A center of excellence in earth sciences and engineering

A Division of Southwest Research Institute 6220 Culebra Road • San Antonio, Texas, U.S.A. 78228-5166 (210) 522-5160 - Fax (210) 522-5155

November 5, 1999 Contract No. NRC-02-97-009 Account No. 20.01402.158

U.S. Nuclear Regulatory Commission Attn: Mr. John J. Linehan, Director Office of Nuclear Material Safety and Safeguards Program Management, Policy Development and Analysis Staff Mail Stop 8-A23 Washington, DC 20555

Subject: CNWRA Program Manager's Periodic Report on Activities of the Center for

Nuclear Waste Regulatory Analyses for Period 1-FY2000

Dear Mr. Linehan:

The enclosed "Program Manager's Periodic Report" (PMPR) documents the progress and financial status of

the Center for Nuclear Waste Regulatory Analyses for the period September 25-October 22, 1999. Its contents

comply with the requirements of section F. 1.5 of the referenced contract. A diskette containing the PMPR in

WordPerfect 8 format is also enclosed.

Cost variance analyses are provided for the Division of Waste Management (D1035), Tank Waste Remediation

System (J5164), Dry Transfer System (J5206), Centralized Interim Storage Facility (D1035), and Private Fuel

Storage Facility (J5226) Job Codes, as well as for composite spending on this contract. All variances are

expressed with regard to the operations plans for FY2000.

Note that External Quality Assurance, Public Outreach, and Development of the Yucca Mountain Review Plan

have been included for the first time in this reporting period. This follows the new work breakdown structure

implemented in FY2000.

The support documentation accompanying the vouchers for period I has changed. Southwest Research Institute

has introduced a new accounting and project management software, and the CNWRA has modified, manually,

the standard project cost reports to accommodate, as closely as possible, the traditional format of the previous

support documentation. This modification may continue for the first three fiscal periods of FY2000. You will

be kept informed relative to any changes in format for the support documentation.

S•i '• ~ Washington Office • Twinbrook Metro Plaza #210 12300 Twinbrook Parkway •Rockville, Maryland 20852-1606

C111161164>c(l0.-/ i1) V

U.S. Nuclear Regulatory Commission Attn: Mr. John J. Linehan, Director Page 2 November 5, 1999

During period 1, there were no changes to staff (tables I and 2). Seven milestones were added and one schedule change was recorded (table 3). Three deliverables were transmitted (table 4).

Please contact me or Mr. Henry Garcia if you have questions regarding this report.

Sincerely yours,

Wesley C. Patrick President

HFG/Ig Enclosures cc: B. Meehan

W. Kane D. DeMarco B. Stiltenpole (40) E. Brach

J. Greeves J. Holonich E. Ten Eyck M. Weber C. Paperiello

S. Shankman M. Federline CNWRA Directors/Element Managers T. Nagy (SwRI Contracts)

CNWRA PROGRAM MANAGER'S PERIODIC REPORT ON ACTIVITIES OF THE

CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES

For the Fiscal Reporting Period

September 25, 1999 - October 22, 1999

PMPR No. FY2000-1

November 5, 1999

TABLE OF CONTENTS

Section Page

T A B L E S .......................................................................... iv A BBREV IATION S .................................................................. v EXECUTIVE SUMMARY- PERIOD 1 ................................................. xi

1 T EC H N IC A L ................................................................ 1 1.1 CNW RA Operations (COPS) ............................................. 1 1.2 External Quality Assurance (EQA) ...................................... 2

1.3 Igneous A ctivity (IA ) .................................................... 3 1.4 Structural Deformation and Seisrnicity (SDS) ................................ 4 1.5 Evolution of the Near-Field Environment (ENFE) ............................. 4 1.6 Container Life and Source Term (CLST) .................................... 6 1.7 Thermal Effects on Flow (TEF) ........................................... 8 1.8 Repository Design and Thermal-Mechanical Effects (RDTME) .................. 9 1.9 Total System Performance Assessment and Integration (TSPAI) ................. 10 1.10 Activities Related to Development of the NRC High-Level Waste

Regulations (ARDR) ................................................... 11 1.11 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC) ........... 11 1.12 Radionuclide Transport (RT) ............................................. 13 1.13 Review of the Draft Environmental Impact Statement (DEIS) ................... 14 1.14 Public O utreach ....................................................... 15 1.15 Development of the Yucca Mountain Review Plan (YMRP) .................... 15 1.16 Tank Waste Remediation Systems (TWRS) ................................. 15 1.17 Dry Transfer System (DTS) .............................................. 16 1.18 Centralized Interim Storage Facility (CISF) ................................. 16 1.19 Private Fuel Storage Facility (PFSF) ....................................... 16

2 M ANAGEM ENT ISSUES ..................................................... 16

3 M AJOR PROBLEM S ........................................................ 17

4 SUMMARY OF SCHEDULE CHANGES ........................................ 17

5 SUMMARY OF FINANCIAL STATUS .......................................... 17

APPENDIX-Planned and Actual Costs, and Cost Variances Period 1-FY2000

iii

TABLES

Table Page

I CNWRA Core Staff-Current Profile and Hiring Plan (Period 1) ...................... 20

2 CNWRA Core Staff-Summary by Area of Concentration (Period 1) ................... 21

3 Summary of Schedule Changes (Period 1) ......................................... 22

4 D eliverables (Period 1) ........................................................ 23

5 Financial Status (Period 1) ..................................................... 24

6 Private Fuel Storage Facility License Fee Cost Recovery Status (Period 1) ............... 25

iv

ABBREVIATIONS

ID 2D 3D AA AAI AC ACD ACF

ACNW ACRS ACS ADAMS

AECL AES AMR AWF AGU Al ALTS AML AMR ANS ANSI AO AP APB AR ARDR

ASCE ASCII

ASLB ASME

ASTM

ASU ATDTS

BDCF BEG BFD BM BMF BTP CAI CAM CAR CCDF

CCL CCM CD-R

One-Dimensional Two-Dimensional Three-Dimensional Atomic Absorption Average Annual Infiltration Acceptance Criteria Advanced Conceptual Design Alumina (in excess of alkali feldspar), Calcium Oxide, Ferromagnesian Oxide Advisory Committee on Nuclear Waste Advanced Computer Review System American Chemical Society Agencywide Documents Access and Management System Atomic Energy of Canada Limited Atomic Emission Spectrometry Analysis Model Report Antler Wash Fault American Geophysical Union Administrative Item Apache Leap Test Site Areal Mass Loading Analysis and Model Report American Nuclear Society American National Standards Institute Annotated Outline Administrative Procedure Acid-Producing Bacteria Assessment Report Activities Related to Development of the NRC High-Level Waste Regulations American Society of Civil Engineers American Standard Code for Information Interchange Atomic Safety and Licensing Board American Society of Mechanical Engineers American Society for Testing and Materials Arizona State University Automated Technical Data Tracking System Biosphere Dose Conversion Factor Bureau of Economic Geology Basis for Design Bare Mountain Bare Mountain Fault Branch Technical Position Color Alteration Index Corrosion Allowance Material Corrective Action Request Complementary Cumulative Distribution Function Commitment Control Log Constant Capacitance Model CDROM Recordable

CDF CDOCS

CDROM CDTS CEB CEC

CFD CFR CHn CIAC CISF CLST CM CNWRA

COI COPS CPP CQAM CRG CRM CRWMS

CSCS

CSH CSPE

DAS DBE DC DCAA DCB DCF DCM D&D DECOVALEX

DEIS DEM DF DFCSS

DIE

DIMNS

DKM DLG DLM DNAG DNFSB DOE

V

Cumulative Distribution Function Consolidated DOCument Management System Compact Disk Read Only Memory Commission Decision Tracking System Center for Environmental Biotechnology Commission of the European Communities Computational Fluid Dynamics Code of Federal Regulation Calico Hills Nonwelded Tuff Computer Incident Advisory Capability Centralized Interim Storage Facility Container Life and Source Term Configuration Management Center for Nuclear Waste Regulatory Analyses Conflict of Interest CNWRA Operations Cyclic Potentiodynamic Polarization CNWRA Quality Assurance Manual Center Review Group Corrosion Resistant Material Civilian Radioactive Waste Management System Constrained Stochastic Climate Simulator Calcium Silicate Hydrate Corrosion Science and Process Engineering Data Acquisition System Design Basis Event Division of Contracts Defense Contract Audit Agency Double Cantilever Beam Dose Conversion Factor Dual Continuum Model Decommissioning and Decontamination DEvelopment of COupled Models and Their VALidation Against EXperiments in Nuclear Waste Isolation Draft Environmental Impact Statement Digital Elevation Model Dilution Factor Division of Fuel Cycle Safety and Safeguards Determination of Importance Evaluation Division of Industrial and Medical Nuclear Safety Dual Permeability Model Digital Line Graph Diffuse Layer Model Decade of North American Geology Defense Nuclear Facilities Safety Board U.S. Department of Energy

ABBREVIATIONS (cont'd)

DOE-DP

DOE-RU

DRA DST DTED DTS DWM DWPF EA EBS ECM ECRB

EDO

EDX EIS EM EMPA ENE ENFE

EnPA ENS EPA EPR

EPRI EQA EROS ESF ESP EW EWDP EXAFS

FCRG FDSHA

FEHM FEM FEPs FFRDC

FFT FOC FTE FTP FY FYTD GDF GEM GEOTRAP

U.S. Department of Energy Defense Program U.S. Department of Energy Regulatory Unit Division of Regulatory Applications Drift Scale Test Digital Terrain Elevation Data Dry Transfer System Division of Waste Management Defense Waste Processing Facility Environmental Assessment Engineered Barrier System/Subsystem Equivalent Continuum Model Enhanced Characterization of Repository Block Office of the Executive Director for Operations Energy-Dispersive X-Ray Spectroscopy Environmental Impact Statement Element Manager Electron MicroProbe Analysis East-NorthEast Evolution of the Near-Field Environment Energy Policy Act of 1992 European Nuclear Society U.S. Environmental Protection Agency Electrochemical Potentiokinetic Reactivation Electric Power Research Institute External Quality Assurance Earth Resource Observation System Exploratory Studies Facility Environmental Simulation Program East-West Early Warning Drilling Project Extended X-Ray Absorption Fine Structure Format and Content Regulatory Guide Fault Displacement and Seismic Hazard Analysis Finite Element Heat and Mass Transfer Finite Element Method Features, Events, and Processes Federally Funded Research and Development Center Fast Fourier Transform Field Operations Center Full-Time Equivalent File Transfer Protocol Fiscal Year Fiscal Year-To-Date Ghost Dance Fault General Electrochemical Migration GEOlogic Transport of RAdionuclides Predictions

vi

GERT General Employee Radiological Training

GET General Employee Training GFM Geological Framework Model GHGC GeoHydrology and GeoChemistry GIA Generalized Importance Analysis GIS Geographic Information System GLGP Geology and GeoPhysics GMS Goundwater Modeling System GPS Global Positioning System GROA Geologic Repository Operations Area GSA Geologic Society of America GTFE Great Tolbachik Fissure Eruption GUI Graphics User Interface GWB Geochemist's WorkBench GWSI GroundWater System Integration GWTI" GroundWater Travel Time HE Hydrogen Embrittlement HLW High-Level Waste HRTEM High-Resolution Transmission Electron

Microscopy HTML HyperText Markup Language IA Igneous Activity IBM International Business Machines ICP Inductively Coupled Plasma ICPP Idaho Chemical Processing Plant ICRP International Commission on

Radiological Protection IDLH Immediately Dangerous to Life and

Health IHLRWMC International High-Level Radioactive

Waste Management Conference and Exposition

IM Intermediate Milestone IME Industrial Mobilization Exemption IMS Information Management Systems INEEL Idaho National Engineering and

Environmental Laboratory INETER Instituto Nicaraguense de Estudios

TERritoriales INTEC Idaho National Technology and

Engineering Center I/O Input/Output IP Inspection Procedure IPA Iterative Performance Assessment IR&D Internal Research & Development IRIS Interim Records Information System IRM Office of Information Resources

Management IRSR Issue Resolution Status Report ISA Integrated Safety Analysis ISFSI Independent Spent Fuel Storage

Installation ISI Integrated SubIssue ISM Integrated Site Model

ABBREVIATIONS (cont'd)

IUGG

IVM iC JPL JRC KESA KTI LA LAAO LAN LANL LARP LAW LBNL LBT LHS LITC

LLC LLNL

LLW LMAES

LSA LSS LWR M Ma MAI MAP MAT MC METRA MGDS MH MIC MINC MIT MM M&O MOU MPC MRS MSS MTU NAS NAWG NCR NEA NEI NFS NIOSH NIR

International Union of Geodesy and Geophysics Interactive Volume Modeling Job Code Jet Propulsion Laboratory Joint Roughness Coefficient Key Elements of Subsystem Abstraction Key Technical Issue License Application License Application Annotated Outline Local Area Network Los Alamos National Laboratory License Application Review Plan Low-Activity Waste Lawrence Berkeley National Laboratory Large Block Test Latin Hypercube Sampling Lockheed Information Technology Company Limited Liability Company Lawrence Livermore National Laboratory Low-Level Waste Lockheed Martin Advanced Environmental Systems Liquid Scintillation Analyzer Licensing Support System Light Water Reactor Molar Million Years Ago Mean Annual Infiltration Mean Annual Precipitation Mean Annual Temperature Monte Carlo Mass and Energy TRAnsport Mined Geologic Disposal System Mechanical-Hydrological Microbially Influenced Corrosion Multiple INteracting Continua Massachusetts Institute of Technology Major Milestone Management and Operations Memorandum Of Understanding Multi-Purpose Canister Monitored Retrievable Storage MultiSpectral Scanner Metric Tonnes of Uranium National Academy of Sciences Natural Analogue Working Group NonConformance Report Nuclear Energy Agency Nuclear Energy Institute Network File Server National Institutes Of Safety and Health Near-InfraRed

