ML20217F855
| ML20217F855 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/07/1999 |
| From: | CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES |
| To: | NRC |
| Shared Package | |
| ML20217F834 | 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, REF-WM-11 HLWR, PMPR-99-13, NUDOCS 9910210099 | |
| Download: ML20217F855 (43) | |
Text
,
en CNWRA PROGRAM MANAGER'S PERIODIC REPORT ON ACTIVITIES OF THE CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES For the Fiscal Reporting Period August 28,1999 - September 24,1999 PMPR No. 99-13 October 7,1999 1
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TABLE OF CONTENTS Section Page TAB LES..............
iv ABBREV!ATIOi4S........
v EXECUTIVE
SUMMARY
-PERIOD 13......
.. xi 1
TECHNICAL.........
I 1.1 CNWRA Operations (COPS)..
1 1.2 Igneous Activity (I A).......
2 j
1.3 Structural Deformation and Seismicity (SDS).......
5 l
1.4 Evolution af the Near-Field Environment (ENFE)...............
5 1.5 Container Life and Source Term (CLST).
6 1.6 Tiv,rmal Effects on Flow (TEF)......
9 1.7 Repository Design and Thermal-Mechanical Effects (RDTME)...
10 1.8 Total System Performance Assessment and Integration (TSPAI)....
I1 1.9 Activities Related to Development of the NRC High-Level Waste Regulations (ARDR)....
12 1.10 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC)..
13 1.11 Radionuclide Trnnsport (RT)....................
. 14 1.12 Review of the Draft Environmental impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel ad High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada (DFm.....
15 1.13 Tank Waste Remediation Systems (I WRS)............
15 1.14 Dry Transfer System (DTS).......
16 1.15 Centralized Interim Storage Facility (CISF)................
16 1.16 Private Fuel Storage Facility (PFSF)...
16 1.17 Savannah River Site Aluminum-Based Spent Fuel (SRSASF).
17 2
M AN AG EM ENT I SSUES...........................
17 3
MAJOR PROBLEMS 17 i
4
SUMMARY
OF SCHEDULE CHANGES 17 l
5
SUMMARY
OF FINANCIAL STATUS.
17 APPENDIX-Planned and Actual Costs, and Cost Variances Period 13-FT 1999 i
iii j
TABLES Table Page 1
CNWRA Core Staff-Current Profile and Hiring Plan (Period 13)..
21 2
CNWRA Core Staff-Summar by Area of Concentration (Period 13)...
22 f
3 Summary of Schedule Changes (Period 13)........
23 4
Deliverables (Period 13).........
24 5
Financial Status (Period 13)
... 25 6
Private Fuel Storage Facility License Fee Cost Recovery Status (Period 13)..
26 iv
ABBREVIATIONS ID One-Dimensional CDOCS Consolidated Document Management 2D Two-Dimensional System 3D Three-Dimensional CDROM Compact Disk Read Only Memory AA Atomic Absorp on CDTS Con mission Decision Tracking System AAl Average AnnualInfiltration CEB Center for Environmental Biotechnology ACD Advanced Conceptual Design CEC Commission of the European ACF Alumina (in excess of alkali feldspar),
Communities Calcium Oxide. Ferromagnesian Oxide CFD Computational Fluid Dynamics ACNW Advisory Committee on Nuclear Waste CFR Code of Federal Regulation ACRS Advanced Computer Review System Clin Calico liills Nonwcided Tuff ACS American Chemiced Society CIAC Computer Incident Advisory Capability ADAMS Agencywide Docaments Access and CISF Centralized Interim Storage Facility Management Sy tem CLST Container Life and Source Term AECL Atomic Energy of Canada Limited CM Configuration Management AES Atomic Emise,,on Spectrometry CNWRA Center for Nuclear Waste Regulatory AWF Antler Wash Fault Analyses AGU American Geophysical union COI Conflict ofinterest Al Administrative item COPS CNWRA Operations ALTS Apache Leap Test Site CPP Cyclic Potentiodynamic Polarization AML
' Areal Mass Loading CQAM CNWRA Quality Assurance Manual AMR Analysis and Model Report CRG Center Review Group ANS American Nuclear Society CRM Corrosion Resistant Material ALSI American National Standards Institute CRWMS Civilian Radioactise Waste AO Annotated Outl;ne Management System AP Administrative Procedure CSCS Constrained Stochastic Climate APB Acid-Producing Bacteria Simulator O
AR Assessment Report CSil Calcium Silicate fly drate ARDR Activities Related to Development of CSPE Corrosion Science and Process the NRC liigh-Level Waste Regulations Engineering ASCE American Society of Civil Engineers DAS Data Acquisition System ASCII American Standard Code for DBE Design Basis Event Information Interchange DC Division of Contracts ASLB Atomic Safety and Licensing Board DCAA Defense Contract Audit Agency ASME American Society of Mechanical DCB Double Cantilever Beam f
Engineers DCF Dose Conversion Factor ASTM American Society for Testing and DCM Dual Continuum Model Materials D&D Decommissioning and Decontamination ASU Arizona State University DECOVALEX Development of Coupled Models and ATDTS Automated Technical Data Tracking Their Validation Against Experiments j
System in Nuclear Waste Isolation BDCF Biosphere Dose Conversion Factor DEIS Draft Environmental impact Statement l
l BEG Bureau of Economic Geology DEM Digital Elevation Model l
BFD Basis for Design DF Dilution Factor BM Bare Mountain DFCSS Division of Fuel Cycle Safety and j
BMF Bare Mountain Fault Safeguards l
BTP Branch Technical Position DIE Determination of importance CA1 Color Alteration Index Evaluation CAM Corrosion Allowance Material DIMNS Division ofIndustrial and Medical CAR Corrective Action Request Nuclear Safety CCDF Complementary Cumulative DKM Dual Permeability Model Distribution Function DLG Digital Line Graph i
CCL Commitment Control Log DLM Diffuse Layer Model
)
CCM Constant Capacitance Model DNAG Decade of North American Geology CD-R CDROM Recordable DNFSB Defense Nuclear Facilities Safety Board CDF Cumulative Distribution Function DOE U.S. Department of Energy i
ABBREVIATIONS (cont'd)
DOE-DP U.S. Department of Energy Defense GEOTRAP Geologic Transport of Radionuclides Program Predictions DOE.RU U.S. Department of Energy Regulatory GERT General Employee Radiological Unit Training DRA Division of Regulatory Applications GET General Employee Training DST Drift Scale Test GFM Geological Framework Model DTED Digital Terrain Elevation Data GilGC Geollydrology and Geochemistry DTS Dry Transfer System GIA Generalized importance Analysis DWM Disision of Waste Management GIS Geographic Information System DWPF Defense Waste Processing Facility GLGP Geology and Geophysics EA Environmental Assessment GMS Goundwater Modeling Sy stem EBS Engineered Barrier System / Subsystem GPS Global Positioning System ECM Equivalent Continuum Model GROA Geologic Repository Operations Area ECRB Enhanced Characterization ofRepository GSA Geologic Society of America Block GTFE Great Tolbachik Fissure Eruption EDO Office of the Executive Director for GUI Grap:.ics User Interface Operations GWB Geochemist's Workbench EDX Energy-Dispersive X-Ray Spectroscopy GWS1 Groundwater System Integration EIS Environmental lmpact Statement GWTT Groundwater Travel Time EM Element Manager HE Ilydrogen Embrittlement EMPA Electron MicroProbe Anal, 4 IILW liigh-Level Waste ENE East-Northeast IIRTEM liigh-Resolution Transmission Electron ENFE Evolution of the Near-Field Microscopy Environment IA Igneous Activity EnPA Energy Policy Act of 1992 IBM International Business Machines ENS European Nuclear Society ICP Inductively Coupled Plasma EPA U.S. Environmental Protection Agency ICPP Idaho Chemical Processing Plant EPR Electrochemical Potentiokinetic ICRP International Commission on Reactivation Radiological Protection EPRI Electric Pow er Research Institute IDLil immediately Dangerous to Life and EQA External Quality Assurance llcalth EROS Earth Resource Observation System IIILRWMC Intemational liigh-Level Radioactive ESF Exploratory Studies Facility Waste Management Conference and ESP Environmental Simulation Program Exposition EW East-West IM Intermediate Milestone EWDP Early Warning Drilling Project IME Industrial Mobilization Exemption EXAFS Extended X-Ray Absorption Fine IMS Information Management Systems Structure INEEL Idaho National Enginecrmg and FCRG Format and Content Regulatory Guide Ensironmental Laboratory FDSHA Fault Displacement and Seismic llazard INETER instituto Nicaraguense de Estudios Analysis TERritonales FEHM Finite Element lleat and Mass Transfer INTEC Idaho National Technology and FEM Finite Element Method Engineering Center FEPs Features, Events, and Processes l'O Input / Output FFRDC Federally Funded Research and IP inspection Procedure Des elopment Center IPA lterative Performance Assessment FFT Fast Fourier Transform IR&D Internal Research & Development FOC Field Operations Center IRIS Interim Records information System FTE Full-Time Equivalent IRM Office ofInformation Resources FTP Fhe Transfer Protocol Management FY Fiscal Year 1RSR issue Resolution Status Report FYTD Fiscal Year-To-Date ISA intregated Safety Analysis GDF Ghost Dance Fault ISFSI Independent Spent Fuel Storage GEM General Electrochemical Migration Installation Vi
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l ABBREVIATIONS (cont'd)
