ML20236S274

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CNWRA Program Manager'S Periodic Rept on Activities,For Fiscal Reporting Period 980606-0703
ML20236S274
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 06/16/1998
From:
CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES
To:
NRC
Shared Package
ML20236S250 List:
References
CON-FIN-D-1035, CON-FIN-J-5164, CON-FIN-J-5186, CON-FIN-J-5190, CON-FIN-J-5206, CON-FIN-J-5210, CON-FIN-J-5226, CON-NRC-02-97-009, CON-NRC-2-97-9, REF-WM-11 HLWR, PMPR-98-10, NUDOCS 9807240235
Download: ML20236S274 (41)


Text

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CNWRA PROGRAM MANAGER'S PERIODIC REPORT ON ACTIVITIES OF THE CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES For the Fiscal Reporting Period June 6,1998 - July 3,1998 l 1

PMPR No. 98-10 4

i July 16,1998 i

9807240235 980716

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TABLE OF CONTENTS Section .

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TABLES..........................................................................iv AB B REV IATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v EXECUTIVE

SUMMARY

-PERIOD 10 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xi 1

TEC H NIC AL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 1.1 CNWRA Operations (COPS) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . I 1.2 Igneous Activity (I A) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1.3 Structural Defonnation and Seismicity (SDS) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 1.4 Evolution of the Near-Field Environment (ENFE) . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 1.5 Container Life and Source Term (CLST) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 1.6

'Ihermal Effects on Flow (TEF) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 1.7 Repository Design and 'Ihermal-Mechanical Effects (RDTME) . . . . . . . . . . . . . . . . . 7 1.8 Total System Performance Assessment and Integration (TSPAI) . . . . . . . . . . . . . . . . . 9 1.9 Activities Related to Development of the NRC High-Level Waste Regulations ( ARDR) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 1.10 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC) . . . . . . . . . . 11

. 1.11 Radionuclides Transport (RT) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 1.12 Tank Waste Remediation Systems (TWRS) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 1.13 'Ihree Mile Island Unit 2 Independent Spent Fuel Storage Installation (TMI-2 ISFSI) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 1.14 Dry Transfer System (DTS) . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 1.15 . Centralized Interim Storage Facility (CISF) ............................... 14 1.16- Private Fuel Storage Facility (PFSF) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 1.17 West Valley Demonstration Project (WVDP) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 1.18 Savannah River Site Aluminum-Based Spent Fuel (SRSASF) . . . . . . . . . . . . . . . . . . . - 15 2 ' M ANAGEMENT ISSUES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 3 MAJOR PROBLEMS ...................... ................................ 15 4

SUMMARY

OF SCHEDULE CHANGES . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . 15 5

SUMMARY

OF FINANCIAL STATUS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15

. APPENDIX -Planned and Actual Costs, and Cost Variances Period 10-FY98 i

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- Table 1 CNWRA Core Staff--Current Proille and Hiring Plan * (Period 10) . . . . . . . . . . . . . . . . . . 19 Sununary of Schedule Changes (Period 10) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 l 2

3- Deliverables (Period 10) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 4 Financial Status (Period 10) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22 5 Private Fuel Storage Facility License Fee Cost Recovery Status (Period 10) . . . . . . . . . . . . . 23

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ABBREVIATIONS 1D , , One-Dimensional . CEC Comunission of the European 2D Two-Dimensional Communities 3D hree-Dimensional . CFD Computational Fluid Dynamics

'AA Atomic Absorption CFR Code ofFederalRegulation AAI Average AnnualInfiltration CIAC ComputerIncident Advisory Capability i ACD. Advanced Conceptual Design CISF Centralized laterim Storage Facility ACF Alumina (in excess of alkali feldspar), CLST Container Life and Source Term Calcium Oxide, Ferromagnesian Oxide CM Configuration Management ACNW Advisory Committee on Nuclear Waste CNWRA Center for Nuclear Waste Regulatory j

ACRS Advanced Computer Review System Analyses ADAMS . Agencywide Documents Access and COI Conflict ofInterest -

Management System COPS CNWRA Operations

.AECL Atomic Energy of Canada Limited CPP Cyclic Potentiodynamic Polarization AES. Atomic Emission Spectrometry CQAM CNWRA Quality Assurance Manual AGU American Geophysical Union CRO Center Review Group Al Admmistrative Item CRM Corrosion Allowance Material ALis l-Apache Leap Test Site CRWMS Civilian Radioactive Waste AML Areal Mass leading Management System ANS- Amancan Nuclear Society CSCS Constrained Stochastic Climate ANSI American National Standards Institute Simulator AO~ Annotated Outline CSH Calcium Silicate Hydrate AP Adnunistrative Procedure -CSPE Corrosion Science and Pmcess APB Acid-Producing Bacteria Engmeerms AR Assessment Report DAS Data Acquisition System ARDR Activities Related to Development of DBE Design Basis Event the NRC High-level Waste Regulations DC Division of Contracts

ASCE American Society of Civil Engineers DCAA Defense Contract Audit Agency ASCII American Standard Code for DCB Double Cantilever Beam InformationInterchange DCF Dose Conversion Factor ASME ' American Societyof Mechanical DCM DualContinuum Model Engineers D&D Decommissioning and Decontamination ASTM American Society for Testing and DECOVAIIX Development of Coupled Models and Materials heir Validation Against Experiments ASU Arizona State University in Nuclear WasteIsolation ATD'13 Automated Technical Data Tracking DEls Draft Environmental Impact Statement System DEM Digital Elevation Model BEG Bureau of Economic Geology DF Dilation Factor BFD Basis for Design DFCSS Division of Fuel Cycle Safety and BM- Bare Mountain Safeguards BMF Bare Mountain Fault DIE Determination ofImportance BNFL ' British Nuclear Fuels Limited Evaluation BTP - Branch Technical Position DIMNS Division ofIndustrial and Medical CAI Color Alteration Index Nuclear Safety I

' LCAM ' Corrosion Resist Material DKM Dual Permeability Model CAR- Corrective Action Request DID Digital Line Graph CCDF Complementary Cumulative DLM Diffuse I.ayer Model

- Distribution Function . DNAG Decade of North American Geology CCL ' Commitment Controlleg DNFSB Defense Nuclear Facilities Safety Board l CCM- l Constant Capacitance Model DOE U.S. Department of Energy

[: CD-R ' CDROM Recordable DOE-DP DOE Defense Program l 'CDF Cumulative Distribution Function DOE-RU U.S. Department of Energy Regulatory l' .CDM' _ ' Complianue Determination Method . Unit CDOCS Consolidated Document Manageirant DRA Division of Regulatory Applications System DST Drift Scale Test CDROM' Compact Disk Read Only Memory DTED DigitalTerrain Elevation Data CDS Compliance Determination Strategy D13 Dry TYansfer System

' CIyrs Commission Decision Tracking System DWM Division of Waste Management

'CEB- Center for Environmental Biotechnology EBS Engineered Barrier System V

I ABBREVIATIONS (cont'd)

EBSER Engineered Barrier System GTFE Great Tolbachik Fissure' Eruption' Experim v tal Research GUI Graphics User Interface EBSPAC Engineerca Barrier System GWSI Groundwater System Integration l

Performance Assessment Code GWTT Groundwater TravelTune ECM Equivalent Continuum Model HLUR High-Level Waste and Uranium EDO Office of the Executive Director for Recovery Projects Branch Operations HLW High-Level Waste EDX Energy-Dispersive X-Ray Spectroscopy HRTEM High-Resolution Transmission Electron EIS EnvironmentalImpact Statement Microscopy EM Element Manager IA Igneous Activity EMPA Electron MicroProbe Analysis IBM International Business Machines ENE East-Northeast ICP Inductively Coupled Plasma ENFE Evolution of the Near-Field ICPP Idaho Chemical Processing Plant Environment IDLH 1mmediately Dangerous to Life and ENGB Engineering and Geosciences Branch Health EnPA Energy Policy Act of 1992 IHLRWMC International High-level Radioactive ENS Eumpean Nuclear Society Waste Management Conference and EPA U.S. Environmental Protection Agency Exposition EPR Electrochemical Potentiokinetic IM Intermediate Milestone Reactivation IME Industrial Mobilization Exemption EPRI Electric Power Research Institute IMS Information Management Systems EQA External Quality Assurance INEEL Idaho National Engineering and EROS Earth Resource Observation System Environmental Laboratory ESF Exploratory Studies Facility INETER Instituto Nicaraguense de Estudios ESP Environmental Simulation Program TERritoriales EW East-West INTRAVAL International Code Validation EXAFS Extended X-Ray Absorption Fine I/O Input / Output Structure IPA Iterative Performance Assessment FAC Favorable Condition IR&D Internal Research & Development FCRG Format and Conterd O w.. tory Guide IRIS Interim Records Information System FDSHA Fault Displacement' * ' e smic Hazard

