ML20237B772
| ML20237B772 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/14/1998 |
| From: | CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES |
| To: | NRC |
| Shared Package | |
| ML20237B753 | List: |
| References | |
| CON-FIN-D-1035, CON-FIN-D-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-98-11, NUDOCS 9808190244 | |
| Download: ML20237B772 (38) | |
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l CNWRA PROGRAM MANAGER'S PERIODIC REPORT l
ON ACTIVITIES OF THE CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES I
For the Fiscal Reporting Period i
July 4,1998 - July 31,1998 PMPR No. 98-11 I
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August 14,1998 l
I 819 980814 l
WM-11 P DR,.,
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TABLE OF CONTENTS Section Page
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TABLES.........................................................................iv AB B RE VIATIONS................................................................ v EXECUTIVE
SUMMARY
-PERIOD 11............................................... xi j
1 TEC H NICAL............................................................... I 1.1 CNWRA Operations (COPS)............................................ I 1.2 Igneous Activity (I A)................................................... 2
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1.3 Structural Deformation and Seismicity (SDS)............................... 3 1.4 Evolution of the Near. Field Environment (ENFE)............................ 3 1.5 Container Life and Source Term (CLST).................................. 4 1.6
'Ihermal Effects on Flow (TEF)......................................... 5 1.7 Repository Design and 'Ibermal-Mechanical Effects (RDTME)................. 6 1.8 Total System Performance Assessment and Integration (TSPAI)................. 7 1.9 Activities Related to Development of the NRC High-Level Waste Regulations (ARDR)...................
............................ 8 1.10 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC)........... 9 1.11 Radionuclides Transport (RT)...........................
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1.12 Tank Waste Remediation Systems (TWRS).
I1 1.13 Three Mile Island Unit 2 Independent Spent Fuel Storage Installation (TMI-21SFSI)........................................... 12 1.14 Dry Transfer System (DTS).......................................... 12 1.15 Centralized Interim Storage Facility (CISF)...............................
13 1.16 Private Fuel Storage Facility (PFSF).....................................
13 1.17 Savannah River Site Aluminum-Based Spent Fuel (SRSASF).................
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M ANAGEMFNT IS S UES.................................................
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MAJOR PROBLEMS
....................................... 13 4
SUMM ARY OF SCHEDULE CHANGES......................................
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SUMMARY
OF FIh A.NCIAL STATUS........................................
14 APPENDIX-Planned and Actual Costs, and Cost Variances Period Il-FY98 1
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TABLES Table Page 1
CNWRA Core Staff-Current Profile and Iliring Plan * (Period 11),,................. 17 2
Summary of Schedule Changes (Period 11)............
........................ 18 3
Deliverables (Period 11)...................................................
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Financia1 Status (Period 11).................................................. 20 5
Private Fuel Storage Facility License Fee Cost Recovery Status (Period 11)............. 21 iv
o ABBREVIATIONS 1D One-Dimensional CDTS Commission Decision Tracking System 2D Two-Dimensional CED Center for Environmental Biotechnology 3D Three-Dimensional CEC Commission of the European AA Atomic Absorption Communities AAI Average AnnualInfiltration CFD Computational Fluid Dynamics ACD Advanced Conceptual Design CFR Code of Federal Regulation ACF Alumina (in excess of alkali feldspar),
CIAC ComputerIncident AdvisoryCapability Calcium Oxide, Ferromagnesian Oxide CISF Centralized Interim Storage Facility ACNW Advisory Committee on Nuclear Waste CIST Container Life and Source Term ACRS Advanced Computer Review System CM Configuration Management ADAMS Agencywide Documents Access and CNWRA Center for Nuclear Waste Regulatory Management System Analyses AECL Atomic Energy of Canada Limited COI Conflict ofInterest AES Atomic Emission Spectrometry COPS CNWRA Operations AGU American Geophysical Union CPP Cyclic Potentiodynamic Polarization Al Administrative item CQAM CNWRA Quality Assurance Manual ALTS Apache Leap Test Site CRG Center Review Group AML Areal Mass Loading CRM Corrosion Allowance Material ANS American Nuclear Society CRWMS Civilian Radioactive Waste ANSI American National Standards institute Management System AO Annotated Outline CSCS Constrained Stochastic Climate AP Administrative Procedure Simulator APB Acid-Producing Bacteria CSH Calcium Silicate Hydrate AR Assessment Report CSPE Corrosion Science and Process
^RDR Activities Related to Development of Engineering the NRC High level Waste Regulations DAS Data Acquisition System ASCE American Society of Civil Engineers DBE Design Basis Event ASCU American Standard Code for DC Division of Contracts Information Interchange DCAA Defense Contract Audit Agency ASME American Society of Mechinical DCD Double Cantilever Beam 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 DECOVALE,X development of Coupled Models and ATDTS Automated Technical Data Tracking
'Ibeir validation Against experiments System in Nuclear Waste Isolation BEG Bureau of Economic Geology DEIS Draft Environmental Impact Statement BFD Basis for Design DEM Digital Elevation Model BM Bare Mountain DF Dilution Factor BMF Bare Mountain Fault DFCSS Division of Fuel Cycle Safety and BNFL British Nuclear Fuels Limited Safeguards BTP Branch Technical Position DIE Determination ofImportance CAI Color Alteration Index Evaluation CAM Corrosion Resist 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 l
CCL Commitment Control leg DLM Diffuse Layer Model l
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 CDM Compliance Determinen Method DOE-DP DOE Defense Program CDOCS Consolidated document Management DOE-RU U.S. Department of Energy Regulatory System Unit CDROM Compact Disk Read Only Memory DRA Division of Regulatory Applications CDS Compliance Determination Strategy DST Drift Scale Test l
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AilllREVI ATIONS (cont'd)
DTED Digital Terrain Elevation Data GIS Geographic Information System DTS Dry Transfer System GLGP Geology and Geophysics DWM Division of Waste Management GPS Global Positioning Satellite EBS Lngineered Barrier System GROA Geologic Repository Operations Area EBSER Engineered Barrier System GS Geologic Setting Experiment.a Research GSA Geologic Society of America EBSPAC Engineered Barrier System GTFS Great Tolbachik Fissure Eruption Performance Assessment Code GUI Graphics User Interface ECM Equivalent Continuum Model GWSI Groundwater System Integration EDO Office of the Executive Director for GWTT Groundwater Travel Time Operations HLUR High-Level Waste and Uranium EDX Energy-Dispersive X-Ray Spectroscopy Recovery Projects Branch EIS EnvironmentalImpact Statement HLW High Level Waste EM Element Manager HRTEM High-Resolution Transmission Electron EMPA Electron MicroProbe Analysis Microscopy ENE East Northeast IA Igneous Activity ENFE Evolution of the Near-Field IBM International Business Machines Environment ICP Inductively Coupled Plasma ENGB engineering and Geosciences Branch ICPP Idaho Chemical Processing Plant EnPA Energy Policy Act of 1992 IDLH Immediately Dangerous to Life and ENS European Nuclear Society Health EPA U.S. Environmental Protection Agency IHLRWMC International High-Level Radioactive EPR Electrochemical Potentiokinetic Waste Management Conference and Reactivation Exposition EPRI Electric Power Research Institute IM Intermediate Milestone EQA ExternalQuality Assurance IME Industrial Mobilization Exemption EROS Earth Resource Observation System IMS Information Management Systems ESF Exploratory Studies Facility INEEL Idaho National Engineering and ESP Environmental Simulation Program Environmental Laboratory EW East-West INETER Instituto Nicaraguense de Estudios EXAFS Extended X-Ray Absorption Fine TERritoriales Structure INTRAVAL International Code Validation FAC Favorable Condit on 1/0 Input / Output i
FCRG Format and Content Regulatory Guide IPA Iterative Performance Assessment FDSHA Fault Displacement and Seismic Hazard IR&D Internal Research & Development Analysis IRIS Interim Records Information System FEMM Finite Element Heat and Mass Transfer IRM Office ofInformation tesources s