ISI Integrated Subissue NFS Network File Server ISM Integrate.d Site Model NIOSil National Institutes Of Safety and llealth l
IUGG International Union of Geodesy and NIR Near-Infrared Geophysics NIST National Institute of Standards and l
IVM Interactive Volume Modeling Technology JC Job Code NMSS Office of Nuclear Material Safety and JPL Jet Propulsion Laboratory Safeguards JRC Joint Roughness Coemcient NNE Nonh-Northeast KESA Key Elements of Subsystem Abstraction NNW North-Northwest KTl Key Technical issue NOAA National Oceanographic and LA License Application i.mospheric Administration LAAO License Application Annotated Outline NRC Nuclear Regulatory Commission LAN Local AreaNetwork NS North-South LANL Los Alamos National Laboratory NTS Nevada Test Site LARP License Application Review Plan NUREG NRC Technical Report Designation LAW Low-Activity Waste NWPA Nuclear Waste Policy Act, as amended LilNL Lawrence Berkeley National Laboratory NWTRB Nuclear Waste Technical Res iew lloard Lilt Large Block Test OBES Omce of Basic Energy Sciences LilS Latin liypercube Sampling OCRWM Omce of Civilian Radioactive Waste l
LITC Lockheed Information Technology Management Company OGC Omce of General Counsel LLC Limited Liability Company OITS Open-Item Tracking System LLNL Lawrence Livermore National OMB Omce of Management and Budget Laboratory OPS Operations Plans for the Repository i
LLW Low-Les el Waste Program LMAES Lockheed Martin Advanced ORR Operations Readiness Review Environmental Systems ORS Oserall Review Strategy LSA Liquid Scintillation Analyzer OWFN One White Flint North LSS Licensing Support System PA Performance Assessment LWR Light Water Reactor PAAG Performance Assessment Adsisory M
Molar Group Ma Million Years Ago PC Personal Computer MAI Mean AnnualInfiltration PC/ICP P 'rsonal Computerffransmission MAP Mean Annual Precipitation Jontrol Protocol MAT Mean Annual Temperature PCT Product Consistency Test MC Monte Carlo PDF Probability Distribution Function METRA Mass and Energy Transport PDR Public Document Room MGDS Mined Geologic Disposal System PEL Permissible Exposure Limit Mil Mechanical-llydrological PEM Program Element Manager MIC Microbially influenced Corrosion PER Prelicensing Evaluation Report MINC f iultiple Interacting Continua PEST Parameter Estimation MIT Massachusetts Institute of Technology PFA Perfluoroalkoxy MM Major Milestone PFD Probabilistic Fault Displacement M&O Management and Operations PFDilA Probabilistic Fault Displacement MOU Memorandum Of Understanding IIAzard MPC Multi-Purpose Canister PFS Private Fuel Storage MRS Monitored Retrievable Storage PFSF Private Fuel Storage Facil ty MSS MultiSpectral Scanner Pila Preliminary llazard Analysis MTU Metric Tonnes of Uranium Pl Principal Investigator NAS National Academy of Sciences PMDA Program Management. Policy NAWG Natural Analogue Working Group Development and Analysis StafT l
NCR NonConformance Report PMPR Program Manager's Periodic Report NEA Nuclear Energy Agency PMR Process Model Reports NEl Nuclear Energy Institute PMT Photo-Multiplier Tube Vii
ABBREVIATIONS (cont'd)
PNNL Pacific Northwest National Laboratory SECY Secretary of the Commissie. Office of PO Project Oflicer the (NRC)
PPE Prepassivated Platinum Electrode SELM Spectral Element Method PRA Probabilistic Risk Assessment SEM Scanning Electron Microscopy PRT Peer Review Team SER Safety Evaluation Report PSAG Probabilistic System Assessment Group SFPO Spent Fuel Project Office PSilA Probabilistic Seismic Ilazard Analyses SFVF San Francisco Volcanic Field SGI Silicon Graphics Inc.
PSI Process Safety Institute SGML Standard Generalized Markup PTFE PolyTetraFluoroEthy lene Language PTn Paintbrush Nonwelded Tuff Si1E Standard Ilydrogen Electrode PUF Pressurized Unsaturated Flow SitT Single lleater Test PVilA Probabilistic Volcanic llazards SKI Swedish Nuclear Power inspectorate Assessment S-L Short Transverse-bngitudinal PVilVIEW Probability of Volcanic Ilazards SLAR Side Looking Ai < ime Radar VIEW SNF Spent Nuclear Fuel PVM Parallel Virtual Machine SNL Sandia National Laboratories PWR Pressurized Water Reactor SOW Statement Of Work QA Quality Assurance SR Site Recommendation QAP Quality Assurance Procedure SRB Sulfate-Reducing Bacteria QRAM Quality Requirements Application SRBS Shafts, Ramps, Boreholes. and Their Matrix Seals RAI Request for AdditionalInformation SRD Software Requirements Description RASA Regional Aquifer System Analysis SRS Savannah River Site i
RDCO Repository Design, Construction.
SRSASF Savannah River Site Aluminum-l and Operations Based Spent Fuel l
RDTME Repository Design and Thermal-SS Stainless Steel Mechanical Effects SSC Structures, Systems, and Components i
REE Rare Earth Element SSW South-Southw est REECO Reynolds Electrical and Engineering STEM Scanning Transmission Electron j
Company, Inc.
Microscopy l
RES OtYice of Nuclear Regulatory Research STP StafT Technical Position l
RFP Request For Proposal SUFLAT Stochastic Analyses of Unsaturated l
Ril Relative llumidity Flow And Transport l
RSRG Real Space Renormalization Group SVF Springerville Volcanic Field l
RT Radionuclide Transport Su RI Southwest Research Institute RTS Radwaste Treatment System SZ Saturated Zone SAIC Science Application International 1A Technical Assistance Corporation TAN Test Area North SAP Standards Approval Package TBD To Be Determined SAR Safety Analysis Report TBM Tunnel Boring Machine SCA Site Characterization Analysis TCP/IP Transmission Control Protocol!
SCC Stress Corrosion Cracking Internet Protocol SCCEX Substantially Complete Containment TDEM Time-Domain Electro-Magnetic Example TEDE Total Effective Dose Equivalent SCE Standard Calomel Electrode TEF Thermal Effects on Flow SCFF Southern Crater Flat Fault TEM Transmission Electron Microscopy SCM Surface Complexation Idodels TFE Tetrafluoroethylene SCP Site Characterization Plan Til Therinal-llydrologic SCR Software Change Report TIIC Thermal-llydrologic-Chemical SDMP Site Decommissioning Management TilMC Thermal-llydrologic-Mechanical-Plan Chemical SDS Structural Peformation and Seismicity TL Transverse-Longitudinal TLM Triple-Layer Model Viii
1
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ABBREVIATIONS (cont'd)
TM Thermal-Mechanical WSRC Westinghouse Savarmah Riser TMil Thermal-Mechanical-Hydrological Company TMI-2 Three Mile Island Unit 2 WSS Waste Solidificatioa Systems TMS The Minerals, Metals, and Materials WTSO Washington Technical Support Office Society WVDP West Valley Demonstration Project TOP Technical Operating Procedure WVNS West Valley Nuclear Senices TP Technical Position WWW World Wide Web TPA Total-system Performance Assessment XPS X-Ray Photoelectron Spectroscopy TPI Time Period of Regulatory Interest XRD X-Ray Diffractometry TR2 DOE Seismic Topical Report No. 2 Y2K Year 2000 TRG Technical Review Group YM Yucca Mountain TSAR Topical Safety Analysis Report YMP Yucca Mountain Project TSPA Total System Performance Assessment YMR Yucca Mountain Region TSPA-VA Total System Performance Assessment-YMRP Yucca Mountain Review Plan l
Viability Assessment YMSCO Yucca Mountain Site Characterization TSPAl Total System Performance Assessment Office and Integration YTD Year-To-Date TSw-Chnv Topopah Spring Welded-Calico liills Nonvitric TVD Total Variation Diminishing TWFN Two White Flint North TWINS Tank Waste Information Network System TWRS Tank Waste Remediation System UA Uni $ersity of Arizona UACil Universidad Aut6 noma de Chihuahua UCLA University of California, Los Angeles UDEC Universal Distinct Element Code 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 USFIC Unsaturated and Saturated Flow Under Isothermal Conditions USGS U.S. Geological Survey UTM Universal Transverse Mercator 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 WFO Work Fer Others WGB Western Great Basin WIPP Waste Isolation Pilot Plant WNYNSC Western New York Nuclerr Service Center WOL Wedge-Opening Loading WP Waste Package iX
EXECUTIVE
SUMMARY
-PERIOD 13 in the Division of Waste Management (DWM) Job Code (JC), the Center for Nuclear Waste Regulatory Analyses (CNWRA) staff transmitted the revised CNWRA Quality Assurance Manual, Assessment of Performance issues Related to Alternate EBS Materials and Design Options, Effect of Environmental Factors on the Aqueous Corrosion of HLW Containers-Experimental Results and Models, Process Level-Sensitivity Analysis (REFLUX 3/MULTIFLO)-Status Report, Pre-Closure Standard Review Plan Rev. 0-Progress Report, Long-Term TM Effects on Repository Design / Performance: Discontinuum Model-Letter Report, Process-Level Rockfall Study for input to SEISMO Module of TPA Code-WP Analysis Report, and Comments on the Proposed EPA Standard 40 CFR Part 197: CNWRA Input to Commission Paper. The staff produced papers and posters for presentation at various technical meetings. 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 3.4 percent. Spending rose from the previous period as a result ofincreased activity in specific key technical issues, and the cumulative cost variance decreased in both dollars and percentages again this fiscal period.