NIST

NMSS

NNE NNW NOAA

NRC NS NTS NUREG NWPA NWTRB OBES OCRWM

OECD

OGC OITS OMB OPS

ORR ORS OWFN PA PAAG

PC PCITCP

PCT PDF PDR PEL PEM PER PEST PFA PFD PFDHA

PFS PFSF PHA PI PMDA

PMPR PMR PMT PNNL PO PPE

vii

National Institute of Standards and Technology Office of Nuclear Material Safety and Safeguards North-NorthEast North-NorthWest National Oceanographic and Atmospheric Administration Nuclear Regulatory Commission North-South Nevada Test Site NRC Technical Report Designation Nuclear Waste Policy Act, as amended Nuclear Waste Technical Review Board Office of Basic Energy Sciences Office of Civilian Radioactive Waste Management Organisation for Economic Co-operation and Development Office of General Counsel Open-Item Tracking System Office of Management and Budget Operations Plans for the Repository Program Operations Readiness Review Overall Review Strategy One White Flint North Performance Assessment Performance Assessment Advisory Group Personal Computer Personal Computer/Transmission Control Protocol Product Consistency Test Probability Distribution Function Public Document Room Permissible Exposure Limit Program Element Manager Prelicensing Evaluation Report Parameter ESTimation PerFluoroAlkoxy Probabilistic Fault Displacement Probabilistic Fault Displacement HAzard Private Fuel Storage Private Fuel Storage Facility Preliminary Hazard Analysis Principal Investigator Program Management, Policy Development and Analysis Staff Program Manager's Periodic Report Process Model Report Photo-Multiplier Tube Pacific Northwest National Laboratory Project Officer Prepassivated Platinum Electrode

ABBREVIATIONS (cont'd)

PRA PRT PSAG PSHA PSI PTFE PTn PUF PVHA

Probabilistic Risk Assessment Peer Review Team Probabilistic System Assessment Group Probabilistic Seismic Hazard Analyses Process Safety Institute PolyTetraFluoroEthylene Paintbrush Nonwelded Tuff Pressurized Unsaturated Flow Probabilistic Volcanic Hazards Assessment Probability of Volcanic Hazards View Parallel Virtual Machine Pressurized Water Reactor Quality Assurance Quality Assurance Procedure Quality Requirements Application Matrix Request for Additional Information Regional Aquifer System Analysis Repository Design, Construction, and Operations Repository Design and ThermalMechanical Effects Rare Earth Element Reynolds Electrical and Engineering COmpany, Inc. Office of Nuclear Regulatory Research Request For Proposal Relative Humidity Review Method Real Space Renormalization Group Radionuclide Transport Radwaste Treatment System Science Application International Corporation Standards Approval Package Safety Analysis Report Site Characterization Analysis Stress Corrosion Cracking Substantially Complete Containment EXample Standard Calomel Electrode Southern Crater Flat Fault Surface Complexation Models Site Characterization Plan Software Change Report Site Decommissioning Management Plan Structural Deformation and Seismicity Secretary of the Commission, Office of the (NRC) Spectral ELement Method Scanning Electron Microscopy Safety Evaluation Report Spent Fuel Project Office San Francisco Volcanic Field

SGI SGML

SHE SHT SKI S-L SLAR SNF SNL SOW SR SRB SRBS

SRD SRS SRSASF

SS SSSA SSC SSW STEM

STP SUFLAT

SVF SwRI SZ TA TAN T3D "TBM TCP/IP

TDEM TEDE TEF TEM TFE TH THC THMC

T-L TLM TM TMH TMI-2 TMS

TOP TP TPA

Viii

Silicon Graphics Inc. Standard Generalized Markup Language Standard Hydrogen Electrode Single Heater Test Swedish Nuclear Power Inspectorate Short Transverse-Longitudinal Side Looking Airborne Radar Spent Nuclear Fuel Sandia National Laboratories Statement Of Work Site Recommendation Sulfate-Reducing Bacteria Shafts, Ramps, Boreholes, and Their Seals Software Requirements Description Savannah River Site Savannah River Site AluminumBased Spent Fuel Stainless Steel Soil Science Society of America Structures, Systems, and Components South-Southwest Scanning Transmission Electron Microscopy Staff Technical Position Stochastic Analyses of Unsaturated FLow And Transport Springerville Volcanic Field Southwest Research Institute Saturated Zone Technical Assistance Test Area North To Be Determined Tunnel Boring Machine Transmission Control Protocol!/ Internet Protocol Time-Domain Electro-Magnetic Total Effective Dose Equivalent Thermal Effects on Flow Transmission Electron Microscopy TetraFluoroEthylene Thermal-Hydrologic Thermal-Hydrologic-Chemical Thermal-Hydrologic-MechanicalChemical Transverse-Longitudinal Triple-Layer Model Thermal-Mechanical Thermal-Mechanical-Hydrological Three Mile Island Unit 2 The Minerals, Metals, and Materials Society Technical Operating Procedure Technical Position Total-system Performance Assessment

PVHView

PVM PWR QA QAP QRAM

RAI RASA RDCO

RDTME

REE REECO

RES RFP RH RM RSRG RT RTS SAIC

SAP SAR SCA SCC SCCEX

SCE SCFF SCM SCP SCR SDMP SDS SECY

SELM SEM SER SFPO SFVF

ABBREVIATIONS (cont'd)

TPI TR2 TRG TSAR TSPA TSPA-VA

TSPAI

TSw-Chnv

TVD TWFN TWINS

TWRS UA UACH

UCLA UDEC UK UNLV UNM UR U.S. USDA USFIC

USGS UTM UZ VA VCS VF VSIP WAN WAPDEG WBS WFO WGB WIPP WNYNSC

WOL WP WSRC

WSS WTSO WVDP WVNS

XAFS XPS XRD

Y2K YM YMP YMR YMRP YMSCO

YTD

Year 2000 Yucca Mountain Yucca Mountain Project Yucca Mountain Region Yucca Mountain Review Plan Yucca Mountain Site Characterization Office Year-To-Date

ix

Time Period of Regulatory Interest DOE Seismic Topical Report No. 2 Technical Review Group Topical Safety Analysis Report Total System Performance Assessment Total System Performance AssessmentViability Assessment Total System Performance Assessment and Integration Topopah Spring Welded-Calico Hills Nonvitric Total Variation Diminishing Two White Flint North Tank Waste Information Network System Tank Waste Remediation System University of Arizona Universidad Aut6noma de Chihuahua University of California, Los Angeles Universal Distinct Element Code United Kingdom University of Nevada, Las Vegas University of New Mexico Uranium Recovery United States U.S. Department of Agriculture Unsaturated and Saturated Flow Under Isothermal Conditions U.S. Geological Survey Universal Transverse Mercator Unsaturated Zone Viability Assessment Version Control System Vitrification Facility Vertical Slice Implementation Plan Wide Area Network WAste Package DEGradation Work Breakdown Structure Work For Others Western Great Basin Waste Isolation Pilot Plant Western New York Nuclear Service Center Wedge-Opening Loading Waste Package Westinghouse Savannah River Company Waste Solidification Systems Washington Technical Support Office West Valley Demonstration Project West Valley Nuclear Services World Wide Web X-Ray Adsorption Fine Structure X-Ray Photoelectron Spectroscopy X-Ray Diffractometry

EXECUTIVE SUMMARY-PERIOD 1

In the Division of Waste Management (DWM) Job Code (JC), the Center for Nuclear Waste Regulatory Analyses (CNWRA) staff transmitted Revision 14, Change 0, to the FY2000 OPS, Thermal-Hydrologic Laboratory Testing-Journal Paper or Presentation, and a report titled A Strategic Plan for Development and Documentation of the Nuclear Regulatory Commission Total-system Performance Assessment Method. Additionally, work continued in areas related to Review of the Draft Environmental Impact Statement, and began in External Quality Assurance, Public Outreach, and Development of the Yucca Mountain Review Plan. The staff produced papers and posters forpresentation at various technical meetings. These papers have been or will be submitted for acceptance in recognized technical journals. Staff also participated in workshops, symposia, and other technical meetings.

The DWM JC year-to-date (YTD) cost variance was - 11.7 percent. Spending fell from the last period in FY 1999, but exceeded spending estimates for the period.

In the Tank Waste Remediation System (TWRS) JC, staff addressed the NRC comments on Process Hazards and Safety Issues for TWRS-P, Volume II, Auxiliary Support Systems and Process Control Systems. Staff attended two topical meetings on the TWRS-P project in Richland Washington. The YTD cost variance was 20.5 percent. This variance is expected to decrease as new activities begin.

In the Dry Transfer System (DTS) JC, staff continued developing the DTS draft Safety Evaluation Report (SER), and made use of CNWRA, Southwest Research Institute (SwRI) staffs, and consultants in this work. The YTD cost variance was 24.7 percent. The spending will increase significantly during the next period as the CNWRA and SwRI staffs prepare the draft SER.

In the Centralized Interim Storage Facility (CISF) JC, staff received the DOE response to the Spent Fuel Project Office Request for Additional Information on the HI-STAR and HI-STORM topical report for high seismic risk sites. The CNWRA review of this response was promptly initiated during this period. The YTD cost variance for the CISF was 45.1 percent. Spending on this project will increase significantly after the NRC comments on the draft Assessment Report are received at the CNWRA in November 1999.

In the Private Fuel Storage Facility (PFSF) JC, staff continued the review of the seismic design reports and extensive interactions took place between the respective NRC and CNWRA staffs in addressing this work. The YTD cost variance was 42.6 percent. The cost underrun will continue until the applicant submits the revised seismic design of PFSF.

xi

CNWRA PROGRAM MANAGER'S PERIODIC REPORT ON ACTIVITIES OF THE

CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES

TITLE: Center for Nuclear Waste Regulatory Analyses (CNWRA)

CONTRACTOR: Southwest Research Institute (SwRI) 6220 Culebra Road, San Antonio, Texas, 78238-5166

CONTRACT NO: NRC-02-97-009

JOB CODES: D1035, J5164, J5206, J5226

NRC CNWRA PROGRAM MANAGER: John J. Linehan, (301) 415-7780

NRC CNWRA DEPUTY PROGRAM MANAGER: Deborah A. DeMarco, (301) 415-7804

CNWRA PRESIDENT: Wesley C. Patrick, (210) 522-5158

ESTIMATED BUDGET: $87,611,477

PERIOD OF PERFORMANCE: 09/27/97-09/27102

PERIOD OF THIS REPORT: 09/25/99-10/22/99

1 TECHNICAL

1.1 CNWRA Operations (COPS)

In addition to a wide range of day-to-day activities, accomplishments in the management and planning area included (i) delivering Revision 14, Change 0, to the FY2000 OPS and other NRC-related operations plans; (ii) meeting with representatives from the French Nuclear Installation Safety Directorate and the Institute for Protection and Nuclear Safety; (iii) reconciling estimates for FY2000 carryover monies; (iv) addressing COI-related topics among the NRC, SwRI, and CNWRA management staffs; and (v) participating in weekly HLW Management Board meetings.

The status of CNWRA staffing is indicated in table 1. During period 1, intensive recruitment continued and several sources were used to identify potential candidates. An operational health physicist is scheduled to join the staff in period 5 and a performance assessment modeler is expected to begin working at the CNWRA in period 6.

Computer system support activities encompassed (i) continuing the use of consultants to develop and modify software as well as document hardwarelsoftware changes to the Sun Microsystems, Silicon Graphics, and Windows NT servers; (ii) upgrading the desktop computers for basic system standardization and Y2K compliance; (iii) pursuing installation of hardware and software for the CNWRA Security System (firewall); (iv) updating all

I

hardware/software inventory records; (v) participating, as requested, in the monthly NRC/CNWRA Computer Coordination meeting; and (vi) maintaining LAN operations.

QA activities included (i) working in response to the CARs from the FY1999 CNWRA QA Audit and making substantial changes to CNWRA QA procedures; (ii) conducting surveillances, issuing nonconformance reports and corrective action requests, as required, and working with cognizant staff in response to these reports; (iii) supporting the application of configuration control for CNWRA scientific and engineering software ready for release; (iv) preventing organizational COI through SwRI RFP reviews; (v) performing QA verification checks on each CNWRA deliverable; (vi) providing QA indoctrination for new CNWRA staff members and consultants; and (vii) submitting the revised CNWRA Quality Assurance Manual and distributing it to key CNWRA staff members.