. IRM Office ofInformation Resources Analysis Management FEHM Finite Element He a Mass Transfer IRSR Issue Resolution Status Report FEM Finite Element Mew ISA Initial Safety Analysis FEP Features, Events, and Procest es ISFSI Independent Spent Fuel Storage FFRDC Federally Funded Research and Installation Development Center ISM Integrated Site Model FFT Fast Fourier Transform IVM Interactive Volume Modeling FTE Full-Time Equivalent IWPE Integrated Waste Package Experiments FTP File Transfer Protocol JC Job Code FY Fiscal Year JPL Jet Propulsion Laboratory FYTD Fiscal Year-to-Date JRC Joint Roughness Coefficient GDF Ghost Dance Fault K"U Key TechnicalIssue GEM General Electrochemical Migration KTU Key Technical Uncertainty GEOTRAP Geologic Transport of Radionuclides LA License Application Predictions LAAO License Application Annotated Outline GERT General Employee Radiological LAN local Area Network Training LANL los Alamos NationalLaboratory GET General Employee Training LARP License Application Review Plan GFM Geological Framework Model LAW low-Activity Waste GHGC GeoHydrology and Geochemistry LBNL lawrence Berkeley National Laboratory j GIA Generalized Importance Analysis LBT large Block Test i GIS Geographic Information System LHS latin Hypercube Sampling j GLGP Geology and Geophysics llTC lockheed Information Technology i GPS Global Positioning Satellite Company )

GROA Geologic Repository Operations Area LLNL Lawrence Livermore National i GS Geologic Setting Laboratory GSA Geologic Society of America 11W low-Level Waste vi l 1

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ABBREVIATIONS (cont'd)

LMAES lockheed Martin Advanced PAHT Performance Assessment and Environmental Systems Hydrologic Transport LSS Ucensing Support System PASP l Performance Assessment Strategic Plan ISSPP Ucensing Support System Pilot Project PC Personal Compute::

LSSTB Licensing Support System Test Bed PCflEP Personal Computerfrransmission LWR Light Water Reactor Control Protocol Ma Million Years Ago PDF Probability Distribution Function MC Monte Carlo PDR Public Document Room METRA Mass and Energy Transport PEL Permissible Exposure Limit MGDS Mined Geologic Disposal System PEM Program Element Manager MH Mechanical-Hydrological PER Relicensing Evaluation Report MIC Microbially influenced Corrosion PFD Probabilistic Fault Displacement MINC Multiple Interacting Continua PFDHA Probabilistic Fault Displacement MIT Massachusetts Institute of Technology Hazard MM Major Milestone PFS Private Fuel Storage MO Management and Operations PFSF Private Fuel Storage Facility MOU Memorandum of Understanding PHA Preliminary Hazard Analysis MPC Multi-Purpore Canister PI PrincipalInvestigator MRS Monitored Retrievable Storage PMDA Program Management, Policy MSS MultiSpectral Scanner Development and Analysis Staff MTU Metric Ton of Uranium PMPR Program Manager's Periodic NAS National Academy of Sciences Report NAWG Natural Analogue Working Gmup PMT Photo-Multiplier hbe NCR NonConformance Report PNNL Pacific Northwest National Laboratory NEA Nuclear Energy Agency PO Project Officer NFS Network File Server PPA Proposed Program Approach NIOSH NationalInstitutes of Safety and Health PPE Prepassivated Platinum Electrode NIR Near-Infrared PRA Probabilistic Risk Assessment NIST NationalInstitute of Standards and PRT Peer Review Team Technology PSAG Probabilistic System Assessment Group NMSS Office of Nuclear Material Safety and PSHA Probabilistic Seismic Hazard Analyses Safeguards PTFE Polytetrafluoroethylene NNE North-Northeast IFTn Paintbmsh Nonwelded Tuff NNW North-Northwest PVHA Probabilistic Volcanic Hazards NOAA National Oceanographic and Assessment Atmospheric Administration PVHVIEW Probability of Volcanic Hazards NRC Nuclear Regulatory Commission VIEW NS North-South PVM Parallel Virtual Machine NSRRC Nuclear Safety Research Review PWR Pressurized Water Reactor Committee QA Quality Assurance NTS Nevada Test Site QAP Quality Assurance Procedure NUREG NRC Technical Report Designation QRAM QualityRequirements Application NWPA Nuclear Waste Policy Act, as amended Matrix NWTRB Nuclear Waste Technical Review Board RAI Request for Additional OBES Office of Basic Energy Sciences Information OCRWM Office of Civilian Radioactive Waste RASA Regional Aquifer System Management Analysis OGC Office of General Counsel RDCO Repository Design, Construction, OITS Open-Item Tracking System and Operations OMB Office of Management and Dudget RDTME Repository Design and Thermal.

OPS Operations Plans Mechanical Effects ORR Operations Readiness Review REE Rare Earth Element ORS Overall Review Strategy REECO Reynolds Electrical and Enginecting OWFN One White Flint North Company,Inc, j PA Performance Assessment RES Office of Nuclear Regulatory Research PAAG Performance Assessment Advisory RFP Request for Proposal Group RH Relative Humidity PAC Potentially Adverse Condition RIP Repository Integration Program Vii l

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ABBREVIATIONS (cont'd) f

! ROC Repository Operations Criteria SUFLAT Stochastic Analyses of Unsaturated RPD Regulatory Program Database Flow And Transport RRT Regulatory Requirement Topic SVF Springerville Volcanic Field RSRG Real Space Renormalization SwRI Southwest Research Institute Group SZ Saturated Zone RT Radionuclides Transport TA Technical Assistance RTS Radwaste Treatment System TBD To Be Determined SAP Standards Approval Package TBM Tunnel Boring Machine SAR Safety Analysis Report TCP/IP Transmission Control SCA Site Characterization Analysis Protocol /Intemet Protocol SCC Substantially Complete TDI Technical DocumentIndex Containment TDOCS Technical Document Reference SCCEX Substantially Complete Database System Containment Example TEF Thermal Effects on Flow SCE Standard Calomel Electrode TEM Transmission Electron Microscopy SCFF Southern Crater Flat Fault THC Thermal-Hydrologic-Chemical SCM Surface Complexation Models THMC %ernal-Hydrologic-SCP Site Characterization Plan Mechanical-Chemical SDMP Site Decommissioning T-L Transverse-Longitudinal Management Plan TLM Triple-Layer Model SDS Structural Deformation and TM Thermal-Mechanical Seismicity TMH Thermal-Mechanical-Hydrologic SECY Secretary of the Commission, Office of TMI-2 nree Mile Island Unit 2 the (NRC) TMS The Minerals, Metals, and Materials SELM Spectral Element Metbod Society SEM Scanning Electron Microscopy TOP Technical Operating Procedure SER Safety Evaluation Report TP Technical Position SF Spent Fuel TPA Total-system Performance Assessment SFPO Spent Fuel Project Office TPI Time Period of Regulatory SFVF San Francisco Volcanic Field Interest SGI Silicon Graphics Inc. TR2 DOE Seismic Topical Report No. 2 SGML Standard Generalized Markup TRG Technical Review Group Language TSAR Topical Safety Analysis Report SHE Standard Hydrogen Electrode TSPA Total System Performance SHT Single Heater Test Assessment SIP Scientific Investigation Plan TSPAI Total System Performance SKI Swedish Nuclear Power Inspectorate Assessment and Integration S-L Short Transverse-Longitudinal TSw-Chnv Topopah Spring Welded-Calico SLAR Side Looking Airborne Radar Hills Nomitric SNF Spent Nuclear Fuel TVD Total Variation Diminishing SNL Sandia National Laboratories TWFN Two White Flint North SOTEC Source Term Code TWINS Tank Waste Information SOW Statement of Work Network System SPCR Software Problem Correction Report TWRS Tank Waste Remediation System SRA Systematic Regulatory Analysis UA Universityof Arizona SRB Sulfate-Reducing Bucteria UACH Universidad Aut6nomade SRBS Shafts, Ramps, Boreholes, and Their Chihuahua Seals UCLA University of California-los SRD Software Requirements Angeles Description UDEC Universal Distinct Element Code SRS Savannah River Site UK United Kingdom SRSASF Savannah River Site Aluminum- UNM University of New Mexico Based Spent Fuel UR Uranium Recovery SS Stainless Stee! U.S. United States STEM Scanning Transmission Electron USDA U.S. Depastment of Agriculture Microscopy USGS U.S. Geologic Survey STP Staff Technical Position UTM Universal Transverse Mercator viii

ABBREVIATIONS'(cont'd)

' USFIC.' ... Unsaturated and Saturated Flow Under Isothermal Conditions UZ- Unsaturated Zone VA Viability Assessment VCS . Version Control System -

.VF . Vitrification Facility

~ VSIP ' Vertical Slice Implementation Plan-WAN Wide Area Network

, WAPDEO . Waste Package Degradation

- WBS Work Breakdown Structure WCIS .' Waste Containment and Isolation Strategy .

. WPO ' Wodt for Others WOB - Western Great Basin x WIPP ' Waste isolation Pilot Plant.

WMB Waste Management Branch WNYNSC Western New York Nuclear .