FEM Finite Element Method Management FEP Features, Events, and Processes IRSR issue Resolution Status Report FFRDC Federally Funded Research and ISA initial Safety Analysis Development Center ISFSI Independent Spent Fuel Storage FIT Fast Fourier Transform Installation FIE Full-Time Equivalent ISM Integrated Site Model FIP File Transfer Protocol IVM Interactive Volume Modeling FY Fiscal Year IWPE Integrated Waste Package Experiments FYTD Fiscal Year-to-Date JC Job Code GDF Ghost Dance Fault JPL Jet Propulsion Laboratory GEM General Electrochemical Migration JRC Joint Roughness Coefficient GEOTRAP geologic Transport of Radionuclides k"11 Key TechnicalIssue Predictions k"IU Key Technical Uncertainty GERT General Employee Radiological LA license Application Training LAAO License Application Annotated Outline GET General Employee Training LAN local Area Network GFM Geological Framework Model LANL los Alamos National Laboratory GHGC GeoHydrology and geochemistry LARP License Application Review Plan GIA Generalized Importance Analysis LAW low-Activity Waste vi
l ABBREVIATIONS (cont'd)
LBNL' Lawrence Berkeley National Laboratory OITS Open-Item Tracking System LBT Large Block Test OMB Office of Management and Budget J
LHS Latin Hypercube Sampling OPS Operations Plans UTC lockheed Information Technology ORR Operations Readiness Review Company ORS Overall Review Strategy LLNL Lawrence Livermore National OWFN One White Flint North Laboratory PA Performance Assessment LLW low-Level Waste PAAG Performance Assessment Advisory LMAES lockheed Martin Advanced Group l
Environmental Systems PAC Potentially Adverse Condition ISS Ucensing Support System PAHT Performance Assessmentand ISSPP Ucensing Support System Pilot Project Hydrologic Transport LSSTB Ucensing Support System Test Bed PASP Performance Assessment Strategic Plan LWR Ught Water Reactor PC Personal Computer Ma Million Years Ago PC/ICP Personal Computerfiransmission MC Monte Carlo Control Protocol METRA Mass and Energy transport PDF Probability Distribution Function MODS Mined Geologic Disposal System PDR Public Document Room MH Mechanical-Hydrological PEL Permissible Exposure Umit MIC Microbially influenced Corrosion PEM Program Element Manager MINC Multiple Interacting Continua PER Relicensing Evaluation Report MIT Massachusetts Institute of Technology PFD Probabilistic Fault Displacement MM Major Milestone PFDHA Probabilistic Fault Displacement MO Management and Operations hazard MOU Memorandum of Understanding PFS Private Fuel Storage MPC Multi Purpose Canister PFSF Private Fuel Storage Facility MRS Monitored Retrievable Storage PHA Preliminary Hazard Analysis MSS MultiSpectral Scanner P1 PrincipalInvestigator MTU Metric Ton of Uranium PMDA Program Management, Policy NAS National Academy of Sciences Development and Analysis Staff l
NAWG Natural Analogue Working Group PMPR Program Manager's Periodic NCR nonconformance Report Report NEA Nuclear Energy Agency PMT Photo-Multiplier Tube NFS Network File Server PNNL Pacific Northwest National Laboratory NIOSH NationalInstitutes of Safety and Health PO Project Officer l
NIR Near-Infrared PPA Proposed Program Approach NIST NationalInstitute of Standards and PPE Prepassivated Platinum Electrode Technology PRA Probabilistic Risk Assessment NMSS Office of Nuclear Material Safety and PRT Peer Review Team Safeguards PSAG Probabilistic System Assessment Group NNE North-Northeast PSHA Probabilistic Seismic Hazard Analyses NNW North-Northwest l'TFE Polytetrafluoroethylene NOAA National Oceanographic and PTn Paintbrush Nonwelded Tuff Atmospheric Administration PVHA Probabilistic Volcanic Hazards NRC Nuclear Regulatory Commission Assessment NS North-South PVHVIEW Probability of Volcanic Hazards NSRkC Nuclear Safety Research Review VIEW Committee PVM Parallel Virtual Machine NTS Nevada Test Site PWR Pressurized Water Reactor NUREG NRC Technical Report Designation QA Quality Assurance NWPA Nuclear Waste Policy Act, as amended QAP Quality Assurance Procedure NWIRB Nuclear Waste Technical Review Board QRAM Quality Requirements Application OBES Office of Basic Energy Sciences Matrix OCRWM Office of Civilian Radioactive Waste RAI Request for Additional l
Management Information OGC Office of GeneralCounsel i
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AllIIREVI ATIONS (cont'd)
RASA Regional Aquifer System SPCR Software Problem Correction Report Analysis SRA Systematic Regulatory Analysis RDCO Repository Design, Construction.
SRB Sulfate-Reducing Bacteria and Operations SRBS Shafts, Ramps, Boreholes, and Their RDTME Repository Design and Thermal-Seals Mechanical Effects SRD Software Requirements REE Rare Earth Element Description REECO Reynolds Electrical and Engineering SRS Savannah River Site Company, Inc.
SRSASF Savannah River Site Aluminum.
RES Office of Nuclear Regulatory Research Based Spent Fuel RFP Request for Proposal SS Stainless Steel RH Relative Humidity STEM Scanning Transmission Electron RIP Repository Integration Program Microscopy ROC Repository Operations Criteria S1P Staff Technical Position RPD Regulatory Program Database SUFLAT Stochastic Analyses of Unsaturated RRT Regulatory Requirement Topic Flow AndTransport RSRG Real Space Renormalization SVF Springerville Volcanic Field Group SwRI Southwest Research Institute RT Radionuclides Transport SZ Saturated Zone RTS Radwaste Treatment System TA Technical Assistance SAP Standards Approval Package TBD To Be Determined SAR Safety Analysis Report TBM Tunnel Boring Machine SCA Site Characterization Analysis TCP/IP Transmission Control SCC Substantially Complete Protocol /Internet Protocol Containment TDI Technical Document Index SCCEX Substantially Complete TDOCS Technical Document Reference Containment Example Database System SCE Standard Calomel Electrode TEF Rermal Effects on Flow SCFF Southern Crater Flat Fault 1EM Transmission Electron Microscopy SCM Surface Complexation Models THC
%ermal-Hydrologic-Chemical SCP Site Characterization Plan THMC Hermal-Hydrologic.
SDMP Site Decommissioning Mechanical-Chemical Management Plan T-L Transverse-Longitudinal SDS Structural Deformation and 11.M Triple Layer Model Seismicity TM Rermal-Mechanical SECY Secretary of the Commission. Office of TMH Thermal-Mechanical Hydrologic the (NRC)
TMI2 Bree Mile Island Unit 2 SELM Spectral Element Method TMS Re Minerals, Metals, and Materials SEM Scanning Electron Microscopy Society SER Safety Evaluation Report TOP Technical Operating Procedure SF Spent Fuel TP Technical Position SFPO Spent Fuel Project Office TPA Total system Performance Assessment SFVF San Francisco Volcanic Field TPI Time Period of Regulatory SGI Silicon Graphics Inc.
Interest SGML Standard Generalized Markup 1R2 DOE Seismic Topical Report No. 2 Lan;;uage TRG Technical Review Group SHE Standard Hydrogen Electrode TSAR Topical Safety Analysis Report SHT Single Heater Test TSPA Total System Performance SIP Scientific Investigation Plan Assessment SKI Swedish Nuclear Power Inspectorate TSPAI Total System Performance S-L Short Transverse-Longitudinal Assessment and Integration SLAR Side Looking Airborne Radar TSw-Chnv Topopah Spring Welded-Calico SNP Spent Nuclear Fuel Hills Nonvitric SNL Sandia National Laboratories TVD Total Variation Diminishing SOTEC Source term Code TWFN Two White Flint North SOW Statement of Work Vili
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ABBREVI ATIONS (cont'd)
"IWINS' Tank Waste Information Network System BVRS Tank Waste Remediation System UA University of Arizona l
UACil Universidad Aut6 noma de i
Chihuahua UCLA University of California-Los i
Angeles j
UDEC Universal Distinct Element Code l
UK United Kingdom j
UNM University of New Mexico UR Uranium Recovery U.S.
United States USDA U.S.Departmentof Agriculture USGS U.S. Geologic Survey i
UTM UniversalTransverse Mercator j
USFIC Unsaturated and Saturated Flow Under Isothermal Conditions UZ Unsaturated Zone VA Viability Assessment i
VCS Version Control System VF Vitrification Facility VSIP Vertical Slice Implementation Plan WAN Wide Area Network WAPDEG waste Package Degradation WBS Work Breakdown Structure WCIS Waste Containment and Isolation Strategy WFO Work for Others WGB Western Great Basin WIPP Waste Isolation Pilot Plant WMD Waste Manatement Branc5 WNYNSC Western New York Nuclear Service Center WOL Wedge-Opening Loading WP Waste Package WSEI Waste Systems Engineering and Integration WSRC Westinghouse Savannah River Company WSS Waste Solidification Systems WTSO Washington Technical Support Office WVDP West Valley Demonstration Project WVNS West Valley Nuclear Services WWW World Wide Web XPS X-ray Photoelectron Spectroscopy XRD X-ray Diffractometry YM Yucca Mountain YMP Yucca Mountain Project YMSCO Yucca Mountain Site Characterization Office YMR Yucca Mountain Region YTD Year-to-Date IX i
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EXECUTIVE
SUMMARY
-PERIOD 11 In the Division of Waste Management (DWM) Job Code (JC), the Center for Nuclear Waste Regulatory
- Analyses (CNWRA) continued work on numerous analyses and revisions to issue resolution status reports (IRSRs). Staff delivered the first part of Probability Models for Yucca Mountain Region-Journal Article.