In the Tank Waste Remediation System JC, staff delivered Final Report on Chemistry of Hanford Tank Waste Remediation System Waste Pretreatment Technology (Revision 1). The YTD cost variance was 11.9 percent. Spending increased from last period-causing the cumulative cost variance to decrease in this period.
In the Dry Transfer System (DTS) JC, staffcontinued developing the DTS draft safety evaluation report, and they received the U.S. Department of Energy (DOE) response to the seccnd round request for additional information (RAI). The YTD cost variance was 2.3 percent. Despite two periods with a negative cumulative percent variance in this JC, the final cumulative percent variance was positive.
In the Centralized Interim Storage Facility (CISF) JC, staff anticipates receiving instructions to revise the draft assessment report and will wait for the DOE response to the Spent Fuel Project Office RAI on the HI-STAR and HI-STORM topical report for high seismic risk sites. The YTD cost variance for the CISF was 38.3 percent. Spending increased from the previous period as staff was engaged in the review of LS-DYN A 3D benchmarking report.
In the Private Fuel Storage Facility JC, staffdelivered the Safety Evaluation Report-Final Letter Report and the Seismic Investigation of Site-Final Report. Moreover, they have engaged in extensive interactions with NRC staff to prepare the NRC final positions on five Group 1 contentions. The YTD cost variance was 7.0 percent. Additional funds coupled with lower per period spending resulted in an increase of the positive cumulative cost variance.
In the Savannah River Site Aluminum-Based Spent Fuel JC, staff trr.nsmitted a revised report, incorporating NRC staffcomments on the report, Review ofthe U.S. Department af Energy Evaluation of the Disposability of Aluminum-Based Spent Nuclear Fuel-Final Report. The YTD cost variance was 33.3 percent. The cumulative cost variance rose as per period spending declined from the previous period.
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I CNWRA PROGRAM MANAGER'S PERIODIC REPORT ON ACTIVITIES OF THE CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES TITLE: Center for Nuclear Waste Regulatory Analyses (CNWRA)
CONTRACTOR: Southwest Research Institute (SwRI) 6220 Culebra Road, San Antonio, Texas 78238-5166 CONTRACT NO: NRC-02-97-009 JOB CODES: D1035, J5164, J5186, J5206, J5226, J5210 NRC CNWRA PROGRAM MANAGER: John J. Linehan,(301)415-7780 NRC CNWRA DEPUTY PROGRAM MANAGER: Deborah A.DeMarco,(301)415-7804 CNWRA PRESIDENT: Wesley C. Patrick,(210) 522-5158 ESTIMATED HUDGET: $87,611,477 PERIOD OF PERFORM ANCE: 09/27/97-09/27/02 i
PERIOD OF THIS REPORT: 08/28/99-09/24/99 1
TECHNICAL 1.1
. CNWRA Operations (COPS)
In addition to a wide range of day-to-day activities, accomplishments in the management and planning area included (i) preparing Revision 14, Change 0, to the OPS for FY2000 and I
other NRC-related operations plans;(ii) finalizing task requirements for the EQA, DOE I
DEIS, Public Outreach, and YMRP sections of the OPS for FY2000; (iii) providing estimates for FY2000 carryover monies; (iv) addressing col-related topics among the j
NRC, SwRI, and CNWRA management staffs; and (v) participating in weekly 11LW j
Management Board meetings.
The status of CNWRA staffing is indicated in trble 1. During period 13, intensive recruitment continued and several sources were used to identify potential candidates. A q
limited-term geotechnical engineer and a chemical engineer joined the staff and a limited-term hydrologist willjoin the staffin period 3 of FY2000.
Computer system support activities encompassed (i) continuing the use of consultants to develop and modify software as well as document hardware / software changes to the Sun j
Microsystems, Silicon Graphics, and Windows NT servers; (ii) upgrading the desktop l
computers for basic system standardization and Y2K compliance;(iii) pursuing acquisition of hardware and software for the CNWRA Security System (firewall); (iv) updating all 1
hardware / software inventory records; (v) participating, as requested, in the monthly NRC/CNWRA Computer Coordination meeting; and (vi) maintaining LAN operations.
QA activities included (i) responding to the CARS from the FY1999 CNWRA QA Audit and making changes to several procedures; (ii) conducting surveillances, issuing nonconformance reports and corrective action requests, as required, and working with
[
cognizant staff in response to these reports; (iii) supporting the application of configuration control for CNWRA scientific and engineering software ready for release; (iv) preventing organizational COI through SwRI RFP reviews;(v) performing QA verification checks on each CNWRA deliverable; (vi) providing QA indoctrination for new CNWRA staff members and consultants; and (vii) submitting the revised CNWRA Quality Assurance Manual and distributing it to key CNWRA staff members.
In the next period, the CNWRA staff expect to (i) deliver Revision 14, Change 0, to the FY2000 OPS and other NRC-related operations plans; (ii) aggressively pursue hiring for open core staff positions; (iii) continue use of consultants to complete Y21C reconciliation, develop new and modify existing databases and spreadsheets, and revise LAN configurations, including installation of revisions to the CNWRA firewall; and (iv) provide CNWRA LAN operation and maintenance support.
In addition, the staff will (i) participate in revising the procurement procedure and the technical operating procedure dealing with the development and control of scientific and engineering software and other activities addressing the CARS identified at the annual CNWRA QA audit,(ii) perform scheduled and unscheduled QA surveillances. (iii) conduct QA indoctrinations for new CNWRA staff and consultants,(iv) review SwRI RFPs for potential COI, (v) perform QA verification checks on eacn CNWRA outgoing deliverable, and (vi) update the quality requirements attached to CNWRA contracts to subcontractors and consultants.
1.2 Igneous Activity (IA)
Staff continued to process data collected during the August 1999 field investigations at Cerro Negro volcano, Nicaragua. Detailed maps were prepared using differential GPS data 3
and field measurements. The August 1999 eruption produced about 1 x 106 m ofjuvenile basalt, with mass-flow rates of 0.5-4 m' s" during 2.5 days of activity. Analyses of geophysical data continue to support the interpretation ofshallow dike emplacement around I km south of the new vents. This dike formed an extensive fissure system with 52-110 cm of pure horizontal extension and created a prominent thermal anomaly in the hydrologically unsaturated zone subsurface. Both free and forced convective flow occur in fissures located within the main thermal anomaly. Staff prepared three abstracts for the 2000 Winter AGU meeting: Transient Electromagnetic Anomalies at the New Cerro Negro Vents, Nicaragua Following the August 1999 Eruption; integrated Geophysical Surveys of the August 1999 Fracture Set at Cerro Negro Volcano, Nicaragua; and August 1999 Eruption ofCerro Negro Volcano, Nicaragua, Successfully Forecast Using Time-Volume Relationships.
Staff observations at Cerro Negro provide timely insights into risi sssessments for YM in four ways. First, probability models of volcanic disruption of the repository depend on spatial factors such as the development of vent alignments and the relationships between 2
preexisting faults and basaltic volcanism. The August activity at Cerro Negro emphasizes the local interrelationships between crustal structures and magma ascent in tectonically l
stressed areas, which supports current NRC volcanic hazard assessments. Second, the eruption illustrated the links between crustal strain, seismicit", and volcanism on an observable timescale. These links have been the topic of debate,, hazard assessments for Yhi. At Cerro Negro, the 1999 eruption and the preeruption seismicity apparently were responses to crustal extension across the volcano alignment. In this case, the resulting strain was partitioned between seismic deformation and magma intrusion. This observation supports the hypothesis that geodetic strain rate is an important indkator of the recurrence rate of basaltic volcanism and seismicity. Third, the eruption illustrated the potential need for dit cet linkage between seismicity and volcanism in pas. Numerous moderate magnitude earthquakes accompany igneous intrusions into the shallow crust. At Yhi, such earthquakes could potentially damage WPs that are otherwise not affected by volcanism. This tie between seismicity and volcanism is not currently included in pas. Fourth, once the shallow intrusion geometry is modeled, these data can be used to evaluate performance models for HLW emplacement at Yhi.
Staff continued development of analog experiments with supporting theoretical models describing the interaction of basalt ascending along a vertical dike and intersecting a repository drift. The experimental system, which was designed at the University of Bristol (U.K.), was shipped and installed at CNWRA during this period. The experimental system is based on a simplified model of the dike-turnel geometry and consists of a vertical Hele-Shaw cell, made up of two parallel plates that represent the dike. In this apparatus, the base of the cell is connected to an aluminum cylinder acting as a fluid reservoir. Initial experiments on low volatile content flows have been completed now using viscous syrup.
This case allows establishment of some of the underlying principles, which control the l'ow, without the complications of volatile exsolution and explosive fragmentation phenomena.
j The syrup is initially stored in the Hele-Shaw cell and the reservoir, where pressures can be controlled independently. A hydraulically controlled gate is then opened rapidly to connect the cell to a horizontal glass cylinder maintained at a lower pressure.
Two sets ofexperiments were performed with the apparatus. Initially, a series ofcalibration experiments were conducted to examine the ascent of syrup in the Hele-Shaw cell as a function of the pressure drop between the reservoir and the top of the ascending layer of syrup. This tested the model of flow resistance in the reservoir-dike part of the system independent of the tunnel. The second main set of experiments involved measuring flow in the tunnel after the gate was opened between the tunnel and the Hele-Shaw cell. The rate of advance of the syrup and the shape of the t'ow front were then measured in the tunnel by analyzing recorded videos of the experiments. Experiments were performed with the tube pressure ranging from 0 to 900 mbar and show that the syrup rapidly advances into the i
tube and progressively fills the drift at a rate determined by the pressure drop. The i
experimental results have been successfully compared to a theoretical model of slow, time-dependent, viscous flow in the tunnel. The model was then scaled-up to examine the potential flow regime that might result if volatile-poor magma intersected a repository drift.
hiagma might advance along the tunnel with speeds up to a few tens of meters per second, thereby flooding the repository in minutes. The staff is preparing a paper describing this experimental system, including the apparatus.