In the next period, the CNWRA staff expect to (i) participate in an NRC/CNWRA Management Meeting at TWFN; (ii) prepare for NRC Annual Review of CNWRA; (iii) aggressively pursue hiring for open core staff positions; (iv) continueuse of consultants to complete Y2K reconciliation, develop new and modify existing databases and spreadsheets, and revise LAN configurations, including installation of revisions to the CNWRA firewall; and (v) provide CNWRA LAN operation and maintenance support.

In addition, the staff will (i) finalize the QA-related procurement procedure and improve control of scientific and engineering software as well as engage in other activities addressing the CARs identified at the annual CNWRA QA audit, (ii) perform scheduled and unscheduled QA surveillances, (iii) conduct QA indoctrinations for new CNWRA staff and consultants, (iv) review SwRI RFPs for potential COI, (v) perform QA verification checks on each CNWRA outgoing deliverable, and (vi) submit QA survey forms to CNWRA subcontractors.

1.2 External Quality Assurance (EQA)

During this period, accomplishments in the EQA area included (i) preparing for and participating in the NRC observation team to observe OCRWM Audit M&O-ARP-99-009, October 11-15, 1999; (ii) working on the observation report on the OCRWM Audit M&OARP-99-009; (iii) holding discussions with NRC staff to prepare for another round of NRC observation audits and to discuss lessons learned and methods to improve the auditing process; and (iv) distributing AMRs and PMRs to team participants.

CNWRA participation in the Integrated Site Model Process Model Report audit observation was the first EQA-funded activity since 1996, when NRC reduced EQA activities. The SwRI QA department has been informed that its support of EQA activities during FY2000 is desired and they have offered assistance to the CNWRA.

In the next period, the CNWRA staff expect to (i) complete the input to the NRC audit report for the ISM/PMR audit; (ii) participate in the Waste Package PMR audit; (iii) participate in the Biosphere PMR audit; and (iv) provide CNWRA input to the respective NRC observation reports on the these audits.

2

1.3 Igneous Activity (IA)

Staff presented the results of Cerro Negro risk analysis and discussed the utility of stochastic process models in risk assessments at an invited presentation to the Royal Society (London) on science in volcanic crises. Through detailed study, time-volume relationships at the Cerro Negro volcano have been used to forecast successfully the timing of the next eruption years before any signs of unrest. Similar studies at other volcanoes with steady-state eruption rates thus are warranted to evaluate the probability of future activity. Staff showed how the tephra dispersion model in ASHPLUME can be used to evaluate quantitatively tephra-fall hazards. The main hazards from tephra falls are building collapse from the weight of the deposit, overloading filtration systems with fine particles, and mechanical abrasion from the particles. Model parameters can be modified during various stages of volcanic unrest or during the eruption, to evaluate more accurately the likely thicknesses and granulometry of tephra-fall deposits at critical localities. In addition, results from the tephra-fall models can be combined with probability estimates to quantify the risk from tephra-fall deposits. This risk then can be compared with other risks in societal cost-benefit analyses. The presentation generated with much interest in applying these methods at other hazardous volcanoes.

The author-final version of a paper on numerical simulation of magma-repository interaction has been sent out for external technical review. This paper, to be submitted to the Journal of Geophysical Research, summarizes modeling shock wave propagation in the repository drift following intrusion of a volatile-rich (1-2 wt percent) magma into the drift. Final revisions also were made to the journal article Geologic Factors Controlling Patterns of Small-volume Basaltic Volcanism: Application to a Volcanic Hazards Assessment at Yucca Mountain, Nevada. This paper is now in press at the Journal of Geophysical Research. Staff also continued to revise sections of the TSPAI IRSR and the YMRP.

Staff continued development of the physical analog model for magma repository interaction. Experiments were delayed in this period, primarily because of difficulties calibrating highly sensitive pressure transducers used in the apparatus. These difficulties have been resolved, and experiments will continue in the coming period. Several JAVA codes were prepared to support the probabilistic volcanic hazard assessment code (PVHAView). These codes perform probability calculations and graphing routines. In addition, a JAVA code was developed that models ash dispersion based on the ASHPLUME model. This JAVA code modifies the grain size parameterization, allowing for easier comparison between the results of model and geologic data sets.

Staff gave two invited lectures at Baylor University in WacoTexas, The first lecture gave an overview of the YM repository program, discussed the general geology of the site, and showed how the probability and consequence of volcanic disruption are being evaluated and compared with other risks. A second lecture examined the range of eruptive styles and products at the Cerro Negro volcano, Nicaragua, and showed how this basic geological information can be used to construct quantitative models for probability and consequences of future events.

In the next period, staff will continue to (i) analyze and model data from the August activity at the Cerro Negro volcano, (ii) prepare for presentations for the NRC Annual Review of the CNWRA and Fall AGU meeting, (iii) revise appropriate sections of the TSPAI IRSR

3

and the deliverable Consequences of Basaltic Igneous Activity on HLW Repository Performance-Journal Article, and (iv) conduct analog experiments of magma-repository interactions that will evaluate the response of a high-volatile content system during sudden decompression and fragmentation.

1.4 Structural Deformation and Seismicity (SDS)

Staff made final additions to the EarthVision geologic model that will be used as input for hydrologic modeling of the saturated zone, and they began the development of the accompanying CNWRA report. They gained insights into model generation during a oneday site visit by a representative from Dynamic Graphics. Technical problems associated with stable model generation appear to have been resolved.

Staff began an analysis of the field data on faults and fractures recently collected in the Volcanic Tablelands of California. The deformation of the Tablelands serves as an analog for deformation at YM. Results of the analysis will be used in resolving uncertainties in orientation and distribution of fracture sets at YM and in the review and evaluation of the faulting models proposed in the DOE PSHA expert elicitation.

Staff pursued development of the Strain Distribution and Tectonic Setting of Yucca Mountain and Crater Flat-Journal Article. This article will evaluate the geological relationships in Crater Flat and present a 3D model of the fault system at Bare Mountain. Alternatives of the model will be used to evaluate sensitivities of the potential seismic hazard at YM.

Staff have made significant progress on developing geometric models of secondary faultblock deformation produced by lateral displacement gradients on normal faults. These models will appear in the deliverable titled Constrain Models of Faults and Fractures at Different Scales in Analysis and Evaluation of Fracture Data-Journal Article.

Staff finished an AI report on the portability of SEISM I. 1. This report documents the completion of all SEISM 1.1 activities, including archiving of the software.

In the next period, staff will (i) begin modifications and additions to the 3DStress software leading to Version 2.0, following completion of the TOP-018 requirements, (ii) continue work on the Strain Distribution and Tectonic Setting of Crater Flat and 3D Structural Model of Amargosa Desert milestones, (iii) travel to the University of Michigan to conduct paleomagnetic measurements of samples collected from southern Crater Flat and the Volcanic Tablelands of California, and (iv) attend the NRC sponsored OECD-NEA workshop on the engineering characteristics of seismic input at Brookhaven National Laboratory in Upton, New York.

1.5 Evolution of the Near-Field Environment (ENFE)

Staff continued an analysis of ENFE-relevant content in the DOE database of FEPs focusing on inclusiveness and FEPs screening. Preparation of a report on FEP analysis was initiated. A meeting between CNWRA and NRC staff in Rockville, Maryland, helped to define the scope and organization of this report. The report will list ENFE-relevant FEPs, their screening status, staff evaluation of inclusiveness, and FEP mapping to ENFE

4

subissues and ISIs. Staff also compiled critiques on the organization and usability of the database, to be included in the report.

Staff continued studies of the Nopal I deposit at Pefia Blanca to improve understanding of radionuclide mobility among secondary phases in a hydrologically unsaturated, chemically oxidizing environment comparable to YM. They obtained final U-Tb concentration data on 18 carbonate samples, and began selection of samples for detailed isotopic analyses. Staff pursued the development of a set of HTML files for the Pefia Blanca natural analog site. These files currently form a CNWRA intranet webpage. In addition to information on the Pefia Blanca natural analog project, the files contain background material on the use of natural analog studies to evaluate geologic disposal of nuclear waste. This material is being gathered from earlier CNWRA publications on the Pefia Blanca site and on the use of natural analogs.

NRC and CNWRA staff continued a review of the DOE Disposal Criticality Analysis Methodology Topical Report. ENFE-related concerns in the SER focused on the approach to, and validation of, geochemical models affecting fissile material release and near-field transport. Staff attended a technical exchange during which DOE staff provided responses to an NRC RAI. These responses will enable staff to continue preparation of an SER. Geochemistry issues were largely resolved at the technical exchange.

Staff made continued progress in the interpretation of the revised YM UZ groundwater chemistry and development of coupled hydrological-geochemical simulations of YM. The revised UZ groundwater chemistry will be used as input for ENFE PA calculations and sensitivity analyses using the TPA code. Staff are preparing a paper, entitled Thermodynamic Interpretations of Chemical Analyses of Water from Yucca Mountain, Nevada, which will give some of the results of this activity. This paper will be presented at the Materials Research Society Fall Meeting in Boston, Massachusetts, November 29December 3, 1999. Moreover, this paper is proposed as a new deliverable in table 3 of this PMPR.

Alternative conceptual models of trace metal transport at the Akrotiri archeological site were analyzed and compared with reference to implications for PA modeling. A paper titled An Archeological Site at Akrotiri, Greece, as a Natural Analog for Radionuclide Transport: Implications for Validity of Performance Assessments, describes the results of this study, and it will be presented at the Materials Research Society Fall Meeting in Boston, Massachusetts, November 29-December 3, 1999. This paper, too, is proposed as a new deliverable in table 3 of this PMPR.

Staff continued development of Versions 1.2 and 2.0 of the MULTIFLO code. Effort focused on the TVD algorithm, which makes it possible to model advection-dominated transport with reduced numerical dispersion. They continued the debugging and testing of the unstructured grid capabilities in GEM and the development of a drift climate module for Version 2.0. This module will make it possible to model ventilation and thermal radiation in an open emplacement drift.

Staff are making progress in the development of process-level models designed to help evaluate THC effects resulting from the EDA-II design. They are developing and debugging a MULTIFLO model which will incorporate a chemical system to a seepage and flow

5

model using an unstructured grid and provide a more realistic assessment of permeability changes due to mineral precipitation/dissolution and the spatial occurrences of geochemical processes. This model would complement efforts already in progress to combine a different seepage and flow model based on a structured grid formulation with chemical constraints.

CNWRA staff and a consultant from the University of Aberdeen met in San Antonio, Texas, to discuss progress that has been made in experimental and thermodynamic modeling studies on performance of concrete at elevated temperatures. NRC staff and a consultant from Johns Hopkins University participated via teleconference.

Staff pursued an assessment of the potential radiolysis effects on the near-field environment-inside and outside the WP-on the basis of the EDA-II design. This assessment will include bounding values of radiolysis effects for typical waste forms.

Staff are considering proposed changes to the TPA Version 4.0 code. Separate discussions were held regarding development of models to place bounds on the chemistry of water first contacting the WP and to characterize the chemical reactions inside WPs.

In the next period, staff will (i) complete an author-final draft of a deliverable on FEPs Database Analysis, (ii) present results of ENFE activities at the Materials Research Society Fall Meeting in Boston, Massachusetts, (iii) participate in designing the third CNWRA heater test and attend a workshop on this activity to be held in Rockville, Maryland, and (iv) obtain U-Th isotopic analyses on Pefia Blanca carbonates. Staff will continue preparation of an SER on the DOE Disposal Criticality Analysis Methodology Topical Report, and they will attend a meeting on an addendum to the topical report concerning criticality analysis of U.S. Navy spent fuels.

1.6 Container Life and Source Term (CLST)

Staff continued to evaluate the applicability of repassivation and corrosion potentials as adequate electrochemical parameters to predict the long-term, localized corrosion of corrosion-resistant container materials through prolonged corrosion testing. Potentiostatic and open-circuit tests conducted in chloride-containing solutions at 95 'C using Alloy 825 specimens with attached crevice-forming devices continued, reaching total test times of 1,484 and 1,338 days, respectively. In addition, for the past several months, three creviced Alloy 22 specimens have been tested at 95 'C in a 4M NaCl solution at pH 8.0. Two of these specimens are being tested at 300 and 400 mVscE, and the third at the open-circuit potential in an air-saturated solution. The time-dependent changes in the corrosion potential are monitored in the test under open-circuit conditions. Staff completed the potentiodynamic polarization tests of as-received and welded Alloy 22 specimens. Expressions for the repassivation potential as a function of chloride concentration and temperature obtained in these tests will be used in the next version of the TPA code.

Staff measured the passive corrosion rates of welded Alloy 22 specimens in slightly alkaline (pH 8.2) and acidic (pH 2.7) chloride solutions at 95 'C. They began tests to measure the passive corrosion rate of welded specimens in highly alkaline solutions (pH 11.0). Results obtained to-date indicate that the passive dissolution rate of the welded material is similar to that measured for the base metal. Staff initiated modeling of the passive behavior of Ni-Cr-Mo alloys using a modified version of the point-defect model to

6

provide a solid mechanistic interpretation to the experimentally measured long-term passive corrosion rates.