Service Center -

WOL . Wedge-Opening leading WP- Waste Package WSEI~ -Weste Systems Engineerms and lategration WSRC . Westinghouse Savannah River .

Company WSS Waste Solidification Systems WTSO > Washington TechnicalSuppon Office WVDP - WestValley Demonstration Project .

WVNS~ West Valley Nuclear Services WWW World Wide Web cXPS X-ray Photoelectron

. Spectroscopy XRD' X-ray Diffractometry

YM Yucca Mountain

.YMP Yucca Mountain Project YMSCO ~ . Yucca Mountain Site Character zaten.

. Office :

YMR Yucca Mountain Region

.YTD Year-to-Date J

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EXECUTIVE

SUMMARY

-PERIOD 10 In the Division of Waste Management (DWM) Job Code (JC), the Center for Nuclear Waste Regulatory l Analyses (CNWRA) continued work on numerous analyses and revisions to issue resolution status reports (IRSRs). In addition, staff delivered CNWRA Quality Assurance Manual Change, Evaluation of Seismic

Energy with Depth-Journal Article,3DStress Modifications-CNWRA User's Guide (Version 1.3), and l;

!'  ; Alkaline Water-Rock Interactions at the Magarin Site-Journal Paper. Moreover, they submitted the following letter reports: (1) Input to Container Life and Source Term IRSR, Rev.1-Letter Report, (ii) Input to Repository Design and 'Ihermal-Mechanical Effects IRSR, Rev.1-Letter Report, (iii) User's Guide for

' IPA Version 3.1.4-Letter Report, and (iv) Preliminary Alluvium Sorption Module for ' IPA 3.2-Letter

. Report. A paper documenting laboratory-scale beating and refluxing test results and analyses, Penetration of the Bolling Isotherm by Flow Down a Fracture, was presented at the 'Ihird International Conference on

- Multiphase Flow in Lyon, France, June 8-12,1998. A report entitled Importance Measures for Nuclear Waste Repositories was submitted. 'Ihe technical lead for the Structural Deformation and Seismicity Key Technical Issue participated in a staff exchange at NRC headquarters.

'Ihe DWM JC year-to-date (YTD) cost variance was 11.6 percent. Although the cumulative variance l increased in dollars since the previous month, this variance decreased on a percentage basis as work l l

accelerated in several areas.

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! In the Tank Waste Remediation System (TWRS) JC, the YTD cost variance was 8.2 percent. This variance fell from last period as a result of increased expenditures associated with incorporating NRC comments into L j two final reports. Costs are anticipated to increase substantially as subcontractor work is completed argi  !

commitments are paid.

t In the Three Mile Island Unit 2 (TMI-2) Independent Spent Fuel Storage Installation (ISFSI) JC, a report entitled Second Round RAI/ Outline of the' Safety Evaluation Report (SER)-Final Letter Report was transmitted along with an outline of the SER. The YTD cost variance for the TMI-2 ISFSI was 38.6 percent-notwithstanding higher spending related to the delivery of these products.

I' In- the Dry 'IYansfer ' System (DTS) JC, the staff delivered First Round Request for Additional Information-Draft Letter Report. The YTD cost variance for the DTS was 34.9 percent, down from last period on a percentage basis.

L In the Centralized Interim Storage Facility (CISF) JC, the staff identifled technical issues specific to one or j more of the cask designs proposed for CISF use and evaluated the DOE response to the NRC first round l Request for Additional Information (RAI) for incorporation into a draft assessment report. The YTD cost L variance for the CISF was 23.2 percent. This variance decreased substantially as a result ofincreased activity

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in this area. '

In the Private Fuel Storage Facility (PFSF) JC, the CNWRA staff reviewed and evaluated the PFS Limited I Liability Company response to the NRC first round RAI and prepared the second round RAI. 'Ihe YTD cost L variance for the PFSF increased to 12.3 percent as spending decreased substantially over last period.

In the West Valley Demonstration Project JC, no activity was recorded during this period. This is the last '

period for reporting under this contract. A new contract began under the Industrial Mobilization Exemption.

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EXECUTIVE

SUMMARY

-PERIOD 10 In the Savannah River Site Aluminum-Based Spent Fuel (SRSASF) JC, the staff submitted the report,

- Review of the Technical Issues Related to Interim Storage and Permanent Disposal of Al-based Spent Nuclear Fuel. T1,e YTD cost variance for the SRSASF JC was 28.2 percent. The variance increased this period because minimal work was associated with transmitting this deliverable, which was largely completed in previous periods.

It should be noted that the current spending estimates in all JCs are based on the assumption that staffing is at authorized levels. Cunent staffing remains below authorized levels and reen11tment continues.

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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, J5154, J5186, J5206, 35190, 35226, J5210 i

NRC CNWRA PROGRAM M ANAGER: John J. Linehan, (301) 415-7780 NRC CNWRA DEPUTY PROGRAM MANAGER: Deborah A. DeMarco, (301) 415-7804 CNWRA PRESIDENT: WesleyC. Patrick,(210)S22-5158 ESTIMATED HUDGET: $87,611,477 PERIOD OF PERFORM ANCE: 09/27/97-09/27/02 PERIOD OF THIS REPORT: 06/06/98-07/03/98 i TECIINICAL 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) conducting an NRC/CNWRA Management Meeting in San Antonio. Texas; (11) clarifying information on CNWRA carryover monies; (iii) delivering a Sununary of COPS Activities Required to Maintain and Operate the CNWRA along with the Explanatory Notes on COPS Trend Analysis; (iv) engaging in the DWM budget-related deliberations with the HLW Management Board; (v) addressing further COI-related issues among NRC, SwRI, and CNWRA management staffs; and (vi) participating in weekly HLW Management Board meetings.

Status of CNWRA staffing is indicated in table 1, consistent with the revised staffing plan submitted as part of the revision to the CNWRA Management Plan. During period 10, recruitment efforts and interviews continued for the approved open positions. Dr. Scott L.

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Painter joined the GHGC staff as a research scientist. One new staff member will begin workin the next period.

Computer system support activities encompassed (i) developing specifications for

) upgrading hardware and software associated with the GIS and IMS computing facilities, (ii) implementing a strategy for standardization of desktop computing operating systems, 1

(iii) pursuing a replacement for the CNWRA-developed CDOCS software, (iv) participating in the monthly NRC/CNWRA Computer Coordination meeting, and (v) maintaining LAN l operations.

' QA activities focused on (i) preparing for and engaging in the CNWRA QA annual audit, which was observed by an NRC representative (June 23-26); (11) conducting surveillance, issuing nonconformance notices as required, and working with cognizant staffin response to these notices; (iii) leading the configuration control effort of the CNWRA scientific and -

engineering software determined ready for release; (iv) controlling issued documents and maintaining QA records; (v) working to prevent organizational COls by review of SwRI  ;

RFPs; (vi) performing QA verificadon checks on each CNWRA deliverable; and l (vil) transmitting CNWRA Quality Assurance Manual Change (IM 1402-159-810).

In the next period, the CNWRA staffexpects to (i) participate in NRC/CNWRA discussions concerning development of guidance for OPS development; (ii) pursue hiring for open core staff positions; (ill) review computer requirements for GIS and IMS computing facilities as well as search for a replacement for the CDOCS software; and (iv) provide CNWRA LAN operation and maintenance support. In addition, the staff will (i) 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. i 1.2 Igneous Activity (IA)

The size of the subsurface conduit that feeds a basaltic volcano is an important parameter in modeling the dose consequences of possible IA at the proposed repository site. Previous studies evaluated conduit dimensions by calculating the volume of subsurface rock .l fragments entrained and dispersed during volcanic eruptions in Kamchatka and the YMR. i These studies indicate a cylindrical conduit may reach 30-60 m in diameter during late- ]

stage disruption events. This period, staff conducted technical investigations in the San l Rafael volcanic field, Utah, to provide additional data on subsurface geometries of basaltic volcanoes like those in the YMR. Conduits and associated dikes for 3-4 Ma basaltic volcanoes are exposed in the San Rafael area around 1 km below the paleosurface. Some of these conduits show evidence of relatively large-scale subsurface disruption during later stages of activity, i

Dikes around San Rafael conduits occasionally widen to 2-3 m without appreciable fragmentation of the surrounding wall rock. These widened areas likely represent zones of g vertical magma flow and may have fed cinder cones or small satellite vents. Some dikes that were examined in this period, however, trend into conduits with measured diameters 10 m to >60 m. Although most examined conduits are roughly ellipticalin cross-sectional shape, several conduits form fissures 10-20-m wide and 200-300-m long. Most of the larger

, conduits examined have fragmented the surrounding wall rock extensively. Conduit interiors contain irregularly defined zones where wall-rmk fragments constitute 40-60 vol % of the conduit. Rock fragments are entrained from the exposed subsurface horizon and from sedimentary units at least 200 m below the exposed horizon. 'Ihese conduit 2

characteristics are consistent with those interpreted from ground-surface data at YMR and analog volcanoes.