In addition, the Total-system Performance Assessment (TPA) Version 3.2 code was transmitted on July 17, 1998, fulfilling, in part, User's Guide for TPA Version 3.2-Letter Report. Moreover, staff submitted the following letter reports: (i) Expanded Independent Coupled Process Modeling Capability, MULTIFLO-Letter Report; (ii) Effects of Environmental Factors on Container Life-Letter Report; and (iii) Input to Thermal Effects on Flow IRSR, Rev.1-Letter Report. A general overview paper on the Nuclear Regulatory Conunission (NRC) TPA approach wasjointly prepared by the NRC and CNWRA staffs for presentation at the DISTEC '98 conference to be held September 9-11,1998, in Germany. A CNWRA j
technical staff member participatedin a staff exchange at the NRC that focused on detailed discussions about
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the Unsaturated and Saturated Flow Under Isothermal Conditions IRSR, Rev.1.
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The DWM JC year-to-date (YTD) cost variance was 10.7 percent. Although the cumulative variance increased in dollars since the previous month, this variance decreased on a percentage basis as work i
accelerated in several areas.
j In the Tank Waste Rer".ediation System JC, the YTD cost variance was a -1.2 percent. This variance evidenced oscg.edmg as a result of increased expenditures associated with incorporating the NRC comments into various reports, staff working on a number of reports, and meeting subcontractor commitments in subtask 1.6. Costs are expected to decline as subcontractor work is completed and commitments paid.
In the Three Mile Island Unit 2 (TMI-2) Independent Spent Fuel Storage Installation (ISFSI) JC, the YTD l
cost variance for the TMI-2 ISFSI was 38.5 percent-reflecting continued preparation of the draft safety l
evaluation report.
In the Dry Transfer System (DTS) JC, the staff delivered the First Round Request for Additional Information-Fmal Letter Report. The YTD cost variance for the DTS was 34.3 percent, down slightly from last period on a percentage basis.
In the Centralized Interim Storage Facility (CISF) JC, staif identified technical issues specific to one or more i
of the cask designs proposed for CISF use and also evaluated the U.S. Department of Energy response to the l
NRC first round Request for Additional Information (RAI) for incorporation into a draft assessment report.
The YTD cost variance for the CISF was 19.1 percent. This variance decreased over the previous period.
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In the Private Fuel Storage Facility (PFSF) JC, the CNWRA staff reviewed and evaluated the Private Fuel j
Storage Limited Liability Company response to the NRC first round RAI and prepared the second round RAI.
The YTD cost variance for the PFSF increased to 13.9 percent despite expanded spending over last period.
In the Savannah River Site Alumimsu-Based Spent Fuel (SRSASF) JC, the staff participated in a meeting with the DOE, Savannah River Site, and the NRC staffs in which the CNWRA and the NRC comments l
relating to disposal of Al-clad fuels were discussed, several issues resolved, and paths toward resolving other issues identified. The YTD cost variance for the SRS ASF JC was 31.9 percent. The variance increased this period, although period expenditures increased.
It should be noted that the current spending estimates in all JCs are based on the assumption that staffing is at authorized levels. Current staffing remains below authorized levels and recmitment continues.
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s CNWRA PROGRAM MANAGER'S PERIODIC REPORT I
ON ACTIVITIES OF THE l
CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES TITIE Center for Nuclear Waste Regulatory Analyses (CNWRA) l CONTRACTOR: Southwest Research Institute (SwRI) 6220 Culebra Road, San Antonio, Texas 78238-5166 CONTRACT NO: NRC-02-97-009
.1011 CODES: D1035, J5164 J5186, J5206, J5226, J5210 NRC CNWRA PROGRAh! N1ANAGER: John J. Linehan,(301) 415-7780 NRC CNWRA DEPUTY PROGRAh! 51 ANAGER: Deborah A. Dehtarco, (301) 415-7804 1
CNWRA PRESIDENT: Wesley C. Patrick, (210) 522-5158 ESTIM ATED HUDGET: $87,611,477
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PERIOD OF PERFORNIANCE: 09/27/97-09/27/02 PERIOD OF TIIIS REPORT: 07/04/98--07/31/98 1
TECIINICAL l
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) hosting a visit from the French Standing Committee of Experts and presenting briefings on CNWRA activities to this group; (ii) clarifying l
information on expected Interim Guidance for the Development of Fiscal Year 1999 j
CNWRA OPS for the repository program and beginning text preparation; (iii) engaging in DWh1 budget-related deliberations with the HLW hianagement Board; (iv) addressing further COI-related issues among the NRC, SwRI, and CNWRA management staffs; and (v) participating in weekly IILW Management Board meetings.
l Status of CNWRA staffing is indicated in table 1, consistent with the revised staffing plan l
submitted as part of the revision to the CNWRA Management Plan. During period 11, l
recruitment efforts and interviews continued for the approved open positions. Dr. Debra L.
I Ifughson joined the GHGC staff as a research scientist.
Computer system support activities encompassed (1) finalizing specifications for upgrading hardware and software associated with the GIS and IMS computing facilities, (ii) implementing a strategy for standardizing desktop computer systems, (111) pursuing a replacement for the CDOCS software, (iv) participating, as requested, in the monthly NRC and CNWRA Computer Coordination meeting, and (v) maintaining LAN operations.
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QA activities focused on (i) completing the two CARS; (ii) conducting surveillance, issuing nonconformance notices as required, and working with cognizant staf fin response to these notices; (iii) leading the configuration control effort of the CNWRA scientific and engineering software detennined ready for release; (iv) controlling issued documents and maintaining QA records; (v) preventing organizational COls by reviewing SwRI RFPs; (vi) performing QA verification checks on each CNWRA deliverable; and (vil) making revisions to QAPs as needed.
In the next period, the CNWRA staff expects to (i) initiate development of the FY99 CNWRA OPS, (ii) pursue hiring for open core staff positions, (iii) secure and install computer hardware for GIS and IhtS computing facilities as well as continue the search for a replacement for the CDOCS software, and (iv) provide CNWRA LAN operation and maintenance suppon. In addition, the staff will (i) send the FY98 CNWRA QA Audit-Letter Report (Ihi 1402-159-820) and proceed with scheduled QA surveillance, (ii) perform QA indoctrinations for new CNWRA staff, (iii) input internal documentation and record copies of delivered documents into QA records,(iv) review RFPs for potential COI, (v) perform QA verification checks on each CNWRA outgoing deliverable, and (vi) address the two CARS from the CNWRA annual QA audit.
1 1.2 Igneous Activity (IA)
Staff met this period with internationally recognized experts to discuss thermo fluid dynamic approaches to modeling the phenomenology that could occur when hot, volatile-rich magma intersects a low pressure shallow void such as the proposed Yht repository.
B asaltic magma ascending through the Earth's shallow crust will be under a large con 11ning pressure, in addition, the magma likely will contain several percent dissolved volatiles such as water. Initial assessments indicate that if the magma intersects the drifts from a mined geologic repository several hundred meters berw the surface, confining pressure will decrease by at least an order of magnitude and magma will preferentially flow into the drifts. Staff also discussed modeling of HLW entrainment and transpon during a basaltic volcanic cruption and methods to evaluate the health effects associated with resuspended volcanic ash. The NRC and CNWRA staffs met for a week of directed discussions and presentations with Professor R.S.J. Sparks (University of Bristol, igneous processes),
Professor A.W. Woods (University of Bristol, thermo-fluid dynamic modeling), and Dr. P.J.
Baxter (University of Cambridge hiedical School, volcanic health effects). Key points of the meetings included (i) the current approach to modeling volcanic ash transport (i.e.,
ASHPLUh1E) appears reasonable and adequate; (ii) alternative approaches should be evaluated for incorporating waste into the ascending magma (e.g., transport of discrete HLW particles); (iii) Yht R basaltic magma likely contains 2 percent dissolved water rather than the near 0 percent assumed in many D OE models; (iv) ascending magma that i ntersects drifts will depressurize and may create a high-velocity flow capable of impacting HLW canisters; and (v) analog cruptions provide guidance on potential health effects of volcanic ash, however, additional work is needed to apply this knowledge to basaltic eruption.These three experts are preparing final reports on the meeting, which will be forwarded along with staff recommendations for directed investigations to resolve key consequence subissues.