Staff continued the SCC testing of Alloy 22 and type 316L SS in hot chloride-containing solutions. Fatigue precracked, wedge-loaded DCB specimens of each material were tested in a deaerated 5 percent NaCl solution, acidified to pH 2.7 by the addition of HCI, and heated to 90 'C to duplicate experimental conditions used at the LLNL. No cracking of the two alloys was observed under these conditions for a cumulative test time of 47 wk. In addition, no crack growth was observed on Alloy 22 specimens exposed to a more aggressive environment, 40 percent MgCl2 solution at 110 'C under open-circuit potential conditions. In contrast, significant crack growth was observed in type 316L SS specimens after a short exposure period in MgCl2 solutions (both 30 and 40 percent) at 110 'C. Tests of type 316L SS specimens conducted at various applied potentials in 30 percent MgC12

solution at 110 'C showed that the crack growth rate decreases with decreasing potential. It appears that no SCC propagation would occur below the repassivation potential. Staff are planning more tests to confirm whether the repassivation potential may be used as a threshold criterion for precracked specimens as was demonstrated previously for smooth specimens in slow strain rate tests.

Staff have prepared a paper containing the results obtained in all these studies on Alloy 22 for presentation at the NACE Corrosion/2000 conference, and it is currently under technical review.

Staff continue to evaluate the effects of environmental variables on the corrosion behavior of Ti-grade 7 (identified by the DOE as a possible candidate material for drip shield construction). Long-term tests are used to examine the effects of high applied potentials. The galvanic coupling of Ti to carbon steel is also examined because carbon steel components will be used for ground support. Crevice corrosion testing also continued at temperatures greater than 100 'C to examine the effects of temperature on the critical potentials for the localized corrosion of Ti. Given the high resistance of Ti alloys to localized corrosion, staff also conducted measurements of the passive dissolution rate. In addition, welded specimens are being evaluated to examine the possible detrimental effects of weldments on corrosion resistance. A paper to be presented at the NACE Corrosion/2000 conference detailing the results obtained to-date is currently under technical review.

Staff conducted electrochemical tests examining the effects of J- 13 well water anions and thermal pre-oxidation on the localized corrosion behavior of Zircaloy-4 in chloride solutions. These tests showed that the anions at the concentrations found in J-13 water have an inhibiting effect at low chloride concentrations. At higher chloride concentrations, inhibition was not observed. Thermal pre-oxidation at 200 °C did not result in a significant change in the susceptibility of Zr-4 to localized corrosion but did change the morphology from broad, shallow pits to hemispherical pits. NRC and CNWRA staff collaborated in the development of a paper discussing these results for presentation at the NACE Corrosion/2000 conference, and this paper, too, has been submitted for technical review.

Staff pursued testing of glass wasteforms using the standard EA glass and two simulated waste glasses (DWPF Blend I and WVNS Reference 6) using the ASTM PCT, Method B. Long-term tests on these three glasses are conducted in deionized water and concentrated FeCI2 and FeCl1 solutions (0.25 and 0.0025 M) with solution replacements twice a week

7

using PFA TFE-flourocarbon vessels. Twenty-four solution replacements have been made and the leachates analyzed using ICP to determine the effect of iron cations on the dissolution rate of the reference glasses. A 1-wk solution replacement interval has been initiated. This effect is important for assessing the influence of steel corrosion products on glass degradation. In addition, staff used PUF test equipment to study the dissolution behavior of simulated wasteforms under repository conditions. Long-term tests exceeding 6 mo are planned.

Staff continued evaluating the suitability of corrosion potential and chemistry (Cl concentration and pH) sensors for heat transfer conditions, as part of a performance confirmation test evaluation program. Electrodes have been fabricated and testing has been conducted at 27.5, 50, and 85 'C. Preliminary results indicate that the chloride and pH electrodes show promise, though the reference electrode shows some variability with time and solution chemistry. It is not yet known how the electrodes will respond to episodic water contact and dry-out. Staff will initiate tests to examine this response in the next period. The final assembly will be employed in the simulated drift experiments coordinated by the TEF KTI team.

Staff completed the analyses of the effect of rockfall on the mechanical failure of SNF cladding using a fracture mechanics approach. A paper, currently under technical review, has been prepared for submittal to Nuclear Engineering and Design.

In the next period, staff will continue long-term corrosion testing of Alloys 825 and C-22 and the SCC tests using Alloy C-22 and type 316L SS along with the Ti-grade 7 test program, including examination of localized corrosion of welded specimens. In addition, staff will continue to examine the effect of the environment on the corrosion behavior of Zircaloy-4 and to evaluate current sensor designs to be used in the simulated drift experiments. Staff will perform additional glass-dissolution tests. Technical and programmatic review of the various papers for presentation at Corrosion/2000 conference and subsequent publication will be completed. Staff will also initiate an investigation of the internal waste package environment in coordination with other CNWRA staff associated with the ENFE and TEF KTIs.

1.7 Thermal Effects on Flow (TEF)

A workshop for the third laboratory-scale heater test has been scheduled for November 9, 1999, at the NRC Headquarters. The coupled corrosion/heater experiment is a collaborative effort among staff related to the TEF, ENFE, and CLST KTIs. CNWRA representatives from these KTIs will attend the workshop. Candidate sensors for the experiment are being bench tested for use in the experiment.

Staff modified the model for calculating drop volume and dripping period for dripping from a fracture face into an opening (i.e., a drift or cavity) to account for the observed transition of negative water potentials on the fracture face to the positive water potentials in the drop. Laboratory measurements of dripping from analogs of open fracture faces were made to confirm the new model. Model predictions also compared favorably with published data on dripping in natural caves in Belgium. A proceedings paper entitled Dripping into Subterranean Cavities from Unsaturated Fractures Under Ventilated Conditions is being prepared for the Society for Mining, Metallurgy and Exploration, Inc. conference to be held

8

in February 2000. Staff also progressed in adapting the UZ constitutive relations for a single fracture face (water retention and relative permeability curves), which already includes film and capillary flow components, to relations that are relevant for movement of water between two closely spaced fracture surfaces by incorporating the physical processes pertinent for water bridging the gap (aperture).

The laboratory investigation of an artificial fracture is focused on attempting to determine whether a threshold for dripping exists and if this threshold can be determined from measurements of flow rate and fracture aperture. Preliminary TH simulations of pressure, temperature, RH, and other variables of state within a backfilled drift have been completed to 10,000 yr. The first set of simulations demonstrated sensitivity of results to thermal properties of backfill material. The Thermal-Hydrologic Laboratory Testing-Journal Paper was transmitted during this period.

In the next period, staff plan to (i) continue defining and planning analyses, in conjunction with staff associated with the ENFE and CLST KTIs for the third laboratory-scale heater

test; (ii) integrate a groove/film-flow model into the mechanistic fracture flow model; (iii) pursue development of a 2D, repository-scale, thermohydrological model; and (iv) continue development of the laboratory-scale capillary diversion experiment.

1.8 Repository Design and Thermal-Mechanical Effects (RDTME)

Staff incorporated the resolution of the NRC management review comments into the RDTME IRSR, Revision 2, and this final version of the IRSR was delivered to the NRC on September 30, 1999.

The ABAQUS code modeling of WPs continued to investigate the thermal stress of WPs and assess the WP responses when subjected to the impact of falling rocks at various times considering the long-term effect of corrosion on WPs. This analysis will develop a reasonable failure criterion for use in the SEISMO module to assess the effect of rockfall on WP integrity.

To support the UDEC code analyses predicting the size and extent of rockfall under seismic loads in the repository thermal environment, staff analyzed the scanline information from the ESF using the stereonet approach to identify distinct joint sets. The identified joint sets were treated individually and statistically to determine the distribution of joint plunge, trend, spacing, and trace length. An attempt is being made to use the joint distributions generated by this joint set information as input to UDEC for model development. The preliminary finding indicated that UDEC has difficulty using this complexjoint distribution information to generate an usable model. Staff is in contact with the developer of the code, and they are seeking ways to resolve this problem. They have initiated efforts to examine rockfall potential using the Key BlockTheory considering thermal stress and seismic loads.

Staff began the study of the thermal-mechanical effects of drift stability using the EDA II. They participated in a meeting to finalize the agenda for an Appendix 7 meeting on Ground Control to be held in Las Vegas, Nevada, November 17-I8, 1999.

One staff member attended the 7'h International Conference on Radioactive Waste Management and Environmental Remediation that was held September 26-30, 1999, in

9

Nagoya, Japan. At the conference, he presented a paper titled Effects of Repetitive Seismic Loads on Underground Excavations in Jointed Rock Mass in a poster session.

Three staff attended the DECOVALEX III workshop that was held October 5-7, 1999, in Las Vegas, Nevada. Two staff members also visited the YM site.

In the next period, staff plan to (i) investigate rock mass behavior under heated conditions on both repository and drift scales with an emphasis on long-term degradation of rock mass material properties and strengths using the new EDA II design, (ii) conduct rockfall simulations, (iii) use the ABAQUS code to model WPs, (iv) initiate modeling work of TMH coupled effects for DECOVALEX HI program, (v) attend the thermal test workshop to be held on November 4, 1999, in Albuquerque, New Mexico, (vi) attend the Appendix 7 meeting on DOE Integrated Safety Analysis and Graded Q Classification, and (vii) attend the Appendix 7 meeting on Ground Control to be held in Las Vegas, Nevada, November 17-18, 1999.

1.9 Total System Performance Assessment and Integration (TSPAI)

Staff continued to implement the NRC-approved modifications to the TPA code and started testing of the TPA Version 3.3 code. Staff also integrated the code changes made by the NRC staff. The CNWRA and NRC PA staffs reviewed and prioritized TPA Version 4.0 process-level changes proposed by staff associated with the various KTIs and system-level changes proposed by staff related to the TSPAI KTI.

The report titled External Review of TPA 3.2 Code-Letter Report was submitted for technical, editorial, and programmatic review. A draft version of this report also was provided to each of the external reviewers for comment. The final version of the report will be submitted to the NRC during the first week of the second period.

The report titled A Strategic Plan for Development and Documentation of the Nuclear Regulatory Commission Total-system Performance Assessment Method was delivered. This report describes a strategy for development and documentation of the PA tools that will be needed to conduct reviews of the DOE SR and LA and to support the performance confirmation program.

The contract with Bayesian Systems was finalized so activities related to the development of a post-processor for the systematic presentation of TPA output can be initiated. Staff will meet with Bayesian Systems employees during the next period to initiate the activity. Staff are also developing an alternative simplified approach for presenting TPA outputs to facilitate interaction with the external contractors.

Staff are currently exploring alternative ways such as the neural net approach for conducting sensitivity analysis of TPA code outputs.

Staff continued updating/preparing Input to TSPAI IRSR, Revision 2-Letter Report. They initiated modifications to the model abstraction section based on new guidance received from the NRC for a systematic, logical, and easy-to-read style of presentation. Work also continued on expanding the discussion of transparency and traceability in performance assessment.

10

Other activities during this period included staff preparation of papers for the NRCapproved presentations at the Waste Management 2000 Conference and the Scientific Basis for Nuclear Waste Management Symposium to be held on November 29-December 3, 1999, in Boston, Massachusetts. Staff also prepared presentations for the American Nuclear Society Winter Meeting to be held November 14-19, 1999, in Long Beach, California.

Staff interviewed candidates for the unfilled positions of a health physicist, a risk analyst, and two PA engineers. Offers have been made and two candidates have accepted. R6sum6s continue to be gathered for the remaining two open positions.

In the next period, the staff will focus on (i) incorporating the NRC staff comments into the Input to TSPAI IRSR, Revision 2-Letter Report, (ii) finalizing the report summarizing the results of the External Review of TPA 3.2 Code, (iii) continuing modifications and testing of the TPA Version 3.3 code, (iv) discussing with staff in other KTIs changes to be implemented in the TPA Version 4.0 code and preparing an SRD document, and (v) preparing papers for conferences and journals. Recruitment will continue for the two remaining PA positions.

1.10 Activities Related to Development of the NRC High-Level Waste Regulations (ARDR)

Staff continued drafting responses to comments on the 10 CFR Part 63 proposed rule. They also continued consideration of potential changes to the Statements of Consideration and this proposed rule based on review of the comments. Analyses were conducted related to comments on technical aspects of the proposed human intrusion requirements, and draft results were provided to the NRC staff to assist in their responding to the public comments on the proposed rule. Such work is expected to be included in the Analyses Supporting Responses on Draft HLW Rulemaking, which was delayed from October 30, 1999 to January 30, 2000 to accommodate the NRC revised schedule for responding to comments on the proposed rule for 10 CFR Part 63.

In the next period, emphasis will be placed on completing draft responses to NRC comments on the proposed rule for 10 CFR Part 63 and the identification of potential changes to the proposed rule and the Statements of Consideration that result from the responses to public comments. Analyses supporting these responses to public comments will be conducted as needed to support an upcoming IM.