An initial interpretation of the San Rafael field data is that volcano conduit diameters of 10-50' m, which is the parameter range currently used in PA calculations, may underestimate by tens of meters the upper value of diameter of a basaltic volcano conduit at 300-m depths. Data from several analog sites will be evaluated in selecting a range or distribution of conduit sizes to be considered in future PA calculations. In addition to the detailed maps of San Rafael conduits, ground-magnetic surveys were conducted over several dikes and conduit areas. %ese data will provide additional information on the subsurface extent of the conduit and dike systems. About 400 rock samples also were collected from conduits and nearby dikes for anisotropy of magnetic susceptibility studies.

Ecse studies will examine the magnetic fabric of the rocks to determine magma flow directions, which will be used to evaluate how far from the conduit wall-rock fragments can-be entrained by the ascending magma system (an indicator ofpotential disruption of HLW).

His period, IA staff also met with Dr. Tim Dixon (University of Miami, Florida) and colleagues to discuss possible collaborative investigations using high-resolution GPS.

Dese investigations would be used to resolve uncertainties on partitioning between short-term crustal strain rates and long-term volcanic and seismic hazard rates. Dr. Dixon gave a detailed review of GPS methods used to derive short-term crustal strain rates and discussed the uncertainties associated with these measurements. A new opportunity arose to integrate Dr. Dixon's ongoing GPS-strain rate investigations in the Owen's Valley area with planned IA-SDS FY99 investigations in the nearby Volcanic Tablelands and Big Pine volcanic field. Integrating Dr. Dixon's GPS network into proposed activities will provide a crucial linkage between planned geologicalinvestigations and sbort-term strain rates. he integrated investigation can address strain partitioning across multiple temporal and spatial scales: (1) short-term strain since 1992 using GPS, (ii) 100-yr seismic record for the area, (iii) mesoscale and microscale deformation on the Volcanic Tablelands, (iv) balanced cross sections for long-term deformation of the 760-ka Bishop tuff on the Volcanic Tablelands, and (v) 1 m.y. of basaltic volcanic activity and contemporaneous faulting in the Big Pine volcanic field. These investigations will provide a solid technical basis to evaluate the proposed relationships between short-term crustal strain rates and long-term volcanic and seismic hazard rates at YM and elsewhere.

~ he staff completed a technical review on the journal article, Volcanic Hazards at the Proposed Yucca Mountain, Nevada, High-Level Radioactive Waste Repository I: Geologic Factors Controlling Patterns of Small-Volume Basaltic Volcanism (IM 1402-461-850).

Moreover, they continued to work on the companion journal article, Volcardc Hazards at the Proposed Yucca Mountain, Nevada, High-Level Radioactive Waste Repository II:

Probabilistic Analysis (also IM 1402-461-850), and on Subsurface Area of Disruption for i Basaltic Volcanoes-Journal Article (IM 1402-461-860). I In the next period, staff will continue to work on Probability Models for Yucca Mountain l

' Region-Journal Article (IM 1402-461-850) and on Subsurface Area of Disruption for Basaltic Volcanoes-Journal Article (IM.1402-461-860). Staff will meet with consultants

. to develop advanced thermo- fluid-dynamic models of HLW entrainment and dispersion in i basaltic volcanic eruptions and to better evaluate health effects associated with basaltic i

1

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l- I l, .C

tephra-fall deposits. Staff also will prepare for an appendix 7 meeting with the DOE on Disruptive Scenarios.

1.3 Structural Deformation and Seismicity (SDS)

Staff delivered 3DStress Modifications-CNWRA User's Guide (Version 1.3)

.(IM 1402-472-890). In addition to code modifications that improve utility and ease of operation, this revision of 3DStress incorporates several new technical features. These features include (i) Mohr Circle diagram capabilities, which allow the user to visualize the effects of stress and fluid pressure on both isotropic and faulted or fractured rocks; and

~ (11) fault leakage calculations, which calculate the effect of the natural competition between fault or fracture tensile strength and dilation of a fault or fracture from pore fluid pressures.

In addition, the manuscript entitled Constant %ickness Deformation Above Curved Normal Faults (IM 5708-471-733) has been revised, incorporating comments by the NRC and the CNWRA staffs, as well as by peer reviewers for the Journal of Structural Geology. The reviews of Evaluation of Seismic Energy with Depth-Journal Anicle (IM 1402-471-840) were completed and the manuscript was submitted.

A CNWRA staff member participated in a NRC/CNWRA staff exchange. The exchange proved to be mutually beneficial. Major activities of the exchange included detailed discussion about the SDS IRSR, Rev.1, and a series of technical presentations and follow.

= up discussions with the NRC staff on the role faults and fractures play as conduits or barriers to groundwater flow.

Staff initiated review of the DOE GFM 3D site model, which was constructed using the EARTHVISION software. De review is a cooperative effort between CNWRA and the NRC staff. Staff also began a detailed review of the DOE probabilistic seismic and fault displacement hazard analyses. These hazard analyses provide input to performance assessment models that calculate the effects of seismicity on repository performance and to preclosure design considerations.

Staff participated injoint SDS and USFIC field investigations of the YMR. These field investigations used differential GPS measurements and concomitant field work to delineate '

details about fractures and faults that influence infiltration. Additional oriented samples from faults in and above the ESF were also collected for SDS studies of fault zone deformation mechanisms. The results of the deformation studies support PA evaluations of the potential for faults to act as either barriers or conduits to flow.

Staff also participated in the FY98 CNWRA Q A audit. No items required corrective action.

'In ths next period, staff will continue reviews of the DOE GFM 3D site model and probabilistic seismic and fault displacement hazard analyses report. Staff will also initiate work for upcoming deliverables on fractures (IM 1402-471-861 and IM 1402-471-862),

Crater Plat tectonics (IM 1402-471-832), and update the GIS archive (IM 1402-471-850).

4 i

m.m._.

t 1.4 Evoludon of the Near Field Environment (ENFE)

Alkaline Water-Rock Interactions at the Magarin Sito-Journal Paper (IM 1402 561-850) was conveyed this period.

"Ihc staff forwarded an abstract titled Yucca Mountain Performance Assessment Sensitivity Study Using a Release Rate Based on Natural Analog Data from Pefia Blanca, prepared in collaboradon with the NRC staf f, for the Materials Research Society Symposium on the Scientific Basis for Nuclear Waste Management XXII scheduled for Boston, Massachusetts, November 30-December 3,1998.

The staff attended an ACNW meeting on the near-field environment and EBS performance on June 10-11,1998, at NRC headquarters. A plenary presentation was given on the near-lield environment, a talk was presented on near-field modeling, and contributions to the panel discussion were made by the CNWRA staff. Other staff attended the meeting via videoconference.

Source term solubility computadons continued to examine a suite of possible near-field solution chemistries and solubility controlling phases.

~

Rock samples from an altered zone near Paiute Mesa on the NTS were prepared and shipped for preparation of thin sections.

The CNWRA and the NRC staffs continued to collaborate on the ENFE IRSR.

Additionally, a CNWRA consultant tecimically reviewed the draft ENFE IRSR.

The LLNL Near-Field / Altered-Zone Models Report was received and internal review begun.

Progress continued on testing and debugging the MULTIFLO code Version 1.2 as well as compledng the user's manual. The MINC implementation in the code does not work properly, so corrections are in progress. A draft update of the user's manual describing the DCM and MINC options in the METPA module was completed. 'this manual will be completed to satisfy the deliverable Expanded Independent Coupled Process Modeling Capability, M ULTIFLO-Letter Report (IM 1402-561 -810). Progress was hindered by loss 1 of key staff. New staff was hired, following an international search, to continue development of the MULTIFLO code, in the next period, the CNWRA staff will attend an organizational meeting in Salt Lake City, Utah, for the Materials Research Society Symposium on the Scientific Basis for Nuclear Waste Management XXII scheduled for Boston. Massachusetts, November ,

30-December 3,1998. The CNW'RA staff will referee abstracts submitted to the I symposium on cc4nentitious materials, natural analogs, waste form chemistry, and other subjects. Collaborative work with a consultant on actinide chemistry will be conducted.

Review will continue on the LLNL Near-Field / Altered-Zone Models Report. Near field radioelement solubility modeling will advance. New stalf will continue familiarization with the MULTIFLO code. I 1

F l

1

1.5 Container Life and Source Term (CLST) i The staff transmitted the report, Input to Container Life and Source Term IRSR, Rev.1-Letter Report (IM 1402-571-820), and it was accepted programmadcally. The NRC staff technical comments continued to be addressed through individual telephone exchanges. Revisions to the IRSR arising from these discussions will be incorporated by -

the NRC prior to transmitting the final version of the IRSR, Rev. I to the DOE.

'Ihe staff continued electrochemical corros!on testing to confirm the applicability of repassivation and corrosion potentials as predictive parameters for the long-term, localized corrosion of Alloy 825 in chloride-containing solutions for a total test time of 1,420 days.

'Ihe open circuit potential, measured for 1,015 days, varied between 280 and 305 mV vs. .