3 i
CNWRA staff gave two presentations at the University Navstar Consortium volcano geodesy workshop was held at Jackson, WY, on September 15-19,1999. Staffattended the workshop with the goals of becoming familiar with the current state-of-the-art in volcano geodesy and presenting recent CNWRA work on volcano deformation associated with small-volume basaltic eruptions at Cerro Negro. The meeting was an outstanding opportunity to learn about new instruments and techniques in geodesy applicable to work in the IA and SDS KTIs and to performance confirmation monitoring of the proposed repository at YM. One of these instruments is the borehole strain-meter recently developed at the Carnegie Institution, capable of resolving strains of 10 3 nm/m. Attention should be paid to the potential role of borehole strain-meters for investigating and monitoring YM.
Very high resolution, continuous strain measurements would be extremely useful for monitoring deformation associated with normal perfonnance of the repository. Such deformation would be produced by, for example, volumetric expansion associated with heating of the repository. These instruments would also provide exceptional insight into tectonic processes operating at YM and may be useful for improving volcanic and seismic hazard assessments. Current users of this method were careful to point out that borehole strain-meters will provide the best results if a long baseline is developed before the onset of deformation that might be expected during normal repository operations. Strain partitioning was also a topic of the workshop. Excellent opportunities exist for integrating some of the current techniques for describing strain partitioning into CNWRA models of seismicity and deformation in the YMR. For example, many talks presented calculations of the geodetic moment (analogous to the seismic moment) and directly calculated coulomb stress from geodetic models. The calculated coulomb stress was then compared to seismicity maps. Staff should consider integrating these types of analyses directly into tectonic models and hazard assessments.
CNWRA staff continued development of models of magnetic anomalies in the YMR that were identified during earlier IA KTl investigations. Techniques for the 3D inversion of magnetic anomalies using simulated annealing and Bayesian updating are being developed in collaboration with staffat the University ofTexas Institute for Geophysics. A preliminary model was prepared of three aligned and reversely magnetized anomalies in the Amargosa Desert,just south of Lathrop Wells. The inversion indicates that all three anomalies have similar depths of burial, intensities of magnetization, and remnant inclination and declination. These results support the interpretation that these anomalies are produced by a buried alignment of basaltic vents and should be included in volcanic hazard assessments.
Staff prepared a presentation for an invited lecture at a meeting of the Royal Society (London) on science during volcanic crises. Staff continued to review the geology suons of the DOE DEIS for the proposed repository and provided additional input to the YMRP.
The Consequences of Basaltic Igneous Activity on HLW Repository Performance--Letter Report for numerical modeling of mag:aa-repository interactions was delayed to allow for additional reviews. Staff participated in the Process Hazard Analysis: Qualitative and Quantitative Analysis Methods course.
In the next period, staff will continue to analyze and model data from the August activity at the Cerro Negro volcano. Staff will participate in a Royal Society meeting on causes of andesitic volcanism and make an invited presentation at the Royal Society meeting on science in volcanic crises. Analog experiments of magma-repository interactions will 4
1 evaluate the response of a high-volatile content system during sudden decompression and fragmentation. Staff will continue to develop user manuals for geophysical software and also the deliverable Consequences of Basaltic igneous Activity on HLW Repository Performance-Journal Article. Staff development of the YMRP and review of the DOE DEIS for the proposed repository will be conducted under newly established separate WSS categories for each of thore activities.
1.3 Structural Deformation and Seismicity (SDS)
Period 13 activities continued to focus on completing the revisions to the SDS IRSR to be forward to the DOE. Staff began incorporating the SDS acceptance criteria into the YMRP and reviewing input to the FY2000 OPS.
Staff completed a field study of faulting in the Volcanic Tablelands in California. The field work revealed the role of folding in accommodation of strain across the tablelands.
Monoclinal folds at the tips of faults suggest that other monoclinal folds unassociated with faults may indicate additional buried faults.
The EarthVision geologic model for hydrologic modeling was nearly completed.
Compilation of the complete model takes 12 hr, and technical problems encountered during compilation of the model appear to have been resolved.
Staff participated in the PSI liazard Evaluation Course.
In the next period, staff will begin modifications and additions to the 3DStress software leading to Version 2.0, following completion of the TOP-018 requirements. Moreover, staff will continue development of the YMRP. The EarthVision model will be provided to the USFIC staff.
1.4 Evolution of the Near-Field Environment (ENFE)
Staff continued an analysis of ENFE-relevant content in the DOE database of FEPs, which focused on inclusiveness and FEPs screening. Attendance at a September 8,1999, DOE /NRC Appendix 7 meeting at Las Vegas, Nevada, afforded an introduction to the DOE scenario screening methodology and the FEPs database. After receiving the database (Rev 00b) during this period, staff began a review for relevant FEPs that DOE excluded.
Staff continued augmented studies of the Nopal I deposit at Pena Blanca to improve understanding of radionuclide mobility among secondary phases in a hydrologically unsaturated, chemically oxidizing environment comparable to YM. U-Th concentrations were measured on 18 carbonate samples collected from near the deposit Crystalline calcites have relatively high U indicative of aqueous release and transport along fractures on the scale of tens of meters. Caliche samples have a high U content similarly indicative of U release from the deposit. Several samples with high U-Th (up to 1,000) have been identified i
for U-Th isotopic analysis. Age data from these samples will provide an independent basis for evaluating DOE work performed at Nopal I as part of the YMP.
5 l
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NRC ant' CNWRA staffs collaborated on a review of the DOE Disposal Criticality Analysis Methodology Topical Report and completed a preliminary draft SER. ENFE-related concerns ir the SER focused on the approach m and validation of geochemical models affecting fissile material release and near field transport.
Staffprogressed in both the interpretation ofthe revised YM UZ groundwater chemistry and the development of cocpled hydrological-geochemical simulations of YM. The revised UZ groundwater chemistry will be used as input for ENFE PA calculations and sensitivity analyses using the TPA code.
Alternative conceptual models of trace metal transport at the Akrotiri archeological site were analyzed and compared with reference to implications for PA modeling. A first draft of the results of this study was completed and is in revision.
Synthesis of uranophane cordinued. Interpretation ofanalytical and XRD data indicates that stoichiometric uranophane, to be used in solubility and coprecipitation studies, was successfully prepared.
Staff continued development of the MULTIFLO code and the TVD algorithm for Version 1.2. The TVD algorithm makes it possible to model advection dominated flow with little numerical dispersion. Staff reiterated the need for development of a drift climate module for Version 2.0. This module will make it possible to model ventilation and thermal radiation in an open emplacement drift.
Preparation of the ENFE portion of the FY2000 OPS was completed. CNWRA staff from the ENFE, CLST, and TEF KTIs held a meeting to discuss the FY2000 OPS and to plan ENFE subissue resolution activities for FY2000. A separate meeting was held between TEF and ENFE staff to develop a consistent approach to TH calculations. ENFE staff also participated in discussions with CLST staff on proposed improvements to SNF dissolution models and sensitivity analysis of releases due to glass waste form dissolution.
In addition, staff began a study on the potential effects of radiolysis on the near-field environment-inside and outside the WP, and searched the DOE and other published literature on this subject matter.
In the next period, staff will obtain U-Th isotopic data on Nopal I carbonates to assess the timing of deposition from U-bearing waters; these data will be supplemented by XRD determination of mineral phases. Staff will participate in a technical exchange on the DOE criticality topical report to discuss DOE responses to the NRC/CNWRA RAl and will continue preparation of the criticality SER. Staff will complete initial analysis of the DOE FEPs database, begin preparation of a letter report on the database analysis, and travel to NRC to discuss the results.
i 1.5 Container Life and Source Term (CLST) j l
Staff transmitted the report Assessment of Performance issues Related to Alternate EBS Materials and Design Options, during this period. This report summarizes the material properties, the physical metallurgical characteristics, and the corrosion processes that may 6
)
affect the major classes of materials considered for construction of the containers for the various WP designs and other components of the EBS, including nickel-base alloys, titanium alloys, and SSs. This report reviews the degradation processes ofZircaloy cladding and ceramic coatings and includes the most recent information provided by the DOE during the DOE /NRC Appendix 7 meeting held at LLNL July 7-8,1999.
Staff delivered the report Effect of Environmental Factors on the Aqueous Corrosion of HLW Containers-Exparimental Results and Models. This report presents experimental results from laboratory investigations ofpassive dissolution, localized corrosion, and stress corrosion cracking susceptibility of Alloy 22. Modeling of these corrosion processes, to be incorporated as a model abstraction in the next version of the TPA code, is discussed and compared with the modeling approach used by the DOE.
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.
Potentiostatic and open-circuit tests using creviced Alloy 825 specimens continued, reaching total test times of1,463 and 1,317 days, respectively. In addition, three Alloy 22 specimens with attached crevice-forming devices are being tested at 95 C in a 4M Nacl solution at pH 8. One specimen is being 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 has been detected on the Alloy 22 specimens held at applied potentials of 300 and 400 mVsce fter approximately 4 mo testing time. Additional a
short-term tests were conducted with as received and welded Alloy 22 specimens to determine the temperature and chloride concentration dependence of the repassivation potential. Expressions for the repassivation potential obtained in these tests will be used in future versions of the TPA code.