Staff submitted the first part of Probability hiodels for Yucca Mountain Region-Journal Article (IM 1402-461-850) and placed the second part (also IM 1402-461-850) in technical review. Staff also continued to work on Subsurface Area of Disruption for Basaltic Volcanoes-Journal Article (IM 1402-461-860).
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In the next period, IA staff will submit the second part of Probability Models for Yucca Mountain Region-Journal Article (IM 1402461-850) and continue work on Subsurface Area of Disruption for Basaltic Volchaocs-Journal Article (IM 1402-461-860). Final reports from the volcanology experts will be received and staff will prepare recommendadons for FY99-01 activities to address these subissues. Preparations will commence for licld activities in eastern California to investigate relationships between different rates of crustal extensions and effects on seismic and volcanic hazard rates. Staff also will prepare for a DOE Appendix 7 meeting on Disruptive Scenarios.
1.3 Structural Deformation and Seismicity (SDS)
Staff developed the software validation and testing procedures and completed software testing necessary to qualify the newest version of 3DStress (Version 1.3) following TOP-018 requirements. Qualification of the code is e.rpected by the end of FY98.
Moreover, evaluating the DOE GFM 3.0 EARTIIVISION model proceeded withjoint NRC and CNWRA participation. SDS Staff also continued detailed review of the DOE probabilistic seismic and fault displacement hazard analyses report. These analyses proside input to performance assessment models that calculate the effects of seismicity on repository performance and to preclosure design considerations.
Staff worked on three upcoming deliverables: 3D Structural Model of the Amargosa Desert for input to USFIC-CNWRA Repon (IM 1402471-860), GIS Archive-CNWRA Report (IM 1402-471-850), and Dilation Tendency Analysis of Fracture Patterns-Journal Article (IM 1402-471-862). Development also began on the Structural Evolution of Crater Flat Nevada-Journal Article (IM 1407-471-832), which include detailed modeling of gravity and magnetic data and evaluation of newly collected paleomagnetic data.
Staff initiated project planning for upcoming field work in Owens Valley, California. The field work-scheduled for September-is designed to test implications of anomalous GPS strain rates proposed in a recent Soence article. The work is part of the detailed GPS strain rate evaluation. In addition, staff began preparing the SDS portion of the FY99 CNWRA OPS.
In the next period, SDS staff will continue reviews of the DOE GFM 3D site model and probabilistic seismic and fault displacement hazard analyses report. Staff will also prepare Analysis and Evaluation of Fracture Data-CNWRA Report (IM 1402471-861), Dilation Tendency Analysis of Fracture Patterns-Journal Article (IM 1402471-862), Structural Evolution of Crater Flat Nevada-Journal Article (IM 1402471-832), and update the GIS Archive-CNWRA Report (IM 1402-471-850).
1.4 Evolution of the Near Field Environment (ENFE)
' Die staff attended an organizational meeting of the Materials Research Society Symposium on the Scientific Basis for Nuclear Waste Management XXII, July 10 and 11,1998, Salt Lake City, Utah. They refereed abstracts submitted to the symposium on cementitious
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materials, natural analogs, waste form chemistry, and other subjects, and contributed to meeting organization.
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Collaborative work with a consultant on aqueous actinide chemistry was conducted and a manuscript is in preparation describing this work.
The staff continued to collaborate with the NRC staf f on revision of the ENFE IRSR.
Source term solubility computadons continued to examine a suite of possible near-field solution chemistries and solubility controlling phases.
Staff continued debugging, testing, and documenting the MULTIFLO code Version 1.2p.
The userk manual for this version was transmitted as Expanded Independent Coupled Process Modeling Capability, MULTIFLO-Letter Report (IM 1402-561-810). Inidal verification tests of the new DCM capabilities in the METRA module were started. Near-term priorities for Version 2.0 development were identified. New staff continued to become familiar with the code details with input from a CNWRA consultant.
A teleconference was held with the NRC staff to plan for an NRC and DOE Appendix 7 meeting on cement tentatively scheduled for September 3 and 4,1998, Las Vegas, Nevada.
An NTS site visit will be conducted in conjunction with this meeting.
Staff provided presentations to the French Standing Group of Experts on Waste Management, including an overview of activities in the ENFE KTI and a tour of geochemistry laboratory facilides.
In the next period, the CNWRA staff will continue to review the LLNL Near-Field and Altered-Zone Models Report. Addidonal revisions to the ENFE IRSR will be made. Near-field radioelement solubility modeling and aqueous actinide chemistry studies will advance.
New stuff will continue familiarization with the MULTIFLO code.
1.5 Container Life and Source Term (CLST)
The report, Effects of Environmental Factors on Container Life-Letter Repon (IM 1402-571-860), was transmitted in the form of a numbered CNWRA report (CNWRA 98-008).
The NRC staff technical comments on the Input to Container Life Source Term IRSR, Rev.1-Letter Report continued to be addressed through individual telephone exchanges.
Revisions to this document arising from these discussions are being incorporated by the NRC prior to transmitting the final version to the DOE. Effort is being made to integrate contents of the ENFE and TSPA 1RSRs with this IRSR.
Electrochemical corrosion testing continued for a total test time of 1,448 days to confirm the applicability of repassivation and corrosion potendals as predicuve parameters for the long-term, localized corrosion of Alloy 825 in chloride-containing soludons at 95 *C The corrosion potential, measured for 1,043 days, varied between 270 and 300 mV cs during 3
the last 28 days of tesung. No localized corrosion was observed on specimens maintained below the repassivation potential.
Confirmatory testing of Alloy C-22 stress corrosion cracking susceptibility in hot, concentrated chloride solutions has been delayed to allow addidonal machining of the test specimens. 'Ihe side groves of several specimens are being corrected and knife edges added to allow the use of a clip gage to measure the extension of the initial precrack during fatigue precracking and wedge loading, prior to exposure to the soludon.
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Ec equipment that will be used to perform localized corrosion testing of Alloys 625 and C-22 at temperatures above 95 *C was assembled. Placement of the various electrodes and probes in the autoclaves was completed, as well as fabrication of the platinum counter electrodes. Design and fabrication of high temperature reference electrodes was also completed and calibration of the electrodes initiated. Internal and external pressure-balanced Ag/AgC1/Cl~ reference electrodes are being calibrated against a saturated calomel electrode up to 95 *C, and against each other above this temperature.
De interdependence of solution chemistry, temperature, and potential on localized corrosion of carbon steel is being investigated in simulated repository environments. New test specimens are being made to continue crevice corrosion testing. A clearer dependence of material performance on the environmental conditions was observed in crevice testing, as opposed to boldly exposed pitting tests, since crevice corrosion is easier to initiate than pitting corrosion because of the mass transport restriction offered by the crevice former.
Equipment continues to arrive that will be used for the long-term tests to further examine the conditions leading to stable localized corrosion. Laboratory modifications continued.
In the next period, long-term corrosion tests of Alloy 825 will continue and further localized corrosion testing of carbon steel and Alloys 625 and C-22 will begin. Stress corrosion cracking testing of Alloy C-22 will be initiated. The CLST KTI section of the CNWRA FY99 OPS will be prepared.
1.6 Thermal Effects on Flow (TEF)
The staff continued preliminary testing of the DCM capability in the MULTIFLO code. The imponance and relevance of the fracture / matrix transfer term are being investigated.
Preliminary testing shifted from 1D models to 2D and 3D models.
he second phase of the boiling isotherm depression heater experiment continued during the reporting period. All cement blocks were coated with a scalant to impede imbibition of water, which may result in a factor of 10-100 reduction in sorptivity for those cement blocks coated with a scalant. The staff anticipates that the sealed blocks will act more like a fractured porous medium than the original unsealed concrete blocks, which responded similarly to a single continuum despite the presence of simulated fractures.
Revision 1 of TEF IRSR was transmitted as Input to Thermal Effects on Flow IRSR, Rev.1-Letter Report (IM 1402-661-810) on July 30,1998.
he staff continued the numerical modeling of the DOE DST and drift-scale repository thermal tests. The DST model has been transformed from a 2D ECM to a 2D DCM formulation. The ability of the DCM fonnulation in the MULTIFLO code is being tested during this modeling exercise. Analysis of the DOE LBT is on hold pending the availability of CNWRA staff currently assigned to another KTI task.