1.11 Unsaturated and Saturated Flow Under Isothermal Conditions (USFIC)

Staff continued the watershed modeling of upper Split Wash. The current work is primarily focused on analyses of subbasin areas to support scaling of parameters to the watershed grid. Field measurements and observations of surficial materials, in conjunction with existing GIS coverages of soil and bedrock lithology, are being incorporated directly into simulations using refined grids to evaluate concerns of runoff/runon during precipitation events leading to focusing of infiltration on the hillslopes. The primary impetus for this study is the potential for high infiltration in the upper watershed because of the combination of focusing of runoff into channels and the thin alluvial cover in those channels.

Staff completed field work at three analog sites for YM under future climate conditions. Based on the field observations, all three sites will be used to some extent as climate

11

-.................... -- . ..........

analogs to YM. Rainier Mesa and Timber Mountain (northwest of the Pahroc Range) are similar to the caprock environment at YM and 3-Springs Basin in the Kawich Range has similarities to both the caprock and hillslope environments at YM. Hydrologic studies relevant to shallow infiltration are published for Rainier Mesa and 3-Springs Basin. An important component of the work is to incorporate the effect of vegetation into the shallow infiltration modeling effort because the expected change in vegetation density and type under future climates is likely to have a significant effect on infiltration estimates. The field efforts helped to identify the relationships between soil cover depths, bedrock type, vegetation, and slope orientation with infiltration under cooler and wetter climate conditions. Based on field work conducted during earlier periods, Phinney Canyon in the Grapevine Mountains continues to be used as an analog site for YM.

Staff pursued the evaluation of dilution of contaminants in pumping wells. Simulations were performed to assess the impact of well-screen length on dilution. For these simulations, the amount of mass captured was recorded. Three screen lengths were considered-approximately 80,50, and 30m-with wells located at the approximate center of a plume. Because of the complex plume geometries that evolved, these well locations did not provide optimal plume capture. This was particularly true for the shallower screen lengths for which no capture was recorded in some simulations. As a result, the wells were moved to new locations, resulting in increased plume capture. Additional simulations are being performed to assess the effect of dispersivity on mass captured. Other simulations are planned to examine the impact of source mixing volume on mass captured. It is important to note that, because of the low pumping rate used and the approach adopted to simulate pumping wells, drawdowns in the region of the pumping cells are negligible.

Staff prepared a paper entitled Comparison of Numerical and Analytical Models of Unsaturated Flow Around Underground Openings, Considerations for Performance Assessments of Yucca Mountain, Nevada, as a High-Level Nuclear Waste Repository for presentation at the annual meeting of the Society for Mining, Metallurgy, and Exploration in Salt Lake City, Utah, February 28 to March 1, 2000. This paper is proposed in table 3 of this PMPR as a deliverable. Another manuscript, The Effect of Cavity Wall Irregularities on Seepage Exclusion from Horizontal Cylindrical Underground Openings (planned for publication in the Journal of Hydrology) is also proposed as a deliverable in table 3.

In addition, staff submitted an additional abstract, On the Origin of the Groundwater Temperature Variations near Yucca Mountain, for the AGU Fall 1999 meeting.

Staff continued development of the site-scale model for the SZ. The unstructured grid for this nonisothermal model is based on the DOE geological framework model. Initial calibration using MULTIFLO suggested residual errors in aquifer pressure as much as

1 10 m in some parts of the model. The calibrated model is currently being used to test the hypothesis that enhanced permeability alongthe fault zone and reduced permeability across the fault zone will improve model calibration.

Data reduction continued in the analysis of the May-June, 1995, aquifer pumping test at the C-Holes Complex. During this test, Well UE-25 C#3 was pumped at a rate of 1,550 m3/d for 10 d, while observation wells distributed over a large area, covering tens of square-kilometers, were monitored hourly. Unfortunately, the water-level responses in many observation wells are obscured by effects of surface barometric pressure fluctuations,

12

earth tides, and background aquifer pressure trends. Several methods for correcting these effects are being investigated. In most cases, it appears that noise in the response-topumping signal can be reduced from greater than 10 cm to no more than a few mm. Early results also indicate that much information regarding properties of the tuff aquifer and the overlying formations can be gained by analyzing water level responses to earth tides and barometric pressure. of these methods also allow for elucidation of UZ properties.

Staff continued to improve understanding of important features and processes that may affect groundwater flow along the alluvial portion of the groundwater flow path from YM. The process includes review of pertinent literature, data, and well logs and analysis of geophysical data collected earlier in the year.

In the next period, USFIC activities will include (i) participation in the GSA Meeting, October 25-28, 1999, in Denver, Colorado; (ii) continued investigation of models for seepage and dripping in underground cavities; (iii) sustained analysis of processes affecting deep percolation under present and future climate scenarios; (iv) continued analysis of aquifer pumping-test data from the C-Holes Complex at YM; and (v) continued development of a site-scale model for SZ flow.

1.12 Radionuclide Transport (RT)

Staff presented a poster on Uranium (VI) Sorption Behavior on Silicate Mineral Mixtures at the Seventh International Conference on the Chemistry and Migration Behavior of Actinides and Fission Products in the Geosphere (Migration '99), held in Lake Tahoe, Nevada, September 26-October 1, 1999. The poster presented experimental and modeling results of U sorption on mixtures of quartz and clinoptilolite. A paper titled Modeling Colloid Transport for Performance Assessment, coauthored by NRC and CNWRA staff, was presented by NRC staff. This paper presented TPA Version 3.2 sensitivity analyses and detailed sorption modeling with site-specific hydrochemistry to evaluate the potential effects of colloid transport of Pu and Am on repository performance. A trip report was prepared and submitted.

Staff prepared an invited presentation for the SSSA Annual Meeting to be held October 31November 5, 1999 in Salt Lake City, Utah. The presentation, the Role of Radionuclide Sorption in High-Level Waste Performance Assessment: Approaches for the Abstraction of Detailed Models, will describe the results from efforts undertaken as part of the RT KTI efforts to provide transport parameters for TPA Version 3.2, and discuss potential modifications in future revisions of the TPA code.

Staff continued preparation of the manuscript Technetium-99 Chemistry in Reduced Groundwaters: Implications for the Performance of a Proposed High-Level Nuclear Waste Repository at Yucca Mountain, Nevada, for presentation at the Materials Research Society Annual Meeting to be held in Boston, Massachusetts, November 29-December 3, 1999. Staff used NEA thermodynamic data to calculate speciation and solubility under sitespecific groundwater conditions at YM. Effects of hydrochemistry on Tc solubility and retardation parameters were investigated using sensitivity analyses with TPA Version 3.2. Staff also proposed and developed approaches for two modifications to TPA Version 4.0 code, including a sorption response surface and a colloid transport module.

13

Staff continued experiments investigating the sorption behavior of Tc. Batch sorption experiments under oxidizing conditions over a pH range of 3-9.5 continued, using an initial Tc-99 concentration of 3 x 10-6 molal and the zeolite mineral clinoptilolite (Na-form) as a substrate. Initial results suggest small amounts of Tc sorption, but uncertainties still need to be constrained. U sorption experiments on silicate mineral mixtures under elevated PCO., (i.e., PCO2 = 10-2 atm; 1% C0 2 ) conditions continued.

Staff continued preparations for experiments investigating the sorption and coprecipitation behavior of Np on calcite. Planning for experimental coprecipitation of calcite and Np is in the final stages. The experimental setup is complete, and can be set-up, run, and taken down, without leaking. Calibration of the syringe pump and other equipment used in the Np-calcite coprecipitation experiments is nearly complete, the final step before initiating experiments.

Staff began an investigation into the local bonding structure, via XAFS analysis at Brookhaven National Laboratory, of the uranyl ion adsorbed onto clinoptilolite and montmorillonite. A set of ion-exchanged and surface-adsorbed samples has been prepared at various uranyl loadings. Sample preparation included preparing the minerals (grinding, separating, and dissolving soluble impurity phases), developing an effective method for maintaining the desired PCO2, and performing the experiments. The adsorption experiments, which are currently under-way, are being monitored to ensure that sufficient uranyl ion is adsorbed for successful analysis by XAFS. XAFS data collection at Brookhaven will take place in early November.

Staff participated in the geochemical data exchange for groundwaters sampled from Nye County EWDP wells, sponsored by the USGS and Nye County, September 29, 1999, in Denver, Colorado. Staff also made preparations to participate in another sampling event at the Nye County EWDP wells November 8-15, 1999.

In the next period, staff will (i) complete TPA sensitivity analyses and Tc thermodynamic modeling for the MRS manuscript being prepared for the MRS Annual Meeting, (ii) attend the SSSA Annual Meeting to present sorption modeling results, (iii) work with staff associated with TSPAI KTI to implement proposed sorption response surfaces for TPA 4.0, (iv) continue to revise reports on ion exchange and surface complexation, and (v) pursue sorption experiments on alluvium minerals and redesign Tc sorption experiments to reduce sources of uncertainty.

1.13 Review of the Draft Environmental Impact Statement (DEIS)

Staff and external consultants continued review of the DOE DEIS for the proposed repository. The CNWRA project manager and members of the external consultant review team participated in public meetings in Pahrump, Nevada, and conducted YM site visits September 29-October 1, 1999. The CNWRA project manager and selected CNWRA staff and consultants participated in an NRC/DOE technical exchange on the DEIS at NRC Headquarters. With the exception of the consultant assigned to review socioeconomic aspects of the DEIS, CNWRA technical staff and consultants completed their evaluative reviews and submitted their comments for compilation. Completion of the socioeconomic review awaits receipt of a DOE compact disk containing socioeconomic analysis data. The CNWRA project manager participated in DEIS review teleconferences with NRC staff.

14

In the next period, the staff will complete compilation of DEIS evaluative review comments and submit them to NRC as Draft Environmental Impact Statement Evaluative Review Comments and participate in a DOE public meeting in Caliente, Nevada.

1.14 Public Outreach

Discussions were held with a risk communications expert about conducting a one or two day course at the CNWRA. Although a date for this course has not been established, it is hoped that it can be conducted by the end of period 5.

In the next period, efforts will continue on establishing a schedule and agenda for the short course on risk communications.

1.15 Development of the Yucca Mountain Review Plan (YMRP)

YMRP development continued in collaboration with the NRC staff. KTI and ISI staff leads continued preparation of the model abstraction portions of the plan, and some ISI sections entered the internal CNWRA review process. Work proceeded on the preclosure and QA portions of the plan. Preparations began for a presentation to the ACNW on YMRP development to be given during the next period.

In the next period, staff will participate in a presentation to the ACNW using an expanded outline of the YMRP with example AC and RMs added and continue development of Revision 0 of the YMRP.

1.16 Tank Waste Remediation System (TWRS)

In subtask 1.2, staff addressed the NRC comments on Process Hazards and Safety Issues for TWRS-P, Volume II, Auxiliary Support Systems and Process Control Systems. Change pages were accepted on October 12, 1999. Staff initiated work on Technical Review Report on Ultrafilters. Also, staff is reformatting the Survey of Solidification Technologies report to NUREG/CR format. Copyright permissions for figures and tables have been requested from authors and publishers.

In subtask 1.4, staff started work on the Classification and Categorization of Process Safety Issues.

In subtask 1.6, staff initiated development of a spreadsheet model of the pretreatment process, based on mass-balance considerations, using reported waste feed envelope compositions and reported or assumed concentration factors or decontamination factors.

In subtask 2.1, staff attended two single-discipline design review meetings on the TWRS-P project. The meetings were held on October 12, 1999, in Richland, Washington. Topics discussed were LAW Melter Consumables, LAW Melter Overpack Transport and Disposable Packaging, and Process Recycle Streams. A trip report on this meeting has been transmitted to the NRC. Staff provided comments to the NRC on the River Protection Project Waste Treatment Plant Explosive Hazards Evaluation Report on October 12, 1999. Staff completed review of the Topical Report on the Management of Risks Posed by Explosive Hazards Present at the River Protection Project-Waste Treatment Plant,

15

providing a review of hydrogen explosive hazards. Comments were provided to the NRC on October 13, 1999.

Staff submitted the FY2000 operations plan to the NRC.

In the next period, in subtask 1.2, staff will continue work on reformatting the Survey of Solidification Technologies report and the technical review report on Ultrafilters. In subtask 1.4, staff will continue work on the Classification and Categorization of Process Safety Issues. In subtask 1.6, development of a spreadsheet model for the TWRS waste pretreatment will continue. In subtask 2. 1, staff plan to attend design review meetings on the TWRS-P project October 26-28 and November 16, 1999.

1.17 Dry Transfer System (DTS)

Development of the DTS draft SER was continued during this period, making use of the CNWRA and SwRI staffs and a consultant. The consultant visited the CNWRA during this period to work with the CNWRA staff on the development of the DTS draft SER. Significant progress was made regarding development of this draft SER.

In the next period, the staff will continue the development of the draft SER.

1.18 Centralized Interim Storage Facility (CISF)

The DOE response to the SFPO RAI on the HI-STAR and HI-STORM topical report for high seismic sites was received. The review of this response was initiated during this period.

In the next period, the staff will continue the review and evaluation of the DOE response to the SFPO RAI on the HI-STAR and HI-STORM topical report for high seismic risk sites. The staff will also initiate the resolution of the NRC comments on CISF draft AR.