Passive corrosion rates of welded Alloy 22 are being measured in slightly alkaline (pH 8.2) and acidic (pH 2.7) chloride solutions at 95 *C. In slightly alkr line solutions, the passive corrosion rate of welded Alloy 22 was quite similar to that measured fer the as-received material. Transpassive dissolution and slight grain boundary attack were observed only at potentials greater than 600 mVset. Tests are being performed in acidic chloride solutions.
Staff conducted SCC tests of Alloy 22 and type 316L SS specimerts. Fatigue precracked, wedge-loaded DCB specimens of each material were immersed m a deaerated 5 percent Nacl solution, acidified to pH 2.7 by the addition of hcl, and heated to 90 *C to duplicate conditions used at the LLNL. Tests on Alloy 22 used an initial stress intensity of 33 MPa m;', whereas the type 316L SS specimens were tested at an initial stress intensity of 25 MPa m. No cracking of the two alloys was observed under these test conditions for a cumulative test time of 44 wk. Testing under open-circuit potential conditions in MgCl2 solutions (30 and 40 percent) at 110 "C shows significant crack growth in the type 316L SS specimens after a short exposure period. An average crack growth rate of 1.0 x 104 m/s was measured at K = 22 MPa m. In contrast, no crack growth was observed on Alloy 22 i
specimens tested for 33 and 44 wk in 40 percent MgCl solution at 110 C under 2
open-circuit conditions. SCC propagation tests of type 316L SS specimens conducted at various applied potentials in 30 percent MgCl solution at 110 C showed the crack growth 2
rate decreases as the potential decreased. A threshold stress intensity for crack growth, Kw 7
l F
=: 13 MPa m'2, was determined in this solution. More tests using 316L SS specimens under applied potential conditions are planned to determine the effect ofpotential on initiation and crack propagation. These experiments are needed to confirm whether the repassivation potential may be used as a threshold criterion for precracked specimens as was previously demonstrated for smooth specimens in slow strain rate tests.
Evaluation continues of the effects of enviro, mental variables on the corrosion behavior of Ti-grade 7 (identified by the DOE as a possible candidate material for drip shield construction). Long-term tests are used to examine the effects of high applied potentials as well as galvanic coupling of Ti to carbon steel. Carbon steel components will be used for ground support. Crevice corrosion testing also continued at temperatures greater than 100 *C to examine the effects of temperature on the critical potentials for localized corrosion of Ti. Given the high resistance of Ti alloys to localized corrosion, studies progressed on the passive dissolution behavior ofTi as well. In addition, welded specimens are being evaluated to examine the potential detrimental effects of weldments on corrosion resistance.
Staff pursued testing of glass wasteforms using the standard EA glass and two simulated waste glasses (DWPF Blend 1 and WVNS Reference 6) using the ASTM PCT, Method B.
Long-term tests on these three g! asses are conducted in deionized water and concentrated FeCl and FeCl solutions (0.25 and 0.0025M) with solution replacements twice a week 2
3 using PFA TFE-flourocarbon vessels. Sixteen solution replacements have been made and the leachates analyzed using ICP to determine the effect ofiron cations on the dissolution rate of the reference glasses. This effect is important for assessing the influence of steel corrosion products on glass degradation. In addition, staff use PUF test equipment to study the dissolution behavior of simulated wasteforms under repository conditions. Long-term tests exceeding 6 mo are planned.
Staff continued developing and implementing suitable corrosion potential and chemistry (Cl concentration and pH) sensors to be used under heat transfer conditions. Electrodes have been fabricated and the test matrix finalized. The final assembly will be employed in the simulated drift experiments coordinated by the TEF KTl team.
Moreover, staff are analyzing the effect of rockfall on the mechanical failure of SNF cladding, in which a fracture mechanics approach is used to evaluate the conditions for fuel rod and fuel assembly fractures, in the next period, staff will pursue long-term corrosion tests of Alloys 825 and C-22 and the SCC tests using Alloy C-22 and type 316L SS along with the Ti-grade 7 test program, including examination oflocalized cor,rosion of welded specimens. In addition, staff will continue to examine the effect of the environment on the corrosion behavior of Zircaloy-4 and begin to evaluate current sensor designs to be used in the TEF KTl simulated drift experiments. Staff also will prepare papers for the CORROSION 2000 conference and submit them for internal technical and programmatic reviews during the next reporting p,:riod. Staff will perform additional glass-dissolution tests and complete analysis of the mechanical failure of fuel cladding.
8
i 1.6 Thermal Effects on Flow (TEF)
Staff pursued analyzing the results of the second test related to the laboratory-scale boiling isotherm depression heater experiment, and they prepared a journal paper based on this activity.
Staff transmitted a report, Process Level-Sensitivity Analysis (REFLUX 3/
MULTIFLO)-Status Report, concerning the results of drift-scale simulations of the 60 MTU/ acre thermal loading with ventilation and a sensitivity analysis to assess TEF and evaluate the TPA Version 3.2 code REFLUX 3 submodule. They also conveyed an abstract summarizing the TPA results to evaluate dripping, for presentation at the 2000 Winter AGU meeting to be held in San Francisco, California, on December 13-17,1999.
Staff continued preparation of a proposed laboratory-scale coupled corrosion / heater experiment in collaboration with the staffs from the TEF, ENFE, and CLST KTIs.
Candidate sensors for the experiment have been received and will be bench tested for use in the experiment. A workshop will be held at the NRC within the next two months to discuss the activities of the coupled experiment.
In addition, staff continued laboratory investigation and visualization into the nature of capillary flow in and dripping from an artificial fracture. They prepared and tested several variations of synthetic fractures and are using the results to assess an analytical solution for seepage into a spherical opening with a periodic internal boundary condition. Staff sent an abstract on this analysis for presentation at the 2000 Winter AGU meeting.
Staff are reviewing temperature data from the Drift-Scale Heater Test in the ESF and posing questions to the DOE regarding apparent anomalous temperature readings. Modeling efforts using the MULTIFLO code are underway to provide more detailed information on l
temperature and relative humidity in the near-field environment to staff in other KTis.
These models include the effects of backfill but not ventilation.
Staff participated in a DOE /NRC Appendix 7 meeting at the DOE Las Vegas Atlas laboratory facilities on September 10,1999. The objective of the meeting was to observe and discuss recent results and future studies of the 1/4-scale drift experiments performed by the DOE.
l Results of a literature review and model development of fracture flow and dripping into an l
underground cavity (under a subcontract to Columbia University) were presented to staff on September 24, 1999. This study was conducted to provide a potential alternative perspective of the critical mechanisms that control fracture flow through partially saturated fractured media and flow into an underground cavity.
l Staff pursued development of the laboratory test apparatus for measuring dripping into a drift opening. Fracture surfaces to be investigated will include plexiglass and glass etched with grooves together with welded tuff (either saw-cut or natural). This conceptual model for dripping uses flow input from an analytical groove / film-flow model, expressions for estimating drip volumes and detachment times as functions of groove geometry and flux rate along the fracture face, and modifications to account for evaporation. Staff completed 9
l l
1
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an independent review of the technical literature on dripping into an opening and is preparing an independent conceptual model for such dripping.
In the next period, staff plan to (i) submit the journal article on the boiling isotherm penetration laboratory-scale experiment; (ii) continue scoping and planning analyses in conjunction with the ENFE and CLST KTl staffs for the third laboratory-scale heater test; (iii) integrate a groove / film-flow model into the mechanistic fracture flow model; (iv) continue development of a 2D, repository-scale, thermohydrological model; and (v) continue development of the laboratory-scale capillary diversion experiment.
1.7 Repository Design and Thermal-Mechanical Effects (RDTME)
Staffincorporated the resolution ofNRC management review comments into the RDTME 1RSR, Revision 2, and will deliver this final version of the IRSR during the next reporting period.
Along with the continued development of the YMRP for the preclosure aspects, the NRC/CNWRA team is currently developing acceptance criteria and review methods for the preclosure performance objectives emphasizing integrated safety analysis, performance confirmation, and retrievability of waste. A report documenting progress to date was conveyed on September 20,1999, as Pre-Closure Standard Review Plan Rev. 0-Progress Report.
Staff completed the first phase of the TM study of drift stability in the area where the transition from strong to weak rock occurs using the repository design provided in the TSPA-VA. This analysis also included the assessment of performance of the rockbolt ground support system under thermally induced stress corJitions. A report documenting the findings of this study was delivered on September 16,1999, as Long-Term TM Effects on Repository Design / Performance: Discontinuum Model-Letter Report.
The ABAQUS code modeling of WPs continued to investigate the thermal stress of WPs and assess the 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. The preliminary findings of this investigation were documented in a progress report, and this report was transmitted on September 24, 1999, as Process-Level Rockfall Study for input to SEISMO Module of TPA Code-WP Analysis Report.
To support the UDEC code analyses predicting the size and extent of rockfall under seismic loads in the repository thermal environment, staff analyzed the scanline information from the ESF using the sterconet approach to identify distinctjoint sets. The identified joint sets were treated individually statistically to determine the distribution ofjoint plunge, trend, spacing, and trace length. Staff are performing a systematic analysis to quantify the distribution of rock block sizes along the ESF. This distribution may be used as input to the SEISMO module in the TPA code.
The RDTME staff attended the training course, Process Hazard Analysis: Qualitative and Quantitative Analysis Methods, on September 13-17,1999 at CNWRA. This training 10
f course was intended to enhance staff understanding on ISA. This understanding will help facilitate development of the preclosure aspects of the YMRP and use of the ISA tool for prediction of preclosure performance of the repository.
The staff continued preparation of the RDTME portion of the FY2000 OPS.
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 ABAQUS l
code to model WPs,(iv) continue working on the RDTME portion of the FY2000 OPS, and l
(v) attend the DECOVALEX 111 workshop to be held Octobe S-7,1999, in Las Vep%,
Nevada.