An analytical model to describe heat coaduction, two-phase flow, and gravity-driven l
fracture film flow was modified. Preliminary efforts to calculate heat flow in the rock l
matrix adjacent to a fracture using a boundary integral method have provided promising results. The resulting numerical / analytical model will assess the refluxing phenomenon for nonisothermal conditions.
l 5
In the next period, TEF KTI staff plans to (i) continue the boiling isotherm penetration laboratory-scale experiment and analysis, (ii) proceed with refinement of the DST and drift-l scale repository numerical models, (iii) maintain testing of the MULT!FLO-DCM numerical code, and (iv) evaluate the conceptual model of refluxing.
1.7 Repository Design and Thermal Mechanical Effects (RDTME)
The technical comments from various NRC KTI staff members on the Input to the Repository Design and Thermal-Mechanical Effects IRSR, Rev. I were received during this reponing period. One CNWRA staff member participated in a two-day working meeting at TWFN, July 28-29,1998, to resolve these comments. This IRS R text is being revised in response to these comments.
'Dus period, UDEC analysis to predict rockfall under seismic load in the repository thermal environment continued. Results of this simulation work are expected to provide a technical basis for determining the magnitude of the dynamic impact load on the WPs owing to rockfall and also will be used as input to the SEISMO module in the TPA code for disruptive scenario assessment. Several UDEC models with underground excavations in a rock mass having differentjoint patterns have been constructed. Joint information used for generating the different patterns is from the ESF. Die joint patterns were generated by varying joint length and gaps while keeping the joint spacing and orientation the same.
Preliminary studies of subjecting the UDEC models to a sinusoidal seismic wave at the bottom of the model without applying thermal loading indicate that the difference in joint patterns could result in different extent of rockfall.
A progress repon is being prepared to document preliminary results regarding the study of the rock mass behavior under heated condidons at the repository scale with an emphasis on long-term degradation of rock mass material propenies and strengths.
'Ihe investigation of drift-scale rock mass behavior and its effect on concrete lining stability using UDEC progressed during this reporting period. The study of temperature changes at the ground surface resulting from various WP thermalloads using UDEC modeling is near completion.
Staff continued the literature review on concrete performance under high temperature. It will provide valuable information to assess the DOE design of the concrete liner for use at high temperature. Preparation began on an interim progress report to document the results of the literature review.
RDTME activities for the remainder of FY98 will include (i) literature review on the behavior of unreinforced and reinforced concrete (liners) under long-duration, high-temperature conditions; (ii) study of drift-scale rock mass behavior and its effect on liner performance at high temperature; (iii) report preparation for analysis of repository-scale rock mass behavior at elevated temperature; and (iv) simulation of rockfall under seismic load to provide input to the SEISMO code.
6
In the next period, RDTME KTI staff plans to (1) review the literature collected on concrete performance at high temperature, (ii) investigate rock mass behavior under heated conditions on both repository and drift scales with an emphasis on long-term degradation of rock mass material properties and strengths, (iii) conduct rockfall simulations, and (iv) conduct reactive activities including review of design documents.
1.8 Total System Performance Assessment and Integration (TSPAI)
The User's Guide for TPA Version 3.1.4-Letter Report (IM 1402-762-800) submitted last period was accepted by the NRC. Preparation of draft sections was initiated for the changes made to TPA Version 3.1.4.
TPA Version 3.2 code was delivered on July 17,1998 and, fulfills, in part, User's Guide for TPA Version 3.2-Letter Report (IM 1402-762-810). The code is currently undergoing verification testing by the NRC PA staff. Work was initiated in conj unction with other KTIs to finalize the input parameter values for the TPA Version 3.2 code. Revision to the User's guide will be submitted September 30,1998, in the form of changed pages.
A draft plan for conducting a formal external review of the TPA Version 3.2 code was
' transmitted to the NRC. The scope and schedule of the external review was outlined and a draft letter to solicit nominations for experts was prepared. This draft plan and nomination letter will be informally reviewed by the NRC, revised, and resubmitted August 14,1998.
The draft report on the sensitivity studies using the TPA Version 3.1.4 code was informally reviewed by the KTI team leads at the NRC and the CNWRA. Additional analyses were conducted in response to the recommendations by the NRC PA staff and the report is currently undergoing formal technical review by NRC and CNWRA staff members. This report wih be Volume II of Input to TPA Version 3.1 Sensitivity Studies Repon-Letter Repon (IM 1402-761-810). Volume I of this report addresses the model abstractions and base case data used in the TPA Version 3.1.4 code and includes selected chapters from the User's Guide for TPA Version 3.1.4. Volume I has been revised to justify the abstracted models and associated parameter values used in the TPA code.
A repon entitled Importance Measures for Nuclear Waste Repositories was transmitted June 26,1998. In-depth discussions on the suitability of the Generalized Importance Analysis method for quantitative assessment of repository subsystems continue. The document will be published as a journal paper during FY99 to subject the method to a formal peer review.
A general overview paper on the NRC TPA approach was jointly prepared by the NRC and CNWRA staffs for presentation at the DISTEC '98 conference to be held September 9-11, 1998,in Germany.
Efforts continue on (i) a PC version of the TPA Version 3.2 code, (ii) a Java-based post processor for the TPA Version 3.2 code, and (iii) a PVM implementation of the TPA Version 3.2 code.
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1
'The TSPAI 1RSR section on scenario analysis was revised to address informal review comments from the NRC and CNWRA staff. In addition, the TSPAI IRS R section on model abstraction was updated to incorporate the latest infonnation on the DOE and NRC TSPA model abstractions. Input to Total System Performance Assessment IRSR, Rev.1-Letter Repon (IM 1402-761-800) will be delivered August 14,1998.
In the next period, the PA staff will focus on (i) completing the first volume of Input to TPA Version 3.1 Sensitivity Studies Report-Letter Report (IM 1402-761-810);
(ii) finalizing the second volume of the input to TPA Version 3.1 Sensitivity Studies Report-Letter Report (IM 1402-761-810), which reflects actual results of the sensitivity study; (iii) revising the Input to Total System Performance Assessment IRSR, Rev.1-Letter Report (IM 1402-761-800); (iv) continuing the development of a plan for l
external review of TPA Version 3.2; and (v) preparing the PC and PVM versions of TPA Version 3.2 and the Java-based post processor for the TPA Version 3.2 code. In addition, recruitment is ongoing for the PA modeler and risk assessment positions.
1.9 Activities Related to Development of the NRC High-Level Waste Regulations (ARDR)
Effort continued on evaluating the effects of well characteristics and plume dimensions on i
dose estimates needed to support development of attributes of the critical group to be used in 10 CFR Part 63. The purpose of this task is to assess the effects of using more realistic models of the complex hydrogeology of the site on estimates of radionuclides concentrations at pumping wells for both residential and agricultural receptor locations. The modeling approach incorporates spatially variable material propentes, compicx initial and boundary conditions, and multiple pumping wells with variable pumping rates. This period, staff focused on conducting geostatistical analyses on spatial distributions of hydraulic conductivity in the tuff and alluvium. The ISATIS program, used to generate random conductivity fields, was obtained and will be run during the next period.
Revisions to the DCF tables in the previously issued report, Information and Analyses to Support Selection of Critical Groups and Reference Diospheres for Yucca Mountain Exposure Scenarios, were completed but text revisions are pending owing to other DWM commitments; however, the text revisions should be completed next period. The revised repon is expected to be issued as a NUREG/CR and will be a key reference document for the rulemaking effort and TSPAI activities.
The CNWRA staff participated in a final review of a draft of 10 CFR Pan 63 and the associated statements of consideration prior to submission for branch chief review. The EPA standard for YM has not been publicly issued, therefore, the CNWRA milestone for reviewing this regulation was put on hold pending public release of the standard.
In the next period, the dilution study will begin running the ISATIS program to generate random conductivity fields for tuff and alluvial aquifers. If EPA publishes the draft standard, staff will assist the NRC with reviewing it and preparing comments. Revisions to the Information and Analyses to Support Selection of Critical Groups and Reference Biospheres for Yucca Mountain Exposure Scenarios report resulting from changes to the internal dose factors used in GENII-S modeling will be completed.
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i 1.10 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC) a Close interactions with the NRC staff condnued during this period to support development of the USFIC IRSR. Interactions included a CNWRA staff member participating in a staff f
exchange at the NRC. The major activity of the exchange involved detailed discussions about the USFIC IRSR, Rev.1. Other activities included a technical presentation and discussions on unsaturated flow issues such as distribution of shallow infiltradon, structural control of flow, and mechanisms for flow bypassing the zeolitic horizons.