1.19 Private Fuel Storage Facility (PFSF)

The staff continued the review of the revised seismic design reports during this period. One PFSF staff member visited the NRC Headquarters to work with the NRC staff on Contention on Accident Analysis. Extensive interactions took place between the NRC and the CNWRA staffs on revised seismic design reports and various contentions.

In the next period, the staff plans to review and evaluate the revised seismic design reports and assist the NRC staff on ASLB hearing activities. Also two PFSF staff will visit the site at Utah, participate in the NRC/PFSF meeting on revised seismic design at Salt Lake City, Utah, and meet the Air Force staff at Hill Air Force Base to discuss the Aircraft Accident issues.

2 MANAGEMENT ISSUES

None to report.

16

3 MAJOR PROBLEMS

None to report.

4 SUMMARY OF SCHEDULE CHANGES

Schedule changes for IMs are included in table 3. Completed deliverables are noted in table 4.

5 SUMMARY OF FINANCIAL STATUS

Table 5 summarizes the CNWRA financial status in the context of authorized funds. Total

commitments are $386,852. The appendix lists planned and actual costs to date, as well as variances

between these, without allowance for fee, on both a per-period and a cumulative basis. These data

do not include commitments. Pertinent financial information is provided for the DWM JC, including COPS, EQA, DEIS, Public Outreach, YMRP and ten KTIs, TWRS JC, DTS JC, CISF JC, and PFSF

JC. The planned costs per period are based on the revised spending plans contained in the FY2000

OPS recently conveyed to the NRC.

It should be noted that the current spending estimates in all JCs are based on the assumption that

staffing is consistent with the aggressive CNWRA hiring plan. A revised staffing plan was delivered

as part of the CNWRA Management Plan, Revision 7, Change 0. Despite focused efforts on

recruitment, current staffing remains below authorized levels. The CNWRA will submit a series of

tables outlining the staff availability in FY2000 during the NRC/CNWRA Management meeting scheduled for October 29, 1999.

Period I FY2000 CNWRA composite expenditures declined 22.1 percent from the last period in

FY1999, and this aggregate of all JCs was overspent by $64,663 or -6.0 percent. When compared

with period 13 of FY1999, only the DWM JC evidenced lower spending levels, while the TWRS,

DTS, CISF, and PFSF JCs showed higher levels.

Expenditures on SwRI labor, consultants, and subcontractors as a proportion of composite spending

on all JCs were 22.1 percent. Expense of consultants and subcontractors as a fraction of composite spending on all JCs was 14.3 percent. The CNWRA continues to enhance, where appropriate,

participation of consultants and subcontractors in the conduct of CNWRA work.

As shown in table 1, the CNWRA has 56 staff members. The available pool of approved consultants and subcontractors is 8 1.

This FYTD, no capital or sensitive equipment was purchased with NRC funds (other than overhead, general and administrative expenses, and fees).

The DWM JC was overspent by $109,318 or - 11.7 percent. Overall expenditures decreased about

25.2 percent from the previous period as costs rose in the ENFE KTI and the DEIS, but declined in

COPS and the IA, SDS, CLST, TEF, RDTME, TSPAI, ARDR, USFIC, and RT KTIs. In various

meetings with NRC senior management staff and other interested parties, CNWRA senior

management staff continue to discuss current and expected levels of spending, aggressive

recruitment efforts for core staff, and effective engagement of consultants and subcontractors. The

CNWRA will revise its estimate of carryover monies in the second period of FY2000.

17

The cost variance for COPS was -31.4 percent: -35.8 percent for the Management, Planning, and Computer Support subtask (158) and - 8.9 percent for the QA subtask (159). The negative variance resulted from delayed payment to consultants and subcontractors, increased travel and time related to staff s professional development, and costs related to the development and submittal of operations plans. In the next period, spending in subtask 158 is expected to decline, but may still exceed the estimated amount. CNWRA management continues to encourage eligible staff to participate in professional development activities. In subtask 159, spending increased in period 1 relative to last period because of QA services and consultant costs associated with the modification of QA documents and other related QA activities. Spending in the first period of FY2000 is anticipated to follow estimated spending.

The cost variance for EQA was 70.5 percent. Spending this period in subtask 331 reflected the start up activities and preparation for re-establishing NRC observation audit teams. In the second period of the new FY, spending in subtask 331 is expected to increase due to the two audits that will be observed and the associated reports that will have to be written.

The cost variance for the IA KTI was -24.3 percent. This overspending was a result of late receipt and payment of outstanding charges from FY 1999.

The cost variance for the SDS KTI was - 19.2 percent. This overspending was the result of late receipt and payment, principally for consultants work in FY1999.

The cost variance for the ENFE KTI was -59.0 percent. This variance resulted mainly from consultant and subcontractor invoices from FY 1999 that were paid during period 1 of FY2000.

The cost variance for the CLST KTI was - 34.6 percent. The variance resulted from the start of new experimental programs. It is anticipated that once this startup phase is completed, the project spending will be in line with budgeted funds.

The cost variance for the TEF KTI was - 16.4 percent. This cost overrun is due to focused effort in the areas of mountain/drift-scale thermohydrological modeling and ongoing dripping laboratory experiments. Another factor that also contributed to this cost overrun is the allocation of funding for period I of FY2000 at a level which is about 93 percent of the average per period allocated funding for FY2000 for TEF KTI. Although the cost overrun will continue for the next few periods, the FY2000 total expenditures are expected to converge to the FY2000 allocation.

The cost variance for the RDTME KTI was -8.7 percent. This cost overrun is due to allocation of funding for period 1 of FY 2000 at a level which is about 80 percent of the average per period allocated funding for FY2000 for RDTME KTI. The FY 2000 total expenditures are expected to converge to the FY2000 allocation.

The cost variance for the TSPAI KTI was - 30.7 percent. Spending decreased substantially from the last period of FY1999 because external QA and YMRP development are now charged to separate accounts. However, the actual spending still exceeded projected spending because a number of invoices from the external review of the TPA Version 3.2 code were carried over from FY 1999. The spending is expected to decrease substantially in the next period.

18

The cost variance for the ARDR KTI was -8.9 percent. Spending should continue at the same pace during the next two periods in order to complete the responses to the public comments on 10 CFR Part 63.

The cost variance for the USFIC KTI was 6.7 percent. There are existing commitments for travel and consultants. As these commitments are paid, the variance is expected to diminish.

The cost variance for the RT KTI was - 80.3 percent. Costs for consultants and subcontractors from FY1999 posted to this account during period 1 of FY2000 and costs associated with starting up new laboratory experiments are responsible for this variance.

The cost variance for review of the DEIS was -41.9 percent. This overspending was the result of the concentrated effort by CNWRA staff and external consultants to complete their reviews of the DEIS. The overspending situation is expected to continue through the next period as consultant billings are paid, but spending will then decrease substantially as DEIS review activity slows. This project is ultimately expected to have net underspending, since the level of required travel and consultant support for public meetings is expected to be less than was envisioned in the original statement of work.

The cost variance for Public Outreach was 100 percent underspent. No charges were made to this project during this period.

The cost variance for Development of the YMRP was 78.6 percent. The large value of this variance is primarily due to priority being given by the project manager to review of the YM DEIS and consultant billing that has not yet been received. Although expenditures are expected to increase in the next period as less effort is spent on review of the DEIS, the underspending situation is expected to persist.

The cost variance for the TWRS project was 20.5 percent. The variance is expected to decrease as new activities accelerate.

The cost variance for the DTS project was 24.7 percent. This cost underrun is primarily due to lagging charges from a consultant. The FY2000 total expenditures are expected to converge to the FY2000 allocation.

The cost variance for the CISF project was 45.1 percent. This cost underrun is due to lack of assignment from the NRC and lagging charges from a consultant.

The cost variance for the PFSF project was 42.6 percent. This cost underrun is because of delay in receiving the final seismic design reports from the applicant that may cause rescheduling of the delivery date of PFSF SER supplement.

19

Table 1. CNWRA Core Staff-Current Profile and Hiring Plan* (Period 1)

Positions Open Expertise/Experience Current No. Professional Staff FY2000

ADMINISTRATION 4 H.GARCIA, W.PATRICK, J.RUSSELI B.SAGAR

CHEMICAL PROCESSING 2 VJAIN, D.DARUWALLA ENGNGJPHYS. CHEM.

CODE ANALYSIS/DEVELOPMENT 2 RJANETZKE, R.MARTIN

DATA MANAGEMIENTWPROCESSING, I P.MALDONADO INCLUDING FINANCIAL

DOSE/RISK/HAZARD ANALYSIS 0

ELECTROCHEMISTRY I G.CRAGNOLINO

ENGINEERING 2 R.CHEN, G.OFOEGBU GEOLOGY/GEOLOGICAL ENGNG.

ENVIRONMENTAL SCIENCES 1 P.LaILANTE

GEOCHEMISTRY 8 P.BERTETTI, L.BROWNING. W.MURPHY, R.PABALAN, E.PEARCY, J.PRIKRYL. D.TURNER, M.NUGENT

GEOHYDROLOGY/HYDROGEOLOGY 5 D.FARRELL, R.FEDORS, R.GREEN, M.HILL, 2 ...WINTERLE

GEOLOGY 3 P.LAFEMINA, L.McKAGUE. M.MIKLAS

HYDROLOGIC TRANSPORT 3 A.ARMSTRONG, D.HUGHSON, SPAINTER

INFORMtATION MANAGEMENT 0 SYSTEMS ,,

MATERIAL SCIENCES 5 S.BROSSIA, D.DUNN. O.MOGHISSI, Y-M.PAN, N.SRIDHAR

MECHANICAL, I D.GUTE INCLUDING DESIGN & FABRICATION

MINING ENGINEERING I S-M.HSIUNG

NUCLEAR ENGINEERING I M.SMITH

OPERATIONAL HEALTH PHYSICS I J.WELDY I

PERFORMANCE ASSESSMENT 3 S.MOHANTY, OPENSADO-RODRIGUEZ, 2 G.WITrMEYER

QUALITY ASSURANCE I B.MABRITO

RADIOISOTOPE GEOCHEMISTRY I D.PICKETT

ROCK MECHANICS, 3 A.CHOWDHURY, A.GHOSH, B.DASGUPTA INCLUDING CIVILJSTRUC. ENGNG.

SOURCE-TERM/SPENT FUEL DEGRAD. I L.YANG

STRUCTURAL GEOLOGY" 3 D.FERRILL, D.SIMS, J.STAMATAKOS SEISMO-TECTONICS

SYSTEMS ENGINEERING 1 P MACKIN

VOLCANOLOGY/IGNEOUS 2 C.CONNOR, B.HILL PROCESSES _._1_111

[TOTAL -56----------- 568

* See staffing plan for details

20

Table 2. CNWRA Core Staff-Summary by Area of Concentration (Period 1)

Positions Area of Concentration Actual Planned Open

ADMINISTRATION, QUALITY ASSURANCE, AND 6 7 1 INFORMATION MANAGEMENT

GEOCHEMISTRY 9 9 0

HYDROLOGY/CLIMATOLOGY 8 9 1

MATERIAL SCIENCES 7 9 2

MECHANICAL, CHEMICAL. NUCLEAR, AND SYSTEMS 5 5 0 ENGINEERING

PERFORMANCE ASSESSMENT 6 10 4

ROCK MECHANICS, MINING, AND GEOLOGICAL 6 6 0 ENGINEERING

STRUCTURAL GEOLOGY, TECTONICS, AND VOLCANISM 9 9 0

TOTAL . 56 64 8

21

Table 3. Summary of Schedule Changes (Period 1)

MILESTONE ORIGINAL REVISED NUMBER TYPE DESCRIPTION DATE DATE RATIONALE FOR CHANGE

01402.331.010 IM Observation Report on 11/26/1999 Milestone number assigned as indicated in the U.S. Department of Energy Yucca FY2000 Operations Plans Mountain Integrated Site Model Audit

01402,331.011 IM Observation Report on Waste 12/17/1999 Milestone number assigned as indicated in the Package U.S. Department of Energy FY2000 Operations Plans Yucca Mountain Audit

01402.331.012 IM Observation Report on Biosphere 12/27/1999 Milestone number assigned as indicated in the U.S, Department of Energy Yucca FY2000 Operations Plans Mountain Audit

01402.561.070 IM Thermodynamic Interpretations of 02/04/2000 Proposed New Milestone Chemical Analyses of Water from Yucca Mountain, Nevada

01402.561.080 IM An Archeological Site at Akrotiri, 02/11/2000 Proposed New Milestone Greece, as a Natural Analog for Radionuclide Transport: Implications for Validity of Performance Assessments

01402.771.030 IM Analyses Supporting Responses to 10/30/1999 01/31/2000 Date revised to meet new schedule for Public Comments on Draft HLW completing 10 CFR 63 Rulemaking

01402,861.050 IM Comparison of Numerical and 01/21/2000 Proposed New Milestone Analytical Models of Unsaturated Flow Around Underground Openings Considerations for Performance Assessments of Yucca Mountain, Nevada, as a High-Level Nuclear Waste Repository

01402,861.060 IM The Effect of Cavity Wall 01/07/2000 Proposed New Milestone Irregularities on Seepage Exclusion from Horizontal Cylindrical Underground Openings

Table 4. Deliverables (Period 1)

ORIGINAL ACTUAL

MILESTONE COMPLETION REVISED # OF COMPLETION REASON

[ NUMBER TYPE DESCRIPTION DATE DATE REVISIONS DATE (IF DELAYED)

01402.158.040 MM FY2000 CNWRA Operations Plans 10/29/1999 10/2211999

01402.661.940 IM Thermal-Hydrologic Laboratory Testing 09/30/1999 09/29/1999

-Journal Paper or Presentation

01402.761.930 IM Strategic Plan for TPA Development 08/31/1999 10/01/1999 1 09/30/1999 Additional time was

through FY2002 needed to address CNWRA internal review comments. This IM was left off inadvertently in the FY2000 Operations Plans. The IM number will be 01402.761,090.