1.8 Total System Performance Assessment and Integration (TSPAI)
- Staff finalized the strategic plan for the PA tool development. This plan describes a strategy for development and documentation of the PA tools that will be needed to conduct reviews of the DOE SR anel LA and to support the performance confirmation program. This report will be delivered during the first week of period.
Staff continued to implement NRC approved modifications to the TPA code and started preliminary testing of the TPA Version 3.3 code. CNWRA and NRC PA staffs continued interactions with staffs in other KTis to identify and compile potential process-level changes for TPA Version 4.0 code.
I i
l Staff participated in a DOE /NRC Appendix 7 Meeting on FEPs held at Las Vegas, Nevada, September 8,1999. A trip report summarizing the key points will be delivered during the first period of FY2000.
Development of the parameter-tree post-processor has been postponed because of the unavailability of key staff members. A delay until the next FY has been approved by the NRC. Activities related to this development are expected to proceed at a slow pace.
Development of the post-processor for the systematic presentation of TPA output awaits finalization of contracts with external contractors.
YMRP development continued in collaboration with NRC staff. KTl team leads and ISI leads prepared acceptance criteria and review methods and were appraised of NRC staff comments on two example ISI sections at a meeting where various aspects of the YMRP development were discussed. A draft version of the preclosure portion of the YMRP was submitted as a progress report developed by an NRC/CNWRA team under the sponsorship 1
of the RDTME KTI. Work progressed on the QA portion of the review plan based on l
guidance provided by the NRC staff.
I Five PA staff members attended the five-day course Process Hazard Analysis: Qualitative and Quantitative Analysis Methods as a part ofISA training.
11 r
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Staff began updating / preparing TSPAI IRSR, Revision 2-Letter Report. A new IM has been establishe to document revisions, and it is scheduled to be completed by the end of l
December 1999.
During this period, a CNWRA QA staff representative attended the annual DOE QA compliance audit of LLNL as a member of the NRC HLW QA Task Force. The DOE audit j
t team evaluated the implementation, adequacy, and effectiveness of LLNL activities supporting the YM site characterization project during the past year. An electronic report was provided.
Other activities during this period include staff participation in an abstract review meeting and information of new PA sessions for the Waste Management 2000 conference to be held on February 27-March 2,2000 in Tucson, Arizona, together with preparation of papers for the NRC approved presentations at the Waste Management 2000 conference and the Scientific Basis for Nuclear Waste Management Symposium to be held on November 29-December 3,1999, in Boston, Massachusetts.
Staffinterviewed candidates for the unfilled positions of a health physicist, a risk analyst, and two PA engineers. R6sumss continue to be gathered for other open positions for core staffin this area.
In the next period, the staff will focus on (i) delivering the strategy paper on TPA code development, DEIS and YMRP will be conducted and reported separately (ii) incorporating NRC staff comments into revision 2 of the TSPAl IRSR,(iii) developing / writing a report summarizing the results of the external review of the TPA Version 3.2 code,(iv) finalizing the input to the TSPAl portion of the FY2000 OPS,(v) continuing code modifications for the TPA Version 3.3 code, (vi) discussing changes to be implemented in the TPA Version 4.0 code, and (vii) preparing papers for conferences. Recruitment will continue for the two PA engineers, one health physicist, and a risk analyst.
1.9 Activities Related to Development of the NRC High-Level Waste Regulations (ARDR)
Staffdelivered an IM entitled Comments on the Proposed EPA Standard 40 CFR Part 197:
CNWRA Input to Commission Paper. This report is the result of a thorough review of the recently proposed EPA HLW Standard. The review was completed on an expedited schedule so comments would be available to NRC staff preparing the Commission paper.
Staffresponded to comments on the draft of 10 CFR Part 63. They also began consideration of potential changes to the Statements ofConsideration and proposed 10 CFR Part 63 based on review of the comments.
Further, staff continued to improve the technique used to simulate the effects efl>orehole dilution. For the residential receptor group, probability distributions for the fraction ofmass captured by the well have been determined for ovo pumping rates and two screen lengths.
This work, begun in the ARDR KTI, will be transferred to the USFIC KTl for FY2000.
Probability distributions for the fraction ofmass captured will be obtained for a wider range of pumping rates, screen lengths, dispersivity values, aqu ifer heterogeneity, and source zone mixing effects.
12
In the next period, emphasis will be placed on identifying potential changes to the proposed 10 CFR Part 63 and the Statements ofConsideration resulting from the responses to public comments on the draft 10 CFR Part 63. Analyses supporting these responses to public comments will be conducted as needed to support an upcoming IM.
1.10 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC)
Staff continued the watershed modeling of upper Split Wash. This work focused on analyses of subbasin areas to support scaling of parameters to the watershed grid. Field measurements and observations of surficial materials, in conjunction with existing GIS coverages of soil and bedrock lithology, are being directly incorporated into simulations using refined grids to evaluate the significance of runoff /runon during precipitation events that could lead to focusing ofinfiltration.
Staffcollected and analyzed meteorologic data from Nevada and nearby areas ofCalifornia, Utah, and Arizona and from around YM to support modeling of infiltration under future climate conditions at YM. Predictions of the spatial distribution ofinfiltration depend on spatial distribution ofclimatic inputs, most importantly MAP and MAT. Daily observations through 1997 from all National Weather Service stations in Nevada and the surrounding states were obtained. At least 171 stations (262 for MAT) east of the Sierra Nevada mountains range in the Mojave Desert and the Great Basin were used, with elevations from
-55 m through 3,800 m. Estimated regression relations for MAP account for 80 percent of variability and for MAT,95 percent of variability. Only stations with record lengths of at least 20 yr were used for MAP (5 yr for MAT) to improve the robustness of the data set.
Observations from the network of 9 DOE meteorological stations are well within the scatter of data points. Annual average snowfall, winter and summer precipitation, and annual average maximum and minimum temperatures were also examined.
Abstracts submitted for the American Geophysical Union Fall 1999 meeting include (i) Possible Sources offocused infiltration: Upper Split Wash Watershed, Yucca Mountain, Nevada; (ii) Climate-Sensitive Vegetation Model for Yucca Mountain Driven by Elevation, Slope, and Aspect; (iii) Coupled Hydrological and Ecological Processes in Arid and i
Semiarid Environments; (iv) Aggregation of Matrix and Fracture Properties for one-dimensional Shallow Infiltration Estimates; and (v) Evaluation of Hydrologic Parameters Used to Assess Performance at Yucca Mountain, Nevada.
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l Staff pursued the analysis of error due to grid discretization m simulating unsaturated flow f
around and into horizontal cylindrical underground openings. The results of this study are l
to be presented at the Annual Meeting of the Society for Mining, Metallurgy, and l
Exploration, February 28-March 1,2000, Salt Lake City, Utah.
1 Staff updated the parameters used in the TPA code to estimate the fraction of radionuclide mass captured by pumping wells at distances of 5-10 km from the repository. Lower pumping rates were incorporated into the algorithm: the previous range of water use for 3
15-300 households was expanded to 1-300 households, or a range of 3.4-1,000 m /d.
In addition, staff continued processing and reducing data from the May-June 1995, i
multi-well hydraulic test at the C-Holes Complex. During this test, the pumping rate in Well i
13
UE-25 C#3 was the greatest of any open borehole pumping test conducted at the C-Holes Complex to date. Additionally, the observation wells, monitored on an hourly basis, are distributed throughout a large area and thus may provide insight into directional dependence and scale dependence of aquifer properties. Observation well water-level data are afTected by surface barometric pressure Ductuations. Staff are investigating several methods for correcting well water-level data for barometric effects. Many of these methods also allow for eluddation of UZ properties.
Staff continue to improve understanding important features and processes that may affect groundwater flow along the alluvial portion of the groundwater flow path from YM. The process includes review of pertinent literature, data, and well logs and analysis of geophysical data collected earlier in the year.
In the next period, USFIC activities will include (i) a field trip to two YM climate analog sites, Rainier Mesa and three-Springs basin in the Kawich range;(ii) continued investigation of models for seepage and dripping in underground cavities; (iii) sustained analysis of processes affecting deep percolation under present and future climate scenarios:
(iv) continued analysis of aquifer pumping-test data from the C-Holes Complex at YM; and (v) continued development of a site-scale model for SZ flow.
1.11 Radionuclide Transport (RT)
Staff prepared two presentaticns for the Seventh International Conference on the Chemistry and Migration Behavior of Actinides and Fission Products in the Geosphere (Migration '99), scheduled for Lake Tahoe, Nevada, September 26-October 1,1999. The first, Uranium (VI) Sorption Behavior on Silicate Mineral Mixtures, will be a poster presentation of experimental and modeling results of U sorption on mixtures of quartz and clinoptilolite. The second presentation, Modeling Colloid Transport for Performance Assessment, will be an oral presentation of TPA sensitivity analyses and detailed sorption modeling with site-specific hydrochemistry to evaluate the potential effects of colloid transport of Pu and Am on repository performance.
Staff completed the evaluation of published data and the development of thermodynamic parameters for predicting ion-exchange equilibria between zeolites and groundwater. They prepared two draft manuscripts summarizing an evaluation ofexperimental data and surface complexation modeling of radionuclide cation ( Am, Pu, and Np) and anion (1, Se, and Tc) sorption onto mineral surfaces. In addition, they developed other draft manuscripts on the stochastic analyses of Np transport through saturated media and a stochastic mathematical development of colloid transport through the SZ.