SCE during the last 28 days of testing. 'Ihe staff observed no localized corrosion on specimens maintained below the repassivation potential.

Confirmatory testing of Alloy C-22 stress corrosion cracking susceptibility was delayed to allow additional machining of the test specimens. The side groves of several specimens are being corrected and knife edges added to allow use of a clip gage to measure the extension of the specimen during fatigue precracking and loading.

Work continued on the test equipment that will be used to perform localized corrosion tesdng of Alloys 625 and C-22 at temperatures above 95 *C. Placement of the various electrodes and probes in the autoclaves was determined and fabricadon of the platinum counter electrodes completed. Fabrication of high temperature reference electmdes was completed and calibration of the electrodes initiated.

'Ihe staffinvestigated the interdependence of solution chemistry, temperature, and potential on localized corrosion of carbon steel in simulated repository environments. Based on work thus far, no systematic dependence of the extent or type of corrosion (pitting or general -

corrosion) on soludon chemistry or temperature has been observed on boldly exposed samples. It is thought this is related to the poorly protective nature of passive film on iron in comparison to that on stainless steels and Ni-base alloys together with the stochastic nature of pit initiadon. A clearer dependence on the carbonate / chloride concentradon ratio and temperature was observed during crevice corrosion tests, as crevice corrosion is easier to initiate than pitting corrosion because of the mass transport restriction offered by the crevice former. Equipment for the long-term tests to further examine the conditions leading to stable localized corrosion is still arriving and laboratory modifications are continuing.

'Ihe report, Effects of Environmental Factors on Container Life-Letter Report (IM 1402-571-860), is currently in the CNWRA internal review process.

Effects ofEnvironmental Factors on Container Life-Letter Report (IM 1402-571-860) will be transmitted next period. Long-term corrosion tests of Alloy 825 will continue and localized carmslon testing of carbon steel and Alloys 625 and C-22 will begin.

Staff participated in the FY98 annual QA Audit. No corrective action;, directly related to this area were identified.

6

1.6 Thermal Effects on Flow (TEF) he staff continued preliminary testing of the DCM capabilityin the MULTIFLO code. %e importance and relevance of the fracture / matrix transfer term are being investigated.

Preliminary testing primarily focused on ID models although 2D models are also being tested.

A paper documenting laboratory-scale heating and refluxing test results and analyses, titled Penetration of the Boiling Isotherm by Flow Down a Fracture, was presented at the Third International Conference on Multiphase Flow in Lyon, France, on June 8-12,1998. This paper has been submitted for consideration for publication in a special issue of the i international Journal ofAfultiphase Flow.  ;

The second phase of the boiling isotherm depression heater experiment was initiated during this reporting period. Some cement blocks were coated with a sealant to impede imbibition

^of water and several candidate scalants are being evaluated. The sorptivity of the original cement blocks was measured and compared with that of the sealed blocks. A factor of 10 to 100 reduction in sorptivity was observed in those cement blocks coated with a sealant, It is anticipated the sealed blocks will act more like a fractured porous medium than the L original blocks, which responded similarly to a single continuum despite the presence of l simulated fractures.

t Revision 1 of TEF IRSR is undergoing CNWRA internal reviews and will be transmitted as Input to Bermal Effects on Flow IRSR, Rev.1-Letter Report (IM 1402-661-810).

l The staff continued the numerical modeling of the DOE LBT, DST, and drift-scale repository thermal tests. %e DST model is being transformed from an ECM to a DCM formulation. De ability of the DCM formulation in the MULTIFLO code will be tested during this modeling exercise.

L An analytical model to describe heat conduction, two-phase flow, and gravity-ddven .

fracture film flow is being modified. De potential to use a boundary integral method to calculate heat flow in the rock matrix adjacent to a fracture is being evaluated. De resulting numerical / analytical model will assess the refluxing' phenomenon for u-nonisothermal conditions, his analytical model will be documented in a report for j' submission as Mechanistic Reflux Model-Journal Paper or Presentation (IM 1402-661-l 840).

In the next period, 'IEF KTI staff plans to (1) continue the boiling isotherm penetration laboratory-scale experiment; (ii) proceed with refinement of the LBT, DST, and drift-scale repository numerical models; (III) maintain testing of the MULTIFLO-DCM numerical code; (iv) evaluate conceptual models of refluxing; and (v) complete Input to Thermal Effects on Flow IRSR, Rev.1-Letter Report (IM 1402-661 810).

'1.7 Repository Design and Thermal-Mechanical Effects (RDTME)

Preparation of the RDTME IRSR developedjointly by the NRC and the CNWRA RDTME KTI staff members was completed during this reporting period. %is IRSR was transmitted 1

7 i

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as Input to Repository Design and Thermal-Mechanical Effects IRSR, Rev.1-Letter

. Report (IM 1402-671-810).

This period, UDEC analysis to predict rockfall under seismicload 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. De feature included in the UDEC code is not sufficient to generate reasonable joint distributions using available joint pattern information collected from the ESF. An existing mesh generation code is being modified to provide suitablejoint distribution information for UDEC to construct a more representative model for the rockfall study. The same program is being used to investigate rock block size distribution.

De staff continued investigating drift-scale rock mass behavior and its effect on concrete lining stability under high temperature using the AB AQUS code. The AB AQUS model will include all components necessary for studying concrete liner behavior. Model development is near completion. De rock mass properties corresponding to rock categories 1 and 5 were developed for use in the ABAQUS analyses. Initially, rock mass behavior of openings without liner support will be analyzed. This will be followed by the analysis of lined openings to obtain a better understanding of how liners function as supports.

De investigation of drift-scale rock mass behavior and its effect on concrete lining stability using UDEC progressed during this reporting period. The mesh generation program for producing input for constructing the UDEC model for the rockfall study is being used in this study as well. Re side and bottom boundaries to be used for UDEC models have been determined considering the thermal effects for 300 yr. De change in temperature at the ground surface resulting from thermal loading is being studied using UDEC so that appropriate boundary conditions can be established for the ground surface. This study considers surface air convection. The outcome of these investigations should provide valuable insight in developing acceptance criteria for review of the DOE LA regarding underground facility design.

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 under high temperature. Preparation began on an interim progress report to document these literature review results.

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 p:rformance under high temperature, (iii) analysis of repository-scale rock mass behavior during elevated temperature, and (iv) simulation of rockfall under seismic load to provide input to the SEISMO code.

Staff participated in the FY98 annual QA Audit. One CAR was issued in this area.

In the next period, RDTME KTI staff plans to (i) review the literature collected on concrete performance of high temperature, (ii) investigate rock mass behavior under heated conditions on both repository and drift scales with an emphasis on long-term degradation 8

l of rock mas material properties and strengths, (iii) conduct rockfall simulations, and l ,

, - (iv) conduct ? .;U cc :;tivities including review of design documents.

1.8 Total System Performance Assessment and Integration (TSPAI)

After undergoing numerous formal as well as informal technical, editorial, and programmade reviews, the User's Guide for TPA Version 3.1.4-Letter Report (IM 1402-762-800) was transmitted. The user's guide was delivered in three-hole binder format to facilitate the incorporation of change pages for User's Guide for TPA Version 3.2-Letter Report (IM 1402-762-810), which will be submitted September 30,1998.

Verification testing of the ' IPA Beta Version 3.2 code continued during period 10.

Submission of the TPA Version 3.2 code on July 17,1998 will fulfill, in part, User's Guide l for TPA Version 3.2-Letter Report (IM 1402-762-810). )

i A draft plan for conducting a formal external review of the TPA Version 3.2 code was conveyed. This draft plan will be revised to address comments received from the NRC staff i

and subsequently re-submitted.

Technical work on the sensitivity studies using the TPA Version 3.1.4 code has been summarized in a draft report. This draft report was transmitted to KTI team leads at the NRC and the CNWRA for informal technical review. The final results will be reported in ]

Volume II of Input to TPA Version 3.1 Sensitivity Studier Report-Letter Report (IM 1402-761-810). Volume I of this report addresses the model abstractions and basecase data used in the TPA Version 3.1.4 code and includes selected chapters from the User's Guide for 1PA Version 3.1.4 -

l A report entitled Importance Measures for Nuclear Waste Repositories was transmitted June 26,1998. In depth discussions on the suitability of GIA for quantitative assessment s of repository subsystems are ongoing.

Efforts continue on (i) a PC version of the TPA Version 3.2 code, (ii) a Java-based post processor for the 1PA Version 3.2 code, and (iii) a PVM implementation of the TPA Version 3.2 code.

The staff revised the draft version of the TSPAI IRSR section on scenario analysis to address informal review comments from the NRC and CNWRA staffs. Revisions began on the TSPAI IRSR section on model abstraction. Input to Total System Performance Assessment IRSR, Rev.1-Letter Report (IM 1402-761-800) will be delivered August 14, 1998.

Staff participated in the FY98 annual QA Audit. No corrective actions directly related to ithis area were identified.