Table 5. Financial Status (Period 1)

Funds Funds Funds

Project Names Authorized Costed to Date Uncosted Commitments

COPS 3,795,302 3.576,956 218,346 36,920 EQA 73,112 7,139 65,972 0 IA 1,601.120 1,541,415 59.705 38.367 SDS 1,981,275 1,896,040 85,235 37,819 ENFE 1,895,049 1.819,640 75,409 105,160 CLST 2.135,233 2,020.953 114.280 8,454 TEF 1,420.941 1,343,074 77,868 19,454 RDTME 1,528,914 1,397,194 131,719 28,327 TSPAI 3,796,839 3.616.019 180,820 39.829 ARDR 418,024 393,864 24,161 4,000 USFIC 2,443,833 2,275,469 168,364 9,403 RT 1.396,689 1,348.133 48,556 12.857 DEIS 216,470 132,224 84,246 1,850 PO 25,080 0 25,080 0 YMRP 355,230 25,126 330,104 0

DWM Costs 23.083,109 21,393,245 1,689,864 DWMI Award Fee 1,196,006 849,751 346,255 DWM Base Fee 923,324 834,579 88,745

TOTAL DWM 25,202,439 23,077,575 2,1241865 342,440 TWRS Costs 1,610,314 1,546,310 64,004 1,000 TWRS Award Fee 93,654 77,449 16,205 TWRS Base Fee 64,413 62.421 1,992

TOTAL TWRS 1,768.381 1.686,180 82.201 1,000 DTS Costs 434.853 423,308 11.545 0 DTS Award Fee 23,323 14,293 9,030 DTS Base Fee 17,394 16,717 677

TOTAL DTS 475.570 454.319 21,251 0 CISF Costs 376,720 350,129 26,591 0 CISF Award Fee 24,338 19,124 5,214 CISF Base Fee 15,069 13,921 1,148

TOTAL CISF 416.127 383,173 32,954 0 PFSF Costs 451,533 450,047 1,486 43,412 PFSF Award Fee 26,581 11,737 14,844 PFSF Base Fee 18,061 16.984 1,077

TOTAL PFSF 496.175 478,768 17,407 43,412 Grand Total 28,358,693 26,080,015 2,278,678 386,852 Note: All authorized funds have been allocated through modification #131. Funds costed to date for each award fee program represent the award fee for FY 1998 and interim for FY 1999. Funds uncosted for each award fee program represent the award fee reserved from the last authorizations based on the Operations Plans for FY1999.

24

Table 6. Private Fuel Storage Facility License Fee Cost Recovery Status (Period 1)

LICENSE FEE COST RECOVERY STATUS

JOB CODE: J5226

TITLE:

PERIOD:

Private Fuel Storage Facility

September 25, 1999-October 22, 1999

Notes: Costs include 4 percent actual base fee plus FY 1998 award fee in the amount of $6,827.

Costs include FY1999 interim award fee in the amount of $4,910.

TAC OR INSPECTION TASK DOCKET IDENTIFICATION PERIOD CUMULATIVE COSTS

NUMBER FACILITY NAME NUMBER NUMBER COSTS CONTRACT TO DATE

01405.041 Private Fuel Storage 72-22 L22462 $24,185.88 $477,677.89

_ Facility I I

APPENDIX Planned and Actual Costs,

and Cost Variances Period 1-FY2000

CNWRA COMPOSITE T O T A L E S T IM A T E C O S T .........

ITEM 0! 02 03 04 05 06 07 08 09 10 11 12 13 Total

EstPdCost 1,083,678 1,070,856 916,344 931,128 1,088,180 1,035,964 1,029,712 1,029,912 1,201,753 1,201,198 1,200,811 1,052,648 1,028,995 1,083,678

Act Pd Cost 1,148,341 0 0 0 0 0 0 0 0 0 0 0 0 1,148,341

Variance, $ (64,663) 0 0 0 0 0 0 0 0 0 0 0 0 (64,663)

Variance, % -6,0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% -6.0%

Est FY Cumul 1,083,678 2,154,534 3,070,878 4,002,006 5,090,186 6,126,150 7,155,862 8,185,774 9,387,527 10,588,725 11,789,536 12,842,184 13,871,179 .........

Act FY Cumut 1,148,341 0 0 0 0 0 0 0 0 0 0 0 0

% Complete 8.3% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

Cumul Var, $ (64,663) 0 0 0 0 0 0 0 0 0 0 0 0

Cumul Var, % -6.0% 0.0% 0.0% 0.0% 0.0% 0,0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

DIVISION OF WASTE MANAGEMENT (DWM) 1402-000

ITEM 01 02 03 04 05 06 07 08 09 10 11 12 13 Total

Est Pd Cost 932,008 927,059 810,641 845.713 986,474 938,239 938,144 938,250 1,110,632 1,110,767 1,110,602 962,027 938,087 932,008

Act Pd Cost 1,041,326 0 0 0 0 0 0 0 0 0 0 0 0 1,041,326

Variance, $ (109,318) 0 0 0 0 0 0 0 0 0 0 0 0 (109,318)

Variance, % -11.7% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% -11.7%

Est FY Cumul 932,008 1,859,067 2.669,708 3,51.1,421 4,501,895 5,440,134 6,378,278 7,316,528 8,427,160 9,537,927 10,648,529 11,610,556 12,548,643

Act FY Cumul 1,041,326 0 0 0 0 0 0 0 0 0 0 0 0

% Complete 8.3% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

Cumul Var, $ (109,318) 0 0 0 0 0 0 0 0 0 0 0 0

Cumul Var, % -11,7% 0.0% 00.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

CNWRA OPERATIONS (COPS) 1402-150

ITEM 01 02 03 04 05 06 07 08 09 10 11 12 13 Total

Est Pd Cost 134,053 134,054 112,122 112,125 134,829 134,833 134,829 134,835 194,873 194,882 194.871 158,588 134,828 134,053

Act Pd Cost 176,208 0 0 0 0 0 0 0 0 0 0 0 0 176,208

Variance, $ (42,155) 0 0 0 0 0 0 0 0 0 0 0 0 (42,155)

Variance, % -31.4% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% -31.4%

Est FY Cumul 134,053 268,107 380,229 '492,354 627,183 762,016 896,845 1,031,680 1,226,553 1,421,435 1,616,306 1,774,894 1,909,722

Act FY Cumul 176,208 0 0 0 0 0 0 0 0 0 0 0 0

% Complete 9.2% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

Cumul Var,$ (42,155) 0 0 0 0 0 0 0 0 0 0 0 0

Cumul Var. % -31.4% 0.0%" 0.0% 0.0% 0.0% 0.0% . 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

EXTERNAL QUALITY ASSURANCE (EQA) 1402-331

ITEM 01 02 03 04 05 06 07 08 09 10 I1 12 13 Total

Est Pd Cost 24,213 24,213 20,826 20,828 24,213 24,215 24,212 24,216 27,428 27,434 27,426 24.216 24.206 24.213

Act Pd Cost 7,139 0 0 0 0 0 0 0 0 0 0 0 0 7,139

Variance, $ 17,074 0 0 0 0 0 0 0 0 0 0 0 0 17,074

Variance, % 70.5% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 70.5%

IEsitFY Cumul 24,213 48,426 69,252 90,080 114,293 138,508 162,720 186,936 214,364 241.798 269,224 293,440 317,646 . _ _

Act FY Cumul 7,139 0 0 0 0 0 0 0 0 0 0 0 0

% Complete 2.2% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

Cumul Vat, $ 17,074 0 0 0 0 0 0 0 0 0 0 0 0

Cumul Var, % 70.5% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%.. . 0.0% 0.0% 00% 0.0% 0.0% 0.0%

IGNEOUS ACTIVITY (IA) 1402-460

ITEM 01 02 03 04 05 06 07 08 09 10 11 12 13 Total

Est Pd Cost 36,787 36,787 30,456 30,461 36,785 36,790 36,782 36,790 42,368 42,377 42,366 36,791 36,774 36,787

Act Pd Cost 45,721 0 0 0 0 0 0 0 0 0 0 0 0 45,721

Variance, $ (8,934) 0 0 0 0 0 0 0 0 0 0 0 0 (8,934)

Variance, % -24.3% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% -24.3%

Est FY Cumul 36,787 73,574 104,030 134,491 171,276 208,066 244,848 281,638 324,006 366,383 408,749 445,540 482,314

Act FY Cumul 45,721 0 0 0 0 0 0 0 0 0 0 0 0

% Complete 9.5% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

Cumul Var, $ (8,934) 0 0 0 0 0 0 0 0 0 0 0 0

Cumul Var, % -24.3% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

STRUCTURAL DEFORMATION AND SEISMICITY (SDS) 1402-470

ITEM 01 02 03 04 05 06 07 08 09 10 11 12 13 Total

Est Pd Cost 51,038 51,040 42,932 42,938 51,035 51,041 51,034 51,044 58,686 58,699 58,685 51,046 51,029 51,038

Act Pd Cost 60,861 0 0 0 0 0 0 0 0 0 0 0 0 60,861

Variance, $ (9,823) 0 0 0 0 0 0 0 0 0 0 0 0 (9,823)

Variance, % -19.2% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% -19.2%

Est FY Cumul 51,038 102,078 145,010 187,948 238,983 290,024 341,058 392,102 450,788 509,487 568,172 619,218 670,247

Act FY Cumul 60,861 0 0 0 0 0 0 0 0 0 0 0 0

% Complete 9.1% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

Cumul Var, $ (9,823) 0 0 0 0 0 0 0 0 0 0 0 0

Cumul Var. % -19.2% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

EVOLUTION OF THE NEAR-FIELD ENVIRONMENT (ENFE) 1402-56

ITEM 01 02 03 04 05 06 07 08 09 10 11 12 13 Total

Est Pd Cost 64,477 64,478 54.913 54,915 64,475 64,478 64,474 64,478 73,858 73.866 73,856 64,482 64,467 64,477

Act Pd Cost 102,508 0 0 0 0 0 0 0 0 0 0 0 0 102,508

Variance, $ (38,031) 0 0 0 0 0 0 0 0 0 0 0 0 (38,031)

Variance, % -59.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0,0% 0.0% 0.0% 0.0% 0.0% 0.0% -59.0%

Est FY Cumul 64,477 128.955 183,868 238,783 303,258 367,736 432,210 496.688 570,546 644,412 718,268 782,750 847,217

Act FY Cumul 102,508 0 0 0 0 0 0 0 0 0 0 0 0

% Complete 12.1% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

Cumul Var, $ (38,031) 0 0 0 0 0 0 0 0 0 0 0 0

Cumul Vat, % -59.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.00 0.0% 0.0%

CONTAINER LIFE AND SOURCE TERM (CLST) ,,, _1402-570

ITEM 01 02 03 04 05 06 07 08 09 10 11 12 13 Total

Est Pd Cost 87,167 87,169 73,583 73,587 87,166 87,170 87,166 87,171 100,372 100,379 100,370 87,172 87,167 87,167

Act Pd Cost 117,352 0 0 0 0 0 0 0 0 0 0 0 0 117,352

Variance, $ (30,185) 0 0 0 0 0 0 0 0 0 0 0 0 (30,185)

Variance, % -34.6% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0,0% 0.0% 0.0% 0.0% 0.0% 0.0% -34.6%

Est FY Cumul 87,167 174,336 247,919 321,506 408,672 495,842 583,008 670,179 770,551 870,930 971,300 1,058,472 1,145,639

Act FY Cumul 117,352 0 0 0 0 0 0 0 0 0 0 0 0

% Complete 10.2% 0.0% 0.0% 0.0% 0,0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

Cumul Var, $ (30,185) 0 0 0 0 0 0 0 0 0 0 0 0

Cumul Var, % -34.6% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

THERMAL EFFECTS ON FLOW (TEF) 14 02 -660 ....... ... ... ................