Staff began sensitivity runs with the TPA Version 3.2 code to support preparation of the manuscript Technetium-99 Chemistry in Reduced Groundwaters: Implications for the Performance of a Proposed High4evel Nu: lear Waste Repository at Yucca Mountain, Nevada, for presentation at the Materials Rcsearch Society Annual Meeting to be held in Boston, Massachusetts, November 29-December 3,1999. Staff obtained Nuclear Energy Agency data on Tc for use in speciation and solubility calculations. They also proposed and developed approaches for two modifications to TPA Version 4.0 code, including a sorption response surface and a colloid transport module.
14
Staffcontinued preliminary experiments investigating the sorption behavior ofTc-99. Batch sorption experiments began using an initial Tc-99 concentration of 3 x 104 molal and the zeolite mineral clinoptitolite (Na-form) as a substrate. These experiments are being conducted over a pH range of 3-9.5 in 0.1 molal Nacl and under oxidizing conditions, where it is calculated that Tc exists in solution as the TcOi ion.
Chemical analyses of groundwaters sampled from Nye County EWDP wells were completed. These results will be used for comparison and discussion at the EWDP geochemical data exchange, sponsored by the USGS and Nye County, on September 29, 1999, in Denver, Colorado.
Staffcontinued preparations for experiments investigating the sorption and coprecipitation behavior of Np on calcite. Due to difficulties with the experimental configuration, an alternative configuration that better suits the experimental requirements for the coprecipitation experiments was chosen. Necessary additional equipments have been ordered. Additional standard solutions of Np-237 were also ordered and received.
Mapping continued of the acceptance criteria from the RT IRSR subissues and integrated subissues into the YMRP autline, for consideration by NRC. Beginning in period 1 of FY2000, this mapping will be conducted and reported under a separate task for YMRP development. Preparation continued on the RT portion of the FY2000 OPS.
In the next period, staff will continue to evaluate Tc thermodynamics and aqueous solubilities for YM groundwater compositions and to revise reports on ion exchange and surface complexation. Staff will continue sorption experiments on alluvium minerals and redesign Tc sorption experiments to reduce sources of uncertainty. Staff also will present technical assistance results at the Migration '99 conference. Staff will assist in the PA abstraction process and perform sensitivity analyses using the TPA Version 3.2 code to investigate the calculated effects oflocalized reduction on Tc transport behavior.
1.12 Review of the Draft EnvironmentalImpact Statement (DEIS)
Staff and external consultants continued review of the DOE DEIS for the proposed repository. Orientation meetings were held at the CNWRA with all but one of the external consultants. Questions were prepared to support an DOE /NRC scheduled for October 7, 1999, at NRC headquarters. Preparations were made for YM site visits and participation in a DOE public meeting in Pahrump, Nevada, to be held September 29-October 1,1999. The CNWRA project manager participated in weekly DEIS review teleconferences with NRC staff.
In the next period, the staff will(i) participate in YM site visits and a DOE public meeting in Pahrump, Nevada; (ii) participate in a DOE /NRC technical exchange; and (iii) continue preparation of specific comments on the DOE DEIS for ths, proposed repository.
1.13 Tank Waste Remediation System (TWRS)
In subtask 1.2, staff addressed the NRC comments on Process 11azards and Safety issues for TWRS-P, Volume I, Low-Activity Waste Feed Makeup, Solidification, and Offgas 15
e Treatment. Change pages were accepted on September 14,1999. NRC staffcomments were received on Process Hazards and Safety issues for TWRS-P, Volume 11, Auxiliary Support Systems and Process Control Svstems. These comments require minor changes to the text, and the staff will address through change pages.
In subtask 1.6, staff completed the revisions to the Hanford Tank Waste Remediation System Pretreatment Chemistry and Technology report and submitted the final version on September 17,1999, in subtask 2.1, staff proviid draft comments to the NRC staff (September 23,1999) on the River Protection Project Waste Treatment Plant Explosive Hazards Evaluation Report. This report reviewed five areas of explosive hazards.
Staff continued development of the FY2000 operations plan based on the NRC guidance.
In the next period, in subtask 1.2, staff will address the NRC comments on the Process Ilazards and Safety issues for TWRS-P, Volume 11, Auxiliary Support Systems and Process Control Systems. Change pages will be delivered by the scheduled date of October 15, 1999. In subtask 1.4, staff will begin work ou the Classification and Categorization of Process Safety Issues. In subtask 1.6, development of a spreadsheet model for the TWRS waste pretreatment will begin. In subtask 2.1, staff will start review of the Topical Report on the Management of Risks Posed by Explosive Hazards Present at the River Protection Project-Waste Treatment Plant. This report provides a review of hydrogen explosive hazards. Draft comments will be provided to the NRC staff via email. Staff will complete development of the FY2000 operations plan.
1.14 Dry Transfer System (DTS)
The DOE response to the NRC second round RAI was received during this period.
Development of the DTS draft SER was reinitiated, making use of the CNWRA and SwRI staffs and an external consultant.
In the next period, the staff will accelerate the development of the draft SER.
1.15 Centralized Interim Storage Facility (CISF)
I Limited review ofthe LS-DYNA 3 D benchmarking report was performed during this period consistent with diminished assignments from the NRC.
In the next period, the staff will review and evaluate the DOE response to the SFPO RAI on the HI-STAR and HI-STORM topical report for high seismic risk sites.
1.16 Private Fuel Storage Facility (PFSF)
The staff delivered the draft SER as Safety Euluation Report-Final Letter Report as well as the final version of the seismic exemption application evaluation report, Seismic Investigation of Site-Final Report. In addition, the NRC and CNWRA staffs engaged in 16
f extensive interactions to prepare the NRC positions on several' contentions. Staff received the revised seismic design reports during this period and started to review these reports.
In the next period, the staff plans to review and evaluate the revised seismic design reports and assist the NRC staff on ASLB hearing activities.
I 1.17 Savannah River Site Aluminum-Based Spent Fuel (SRSASF)
The staff responded to NRC comments on the report, Review of the U.S. Department of Energy Evaluation of the Disposability of Aluminum-Based Spent Nuclear Fuel-Final Report, incorporated these comments into the text, and transmitted the revised repon. This project is now complete.
In the next period, there will be no activity on the SRSASF project and therefore, no reporting.
2 MANAGEMENT ISSUES None to report.
3 MAJOR PROBLEMS None to repon.
1 4
SUMMARY
OF SCHEDULE CIIANGES Schedule changes for IMs are included in table 3. Completed deliverables are noted in table 4.
5
SUMMARY
OF FINANCIAL STATUS Table 5 summarizes the CNWRA financial status in the context of authorized funds. Total commitments are $425,427. 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, DEIS, and ten KTis, TWRS JC, DTS JC, CISF JC, PFSF JC, and SRS ASF JC. The planned costs per period are based on the revised spending plans contained in the current OPS.
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. Despite focused efforts on recruitment, current staffing remains below authorized levels.
reriod 13 FY1999 CNWRA composite expenditures rose 25.3 percent from the previous period, and this aggregate of all JCs was underspent by $620,983 or 4.5 percent. This is the lowest cumulative percentage variance for the entire fiscal year. When comparing period 13 with last period, only the PFSF and SRS ASF JCs evidenced lower spe:: ding levels, while the DWM, TWRS, DTS, and CISF JCs showed higher levels.
17
Expenditures on SwRI labor, consultants, and subcontractors as a proportion ofcomposite spending on all JCs were 34.2 percent-reDecting payment of accrued vouchers from ci wultants and subcontractors. Expense of consultants and subcontractors as a fraction of coryosite spending on all JCs was 30.6 percent-primarily resulting from payments of those acc. ed vouchers. The CNWRA continues to enhance, where appropriate, participation of consultants and r'., contractors in the conduct of CNWRA work.
As shown in table 1, the CNWRA has 56 staff members. The available pool of appreved consultants and subcontractors is 81.
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 $403,571 or 3.4 percent. Overall expenditures increased about 30.7 percent from the previous period as costs rose in COPS, DEIS, and the IA, CLST, TEF, RDTME, TSPA, USFIC, and RT KTIs; but declined in the SDS, ENFE, and ARDR KTis. Costs to date are 33 percent above those a year ago, and period 13 costs are 72 percent greater than the same period last year. Although below expectations, spending on the augmented scope of s A has documented significant progress in accomplishing the work associated with this augmentation. In various meetings with NRC senior management staff and other interested parties, CNWRA senior management staff continue to discuss current and expected levels of spending, aggressive recruitment efforts for core staff, and effective engagement of consultants and subcontractors.
Although actual spending in the last five fiscal periods exceeded estimates, the CNWRA did not attain the estimated spending in the currently approved OPS by the end of FY1999. However, the cumulative variance for FY1999 was lower tha previously estimated. The CNWRA will offer a revised estimate of carryover monies in the first period of FY2000.
The cost variance for COPS was 4.8 percent: 5.9 percent for the Management, Planning, and Computer Support subtask (158) and 0.4 percent for the QA subtask (159). Spending this period in subtask 158 increased relative to last period. In the first period of the new fiscal year, spending in subtask 158 is expected to exceed the estimated amount because some consultants and temporary staff wi;l be retained for specific tasks (e.g., complete Y2K compliance, revise the CNWRA LAN, create new and revise existing databases, and modify the firewall). CNW RA management continues to encourage eligible staff to participate in professional development activities. In subtask 159, spending decreased in period 13 relative to last period because costs associated with the annual QA audit were paid. Spending in the first period of FY2000 is anticipated to follow estimated spending.
)
The cost variance for the I A KTI was - 14.8 percent. Spending increased significantly relative to last period because outstanding subcontractor invoices were paid. Approximately $33,000 of unpaid commitments will be carried over into FY2000.