.J In the next period, the PA staff will focus on (1) completing the first volume of Input to

TPA Version 3.1 Sensitivity Studies Report-Letter Report (IM 1402-761-810);

(11) flnalizing the second volume of the Input to TPA Version 3.1 Sensitivity Studies j

l Report-Letter Report (IM 1402-761-810), which reflects actual results of the sensitivity i study;-(111) revising the Input to Total System Performance Assessment IRSR, )

l 9

Rev.1-Letter Report (IM 1402-761-800); (iv) continuing the development of a plan for external review of TPA Versi an 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.

L 1.9 ' ActivitiesRelatedtoDevelopmentof theNRCHigh-LevelWasteRegulations(ARDR) i Effon began to evaluate assumptions of well characteristics and plume dimensions on dose estimates needed to support development of attributes of the critical group used in 10 CFR Part 63. The purpose of this task is to develop more realistic methods for modeling the complex hydrogeology of the site regarding determination of radionuclides concentradons at pumping wells for both residential and agricultural receptor locations. The modeling approach incorporates spatiafly variable material properties, complex initial and boundary conditions, and multiple pumping wells with variable pumping rates. This period, staff focused on obtaining and reviewing literature on hydrologic properties of tuff and geostatistical methods.

Revisions to the DCF tables in the previously issued report, Information and Analyses to Support Selection of Critical Groups and Reference Biospheres for Yucca Mountain Exposure Scenarios (CNWRA 97-009), were started but not finished owing to other DWM commitments; however, the revisions should be completed in the next period. 'Ihe revised report is expected to be issued as a NUREO/CR and will be a key reference document for the rulemaking effort and TSPAI activities.

'Ihe CNWRA staff particip ated in review of the revised draft of 10 CFR Part 63 (following incorporation of HLW Management Board and staff comments). Additional effort this period involved completing the CNWRA input to the draft statements of consideration for the reference biosphere and critical group requirements in the draft rule. The EPA Standard for YM has not been publicly issued, therefore, the review was put on hold pending public release of the standard.

A final report on the sensitivity of peak dose with respect to several intermediate outputs using the TPA code is ready to be finalized but was not completed this period because emphasis was placed on higher priority work on the system level sensitivity analysis for ~

TPA Version 3.1.4. Calculations contained in the sensitivity of peak dose report are expected to provide technical insight useful in developing the revised NRC HLW rule. A final letter report for this deliverable will be prepared following completion of the higher priority work.

In the next period, the staff will assist the NRC in reviewing and revising sections of the draft NRC HLW mie so it can be finalized for branch chief review. If EPA publishes the draft standard, staff will assist the NRC with reviewing the draft standard and preparing comments. The dilution study will begin geostatistical modeling to determine spatial correlations in geohydrologic data identified in the literature search. Revisions to the CNWRA 97-009 report resulting from changes to the internal dose factors used in GENII-S modeling will be completed. Pr eparation will continue on the final report on the sensitivity analysis of peak dose with intennediate calculations in the TPA code pending completion of higher priority HLW tasks.

10

e 1.10 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC)

His period, plans were finalized for a staff exchange with the NRC. A CNWRA staff

' member primarily will support work in the USFIC KTI.

He staff initiated laboratory measurements on samples of colluvium collected during recent field work at YM. These measurements will include particle size distribution, bulk density, hydraulic conductivity, and retention curves.

Close interactions with the NRC staff continued during this period to support development of the USFIC IRSR.

Interpretations of transient electromagnetic sounding data progressed. During earlier periods, data were collected from 21 transient electromagnetic soundings, mainly on an N-trending line from southern Amargosa Valley into Fortymile Wash. It appears the data may -

show more geological variation than simply depth to the water table. The deep soundings appear to have responded to the bedrock-alluvium interface. Additional processing of the data is planned.

Gravity data collected during prior USFIC field work in the YMR continued to be evaluated. Data were collected on three gravity lines in Amargosa Valley to provide input for further developmen' of the 3D SZ model. These gravity data will be used to model geologic structure and depth to basement in Fortymile Wash. During this period, GPS data from the surveys were processed to enable corrections to the gravity measurements to be applied.

Activities continued on independent interpretation of C-well hydraulic and tracer tests.

These included literature review and coordination with the NRC site representatives (to obtain additional data from the DOE),

.An abstract entitled Time Scales for Dissolution of Calcite Fracture Fillings and

. Implications for Saturated Zone Radionuclides Transport at Yucca Mountain, Nevada, was prepared forthe Materials Research Society Symposium on the Scientific Basis for Nuclear Waste Management XXII scheduled for Boston, Massachusetts, November 30-December 3,1998. This abstract describes an analysis performed in cooperation with RT staff to estimate time scales for dissolution of. calcite fracture fillings in the YM SZ where groundwater are chemically undersaturated with respect to calcite. Results reported in this abstract suggest it is possible for calcite fracture fillings to persist over geologic time scales in aquifers where flowing water is undersaturated with calcite. Thus, the presence of calcite at YM does not necessarily indicate limited matrix diffusion.

Field work was conducted at YM in collaboration with SDS staff to analyze fractures in the L Tiva Canyon Tuff. Data collection involved mapping tectonic and cooling joints (using

' differential GPS) in the Upper Lithophysal Zone of the Tiva Canyon Tuff along Live Yucca Ridge and scan-line analyses in Split Wash and along Live Yucca Ridge. Sct.n-line analyses were conducted along the upper section of the north branch of Split Wash (one scan line) and along two narrow bedrock exposures on the south flank of Live Yucca Ridge (two parallel scan lines). Analyses of these data will be performed during future periods to provide input to watershed analysis and modeling of Split Wash.

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In the next period, activities will include (i) interaction with the NRC staff to finalize the USFIC 1RS R; (ii) continued development of a 3D, subregional site-scale flow and transport

]i model; (iii) interpretation of data from CNWRA field studies at YM; (iv) interpretauon of l C-Wells data; and (v) CNWRA USFIC staff exchange at the NRC.

1.11 Radionuclides Transport (RT)

Preliminary Alluvium Sorption Module for ' IPA 3.2-Letter Report (IM 1402-871-830) was transmitted in Period 10. His report includes a description of an approach using geochemical sorption models to develop response surfaces that define Np somtion behavior as a function of system geochemistry. De approach is demonstrated using site-specific hydrochemical information for the YMR. Change pages were also conveyed for the earlier report, Preliminary Fracture Sorption Module for TPA 3.2-Letter Report (IM 1402-871-L 810), correcting the sorption models that used an incorrect equilibrium constant (log K).

l De analyses were recalculated with the proper log K. 'Itc resuldng Np-montmorillonite sorption coefficients (Ko) values were slightly lower than those initially reported because of the stronger carbonate complexation of Np in the revised model.'

Site-specific hydrochemistry was combined with sorption models for Am, Np, Pu,3, and U to calculate sorption coefficient PDFs and correlation coefficients among the different radionuclides for input into TPA. PDFs were developed for each radionuclides for seven tuff units and the alluvial aquifer.

Activity continued using GIS coverages to study spatial variation in predicted radionuclides sorption coefficients bsed on ambient SZ water chemistry. Contour maps of U and Np sorption coefficients predicted with a surface complexation model were revised and combinedwithbothgeologicalmapcoveragesandshadedreliefimages. Aliteraturereview 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. Work also continues to constrain alluvium mineralogy through water well-log information. Laboratory analyses for radionuclides sorption on mineral mixtures were deferred during this period because of staff unavailability.

Two abstracts, Unsaturated Zone Waters from the Nopal I Natural Analog, Chihuahua, Mexico-implications for Radionuclides Mobility at Yucca Mountain and Radionuclides Sorption at Yucca Mountain, Nevada-Demonstration of an Alternative Approach for Performance Assessment, were submitted for presentation at the Materials Research Society

> Symposium on the Scientific Basis for Nuclear Waste Management XXII, Boston, Massachusetts, November 30-December 3,1998. De first presentation will focus on

' chemical and U-series isotopic data from perched and seep waters collected at the Nopal I analog site, with comparison to YM waters regarding U and Si phase solubility relationships and reaction paths. De second presentation involves using mechanistic sorption models and site-specific hydrochemical data to constrain Ko PDFs for PA abstractions.

De RT KTI was audited during the annual CNWRA QA audit held June 23-26,1998 in San Antonio, Texas. Members of the RT team worked with QA audit specialists to review 12

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adherence to CNWRA QA procedures. No corrective action requests directly related to this

, , KTI resulted from this audit.

In the next period, progress will ensue onliterature reviews of key geochemical parameters controlling sorption, colloid transport, and alluvium mineralogy. Laboratory analysis will resume for the planned experimental program. RT staff will help in the PA abstraction process.

1.12 Tank Waste Remediation System (TWRS)

Discussions are being held with the NRC staffregarding rescheduling some milestones. De new dates will be reflected in the next PMPR. In the meantime, work is continuing on the l following subtasks.