- t Laboratory experiments were developed and initiated to investigate differences between observed rates of moisture imbibition in YM rocks and the imbibition rates predicted by models that use laboratory-determined rock properties. These experiments are presendy in the sample preparation stage.
Laboratory measurements of saturated hydraulic conductivity and water retention of colluvium from the side slopes of YM and the pluvial analog sites are ongoing. Modeling exercises have demonstrated that the development of a soil profile that includes a C-horizon f
could significantly impact shallow infiltration estimates, i
]
u Activities to support the further development of a 3D SZ model continued. A 3D geological model is being prepared to include the area south of YM that is not shown in the DOE model. The existing geological cross sections, acquired from the NTS environmental
=
restoration program, were digitized to create the preliminary structure of the model. Gravity data collected during previous USFIC field work are being processed and analyzed to fill data gaps in the preliminary model. These gravity data will be used to model geologic structure and depth to basement in Fortymile Wash. The search for addidonal data (e.g.,
borehole logs for wells and exploration holes) continued. m x
Interpretation of the C-wells hydraulic and tracer tests progressed. Literature reviews condnue and data manipulation and interpretation have begun. A model used by USGS to interpret three of the tracer tests conducted so far at YM has lieen reviewed with regard to its suitability and the assumptions inherent in the model, especially those related to the
)
exchange of material between the fracture and the matrix. Where possible, improvements to the model will be implemented. Analyses of hydraulle tests conducted at the C-well have also begun. Unfortunately, much of the raw data needed to conduct these analyses are not yet available from the DOE. With the data obtained to date, USFIC staff is presently invesugating the appropriateness of various analytical models'and analysis methods for use in interpreting pump test data.
Work continued in collaboradon with SDS staff to analyze fractures in the Tiva Canyon Tuff. Field data from Live Yucca Ridge and upper Split Wash collected during the last period are being analyzed in conjuncdon with published structural data. Analyses of these l
data will provide input to watershed analysis and modeling of Split Wash.
USFIC staff participated in discussions of an informal working group investigating j
structural controls on SZ 110w at YM. Preliminary assessments of regional anisotropy in the vicinity of the C-wells were provided to working group participants as an example of how fracture and fault orientations may exert control on groundwater flow directions at YM.
9
j in the next period, USFIC activities will include (1) interaction with the NRC staff to l
finalize the USFIC IRSR; (11) preparation of a 3 D, subregional site-scale flow and tra'nsport I
model; (iii) interpretation of data from the CNWRA field studies at YM; (iv) continued interpretation of C-wells data; (v) progress on approaches for modeling future infiltradon; (vi) ongoing discussions with the NRC working group on structural controls on groundwater flow; and (vii) review of the LBNL site-scale unsaturated zone model of YM.
1.11 Radionuclides Transport (RT)
During the last period, work began on two manuscripts for submittal to a peer-reviewed journal. These manuscripts are based on information presented in two earlier reports:
Preliminary Alluvium Sorption Module for TPA 3.2-Letter Report (IM 1402-871-830) and Preliminary Fracture Sorption Module for TPA 3.2-Letter Report (IM 1402-871-810).
In addition, the staff began preparing work on a manuscript entitled Radionuclides Sorption at Yucca Mountain, Nevada-Demonstration of an Alternative Approach for Performance Assessment for the proceedings volume of the Materials Research Society Symposium on the Scientific Basis for Nuclear Waste Management XXII. This manuscript uses mechanistic sorption models and site-specific hydrochemical data to constrain Ko PDFs for PA abstractions and will be presented in Boston, Massachusetts, November 30-December 3,1998. The staff also began evaluation of data on ion exchange between aqueous solutions and the zeolite mineral clinoptilolite based on published literature and unpublished CNWRA results. The data will be used to generate thermodynamic models for describing and predicting ion exchange equilibria between groundwater and zeolitic tuffs.
CNWRA consultants concluded a literature review on geochemical controls on sorption of Tc, Np, Pu, I, Se, Am, and Ac. The review includes a spreadsheet summarizing sorption results from more than 50 articles and reports and Eh-pH diagrams for radionuclides speciation. A second literature review focused on identifying geochemical parameters likely to control colloid stability during transport. These parameters will be used to investigate the feasibility of developing abstractions of colloid transport suitable for PA. Well logs for water wells drilled in the vicinity of YM were received from the USGS offices in Carson City, Nevada. Information in these logs will be used to constrain alluvium mineralogy, depth to water, and perforated intervals, and to identify producing horizons.
During this period, the staff started radionuclides sorption laboratory analyses. To establish sorption for single mineral systems and to bring the laboratory on-line, U-adsorption on clinoptilolite experiments began using 500 ppb U, a pH range from 2.5 to 9.5, and a solid mass to solution volume ratio (M/V) of 2 g/L. Laboratory procedures for multi-mineral experiments were prepared.
CNWRA staff attended the DOE Workshop on Anthropogenic Analogues in Las Vegas, July 20-21,1998. The meeting covered the application of anthropogenic analogues at Hanford, INEEL, and the NTS to understand flow and transport at YM. Acre was particular emphasis on the UZ. The first day was concerned with Hanford and INEEL, while the second day dealt with the DOE colloids program and the discovery on the NTS of colloid-associated Pu migration from the BENHAM bomb test site, The CNWRA staff assisted the NRC staff in finalizing the RT IRSR. The CNWRA staff also developed input for the FY99 CNWRA OPS.
10
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l In the next period, literature reviews of key geochendcal parameters controlling colloid transport will progress. Well logs will be used to constrain alluvium mineralogy. Ion exchange data will be evaluated and a peer-reviewed paper on the subject will be initiated.
Preparation of peer-reviewed papers on the application of sorption modeling for PA calculations will continue. There will be continued laboratory analysis for the planned experimental program and muldple mineral experiments will begin. RT staff will assist the PA abstraction process.
1.12 Tank Waste Remediation System (TWRS)
Several items, including rescheduling of some milestones, were discussed with the NRC staffin a conference call on July 28,1998. Consistent with discussions with the NRC staff, the dates for the following four milestones have been changed:
Low Activity Waste Feed Makeup, Solidification, and Offgas Technology and Process System Hazard and Safety Issues Report for TWRS-Letter Report (IM 1403-102-832).The new date for submitting this milestone is January 29,1999.
The delay in submitting this report is attributed to diversion of resources to subtask 1.8.
Final Report on Chemistry of the DOE Contractor Retreatment Activities (IM 1403-106-815). The new date for submitting this milestone is December 28, 1998. The delay in submitting this report is attributed to unavailability of adequate resources to complete the task.
Consequence Criteria for the TWRS-Final Report (IM 1403-104-820). An AI will l
be subndtted to the NRC in August 1998 for their comments. The iinal report, i
incorporating the NRC comments, will be issued as an IM in FY99.
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I Low-Activity Waste Retrieval and Retreatment Technology and Process System
+
and Safety for TWRS-Letter Report (IM 1403-102-831). This report will be issued as an AI instead of an IM. The IM, incorporating the NRC comments, will be combined with Final Repor; on Chemistry of the DOE Contractor Retreatment Activities (IM 1403-106-815).
In the meantime, progress occurred on the following subtasks.
In subtask 1.2, changed pages, incorporating the NRC staff comments on the final report, Survey of Solidification Process Technologies Final Report (IM 1403-102-810), were sent l
to the NRC. The Low-Activity Waste Auxiliary Support Equipment and Process Control Technology System Hazard and Safety Issues Ret ort for'IWRS-Letter Report (IM 1403-102-833) has undergone internal review and was delivered as scheduled on August 7. In I
addition, the stiff is working at a slightly reduced level of activity on the Low-Activity l
Retrieval and Retreatment Technology and Process System liazard and Safety Issues l
1 Report for TWRS (IM 1403-102-831) and the Low-Activity Waste Feed Makeup, l
Solidification, and Offgas Technology and Process System Hazard and Safety Issues Report f
for TWRS (IM 1403-102-832).
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In subtask 1.3, Comparison of Risk Assessment Techniques-Final Report (IM 1403-103-810) is undergoing technical review after incorporating the NRC comments. In suotask 1.4, the author-final version of the Consequence Criteria for the TWRS Repon (IM 1403-104-820) is ready for review.
In subtask 1.6 preparation moved forward on the Final Report on Chemistry of the DOE Contractor Retreatment Activities (IM 1403-106-815). Draft chapters on sludge washing, ion exchange, electrochemical ion exchange, and organic ozonation were received from subcontractors and SwRI staff.