The cost variance for the SDS KTl was 2.3 percent. Spending decreased relative to period 12 because most of the consultant and subcontractor invoices were processed for work completed earlier this summer. The approximate $20,000 is the result ofnot receiving data requested from DOE in a timely fashion.
The cost variance for the ENFE KTl was 2.1 percent. This variance resulted mainly from payment of consultant and subcontractor invoices.
18
The cost variance for the CLST KTl wa; -9.5 percent. Spending increased significantly compared to period 12 due to the effort required to complete the deliverables for FY1999 on schedule an'i the addition of a new staff member.
The cost variance for the TEF KTl was -0.6 percent. Spending increased markedly from the previous period, yet actual expenditures in FYl999 closely followed the budget for this KTl for FY1999.
The cost variance for the RDTME KTl was O percent. Thus, the FY1999 total expenditures converged tr 'ne FY1999 allocation.
The cost variance for the TSPAI KTl was 5.' percent. For the fifth consecutive period actual spending increased significantly over budgeted spending, due in part to increased work on the YMRP and paymem ofconsultant invoices for the TPA external review meeting. Tm spending rate is expected to decrease somewhat during the first period of FY2000.
The cost variance for 6he ARDR FTI was 38.7 percent. A portion of the funds associated with the cumulative underspending has been reallocated to a new taA-review of the DOE DEls for the proposed repository. This reallocation was presented as chwge pages to the OPS.
1 The cost variance for the USFIC KTI was 5.3 percent. This is a decrease in both cumulative percent and absolute variance from the pievious period. The decrease in variance resulted from the processing ofinvoices received during periods 12 and 13 and posted to the account in period 13.
The cost variance for the RT KTl was 9.3 percent. This is a significant decrease in both cumulative percent and absolute variance from the previous period, resulting from payment of consultant invoices and material costs.
The cost variance for the DEIS project was 58.5 percent. This variance is a result of a delayed start caused by late receipt of the DEIS and by the administrative process necessary to establish the external consultant contracts. Spending increased as CNWRA staff and external reviewers began preparation of DEIS comments. Spending will continue to increase in the next period due to participation in several site visits and a DOE public meeting in Nevada. The CNWRA FY2000 OPS proposes a revised spending plan to reflect more accurately the expected expenditure schedule.
The cost variance for the TWRS project, was 11.9 percent. A slight increase in spending from the previous period coupled with significant negative variance in per period spending has resulted in the decrease in the cumulative percent variance.
The cost variance for the DTS pmject was 2.3 percent. Thus, the FY1999 total expenditures closely followed the FY1999 allocation.
The cost variance for the CISF project was 38.3 percent. This cost underrun is due to lack of assignment from the NRC.
The cost variance for the PFSF project was 7.0 percent. This cost underrun is because of lagging charges from the subcontractors.
19
The cost variance for the SRSASF. after a budget reduction in the project during period 9, was 333 percent. Spending for period 13 was lowerthan period 12 because repcrt production and related activities decreased for the majority of the period. This project was completed during this period, i
i f
1 I
i 20
O T.able 1. CNWRA Core Staff--Current Profile and Iliring Plan * (Period 13)
Es pertise/Es perience Current No.
Professional Staff Posiemns Open FY1999 ADMINISTRAllON 4
11 GARCIA. W. PATRICK. J RUSSELL B SAGAR Cl!EMICAL PikOCESSING 2
VJAIN, D.DARUWALLA ENGNGlPIIYS CitLM j
CODE ANALYSIS / DEVELOPMENT 2
R.JANETZKE. R. MARTIN DATA MANAGEMENT / PROCESSING.
I P.MALDONADO INC1.UDING FIN ANCIAL DOSE'RlSK!!!AZARD ANALYSIS 0
i ELECTROCill:M!STRY a
G CRAGNOLINO ENGINEERING 2
R.CIIEN. G OFOEGBU GE OLOGY / GEOL.OGICAL ENGNG ENVIRONMENTAL SCIENCES I
P.LaPLANTE GEOCIILMISTRY 8
P.BERTETTI. LBROWNING. W.MURPilY, R.PARALAN, E PEARCY. J PRIKRYL D TURNER. M NUGENT GEOffYDROL.1XiY/IIYDROGEOLOGY DTARRELL, RIEDORS. R. GREEN. M.llILL, J WINITRLE Gl.0 LOGY 3
P LAFEMINA. LMcKAGl'E. M.MIKLAS IIYDROLOGIC TRANSPORT 3
A.ARMSTRONG. D i{UG11 SON. S. PAINTER I
INFORMATION MANAGEMENT 0
l SYSTEMS MATERIAL SCIENCES 6
S BROSSIA, D.DUNN, O.MOGHISSI. Y-M PAN, 1
N.SRIDilAR, LYANG MECilANICAL.
1 D GL IT.
INCLUDING DESIGN & FADRICATION MINING ENGINEERING 1
S-M tiSIUNG NUClf.AR ENGINEERING 1
M SMint OPERATIONAL IIEALTil PIIYSICS I
J WELDY l
PERFORMANCE ASSESSMENT 3
S.MOHANTY. O PENSADO-RODRIGUEZ, 2
G WITTMEYER l
OUALITY ASSURANCE I
D.MABRITO RADIOISOTOPE GEOCllEMISTRY l
D PICKETT ROCK MECHANICS.
3 A CllOWDlIURY, A GilOSil. B.DASGUI'I'A INCLUDING CIVIUSTRUC. ENGNG SOURCE-TERM.' SPENT FUEL DEGRAD 0
1 STRUCTURAL GEOLOGY /
3 DIERRILL, D SIMS, J.STAMATAKOS SE1SMO-TECTONICS SYSTEMS ENGINEERING I
P.MACKIN VOLCANOLOGY.1GNEOUS 2
C.CONNOR, B Hill y E SSES TOTAL
$6 8
- See staffing plan for details 21
r O
e Table 2. CNWRA Core Staff-Summary by Area of Concentration (Pe*iod 13)
Positions Area of Concentration
~ Actual Planned Open ADMINISTRATION, QUALITY ASSURANCE AND 6
7 1
INFORMATION MANAGEMEN T GEOCllEMISTRY 9
9 0
1 IlYDROLOGY/ CLIMATOLOGY -
8 9
1 MATERIAL SCIENCES 7'
9 2
MECHANICAL, CIIEMICAL, NUCLEAR, AND SYSTEMF 5
5 0
ENGINEERING PERFORMANCE ASSESSMENT-6 10 4
ROCK MECilANICS, MINING, AND GEOLOGICAL 6
6 0
ENGINEERING STRUCTURAL GEOLOGY, TECTONICS, AND VOLCANISM -
9 9
0 TOTAL 56 64 8
22
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e Table 5. Financial Status (Period 13)
Funds Funds Funds Project Names Authorized Costed to Date Uncosted Commitments COPS 3.486.007 3.400.748 85.260 34.820 IA 1.389.829 1.495.694 (105.864) 32.809 SDS 1.849.790 1.835.179 I4.611 37.819 ENFE 1.721.526 1.717.132 4.395 125.585 CLST 1.793.743 1.903.601 (109.858) 6.569 TEF 1.288.017 1.294.394 (6.377) 20.811 RD1ME I.320.362 1.321.683 (l.32 I) 39.590 TSPAI 3.568.908 3.460.857 108.051 54.972 ARDR 494,99's 379.441 115.554 4.276 USFIC 2.268.997 2.204.022 64.975 7.833 RT l.360.633 1.274.991 85.642 17.732 DEIS 154.506 64.179 90.327 0
DWM Costs 20.697.313 20.351.919 345.394 DWM Award Fee 1,196.006 849,751 346.255 DWM Base Fee 827.893 794.157 33.736 TOTAL DWM 22.721.211 21.995.826 725.385 382.815 TWRS Costs 1.583.378 1.497.850 85.527 0
TWRS Award Fee 93.654 77.449 16.205 TWRS Base Fee 63.335 60.556 2.780 j
TOTAL TWRS 1.740.367 1.635.855 104.512 0
)
TMI 2 ISFSI SAR Costs 282.197 282.758 (561) 0 TMI-2 ISFSI SAR Award fee 16.423 15.552 871 TMI-2 ISFSI Base Fee 11.288 11.061 227 TOTAL TMI-2 ISFSI SAR 309.908 309.371 537 0
DTS Costs 400.435 394.796 5.639 0
DTS Award Fee 23.323 14.293 9.030 DTS Hase Fee 16.017 15.621 396 TOTAL DTS 439.775 424.710 15.065 0
CISF Costs 409.053 343.375 65.678 0
CISF Award Fee 24.338 19.124 5.214 CISF Base Fee 16.362 13.661 2.70i TOTAL CISF 449.753 376.160 73.593 0
PFSF Costs 445.968 426.758 19.210 42.612 PFSF Award Fee 26.581 11.737 14.844 PFSF Base Fee 17,839 16.087 1.752 TOTAL PFSF 490.388 454.582 35.806 42.612 SRSASF Cests i13.401 100.492 12.909 0
i SRSASF Award Fee 7.110 5.439 1.671 l
SRSASF Base Fee 4.536 4.244 292 l
TOTAL SRSASF 125.047 IIn i /,
14.872 0
Grand Total 26.276.450 25.306$a$i 969.770 425.427 Note: All authorized funds have been allocated through modification #131. Funds costed to date for each award fee program represent the award fee for FY 1998 and interim for FY 1999. Funds uncosted for each award fee program represent the aw ard fee reserved from the last authorizations based on the Operations Plans for FYl999.
25
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a APPENDIX Planned and Actual Costs, and Cost Variances Period 13-FY1999 i
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