ITEM 01 02 03 04 05 06 07 08 09 10 11 12 13 -Total

Est Pd Cost 41,829 41,830 38,373 38,378 45,013 45,018 45,012 45,019 51,276 51,283 51,273 45,020 45,010 41,829

Act Pd Cost 48,680 0 0 0 0 0 0 0 0 0 0 0 0 48,680

Variance, $ (6,851) 0 0 0 0 0 0 0 0 0 0 0 0 (6,851)

Variance, % -16.4% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0,0% 0.0% 0.0% 0.0% 0.0% -16.4%

Est FY Cumul 41,829 83,659 122,032 160,410 205,423 250,441 295,453 340,472 391,748 443,031 494,304 539,324 584,334

Act FY Cumul 48,680 0 0 0 0 0 0 0 0 0 0 0 0

% Complete 8.3% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

Cumul Var, $ (6,851) 0 0 0 0 0 0 0 0 0 0 0 0

Cumul Var % -16.4% 0.0% 0.0% 0.0% 0.0% 0.0% 00% 0.0% 0.0% 0.0% 0.0% 0.00/0 06.0%

REPOSITORY DESIGN AND THERMAL-MECHANICAL EFFECTS (RDTME) 1402-670

ITEM 01 02 03 04 05 06 07 08 09 10 11 12 13 Total

Est Pd Cost 69,482 69,483 58,857 80,786 91,405 91,411 91,405 91,412 101,982 101,990 101,980 91,414 91,400 69,482

Act Pd Cost 75,511 0 0 0 0 0 0 0 0 0 0 0 0 75,511

Variance, $ (6,029) 0 0 0 0 0 0 0 0 0 0 0 0 (6,029)

Variance, % -8.7% 0.0%. 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% -8.7%

Est FY Cumul 69,482 138,%5 197,822 278,608 370,013 461,424 552,829 644,241 746,223 848,213 950,193 1,041,607 1,133,007

Act FY Cumul 75,511 0 0 0 0 0 0 0 0 0 0 0 0

% Complete 6.7% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

Cumul Var, $ (6,029) 0 0 0 0 0 0 0 0 0 0 0 0

Cumul Var, % -8.7% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%. 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

TOTAL SYSTEM PERFORMANCE ASSESSMENT AND INTEGRATION (TSPAI) 1402-760

ITEM 01 02 03 04 05 06 07 08 09 10 11 12 13 Total

Est Pd Cost 118,702 113,734 98,060 109,681 131,276 131,286 131,275 131,287 149,616 149,632 149,612 131,292 131,275 118,702

Act Pd Cost 155,162 0 0 0 0 0 0 0 0 0 0 0 0 155,162

Variance, $ (36,460) 0 0 0 0 0 0 0 0 0 0 0 0 (36,460)

Variance, % -30.7% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% -30.7%

Est FY Cumul 118,702 232,436 330,496 440,177 571,453 702,739 834,014 966,301 1,114,917 1,264,549 1,414,161 1,545,453 1,676,728

Act FY Cumul 155,162 0 0 0 0 0 0 0 0 0 0 0 0

% Complete 9.3% 0.0% 0.0% 0.0% 0.0% 0,0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

Cumul Var, $ (36,460) 0 0 0 0 0 0 0 0 0 0 0 0

Cumul Var, % -30.7% 0.0% 0.0% 0,0% 0.0% 0.0% 5.' 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

ACTIVITIES RELATED TO DEVELOPMENT OF THE NRC HIGH-LEVEL WASTE REGULATIONS TECHNICAL ASSISTANCE (ARDR) 1402-770

ITEM 01 02 03 04 05 06 07 08 09 10 11 12 13 Total

Est Pd Cost 13,246 13,247 10,677 12,028 14,893 14,900 14,893 14,900 16,930 16,937 16,929 14,900 14,893 13,246

Act Pd Cost 14,423 0 0 0 0 0 0 0 0 0 0 0 0 14,423

Variance, $ (1,177) 0 0 0 0 0 0 0 0 0 0 0 0 (1,177)

Variance, % -8.9% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% -8.9%

Est FY Cumul 13,246 26,493 37,170 49,198 64,091 78,991 93,884 108,784 125,714 142,651 159,580 174,480 189,373

Act FY Cumul 14,423 0 0 0 0 0 0 0 0 0 0 0 0

% Complete 7.6% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0,0% 0.0% 0.0% 0.0%

Cumul Var, $ (1,177) 0 0 0 0 0 0 0 0 0 0 0 0

Cumul Var, % -8.9% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% ____.....

UNSATURATED AND SATURATED FLOW UNDER ISOTHERMAL CONDITIONS (USFIC) 1402-860

ITEM 01 02 03 04 05 06 07 08 09 10 11 12 13 Total

Est Pd Cost 76,565 76,570 77,509 77,520 89,532 89,546 89,532 89,546 101,785 101,800 101,783 89,549 89,528 76,565

Act Pd Cost 71,447 0 0 0 0 0 0 0 0 0 0 0 0 71,447

Variance, $ 5,118 0 0 0 0 0 0 0 0 0 0 0 0 5,118

Variance, % 6.7% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 6.7%

Est FY Cumul 76,565 153,135 230,644 308,164 397,696 487,242 576,774 666,320 768,105 869,905 971,688 1,061,237 1,150,765

Act FY Cumul 71,447 0 0 0 0 0 0 0 0 0 0 0 0

% Complete 6.2% 0,0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

Cumul Var, $ 5,118 0 0 0 0 0 0 0 0 0 0 0 0

Cumul Var, % 6.7% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

RADIONUCLIDE TRANSPORT (RT) 1402-870

ITEM 01 02 03 04 05 06 07 08 09 10 11 12 13 Total

Est Pd Cost 40,573 40,575 35,306 35,311 40,568 40,576 40,566 40,577 46,193 46,206 46,193 40,580 40,565 40,573

Act Pd Cost 73,142 0 0 0 0 0 0 0 0 0 0 0 0 73,142

Variance, $ (32,569) 0 0 0 0 0 0 0 0 0 0 0 0 (32,569)

Variance, % -80.3% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% -80.3%

Est FY Cumul 40,573 81,148 116,454 151,765 192,333 232,909 273,475 314,052 360,245 406,451 452,644 493,224 533,789

Act'FY"Cumul 73,142 0 0 0 0 0 0 0 0 0 0 0 0

% Complete 13.7% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

Cumul Var, $ (32,569) 0 0 0 0 0 0 0 0 0 0 0 0

Cumul Var, % -80.3% 0U 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

REVIEW OF THE YUCCA MOUNTAIN DRAFT ENVIRONMENTAL IMPACT STATEMENT (DEIS) 1402-930

ITEM 01 02 03 04 05 06 07 08 09 10 11 12 13 Total

Est Pd Cost 47,968 47,969 48,321 48,442 48,319 0 0 0 0 0 0 0 0 47,968

Act Pd Cost 68,045 0 0 0 0 0 0 0 0 0 0 0 0 68,045

Variance, $ (20,077) 0 0 0 0 0 0 0 0 0 0 0 0 (20,077)

Variance, % -41.9% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% -41.9%

Est FY Cumul 47,968 95,937 144,258 192,700 241,019 241,019 241,019 241,019 241,019 241,019 241,019 241,019 241,019

Act FY Cumul 68,045 0 0 0 0 0 0 0 0 0 0 0 0

% Complete 28.2% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

Cumul Var, $ (20,077) 0 0 0 0 0 0 0 0 0 0 0 0

Cumul Var, % -41.9% 0.0 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0..0% 00% 0.0% 0.0% 0.0% 0_0

PUBLIC OUTREACH

1402-940ITEM 01 02 03 04 05 06 07 08 09 10 11 12 13 Total

Est Pd Cost 8,437 8,438 6,898 6,900 8,673 8,676 8,673 8,676 10,090 10,094 10,090 8,677 8,668 8,437

Act Pd Cost 0 0 0 0 0 0 0 0 0 0 0 0 0 0

Variance, $ 8,437 0 0 0 0 0 0 0 0 0 0 0 0 8,437

Variance, % 100.0% 00% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0,0% 0.0% 0.0% 0.0% 0.0% 100.0%

Est FY Cumul 8,437 16,875 23,773 30,673 39,346 48,022 56,695 65,371 75,461 85,555 95,645 104,322 112,990

Act FY Cumul 0 0 0 0 0 0 0 0 0 0 0 0 0

% Complete 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0,0% 0.0% 0.0%

Cumul Var, $ 8,437 0 0 0 0 0 0 0 0 0 0 0 0

Cumul Var, % 100.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

DEVELOPMENT OF THE YUCCA MOUNTAIN REVIEW PLAN (YMRP)

1402-950

ITEM 01 02 03 04 05 06 07 08 09 10 11 12 13 Total

Est Pd Cost 117,471 117,472 101,808 101,813 118,292 118,299 118,291 118,299 135,175 135,188 135,168 118,300 118,277 117,471

Act Pd Cost 25,126 0 0 0 0 0 0 0 0 0 0 0 0 25,126

Variance, $ 92.345 0 0 0 0 0 0 0 0 0 0 0 0 92,345

Variance, % 78.6% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 78.6%

Est FY Cumul 117,471 234.943 336,751 438,564 556,856 675,155 793,446 911,745 1,046,920 1,182,108 1,317,276 1,435,576 1,553,853

Act FY Cumul 25,126 0 0 0 0 0 0 0 0 0 0 0 0

% Complete 1.6% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

Cumul Var, $ 92,345 0 0 0 0 0 0 0 0 0 0 0 0

Cumul Var, % 78.6% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

TANK WASTE REMEDIATION SYSTEM (TWRS) 1403-000

ITEM 01 02 03 04 05 06 07 08 09 10 11 12 13 Total

Est Pd Cost 60,928 60,930 51,298 51,308 60,923 62,495 60,917 60,937 69,072 69,094 69,069 60,938 60,905 60,928

Act Pd Cost 48,460 0 0 0 0 0 0 0 0 0 0 0 0 48,460

Variance, $ 12,468 0 0 0 0 0 0 0 0 0 0 0 0 12,468

Variance, % 20.5% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 20.5%

Est FY Cumul 60,928 121,858 173,156 224,464 285,387 347,882 408,799 469,736 538,808 607,902 676,971 737,909 798,814

"Act FY Cumul 48,460 0 0 0 0 0 0 0 0 0 0 0 0

% Complete 6.1% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

Cumul Var, $ 12,468 0 0 0 0 0 0 0 0 0 0 0 0

Cumul Var. % 20.5% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% ...... 0%....,, 0.0% 0.0% 0.0%... 0.0% 0.0%

DRY TRANSFER SYSTEM (DTS) 1405-020

ITEM 01 02 03 04 05 06 07 08 09 10 11 12 13 Total

Est Pd Cost 37,856 37,789 28,660 8,149 10,132 4,571 0 0 0 0 0 0 0 37,856

Act Pd Cost 28,512 0 0 0 0 0 0 0 0 0 0 0 0 28,512

Variance, $ 9,344 0 0 0 0 0 0 0 0 0 0 0 0 9,344

Variance, % 24.7% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 24.7%

Est FY Cumul 37,856 75,645 104,305 112,454 122,586 127,157 127,157 127,157 127,157 127,157 127,157 127,157 127,157

Act FY Cumul 28,512 0 0 0 0 0 0 0 0 0 0 0 0

% Complete 22.4% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

Cumul Var, $ 9,344 0 0 0 0 0 0 0 0 0 0 0 0

Cumul Var, % 24.7% 0.0% 0.0% 0.0% 0.0% 0.0% 0,0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

CENTRALIZED INTERIM STORAGE FACILITY (CISF) 1405-030 ......

ITEM 01 02 03 04 05 06 07 08 09 10 11 12 13 Total

Est Pd Cost 12,299 11,379 9,378 9,380 11,378 11,380 11,378 11,446 12,771 12,052 11,862 10,404 11,074 12,299

Act Pd Cost 6,754 0 0 0 0 0 0 0 0 0 0 0 0 6,754

Variance, $ 5,545 0 0 0 0 0 0 0 0 0 0 0 0 5,545

Variance, % 45.1% 0.0% 0,0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 45.1%

Est FY Cumul 12,299 23,678 33,056 42.436 53,814 65,194 76,572 88,018 100,789 112,841 124,703 135,107 146.181

Act FY Cumul 6,754 0 0 0 0 0 0 0 0 0 0 0 0

% Complete 4.6% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

Cumul Var, $ 5,545 0 0 0 0 0 0 0 0 0 0 0 0

Cumul Var, % 45.1% 0.0% 0.0% 0.0% 0.0% 0,0% 0% 0. 0% % 0.0% 0.%. 0.0% 0.0% 0.0%

PRIVATE FUEL STORAGE FACILITY (PFSF) 1405-040

ITEM 01 02 03 04 05 06 07 08 09 10 11 12 13 Total

"Est Pd Cost 40,587 33,699 16,367 16,578 19,273 19,279 19,273 19,279 9,278 9,285 9,278 19,279 18,929 40,587

Act Pd Cost 23,289 0 0 0 0 0 0 0 0 0 0 0 0 23,289

Variance, $ 17,298 0 0 0 0 0 0 0 0 0 0 0 0 17,298

Variance, % 42.6% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0,0% 0.0% 0.0% 0.0% 42.6%

Est FY Cumul 40,587 74,286 90,653 107,231 126,504 145,783 165,056 184,335 193,613 202,898 212,176 231,455 250,384

Act FY Cumul 23,289 0 0 0 0 0 0 0 0 0 0 0 0 % Complete 9.3% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%

CumulVar,$ 17,298 0 0 0 0 0 0 0 0 0 0 0 0

H'_Cumul Var, % o 42.6% 1 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0,0% 0.0% 0.0% 0.02,% 0.0%