In subtask 1.2, the NRC staff conunents on the final report Survey of Solidification Process Technologies Final Report (IM 1403-102-810), have been incorporated and change pages sent for review. The author-final for the Low-Activity Waste Auxiliary Support Equipment ll and Process Control Technology System Hazard and Safety Issues Report for L TWRS-Letter Report (IM 1403-102-833) will be delivered as scheduled on August 7, i

1998. Staff worked on the Low-Activity Retrieval and Retreatment Technology and Process System Hazard and Safety Issues Report for TWRS (1403-102-831) and the Low-l Activity Waste Feed Makeup, Solidification, and Offgas Technology and Process System Hazard and Safety Issues Report for TWRS (1403-102-832).

De input to Comparison of Risk Assessment Techniques-Final Report (IM 1403-103-810) was received from the subcontractor under subtask 1.3 and sent for comments as an AI. The NRC staff comments have been received and will be incorporated into the draft final report. In subtask 1.4, preparation continued on the Consequence Criteria for the l TWRS Report (IM 1403-104-820).

In subtask 1.6, preparation continued on the Final Report on Chemistry of the DOE Contractor Retreatment Activities (IM 1403-106-815). With concurrence from the NRC '

f J

staff, delivery of this report was postponed to December 28,1998, from its current due date of August 26,1998. In the interim, 75 percent complete draft of the report will be submitted -

as an AIon October 26,1998.

In subtask 1.8, based en the NRC guidance for reviewing the DOE-RU Evaluation of the BNFL Initial Safety Analysis and Safety Requirements Document, a review team is being 1 assembled to respond to the DOE-RU evaluation. Results of the review will be reported in i response to the BNFL comments and additional information (IM 1403-108-830).

In the next period, activities will continue in subtask 1.2. Revisions to the Survey of Solidification Process Technologies Final Report (IM 1403-102-810) and change pages will be issued based on the NRC comments. Progress will be made in completing the LAW Feed

- Makeup, Solidification, and Offgas Treatment (IM 1403 102-832) and Low-Activity Waste

- Auxiliary Support Equipment and Process Control Technology System Hazard and Safety Issues Report for TWRS-Letter Report (IM 140.t102-833). Work will advance on the

- Consequence Criteria Report for the 'IWRS .(IM 1403-104-820). In subtask 1.6, the  ;

I:  ; literature review will continue on topics covered in the Final Report on Chemistry of the L

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g DOE Contractor Retreatment Activities (IM 1403-105-815). In subtask 1.8, the DOE-RU

}. evaluation report will be reviewed.

l 1.13 Three Mile 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 was submitted during this reporting period. Preparation of the draft SER has been initiated. Tids draft SER will be

- documented as Safety Evaluation Report-Draft Letter Report (IM 1405-014-910).

A formal report titled Seismic Ground Motion at Three Mile Island Unit 2 Independent Spent Fuel Storage Installation Site in Idaho Nadonal Engineering and Envirotunental Laboratory-Final Report has been published r.s CNWRA 98-007. The predecisional letter report version (IM 1405-002-810) of this document was submitted on December 11,1997.

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)

De safety review of the DTS TSAR, reinitiated during period 6, continued this reporting period. A draft report documenting the first round RAI was completed and delivered as First Round Request for Additional Information-Draft Letter Report (IM 1405-021-810).

In the next period, DTS staff plans to revise the draft version of the report on First Round RAI to resolve the NRC comments, if any. De revised version will be submitted as First Round Request for Additional Information-Final Letter Report (IM 1405-021-820).

1.15 Centralized Interim Storage Facility (CISF)

Activity regarding the identification of technical issues specific to one or more of the cask

' designs proposed for use at the CISF advanced during this reporting period. De specified 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 began during this period. 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) he review and evaluation of the PFS Limited Liability Company response to the NRC first round RAI continued. De preparation of the second round RAI was initiated.

14

4 In the next period PFSF staff plans to continue review and evaluation of the PFS Limited Liability Company response to the NRC first round RAI and preparation of the second I round of RAI for submission as Second Round Request for Additional Information-Final Letter Report (IM 1405-041-820) . f I

1.17 West Valley Demonstration Project (WVDP) .l Dere were no expenditures or activities this period. This is the last period for reporting on this project. A new contract was initiated pursuant to work under the Industdal {

1 Mobil 17ation Exemption.

1.18 Savannah River Site Aluminum-Based Spent Fuel (SRSASF)

De report, Review of the Technical Issues Related to Interim Storage and Permanent Disposal of Al-based Spent Nuclear Fuel (IM 1407-001-810), was transmitted. A meeting has been scheduled with the DOE during the next period to discuss the conclusions in the {

i report.

In the next period, the staff will participate in a videoconference meeting with the DOE to discuss the review of the report and obtain clarification, as necessary.

2 MANAGEMENTISSUES None to report.

3- MAJOR PROBLEMS None to report.

4

SUMMARY

OF SCHEDULE CHANGES Schedule changes for IMs are included in table 2. Completed deliverables are noted on table 3 and in the Executive Summary.

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 CNWRA are $263,363. 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. Dese 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, WVDP JC, and SRSASF JC. The planned costs per period are based on the i spending plans contained in the CNWRA OPS, Revision 10, Change 2, for the DWM JC; TWRS Operations Plan, Revision 1, Change 1, for the TWRS JC; SFPO Operations Plan, Revision 1,  ;

Change 5, for the TMI-2 ISFSI, DTS, CISF, and PFSF JCs; WVDP Operations Plan, Revision 8, j Change 1, for the WVDP JC (Closed); and SRSASF Operations Plan, Revision 0, Change 2, for the i i

SRSASFJC.

15 i

It should be noted the current spendmg estimates in all JCs are based on the assumption that staffing is at authorized levels. Staffing remains below authorized levels and accelerated recruitment is in progress. An updated staffing plan has been submitted as part of Revision 6, Change 3, to the CNWRA Management Plan.

Period 10 FY98 CNWRA composite expenditures rose 5.7 percent from last period and this aggregate of all JCs was underspent by $1,071,020 or 12.6 percent. The DWM, TWRS, TMI-2 ISFSI, and CISF JCs evidenced higher spending levels, while the DTS, PSF, and SRSASF JCs j showed lower levels. The WVDP was inactive this period. In percentage terms, the TMI-2 ISFSI and i CISF JCs registered sharp rises in expenses in contrast with a pronounced decline in expenditures for the SRSASF JC. Specific explanations for these swings are provided in the individual sections  ;

of each JC.

De DWM JC was underspent by $835,301 or 11.6 percent. Overall expenditures increased 5.1 percent from the previous period as costs rose in COPS and the IA, SDS, ENFE, RDTME, ARDR, and RT KTIs, but declined in the CLST. TEF, TSPAI, and USFIC KTIs.

De TWRS JC was underspent by $51,040 or 8.2 percent. Expenditures increased 10.8 percent over  !

last period. his rise is the result of incorporating the NRC comments into the Survey of Solidification Process Technologies Final Report and the Final Report on Chemistry of the DOE l Contractor Retreatment Activities, as well as submitting change pages, drafts, or both for these reports.

De TMI-2 ISFSI JC was underspent by $50,072 or 38.6 percent. Costs rose significantly from last period as a result of preparing and conveying Second Round RAI/ Outline of SER-Final Letter

< Report and preparing a draft SER letter report.

De DTS JC was underspent by $58,349 or 34.9 percent. Spending declined 53.1 percent despite '

delivery of First Round Request for Additional Information-Draft Letter Report. l l

De CISFJC was underspent by $39,562 or 23.2 percent. Expenses rose markedly from the previous  ;

period as the result of spending related to the continued identification of technical issues specific I 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.

De PFSF JC was underspent by $12,784 or 12.3 percent. Expenditures fell by 52.7 percent over last period because of reduced involvement in evaluation of the DOE responses to the NRC first round RAI and initiation of the second round RAI.

He WVDP JC was inactive this period. The project was closed and a new contract executed in accordance with the provisions of the IME.

' De SRSASF JC was underspent by $23,913 or 28.2 percent. Spending decreased considerably over last period notwithstanding delivery of Review of the Technical Issues Related to Interim Storage and Permanent Disposal of Al-based SNF.

De CNWRA expenditures on SwRIlabor, consultants, and subcontractors as a percentage of composite spending on all JCs was 19.4. De CNWRA expense on consultants and subcontractors as a fraction of composite spending on all JCs was 14.1 percent. These percentages increased from 16

__==

m.

l o

the previous period. The CNWRA remains committed to enhance, where appropriate, participadon 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 has updated the staffing plan portion of the Management Plan, which is reflected in table 1. De l available pool of approved consultants and subcontractors expanded to 51.

l i

This FYTD no capital or sensitive equipment was purchased with NRC funds (other than overhead,

. general and administrative expenses, and fees).

l

~DWMJC The DWM JC cumulative cost variance through period 10 was 11.6 percent. Expenditures in this

' JC increased by 5.1 percent over the previous period. Specific explanations for over/ underspending for COPS and each KTI follow.

The cost variance for COPS was 7.5 percent: 6.5 percent for the Management, Planning, and i

Computer Support subtask (1402-158) and 12.0 percent for the QA subtask (1402 159). Spending in the 158 and 159 subtasks rose relative to last period. Expenses in the Management, Planning, and Computer Support subtask are expected to remain near estimated levels for the next period and those associated with the QA subtask will be at a higher level because of writing the QA audit report by the Audit Team Leader, auditors, and technical specialists.

