Base Fee 12.398 11.142 1.257 TOTAL DTS 341.830 298.713 43.117 27,37I CISF Costs 409.053 313,471 95.582 14.563 CISF Award Fee 24.338 12.848 11.490 CISF Base Fee -
16.362 12.614 3.748
'IDTAL CISF 449.753 338.933 110.820 14.563 PFSF Costs 275,068 233.917 41,150 32,125 PFSF Award Fee 16.185 6.827 9.358 PFSF Base Fee 11.003 9.537 1.465 TOTAL PFSF 302.255 250.282 51,974 32.125 SRSASF Costs 113.185 83.739 29,446 0
SRSASF Award Fee 7,110
' 3,992 3.118 SRSASF Base Fee 4.527 3.595 932 l
'IDTAL SRSASF 124.823 91,326 33.496 0
Grand Total 26.000.456 18.480.285 7.520.171 557.292 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 the award fee reserved from the last authorizations based on the Operations Plans for FY 1999.
24 1
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