In subtask 1.8, based on the NRC guidance for reviewing the DOE-RU Evaluation of the BNFL Initial Safety Analysis and Safety Requirements Document, a review team is currently responding to BNFL open issues in the DOE-RU evaluation report. Results of the review will be reported in Response to the BNFL Comments and Additional Information (IM 1403-108-860).
In the next period, activities in subtask 1.2 will continue on the Low-Activity Waste Feed i
Makeup, Solidification, and Offgas Technology and Process System liazard and Safety Issues Report for TWRS-Letter Report (IM 1403-102-832). The Low-Activity Waste Auxiliary Support Equipment and Process Control Technology System liazard and Safety Issues Report for TWRS-Letter Report (IM 1403-102-833) will be issued to the NRC for review. In subtasks 1.3 and 1.4, review of the Comparison of Risk Assessment Techniques (IM 1403-103-810) will be transmitted as an IM and the Consequence Criteria Report for the TWRS (IM 1403-l'M-820) as an AI. 'Ihe literature review for subtask 1.6 will continue on topics covered in the Final Report on Chemistry of the DOE Contractor Retreatment Activities (IM 1403-106-815). In subtask 1.8, review of the DOE-RU evaluation report for the BNFL will be completed and the draft report will be forwarded.
1.13 Three Mlle Island Unit 2 Independent Spent Fuel Storage Installation (TMI-2 ISFSI)
A final report titled Second Round RAI/ Outline of SER-Final Letter Report (TMI-2)
(IM 1405-014-830) documenting review and evaluation of the DOE response to the NRC first round RAI, second round RAI, and an outline of the SER that was submitted during period 10 were accepted. The draft SER, currently in preparation, will be documented as Safety Evaluation Report-Draft Letter Report (IM 1405-014-910).
In the next period, TMI-2 ISFSI staff plans to continue preparation of the draft SER while waiting for the DOE response to the NRC second round RAI.
1.14 Dry Transfer System (DTS)
A final report documenting the first round RAI was delivered as First Round Request for Additional Information-Final Letter Report (IM 1405-021-820) was accepted.
In the next period, DTS staff plans to prepare for the site visit at INEEL, which is scheduled the week of September 14,1998, while waiting for the DOE response to the NRC first round RAI.
1 12
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i 1.15 Centralized Interim Storage Facility (CISF)
Activity regarding the identificadon of technical issues specific to one or more of the cask designs proposed for use at the CISF continued during this reporting period. These issues will be documented in a report for delivery as Recommendations for Cask Specific Issues to be Investigated (IM 1405-031-830). Evaluation of the DOE response to the NRC first round RAI and preparation of the draft AR continued. This draft AR will be documented in a report for submission as Assessment Report-Draft Letter Report (IM 1405-031-840).
In the next period, CISF staff plans to identify cask-specific issues that may need to be investigated by the NRC, review and evaluate the DOE response to the NRC first round RAI, and prepare the draft AR.
1.16 Private Fuel Storage Facility (PFSF)
The PFS Limited Liability Company response to the NRC first round RAI was reviewed and evaluated. Preparation of the second round RAI continued.
In the next period, PFSF staff plans to continue review and evaluation of the PFS Limited j
Liability Company response to the NRC first round RAI and preparation of the second round of RAI for submission as Second Round Request for Additional Information-Final Letter Report (IM 1405 441-820).
l 1.17 Savannah River Site Aluminum liased Spent Fuel (SRSASF) l A meeting was held with the DOE, Savannah River Site, and the NRC staffs in which the CNWRA and the NRC comments related to disposal of Al-clad fuels were discussed. B ased on the discussion, several issues were resolved and a path toward resolving other issues was identified. The DOE stated their preferred option for the disposition of Al-based fuel will be the melt and dilute technology, and therefore will send appropriate technical reports for review by the NRC and the CNWRA.
In the next period, no significant activity is anticipated since the DOE is conducting various studies associated with the melt and dilute option and is in the process of identifying appropriate documents for review.
2 MANAGEMENT ISSUES None to report.
3 MAJOR PROBLEMS None to report.
l 4
SUMMARY
OF SCIIEDULE CIIANGES I
l Schedule changes for IMs are included in tabic 2. Completed deliverables are noted on table 3 and in the Executive Summary.
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5
SUMMARY
OF FINANCIAL STATUS Table 4 summarizes the CNWRA financial status in the context of authorized funds provided by the NRC. Total commitments of the CNWR A are $ 195,193. 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 y
l cumulative basis. These data do not include commitments. Pertinent financial information is provided for the DWM JC, including COPS and 10 KTis, TWRS JC, TMI-2 ISFSI JC, DTS JC, CISF JC, PFSF JC, and S RS ASF JC. The planned costs per period are based on the spending plans contained in the CNWRA OPS, Revision 10, Change 2, for the DWM JC; TWRS OPS, Revision 1, Change 1, for the TWRS JC, SFPO OPS, Revision 1, Change 5, for the TMI-2 ISFSI, DTS, CISF, and PFSF JCs; and SRSASF OPS, Revision 0, Change 2, for the SRSASF JC.
It should be noted the current spending estimates in all J Cs are based on the assumption that staffing is at authorized levels. Staffing remains below authorized levels and accelerated recruitment is in progress. An updated staffing plan was delivered as part of Revision 6, Change 3, to the CNWRA Management Plan.
Period 11 FY98 CNWRA composite expenditures rose 8.4 percent from last period and this aggregate of all JCs was underspent by $1,042,363 or 11.0 percent. The DWM, TWRS, TMI-2 ISFSI, PFSF, and SRSASF JCs evidenced higher spending levels, while the DTS and CISF JCs showed lower levels. In percentages, the TWRS JC registered a sharp rise in expenses in contrast with a decline in expenditures for the DTS and CISF JCs. Specific explanations for these swings are provided in the individual sections of each JC.
The DWM JC was underspent by $855,242 or 10.7 percent. Overall expenditures increased 3.1 percent from the previous period as costs rose in COPS and the SDS, CLST, TEF, TSPAI, ARDR, and RT KTis, but declined in the IA, ENFE, RDTME, and USFIC KTIs.
We TWRS JC was overspent by $8,399 or - 1.2 percent. Expenditures increased 11.9 percent over last period. This rise is the result of incorporating the NRC conunents into various reports, working on a number of reports concurrently, and meeting subcontractor conunitments in subtask 1.6.
The TMI-2 ISFSI JC was underspent by $53,444 or 38.5 percent. Costs rose from last period as a result of the staff preparing a draft SER letter report.
The DTS JC was underspent by $60,145 or 34.3 percent. Spending declined 22.1 percent despite delivery of First Round Request for Additional Information-Final Letter Report.
The CISF JC was underspent by $36,230 or 19.1 percent. Expenses declined from the previous period as the result of reduced spending associated with the continued identification of technical issues specific to one or more of the cask designs proposed for CISF use and evaluation of the DOE response to the NRC first round RAI for incorporation into a draft AR.
He PFSF JC was underspent by $16,214 or 13.9 percent. Expenditures rose over last period even as the cumulative varW.ce widened. The review and evaluation of the PFS Limite'l Liability Company resIv% to the NRC first round RAI continued along with the preparation of the second rouno KAI.
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The SRS ASF JC was underspent by $29,487 or 31.9 percent. Spending increased considerably over
. last period as a result of staff participation in a meeting with the DOE, Savannah River Site, and the NRC staffs.
The CNWRA expenditures on SwRI labor, consultants, and subcontractors as a proportion of composite spending on all JCs was 25.0 percent. He CNWRA expense on consultants and subcontractors as a fraction of composite spending on all JCs was 19.1 percent. Rese percentages increased from the previous period. The CNWRA remains committed to enhance, where appropriate, participation of consultants and subcontractors in the conduct of the CNWRA work.
As shown in table 1, the CNWRA has 48 core and one limited-term staff members. The CNWRA updated the staffing plan portion of the Management Plan, reflected in table 1. The available pool of approved consultants and subcontractors expanded to 52.
This FYTD no capital or sensitive equipment was purchased with NRC funds (other than overhead, general and admin'strative expenses, and fees).
DWh1JC l
The DWM JC cumulative cost variance through period 11 was U / percent. Expenditures in this JC increased by 3.1 percent over the previous period. Specific explanations for over/ underspending for COPS and each KTI follow.
De cost variance for COPS was 6.4 percent: 5.5 percent for the Management, Planning, and Computer Support subtask (1402-158) and 10.1 percent for the QA subtask (1402-159). Spending in the 158 subtask rose relative to last period but declined in the 159 subtask. Expenses in the Management, Planning, and Computer Support and QA subtasks are expected to remain near estimated levels for the next period.