De cost variance for the IA KTI was - 2.6 percent. Spending is anticipated to increase in the next several periods owing to field investigations and planned use of consultants.

The cost variance for the SDS KTI was - 10.6 percent. This reflects an expansion in work to meet the KTI augmented scope and budget.

De cost variance for the ENFE KTI was 15.5 percent. This represents a variance decrease both in percentages and cumulative dollars. Future variances are andcipated to rise during period 11 and then fall again as existing commitments are realized.

The cost variance for the CLST KTI was 8.1 percent. De positive cost variance increased with respect to the last period because of vacation days taken by some staff members, but will decline in the next period with augmentation of activides in various tasks related to corrosion tesung.-

The cost variance for the TEF KTI was 18.3 percent. This variance may decline if new CNWRA staff are hired to work on this KTI.

De cost variance for the RDTME KTI was 14.8 percent-lower than that of the previous period.

His variance is anticipated to reduce further as additional non-CNWRA staff, including several summer student employees, continue to work on KTI activities.

The cost variance for the TSPAI KTI was 16.2 percent. The variance may remain about the same, since the spending rate is expected to remain roughly constant during period 11.

De cost variance for the ARDR KTI was 51.3 percent. This percentage variance is similar to the variance for last period, although it continues to increase in dollar terms. Expanded spending is 17

anticipated resulting from tasking a recently hired staff member with the new dilution analyses together with the continued effort from the CNWRA team to assist the NRC with revising the HLW rule. Furthermore, following HLW Management Board recommendations regarding 10 CFR Part 63, it is anticipated that additional tasking to support the definition of the critical group may be forthcoming.

De cost variance for the USFIC KTI was 11.0 percent. His decrease continues the trend of diminishing variances begun in period 9. Further reductions are anticipated in coming periods as existing commitments are posted to this account. '

The cost variance for the RT KTI was 20.0 percent. This variance continues the decline in percentage begun in period 5 and represents a reduction in cun .alative dollar variance from the previous period. This variance is expected to continue declining in coming periods as consultant costs are posted and as laboratory work resumes.

De cost variance for the TWRS project was 8.2 percent. The positive cost variance decreased slightly from the last period. It is anticipated that the spending rate will increase substantially in the next period as activities on other milestones continue and commitments are posted.

De cost variance for the TMI-2 ISFSI project was 38.6 percent. This cost underrun will decrease as the CNWRA receives the DOE response to the NRC second round RAI and resources are allocated for preparing the draft SER and by acquiring core staff to be used on this project.

De cost variance for the DTS project was 34.9 percent, lower than that of the previous period.

During the next few periods, however, the cost underrun will increase until the CNWRA receives the DOE response to the NRC first round RAI.

De cost variance for the CISF project was 23.2 percent-lower than that of the previous period.

His cost tmderrun will decrease further as the activities progress and the CNWRA hires staff that will also support this project.

The cost variance for the PFSF project was 12.3 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.

he WVDP project was inactive during this period.

He cost variance for the SRSASF.was 28.2 percent. The positive cost variance rose from the last period following completion of the main task in the project, but will abate somewhat as a result of

' interaction with the DOE.

18

1 I

! Table 1. CNWRA Core Staff-Current Profile and Iliring Plan * (Period 10)

\

l FxpertismExpwtence Current No. Professional Staff Postthms Open FY98 ADMINISTRATION 4 11 GARCIA. W. PATRICK. J.RUSSIIL B.S AGAR GIEMICAL PROCESSNO 2 VJAN D.DARUWAllA ENGNGJPHYS. CIIEM.

l CODE ANALYSIS /DfWEIDPMINT 1 RJANITI.KE. R. MARTIN. J B ANOS DATA MANAGEMENT /PROCESSNO, 1 PMAIDONADO INCLUDING FINANCIAL DOSF/ RISK 4(AZARD ANAI.YSIS 0 1

EIJ3CTROr1TPMISTRY 1 G CR AGNOIINO ENGINEERING 2 R.QlEN,0.Of00GBU GEOIDGYKiEGIDGICAL FNGNG.

ENVIRONMENTAL SCIENCES 1 P. tartan 111 OBOCHEMIS11tY 5 W. MURPHY, R.PABAIAN, EPEARCY, J.PRIKRYL D TURNER GEOTTYDROIDGY41YDROGEOIDGY 4 R.FEDORS. R GREEN. LWINIT?RIA DFARRF11 1 GEOIDGY 2(1)t LMcKAGUE. M MTKIAS. P.IAITIMNAt

. liYDROIDGIC11t ANSPORT 2 A ARMSTRONG. S PANTER 1 INIVRMAllON MANAGEMENT 1 R. KUTARA SYS1TMS MATERIAL SCIENCES 1 D DUNN, N.SRIDHAR. S.BROSSIA 1 i

MECHANICAI. 0 I

NCIUDNG DESIGN & FABRICATION MINNO ENGINEERING 1 S-M HSIUNG NUCtEAR ENGINEERING 1 MJARZEMBA OPERATIONAL HEAL 11I PIIYSICS 2 J WEIDY, LDFIRE PERFORMANCE ASSESSMENT 2 S.MO:IANTY, G.WTITMFYFR 2 QUAIITY ASSURANCE 1 B M ADRTFO RADIOtSUFOPE GEOCHEMISTRY 1 D PICKITT ROCKMECHANICS, 2 A.CIIOWDI!URY, A.GHOSH INCLUDING CfVII/STRUC. ENGNG.

SOURCE-17.RM/SPFNTIUEL DEGR AD. 1 P.IJCFrrNER STRUCTURALGEOIDGY/ 3 D.FURRIIL J.STAMATAKOS, D.SIMS sErSuO-1TerONICS SYSTEMS ENGINEERNG 1 P.MACKN l j

VOIIANOIDGYAGNEOUS 2 C.CONNOR, BJIILL PROCESSES numma TOTAL 48(1)t 1 l

l

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Table 4. Financial Status (Period 10) r d. r as r d.

Proiset Namees A.8hartsad Casted to Date t'neasted Caera-a-1,157.001 COPS 1.626.360 469.357 4.512 IA 619,186 478.535 140.651 23.746 SDS 784,930 692.091 92,839 10.558 ENFE 922,779 598.468 324.311 62,166 CtJT 115.548 464.681 250.867 8.415 113P 736,729 446.514 290,215 6,348 RIylMP 483.829 288.148 195,681 0 TSPAI 1,738.058 1.059.521 678,537 107 ARDR 463,756 150.166 313.590 0 USPlc 1,113,397 736.807 376,590 9,542 RT 477.466 265.643 211.823 67,800 DWM Costs 9.682.038 6,337,577 3.344.461 DWM Award Fee 563.865 260.511 303.334 DWM Base Fee 375.910 246,254 129.656 1DTAllWM 10.621,812 6.844.362 3,777.450 193.194 TWRS Costs 821,901 572.311 249.590 70.169 1WRS Award Fee 47.643 22,741 24.902 1TRS Base Fee 31.762 22.249 9,512

. TOTAL 1WRS -901.305 617.301 284,004 70.169 1MI 2 ISFS! S AR Costs 157,704 79.778 77,926 0 1MI-21SPSISAR Award'/ee 9.191 5.585 3.606 1MI-2 ISPSI Base Fee 6.121 3.080 3.047 1DTAL1MI-? 1SPSI S AR 173.023 88.443 84,579 0 DTS Costs 192.277 108.890 83,387 0 tyr5 Award Fee 11.175 1,774 3,401 DTS Base Fee 7.451 4.203 1.248 1Y.frAL DTS 210.903 120,866 90,037 0 CISP Ccuta 228.022 131,140 96.882 0 CISF Awr.d Fee 13.245 6,203 7.042 CISP Base Fee 8.831 5.054 3,777 1DTAL CISP 250.098 142,397 107,701 0 PFSF Ccuts 142.880 91,110 51.770 0 PPSF Award Fee 8.310 3.512 4.708 PPSP Base Fee 5.540 3.516 2,024 TUTAL PPSP 156,730 98.138 58.592 0 WVDP Ccuts 34.495 34.266_ 229 0 WVDP Award Fee - 2.287 1.896 391 WVDP Base Fee 1,331 1.331 0 1DTALWVDP 38.112 37.492 620 0 SRSASF Costs 108.826 60,846 47.980 0 SRSASF Award Fee 6,340 3.351 2,989 SRSASF Base Fee 4.227 2,355 1.872 1 URAL SRS ASP 119,393 66.552 52,841 0 denad Tcen! 12.471.376 8.015.551 4.455.825 263.363 Note: AE authorized funds have been allocated 22

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a APPENDIX Planned and Actual Costs, and Cost Variances Period 10-FY98 I

l

3, 9, 0 6 0 3 0 0 7 0 0 %0 6 0 0 %0 0 %0 0 0 0 1, C. 5, 3

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