The cost variance for the IA KTI was - 6.7 percent. Spending is anticipated to increase in the next several periods because of planned field investigations and use of consultants, The cost variance for the SDS KTI was - 14.8 percent. This reflects an expansion in work to meet the KTI augmented scope and budget.
The cost variance for the ENFE KTI was 16.9 percent. This represents a variance increase both in percentages and cumulative dollars. Future variances are anticipated to decrease during period 12
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as existing commitments are realized.
I ne cost variance for the CLST KTI was 8.6 percent. he positive cost variance continued to increase because of vacations taken by some staff members. It is expected to decline in the next period with augmentation of activities related to IRSR revision and corrosion testing of Alloy C-22.
f The cost variance for the TEF KTI was 19.4 percent. This variance may decline contingent on hiring new staff.
De cost variance for the RDTME KTI was 13.3 percent-lower than that of the previous period.
This variance may be reduced further as additional non-CNWRA staff and newly hired staff work on KTI activities.
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i De cost variance for the TSPAI KTI was 15.1 percent. De variance may remain about the same, since the spending rate is expected to remain roughly constant during period 12.
I The cost variance for the ARDR KTI was 52.0 percent. Tius percentage variance is similar to the variance for last period, although it continues to increase. A decrease in the 10 CFR Part 63 development work is expected in the next period while the draft rule begins the NRC internal review. Also, there is presently no indication the EPA standard will be released for review in the coming months. Therefore, increased efforts to recommend options for additional tasking will be pursued in the next period.
The cost variance for the USFIC KTI was 11.3 percent, slightly higher than the 11.0 percent variance during the previous period. Reductions in variance are anticipated in coming periods as existing commitments are posted to this account.
The cost variance for the RT KTI for this period was 12.3 percent compared to 20.0 percent in period 10. This variance continues the decline begun in period 5. This variance is expected to continue declining in coming periods as consultant costs are posted.
The cost variance for the TWRS project was - 1.2 percent. The substantial increase in spending in period 11 results from meeting subcontractor commitments in subtask 1.6. It is anticipated the spending rate will be reduced in the next two periods and will track the Ludgeted spending as some of the milestones are extended into FY99.
The cost variance for the TMI-2 ISFSI project was 38.5 percent. This cost underrun will decrease as the CNWRA receives the DOE response to the NRC second round RAI, as resources are allocated for preparing the draft SER, and as core staff to be used on this project are acquired.
The cost variance for the DTS project was 34.3 percent, slightly lower than that of the previous period. During the next two periods, however, the cost underrun will increase until the CNWRA receives the DOE response to the NRC first round RAI.
The cost variance for the CISF project was 19.1 percent-lower than that of the previous period.
His cost underrun will decline further dependent on continuing the activities and hiring new staff that will also support this project.
De cost variance for the PFSF project was 13.9 percent. Despite a variance increase from the previous period, this cost underrun will diminish as the CNWRA reviews and evaluates the PFS Limited Liability Company response to the first round RAI and employs staff to support this and other activities.
De cost variance for the SRS ASF was 31.9 percent. Notwithstanding an increase from the previous period, spending is expected to remain flat as a result of lack of further tasking.
16
Table 1. CNWRA Core Staff-Current Profile and Iliring Plan * (Period 11)
ExpertiseExperience Current Na.
Profcul, mal Staff Pewillems Open FY98 ADMINISTRATION 4
Il GAR (1 A. W PATRICK. J Rt'SSEIL B S AG AR Cl!1'MICAL PROCESSNO 2
VJ AIN, D DARUW AILA ENONG /PifYS. Ci!EM.
CODE ANAI.YSIS/DEVr!DPMENT 1
RJANT*I7KE. R MARTIV J B ANGS 1
DATA MANAGEMENT / PROCESSING, 1
P.MAIDONADO INCIUDING T1NANCI AI.
j DOSF/ RISK /IIAZARD ANAL.YSIS 0
1 ELECTROCIIl%11STRY I
G CR AGNO!INO ENGINEERING 2
R.Cl!EN, O.OICEGBU GEO!DGYKEOIDOICAI. ENGNG ENVIRONMENTAL SCIENCES 1
P.IaPt.ANTP GEOCIIEMISTRY 5
W.MURPilY, R.PABA1AN, E.PEARCY, LPRIKRYI, D TI'RNTR GEOllYDROIDGY/ITYDROGEOIOGY 4
R FEDORS. R GREFN J %1NTERIE, D FARRI'll.
I GEOIDGY 2(1)t I_McKAGlTL M MIKI.AS Pl.ATEMINAt IlYDROIDGIC11t ANSPORT i
A ARMSTRONG. S PAINTER. D litfGIISON O
INFORMATION MANAGEMENT 1
R. KUTARA SYSTTStS M ATERIAI. SCENCES 3
D.DUNN, N SRIDilAR. 5 BROSSIA 1
MECIIANICAI, 0
1 INC1UDING DESIGN & FABRICATION MINING ENGINEERING I
S-M llSilfNG 1
NtICIEAR ENGINEERING 1
M J AR7EMB A OPER ATIONAL IIEAI.111 PETYSICS 2
J %TI.DY,I.DEERE PI RIURMANCE ASSPSSMEVr 2
S MOH AN'IY, G WTITMEYFR 2
OUAIJrY ASSUR ANCE I
B M ABRITO l
R ADIGISOTOPE GEOCIIEMISTRY l
D I1CKf7T ROCK MEC11ANICS, 2
A.CIIOWDIiURY, A.GilOSII INCI.ITDING CIVIT/STRtrC. ENONG sot rRCE 1TRM/SPPNr ilTL DFOR AD 0
1 STRUCTURALGEOIDOY/
3 D.fERRIII, J.STAMATAKOS, D.SIMS SE!SMO TDCTONICS SYSTEMS ENGINEERING 1
P.MACKIN VolfANOIDOY/IONEOUS 2
C.CONNOk, B.1[III PROCESS ES 1DTA!,
4RII)t 7
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4 Table 4. Financial Status (Period 11)
Funds Funds Funds Project Names A uthorlied Costed to Date Ifacated Commitments COPS 1.626.360 1.287.820 til 540 0767 IA 619 186 591.471 67 711 21.679 SDS 784 910 778 047 6 883 6 041 FNTE 922.779 646 814 275065 68 887 CIST 719.948 525,640 189 908 7.601 Tfy 716 729 491.697 24% 072 6.5 t 3 R[YTME 481 820 114.712 140 098 1000 TSPA[
1.738 058 1 206.507 511.551 2.600 ARDR 461756 172.561 291.195 0
ifSFIC 1.111 197 818.176 295.221 10 028 RT 477 466 311 226 144 240 18.563 DWM Costs 9 682 018 7.146 652 2.535 186 DWM Award Fee 561.865 260511 301.334 DWM Base Fee 175 010 277,705 98 205 TOT AI. DWM 10 621 812 7 684 888 2.916 924 174 680 1TRS Costs 821 901 695.950 125.991 20511 1WRS Award Fee 47.641 22.741 24 902 TWRS Base Fee 11.762 27 114 4 627 T(YTAT.TWRS 901,305 745825 155.480 20.511 TMI-2 tSF5f S AR Costs 157.704 85.169 72.519 0
TMI-2 ISf31 S AR Award Fee 9.191 5.585 3 606 1MI-2 ISFSI Base Fee 6.I27 3.291 2 837 TOTAI.TMI-2 iSIST S AR 173.021 44 04I 78.981 0
DTS Costs 102.277 I I 5.066 77.211 0
TYl'S Award Fee 11 175 7.774 1 401 DTS Base Fee 7 451 4 441 1.010 TOTAI.DTS 210.901 127.281 83.622 0
CfSF Cmts 228.022 151 050 74.972 0
CISF Award Fee 13145 6 201 1.042 CISF Base Fee 8 831 5.898 2 912 TOT AI.CISP 250 098 165 152 84 946 0
PIMF Cmts 142 880 100 156 42.724 0
PI5F Award Fee 8 110 1.512 4 798 ITSF Base Fee 5 540 1864 1.676 TOTAI. PFSF 156.710 107.532 40.198 0
Wt/DP Cmts 34 495 34.266 229 0
WVDP Award Fee 2.287 1896 391 WVDP Base Fee
! 311 1 111 0
T(7 TAT.WVDP 18.112 17.492 620 0
SR S ASF rosts 108 826 62.891 45935 0
SRS ASF Award Fee 6.140 1.151 2.989 SRS ASF Base Fee 4.227 2.414 1791 1UTAI. SRS ASP 119.191 68 675 50 718 0
Orand Total 12 471.176 9 030 886 1 440 490 104191 Note: All authortred funds have been allocated.
20 1
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